Regulation on the protection against damage caused by ionizing radiation

Original Language Title: Verordnung über den Schutz vor Schäden durch ionisierende Strahlen

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Regulation on the protection against damage caused by ionizing radiation (Radiation Protection Regulation-StrlSchV)

Unofficial table of contents

StrlSchV

Date of completion: 20.07.2001

Full quote:

" Radiation Protection Ordinance of 20 July 2001 (BGBl. I p. 1714; 2002 I p. 1459), as last amended by Article 5 of the Regulation of 11 December 2014 (BGBl I). 2010).

Status:

Last amended by Art. 5 V v. 11.12.2014 I 2010

For more details, please refer to the menu under Notes

Footnote

(+ + + Text evidence from: 1.8.2001 + + +)

The V was referred to as Art. 1 d. V v. 20.7.2001 I 1714 (StrlSchRLUmsV) of the Federal Government, the Federal Ministries for the Environment, Nature Conservation and Nuclear Safety, for Health, Transport, Building and Housing after consultation of the interested parties, in agreement with the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety She's gem. Article 12 (1) sentence 1 of the V v. 20.7.2001 I 1714 mWv 1.8.2001 entered into force. Gem. Article 12 (2) occurs outside the provisions of Article 3 of the agreement of 6 September 1990 (BGBl). § § 95 (3) to (12), § § 97 to 102, as well as § 118 (4) and (5), on 1 January 2004, in force. Unofficial table of contents

Content Summary

Part 1
General provisions
§ 1	Purpose
§ 2	Scope
§ 3	Definitions

Part 2
Protection of humans and the environment from radioactive substances or ionizing radiation from the targeted use of activities
Chapter 1
Principles of radiation protection, basic duties and general limit values
§ 4	Justification
§ 5	Dose limit
§ 6	Avoidance of unnecessary exposure to radiation and dose reduction

Chapter 2
Approvals, approvals, release
	Section 1
	Handling of radioactive substances
§ 7	Dealing with radioactive substances in need of approval
§ 8	Authorisation-free handling of nuclear fuel-free
§ 9	Authorisation requirements for the handling of radioactive substances
§ 10	Exemption from the obligation to provide cover

	Section 2
	Installations for the production of ionizing radiation
§ 11	Permit-in-demand construction and operation of plants for the production of ionizing radiation
§ 12	Notifiable operation of installations for the production of ionizing radiation
§ 12a	Authorisation and display-free operation of installations for the production of ionizing radiation
§ 13	Conditions for the setting up of installations for the production of ionizing radiation
§ 14	Conditions of approval for the operation of installations for the production of ionizing radiation

	Section 3
	Employment in foreign installations or facilities
§ 15	Employment in foreign installations or facilities in need of approval

	Section 4
	Transport of radioactive substances
§ 16	Transport in need of approval
§ 17	Permit-free transport
§ 18	Conditions of approval of transport

	Section 5
	Transboundary movements of radioactive substances
§ 19	Cross-border movements in need of authorisation
§ 20	Transboundary movements in need of display
Section 21	Derogations; other rules on transboundary movements
Section 22	Conditions for the approval of transboundary movements

	Section 6
	Medical Research
Section 23	Application of radioactive substances or ionising radiation to humans in medical research
§ 24	Conditions of approval for the application of radioactive substances or ionising radiation to humans in medical research

	Section 7
	Type approval
Section 25	Method of type approval
Section 26	Registration certificate and publication of the type
§ 27	Obligations of the holder of a type-approval certificate and of the holder of a component type-approved device

	Section 8
	Exceptions
§ 28	Exceptions to the requirement of approval and notification

	Section 9
	Release
§ 29	Prerequisites for approval

Chapter 3
Requirements for the use of radioactive substances and ionizing radiation
	Section 1
	Specialist in radiation protection
§ 30	Required specialist knowledge and knowledge in radiation protection

	Section 2
	Operational organisation of radiation protection
Section 31	Radiation protection officer and radiation protection officer
Section 32	Position of the radiation protection officer and of the radiation protection officer
§ 33	Duties of the radiation protection officer and of the radiation protection officer
Section 34	Radiation protection statement
§ 35	Interpretation or application of the Regulation

	Section 3
	Protection of persons in radiation protection areas; physical radiation protection control
§ 36	Radiation protection areas
Section 37	Access to radiation protection areas
§ 38	Briefing
§ 39	Metrological monitoring in radiation protection areas
§ 40	People to monitor
Section 41	Determination of body dose
§ 42	Obligation to record and share
Section 43	Protective measures
Section 44	Contamination and decontamination
§ 45	Employment bans and restrictions on employment

	Section 4
	Protection of the population and the environment in radiation exposures from activities
Section 46	Limiting the exposure of the population
§ 47	Limitation of the discharge of radioactive substances
§ 48	Emission and immission monitoring

	Section 5
	Protection against safety-related events
§ 49	Safety-technical design for the operation of nuclear power plants, for the location-near storage of irradiated fuel elements and for federal plants for the purpose of ensuring and disposal of radioactive waste
§ 50	Limitation of exposure to radiation as a result of incidents in other installations and installations and in the case of decommissioning
Section 51	Measures in the event of safety-related events
Section 52	Preparation of fire-fighting
Section 53	Preparation of damage control in case of safety-related events

	Section 6
	Limitation of exposure to radiation during the exercise of the profession
§ 54	Categories of professionally radiated persons
§ 55	Protection of occupational radiation exposure
§ 56	Occupational dose
Section 57	Dose limitation when exceeded
Section 58	Specially approved radiation exposures
§ 59	Exposure to radiation in the case of personal risk and assistance

	Section 7
	Occupational health care of persons exposed to radiation
§ 60	Need for occupational health care
Section 61	Medical certificate
Section 62	Decision by the authorities
§ 63	Special occupational health care
Section 64	Authorised Doctors

	Section 8
	Other requirements
Section 65	Storage and Safety of Radioactive Substances
Section 66	Maintenance, inspection and leak testing
Section 67	Radiation measuring instruments
Section 68	Labelling
Section 69	Release of radioactive substances
§ 69a	Withdrawal of high-level radioactive sources
Section 70	Bookkeeping and communication
Section 70a	Register of highly radioactive sources of radiation
Section 71	Find out, find, obtain the actual violence

	Section 9
	Radioactive waste
Section 72	Planning for the seizage and fate of radioactive waste
Section 73	Collection
Section 74	Treatment and packaging
§ 75	Duties on the release of radioactive waste
Section 76	Delivery
Section 77	Exemptions from the obligation to deliver
Section 78	Intermediate Storage
§ 79	Prohibition of circumcration

Chapter 4
Special requirements for the medical use of radioactive substances and ionizing radiation
	Section 1
	Medicine and Dentistry
§ 80	Justifying indication
§ 81	Limitation of exposure to radiation
Section 82	Use of radioactive substances or ionizing radiation in humans
Section 83	Quality assurance in medical radiation applications
Section 84	Irradiation rooms
§ 85	Recording requirements
§ 86	Applications in people outside of medicine or dentistry

	Section 2
	Medical Research
Section 87	Special protection and information obligations
Section 88	Application prohibitions and application restrictions for individual person groups
§ 89	Participation and reporting obligations
§ 90	Protection Order
Section 91	Cover prevention in case of clinical trials
§ 92	Ethics Commission

Chapter 5
Use of radioactive substances or ionizing radiation in veterinary medicine
§ 92a	Restriction of exposure to radiation in the case of animal accompanying persons
Section 92b	Authorized persons in veterinary medicine

Part 3
Protection of humans and the environment from natural sources of radiation during work
Chapter 1
Basic duties
Section 93	Dose limit
Section 94	Dose reduction

Chapter 2
Requirements for terrestrial radiation at workplaces
§ 95	Naturally occurring radioactive substances in workplaces
§ 96	Documentation and other protective measures

Chapter 3
Protection of the population with naturally occurring radioactive substances
Section 97	Arrears in need of surveillance; inadmissible shipment
Section 98	Dismissal of residues from surveillance
§ 99	Residues remaining in monitoring
§ 100	Notification requirement, residue concept, balance of residues
§ 101	Removal of radioactive impurities from land
Section 102	Monitoring of other materials

Chapter 4
Cosmic radiation
Section 103	Protection of flying personnel from exposure to cosmic radiation

Chapter 5
Operational Organization
Section 104	Participation obligations for the operational organisation

Part 4
Protection of the consumer in the addition of radioactive substances to products
Section 105	Illegal addition of radioactive substances and inadmissible activation
Section 106	Approval of the need for the addition of radioactive substances and the activation need for approval
Section 107	Authorisation requirements for the addition of radioactive substances and activation
Section 108	Cross-border movements of consumer goods in need of approval
§ 109	Conditions for the approval of transboundary movements of consumer goods
§ 110	Return of consumer goods

Part 5
Common rules
Chapter 1
Consideration of radiation exposures
Section 111	Definitions for the determination of exposure to radiation; duty to duty
Section 112	Radiation protection register

Chapter 2
Powers of the Authority
Section 113	Arrangement of measures
Section 114	Regulatory exemptions from radiation protection regulations

Chapter 3
Formal requirements
§ 115	Electronic communications

Chapter 4
Irregularities
Section 116	Irregularities

Chapter 5
Final provisions
Section 117	Transitional provisions
Section 118	Delimitation to other regulations, remediation of legacies

Assets
Annex I	(on § § 8, 12, 17, 21) Approval-free activities
Annex II	(§ § 9, 14, 107) Documents required for examination of permit applications
Annex III	(§ § 3, 8, 10, 18, 20, 29, 43, 44, 45, 50, 53, 65, 66, 68, 70, 71, 105, 106, 107, 117) Free limits, free values for different release types, values of surface contamination, list of radionuclides in radioactive equilibrium
Annex IV	(on § 29) Release considerations
Annex V	(on § 25) Requirements for the type approval of devices
Annex VI	(§ § 3, 47, 49, 55, 117) Dosimetry sizes, tissue and radiation weighting factors
Annex VII	(§ § 29 and 47) Assumptions in the determination of radiation exposure
Annex VIII	(in accordance with § § 61, 62, 63) Medical certificate
Annex IX	(on § 68) Radiolabel
Appendix X	(§ § 72 to 79) Radioactive waste: designation, accounting, transport notification
Annex XI	(§ § 93, 95, 96) Fields of work in which significantly increased exposures may occur due to natural terrestrial radiation sources
Annex XII	(in accordance with § § 97 to 102) Recovery and disposal of residues in need of monitoring
Annex XIII	(§ § 51 and 53) Information of the population
Annex XIV	(to § 48 (4)) Federal guidelines for emission and immission monitoring
Annex XV	(§ § 70, 70a and 71) Standard recording sheet for high-level radioactive sources (HRQ)
Annex XVI	(to § 4 (3)) List of non-justified types of activity

Part 1
General provisions

Unofficial table of contents

§ 1 Purpose

The purpose of this Regulation is to regulate, for the protection of man and the environment against the harmful effects of ionizing radiation, principles and requirements for preventive and protective measures relating to the use and exposure of radioactive substances and ionizing radiation of civilizational and natural origin. Unofficial table of contents

§ 2 Scope

(1) This Regulation shall apply to:

1.

the following activities:

a)

the handling of

aa): artificially generated radioactive substances,
bb): of naturally occurring radioactive substances, where this is due to their radioactivity, their use as nuclear fuel, or to the production of nuclear fuel,

b)

the acquisition of the radioactive substances referred to in point (a), their distribution to others, their transport, and their transboundary movements;

c)

the safekeeping of nuclear fuels according to § 5 of the Atomic Energy Act, the storage of nuclear fuel in accordance with § 6 of the Atomic Energy Act, the establishment, operation, other innehabation, the decommissioning, the safe confinement of a plant and the dismantling of nuclear fuel an installation or parts of a plant according to § 7 of the Atomic Energy Act, the processing, processing and other use of nuclear fuel in accordance with § 9 of the Atomic Energy Act, the establishment and operation of federal plants for the purpose of ensuring and to Final disposal of radioactive waste,

d)

the establishment and operation of installations for the production of ionizing radiation with a particle or photon limit energy of at least 5 kiloelectronvolts, and

e)

the addition of radioactive substances in the manufacture of consumer goods, of medicinal products within the meaning of the Medicines Act, of plant protection products within the meaning of the Plant Protection Act, of pesticides and of substances according to § 1 No. 1 to 5 of the Fertilizer Act as well as the activation of the aforementioned products,

2.

Work that allows persons to be exposed to natural sources of radiation in such a way that radiation exposures cannot be disregarded from the point of view of radiation protection.

(2) This Regulation shall not apply to:

1.: the restoration of the legacy of previous activities and works, with the exception of the regulations in § 118,
2.: the decommissioning and refurbishment of the operating facilities and premises of the uranium ore mining industry, with the exception of the regulations in § 118,
3.: the establishment and operation of X-ray equipment and radiators in accordance with the X-ray Regulation;
4.: the exposure to radiation by radon in dwellings, including the parts of the buildings belonging to it, and
5.: radiation exposure through radionuclides naturally contained in the human body, by cosmic radiation near the ground, and by radionuclides present in the non-interference-affected earth crust.

Unofficial table of contents

§ 3 Definitions

(1) The nomenclature and application of this Regulation shall be divided between activities and works.

1.

Activities are:

a)

the operation of installations for the production of ionizing radiation,

b)

the addition of radioactive substances in the manufacture of certain products or the activation of such products,

c)

other acts which may increase radiation exposure or contamination,

aa): because they are done with artificially generated radioactive materials, or
bb): because they are carried out with naturally occurring radioactive substances, and these actions are carried out on the basis of the radioactivity of these substances, or for the use of these substances as nuclear fuel or for the production of nuclear fuel,

2.

Work is: actions that can increase radiation exposure or contamination with naturally occurring radioactivity, without being an activity.

a): in connection with the prospecting, extraction, production, storage, processing, processing and other use of materials,
b): insofar as they are carried out using materials which are incurred in operating procedures, provided that such actions are not already covered by point (a),
c): in connection with the recovery or disposal of materials resulting from acts referred to in point (a) or (b),
d): natural terrestrial sources of radiation, in particular radon and radon products, where such acts do not already fall under points (a) to (c) and do not take place for a purpose referred to in point (a); or
e): in the context of the professional practice of flying personnel on aircraft.

The agricultural, forestry or technical processing of the earth's surface shall not be considered to be a work within the meaning of this Regulation, insofar as these actions are not carried out for the purpose of removing impurities in accordance with § 101.

(2) For the purposes of this Regulation, the following shall be:

1.

Waste:

a): radioactive waste: radioactive substances within the meaning of § 2 (1) of the Atomic Energy Act, which must be disposed of in accordance with § 9a of the Atomic Energy Act, with the exception of discharges within the meaning of § 47;
b): Treatment of radioactive waste: processing of radioactive waste into waste products (e.g. by solidifying, binding, pouring or drying);
c): trash: unit of waste product, also with packaging, and waste container;
d): Waste product: processed radioactive waste without packaging and waste containers;

2.

Discharge: supply of liquid, aerosol-bonded or gaseous radioactive substances from installations and installations by means of routes provided for this purpose;

3.

Activity, specific: ratio of the activity of a radionuclide to the mass of the material in which the radionuclide is distributed. In the case of solid radioactive substances, the reference mass for the determination of the specific activity is the mass of the body or object, by means of which the radioactivity is inseparably connected with the intended use. In the case of gaseous radioactive substances, the reference mass shall be the mass of the gas or gas mixture;

4.

Activity concentration: ratio of the activity of a radionuclide to the volume of the material in which the radionuclide is distributed;

5.

Installations within the meaning of this Regulation are installations within the meaning of § § 7 and 9a (3) sentence 1 semisentence 2 of the Atomic Energy Act as well as installations for the production of ionizing radiation within the meaning of Section 11 (1) No. 2 of the Atomic Energy Act, which are suitable for photons or To produce particle radiation intentionally or unintentionally (in particular electron accelerators, ion accelerators, plasma plants);

6.

Irradiation device: device with shielding containing enclosed radioactive substances or constituent of nuclear fuel splitting installations, which shall be temporarily activated by the opening of the shielding or extension of these radioactive substances ionizing radiation,

a): which is used in human or animal use in the veterinary medicinal product or in the animal, or
b): which is intended to cause an effect in the objects to be irradiated for other purposes, and in which the activity 2 x 10 ¹³ Becquerel exceeds;

7.

Premises: land on which installations or facilities are located and which may restrict access to or the length of stay of persons by the person responsible for radiation protection;

8.

Decontamination: disposal or reduction of contamination;

9.

Dose:

a): Equivalent dose: Product from the absorbed dose (absorbed dose) in the ICRU soft tissue and the quality factor of publication No 51 of the International Commission on Radiation Units and Measurements (ICRU report 51, ICRU Publications, 7910 Woodmont Avenue, Suite 800, Bethesda, Maryland 20814, U.S.A.). In the presence of several radiation types and energies, the total equivalent dose is the sum of the individual contributions determined;
b): effective dose: the sum of the weighted organdoses in the tissues or organs of the body specified in Annex VI, part C, by external or internal radiation exposure;
c): Body dose: collective term for organdosis and effective dose. The body dose for a reference period (e.g. calendar year, month) is the sum of the dose received by external exposure during this reference period and the follow-up dose resulting from a reference period during this reference period. Activity intake is conditional;
d): Organdosis: Product from the mean dose of energy in an organ, tissue or body part and the radiation weighting factor as set out in Annex VI, Part C. In the presence of several types of radiation and energy, the organdosis is the sum of the total of those according to Annex VI, Part B the individual contributions determined by external or internal radiation exposure;
e): Local dose: dose equivalent, measured using the measured quantities specified in Annex VI, Part A, in a given location;
f): Location dose rate: local dose generated at a given time interval divided by the length of the time interval;
g): Person dose: equivalent dose, measured using the measured quantities indicated in Annex VI, Part A, at a body surface area representative of the exposure to radiation;

10.

Facilities: buildings, parts of buildings or individual rooms in which, according to § § 5, 6 or 9 of the Atomic Energy Act or in accordance with § 7 of this Regulation, radioactive substances have been dealt with or in accordance with § 11 para. 2 an installation for the production of ionizing radiation operation;

11.

Site of exposure, unfavourable: location in the vicinity of an installation or facility where the distribution of the derived radioactive substances in the environment takes into account real possibilities of use by means of a stay or by Consumption of food produced there is to be expected to be the highest exposure of the reference person;

12.

Members of the general population: members of the general population who are not exposed to persons exposed to radiation or who are medically or as a helping person;

13.

Exposure path: path of the radioactive substances from the derivation from an installation or device via a spreading or transport operation to a radiation exposure of the human;

14.

Research, medical: use of radioactive substances or ionizing radiation in humans, insofar as they are the further development of medicine or medical science and not primarily the examination or treatment of the individual patients;

15.

Release: Administrative act, which is the release of radioactive materials and movable objects, buildings, ground surfaces, installations or parts of the plant which are activated or contaminated with radioactive substances and which are derived from activities as defined in Article 2 (1) Point 1 (a), (c) or (d), from the Regulatory Area

a): of the Atomic Energy Act and
b): the legal regulations and administrative decisions of the administrative authorities

for the use, recovery, disposal, inching or transfer thereof to third parties as non-radioactive substances;

16.

Free limits: values of the activity and specific activity of radioactive substances as set out in Annex III, Table 1, columns 2 and 3, where activities with these radioactive substances are subject to the monitoring under this Regulation;

17.

Indication, justifying: decision of a physician with the necessary specialist in radiation protection, that and in what way radioactive substances or ionizing radiation are applied to humans in the field of medicine or dentistry;

18.

Consumer goods: goods intended for the final consumer as defined in the Food and Feed Code, as well as goods and articles of daily use for domestic and occupational use, with the exception of building materials and -type-approved devices into which other radioactive substances are inserted in accordance with Article 2 (1) of the Atomic Energy Act;

19.

Contamination: contamination with radioactive substances

a): Surface contamination: contamination of a surface with radioactive substances which comprises the non-adherent, the adherent activity and the activity which has penetrated the surface. The unit of measurement size of surface contamination is the area-related activity in Becquerel per square centimeter;
b): Surface contamination, non-adherent: contamination of a surface with radioactive substances in which the proliferation of radioactive substances cannot be ruled out;

20.

Materials: substances which contain naturally occurring radionuclides or are contaminated with such substances. For this definition, natural and artificial radionuclides which are or have been the subject of activities or have been derived from events pursuant to § 51 (1) sentence 1 shall not be taken into account. Similarly, environmental contamination due to nuclear weapons tests and nuclear accidents outside the scope of this Regulation shall not be taken into account;

21.

Medical physicist: qualified physicist in medical physics with the required specialist in radiation protection, or any other person with equivalent qualifications, with a university degree or a university of applied sciences degree and with the the required technical expertise in radiation protection;

22.

Emergency situation, radiological situation: situation as defined in Article 2 of Directive 89 /618/EURATOM of 27 November 1989 (Council Directive of 27 November 1989 on informing the general public of the situation in the event of a radiological emergency the rules of conduct and the health protection measures to be taken; OJ L 327, 28.4.2002 EC No 31), which is based on the population limit of 5 millisieverts in the calendar year of Directive 80 /836/EURATOM of 15 July 1980 (Council Directive of 15 July 1980 amending the directives laying down the basic standards for health protection the population and the labour force against the dangers arising from ionizing radiation; OJ L 327, 28.4.2002, p. EC No L 246 p. 1);

23.

Person exposed to occupational radiation: person exposed to radiation as defined in this Regulation

a): in the field of activities, those of category A or B of section 54; and
b): in the area of the work, the one for which the assessment pursuant to Article 95 (1) has shown that the effective dose may exceed 6 millisievert in the calendar year, or for which the determination in accordance with section 103 (1) has shown that the effective dose in the The calendar year may exceed 1 millisievert;

24.

Person, helping: a person who is able to give his or her legal representative's consent or who, outside of her professional activity, voluntarily supports or supervises persons in the exercise of medicine or dentistry. or in the context of medical research, radioactive substances or ionizing radiation;

24a.

Proband, gesunder: person in which a radioactive substance or ionizing radiation is used for the purpose of medical research and in the case of a research project which is in need of approval in accordance with § 23, no disease, the research is the subject of the project, or there is no such suspicion of disease;

25.

Reference person: Normal person, who is assumed to be in the determination of the radiation exposure in accordance with § 47. The assumptions used to determine the exposure of this standard person (lifestyle and other assumptions for the calculation of the dose) are set out in Annex VII;

26.

Reference values, diagnostic:

a): Dose values for medicinal use of ionizing radiation, or
b): recommended activity levels in the case of medicinal use of radioactive medicinal products;

for typical studies, based on standard phantomas or on patient groups with standard dimensions, for individual types of equipment;

27.

Residues: materials which are produced in the industrial and mining processes listed in Annex XII, Part A, and which meet the conditions laid down therein;

28.

Malfunction: event flow, when the operation of the plant or the activity cannot be continued for safety reasons and for which the installation is to be interpreted or for which protective measures can be taken as a precaution during the activity shall be provided;

29.

Substances, open and enclosed radioactive:

a): Substances, open radioactive substances: all radioactive substances, with the exception of the radioactive substances enclosed; (b)

Substances, enclosed radioactive:

aa): Radioactive substances which are constantly surrounded by a solid, solid, inactive shell or are permanently embedded in solid inactive substances in such a way that, in the case of normal operational stress, radioactive substances discharge with safety. ; a dimension must be at least 0.2 cm;
bb): Sources of radiation, highly radioactive: radioactive substances according to double-letter aa, the activity of which corresponds to or exceeds the values of Appendix III, Table 1, column 3a, excluding fuel elements and solidified high-level radioactive fission product solutions from the work-up of nuclear fuels; permanently dense and solid transport or storage containers with radioactive substances are not highly radioactive sources;

30.

Radiation exposure: the action of ionizing radiation on the human body. The whole body exposure is the effect of ionizing radiation on the whole body, partial body exposure is the effect of ionizing radiation on individual organs, tissue or body parts. External radiation exposure is the effect of radiation sources outside the body, inner radiation exposure is the effect of radiation sources within the body;

31.

Radiation exposure, occupational: the exposure of a person to radiation

a): in the case of an activity pursuant to section 2 (1) (1) or of a work pursuant to section 2 (1) (2), is in employment or training relationship, or carries out this activity or work itself,
b): a task in accordance with § 19 or § 20 of the Atomic Energy Act or in accordance with § 66 of this Regulation, or
c): In the context of § 15 or § 95 of this Regulation, it is employed in foreign plants, facilities or premises, there is a task according to § 15 itself or in accordance with § 95 carries out a work itself.

A radiation exposure which is not related to the professional practice is not taken into consideration;

32.

Radiation exposure, medical:

a): Exposure of a person in the course of their examination or treatment in the field of medicine or dentistry (patient),
b): exposure of a person to which, with his consent or with the consent of its legal representative, radioactive substances or ionizing radiation are used in medical research (Proband);

33.

radiation protection areas: monitoring area, control area and restricted area as part of the control area;

33a.

Animal accompanying person: A person capable of consent, who is the 18. is completed and who, outside of its professional activity, voluntarily accompanies an animal in which radioactive substances or ionizing radiation are applied in the exercise of veterinary medicine;

34.

Handling of radioactive substances: extraction, production, storage, processing, processing, other use and disposal of radioactive substances within the meaning of § 2 of the Atomic Energy Act, in so far as these are not works, and the operation of radioactive substances Irradiation facilities; the handling, extraction and treatment of radioactive mineral resources within the meaning of the Federal Mining Act (Bundesberggesetz) is also applicable;

35.

Accident: Event flow, which may result in an effective dose of more than 50 millisievert for one or more persons;

36.

Shipment:

a): import into the scope of this Regulation from a State which is not a Member State of the European Communities,
b): export from the scope of this Regulation to a State which is not a Member State of the European Communities, or
c): cross-border trade in goods from a Member State of the European Communities within the scope of this Regulation or into a Member State of the European Communities from the scope of this Regulation;

37.

Medical examinations, medical examination, health assessment and advice of a professionally exposed person by a doctor in accordance with § 64 para. 1 sentence 1.

38.

Addition of radioactive substances: purpose-directed addition of radionuclides to substances for the production of special properties, if:

a): the addition of artificially produced radionuclides to substances means that the specific activity in the product exceeds 500 microbecquerels per gram, or
b): The addition of naturally occurring radionuclides leads to the fact that their specific activity in the product exceeds one fifth of the free limits of Annex III, Table 1, column 3.

It is immaterial whether the additive is based on radioactivity or on other properties.

Part 2
Protection of humans and the environment from radioactive substances or ionizing radiation from the targeted use of activities

Chapter 1
Principles of radiation protection, basic duties and general limit values

Unofficial table of contents

§ 4 justification

(1) New types of activities which would be covered by Section 2 (1) (1), which may involve exposure to radiation or contamination of man and the environment, shall be subject to consideration of their economic, social or other benefits; may be justified in relation to the health impact that they may have. The justification of existing types of activities can be reviewed as soon as substantial new knowledge of the usefulness or impact of the activity is available. (2) Medical radiation exposures within the scope of the medical certificate, dentistry or medical research must be of sufficient benefit, with their overall potential of diagnostic or therapeutic benefit, including the immediate health benefits for the individual and the benefit for the Society, to weigh in relation to the one from radiation exposure (3) The types of activity referred to in Annex XVI are not justified. Unofficial table of contents

§ 5 Dose limit

Anyone who is planning, exerting or exercising an activity in accordance with § 2 (1) No. 1 (a) to (d) shall be obliged to ensure that the dose limits of § § 46, 47, 55, 56 and 58 are not exceeded. The limit values for the effective dose in the calendar year are 1 millisievert in accordance with § 46 (1) for the protection of individuals of the population and, in accordance with section 55 (1) sentence 1, for the protection of persons exposed to radiation exposed to their professional activities 20 Millisievert. Unofficial table of contents

§ 6 avoidance of unnecessary exposure to radiation and dose reduction

(1) Anyone who plans or exercises an activity in accordance with § 2 (1) no. 1 shall be obliged to avoid any unnecessary radiation exposure or contamination of humans and the environment. (2) Anyone who plans or exercises an activity pursuant to § 2 para. 1 no. 1 shall be obliged to: to minimise any exposure to radiation or contamination of man and the environment, taking into account the state of science and technology, and taking into account all the circumstances of the individual case, even below the limit values.

Chapter 2
Approvals, approvals, release

Section 1
Handling of radioactive substances

Unofficial table of contents

Section 7 Authorisation of radioactive substances in need of authorisation

(1) Those who deal with other radioactive substances in accordance with § 2 para. 1 of the Atomic Energy Act or with nuclear fuels pursuant to § 2 para. 3 of the Atomic Energy Act shall require the approval. An authorisation shall also be required if it deviates significantly from the handling defined in the instrument of approval. (2) A permit according to § § 6, 7 or 9 of the Atomic Energy Act or in accordance with § 11 (2) of this Regulation or a plan-determination decision in accordance with § 9b of the Atomic Energy Act may also extend to a handling in need of authorisation in accordance with paragraph 1. In so far as such extension is carried out, an authorisation under paragraph 1 is not required. (3) A permit referred to in paragraph 1 shall not be required in the case of the search, winnings or preparation of radioactive mineral resources, if: This applies to the provisions of the Federal Mining Act. Unofficial table of contents

§ 8 Authorisation-free handling of nuclear fuel-free possession

(1) A permit pursuant to section 7 (1) shall not be required in the cases referred to in Annex I, Part A and B. In the examination of the conditions laid down in Annex I, Part B, No 1 or 2, the activities of radioactive substances of the species listed in Annex I, Part A or B No 3 to 7 shall be disregarded. Sentence 1 shall not apply to highly radioactive sources of radiation. (2) In the case of a handling approved in accordance with § 7 (1), an authorisation-free handling under paragraph 1 for the radioactive substances listed in the authorization shall also be subject to the authorisation of the radioactive substances under the conditions laid down in paragraph 1. Annex III, table 1, columns 2 and 3, shall not be allowed. Sentence 1 shall not apply if, in a single establishment or independent branch, in the case of non-traders at the place of activity of the licence holder, radioactive substances in several separate buildings, parts of buildings, equipment or facilities is dealt with and it is sufficiently ensured that the radioactive substances from the individual buildings, parts of buildings, installations or facilities cannot cooperate. (3)

1.

with nuclear fuel

a): in accordance with paragraph 1 in conjunction with Annex I, Part B, No 1 or 2, without authorization, or
b): on the basis of an authorisation pursuant to section 7 (1

be circumvent or

2.

Nuclear fuel

a): on the basis of Section 17, without authorisation or
b): on the basis of an authorisation pursuant to section 16 (1

shall be allowed to

the provisions of Section 5 (2) to (4) of the Atomic Energy Act shall not apply. The release of nuclear fuel from the state's custody pursuant to § 5 (1) of the Atomic Energy Act or from the approved storage pursuant to § 6 of the Atomic Energy Act or § 7 of this Regulation is also permissible if the recipient is in possession according to sentence 1. the nuclear fuel is authorised, or if these nuclear fuel are to be transported for export purposes. Unofficial table of contents

§ 9 Approval requirements for the handling of radioactive substances

(1) The authorisation in accordance with § 7 (1) shall be granted if:

1.: there are no facts in which there are concerns about the reliability of the applicant, his legal representative or, in the case of legal persons or non-legal persons ' associations, which are in accordance with the law, the statutes, or the contract of association for the representation or management of the person concerned, and, if a radiation protection officer is not required, the applicant has the necessary technical knowledge in radiation protection,
2.: there are no facts in which there are concerns about the reliability of the radiation protection officers and they have the necessary expertise in radiation protection,
3.: the number of radiation protection officers necessary for the safe execution of the handling is available and the necessary powers are given to them for the performance of their duties,
4.: ensures that the persons involved in the handling of other persons have the necessary knowledge of the potential radiation risk and the protective measures to be applied,
5.: ensures that the equipment is handled and that the measures taken in accordance with the state of the art of science and technology are in place in order to comply with the protection requirements,
6.: there are no facts in which there are concerns that the staff necessary to ensure the safe execution of the handling does not exist,
7.: the necessary provision is made for the fulfilment of statutory claims for damages,
8.: the necessary protection against disrupting measures or other effects of third parties is ensured,
9.: overriding public interests, in particular with regard to the environmental impact, not being able to prevent the use of
10.: § 4 (3) does not preclude the intended handling.

(2) For an authorisation pursuant to section 7 (1) in conjunction with § 77 sentence 1, half sentence 2 for the other disposal or in accordance with section 7 (1) in conjunction with § 77 sentence 2 half sentence 2 for the other interim storage of radioactive waste, the following shall apply: the conditions laid down in paragraph 1. This authorisation may only be granted if there is a need for alternative disposal or interim storage. (3) In addition to the conditions for a permit to deal with the application in humans, the following conditions must be met: (1) the applicant or the radiation protection officer appointed by him in writing shall be approved as a doctor or a dentist, or the temporary exercise of the medical or dental profession shall be permitted, and

1.: be ordered for treatments in required number of medical physics experts as additional radiation protection officers, or
2.: for nuclear medical examinations or standard treatments, it is ensured that a medical physics expert, in particular for the optimization and quality assurance in the use of radioactive substances, is available.

(4) In addition to the conditions set out in paragraph 1, the applicant or the radiation protection officer appointed by him in writing shall be required to carry out an authorisation to deal with the application of the animal in the veterinary medicinal product in addition to the conditions laid down in paragraph 1. of the veterinary or medical profession. (5) The requirements for the nature of irradiation devices and of radioactive substances which are medical devices or accessories in the sense of the Medical Devices Act shall be determined by: the applicable requirements of the Medical Devices Act. (6) The The application for authorisation shall be accompanied, in particular, by the documents referred to in Annex II, Part A. Unofficial table of contents

§ 10 Liberation of the obligation to provide cover

(1) No provision of financial security pursuant to § 6 (2) sentence 1 no. 3, § 9 (2) sentence 1 no. 4 of the Atomic Energy Act and § 9 (1) (7) of this Regulation shall be required if the total activity of the radioactive substances, with which in the individual holding or self-employed Branch, in the case of non-trader at the place of activity of the applicant, is dealt with 10 (high) 6 times the free limits of Annex III, Table 1, column 2 and, in the case of enriched uranium, the mass of uranium-235 does not have a value of 350 grams , and it is sufficiently ensured that the other radioactive substances from the individual buildings, parts of buildings, installations or facilities cannot cooperate. (2) No provision of financial security pursuant to Article 9 (1) no. 7 shall also be required if, in the individual establishment or independent branch, the non-trader shall be at the place of the the activity of the applicant, with other radioactive substances, in several separate buildings, parts of buildings, installations or facilities, the activity of the other radioactive substances in the individual buildings, Building parts, installations or facilities 10 (high) 6 times the free limits of the Annex III, Table 1, column 2 does not exceed and is sufficiently ensured that the other radioactive substances from the individual buildings, parts of buildings, installations or equipment cannot cooperate. (3) When applying the paragraph 1 or 2, the proportion of open radioactive substances shall not exceed 10 (high) 5 times the free limits of Annex III, Table 1, column 2. (4) Paragraphs 1 and 2 shall not apply to highly radioactive sources.

Section 2
Installations for the production of ionizing radiation

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Section 11 Need for approval for the establishment and approval of plants for the production of ionizing radiation

(1) Anyone who establishes an installation for the production of ionizing radiation of the following type shall require the approval:

1.: Accelerator or plasma system, in which more than 10 per second ¹² neutrons can be generated,
2.: Electron accelerator with a final energy of electrons of more than ten mega-electronvolts, provided that the mean beam power can exceed 1 kilowatt,
3.: Electron accelerator with a final energy of electrons of more than 150 mega-electron volts,
4.: ion accelerator with a final energy of ions of more than ten mega-electronvolts per nucleon, provided that the mean beam power may exceed 50 watts,
5.: Ion accelerator with a final energy of ions of more than 150 mega-electronvolts per nucleon.

(2) Anyone who operates an installation for the production of ionizing radiation or substantially changes the plant or its operation requires authorization. (3) A permit referred to in paragraph 2 shall also require the use of ionizing radiation from a single source. Irradiation device, which is part of a nuclear fuel division approved in accordance with § 7 of the Atomic Energy Act, applies in the field of medicine, dentistry or veterinary medicine. Unofficial table of contents

§ 12 Display in need of operation of installations for the production of ionizing radiation

(1) By way of derogation from Article 11 (2), a person intending to operate an installation of the following type, or to substantially alter such an installation or operation, shall have the intended commissioning or essential operation of the competent authority. Change previously to be notified in writing:

1.: a plasma installation during which the local dose rate of 10 microsieverts is not exceeded by an hour at a distance of 0.1 metres from the walls of the area inaccessible for electrical reasons during operation; or
2.: an ion accelerator during which the local dose rate of 10 microsieverts is not exceeded by an hour at a distance of 0.1 metres from the touchable surface.

(2) The competent authority shall, on request, prove that:

1.: the number of radiation protection officers necessary for the safe execution of the operation is available and the necessary powers are given to them for the performance of their duties,
2.: any person responsible for radiation protection or, if a radiation protection officer is not required, the person responsible for the notification referred to in paragraph 1, his or her legal representative or, in the case of legal persons, associations or companies, Legal personality, which has the necessary expertise in radiation protection according to the law, the statutes or the contract for the representation or management of the person entitled to represent or management.

The competent authority may prohibit the holding referred to in paragraph 1 if:

1.: one of the conditions referred to in paragraph 2 is not met or is no longer fulfilled, or
2.: the person responsible under paragraph 1, his or her legal representative or, in the case of legal persons, associations or companies without legal personality, who are entitled under the law, the statutes or the contract of representation or management; The person or the radiation protection officer appointed for the management or supervision of the holding is not reliable.

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Section 12a Authorisation and display-free operation of installations for the production of ionizing radiation

Anyone who operates an installation of the type referred to in Annex I, Part C, shall not be required to obtain an authorisation pursuant to Article 11 (2), nor shall he be obliged to submit an indication in accordance with Section 12 (1). Unofficial table of contents

Section 13 Approval requirements for the establishment of installations for the production of ionizing radiation

The authorisation provided for in Article 11 (1) for the establishment of a plant for the production of ionizing radiation shall be granted where:

1.: there are no facts in which there are concerns about the reliability of the applicant, his legal representative or, in the case of legal persons or non-legal persons ' associations, which are in accordance with the law, the statutes, or Contract of association for the representation or management of the person entitled to the right of representation and, if a radiation protection officer is not required, the applicant has the necessary technical knowledge in radiation protection,
2.: shall ensure that a radiation protection officer is appointed for the establishment of the plant, who has the necessary expertise in radiation protection and who can set up or set up the plant in accordance with the permit; there are no facts in which there are concerns about the reliability of the radiation protection officer,
3.: shall ensure that, in the generally accessible areas outside the operating site, the exposure of persons in the event of permanent residence, as a result of the operation of the installation, shall be subject to the limit values allowed for individuals of the population , taking into account the disposal of radioactive substances with air and water, and the emission and scattered radiation,
4.: the provisions relating to the protection of the environment can be complied with in the course of the intended operation of the plant and in the event of accidents,
5.: the necessary protection against disrupting measures or other effects of third parties is ensured,
6.: the overriding public interests, in particular with regard to the environmental impact, do not conflict with the intended operation of the installation; and
7.: § 4 (3) does not preclude the intended establishment.

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Section 14 Approval requirements for the operation of plants for the production of ionizing radiation

(1) The authorisation pursuant to section 11 (2) shall be granted if:

1.: there are no facts in which there are concerns about the reliability of the applicant, his legal representative or, in the case of legal persons or non-legal persons ' associations, which are in accordance with the law, the statutes, or Contract of association for the representation or management of the person entitled to the right of representation and, if a radiation protection officer is not required, the applicant has the necessary technical knowledge in radiation protection,
2.: there are no facts in which there are concerns about the reliability of the radiation protection officers and they have the necessary expertise in radiation protection,
3.: the number of radiation protection officers necessary for the safe execution of the operation is available and the necessary powers are given to them for the performance of their duties,
4.: shall ensure that persons who otherwise carry out the operation have the necessary knowledge of the potential risk of radiation and of the protective measures to be applied,
5.: ensures that equipment is in place during operation and that the measures taken in accordance with the state of the art of science and technology are in place in order to comply with the protection requirements;
6.: there are no facts from which there are concerns that the staff required to carry out the operation safely does not exist,
7.: the necessary provision is made for the fulfilment of statutory claims for damages,
8.: the necessary protection against disrupting measures or other effects of third parties is ensured, in so far as the establishment of the installation requires the approval pursuant to Article 11 (1),
9.: the overriding public interests, in particular with regard to the environmental impact, do not conflict with the intended operation of the installation; and
10.: § 4 (3) does not preclude the intended operation.

Article 9 (5) shall apply. (2) In addition to paragraph 1, the following conditions must be fulfilled for a permit to operate an installation for the production of ionizing radiation in connection with the application to humans:

1.: The applicant or the radiation protection officer appointed by him in writing shall be approved as a doctor or dentist, or the temporary exercise of the medical or dental profession shall be permitted, and
2.: A medical physics expert has been appointed as a further radiation protection officer.

(3) In addition to the conditions set out in paragraph 1 of the applicant or of the applicant, for a permit to operate a plant for the production of ionizing radiation in connection with the application to the animal in the veterinary medicinal product, the applicant shall: (4) The application for a permit must be accompanied, in particular, by the documents referred to in Annex II, Part B. (5) It is only possible to have a request for authorisation during the course of the application. Trial operations shall assess whether the conditions set out in paragraph 1 (5) are met, the the competent authority shall grant the authorisation pursuant to section 11 (2) of the contract. The operator must ensure that the requirements for the dose limits, the restricted areas, control areas and the limitation of the disposal of radioactive substances during the trial operation are complied with.

Section 3
Employment in foreign installations or facilities

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Section 15 Employment in foreign installations or facilities

(1) Any person who, under his supervision, employs persons in external facilities or facilities, or performs tasks themselves, and in the case of such persons, or in the case of himself, in the calendar year, at an effective dose of more than 1 millisievert (2) In the case of employment referred to in paragraph 1 in installations or establishments in which radioactive substances are dealt with, Article 9 (1) (1) to (5), in the case of employment referred to in paragraph 1, shall be related to the operation of Installations for the production of ionizing radiation shall be subject to Article 14 (1) (1) to (5). (3) In the case of employment referred to in paragraph 1, the orders of the person responsible for radiation protection and of the radiation protection officers of the installation or establishment which meet them in accordance with their obligations pursuant to § 33 shall be complied with. The holder of a permit referred to in paragraph 1 shall ensure that the persons employed under his supervision comply with the orders of the radiation protection officers and radiation protection officers of the installations or facilities.

Section 4
Transport of radioactive substances

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Section 16 Transport in need of authorisation

(1) Anyone who carries other radioactive substances in accordance with § 2 (1) of the Atomic Energy Act or nuclear fuels pursuant to § 2 (3) of the Atomic Energy Act to public or public transport routes is subject to the authorisation. The authorisation may be granted to the shipper or carrier within the meaning of the provisions relating to the transport of dangerous goods, to the transferor or to the person who takes over the shipment or carriage. It shall be granted for the individual transport operation, but may be granted to an applicant in general for a maximum of three years, in so far as the purposes referred to in Article 1 (2) to (4) of the Atomic Energy Act are not contrary to that. The authorisation shall also cover the stages of a transport operation which does not take place on public or public transport routes, provided that there is no authorisation to deal with radioactive waste for such part-sections. (2) A permit in accordance with Article 4 (1) of the Atomic Energy Act may also extend to an authorized transport of radioactive substances referred to in paragraph 1, in so far as the same transport operation is concerned; to the extent that such a transport operation is The extension shall not be subject to approval pursuant to paragraph 1. (3) (4) In the case of transport, a copy or an officially certified copy of the approval certificate must be carried. The copy or copy of the approval certificate shall be presented to the authority responsible for the supervision or to the authority of the supervisor upon request. (5) The provisions of the approval certificate shall also be laid down in the execution of the carriage by the (6) The legislation on the transport of dangerous goods in force for each mode of transport shall be without prejudice to the provisions of the Regulation. Unofficial table of contents

Section 17 Authorisation-free transport

(1) No authorization pursuant to § 4 (1) of the Atomic Energy Act or § 16 (1) of this Regulation shall be required, who shall carry the following substances:

1.

substances of the type referred to in Annex I, Part B, or substances which are exempt from the application of the rules relating to the transport of dangerous goods,

2.

Other radioactive substances according to § 2 paragraph 1 of the Atomic Energy Act or nuclear fuel according to § 2 paragraph 3 of the Atomic Energy Act

a): under the conditions laid down for exempted consignment items, in accordance with the rules applicable to the transport of dangerous goods,
b): in accordance with the provisions of the Maritime Safety Regulation
c): with aircraft and the permission required for this purpose in accordance with § 27 of the Air Traffic Act.

The first sentence shall not apply to the transport of major sources within the meaning of Article 23 (2) of the Atomic Energy Act. (1a) (omitted) (2) (3) Those who are radioactive products or waste which are nuclear materials within the meaning of Annex I (1) No. 5 to the Atomic Energy Act, , without requiring the approval pursuant to Article 16 (1), if it does not itself have to provide proof of the necessary provision for the fulfilment of statutory claims for damages in accordance with Section 4b (1) of the Atomic Energy Act, the Take over nuclear materials for transport or further transport only if it is , at the same time, a certificate from the competent authority is submitted to the effect that the provision made by the person who passes the nuclear materials to him shall also be subject to the fulfilment of statutory claims for compensation in connection with the transport or continue to transport. Unofficial table of contents

Section 18 Authorisation requirements for transport

(1) The authorisation in accordance with § 16 (1) shall be granted if:

1.: where there are no facts which concern the reliability of the donor, the shipper, the carrier and the persons concerned, their legal representatives or, in the case of legal persons, the sending and the transport of persons, who are not legally competent, who, according to the law, the statutes or the social contract, are responsible for the representation or management of persons entitled to
2.: shall ensure that the carriage is carried out by persons who possess the knowledge necessary for the intended type of transport of the potential risk of radiation and of the protective measures to be applied,
3.: ensure that the radioactive substances are transported in compliance with the legislation on the transport of dangerous goods in force for each mode of transport, or, where such rules are lacking, in other ways, the state of science and technology has been taken into account for damage caused by the transport of radioactive substances,
4.: for the transport of other radioactive substances in accordance with Article 2 (1) of the Atomic Energy Act, the activity of which shall be 10% per item of dispatch ⁹The limits of the free limits of Appendix III, Table 1, column 2 or 10 ¹⁵ Becquerel, or of nuclear fuel in accordance with § 2 para. 3 of the Atomic Energy Act, the activity of which shall be greater than 10 per shipment ⁵The limits of the free limits of Appendix III, Table 1, column 2 or 10 ¹⁵ Becquerel, the necessary provision is made for the fulfilment of statutory damages obligations,
5.: the necessary protection against interference or other effects of third parties is ensured;
6.: is ensured that, in the case of the transport of other radioactive substances in accordance with Article 2 (1) of the Atomic Energy Act or nuclear fuel, according to Article 2 (3) of the Atomic Energy Act, with an activity of more than 10 ¹⁰(b) the limits of the free limits of Annex III, Table 1, column 2, subject to the appropriate application of Section 53, with an institution referred to therein, are the agreements which the institution shall conclude in the event of an accident or an accident to combat damage , and
7.: the overriding public interests of the choice of the type, time and route of transport are not in conflict.

(2) Where liability under the Paris Convention is contemplated in conjunction with Section 25 of the Atomic Energy Act, the provisions of Annex 2 to the Atomic Energy Act shall be replaced by nuclear materials instead of the provisions of paragraph 1 (4).

Section 5
Transboundary movements of radioactive substances

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Section 19 Cross-border movements in need of approval

(1) An authorisation shall be required for the purpose of which highly radioactive sources of radiation are not limited to their own use within the framework of an approved transfer from a Member State other than the Member State of the European Union to the scope of such a Regulation shall apply if:

1.: whose activity is equal to or greater than 100 times the value of Annex III, Table 1, column 3a,
2.: as well as their protective containers or storage containers, they do not have any marking in accordance with Article 68 (1a) or
3.: is not accompanied by documentation in accordance with § 69 (2) sentence 4.

(2) An authorisation shall be required for the non-use of the following radioactive substances temporarily for their own use in the context of an approved transfer from the scope of this Regulation to a State which is not a Member State of the The European Union is:

1.

high-level radioactive sources,

a): whose activity is equal to or greater than 100 times the value of Annex III, Table 1, column 3a,
b): which, in the same way as their protective containers or storage containers, have no marking in accordance with Article 68 (1a), or
c): which are not accompanied by documentation in accordance with Article 69 (2), sentence 4,

2.: other radioactive substances in accordance with § 2 (1) of the Atomic Energy Act or nuclear fuels pursuant to § 2 (3) of the Atomic Energy Act, the activity of which shall be per shipment. ⁸-Fache of the free limits of Appendix III, Table 1, column 2 is or exceeds the limit.

(3) A permit pursuant to Section 3 (1) of the Atomic Energy Act may also extend to a shipment in need of approval pursuant to paragraph 1 or paragraph 2. In so far as this is the case, a permit referred to in paragraph 1 or 2 shall not be required. Unofficial table of contents

Section 20 Display needy transboundary movements

(1) Any other radioactive material in accordance with § 2 (1) of the Atomic Energy Act or nuclear fuels pursuant to § 2 (3) of the Atomic Energy Act

1.: from a State which is not a Member State of the European Union, within the scope of this Regulation, or
2.: from the scope of this Regulation to a State which is not a Member State of the European Union,

The shipment of the competent authority in accordance with Section 22 (1) of the Atomic Energy Act shall be notified and shall not require any authorisation pursuant to Article 19 (1) or (2) of this Regulation. The notification shall be submitted to the authority competent in accordance with the first sentence or at the latest in connection with the customs clearance at the authority responsible for the supervision referred to in Article 22 (2) of the Atomic Energy Act or of the body designated by it. The form must be used for the display, which has determined the competent authority in accordance with Section 22 (1) of the Atomic Energy Act. (2) In the event of a shipment within the scope of this Regulation, the beneficial provision must be made to ensure that the for the first time only by persons who possess a permit required by § § 6, 7 or § 9 of the Atomic Energy Act or in accordance with § 7 (1) or § 11 (2) of this Regulation. (3) Who Nuclear fuel in accordance with § 2 paragraph 1 of the Atomic Energy Act in the form of

1.: up to 1 kilogram of uranium enriched to 10 per cent or more, but less than 20 per cent of uranium-235, or
2.: less than 10 kilos of uranium enriched to less than 10 per cent of uranium-235,

from a State which is not a Member State of the European Union to the scope of this Regulation shall, by way of derogation from Article 3 (1) of the Atomic Energy Act, reimburse a notification in accordance with paragraph 1. Unofficial table of contents

Section 21 Exceptions; other provisions relating to transboundary movements

(1) No prior authorisation pursuant to § 3 (1) of the Atomic Energy Act or § 19 of this Regulation shall be required and shall not be subject to any indication in accordance with Article 20 of this Regulation.

1.: shall be one of the substances referred to in Annex I, Part B, points 1 to 6,
2.: other radioactive substances referred to in Article 2 (1) of the Atomic Energy Act or nuclear fuel according to § 2 (3) of the Atomic Energy Act, subject to customs supervision by the scope of this Regulation,
3.: substances referred to in point 2 for their own use on a temporary cross-border basis in the context of an approved transfer, provided that they are not highly radioactive sources, or
4.: in accordance with § 108 of this Regulation.

(2) § § 19 and 20 of this Regulation shall not apply to the shipment by the Bundeswehr. (3) Other provisions relating to the shipment shall remain unaffected. (4) The provisions of Council Regulation (Euratom) No 1493/93 of 8 June 1993 on the Shipments of radioactive substances between Member States (OJ L 136, 31.7.2006 1) as amended and the Nuclear Waste Shipments Regulation of 30 April 2009 (BGBl). I p. 1000) shall remain unaffected in the current version. Unofficial table of contents

Section 22 Approval requirements for transboundary movements

(1) The authorisation in accordance with § 19 (1) shall be granted if:

1.: there are no facts which concern the reliability of the publisher, his legal representative, or, in the case of legal persons or non-legal persons associations, which are in accordance with the law, the articles of association or the social contract for the representation or management of beneficiaries; and
2.: the provider has made provision for the fact that, after the shipment, the radioactive substances will be acquired for the first time only by persons who have the authorisation required for the handling of the radioactive material.

In the case of highly radioactive sources, the authorisation referred to in the first sentence may be granted only if it is guaranteed that:

1.: they and their protective container or storage container have a marking in accordance with section 68 (1a) and
2.: the written documents referred to in Article 69 (2) sentence 4 are attached.

(2) The authorisation in accordance with § 19 (2) shall be granted if:

1.: there are no facts which concern the reliability of the publisher, his legal representative, or, in the case of legal persons or non-legal persons associations, which are in accordance with the law, the articles of association or the social contract for the representation or management of beneficiaries; and
2.: shall ensure that the radioactive substances to be delivered are not used in a manner which is of the internal or external security of the Federal Republic of Germany or of the fulfilment of its international obligations in the field of Nuclear energy and radiation protection.

The second sentence of paragraph 1 shall apply accordingly.

Section 6
Medical Research

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Section 23 Authorised application of radioactive substances or ionising radiation to humans in medical research

(1) Anyone who applies radioactive substances or ionizing radiation to humans for the purpose of medical research is subject to approval. (2) The Federal Office for Radiation Protection is responsible for the granting of the permit. Unofficial table of contents

§ 24 Approval requirements for the application of radioactive substances or ionizing radiation to humans in medical research

(1) The authorisation referred to in Article 23 (1) may only be granted if:

1.

there is a compelling need for the proposed research project, because the results of the research and the medical findings to date are not sufficient,

2.

the use of a radioactive substance or ionising radiation cannot be replaced by an examination or treatment type which does not cause exposure to radiation;

3.

the radiation-related risks associated with the application for the test person, as measured by the likely significance of the results for the further development of medicine or medical science, are warranted by a medical certificate,

4.

the radioactive substances or types of application of ionizing radiation intended for medical research correspond to the purpose of the research and are not replaced by other radioactive substances or types of application of ionizing radiation; , which may lead to less exposure to radiation for the subject,

5.

the exposure to radioactive substances or ionizing radiation and the activity of the radioactive substances to be applied in accordance with the state of science and technology cannot be further reduced without the use of the To endanger the purpose of the research project,

6.

the body dose of the test person has been estimated,

7.

the number of subjects is limited to the necessary level,

8.

the opinion of an Ethics Committee in accordance with § 92 of the proposed research project;

9.

ensuring that

a): the application is directed by a doctor who can demonstrate at least two years ' experience in the use of radioactive substances or ionising radiation in humans, who has the necessary expertise in radiation protection and during which application is constantly available, and
b): a medical physics expert will be involved in the planning and the application,

10.

the necessary provision is made for the fulfilment of statutory claims for damages; and

11.

an authorisation in accordance with § 7 (1) in conjunction with § 9 (1) and (3) or in accordance with § 11 (2) or (3) in conjunction with § 14 (1) and (2).

By way of derogation from paragraph 1, in the case of a research project dealing with the safety or efficacy of a procedure for the treatment of sick people, the competent authority may, notwithstanding paragraph 1, paragraph 1, paragraph 1, even then: , if the applicant

1.

can be traced in a comprehensible way

a): the use of radioactive substances or ionizing radiation itself is not the subject of the research project;
b): the nature of the use of radioactive substances or ionising radiation is equivalent to the standard methods of medicine used in human beings,
c): the nature and frequency of the use of radioactive substances or ionising radiation in accordance with the purpose of the research project; and
d): is ensured that only those who are able to give consent are the 18. They shall be included in the research project in which a disease is present, the treatment of which will be examined in the context of the research project, and

2.

the assesment of an Ethics Committee according to § 92.

(3) The effective dose resulting from the research project may not exceed the limit value of 20 millisievert for healthy subjects. (4) The application sees the use of radioactive substances or ionizing radiation at several facilities (Multi-centre study), the approval authority may grant a full authorisation to all bodies if it is to carry out the study in a proper way. In the case of a permit referred to in the first sentence in conjunction with paragraph 1, each institution concerned shall be required to demonstrate that the conditions laid down in paragraphs 9 and 11 of paragraph 1 are fulfilled.

Section 7
Type approval

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Section 25 Procedure of type approval

(1) The type of equipment and other devices into which other radioactive substances are inserted in accordance with Article 2 (1) of the Atomic Energy Act and of installations for the production of ionizing radiation (type approved devices) may, at the request of the The manufacturer or the feeder of the device shall be approved if the conditions set out in Annex V are fulfilled. The authorisation authority may, on a case-by-case basis, allow derogations from the conditions laid down in Annex V, Part A, No 1 (a), No 3 or 4. Sentence 1 shall not apply to equipment or other devices to which highly radioactive sources of radiation are inserted. (2) Before its decision, the approval authority shall have the Bundesanstalt für Materialforschung und -prüfung zu Ask the questions of tightness, the choice of materials and the design of equipment or devices and quality assurance. The applicant shall, on request, leave the approval authority to the type of design required for examination. (3) The type approval shall be refused if:

1.: There are grounds for speaking out against a permit-free approach,
2.: where the manufacturer or the person responsible for the management of the production or the technical experience of the manufacturer or the person responsible for the manufacture of such equipment is not responsible or the person responsible for the manufacture of such a person, the reliability of the person who spends an apparatus within the scope of this Regulation;
3.: the predominant public interests of the type-approval are contrary to
4.: § 4 (3) preclude the approval of the type of component.

(4) The type-approval shall be limited to a maximum of ten years. The period may be extended upon request. (5) A type-approved device which has been placed on the market before the expiry of the time-limit for approval may be further operated in accordance with § 8 (1) or § 12a of the approval and display-free period, unless the authorisation authority has made known in accordance with Article 26 (2) that adequate protection against radiation damage is not guaranteed and that this device must not be operated further. (6) Paragraph 1 sentence 1 shall not apply to devices, the medical devices or accessories in the sense of the Medical Devices Act. (7) For the The Federal Office for Radiation Protection is responsible for granting type approval. Unofficial table of contents

§ 26 Registration certificate and publication of the type

(1) If the type is approved in accordance with Section 25 (1), the approval authority shall issue a certificate of approval. To be included in these

1.: the characteristics of the device, which are essential for radiation protection,
2.: the authorised use of the device;
3.: Restrictions on content, conditions for the holder of the device and on time limits,
4.: the type mark and the particulars to be provided with the device;
5.: an indication of the obligations of the proprietor of the device pursuant to Article 27 (2) to (6) and
6.: in the case of a device containing radioactive substances, requirements for the return of the device to the authorisation holder or to the disposal of the device.

(2) The essential content of the type-approval, its modification, its withdrawal, its revocation, the extension of the approval period and the declaration that a device approved by the type-approval may not continue to be operated shall be subject to the approval of the authorisation authority in the Federal Gazette to make known. Unofficial table of contents

Section 27 Duties of the holder of a type-approval and of the holder of a component type-approved device

(1) The marketing authorisation holder shall:

1.: to carry out a quality control procedure prior to the supply of the manufactured component type-approved devices, in order to ensure that they correspond to the characteristics of the type approval which are essential for the protection of radiation, and to ensure that they are marked with the type of design character and the other information to be determined by the authorisation authority,
2.: monitor quality control through an expert to be determined by the regulatory authority,
3.: to issue a copy of the certificate of approval to the acquirer of a component type-approved device, on which the result and, in so far as tightness tests as referred to in paragraph 6 are required, the date of the quality control referred to in point 1 is confirmed is,
4.: to issue the acquirer of a component type-approved device with the same operating instructions, which shall refer in particular to the measures used for radiation protection; and
5.: to ensure that a component type-approved device containing radioactive substances can be withdrawn after the end of use.

(2) The holder of a component type-approved device shall keep the certificate referred to in paragraph 1 (3) and the test findings referred to in the first sentence of paragraph 6 ready for use in the device. In the case of the transfer of the component type-approved device, paragraph 1 (3) and (4) shall apply. (3) No modifications to the type-approved device shall be made concerning the essential characteristics of radiation protection. (4) The type-approved device which, as a result of wear, damage or destruction, no longer corresponds to the provisions of this Regulation or to the characteristics which are essential for radiation protection in respect of radiation protection, shall no longer be permitted to: shall be used. The holder of the device shall immediately take the necessary protective measures to prevent radiation damage. (5) Is the withdrawal, withdrawal of a type approval or the declaration that a type-approved device shall not continue to be (6) The holder of a type-approved device, the holder of a type-approved device, shall immediately shut down the equipment concerned and take the necessary protective measures to prevent damage to the radiation. radioactive substances, it shall have radioactive substances in accordance with § 66 (1) of the 1 sentence 1 shall be checked for tightness by certain experts. The date of the quality control day is the date of the approval certificate. The approval authority may, in the registration form, meet different regulations for leak testing. (7) The holder of a component type-approved device containing radioactive substances has it after the end of the use to return immediately to the authorisation holder. If this is not possible or is possible only with a disproportionate effort, it shall be submitted to a land register or to a body designated by the competent authority.

Section 8
Exceptions

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§ 28 Exceptions to the requirement of approval and notification

Any person who is employed as an employee or otherwise under the supervision of an activity which is subject to approval or display in accordance with the Atomic Energy Act or this Regulation shall not require an authorisation pursuant to § § 3, 4, 6, 7 or 9 of the Nuclear Act or in accordance with § § 7, 11, 15, 16, 19, 23 or 106 of this Regulation, a decision on the planning of a decision pursuant to § 9b of the Atomic Energy Act and is exempt from the obligation to notify pursuant to § 12 or § 20 of this Regulation. Anyone acting as a third party pursuant to Section 9a (3) sentence 3 of the Atomic Energy Act shall not require an authorisation in accordance with § 15 of this Regulation. Sentence 1 shall not apply to home workers or to domestic workers within the meaning of the Home Labour Code.

Section 9
Release

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§ 29 Conditions for release

(1) The holder of an authorisation pursuant to § § 6, 7 or 9 of the Atomic Energy Act, a plan determination decision in accordance with § 9b of the Atomic Energy Act or a permit pursuant to § 7 or § 11 (2) of this Regulation may be permitted to use radioactive substances as well as movable Objects, buildings, floor areas, installations or parts of the plant which are activated or contaminated and which originate from activities as defined in Article 2 (1) (1) (a), (c) or (d), when not radioactive substances use, exploit, dispose of, or dispose of, or pass it on to a third party if the competent authority has granted the clearance referred to in paragraph 2 and in accordance with paragraph 3, the conformity with the requirements laid down in the notification of release is established. § 44 (3) and § 47 shall remain unaffected. (2) The competent authority shall, at the request of the holder, issue a permit pursuant to § § 6, 7 or 9 of the Atomic Energy Act, a plan determination decision in accordance with § 9b of the Atomic Energy Act or a permit pursuant to § 7 or § 11 (2) of this Regulation in writing, if only an effective dose in the range of 10 microsieverts in the calendar year may occur for individuals of the population. The competent authority may assume that this is satisfied if:

1.

for an unrestricted release of

a): Substances which comply with the free values referred to in Annex III, Table 1, column 5 or Table 3, as well as the provisions laid down in Annex IV, Part A, points 1 and B, and, where a solid surface is present, compliance with the values of the Surface contamination of Appendix III, Table 1, column 4,
b): Building debris and soil excavation, with a mass to be expected of more than 1 000 tonnes in the calendar year, compliance with the free values set out in Annex III, Table 1, column 6, and compliance with the values referred to in Annex IV, Part A, point 1, part B and F Definitions,
c): soil surfaces to comply with the free values set out in Annex III, Table 1, column 7, and to comply with the provisions of Annex IV, Part A, point 1, part B and E,
d): buildings for re-use and re-use of the shares referred to in Annex III, Table 1, column 8, and compliance with the provisions laid down in Annex IV, Part A, point 1, part B and D,

2.

for a release of

a)

solid substances for disposal in landfills at a mass to be expected of

aa): up to 100 tonnes in the calendar year of compliance with the provisions of Annex III, Table 1, column 9a or
bb): more than 100 tonnes up to 1 000 tonnes in the calendar year of compliance with the provisions of Annex III, Table 1, column 9c

, as well as the specifications referred to in Annex IV, Part A, points 1 and C, and, where a solid surface is present, compliance with the values of surface contamination of Annex III, Table 1, column 4,

b)

Substances for disposal in an incineration plant at a mass to be expected of

aa): up to 100 tonnes in the calendar year of compliance with the provisions of Annex III, Table 1, column 9b or
bb): more than 100 tonnes up to 1 000 tonnes in the calendar year of compliance with the provisions of Annex III, Table 1, column 9d

c)

buildings for demolitions, compliance with the free values referred to in Annex III, Table 1, column 10, and compliance with the provisions laid down in Annex IV, Part A, No 1 and Part D,

d)

Scrap metal for recycle, compliance with the free values referred to in Annex III, Table 1, column 10a, as well as the provisions set out in Annex IV, Part A, No. 1 and Part G, and, where a solid surface is present, compliance with the Values of surface contamination of Appendix III, Table 1, column 4

, unless there is evidence available to the competent authority that, in the cases referred to in point 2 (a) and (b), an effective dose of 10 microsievert is available at the site of the disposal facility for individuals of the population, in the The calendar year is exceeded. In so far as the provisions of Annex IV required by the second sentence are not available in individual cases, no free values for individual radionuclides or other liquid substances other than those referred to in Annex IV, Part B, second sentence, point 3 , for substances which do not exceed the limits of Annex III, Table 1, column 3, the proof that only an effective dose of 10 microsievert in the calendar year may occur for individuals of the population may be found at: Consideration of the provisions of Annex IV, Part A, No 2, shall also be taken in other ways. The conditions for release may not be brought about, caused or made possible by mixing or dilution in a purposefully intended manner. In the cases referred to in point 2 (2) (a), (b) and (d), the competent authority may waive the fact that the values of surface contamination of Appendix III, Table 1, column 4 are complied with, if it is excluded that: Persons can be contaminated by the substances to be released. The competent authority referred to in the second sentence shall, in the event of an intended release for the disposal of masses exceeding 10 tonnes in the calendar year in order to ensure the dose criterion set out in the first sentence of the first sentence, provide for the agreement at the site of the disposal facility. the supreme state authority responsible for the implementation of this Regulation, in the area of competence of which the masses to be released are to be removed. If, on the basis of an assessment, it cannot be ruled out that the intended release can no longer meet the dose criterion of the first sentence, the supreme state authority responsible for the implementation of this Regulation shall, in its (3) For each mass or partial mass which is due to the competent authority, the competent authority responsible for the intended release shall be responsible for the elimination of the competent authority. (3) For each mass or mass of mass which is modesty referred to in paragraph 2, as a non-radioactive substance used, recovered, should be held or passed on to third parties, the conformity with the requirements laid down in the communication must be determined beforehand. The required free measurements and their results are to be documented. (4) The competent authority may, in a permit pursuant to § § 6, 7 or 9 of the Atomic Energy Act, a plan determination decision in accordance with § 9b of the Atomic Energy Act or a (5) In the cases referred to in the second sentence of paragraph 2, the procedure for the fulfilment of the requirements laid down in the second sentence of paragraph 2 and the second sentence of paragraph 2 shall be determined in a separate communication. Point 2 (a), (b) and (d) may not, in addition to the second sentence of paragraph 2 or 3, be concerned with the waste-legal admissibility of the intended recovery or disposal route and its compliance. Before issuing the release, the competent authority shall make a declaration by the applicant of the fate of the future waste and a declaration of acceptance by the operator of the recovery and disposal facility or any other agreement between: submit to the applicant and the operator of the recovery and disposal facility. The applicant shall, at the same time, send a copy of the declaration of acceptance or the agreement referred to in the second sentence to the competent authority for the recovery and disposal facility in accordance with the Circular Economy Act, and this shall be the responsibility of the competent authority. Proof. The competent authority may, within a period of 30 calendar days after receipt of the copy, require the competent authority to require the competent authority to agree on the basis of the Requirements to be made to the recovery or disposal route. The provisions of the Circular Economic Law as well as the provisions adopted pursuant to this Act for the management of evidence on the proper disposal of waste remain unaffected. (6) On request, the competent authority may decide to apply: the individual questions on which the issue of the release depends, whether certain conditions of paragraph 2 are met. This determination shall be based on the release procedure. The approval in accordance with § § 6, 7 and 9 of the Atomic Energy Act or a planning order decision in accordance with § 9b of the Atomic Energy Act or the approval pursuant to § 7 or § 11 (2) of this Regulation may be provided with a determination according to sentence 1. A release does not replace permission to decommission pursuant to § 7 para. 3 of the Atomic Energy Act. (7) If no marketing authorisation holder is present, a release can also be carried out on its own account if only an effective dose for individuals of the population is provided in the Range of 10 microsieverts may occur in the calendar year. For federal installations to ensure and end the disposal of radioactive waste according to the Atomic Energy Act, the competent surveillance authority in accordance with Section 23 (1) (2) of the Atomic Energy Act can decide on release.

Chapter 3
Requirements for the use of radioactive substances and ionizing radiation

Section 1
Specialist in radiation protection

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§ 30 Required specialist knowledge and knowledge in radiation protection

(1) The required subject-matter in radiation protection according to § § 9, 12, 13, 14, 15, 24, 31, 64 or 82 is usually provided by a training, practical experience and successful participation in the field of application of the relevant application. competent authority. The training is provided by certificates, the practical experience by means of proof and the successful course attendance by a certificate. The competent authority shall examine and certify the acquisition of the technical certificate. The course may not be longer than five years. For medical-technical radiology assistants and medical-technical radiology assistants, proof in accordance with sentence 1 with the permission in accordance with § 1 no. 2 of the law on technical assistants in medicine applies to the reserved activities. in accordance with Article 9 (1) (2) of this Act. (2) The subject of radiation protection must be successful at least every five years by a successful participation in a course recognised by the competent authority or by others from the competent authority as suitable recognised training measures are to be updated. By way of derogation, the subject of radiation protection may be updated in an appropriate manner in the individual case and the updating of the competent authority can be demonstrated. Proof of the updating of the technical certificate referred to in the first sentence shall be submitted to the competent authority on request. The competent authority may withdraw a certificate of expertise or knowledge of, or impose conditions on, the certificate if proof of training is not or is not submitted in full or if the certificate is not submitted in full or if the certificate is not available in full or in the Verification in accordance with sentence 5 shows that the subject or knowledge in the field of radiation protection is not available or is not available to the required extent. If there are reasonable doubts as to the required subject-matter, the competent authority may request a review of the certificate. (3) Courses referred to in the first sentence of paragraph 1, the second sentence of paragraph 4 and the second sentence of the second sentence may be accepted only by the body responsible for the course if the course contents are suitable to provide the knowledge necessary for the respective application in the radiation protection field and the qualification of the teaching staff and the equipment of the course site a proper knowledge transfer (4) The necessary knowledge of radiation protection shall be provided in the Usually acquired by an instruction suitable for the respective application area and practical experience. For persons pursuant to § 82 (1) (2) and (2) (2) and (2) (2) (2) and (2) (2) and (2) (3), the first sentence of paragraph 1 (2) to (4) and the By way of derogation from the third sentence of paragraph 1, the knowledge of the successful completion of a recognised course shall be considered to be considered for the persons referred to in sentence 2 and shall be certified if the competent authority has previously received a certificate at the request of a course organiser. noted that the necessary knowledge of radiation protection is acquired with the existence of the final examination of this course. Paragraph 3 shall apply accordingly.

Section 2
Operational organisation of radiation protection

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§ 31 Radiation protection officer and radiation protection officer

(1) The person who is responsible for radiation protection is who requires a permit pursuant to § § 6, 7 or 9 of the Atomic Energy Act or in accordance with § § 7, 11 or 15 of this Regulation or who requires the planning of the planning according to § 9b of the Atomic Energy Act or who is an activity according to § 5 of the German Atomic Energy Act. In accordance with § 12 (1) sentence 1 of this Regulation, or who is not required to obtain an authorisation pursuant to § 7 (3) of this Regulation pursuant to Section 7 (3) of this Regulation, he or she shall not be required to submit a notification pursuant to If the person responsible for radiation protection is a legal person or a member of a civil society which is legally competent, the duties of the person responsible for radiation protection shall be those of the person concerned by the law, the statutes or the contract to represent them. authorized person. Where the representative body is composed of several members or if there are several persons entitled to represent it in the case of non-legal persons ' associations, the competent authority shall be notified of the tasks to be carried out by those persons. of the person responsible for radiation protection. The overall responsibility of all organ members or members of the association of persons remains unaffected. (2) To the extent that this is necessary to ensure the radiation protection in the course of the activity, the radiation protection officer responsible for the To order the necessary number of radiation protection officers in writing, or supervise these activities. In the case of the appointment of a radiation protection officer, its tasks, its internal decision-making area, and the powers necessary for the performance of its tasks shall be laid down in writing. The person responsible for radiation protection shall also be responsible for compliance with the requirements of Parts 2 and 5 of this Regulation, if he has appointed Radiation Protection Officer. (3) Only persons may be appointed to radiation protection officers where there are no facts from which there are concerns about their reliability and who have the necessary expertise in radiation protection. (4) The appointment of the Radiation Protection Officer, stating the tasks, and powers, changes in tasks and powers, and the departure of the Radiation protection officers from his function shall be notified without delay to the competent authority. The notification of the order must be accompanied by the certificate of the required subject in the radiation protection according to § 30 (1). A copy of the communication shall be transmitted to the radiation protection officer and to the holding or staff council. (5) If radiation protection officers are to be ordered for the search, winnings or preparation of radioactive mineral resources, the Commission shall: be appointed as responsible persons for the management or supervision of the holding or of an operating part pursuant to § 58 (1) no. 2 of the Federal Mining Act, if the provisions of the Federal Mining Act apply to these activities. Unofficial table of contents

Section 32 Position of the radiation protection officer and the radiation protection officer

(1) The radiation protection officer shall be subject to the obligations imposed on him by this Regulation only within the limits of his powers. If it is found that the radiation protection officer is unable to fulfil his obligations insufficiently due to insufficient powers, insufficient expertise in radiation protection or a lack of reliability or for other reasons, the competent authority may (2) The person responsible for radiation protection shall not be regarded as a radiation protection officer within the meaning of this Regulation. (2) The person responsible for radiation protection shall be immediately informed of the need to to communicate any defects that affect radiation protection. If the radiation protection officer cannot agree on a correction proposed by him to the person responsible for radiation protection, the radiation protection officer shall in writing reject the proposal to the radiation protection officer. (3) The radiation protection officers shall be informed of all administrative acts and measures relating to their duties or powers, and shall be responsible for the inform immediately. (4) The radiation protection officer and the In the performance of their duties, radiation protection officers have to cooperate with the works council or the staff council and the specialists in occupational safety and to inform them about important matters relating to radiation protection. The radiation protection officer shall advise the works council or the staff council at its request in matters relating to radiation protection. (5) The radiation protection officer shall not be impeded in the performance of his duties and shall be entitled to fulfil his duties. are not disadvantaged. Unofficial table of contents

Section 33 obligations of the radiation protection officer and of the radiation protection officer

(1) The person responsible for radiation protection shall, in accordance with the state of science and technology for the protection of man and the environment against the harmful effects of ionizing radiation, by means of appropriate protective measures, in particular by: provision of appropriate spaces, equipment and equipment to ensure, by appropriate regulation of the operational sequence and by providing adequate and appropriate staff, that:

1.

the following rules are complied with:

a)

Part 2 Chapter 2: Approvals, authorisations, release, Section 9: Release § 29 (1) sentence 1,

b)

Part 2 Chapter 3: Request for the use of radioactive substances and ionizing radiation

aa): Section 2: Operational organisation of radiation protection § 31 (2) sentence 2, para. 3 and 4, § 32 (2) and (3), § 34 sentence 1,
bb): Section 3: Protection of persons in radiation protection areas; physical radiation protection control § 40 para. 2 sentence 2,
cc): Section 4: Protection of the population and the environment in the case of exposure to radiation from activities § 47 (1) sentence 1 in conjunction with § 5,
dd): Section 5: Protection against significant security incidents § 49 (1) sentence 1 and (2), § 50 (1) sentence 1, para. 2 and 3, § § 52, 53 (1), (4) and (5),
ee): Section 6: Limitation of the exposure to radiation during the exercise of the profession § 58 (5),
ff): Section 7: Occupation of occupational health care workers § 61 (3) sentence 2,
gg): Section 8: Other requirements § 69a,

c)

Part 2 Chapter 4: Special requirements for the medical use of radioactive substances and ionizing radiation, Section 1: Heilkunde und Zahnheilkunde § 81 (7), § 83 (4) sentence 1,

2.

the protection rules laid down in the following parts, chapters and sections are complied with:

a)

Part 2 Chapter 2: Approvals, authorisations, release, Section 9: Release of Section 29 (2) sentence 4,

b)

Part 2 Chapter 3: Requirements for the use of radioactive substances and ionizing radiation

aa)

Section 2: Operational organisation of radiation protection § 35,

bb)

Section 3: Protection of persons in radiation protection areas; physical radiation protection control

aaa): Section 36 (1) sentence 1, subsection 2 sentence 1 and 2 and paragraph 4 sentence 1, § 37 para. 1 sentence 1 and paragraph 2, § § 38, 39, 40 para. 1 sentence 1 and 2 and subsection 2 sentence 1, para. 3 and 4, § 41 (1) sentence 1, subparagraphs 2 and 3 sentence 1 to 4, paragraph 4 sentence 1, paragraphs 5, 6 and 9, § 42 para. 1, 2 sentence 2 and para. 3, § § 43, 44 (1) sentence 1 to 3, paragraph 2 sentence 1, paragraph 3 sentence 1 to 3, paragraphs 4 and 5, § 45 (1) and (3),
bbb): Section 42 (2), first sentence,

cc)

Section 4: Protection of the population and the environment in radiation exposures from activities

aaa): Section 46 (1) to (3), Section 47 (1) sentence 1, in conjunction with § 5,
bbb): Section 47 (1) sentence 2, § 48 (1) no. 1,
ccc): Section 48 (1) (2),

dd)

Section 5: Protection against significant security incidents § § 51 para. 1 sentence 1 and 2, 53 para. 2,

ee)

Section 6: Limitation of exposure to radiation during the exercise of the profession

aaa): § § 55, 56 sentence 1, § 58 (1) sentence 2 in conjunction with § 5,
bbb): § 57, sentence 1, § 58 (2) to (5), § 59 (2) and (3),

ff)

Section 7: Occupation of occupational health care workers § 60 (1), (2) and (5), § 63 (1),

gg)

Section 8: Other requirements

aaa): § § 65, 66 (2) sentence 1, para. 5 and 6 sentence 1 and 2, § § 67, 68 (1), (1a), 3 to 6, § 69 (1) to (3) and (5), § 70 (1) sentence 1 (2) and sentence 4, (2) sentence 1 and 2, (3), (4) and (6),
bbb): § 66 (6) sentence 3, § 68 (1b), § 70 (1) sentence 1, no. 1 and 3, and sentence 3, § 71 (1) sentence 2 and 4,

hh)

Section 9: Radioactive wastes § 72 sentence 1 and 3, § 73 para. 1, 2 sentence 1, para. 3 and 4, § 74 para. 2 and 3, § 75 para. 1 to 3, § 76 para. 1 to 5, § 78 sentence 1, § 79 sentence 1,

c)

Part 2 Chapter 4: Medical radiation applications

aa): Section 1: Special requirements for the medical use of radioactive substances and ionizing radiation § 80 (1) sentence 1, para. 2 and 3, § 81 (1) sentence 1 and 2, subsection 2 sentence 1 and 2, para. 5 sentence 1 and 2 and subsection 6 sentence 1, § § 82, 83 The first sentence of the first sentence of paragraph 4, the first sentence of paragraph 5, paragraphs 6 and 7, § 84, 85 (1) to 3, first sentence, (4), first sentence, and (6), first sentence, and (3), § 86,
bb): Section 2: Medical research § 87 (1) sentence 2 and (3) to (7), § 88 (1), 2 sentence 1 and (3) and (4), § 89,

d)

Part 2 Chapter 5: Application of radioactive substances or ionising radiation in veterinary medicine § § 92a, 92b (1) and (2),

e)

Part 5 Chapter 1: consideration of radiation exposures § 111 and

3.

the necessary measures are being taken against an unintentional critic of nuclear fuel.

(2) The radiation protection officer shall ensure that:

1.

a): within the limits of its duties and powers, the protective measures referred to in paragraph 1 (2) and,
b): insofar as they have been transferred and fulfilled in accordance with section 31 (2), the provisions of the date of the authorization or general authorisation and the orders and requirements issued by the competent authority

are complied with and

2.

the person responsible for radiation protection is informed in accordance with § 32 (2) sentence 1 or § 113 (2) sentence 3.

(3) The radiation protection officer and the radiation protection officer shall ensure that, in the event of danger to man and the environment, appropriate measures shall be taken without delay to avert such danger. Unofficial table of contents

Section 34 Radiation protection directive

A radiation protection statement shall be issued in which the radiation protection measures to be observed in the establishment are to be listed. These measures shall include:

1.: the establishment of a plan for the organisation of radiation protection, with the provision, if necessary, of the fact that one or more radiation protection officers must be permanently present or immediately reachable in the approved activity,
2.: the regulation of the operational sequence for the protection of radiation,
3.: the measurements and measures for the determination of body dose, in accordance with exposure conditions,
4.: the management of an operational manual in which the operations essential to the protection of radiation are to be entered;
5.: the periodic functional testing and maintenance of irradiation equipment, installations for the production of ionizing radiation, equipment and equipment essential to radiation protection, as well as the management of records of the functional tests and on the maintenance,
6.: the establishment of a plan for regular alert exercises, as well as for use in the event of accidents and incidents, if necessary with rules on fire protection and the preparation of damage control in accordance with § 53, and
7.: the regulation of the protection against disturbance or other effects of third parties, against the removal of radioactive substances or against the unauthorised commissioning of a radiation device or plant for the production of ionizing agents Rays.

The radiation protection instruction may be part of any other necessary operating instructions according to occupational safety, emission protection or vehicle safety regulations. Unofficial table of contents

Section 35 Interpretation or application of the Regulation

An impression of this Regulation shall be kept in establishments or separate branches, in the case of non-traders in the place of activity, to be kept available for inspection whenever at least one person regularly employs or under the supervision of: in another.

Section 3
Protection of persons in radiation protection areas; physical radiation protection control

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Section 36 Radiation protection areas

(1) In the case of activities in accordance with Article 2 (1) (1) (a), (c) or (d) in need of approval and display, radiation protection areas shall be set up in accordance with the provisions of sentence 2. Depending on the level of radiation exposure, a distinction is made between monitoring areas, control areas and restricted areas, the latter as parts of the control areas, taking into account external and internal radiation exposure:

1.: Surveillance areas are non-controlling operational areas in which persons in the calendar year have an effective dose of more than 1 millisievert or higher organdoses than 15 millisievert for the eye lens or 50 millisievert for the skin, the hands, the forearms, the feet and the ankles can be preserved,
2.: Control areas are areas in which persons in the calendar year have an effective dose of more than 6 millisieverts or higher organdoses than 45 millisievert for the eye lens or 150 millisievert for the skin, hands, forearms, feet and Ankles can be obtained
3.: Blocking areas are areas of the control area in which the local dose rate can be higher than 3 millisieverts by hour.

A residence time of 40 hours per week and 50 weeks in the calendar year is decisive for the determination of the limit of control or surveillance area, unless there are other reasoned information on the period of stay. (2) Control areas and restricted areas are to be distinguished and clearly visible and permanently in addition to the marking in accordance with § 68 (1) sentence 1 no. 3 with the addition "CONTROL AREA" or "BLOCKING AREA-NO ACCESS-" to be marked. In addition, blocking areas are to be secured in such a way that persons, even with individual parts of the body, cannot enter in an uncontrolled manner. The Authority may allow exceptions to the provisions of sentences 1 and 2 if it does not endanger individuals or the general public. (3) The competent authority may decide that further areas should be treated as radiation protection areas if this is the case. Protection of individuals or of the general public is required. In the operation of installations for the production of ionizing radiation or irradiation devices, the competent authority may allow areas to be considered as control areas or restricted areas only during the on-time of these installations or devices (4) In the event of a change in the location of radioactive substances and the operation of mobile installations for the production of ionizing radiation or radiation devices, a control area to be established in accordance with the second sentence of paragraph 1, second sentence, shall be and to indicate that uninvolved persons do not be able to enter unintentionally. If it is possible to rule out the possibility of unintentional entry into the control area, it is not necessary to define the control area. Unofficial table of contents

Section 37 Access to radiation protection areas

(1) Persons may be allowed to enter

1.

to be allowed to be monitored only if:

a): carry out a task in which the operation is carried out,
b): their stay in this area is required as a patient, a proband, a helping person or an animal accompanying person,
c): in the case of apprentices or students, this is necessary in order to achieve their training target, or
d): they are visitors,

2.

to control areas only if:

a): they have to act to carry out or maintain the operations provided for therein;
b): your stay in this area is required as a patient, a proband, a helping person or an animal accompanying person, and a person entitled to exercise the medical, dental or veterinary profession, who has the necessary specialist knowledge in the Radiation protection has agreed,
c): in the case of apprentices or students, this is necessary in order to achieve their training target, or
d): in the case of pregnant women, the competent radiation protection officer or the radiation protection officer shall do so and shall ensure, through appropriate monitoring measures, that the special dose limit is complied with in accordance with § 55 (4) sentence 2 and this is documented,

3.

Restricted areas are only allowed if:

a): to carry out operations in the restricted area or for compelling reasons and under the control of a radiation protection officer or a person appointed by him, who shall carry out the necessary technical studies in the radiation protection, standing or
b): your stay in this area is required as a patient, a professional or a helping person, and a person entitled to practize the medical or dental profession, who has the required subject in radiation protection, in writing agreed.

The competent authority may allow the competent authority responsible for radiation protection, or the competent radiation protection officer, to allow other persons to enter radiation protection areas. Rights of use under other legal regulations shall remain unaffected. (2) A pregnant woman shall be allowed to enter

1.: the restricted areas are not permitted unless their stay as a patient is required,
2.: by way of derogation from the first sentence of the first sentence of paragraph 1, point 2 (b), as a helping person, shall be permitted only where there are compelling reasons for such control,
3.: By way of derogation from the first sentence of paragraph 1, point 2 (b), control areas shall not be permitted as an animal accompanying person.

By way of derogation from the first sentence of paragraph 1, point 2 (b), a breast-feeding woman shall not be allowed to enter as an animal accompanying person in control areas in which the radioactive substances are being treated with open radioactive substances. Unofficial table of contents

§ 38 Substruction

(1) Persons authorised to enter control areas pursuant to Article 37 (1) sentence 1 (2) (a) or (c) or (3) (a) shall be entitled, before initial access, to the working methods, the possible risks, the security to be applied. and safeguard measures and the substance of this Regulation, the authorisation, the radiation protection statement and the essential content of their employment or their presence, for the purpose of monitoring dose limits and compliance with Radiation protection principles concerning the processing and use of personal data instruct. The first sentence shall also apply to persons who, outside the control area, deal with radioactive substances or who use ionizing radiation to the extent that such activity requires authorisation. The instruction shall be carried out at least once a year. This instruction may be part of any other necessary instructions in accordance with regulations on protection or employment protection. (2) Other persons who are allowed access to control areas shall be previously informed of the possible (3) In the context of the teachings referred to in paragraph 1 or 2, women must be informed that pregnancy is as early as possible with regard to the risks of exposure to radiation for the unborn child. is to be communicated In the event of a contamination of the mother, it should be noted that the infant could be incorporated into radioactive substances when breastfeeding. (4) The contents and the date of the instructions referred to in paragraph 1 or 2 shall be kept in keeping with the records which: are to be signed by the person who has been instructed. Records shall be kept for a period of five years in the cases referred to in paragraph 1, in which paragraph 2 shall be kept for one year after the instruction and shall be submitted to the competent authority upon request. Unofficial table of contents

Section 39 Measurement of metrological control in radiation protection areas

In radiation protection areas, the extent required for the determination of the radiation exposure is in each case individually or in combination

1.: the local dose or the local dose rate, or
2.: the concentration of radioactive substances in the air, or
3.: the contamination of the workplace

to measure. Unofficial table of contents

§ 40 Persons To Be Monitored

(1) The body dose should be determined on persons who are in the control area. The results of the investigation must be available no later than nine months after the stay in the control area. If, during the stay in the control area, it is ensured that in the calendar year an effective dose of 1 millisievert or higher organdoses cannot be reached than one tenth of the Organdosi limit values of section 55 (2), the competent authority may: (2) Anyone who requires a permit pursuant to Article 15 (1) shall ensure that the persons under his supervision are employed in control areas only if each individual professionally exposed person is exposed to radiation. Person in possession of a fully managed, registered office registered with the competent authority Radiation passes. If he himself is active in control areas, the first sentence shall apply accordingly. The competent authority may recognise records of exposure to radiation issued outside the scope of this Regulation as being sufficient within the meaning of the first sentence if the latter correspond to the radiation passport. The Federal Government, with the consent of the Federal Council, shall adopt general administrative provisions concerning the content, form, management and registration of the radiation passport. (3) Persons exposed to radiation as referred to in the first sentence of paragraph 2 may be employed in the The control area shall only be permitted if they present the radiation pass according to the first sentence of paragraph 2 and carry a dosemeter according to § 41 (3) sentence 1. (4) Any person who is authorised pursuant to § § 6, 7 or 9 of the Atomic Energy Act or in accordance with § 7 or § 11 (2) of this Act Regulation or a planning decision pursuant to Section 9b of the Atomic Energy Act shall require each of the following: (a) to be informed in writing, at their request, of the occupational radiation exposure obtained in the employment relationship, unless already on the basis of a permit pursuant to Article 15 (1) of this Directive, (5) The competent authority may order that persons who are not professionally exposed or have stopped in areas where the activities referred to in Article 2 (1) (1) (1) (1) (1)) do not apply. of this Regulation shall, by means of appropriate measurements, determine whether: they have incorporated radioactive substances. It can arrange for the body dose to be determined in the case of persons who are in the surveillance area. Unofficial table of contents

Section 41 Determination of body dose

(1) The dose of person is measured for the determination of the body dose. The competent authority may, on the basis of the conditions of exposure, determine in addition or, by way of derogation from the first sentence, that the body dose may be determined in addition to the dose.

1.: the local dose, the local dose rate, the concentration of radioactive substances in the air or the contamination of the workplace is measured,
2.: the body activity or the activity of the excretions is measured or
3.: further properties of the radiation source or of the radiation field are determined.

The competent authority may set a replacement dose in the event of a subliminal or defective measurement. The competent authority shall designate measurement points for measurements in accordance with the first sentence and for the measurements referred to in the second sentence of 2. (2) If, on the basis of the findings referred to in paragraph 1, there is a suspicion that the dose limit values of § 55 are exceeded, the The dose should be measured by taking into account the exposure conditions. (3) The personal dose is to be measured with

1.: a dosemeter to be requested at a measurement point determined in accordance with the fourth sentence of paragraph 1, or
2.: a dosemeter whose measured value is evaluated in the establishment of the person to be monitored and whose use has been authorised by the competent authority after the approval of a measuring point determined in accordance with the fourth sentence of paragraph 1.

The dosimeters are to be worn at a point of body surface area which is representative of the exposure to radiation, usually at the front of the hull. The indication of this dosimeter shall be measured as a measure of the effective dose, provided that the body dose for individual body parts, organs or tissues has not been determined more precisely. If it is to be seen that in the calendar year the organdosis for the hands, forearms, feet and ankles or skin is greater than 150 millisievert or the organdosis of the eye lens is greater than 45 millisievert, the person dose shall be to determine further dosimeters also on these parts of the body. The competent authority may order that the personal dose shall be measured by another appropriate method or by two independent procedures. (4) The dosimeters referred to in the first and fourth sentences of paragraph 3 shall be the measuring point at the end of one month. or, in the case referred to in the first sentence of paragraph 3, point 2, to provide the measurement point of the measuring point for verification and determination, in which case the personal data (surname, first name, date and place of birth, sex), in the case of radiation passport holders in accordance with § 40 (2) sentence 1 and 2, the registration number of the radiation passes, as well as the characteristics of employment and the conditions of exposure. The competent authority may allow dosemeters to be submitted at intervals of up to three months at the measuring point. (5) The person to be monitored shall be required to provide a dosimeter at the request of the person to be monitored at any time with the dose of the person. can be detected. As soon as a woman has informed her employer that she is pregnant, her occupational exposure to radiation is to be determined and reported on a weekly basis. (6) The measurement of the body activity or activity of the excrements is in the case of a measuring point determined in accordance with the fourth sentence of paragraph 1. The measuring point is the personal data (surname, first name, date and place of birth, sex), in the case of radiation passport holders according to § 40 (2) sentence 1 and 2, the registration number of the radiation passport as well as the employment characteristics and the (7) The measuring point referred to in the first sentence of paragraph 3 shall be subject to the provision of personal dosimeters or, in the case referred to in the first sentence of paragraph 3, point 2 of the use; it shall determine the dose of persons, the results of which shall be: record and inform them in writing of the person who has made the measurement. The measuring point referred to in the first sentence of paragraph 6 shall determine the body activity or the activity of the excretions and the body dose in question, record the results and inform the person who has made the measurement in writing. The measuring points shall keep their records for five years after the relevant determination. They shall, on request, communicate the results of their findings, including the information referred to in the first sentence of paragraph 4 or the second sentence of paragraph 6, to the competent authority. (8) The measuring points referred to in the first sentence of paragraph 3 and the first sentence of paragraph 6 shall take the form of measures to: Quality assurance carried out by the Physikalisch-Technische Bundesanstalt (Physikalisch-Technische Bundesanstalt) for the measurements referred to in the first and fourth sentences of paragraph 3 and by the Federal Office for Radiation Protection (Bundesamt für Strahlenschutz) for measurements pursuant to the first sentence of paragraph 6. (9) The quality of the measurements referred to in The second sentence of paragraph 2 shall be ensured by means of regular internal audits. The results of the tests shall be communicated to the competent authority upon request. Unofficial table of contents

Section 42Oblition to record and share

(1) The results of the measurements and investigations in accordance with § § 40 and 41 shall be recorded immediately. The records shall be kept until the person being monitored is 75. At least 30 years after the end of the respective employment. They shall be deleted no later than 100 years after the birth of the person concerned. They shall be submitted at the request of the competent authority or shall be deposited in the case of a body to be determined by the competent authority. In the event of a change in the employment relationship, the results of the investigation shall be communicated to the new employer upon request if employment continues to be carried out as a person exposed to work. Records which are no longer required as a person exposed to radiation as a result of termination of employment shall be handed over to the body responsible under national law. § 85 (1) sentence 4 shall apply accordingly. (2) Exceedances of the limits of the body dose in accordance with § 55 (1) sentence 1, para. 2 and 3 sentence 1, para. 4 and radiation exposures in accordance with § 58 (1) sentence 2 shall be the competent authority, stating the reasons that: the persons concerned and the body doses determined. The person concerned must be informed immediately of the body dose. (3) In the event of exceedances of the values of surface contamination in accordance with section 44 (2) (3), paragraphs 1 and 2 shall apply accordingly. Unofficial table of contents

Section 43 Protection measures

(1) The protection of exposed persons from external and internal radiation exposure shall be ensured, as a priority, by means of constructional and technical devices or by appropriate working methods. (2) As soon as a woman has her employer, has been informed that she is pregnant or breastfeeding, that her working conditions are to be designed in such a way that an internal occupational exposure to radiation is excluded. (3) In the case of persons who deal with open radioactive substances, the activity of which is the The free limits of Appendix III, Table 1, column 2 and 3, shall be ensure that they carry the necessary protective clothing and that they use the necessary protective equipment. They shall be subject to a behaviour in which they or others may take up radioactive substances in the body, in particular by eating, drinking, smoking, by using health care products, or by using them in the body. Cosmetic products. This shall also apply to persons residing in areas where the activity of open radioactive substances is dealt with, the activity of which exceeds the free limits of Annex III, Table 1, columns 2 and 3. Open radioactive substances may only be present in workplaces for as long and in such activities as the working method requires. Unofficial table of contents

§ 44 Contamination and decontamination

(1) In the case of the presence of open radioactive substances in radiation protection areas, to the extent necessary for the protection of the persons or the materials in question, it is necessary to establish whether or not contamination by such substances exist. Persons leaving control areas where there are open radioactive substances shall be tested to see whether they are contaminated. Where contamination is detected, measures shall be taken without delay to prevent further exposure to radiation and the redistribution of radioactive substances. The competent authority may stipulate that a test in accordance with the second sentence shall also be carried out on leaving the surveillance zone. (2) To prevent the retransmission of radioactive substances or their inclusion in the body, the competent authority shall immediately: Measures to be taken if:

1.: in the case of traffic areas, workplaces or clothing in control areas, it is found that the non-adherent surface contamination exceeds 100 times the values of Annex III, Table 1, column 4; or
2.: in the case of traffic areas, workplaces or clothing in surveillance areas, it is found that the non-adherent surface contamination exceeds 10 times the values of Annex III, Table 1, column 4; or
3.: out of a radiation protection area on the premises, surface contamination of land, buildings and movable objects, in particular clothing, exceeds the values of Annex III, Table 1, column 4.

Sentence 1 shall not apply to the goods which are transported as dangerous goods in accordance with § 2 of the German Dangerous Goods Transport Act or in accordance with Article 69 of this Regulation. (3) Should movable objects, in particular tools, measuring instruments, should be used. Measuring devices, other apparatus, equipment parts or garments, of control areas for the purpose of handling, use or other use with the aim of re-using or repairing outside radiation protection areas , it must be checked whether they are activated. In addition, if movable objects within the meaning of the first sentence for the purposes and objectives referred to therein are to be brought out of control areas in which there are open radioactive substances, it shall also be necessary to check whether these objects are contaminated . Articles referred to in the first sentence shall not be taken out of the control area if:

1.: in the case of their activation, the values of Annex III, Table 1, column 5, are exceeded, or
2.: in the case of their contamination, the values of Annex III, Table 1, column 4 or column 5, are exceeded.

The competent authority may stipulate that the sentences 1 to 3 shall also be applied to surveillance areas. The sentences 1 to 3 do not apply to the items which are transported as dangerous goods in accordance with § 2 of the Dangerous Goods Transport Act or are handed out in accordance with Article 69 of this Regulation. § 29 shall not apply. (4) Only persons who possess the necessary knowledge may be entrusted with a decontamination treatment. (5) The values of surface contamination referred to in the first sentence of paragraph 2, point 1 or no. 2, cannot be used. , the persons employed in such work areas shall be protected by special measures. Unofficial table of contents

Section 45 Employment bans and restrictions on employment

(1) It is necessary to ensure that persons under the age of 18 years do not deal with open radioactive substances above the free limits of Annex III, Table 1, columns 2 and 3. (2) The competent authority may grant exemptions from paragraph 1 for apprentices and apprentices. Allow students aged between 16 and 18, to the extent that this is necessary to achieve their training objectives, and to have permanent supervision and guidance by a person who has the necessary expertise in radiation protection, (3) It is necessary to ensure that students need to be treated in a way that is subject to approval. radioactive substances only in the presence and under the supervision of the competent radiation protection officer.

Section 4
Protection of the population and the environment in radiation exposures from activities

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Section 46 Limitation of the exposure of the population

(1) For individuals of the population, the effective dose limit is a millisievert in the calendar year from activities in accordance with § 2 (1) (1) (1). (2) Without prejudice to paragraph 1, the limit value of the organdosis shall be: the eye lens 15 millisievert in the calendar year and the limit of the organdosis for the skin 50 millisievert in the calendar year. (3) In the case of installations or facilities, the limit value for the effective dose referred to in paragraph 1 shall apply to the premises or facilities. Sum of radiation exposure from direct radiation and radiation exposure Derivations. The periods of residence applicable to the exposure of radiation from direct radiation shall be based on the spatial conditions of the facility or facility or location; there shall be no substantiated information for the periods of residence, To accept permanent residence. Unofficial table of contents

Section 47 limitation of the disposal of radioactive substances

(1) The following limit values shall apply to the planning, construction, operation, decommissioning, safe containment and dismantling of installations or installations, by means of air or water discharges from such installations, or Facilities in each case conditional radiation exposure of individuals of the population in the calendar year:

1.	Effective dose	0.3 millisievert
2.	Organdosis for germ glands, Uterus, bone marrow (red)	0.3 millisievert
3.	Organdosis for large intestine, lung, Stomach, bladder, breast, liver, Esophagus, thyroid gland, other Organs or tissues in accordance with Annex VI Part C No. 2 footnote 1, unless referred to in paragraph 2	0.9 millisievert
4.	Organdosis for bone surface, skin	1.8 millisievert.

It is necessary to ensure that radioactive substances are not discharged into the environment in an uncontrolled manner. (2) When planning installations or facilities, the exposure to radiation as referred to in paragraph 1 shall be the most unfavourable for a reference person. Identifying the exposure pathways, taking into account the exposure paths referred to in Annex VII, Part A to C, the life habits of the reference person and other assumptions, with the average consumption rates of Annex VII, Part B, Table 1 multiplied by the factors of column 8. The Federal Government, with the consent of the Federal Council, shall adopt general administrative provisions relating to the further assumptions to be made. The competent authority may assume that the limit values set out in paragraph 1 are complied with, if this is demonstrated on the basis of the general administrative provisions. (3) For the establishment, decommissioning, safe confinement and the dismantling of installations or installations shall determine the permissible discharges of radioactive substances with air and water by limiting the concentrations of activity or amounts of activity. Proof of compliance with the limit values laid down in paragraph 1 shall be deemed to have been provided if these limits are not exceeded. (4) In the case of installations or facilities which are not authorised in accordance with § § 6, 7 or 9 of the Atomic Energy Act and none of the following: In accordance with Article 9b of the German Atomic Energy Act, the competent authority may depart from the determination of amounts of activity and activity concentrations and the proof referred to in paragraph 2 in order to comply with the limit values referred to in paragraph 1. as provided, provided that the activity concentrations permitted under Annex VII, Part D, Discharges of radioactive substances with air or water from radiation protection areas shall not be exceeded in the annual average. Unless the competent authority decides otherwise, the permissible concentrations of activity at the limit of a radiation protection area shall be complied with. The first sentence shall not apply if there is evidence to the satisfaction of the competent authority that the limit values referred to in paragraph 1 at one site may be exceeded by discharges from installations or installations or previous activities. (5) In so far as discharges from the operation of other installations or installations or previous activities within the scope of this Regulation at these or other sites for exposure to radiation shall be carried out at the points of impact referred to in the first sentence of paragraph 2 , the competent authority shall ensure that the competent authority referred to in paragraph 1 Total values are not exceeded. The assumptions to be made for the consideration of other installations and facilities shall be incorporated into the general administrative provisions referred to in paragraph 2. Unofficial table of contents

§ 48 Emission and Immission Monitoring

(1) It is necessary to ensure that discharges from installations or facilities

1.: monitor and
2.: according to the type and activity specified by the competent authority shall be communicated at least annually. The competent authority may, on a case-by-case basis, exempt wholly or in part from the obligation to provide notification if it can otherwise sufficiently assess that the limit values set out in § 47 (1) sentence 1 are not exceeded by the deduction.

(2) The competent authority may order that, in the operation of installations or facilities, the activity of samples from the environment, as well as the local doses according to a plan to be determined, shall be determined by measurement and that the results of the measurement shall be determined by the competent authority. shall be submitted to the competent authority upon request and shall be made available to the public. The competent authority may designate the body to carry out the measurements. (3) The competent authority may order that, in the case of installations or facilities subject to an authorisation pursuant to § 6, 7 or 9 of the Atomic Energy Act or of a Decision of the planning decision in accordance with § 9b of the Atomic Energy Act requires, in order to determine the exposure to radiation by discharges, in addition to the information referred to in paragraph 1, the necessary for the meteorological and hydrological propagation conditions Data should be identified and communicated to the competent authority at least annually. (4) To ensure a uniform quality standard for emission and immission monitoring, the federal administration authorities referred to in Annex XIV carry out comparative measurements and comparative analyses as guidance points. The control centres also have the task of developing and defining sampling, analysis and measurement methods as well as to summarize, process and document the data of emission and immission monitoring. The Physikalisch-Technische Bundesanstalt provides radio-activity standards for comparison measurements.

Section 5
Protection against safety-related events

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§ 49 Safety engineering design for the operation of nuclear power plants, for the location-near storage of irradiated fuel elements and for federal plants for the purpose of securing and disposal of radioactive waste

(1) In the planning of constructional or other technical protection measures against incidents in or at a nuclear power plant which is used for the production of electricity, up to the decommissioning pursuant to Section 7 (3) of the Atomic Energy Act, without prejudice to the requirements of the § § 6 in the vicinity of the facility in the worst possible incident caused by the release of radioactive substances into the environment at most

1.: an effective dose of 50 millisieverts,
2.: an organdosis of the thyroid gland and the eye lens of 150 millisieverts each,
3.: an organdosis of the skin, hands, forearms, feet, and ankles of 500 millisieverts each,
4.: an organdosis of the germ glands, the uterus, and the bone marrow (red) of 50 millisieverts each,
5.: an organdosis of the bone surface of 300 millisievert,
6.: an organdosis of the colon, the lung, the stomach, the bladder, the breast, the liver, the oesophagus, the other organs or tissues in accordance with Annex VI, Part C, No 2, footnote 1, unless not mentioned in point 4, of 150 millisieverts each

on the basis of the The state of science and technology is decisive for adequate protection against accidents according to sentence 1. The approval authority may, in particular, consider this provision if, in the design of the installation, the applicant has taken the basis of the incident which, in accordance with the published safety criteria and guidelines, provides for: Nuclear power plants must determine the design of a nuclear power plant. (2) The first sentence of the first sentence of paragraph 1 and 2 shall also apply to the storage of irradiated nuclear fuels according to § 6 of the Atomic Energy Act at the respective sites of the approved nuclear materials according to § 7 of the Atomic Energy Act. Nuclear power plants as well as federal plants for the securing and disposal of radioactive waste Waste. (3) Paragraphs 1 and 2 shall not apply to goods which are transported as dangerous goods in accordance with § 2 of the Dangerous Goods Transport Act. Unofficial table of contents

§ 50 Limitation of exposure to radiation as a result of incidents in other installations and installations and in the case of decommissioning

(1) In the planning of installations other than those referred to in § 49 of the Atomic Energy Act, structural or technical protection measures shall be taken, taking into account the potential extent of damage, in order to ensure the exposure to radiation in the event of a fault. by the release of radioactive substances into the environment. The approval authority shall determine the nature and extent of the protective measures taking into account the individual case, in particular the hazard potential of the installation and the probability of the occurrence of an accident. (2) Paragraph 1 shall also apply to the Decommissioning, the safe confinement of the permanently decommissioned plants and the dismantling of installations or parts of the plant according to § 7 (3) sentence 1 of the Atomic Energy Act. (3) For the remaining activities pursuant to § 6 (1) and § 9 (1) of the Atomic Energy Act, paragraph 1 shall apply. accordingly. Sentence 1 shall also apply to dismantling and decommissioning activities in the context of activities pursuant to § 6 (1) and § 9 (1) of the Atomic Energy Act. The first sentence shall also apply to the activities referred to in Article 7 of this Regulation, in which, at more than 10 (high) 7 times the free limits of Appendix III, Table 1, column 2 is an open radioactive substance or more than 10 (high) 10 times the free limits of the installation. III Table 1, column 2, as enclosed radioactive substance, unless a single holding or independent branch, in the case of non-traders at the place of activity of the marketing authorisation holder, is treated with these radioactive substances in several, spatially separated buildings, parts of buildings, installations or The Federal Government shall, with the consent of the Federal Government, ensure that the radioactive substances from the individual buildings, parts of buildings, installations or facilities are not able to cooperate. Federal Council general administrative provisions in which, taking into account the probability of occurrence of the extent of the damage and the multiple of the free limits for open and enclosed radioactive substances, in the case of activities pursuant to section 7 (1) of this Regulation of protection objectives for the prevention of accidents according to paragraphs 1 to 3 (5) The provisions of paragraphs 1 to 3 shall not apply to goods which are transported as dangerous goods in accordance with § 2 of the Dangerous Goods Transport Act. Unofficial table of contents

Section 51 Measures in the case of safety-related events

(1) In case of radiological emergencies, accidents and incidents, all necessary measures shall be taken without delay in order to minimize the risks to man and the environment. The occurrence of a radiological emergency situation, an accident, an accident or any other relevant safety-related event shall be the nuclear regulatory authority and, if necessary, also the one for the public authorities. (2) In case of radiological emergency situations, the competent authorities shall immediately inform the competent authorities of the potentially affected persons. population and provide information on behavioural measures, , including accurate indications of health protection measures to be taken. The information to the population shall contain the information listed in Annex XIII, Part A. Unofficial table of contents

Section 52 Preparation of fire-fighting

In order to prepare fire-fighting, the necessary measures must be planned with the authorities responsible under national law. In particular, it is necessary to determine at which locations the fire brigade (in underground operations: mine brigade) in case of use

1.: be able to take action without special protection against the risks of radioactive substances (Group I),
2.: can only be carried out using a special equipment (category II) and
3.: can be used only with special equipment and with the help of an expert who can assess the risk of radiation arising during the operation and the protective measures to be applied (category III).

The areas concerned shall each be clearly visible and permanently marked with the sign "hazard group I", "danger group II" or "danger group III". Unofficial table of contents

Section 53 Preparation of damage control in case of safety-related events

(1) In order to contain and eliminate the hazards caused by accidents or incidents on the premises, the necessary staff and the necessary tools shall be required to do so. The competent authority shall be required to demonstrate its operational capability. This can also be done by demonstrating the right to use an institution suitable for the performance of these tasks. (2) The competent authority responsible for public safety or order as well as the civil protection authority responsible for civil protection. The authorities, the fire brigades and the public and private relief organisations must provide the necessary information and advice for the elimination of a radiological emergency situation, an accident or an accident. The same is true for the planning of the elimination of the consequences of a radiological emergency situation, an accident or an accident. In addition, the competent authorities, the fire brigades and the aid organisations shall provide any information and advice which may be used for the training and further training of operational staff and for the provision of information in respect of the occurrence of (3) The competent authorities, fire brigade and aid organisations shall inform the persons employed in the event of a radiological emergency in the case of rescue operations. , the health risks of such an operation, and relevant precautions. The relevant information shall take account of the different types of radiological emergency situations and shall be updated regularly. The information will be supplemented, as soon as an emergency situation occurs, in accordance with the circumstances of the specific situation. (4) Paragraphs 1 and 2 shall not apply to the handling of radioactive substances, the activities of which shall be subject to the free limits of the Annex III, Table 1, column 2, shall not exceed that of

1.: 10 (high) 7 times when it is about open radioactive substances,
2.: 10 (high) 10 times when it is about enclosed radioactive substances.

The same applies to installations for the production of ionizing radiation if their establishment does not require a permit pursuant to Article 11 (1). Sentences 1 and 2 shall also apply if, in the individual holding or independent branch, in the case of non-traders at the place of activity of the applicant, radioactive substances in several buildings which are physically separate from one another, In the case of buildings, installations or facilities, the activity of the radioactive substances in the individual buildings, parts of buildings, installations or installations shall not exceed the values of the sentence 1 and shall be sufficiently ensured that the radioactive substances from the individual buildings, parts of buildings, installations or (5) As far as the public security or order, or the authorities responsible for civil protection have drawn up special protection plans in the event of a radiological emergency, the population likely to be affected in the event of a radiological emergency shall be suitably To inform at least every five years on the security measures and the correct behaviour of such events. Appropriate information shall be made available to everyone. The information shall contain the information listed in Annex XIII, Part B, and shall be updated in the event of changes which have an impact on the safety or protection of the population. To the extent that the information is intended for the protection of the public, they shall be in line with the authorities responsible for public security or public order and the authorities responsible for civil protection. The way in which the information is to be given, to be repeated and to be updated is to be coordinated with the authorities responsible for civil protection.

Section 6
Limitation of exposure to radiation during the exercise of the profession

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Section 54 Categories of persons exposed to radiation

Persons who are exposed to occupational exposure to radiation by activities in accordance with Article 2 (1) (1) No. 1 are assigned to the following categories for the purpose of control and occupational health care:

1.: Persons exposed to occupational exposure to the category A:persons exposed to occupational exposure to radiation in the calendar year to an effective dose of more than 6 millisievert or higher organdosis than 45 millisievert for the Eye lens or a higher organdosis than 150 millisievert for the skin, hands, forearms, feet or ankles can lead.
2.: Persons exposed to occupational exposure to the category B:persons exposed to occupational exposure to radiation in the calendar year to an effective dose of more than 1 millisievert or higher organdosis than 15 millisievert for the Eye lens or higher organdosis as 50 millisievert for the skin, hands, forearms, feet or ankles can lead without falling into category A.

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Section 55 Protection of occupational radiation exposure

(1) For persons exposed to radiation, the limit value of the effective dose is 20 millisievert in the calendar year. § 58 shall remain unaffected. The competent authority may, on a case-by-case basis, authorise an effective dose of 50 millisievert for a single year, with 100 millisieverts not being exceeded for five consecutive years. (2) The limit value of the organdosis is for: Persons exposed to radiation:

1.: for the eye lens 150 millisievert,
2.: for the skin, the hands, the forearms, the feet and ankles 500 millisievert each,
3.: for the germ glands, the uterus and the bone marrow (red) 50 millisievert each,
4.: for the thyroid gland and the bone surface 300 millisievert each,
5.: in the case of the colon, the lungs, the stomach, the bladder, the breast, the liver, the esophagus, other organs or tissues in accordance with Annex VI, Part C, No 2, footnote 1, unless stated in point 3, 150 millisieverts each

in the calendar year. (3) For persons under 18 years of age, the limit value of the effective dose is 1 millisievert in the calendar year. The limit value of the organdosis is 15 millisievert for the eye lens, for the skin, the hands, the forearms, the feet and ankles each 50 millisievert in the calendar year. By way of derogation from sentences 1 and 2, the competent authority for apprentices and students aged between 16 and 18 may have a limit value of 6 millisievert for the effective dose, 45 millisievert for the organdosis of the eye lens and in each case. 150 millisievert for the organdosis of the skin, hands, forearms, feet and ankles in the calendar year, if this is necessary to achieve the training target. (4) For childbearing women, the limit for the more than one month is the cumulative dose of the uterus 2 millisieverts. For an unborn child exposed to exposure to radiation as a result of the employment of the mother, the dose limit of the dose of external and internal radiation exposure shall be from the date of the notification of pregnancy to the date of the pregnancy until the date on which the child is exposed to radiation. End 1 millisievert. Unofficial table of contents

§ 56 Professional dose

The limit value for the sum of the effective doses of persons exposed to radiation exposed in all calendar years is 400 millisievert. The competent authority may, in consultation with a doctor referred to in Article 64 (1) sentence 1, authorise a further occupational exposure if the latter is not more than 10 millisievert effective dose in the calendar year and the occupational exposure to radiation exposure is not more than 10 millisievert. Person agrees. Consent shall be given in writing. Unofficial table of contents

§ 57 Dose limit for exceeding

If, in breach of Section 55 (1) or (2), a limit value has been exceeded in the calendar year, further employment as a person exposed to radiation shall be permitted only if the exposures are carried out in the following four calendar years: To take account of the fact that the limit value has been exceeded in such a way that the sum of the doses does not exceed five times the respective limit value. If the exceeding of a limit value is so high that the previous employment cannot be continued for the application of the first sentence, the competent authority may, in consultation with a doctor, allow exceptions to the first sentence of paragraph 64 (1) sentence 1. Unofficial table of contents

Section 58 Particularly authorised radiation exposures

(1) In exceptional circumstances to be assessed on a case-by-case basis, the competent authority may, by way of derogation from § 55 (1), (2) and 4 (4), permit the competent authority to carry out radiation exposures in order to carry out the necessary specific work. The limit value of the effective dose is 100 millisievert, the limit of the organdosis for the eye lens 300 millisievert, the limit of the organdosis for the skin, the hands, the forearms, the limit of the effective dose of 100 millisievert for this particularly authorised exposure. (2) A radiation exposure as referred to in paragraph 1 may only be suspended by volunteers who are professionally exposed persons of category A, except for pregnant women and, if: the possibility of contamination cannot be ruled out, Women. (3) A radiation exposure as referred to in paragraph 1 shall be justified in advance. The persons referred to in paragraph 2 shall be informed of the radiation risk associated with exposure to radiation. The works council or the staff council, the occupational safety experts, the doctor in accordance with § 64 para. 1 sentence 1 or the occupational physicians, insofar as they are not doctors according to § 64 para. 1 sentence 1, are to be involved. (4) The body dose through a radiation exposure in accordance with paragraph 1, taking into account the conditions of exposure. It shall be entered in the records in accordance with § § 42 and 64 (3) separately from the other results of the measurements and investigations of the body dose. The exposure to radiation as referred to in paragraph 1 shall be taken into account in the sum of the effective doses determined in all calendar years in accordance with § 56. (5) If the exposure limits in accordance with paragraph 1 were exceeded, the limit values of § 55 (1) or (2) have been exceeded in the case of radiation exposure. this excess alone is no reason to exclude the person without their consent from their previous employment. Unofficial table of contents

§ 59 Radiation exposure in the case of personal risk and assistance

(1) For measures to prevent hazards to persons, it is desirable to ensure that an effective dose of more than 100 millisieverts occurs only once in the calendar year and an effective dose of more than 250 millisievert only once in life. (2) The Rescue operations may only be carried out by volunteers over 18 years of age who have previously been informed of the risks of these measures. It is necessary to ensure that pregnant women are not used in rescue operations. (3) The body dose of a person employed in rescue operations by exposure to radiation in the rescue operations is taken into account Exposure conditions should be determined. The rescue measure and the determined body dose of the persons employed in the rescue operation shall be notified without delay to the competent authority. The exposure to radiation as set out in the first sentence shall be taken into account in the sum of the effective doses determined in all calendar years in accordance with Section 56. § 58 (4) sentence 2 and (5) shall apply accordingly.

Section 7
Occupational health care of persons exposed to radiation

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Section 60 requirement of occupational health care

(1) A professionally exposed person in category A may only perform tasks in the control area if it has been examined by a doctor in accordance with Article 64 (1) sentence 1 within one year before the start of the exercise of the duties and the person who has been subject to the task of the Persons responsible for radiation protection shall have a certificate issued by this doctor who does not have any health concerns as to the exercise of the duties. (2) A professionally exposed person in category A may be referred to in paragraph 1. after the end of a year since the last assessment or investigation only carry out tasks further if it has been re-evaluated or investigated by a doctor in accordance with § 64 (1) sentence 1 and if the person responsible for radiation protection has received a certificate issued by this physician, that the person responsible for the Task perception does not have any health concerns. If an assessment has been carried out in one year, the person shall be examined in the following year. (3) The competent authority may, on a proposal from the doctor referred to in Article 64 (1) sentence 1, shorten the time limit referred to in paragraph 2 if the (4) The competent authority may, in the appropriate application of paragraphs 1 and 2, apply to a professionally exposed person of category B measures of occupational health care. (5) After completion of the task perception ensure that occupational health care is continued with the consent of the person concerned for as long as the doctor considers it necessary to protect the person exposed to radiation in accordance with Article 64 (1) sentence 1 (subsequent investigation). Sentence 1 shall also apply in the case of special occupational health care pursuant to Section 63 (1). The obligation to offer subsequent examinations no longer exists if the competent statutory accident insurance institution has the following examination with the consent of the person concerned after termination of the employment relationship. . The prerequisite for this is that the required documents must be made available to the accident insurance institution in the form of a copy; this must be made in writing to the person concerned before giving his consent. Unofficial table of contents

Section 61 Medical certificate

(1) In accordance with § 64 (1) sentence 1, the doctor must request the medical certificate issued by other doctors pursuant to § 64 (1) sentence 1 for the granting of the medical certificate to the extent that such medical records are required for the assessment , as well as the medical certificates issued up to now, the decisions taken by the authorities in accordance with Section 62 and the opinion on the basis of which they are based. The requested documents must be handed over to the doctor without delay in accordance with § 64 (1) sentence 1. The medical certificate must be issued on the form referred to in Annex VIII. (2) The doctor may, in accordance with § 64 (1) sentence 1, make the issue of a medical certificate conditional upon him being granted a medical certificate.

1.: the nature of the tasks of the person exposed to radiation and the working conditions associated with those tasks,
2.: any change in the nature of the tasks and the working conditions associated with them;
3.: the results of the physical radiation protection control according to § 42 and
4.: the contents of the last medical certificate

in writing. The person who is subject to occupational health care may request a copy of these communications. (3) The doctor referred to in § 64 (1) sentence 1 shall have the medical certificate to the person responsible for radiation protection who exposed the occupational exposure to radiation. The competent authority shall be immediately sent to the competent authority and, if there are any health concerns, to the competent authority without delay. The medical certificate must be kept and, at the request of the competent authority, kept for the duration of the performance of tasks as a person exposed to radiation. The consignment to the person exposed to radiation can be replaced by the registration of the certificate in the radiation passport. (4) The medical certificate may be replaced by the decision of the competent authority in accordance with § 62. Unofficial table of contents

Section 62 Public Decision

(1) If the person responsible for radiation protection or the person exposed to the profession does not apply the assessment made by the doctor in accordance with § 64 (1) sentence 1 in the certificate according to § 61, the decision of the competent authority may be (2) The competent authority may, prior to its decision, obtain the opinion of a doctor who has the expertise in radiation protection required for the occupational health care provision of persons exposed to radiation. The costs of the medical expert opinion shall be borne by the person responsible for radiation protection. Unofficial table of contents

Section 63 Special occupational health care

(1) It cannot be ruled out that a person has received radiation exposures through a radiation exposure in accordance with § 58 or § 59 or on the basis of other exceptional circumstances, which in the calendar year the effective dose of 50 millisievert or the Organdosis of 150 millisieverts for the eye lens or of 500 millisieverts for the skin, the hands, the forearms that exceed the feet or ankles, shall ensure that it is immediately presented to a doctor in accordance with § 64 (1) sentence 1. (2) If, according to the result of the special occupational health provision referred to in paragraph 1, it is necessary to ensure that: this person is put at risk in the course of his or her health if he or she is once again performing or continuing a task as a professionally exposed person, the competent authority may order that he or she shall not exercise that task, or only under restrictions, may. Section 62 (2) shall apply accordingly. (3) (omitted) (4) (omitted) Unofficial table of contents

§ 64 Ermighty Doctors

(1) The competent authority empowers physicians to carry out the occupational health care in accordance with § § 60, 61 and 63. Authorisation may be granted only to a doctor who has the necessary expertise in radiation protection for persons who have been exposed to occupational health care. (2) The doctor referred to in the first sentence of paragraph 1 shall have the task of: to carry out initial investigations, re-assessments or examinations and special occupational health care in accordance with § 63, as well as to propose measures to be taken in the event of increased exposure to radiation for prevention of damage to health and they are required to defend them. Persons employed in workplaces where the lens of the eye is particularly burdened shall be examined to see whether a cataract has formed. (3) The doctor referred to in the first sentence of paragraph 1 shall be obliged to apply for any occupational exposure to radiation. The person who is subject to occupational health care must carry out a health file in accordance with the sentence 2. This health file has provided information on the working conditions, the results of the occupational health provision in accordance with § 60 (1) or (2), the medical certificate according to § 61 (1) sentence 3, the results of the special occupational health care after § 63 (2) and measures pursuant to § 60 (3) or § 62 (1) sentence 2 or opinion pursuant to § 62 (2) sentence 1 as well as the body dose received by the performance of duties as a person exposed to radiation. The health file shall be kept for such a long period of time until the person has the 75. At least 30 years after the termination of the performance of duties as a person exposed to the profession. It shall be destroyed not later than 100 years after the birth of the person being monitored. (4) The doctor referred to in the first sentence of paragraph 1 shall be obliged to submit the health records to the competent authority of a body designated by the competent authority for inspection and at the end of the authorization. (5) The doctor referred to in the first sentence of paragraph 1 shall provide the person under examination with an insight into their health records at the request of the person under consideration.

Section 8
Other requirements

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Section 65 Storage and safety of radioactive substances

(1) Radioactive substances whose activity exceeds the free limits of Annex III, Table 1, columns 2 and 3, are:

1.: as long as they are not processed, processed or otherwise used, to be stored in sheltered rooms or protective containers; and
2.: against the removal of goods and the access by unauthorised persons.

(2) Nuclear fuels must be stored in such a way that no critical condition can arise during storage. (3) Radioactive substances subject to security measures under international obligations shall be stored in such a way as to ensure that they are carried out in such a way that: the security measures are not affected. Unofficial table of contents

§ 66 Maintenance, inspection and leak testing

1. The competent authority shall designate experts for the tasks referred to in the first sentence of paragraph 2, the tasks referred to in paragraph 4 and the tasks referred to in paragraph 5. The competent authority may require an expert in accordance with the first sentence with regard to his or her training, professional experience, suitability, instruction in subject-matter understanding, its scope of test activity and its other requirements and, in particular, its metrological equipment, as well as its reliability and impartiality. (2) Plants for the production of ionizing radiation and irradiation equipment, as well as equipment for gamma radiography, are annually to wait at least once, and between the waiting times in accordance with paragraph 1, to verify the safety, security and radiation protection of certain experts. Sentence 1 shall not apply to the installations referred to in Article 12 (1) and (12a). (3) The competent authority may

1.: Irradiation devices used in the exercise of the medicine or dentistry in humans and their activity 10 ¹⁴Do not exceed Becquerel,
2.: Irradiation devices used for blood or product irradiation and their activity 10 ¹⁴Do not exceed Becquerel, and
3.: Devices for Gammaradiography

the time limit for the review referred to in the first sentence of paragraph 2 to be extended to three years. (4) The competent authority may determine that the integrity and tightness of the enclosure in the case of enclosed radioactive substances, the activity of which shall be subject to the free limits of the Annex III, Table 1, column 2, shall be examined in a suitable manner and the test shall be repeated at certain intervals. In the case of highly radioactive sources, the test shall be carried out at least once a year, provided that the competent authority does not determine another period. It may stipulate that the examination shall be carried out by an expert appointed in accordance with paragraph 1. Sentences 1 and 2 shall not apply to enclosed radioactive substances which have been delivered as radioactive waste. (5) If the enveloping of enclosed radioactive substances or the device into which they are inserted is mechanically damaged, or corroded, prior to re-use, it shall be necessary to ensure that the enveloping of the radioactive substance enclosed is tested for leaktightness by an expert designated in accordance with paragraph 1. (6) The test findings referred to in paragraph 2 shall be the competent authority. The test findings referred to in paragraph 4 or 5 shall be submitted to the competent authority upon request. Any identified leaks and deficiencies in the integrity shall be notified without delay to the competent authority. Unofficial table of contents

§ 67 Radiation measuring instruments

(1) Measuring instruments for photon radiation of the type referred to in Article 1 (1) (13) of the measuring and calibration regulation must comply with the measurement and calibration law if they are used for subsequent purposes:

1.

for the physical radiation protection control by means of measurement

a): the personal dose in accordance with the first sentence of Article 41 (1), the first sentence of paragraph 3 or the first sentence of paragraph 5, or
b): the local dose or the local dose rate in accordance with section 41 (1), second sentence, point 1, or

2.

for measurements on the delimitation of radiation protection areas or for the determination of residence times of persons in radiation protection areas.

For the measurement of the dose, the local dose, the local dose rate, the surface contamination, the activity of air and water, and in the case of a free measurement in accordance with § 29 (3), are due to the provisions of this Regulation, unless, in accordance with the first sentence, Number 1 measuring instruments according to the measuring and calibration law are required to use other suitable radiation measuring instruments. It is necessary to ensure that the radiation measuring instruments are in accordance with the rates 1 and 2

1.: comply with the requirements of the measurement;
2.: are available in sufficient numbers, and
3.: are regularly checked for their functionality and are maintained.

(2) The date and the result of the function test and maintenance referred to in the third sentence of paragraph 1, point 3 shall be recorded. The records shall be kept for ten years from the date of the function test or maintenance and shall be submitted, at the request of the competent authority, or deposited at a position to be determined by the competent authority. (3) Radiation measuring instruments for this purpose. to be continuously measured in order to warn of hazards to humans and the environment in the event of an accident or incident must be such that their failure is indicated by a clearly perceptible signal, unless two or more measuring devices which are independent of each other serve the same measurement purpose. (4) The display of the Devices for monitoring the local dose or local dose performance in restricted areas must also be perceptible outside these areas. Unofficial table of contents

Section 68 Labelling obligation

(1) With a radiation sign in accordance with Annex IX in sufficient numbers, it shall be clearly visible and permanently marked:

1.: Rooms, appliances, devices, protective containers, storage containers and envelopes for radioactive substances, with which only on the basis of an authorisation pursuant to § § 6, 7 or 9 of the Atomic Energy Act or the planning of the plan according to § 9b of the Atomic Energy Act or may be dealt with in accordance with Article 7 (1) of this Regulation;
2.: Installations for the production of ionizing radiation,
3.: control areas and restricted areas,
4.: areas in which the contamination exceeds the values referred to in Article 44 (2);
5.: Type-approved devices according to § 25 (1).

The marking must contain the words "CAUTION-RADIATION", "RADIOACTIVE", "NUCLEAR FUEL" or "CONTAMINATION", to the extent that this is possible according to the size and nature of the object to be marked. (1a) In addition to the marking according to Paragraph 1, first sentence,

1.: high-level radioactive sources in the manufacture, where technically possible, and
2.: their protective containers or storage containers

visibly and permanently with an unmistakable identification number. Where the additional identification of the source of radiation in accordance with the first sentence of 1 (1) is not possible, or if reusable protective containers or storage containers are used, they shall, in addition to the marking referred to in the first sentence of paragraph 1, be used in addition to the (1b) The identification numbers referred to in paragraph 1a shall be communicated to the Federal Office for Radiation Protection within a period of one month. (2) Paragraph 1 shall not apply to containers or equipment which are within a Control area in separate areas is used as long as the of this use is present in the separate area, or such areas are secured against unintended access. The first sentence shall not apply to containers or equipment containing highly radioactive sources of radiation. (3) Safety containers and storage containers which are labelled in accordance with paragraph 1 may only be used for the storage of radioactive substances. (4) The markings referred to in paragraph 1 shall be removed after a release pursuant to § 29 or after a removal from radiation protection areas in accordance with § 44 (3). (5) All reservoirs, the radioactive substances in the open form of more than the 10 (high) 4 times the values of Appendix III, Table 1, column 2, must be marked in such a way that: that the following details can be determined:

1.: radionuclide,
2.: chemical compound,
3.: Day of bottling,
4.: Activity on the day of bottling or on a reference date which is particularly relevant to the day of bottling and
5.: Radiation protection officer at the time of bottling.

Identification numbers, signs and other abbreviations may only be used if they are generally known or can be easily removed from the accounts in accordance with § 70 (1) sentence 1 no. 2. The first and second sentences shall also apply to devices containing radioactive substances in an enclosed or adherent open form of more than 10 (high) 5 times the values of Annex III, Table 1, column 2. where other radioactive substances are inserted in accordance with Article 2 (1) of the Atomic Energy Act, the labelling referred to in paragraph 1 (5) shall be labelled in such a way as to indicate that the radionuclides contained therein and their activity at the time of manufacture are apparent, as far as this is possible according to the size and nature of the device. Unofficial table of contents

Section 69 release of radioactive substances

(1) Substances that may be dealt with only on the basis of an authorization pursuant to § § 6, 7 or 9 of the Atomic Energy Act or pursuant to Section 7 (1) or § 11 (2) of this Regulation may only be handed over to persons who are subject to the provisions of the Atomic Energy Act. (2) Any person who makes use of enclosed radioactive substances for further use shall certify to the acquirer that the wrapping is leak-proof and free of contamination. The certificate must include the body responsible for the examination and the date, type and outcome of the examination. Sentence 1 shall not apply if the radioactive substance to be dispensed is not to be used further as a radioactive substance enclosed. High-level radioactive sources may only be emitted if they are accompanied by a documentation of the manufacturer which:

1.

the identification number,

2.

information on the nature and activity of the radiation source; and

3.

Photographs or technical drawings

a): the type of radiation source,
b): of a typical protective container or storage container, and
c): of a typical transport container

(3) Without prejudice to § 75, anyone who makes radioactive substances for transport or further transport on public or public transport routes shall ensure that they are transported by persons who are subject to the provisions of Section 4 of the Nuclear law or pursuant to § 16 or § 17 of this Regulation are entitled to carry the substances. Any person who supplies the substances for transport shall also have to ensure that they are packaged at the time of handover, in accordance with the legislation applicable to the type of transport in question. In the absence of such legislation, the substances shall be packaged in accordance with the requirements of the scientific and technical standards for the intended type of transport. For the purpose of further transport, the substances may only be delivered if the packaging is intact. (4) Anyone who carries radioactive substances shall ensure that these substances are only available to the consignee or to a person entitled to receive such substances. will be passed. Until the handover, he has to provide the necessary protection against the removal of goods, disturbance measures or other effects of third parties. (5) High-level radioactive sources which are no longer to be dealt with or which are to be dealt with are, according to the invention, in accordance with the invention. To put an end to the use of the manufacturer, the supplier or any other marketing authorisation holder, or to deliver it as a radioactive waste, or to temporarily store it. Unofficial table of contents

§ 69a withdrawal of highly radioactive radiation sources

Anyone who has produced highly radioactive sources of radiation or who has spent time in accordance with § 3 (2) No 36 has to withdraw it or to ensure that it can be withdrawn by third parties. Unofficial table of contents

Section 70 Accounting and communication

(1) Anyone who deals with radioactive substances has

1.: inform the competent authority of the production, production, acquisition, supply and other fate of radioactive substances within one month, indicating the type and activity of the radioactive substances,
2.: the collection, production, acquisition, supply and other remaining of radioactive substances, with the indication of the type and activity of the book, and
3.: to communicate to the competent authority the stock of radioactive substances with half-life of more than 100 days at the end of each calendar year within one month.

Sentence 1 shall not apply to activities which do not require authorisation pursuant to Section 8 (1). In addition to the data provided for in the first sentence, the Federal Office for Radiation Protection in Safe Electronic Form of the Federal Office for Radiological Radiation Protection (Bundesamt für Strahlenschutz)

1.: with the fully completed standard collection sheet referred to in Appendix XV, purchase and supply and any changes to the information covered by this Annex without delay and
2.: The date of the examination in accordance with section 66 (4) sentence 2 within a period of one month with an updated standard collection sheet according to Appendix XV under the number 6 there

. The competent authority shall be informed without delay of the communication pursuant to sentence 3. (2) The mass of substances for which an effective determination has been made in accordance with § 29 (3) sentence 1 shall be provided, indicating the type of release in question pursuant to Article 29 (2). (3) on the substances for which an effective determination has been made pursuant to Article 29 (3) sentence 1, and in the case of the second sentence of Article 29 (2), second sentence, of the competent authority. is to keep a book. It shall specify the provisions adopted in accordance with Annexes III and IV, in particular the specific activity, the mass, the radionuclides, the free-measurement procedure, the mean mass, the averaging area and the date of determination. (4) The notification referred to in the first sentence of the first sentence of paragraph 1 on the acquisition of enclosed radioactive substances shall be accompanied by the certificate provided for in Article 69 (2). (5) The competent authority may, in individual cases, be subject to the obligation to carry out the accounting and notification in whole or in part , if this does not pose a threat to man and the environment and (5a) The competent authority shall, within a period of one month, examine the data submitted in accordance with the third sentence of paragraph 1 for the completeness and consistency of the information provided for in paragraph 1, sentence 3 or paragraph 2 or paragraph 3. The documents referred to in the first sentence of the first sentence of paragraph 1 and the first sentence of paragraph 3 shall be 30 years from the date of the date of the declaration of approval pursuant to § 9 of the Atomic Energy Act or § 7 of this Regulation. Production, production, acquisition, supply, other whereabout or determination and, at the request of the competent authority, to deposit it with the competent authority. In the event of termination of the activity before the expiry of the retention period referred to in the first sentence, the documents shall be handed over immediately to a body designated by the competent authority. Unofficial table of contents

Section 70a Register of highly radioactive sources of radiation

(1) The data according to § 12d (2) of the Atomic Energy Act shall be reported to the register by means of the standard version of Annex XV in a secure electronic form. (2) The Federal Office of Economics shall forward to the Register pursuant to § 12d of the Atomic Energy Act and export control immediately the information on the licences issued pursuant to § 3 (1) of the Atomic Energy Act or the first sentence of Article 19 (1) of this Regulation for the transboundary movement of a highly radioactive source of radiation from a State which does not Member State of the European Communities shall be included in the scope of the Radiation protection regulation, in particular the information given in points 1, 2, 5 and 7 of the standard specification sheet of Appendix XV. According to Section 12d of the Atomic Energy Act, the data shall be entered in accordance with

1.: § 70 (1) sentence 3 or § 71 (1) sentence 2 and 5 by the radiation protection officer or the radiation protection officer; and
2.: the information provided pursuant to § 71 (1) sentence 4 and (2) sentence 3 by the competent authority

is transmitted. The competent authority shall be immediately informed of the notification referred to in the first sentence. The Federal Office for Radiation Protection (Bundesamt für Strahlenschutz) shall inform the Federal Office for Radiation Protection at the request of the radiation protection officer or of the radiation protection officer on highly radioactive sources of radiation. Persons responsible for radiation protection in accordance with the second sentence of paragraph 2, no. 1, on the data relating to them. (4) The Federal Office for Radiation Protection shall collect the transmitted data in the register. The Federal Office for Radiation Protection shall immediately inform

1.: the Federal Ministry for Nuclear Safety and Radiation Protection and the Federal Criminal Police Office on the receipt of a communication on the discovery, loss or theft of a highly radioactive radiation source,
2.: the competent authority, if data are not complete or a highly radioactive source of radiation has been found.

(5) The Federal Office for Radiation Protection shall determine the data format and the method of transmission. Unofficial table of contents

Section 71 Abhanding, finding, obtaining of actual violence

(1) The previous holder of the actual violence on radioactive substances whose activity exceeds the free limits of Annex III, Table 1, columns 2 and 3, shall be subject to the nuclear regulatory authority or to the public safety or security authority; or The competent authority shall immediately inform the competent authority of the removal of such substances. In addition to the communication referred to in the first sentence, the disposal of a highly radioactive source of radiation shall be immediately sent to the Register of highly radioactive sources of radiation at the Federal Office for Radiation Protection in electronic form, with the standard Annex XV to point 10. The competent authority shall be immediately informed of the communication referred to in the second sentence. The second sentence shall also apply to the retrieval of a highly radioactive radiation source. The holder of a licence pursuant to § § 6, 7 or § 9 of the Atomic Energy Act, a planning decision pursuant to § 9b of the Atomic Energy Act or a permit pursuant to § 7 or § 11 (2) of this Regulation shall also have the agreement beyond the first sentence. Radioactive substances which are covered by the permit or which are dealt with under a permit to communicate to the authorities referred to in the first sentence if the activity of the substances which have been removed is the values of the Annex III table 1 column 2 and 5. The authorities referred to in the first sentence shall, in each case, inform each other immediately of the communication they receive. (2)

1.: radioactive substances, or
2.: without its will, the actual violence of radioactive substances, or
3.: has achieved actual violence over radioactive substances without knowing that these substances are radioactive,

shall immediately inform the nuclear regulatory authority or the competent authority of public security or order as soon as it becomes aware of the radioactivity of these substances. Sentence 1 shall not apply if the activity of the radioactive substances does not exceed the values of Annex III, Table 1, column 2 or 3. The competent authority shall communicate the discovery of a highly radioactive source of radiation, with reference to point 10 of the standard summary sheet of Annex XV, to the Register of highly radioactive sources of radiation at the Federal Office for Radiation Protection in Electronic Form without delay, at the latest on the second working day following the date of knowledge. The authorities referred to in the first sentence shall, in each case, immediately inform each other of the communication received by them. (3) Paragraph 2 shall also apply to the person who, as the owner of a water supply system or a waste water system, has the actual Water, which contains radioactive substances, when the concentration of radioactive substances in the cubic metre of water is

1.: Water supply systems three times or more
2.: Waste water systems 60 times

(4) An authorization pursuant to § § 4, 6 or 9 of the Atomic Energy Act or in accordance with § 7 (1) or § 16 (1) of this Regulation does not require any person who, in the cases referred to in paragraph 2 or 3, is not required to communicate without delay. the radioactive substances are stored or transported to the decision of the competent authority or on the basis of the decision of the competent authority or, for compelling reasons, for the protection of life and health.

Section 9
Radioactive waste

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Section 72 Planning for seizage and fate of radioactive waste

Anyone planning or carrying out an activity pursuant to Article 2 (1) (1) (a), (c) or (d) shall have

1.

to estimate the expected annual seizage of radioactive waste for the duration of the operating period and to communicate to the Authority, indicating the planned fate of the radioactive waste, and

2.

To demonstrate the fate of radioactive waste and to

a): to estimate the expected seizage of radioactive waste for the next year for the first time from the start of operation, then from the date of the closing date, and to provide information on the whereabout and
b): indicate the seizure of radioactive waste since the last cut-off date and the stock on the date of the cut-off date.

The information referred to in the first sentence of paragraph 2 shall be updated on the date of 31 December and shall be submitted to the competent authority by the following 31 March. They shall be continued without delay and shall be submitted to the competent authority if there are substantial changes. The rates 1 to 3 shall not apply to irradiated fuel elements and to radioactive waste to be delivered to land register offices in accordance with section 76 (4), insofar as they are untreated. By way of derogation from the fourth sentence, the rates 1 to 3 shall apply mutagenically to those who take over radioactive waste within the meaning of the fourth sentence of the waste caused by the waste and which, as a result, shall be subject to the obligation to deliver it. Unofficial table of contents

Section 73 Collection

(1) Anyone exercising an activity in accordance with Article 2 (1) (1) (a), (c) or (d) shall record the radioactive waste in accordance with Annex X, Part A and B, and update the collection in the event of alterations. If, in the event of changes to the information collected, a person other than the one who has pledged the waste in accordance with Article 9a (1) of the Atomic Energy Act, the owner has to record those changes in accordance with Annex X, Part A and B, and the data collected shall be subject to the information collected by the waste management (2) The information collected shall be recorded in an electronic accounting system to be established by the electronic accounting system provided for in Article 9a (1) of the Atomic Energy Act in such a way as to ensure that the information collected is available on request from the competent authority. may be made available immediately. The accounting system shall be subject to the agreement of the competent authority. (3) The information in the accounting system referred to in paragraph 2 shall be updated and, after the relevant radioactive waste has been delivered to the Landessammelstelle or to an installation of the To keep the federal government ready for the disposal of radioactive waste for at least one year. (4) § 72 sentences 4 and 5 shall apply accordingly. Unofficial table of contents

Section 74 Treatment and packaging

(1) The competent authority or body designated by it may order the type of treatment and packaging of radioactive waste prior to its delivery and may require proof of compliance with this order. The competent authority in accordance with the Atomic Energy Act for the freezing and disposal of radioactive waste shall lay down all the safety requirements for the disposal of waste intended for disposal as well as the requirements for the treatment of the waste (2) In the treatment and packaging of radioactive waste for the production of end-storage waste products, procedures are , the application of which the Federal Office for Radiation Protection agrees . If the radioactive waste delivered to Landessammelstellen (Landessammelstellen) has been treated and packaged in accordance with the second sentence of paragraph 1, the Federal Government shall bear the costs arising from a subsequent amendment of the requirements and requirements. (3) Waste containers or other units shall be marked with a marking in accordance with Annex X, Part B. § 72 sentence 4 and 5 shall apply mutagens. (4) Requirements on the basis of the Dangerous Goods Transport Act shall remain unaffected. Unofficial table of contents

Section 75 duties on the release of radioactive waste

(1) Anyone who makes radioactive waste must have previously received a written declaration from the recipient of the readiness to accept the waste. He has to give the recipient the information in accordance with Section 73 (1). (2) He/she shall inform the competent authority of radioactive waste for at least five working days prior to the commencement of the transport. The information provided for in Annex X, Part C, shall be included in the communication. A copy of the communication shall be sent to the recipient at the same time. If the date of carriage is not binding in the notification, it shall be reported at least two working days before the commencement of the transport operation in accordance with the first and second sentences. The first and second sentences shall also apply to the consignee if the competent authority of the consignee is not the same as the competent authority of the issuing authority. (3) The addressee has the following:

1.: to examine without delay the imprint of the notification referred to in paragraph 2 of Annex X, part C, to inconsistencies between the particulars and the goods transported, and to communicate inconsistencies to the competent authority of the competent authority,
2.: inform the transferor immediately in writing of the adoption of the radioactive waste; and
3.: the information referred to in § 75 (1) shall be included in its accounting system.

(4) Communications pursuant to paragraph 2 shall not be required in the case of a shipment pursuant to Article 5 (2) of the Nuclear Waste Shipments Regulation. (5) § 72 sentence 4 and 5 shall apply accordingly. Unofficial table of contents

Section 76 Delivery

(1) Radioactive waste shall be delivered to a federal government facility for the purpose of ensuring and for the disposal of radioactive waste when it is

1.: in the case of the state preservation of nuclear fuel in accordance with § 5 of the Atomic Energy Act,
2.: in the case of storage pursuant to § 6 of the Atomic Energy Act,
3.: in the installations in need of approval pursuant to § 7 of the Atomic Energy Act, or
4.: in the case of activities under Section 9 of the Atomic Energy Act
5.: in the case of activities which are not subject to § 9 of the Atomic Energy Act only on the basis of Section 2 (3) of the Atomic Energy Act,

(2) Paragraph 1 shall also apply to radioactive waste arising from the handling of Article 7 (1) if the waste is in connection with one of the activities referred to in paragraph 1 or if, pursuant to Section 7 (2), a nuclear waste has been granted pursuant to the Atomic Energy Act. (3) Other radioactive waste may only be delivered to the Federal Government for the purpose of ensuring and for the disposal of radioactive waste when the competent authority responsible for the waste producer is responsible for the disposal of radioactive waste. State authority has allowed this. In the case of authorisation, the obligation to supply the waste shall not be required in accordance with paragraph 4. (4) Radioactive waste shall be delivered to a Landessammelstelle, if it is not

1.: from a handling pursuant to section 7 (1) or
2.: from an approved operation of installations for the production of ionizing radiation

, unless such waste is to be supplied, in accordance with paragraph 1, point 5, to an installation of the Federal Government for the purpose of ensuring and disposal of radioactive waste. (5) The radioactive waste referred to in paragraphs 1 and 2 may be sent to a land-collection office shall be delivered only if the competent State authority responsible for the waste producer has allowed it. In the case of approval, the obligation to deliver the radioactive waste in accordance with paragraph 1 or 2 shall not be required. (6) The land register office shall, in principle, carry out the radioactive waste which it has temporarily stored on an installation of the federal government for the purpose of ensuring and disposal of radioactive waste. wastes. Unofficial table of contents

Section 77 Exceptions to the obligation to deliver

The obligation to deliver in accordance with § 76 does not refer to radioactive waste, insofar as its other disposal or disposal in individual cases or for individual waste types in agreement with the competent authority for the recipient of the radioactive waste. Authority has been ordered or approved. It shall rest as long as a request for release pursuant to section 29 has not yet been decided or any other intermediate storage of the radioactive waste is arranged or approved. Unofficial table of contents

Section 78 interim storage

The radioactive waste to be delivered in accordance with section 76 (1) or (2) shall be intermediately stored by the supplier until the Federal Government has been put into service for the purpose of ensuring and for the disposal of radioactive waste; the intermediate storage facilities shall be in the form of interim storage facilities. radioactive waste will be obtained from its operators after these plants have been put into service. The interim storage can also be carried out jointly by a number of suppliers or by third parties. Unofficial table of contents

Section 79 Prohibition of rebates

No one shall be entitled to withdraw from the obligations of § § 72 to 78 by the fact that he/she is subject to radioactive waste from activities in need of approval pursuant to § 2 (1) No. 1 without authorisation under the regulation of § 8 (1) by dilution or It is possible to eliminate, eliminate, eliminate or eliminate the elimination of free-limits. Section 29 (2) sentence 4 shall remain unaffected.

Chapter 4
Special requirements for the medical use of radioactive substances and ionizing radiation

Section 1
Medicine and Dentistry

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Section 80 Justifying indication

(1) Radioactive substances or ionizing radiation shall only be used in the exercise of a medicine or dentistry only if a person has provided the justifiable indication for this purpose in accordance with § 82 (1) (1). The justifiable indication requires the determination that the health benefits of an application in humans are greater than the radiation risk. Other methods with comparable health benefits, which are not associated with any or less exposure to radiation, must be taken into account in the weighing process. A justifiable indication according to the first sentence shall also be made if there is a requirement of a referring doctor. § 23 shall remain unaffected. (2) The physician who has the right indication shall have prior to use, if necessary in collaboration with a referring physician, to use the available information on previous medical findings, in order to avoid any unnecessary exposure to radiation. Patients are to be asked about prior medical applications of radioactive substances or ionizing radiation, which are important for the intended use. (3) Prior to the use of radioactive substances or ionizing radiation, the If necessary, in collaboration with a referring physician, consult women who are incapable of being pregnant, whether or not they may be pregnant or whether they are breast-feeding. In the case of pregnancy or pregnancy which is not to be completed, the urgency of the application shall be examined in particular. In the case of open radioactive substances, the second sentence shall be applicable to breast-feeding women. Unofficial table of contents

§ 81 Restriction of radiation exposure

(1) The exposure to radiation caused by medical examinations shall be limited to the extent to which this is compatible with the requirements of medical science. Whereas, in the case of women, despite existing or non-exclusive pregnancy, the use of radioactive substances or ionising radiation is required, all possibilities for reducing the exposure of the pregnant woman to radiation, and in particular the unborn child. In the case of open radioactive substances, the second sentence applies to women who are breastfeeding. (2) In the study of humans, diagnostic reference values should be used. An overshoot of the diagnostic reference values shall be justified in writing. The Federal Office for Radiation Protection shall establish and publish the diagnostic reference values. (3) Prior to the use of radioactive substances or ionizing radiation for treatment in humans, a doctor has to be responsible for the treatment of radioactive substances or ionizing radiation in accordance with § 82 (1) (1) and (1). Medical physics experts will be able to provide a written examination of a patient-related irradiation plan. The dose in the target volume shall be determined individually for each person to be treated in accordance with the requirements of medical science; the dose outside the target volume shall be kept as low as this taking into account the requirements of the medical science. (4) The rules on dose limits and on physical radiation protection control in accordance with § § 40 to 44 do not apply to persons to whom radioactive substances are used in the exercise of medicine or dentistry or dentistry. ionizing radiation. (5) Helping people are about the possible dangers of the exposure to radiation prior to entering the control area. Measures must be taken to limit their exposure to radiation. Paragraph 4, section 40 (1), first sentence, and § 42 (1) sentence 1 shall apply to persons helping to help. (6) appropriate written instructions must be given to the patient or to the assisting person after the examination or treatment with radioactive substances, how the exposure to radiation or contamination of the relatives, third parties and the environment can be kept as low as possible or avoided, insofar as this is necessary for reasons of radiation protection. Sentence 1 shall not apply if such exposure to radiation or contamination can be ruled out or the patient continues to be treated in a stationary manner. (7) It is necessary to ensure that radioactive substances are used exclusively for the use of radioactive substances or substances. Ionizing radiation in humans, certain installations for the production of ionizing radiation, irradiation devices or other equipment or equipment are available only to the extent to which they are intended for the proper conduct of medical Applications are required. Unofficial table of contents

Section 82 Application of radioactive substances or ionizing radiation in humans

(1) In the field of medicine or dentistry, radioactive substances or ionizing radiation may only be used by humans.

1.: persons who are approved as doctors or dentists, or who are allowed to exercise the medical profession and who have the necessary expertise in radiation protection,
2.: Persons who are approved as doctors or dentists, or who are authorised to exercise the medical or dental profession and who do not have the necessary expertise in radiation protection, if they are working on their specific field of work on the in the case of radioactive substances and the application of ionizing radiation, have the necessary knowledge of radiation protection and are under the permanent supervision and responsibility of one of the persons referred to in paragraph 1.

(2) In addition to the persons referred to in paragraph 1, technical assistance for the use of radioactive substances or ionising radiation in the field of medicine or dentistry shall not be required.

1.: Persons with a licence pursuant to Section 1 (1) (2) of the MTA Act of 2 August 1993 (BGBl. 1402), as last amended by Article 23 of the Law of 2 December 2007 (BGBl). 2686) has been amended,
2.: Persons with a state-regulated, state-approved or state-supervised successfully completed training if the technical assistance was the subject of their training and examination and they have the required technical expertise in the to have radiation protection,
3.: Persons who are in a vocational training providing the necessary conditions for technical participation, if they carry out work under the permanent supervision and responsibility of a person referred to in paragraph 1 (1), who shall be responsible for the work of the the framework of their training, and have the necessary knowledge of radiation protection,
4.: persons who have successfully completed other medical training, if they are under the permanent supervision and responsibility of a person referred to in paragraph 1 (1) and possess the necessary knowledge of radiation protection,
5.: medical physic experts, if they are acting under the permanent supervision and responsibility of a person referred to in paragraph 1 (1);

(3) Written work instructions are to be drawn up for examinations and treatments which are often carried out. They shall be kept ready for inspection by the persons involved in these investigations and treatment and shall be sent to the competent authority at the request of the competent authority. (4) For treatment with radioactive substances or ionizing agents. Radiation is a medical physics expert to be added to close cooperation. In the case of nuclear medical examinations or in the case of standard treatments with radioactive substances, a medical physics expert, in particular for the optimization and quality assurance in the use of radioactive substances, must be available. Unofficial table of contents

§ 83 Quality Assurance in Medical Radiation Application

(1) In order to ensure quality assurance of medical radiation, the competent authority shall designate medical authorities. The licence holders according to § § 7 and 11 for the applications of radioactive substances or ionizing radiation are subject to the tests to be carried out by the medical authorities for the quality assurance of medical radiation applications. The competent authority shall determine the manner in which the medical authorities carry out the tests to ensure that the requirements of the medicinal product for the use of radioactive substances or ionising radiation in humans are met by the medical authorities. Science and the methods used and equipment used for the production of ionizing radiation, irradiation devices, other equipment or equipment, which are necessary in accordance with the state of the art of science and technology comply with quality standards in order to reduce the exposure to radiation as low as possible. The medical authorities shall have the competent authority

a): the results of the tests referred to in the third sentence,
b): the persistent, unjustified exceedings of the diagnostic reference values to be used in the investigation pursuant to section 81 (2) sentence 1 and
c): Failure to comply with the optimisation proposals referred to in paragraph 2

. The medical authority may pass on the results of the tests provided for in the third sentence, except for the personal data of the persons studied or treated, to the body responsible for the quality inspection after the ninth section of the fourth (2) within the limits of its powers under paragraph 1, the medical body shall have the task of providing radiation protection responsible for the optimisation of medical radiation applications. to propose and verify whether and how far the proposals will be implemented. (3) The medical centre is subject to medical confidentiality with regard to patient-related data. (4) The activity in need of approval pursuant to § 7 (1) in conjunction with § 9 (1) and (3) or § 11 (2) in conjunction with Section 14 (1) and (2) shall apply to: a medical body designated by the competent authority. A copy of the application shall be sent to the competent authority. The medical body shall, on request, submit the documents necessary for the performance of its tasks referred to in paragraphs 1 and 2, in particular information on the activity and dose administered, the installations for the production of ionizing products. Radiation, irradiation equipment or any other equipment or equipment used and information on the application of § 80. The medical authority must, on request, submit the written justification for exceeding the diagnostic reference values in accordance with § 81 (2) sentence 2. (5) In the case of installations for the production of ionizing radiation, irradiation devices and other Equipment, including devices for diagnostic purposes, used in the use of radioactive substances or ionizing radiation for the purpose of investigating or treating humans, shall be ensured prior to putting into service that the devices for the use of radioactive substances or ionizing radiation are used for the purposes of: Application of the required quality is achieved. For this purpose, the operator shall ensure that the manufacturers or suppliers of the individual components carry out an acceptance test, which shall be determined. Installations for the production of ionizing radiation for the treatment of human beings shall be subject to an examination by the operator in addition to the acceptance tests as set out in the second sentence, which shall include all the systems involved for localisation, therapy planning and positioning . The acceptance test shall determine the reference values for the internal quality assurance referred to in paragraph 6. (6) The installations used in the use of radioactive substances or ionizing radiation for the examination or treatment of humans shall be determined. (7) The extent and timing of the tests referred to in paragraphs 5 and 6 shall be recorded. The records of the tests referred to in paragraph 5 shall be kept for the duration of the holding, but at least two years from the conclusion of the next complete acceptance test. The records of the tests referred to in paragraph 6 shall be kept for a period of ten years. The records referred to in sentences 2 and 3 shall be submitted to the competent authority upon request. Unofficial table of contents

Section 84 Radiation rooms

Installations for the production of ionizing radiation and irradiation devices whose activity exceeds 5 x 10 (high) 10 becquerels may only be operated in rooms enclosed on all sides (irradiation rooms) in the exercise of medicine or dentistry. . These must be dimensioned in such a way that the necessary orientations can be carried out without hindrants. The operating devices, which release the radiation, must be located in a secondary space outside the control area. In the irradiation space, there must be at least one emergency switch with which the system is switched off, the beam head of the irradiation device can be closed or the radioactive substance can be moved into the shielding. There must be a suitable equipment for monitoring the patient in the irradiation room. Unofficial table of contents

§ 85 Recording obligations

(1) It is necessary to ensure that records are made on the basis of the records 2 and 3 of the survey in accordance with § 80 (2) sentence 2 and subsection 3 sentence 1, the examination and the treatment of patients. The records must contain:

1.: the outcome of the survey,
2.: the date, the nature and purpose of the examination or treatment, the radioactive substances administered to the patient by type, chemical composition, form of administration, activity,
3.: information on the justifiable indication in accordance with § 80 (1) sentence 1,
4.: the justification in accordance with Article 81 (2), second sentence,
4a.: in the case of an examination, the findings collected,
5.: in addition, the body dose and the radiation plan in accordance with section 81 (3) sentence 1,
6.: in the case of treatment with irradiation devices or installations for the production of ionizing radiation, the irradiation protocol.

The records shall be secured against unauthorised access and unauthorised changes. Records made using data-processing equipment must be able to be made legible within the retention period referred to in paragraph 3. (2) The person being examined or treated is at their request. to issue a copy of the record referred to in the first sentence of paragraph 1. (3) The records of the investigation shall be kept for 10 years for the period of treatment for 30 years after the last examination or treatment. The competent authority may require that, in the event of a practical task or any other cessation of activity, the records must be deposited at a position designated by that authority, in which case the obligation to observe the medical confidentiality must be observed. (4) In the case of radioactive substances or ionizing radiation, the person who subsequently carries out such an examination or treatment shall, at his request, provide information on the records referred to in paragraph 1, and the documents relating to this shall be temporarily left to the documents relating to it. If the documents are kept by another person, the person has to leave the documents temporarily to the person entitled to the information. (5) The Federal Office for Radiation Protection regularly determines the medical radiation exposure of the population and (6) An up-to-date list of irradiation facilities, installations for the production of ionizing radiation or other equipment or equipment must be carried out. The inventory according to § 8 of the Regulation on the setting up, operation and application of medical devices can be used for this purpose. The inventory shall be submitted to the competent authority upon request. Unofficial table of contents

§ 86 Applications in the field of human beings outside of medicine or dentistry

§ § 80 to 85 apply accordingly for applications of radioactive substances or ionizing radiation in humans, which are provided for or approved by other legal regulations.

Section 2
Medical Research

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Section 87 Special protection and information obligations

(1) The use of radioactive substances or ionizing radiation in humans in medical research is only permitted with the personal consent of such radiation. The holder of the authorisation in accordance with § 23 shall obtain a written statement from the test person on the fact that the proband with

1.: the application of radioactive substances or ionizing radiation to his or her person, and
2.: the studies which are necessary before, during and after the application for control and maintenance of its health,

I agree. The declaration shall be effective only if the proband is capable of acting and capable of viewing the risk of the application of the radioactive substances or ionizing radiation and determining its will. This declaration and any consents in connection with the application may be revoked at any time by the test person. (2) The application shall also be admissible only if the proband has previously issued a further written declaration on the subject has made it possible to

1.: the communication of its participation in the research project; and
2.: the irrevocable communication to the competent authority of the exposure to radiation received by the application

(3) Before issuing the consent, the proband shall be responsible for the nature, significance, scope and risk of the use of the radioactive substances or ionizing substances by the doctor responsible for the research project or by the latter. Radiation and the possibility of revocation. The proband shall be asked whether radioactive substances or ionizing radiation have already been applied to him for the purpose of examination, treatment or outside of the medicine or dentistry. Records must be made about the investigation and the interview of the test person. (4) Before the start of the application of radioactive substances or ionizing radiation, the proband should be examined in a medical examination. The activity of the radioactive substances shall be determined prior to their application. The body dose should be monitored by appropriate procedures. The date of application, the results of the surveillance measures and the findings shall be recorded. (5) The declarations referred to in the second sentence of paragraph 1 and paragraph 2 and the records referred to in the third sentence of paragraph 3 and the fourth sentence of paragraph 4 shall be for 30 years after the date of application. to keep the levy or the date of application and, at the request of the competent authority, to submit it. § 85 (1) sentences 2 to 4, subsection 2, para. 3 sentence 2 and 4 (4) shall apply to the records. (6) The use of radioactive substances or ionizing radiation in medical research may only be used by one person in accordance with § 82 (7) § 81 (5) and (6) as well as § § 83, 84 and 85 (5) and (6) shall apply accordingly. Unofficial table of contents

Section 88 Application prohibitions and restrictions on the use of individual groups of persons

(1) Radioactive substances or ionising radiation in medical research should not be used in pregnant women. Radioactive substances must not be used in medical research on breast-feeding women. The use of radioactive substances or ionizing radiation in medical research may not be applied to persons who are held in a judicial or administrative order. (2) Healthy subjects are excluded from the use of the system. which have been used for research or treatment purposes over the past 10 years, when an effective dose of more than 10 is effective in medical research. Millisievert is to be expected. § 24 (3) remains unaffected. (3) The use of radioactive substances or ionizing radiation in healthy subjects, which is the 50. It is only permissible if this is justified by medical reasons and is particularly necessary in order to achieve the research objective. (4) The use of radioactive substances is radioactive and is restricted to the use of radioactive waste. Substances or ionizing radiation shall be permitted only if:

1.: the research objective cannot be achieved in a different way,
2.: the application is made to subjects where there is a disease or suspicion of disease in relation to the research project in need of approval, and the application is capable of detecting this disease, the life of the to save the person affected, to restore their health or to alleviate their suffering, and
3.: the legal representative or the supervisor has given his consent, after he has been informed of the nature, significance, scope and risks of the doctor conducting the research project. If the incapable or limited-acting proband is capable of viewing the nature, meaning and scope of the application and determining its will in this regard, his/her personal consent shall be required in addition.

Section 87 (1) to (3) shall apply mutas to the declarations provided for in the first sentence of sentence 1. Unofficial table of contents

Section 89 Co-participation and reporting obligations

(1) The competent supervisory authority and the approval authority shall be notified without delay:

1.: any exceeding of the dose limit values in accordance with Article 24 (3) and section 88 (2) sentence 1, specifying the circumstances and
2.: the completion of the use of radioactive substances or ionising radiation for the implementation of the research project.

(2) A final report shall be submitted to the competent supervisory authority and to the approval authority after the end of the application, from which the body dose determined in the individual case or the data relevant for the calculation of the body dose shall be produced. Unofficial table of contents

§ 90 Protection Order

If it is necessary to arrange for a proband to be damaged in health research due to exceeding the approved dose levels for the use of radioactive substances or ionising radiation, the competent authority shall: Authority to be examined by a doctor in accordance with § 64 (1) sentence 1. Unofficial table of contents

Section 91 Cover provision in the case of clinical trials

The provision for the fulfilment of statutory claims for damages is to be taken for a period of ten years after the end of the research project. The provisions of Section 24 (1) (10) of this Regulation shall not apply in so far as the requirements of the Nuclear Security Board regulation by means of the provision for the performance of statutory claims for damages in accordance with the relevant provisions of the relevant provisions of the Regulation Regulations of the Medicines Act or of the Medical Devices Act are the reason and the level of compliance are fulfilled. In the case of a permit pursuant to section 24 (2), no security cover is required, which goes beyond the provisions of the Proband Insurance pursuant to the Medicinal Products Act or the Medical Devices Act. Unofficial table of contents

Section 92 Ethics Committee

An Ethics Committee operating within the scope of this Regulation must be independent, interdisciplinary and registered with the competent federal authority. Its task is to provide oral advice to the proposed research project according to ethical and legal aspects, with at least five members, and to a written one within 60 days of the receipt of the required documents. To give an opinion, in particular whether the requested project has a compelling need within the meaning of Section 24 (1) (1). In the case of multicenter studies, the opinion of an Ethics Committee is sufficient. Registration shall only be made if, in a published procedure, the members, consisting of medical experts and non-medical members, have the necessary expertise, the procedure and the Address of the Ethics Committee. Any changes in the composition of the Commission, of the procedure or of the other provisions of the Rules of Procedure shall be notified without delay to the competent authority responsible for registration.

Chapter 5
Use of radioactive substances or ionizing radiation in veterinary medicine

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§ 92a Restriction of radiation exposure in the case of animal accompanying persons

Animal accompanying persons shall be informed of the possible dangers of exposure to radiation before entering the control area. Measures must be taken to limit their exposure to radiation. The regulations on dose limits and on the physical radiation protection control in accordance with § § 40 to 44, with the exception of § 40 (1) sentence 1 and § 42 (1) sentence 1, shall not apply to animal accompanying persons. Unofficial table of contents

§ 92b Authorised persons in the veterinary medicine

(1) Radioactive substances or ionizing radiation may only be used in veterinary medicinal products by

1.: persons who have the right to exercise the veterinary, medical or dental profession and who have the necessary expertise in radiation protection,
2.: Persons who are entitled to exercise the veterinary, medical or dental profession and who do not have the necessary expertise in radiation protection, if they are in their special field of work on the subject of the application have the necessary knowledge of radiation protection and are under the permanent supervision and responsibility of one of the persons referred to in paragraph 1.

(2) In addition to the persons referred to in paragraph 1, only the following persons may be technically involved in the use of radioactive substances or ionizing radiation in the veterinary medicinal product:

1.: Persons with a licence pursuant to Section 1 (1) (2) of the MTA Act of 2 August 1993 (BGBl. 1402), as last amended by Article 23 of the Law of 2 December 2007 (BGBl). 2686) has been amended,
2.: Persons with a state-regulated, state-approved or state-supervised successfully completed training if the technical assistance was the subject of their training and examination and they have the required technical expertise in the to have radiation protection,
3.: persons who have the necessary knowledge of radiation protection if they are under the permanent supervision and responsibility of a person referred to in paragraph 1 (1),
4.: Medical physic experts, if they are under constant supervision and responsibility of a person referred to in paragraph 1 (1).

(3) In the case of the use of radioactive substances or ionizing radiation on the animal, animal welfare regulations remain unaffected.

Part 3
Protection of humans and the environment from natural sources of radiation during work

Chapter 1
Basic duties

Unofficial table of contents

§ 93 Dose limitation

Those who exercise or exercise their own responsibility for the work of the type referred to in Chapter 2 or Chapter 4 shall ensure that the dose limits in Chapters 2 and 4 are not exceeded. Unofficial table of contents

§ 94 Dose reduction

Those who, under their own responsibility, plan, exercise or exercise the work of the species referred to in Chapters 2 to 4 shall take appropriate measures to minimise the exposure to radiation, taking into account all the circumstances of the individual case. ,

Chapter 2
Requirements for terrestrial radiation at workplaces

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§ 95 Naturally occurring radioactive substances in workplaces

(1) Anyone who carries out or is engaged in a work in his or her permanent establishment which is to be assigned to one of the fields of work listed in Annex XI shall have, on the basis of the membership of the field of work, part A or B of Annex XI within six months from the date of the commencement of the operation Work on a workplace assessment of radon-222 exposure, potential alpha-energy exposure, or body dose. The estimation shall be repeated immediately if the workplace is altered in such a way that a higher exposure to radiation may occur. The first sentence shall also apply to the person who, under his own responsibility, performs work under the first sentence of a sentence 1 or who, under his supervision, is able to carry out work under his supervision. In this case, the estimates provided for in the first sentence shall be made available to him for the workplace. (2) The competent authority referred to in paragraph 1 shall, within three months of the implementation of the assessment referred to in paragraph 1, have the right to make available to the competent authority. If the estimate referred to in paragraph 1 shows that the effective dose may exceed 6 millisievert in the calendar year, the indication referred to in the second sentence shall be refunded. The display must include the specific type of work, the field of work or fields of work concerned, the number of persons concerned, who can receive an effective dose of more than 6 millisievert in the calendar year, according to the The provisions of paragraph 10, first sentence, and the measures provided for in paragraph 94 shall be established. In the case of radon exposures, paragraph 13 shall be taken into account. (3) The third sentence of the third sentence of paragraph 1 shall ensure that he himself and the persons under his supervision in foreign establishments only carry out work in need of notifiable works if each of them has: Person holding a fully-managed radiation passport registered with the competent authority. (4) For persons performing display-related work, the limit value of the effective dose is 20 millisievert in the calendar year. The limit value of the organdosis amounts to 150 millisieverts for the eye lens, 500 millisievert for the skin, hands, forearms, feet and ankles. (5) The limit value for the sum of the effective doses determined in all calendar years professionally exposed persons is 400 millisievert. The competent authority may, in consultation with a doctor referred to in Article 64 (1) sentence 1, authorise a further occupational exposure if the latter is not more than 10 millisievert effective dose in the calendar year and the occupational exposure to radiation exposure is not more than 10 millisievert. Person agrees. Consent shall be given in writing. (6) If, in breach of paragraph 4, sentence 1 or 2, a limit value has been exceeded in the calendar year, further employment as a person exposed to radiation shall be permitted only if the exposures in the following four calendar years shall be limited, taking into account the exceeding of the limit value, in such a way that the sum of the doses does not exceed five times the relevant limit value. If the exceeding of a limit value is so high that in the case of the application of the first sentence the previous employment cannot continue, the authority may, in consultation with a doctor pursuant to section 64 (1) sentence 1, allow exceptions to the first sentence. (7) For persons below 18 years the limit of the effective dose is 6 millisievert in the calendar year. The limit value of the organdosis is 50 millisievert for the eye lens, for the skin, hands, forearms, feet and ankles 150 millisievert each in the calendar year. (8) For an unborn child, due to the employment of his mother of exposure to radiation, the limit value for the sum of the dose of external and internal radiation exposure from the date of notification of pregnancy to the end of the pregnancy is 1 millisievert. (9) As soon as a woman who has received a , the work according to Annex XI, Part B, which is subject to display, which has been provided for in paragraph 1 above, has informed that it is pregnant or breastfeeding, in order to ensure that an internal occupational exposure to radiation is excluded. (10) In the case of persons who are in need of a display, the person referred to in paragraph 1 shall have the right to work in accordance with paragraph 1 of this Article. Committed the Radon-222 exposure or potential alpha-energy exposure and body dose in a suitable manner by measuring the local dose, the local dose rate, the concentration of radioactive substances or gases in the air, the contamination of the Workplace, personal dose, body activity or activity of the To determine excretion in accordance with sentence 3. Radon-222 exposure and potential alpha-energy exposure can also be determined by direct measurement. The results of the investigation must be available no later than nine months after the radiation exposure of the person performing the task in need of display has been carried out. For the measurements, the competent authority may establish the measuring methods and measurement methods to be applied and determine measuring points for measurements. Section 41 (8) shall apply accordingly. The competent authority may set a replacement dose in the case of a subliminal or erroneous investigation. (11) The person who is required to carry out notifiable work in accordance with the provisions of paragraph 1 shall only allow employment or further employment to be carried out, if they have been examined by a doctor in accordance with § 64 (1) sentence 1 within the respective calendar year and have received a certificate issued by the doctor referred to in paragraph 1, after which the employment does not constitute a health certificate Take into account the concerns. The first sentence shall apply to persons who, on their own responsibility, carry out work on their own premises or in another establishment. Section 60 (3) and § § 61 and 62 shall apply accordingly. In accordance with § 64 (1) sentence 1, the documents requested in accordance with § 61 (1) sentence 1 are to be handed over immediately to the doctor. The doctor must immediately send the medical certificate to the competent authority to the competent authority in accordance with the first sentence of paragraph 1, the professionally exposed person and, where there are concern for health, the competent authority. (12) Paragraph 1, which results in an effective dose of less than 6 millisievert in the calendar year, may also be fulfilled by the obligation under section 94 to apply radiation protection measures on the basis of provisions of general employment protection. . The competent authority may require appropriate evidence. (13) For the conversion of radon 222 exposure into the effective dose, it can be assumed that a radon 222 exposure of 0.32 Megabecquerel per cubic metre of exposure to an hour of an hour of effective dose of 1 millisievert. In the event of significant deviations of the equilibrium factor between Radon-222 and its short-lived decay products from the underlying value of 0.4, the competent authority may set different conversion factors. For the conversion of the potential alpha-energy exposure to the effective dose, a potential alpha energy exposure of 0.71 millijoule per cubic meter of time corresponds to an effective dose of 1 millisievert per cubic meter. Unofficial table of contents

§ 96 Documentation and other protective measures

(1) If you exercise or exercise your own responsibility in accordance with § 95 (2), the results of the investigation pursuant to § 95 (10) sentence 1 or the replacement dose in accordance with § 95 (10) sentence 6 shall be recorded immediately. Radon 222 exposure and potential alpha-energy exposure are to be converted to a value of the effective dose in accordance with § 95 (13). (2) The person referred to in paragraph 1 shall be responsible for the exposure to alpha-energy.

1.

the records referred to in paragraph 1

a): keep up until the monitored person is 75 years old. is completed or would have been completed, but at least 30 years after the end of the respective employment,
b): at the latest 100 years after the birth of the person concerned,
c): to submit, at the request of the person being monitored or to the competent authority, or to deposit at a position to be determined by that authority,
d): in the event of a change in the employment relationship, to communicate to the new employer upon request if employment continues to be practised as an exposed person,

2.

exceeding the limit values of the body dose in accordance with § 95 (4) sentence 1 or 2, (5) sentence 1, (7) and (8) of the competent authority, stating the reasons for immediately informing the persons concerned and the body doses determined,

3.

to inform the person concerned of the body dose immediately in the case of point 2.

(3) The body dose referred to in paragraph 1 sentence 2 or determined in accordance with Article 95 (10) sentence 1 and the information referred to in Article 112 (1) (2) and (3) of the competent authority or of a body designated by it pursuant to paragraph 1 (1) (2) and (3) shall be the subject of the obligation to Transfer to the Radiation Protection Register within a period of one month after the recording. The Federal Office for Radiation Protection shall determine the format and the method of transmission. Information from the Radiation Protection Register shall be provided to the person referred to in paragraph 1 as far as it is necessary for the performance of his duties. Section 112 (4), first sentence, no. 1 and 3 and second sentence 2 shall apply. (4) In so far as the conditions of exposure so require, the competent authority shall take appropriate measures in accordance with § § 30, 34 to 39, 43 to 45, 47 (3) sentence in the case of display-requiring work. 1, § 48 (2), § 67 and § 68 (1), first sentence, no. 3 and 4. It may also arrange the manner in which the materials arising from the display in need of display are to be disposed of. (5) In other fields of work other than those mentioned in Annex XI, Part B, exposures to those of the items listed in Annex XI, Part B , the competent authority may, in the appropriate application of paragraphs 1 to 4 and of Article 95, take the necessary measures.

Chapter 3
Protection of the population with naturally occurring radioactive substances

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Section 97 Residues in need of supervision; inadmissible shipment

(1) Any person who, under his own responsibility, carries out or has carried out work in which the residues in need of surveillance are incurred, by their recovery or disposal for individuals of the population, the indicative value of the effective dose of 1 millisievert in the Measures to protect the population have to be taken in calendar year. The first sentence shall apply mutatically to those who have been subject to surveillance in need of surveillance, who have been recruit abroad and who have been brought to the country for recovery. (2) Residues in need of monitoring shall be in accordance with Annex XII, Part A, unless it is ensured that, in the course of their disposal or recovery, the surveillance limits laid down in Annex XII, Part B, and the disposal or recovery routes referred to therein are complied with. Residues obtained may not be mixed or diluted with other materials prior to the intended disposal or recovery in order to comply with the control limits of Annex XII, Part B. The competent authority may require that, for the residues referred to in Annex XII, Part A, compliance with the monitoring limits of Annex XII, Part B, shall be required. is demonstrated. It may lay down technical procedures, appropriate measurement methods and other requirements, in particular those for the determination of representative measurements of the specific activity. (4) The pledge referred to in paragraph 1 shall have residues in accordance with the provisions of the Annex. XII Part A prior to their disposal or recovery from the date of disposal and prior to access by unauthorised persons. They may only be delivered to other persons for the purpose of disposal or recovery. (5) The transboundary movement of residues into the territory of the country for disposal is prohibited. Unofficial table of contents

Section 98 Dismissal of residues from surveillance

The competent authority shall, at the request of the competent authority, release residues in need of recovery for the purpose of a particular recovery or disposal by written communication from the surveillance, where the circumstances of the individual case and of the measures taken are Protective measures to ensure the necessary protection of the population from exposure to radiation. The measure is that an effective dose of 1 millisievert in the calendar year, even without further measures, shall not be used as a benchmark for the exposure of individuals to the population as a result of the disposal or recovery of the population. is exceeded. Waste disposal or disposal without dismissal from surveillance shall not be permitted. (1a) Paragraph 1 shall apply mutas to the shipment of residues in need of surveillance carried out abroad. Anyone who spends the residues in the country abroad must first demonstrate to the competent authority that the monitoring limits laid down in Annex XII Part B are complied with or that the conditions for dismissal from the surveillance (2) The proof referred to in the first and second sentences of paragraph 1 shall be provided by the application of the principles set out in Annex XII, Part D. The workers employed in disposal or recovery shall be considered to be individuals of the population. Where the residues are to be deposited jointly with other residues or with waste, the competent authority may assume that the conditions set out in paragraph 1 are met if the requirements set out in Annex XII, Part C are met. (3) A dismissal can only take place if there are no objections to the admissibility of the intended recovery or disposal route and its compliance with the waste. The competent authority shall, before issuing the person referred to in paragraph 1, submit a declaration by the applicant on the whereabout of the future waste and a declaration of acceptance by the shipyard or the disposal agent. The applicant shall, at the same time, send a copy of the declaration of acceptance to the authority responsible for the recovery and disposal facility in accordance with the Circular Economy Act, and shall demonstrate this to the competent authority. This authority may require the competent authority, within a period of 30 calendar days after receipt of the copy, to ensure that agreement is reached on the requirements for the recovery or disposal route. The provisions of the Circular Economy Act as well as the provisions adopted pursuant to this Act for the management of evidence on the proper disposal of waste remain unaffected. Unofficial table of contents

Section 99 Residues remaining in the supervision

The competent authority shall, within one month, within one month, comply with the provisions of the first sentence of paragraph 97 (1) of this Directive, the nature, mass and specific activity of the residues in need of monitoring, as well as the planned disposal or recovery of such residues or the levy. to this end, where the nature and specific activity of the residues does not allow the dismissal of the monitoring pursuant to Article 98 (1) sentence 1. The competent authority may arrange for protective measures to be taken and in which way the residues shall be removed. Unofficial table of contents

§ 100 Obligation to provide notification, residue concept, balance of residues

The competent authority and the competent authority shall be responsible for the recovery or disposal of any work carried out or carried out at his or her premises where more than 2000 tonnes per year of residues within the meaning of Annex XII A are obtained, recovered or disposed of in the plant. to communicate to the Circular Economy Act at the beginning of each calendar year. The first sentence shall apply mutadensely to those who have been subject to surveillance in need of surveillance, who have been taken up abroad and who have been brought to the country for recovery. (2) The person referred to in paragraph 1 shall have a concept of recovery and disposal of these residues (residue concept) in accordance with the first sentence of the third sentence and the first sentence of paragraph 3, and to submit it to the competent authority upon request. The residue concept serves as an internal planning instrument. It has to contain:

1.: information on the nature, mass, specific activity and fate of the residues, including estimates of the residues occurring in the next five years,
2.: Presentation of the disposal or recovery measures taken and planned for the next five years.

(3) The residue concept shall be drawn up for the first time up to 1 April 2003 for the next five years. It is to be updated every five years. The competent authority may require the submission at an earlier date. It may require that the form and content satisfy certain requirements. (4) The annual, for the first time as of 1 April 2004, of the obligation referred to in paragraph 1 shall have a balance sheet of type, mass, specific activity and whereabilty for the preceding year. the devalued and disposal residues (balance of residues) and to submit them to the competent authority upon request. The third sentence of paragraph 3 shall apply accordingly. Corresponding proofs according to § 21 of the Circular Economic Law can be submitted in addition. Unofficial table of contents

Section 101 Removal of radioactive contamination of land

(1) Any person who terminates work within the meaning of section 97 (1) sentence 1 or sentence 2 shall remove any contamination from residues in need of surveillance by third parties, no later than five years after the end of use, in such a way that: the residues do not justify any restriction of use. The scale of the use of land without restrictions is that, with regard to the exposure of individuals to radiation by non-distant residues as a guideline, an effective dose of 1 millisievert in the calendar year (2) The competent authority shall notify the competent authority of the completion of the removal of the impurities, with appropriate evidence, within three months. The proof referred to in the first sentence shall be provided by the application of the principles set out in Annex XII, Part D, point 4. The authority may require that the presence of the removed impurities be detected. (3) The competent authority may, on a case-by-case basis, exempt wholly or in part from the obligation referred to in paragraph 1 where circumstances exist or safeguard measures , which shall prevent the exposure of more than 1 millisievert of effective dose in the calendar year to individuals of the population even without removal of the impurities. It may also allow the implementation of the obligation referred to in paragraph 1 at a later date if work is to continue to be carried out in accordance with section 97 (1) on the property. Unofficial table of contents

Section 102 Monitoring of other materials

May be carried out by working with materials falling within the territory of the country or abroad which are not residues within the meaning of Annex XII, Part A, or the exposure of such materials to the exposure of such materials to The competent authority shall take the necessary measures to increase the number of individuals in the population to such an extent that radiation protection measures are necessary. It may, in particular, arrange

1.: that certain protective measures should be taken,
2.: that the materials must be kept or kept at a position to be determined by the materials,
3.: that and in what way the materials are to be eliminated, or
4.: that the person who has accepted materials that have been recruit abroad and who have been transferred to the country will return them to the original owner in the country of dispatch.

Chapter 4
Cosmic radiation

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Section 103 Protection of flying personnel from exposure to cosmic radiation

(1) Those who aircraft in the German aircraft in accordance with § 3 of the Air Traffic Act as amended by the Notice of 27 March 1999 (BGBl). 550), as amended in each case, whether commercial or within the framework of an economic undertaking, or who, as an entreprenter who has its registered office in the scope of this Regulation, operates aircraft in another country , and staff employed in an employment relationship according to German labour law, the effective dose of the flying personnel by cosmic radiation during the flight, including the journey time, shall be pursuant to Article 4 (1), first sentence, of the Second Implementing Regulation relating to the operating rules for Aeronautical equipment of 12 November 1974 (BGBl. 3181), as last amended by the Regulation of 6 January 1999 (BAnz. 497), as amended, to be determined in accordance with sentence 2, provided that the effective dose of cosmic radiation may exceed 1 millisievert in the calendar year. The results of the investigation must be available no later than six months after the application. The first and second sentences also apply to aircraft operated under the division of the Federal Ministry of Defence. (2) For the flying personnel, the limit of the effective dose by cosmic radiation is 20 millisievert in the Calendar year. The duty to reduce the dose in accordance with § 94 may be taken into account, in particular, in the preparation of the work plans and in the definition of the flight routes and profiles. (3) The limit value for the sum of the total of the calendar years. Effective doses of professionally exposed persons are 400 millisievert. The competent authority may, in consultation with a doctor referred to in Article 64 (1) sentence 1, authorise a further occupational exposure if the latter is not more than 10 millisievert effective dose in the calendar year and the occupational exposure to radiation exposure is not more than 10 millisievert. Person agrees. The consent shall be given in writing. (4) If, in breach of the first sentence of paragraph 2, the limit of the effective dose has been exceeded in the calendar year, further employment as a person exposed to radiation shall be permitted only if the person concerned has been informed of the Exposures in the following four calendar years, taking into account the exceeding of the limit value, shall be limited so that the sum of the doses does not exceed five times the limit value. If the exceeding of a limit value is so high that in the case of the application of the first sentence the previous employment cannot continue, the competent authority may, in consultation with a doctor in accordance with section 64 (1) sentence 1, allow exceptions to the first sentence. (5) In the case of an unborn child exposed to radiation exposure as a result of his/her mother's employment, the dose limit of the dose from external exposure shall be from the date of notification of pregnancy to the end of the pregnancy. 1 Millisievert. (6) The person who has pledged in accordance with paragraph 1 shall have the flying staff at least once in the Calendar year on the health effects of cosmic radiation and on the processing and use of personal data relating to the purpose of monitoring dose limits and observance of the principles of radiation protection shall inform women that a pregnancy should be communicated as early as possible with a view to the risks of exposure to radiation for the unborn child. The information may be part of the required instructions in accordance with other provisions. The person who has pledged in accordance with paragraph 1 shall keep records of the content and date of the information to be signed by the person who has been informed. He shall keep the records for five years after the date of notification and shall submit it to the competent authority upon request. (7) The person referred to in paragraph 1 shall have the following information:

1.

to record without delay the results of the dose determination referred to in paragraph 1;

2.

the records referred to in point 1

a): keep up until the monitored person is 75 years old. is completed or would have been completed, but at least 30 years after the end of the respective employment,
b): at the latest 95 years after the birth of the person concerned,
c): to submit, at the request of the person being monitored or to the competent authority, or to deposit at a position to be determined by that authority,
d): in the event of a change in the employment relationship, to inform the new employer at the request of the new employer if employment continues to be practised as an exposed person,

3.

exceed the limit value of the effective dose referred to in the first sentence of paragraph 2 of the competent authority, indicating the reasons for the immediate notification of the persons concerned and the doses determined;

4.

inform the person concerned immediately of the effective dose in the case of point 3.

(8) The effective dose determined in accordance with paragraph 1 and the information referred to in § 112 (1) (2) and (3) shall be forwarded to the Aeronautical Federal Office or to a body designated by the Federal Aviation Office for forwarding to the radiation protection register. at least half-yearly. Information from the Radiation Protection Register shall be provided to the person referred to in paragraph 1 as far as it is necessary for the performance of his duties. Section 112 (4), first sentence, no. 1 and 3 and second sentence 2 shall apply. (9) The person referred to in paragraph 1 shall be entitled to exceed 6 millisievert in the calendar year in respect of which the determination referred to in paragraph 1 has shown that an effective dose of more than 6 millisieverts is exceeded. may only permit employment or continued employment if, within the calendar year concerned, they have been examined by a doctor in accordance with Article 64 (1) sentence 1 and who, according to the provisions of paragraph 1, issued a plea issued by that doctor certificate, after which the employment does not raise any health concerns. In accordance with § 64 (1) sentence 1, the documents requested in accordance with § 61 (1) sentence 1 are to be handed over immediately to the doctor. The doctor shall immediately send the medical certificate to the competent authority to the competent authority, in accordance with the first sentence of paragraph 1, the professionally exposed person and, where there are concern for health, also to the competent authority. The examination can be carried out within the framework of the examination of the medical examination.

Chapter 5
Operational Organization

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Section 104 Duty of notification of the company's organisation

If, in the case of legal persons, the representative body is composed of a number of members or, in the case of members of a group of persons with a right of participation or of persons who are not legally competent, there are several persons entitled to represent them, the competent authority shall inform the competent authority of the obligations under this part of the Regulation. This does not affect the overall responsibility of all organ members or members of the association of persons representing the members of the association.

Part 4
Protection of the consumer in the addition of radioactive substances to products

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Section 105 Illegal addition of radioactive substances and inadmissible activation

The addition of radioactive substances in the manufacture of

1.: Toys,
2.: Jewelry,
3.: food, including drinking water and food additives, as defined in the Food and Feed Code,
4.: feedingstuffs within the meaning of the Food and Feed Code,
5.: tobacco products within the meaning of the Preliminary Tobacco Act,
6.: Gas annealing stockings, in so far as these are not intended to be used to illuminate public roads,
7.: lightning protection systems or
8.: Glassware where contact of the product with food cannot be ruled out,

and the transboundary movement of such goods under section 108 and the placing on the market of such goods shall be inadmissible. The first sentence shall apply to the activation of such goods if this leads to a specific activity in the product of more than 500 microbecquerels per gram, or where the values are exceeded in the case of jewellery according to Annex III, Table 1, column 5. Sentence 1 shall not apply to the addition of radionuclides for which no free limits are laid down in Table 1 of Annex III. In addition, the legislation on food, drinking water, cosmetic products, feedingstuffs and other consumer goods shall remain unaffected. Unofficial table of contents

Section 106 Authorisation in need of addition of radioactive substances and activation requiring approval

(1) Anyone in the manufacture of consumer goods, of medicinal products within the meaning of the German Medicines Act, of plant protection products within the meaning of the Plant Protection Act, of pesticides and of substances according to § 1 Nr. 1 to 5 of the German Medicines Act Fertiliser law, which is to be acquired in the scope of this Regulation or to be delivered to others, shall be subject to the approval of radioactive substances. Sentence 1 shall apply accordingly to the activation of the products mentioned therein. § 105 shall remain unaffected. (2) A permit referred to in paragraph 1 shall not replace an authorisation pursuant to § 7 (1) or § 11 (2). (3) A permit referred to in paragraph 1 shall not be required for the addition of

1.: noble gases obtained from the air, if the isotope ratio in addition corresponds to that in the air, or
2.: Radionuclides, for which no free limits are laid down in Table 1 of Annex III.

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Section 107 Requirements for the approval of the addition of radioactive substances and the activation

(1) The authorisation in accordance with § 106 for the addition of radioactive substances in the manufacture of consumer goods shall be granted if:

1.

the level of activity of the radioactive substances added to the state of the art is as low as possible; and

a): if the consumer product does not exceed the values of Annex III, Table 1, column 2, and, if the specific activity of the artificial radioactive substances added in the consumer product, the values of Annex III, Table 1, column 5 or the the specific activity of the natural radioactive substances added in the consumer product exceeds 0,5 becquerel per gram, and it is ensured that, in a withdrawal concept, the consumer, after use, shall be free of charge to the applicant; or a body designated by it may be returned; or
b): it is shown that only an effective dose of 10 microsieverts can occur for individuals in the population in the calendar year,

2.

the material containing the radioactive substances is covered in a contact-proof manner, or the radioactive material is firmly embedded in the consumer goods and the local dose rate at a distance of 0.1 metres from the touchable surface of the consumer goods 1 microsievert does not exceed by hour under normal conditions of use,

3.

ensures that information is provided to the consumer goods, which

a): the radioactive additive,
b): describes the intended use and
c): in the case referred to in point 1 (a), second sentence, to the obligation to return pursuant to section 110, second sentence, and the body responsible for the withdrawal,

if the specific activity of the artificial radioactive substances added in the consumer product is the values of Annex III, Table 1, column 5, or the specific activity of the natural radioactive substances added in the consumer product, 0,5 becquerel per Gram exceeds,

4.

it is the addition of other radioactive substances according to § 2 para. 1 of the Atomic Energy Act,

5.

in the case of the setting up, the requirements of section 9 (1) (1) to (9) are fulfilled

6.

§ 4 (3) does not preclude the addition.

In the case of the radionuclide H-3, the value of the specific activity of 100 becquerels per gram shall apply to the radionuclide H-3 for the radionuclide H-3 of Table 1, column 5. (2) The competent authority may, in the case of consumer goods, mainly in the (3) The authorisation in accordance with § 106 shall be granted in the case of a professional, non-residential area, and shall allow for derogations from paragraph 1 (1) (a) and (2). Manufacture of medicinal products within the meaning of the Medicines Act, of plant protection products in the sense of of the Plant Protection Act, of pesticides and of substances according to Article 1 (1) (1) to (5) of the Fertilizer Act, if:

1.: it is the addition of other radioactive substances according to § 2 para. 1 of the Atomic Energy Act,
2.: in the case of adding the conditions of § 9 (1) (1) to (9).

(4) Paragraphs 1 to 3 shall apply mutas to the activation with the proviso that, instead of the approval requirements of § 9, those of § 14 Nos. 1 to 9 shall enter into force. (5) The application for approval shall be the documents corresponding to Annex II, Part A, shall be attached. Unofficial table of contents

Section 108 Cross-border movements of consumer goods in need of approval

Those consumer goods to which radioactive substances have been added or which have been activated,

1.: within the scope of this Regulation, or
2.: from the scope of this Regulation to a State which is not a Member State of the European Communities,

will require approval. Sentence 1 shall not apply to:

1.: the movement of goods in the carriage of goods which are not intended for trade or for commercial use;
2.: the transit through which the goods are subject to duty,
3.: Consumer goods, the manufacture of which is authorised in accordance with Section 106 in conjunction with Section 107 (1) (1) (b),
4.: Products to which consumer goods are incorporated, the manufacture of which is approved in accordance with Section 106 or their shipment in accordance with the first sentence.

Section 106 (3) shall apply accordingly. Unofficial table of contents

Section 109 Approval requirements for the transboundary movement of consumer goods

The approval pursuant to § 108 shall be granted if the condition of section 22 (1) no. 1 is fulfilled. In the case of shipments within the scope of this Regulation, the conditions set out in the first sentence of Article 107 (1) (1) to (4) and (6) and the second sentence must be fulfilled. § 107 (2) and (110) sentence 1 shall apply accordingly, the provider shall enter the place of the manufacturer within the meaning of § 110 sentence 1. Unofficial table of contents

Section 110 Repatriation of consumer goods

Those who, as producers of a consumer goods, require a permit pursuant to § 106 in conjunction with Section 107 (1) (1) (a) half-sentence 2, must ensure that the consumer goods can be withdrawn free of charge. After the end of use, the final consumer shall immediately return the consumer goods to the position indicated in the information in accordance with section 107 (1) no. 3.

Part 5
Common rules

Chapter 1
Consideration of radiation exposures

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Section 111 Determination of the exposure to radiation, duty to be didled

(1) In the determination of body dose by activities in accordance with § 2 (1) No. 1, medical exposure, exposure to radiation as a helping person or animal accompanying person, natural radiation exposure and exposure to radiation shall be determined in accordance with § 86 shall not be taken into account. Occupational exposure to radiation from the scope of the X-ray Regulation and occupational exposures outside the geographical scope of this Regulation shall be taken into account. (2) In the determination of the Body dose by working according to § 2 para. 1 no. 2 are not to take into account the medical radiation exposure, the radiation exposure as a helping person or an animal accompanying person, and the radiation exposure according to § 86. The natural exposure to radiation shall be taken into consideration, insofar as it is to be determined in accordance with § 95 (10) and § 103 (1). Occupational exposures, which take place outside the territorial scope of this Regulation, must also be taken into account. (3) For a person, both the body dose by activities in accordance with § 2 para. 1 No. 1 and the body dose by the work of Article 2 (1) (2), the effective doses and the respective organdoses shall be added together. In order to prove that the limit values in force for the activity or for the work have not been exceeded, the added value is decisive. (4) Persons,

1.: in accordance with § 40 (1) sentence 1, § 41 (1) sentence 1 or 2, para. 2, 3 sentence 1, paragraph 6 sentence 1, § 58 para. 4 sentence 1 or § 59 para. 3 sentence 1 the body dose or according to § 95 para. 10 sentence 1 or § 103 para. 1 the dose must be determined or
2.: where contamination can be detected in accordance with § 44 (1) sentence 1 or 2
3.: which are subject to occupational health care in accordance with § 60 (1) or (2), § 95 (11) or § 103 (9) of the occupational health care provision
4.: which are subject to special occupational health care pursuant to Section 63 (1),

have the necessary measurements, findings and medical examinations to be carried out. Sentence 1 shall also apply to persons for which the competent authority has ordered measurements or medical examinations in accordance with Section 60 (4), § 96 (4) and (5) or § 113 (4). If limit values are exceeded or if requested, these persons shall be informed of the outcome of the investigations or findings. Unofficial table of contents

Section 112 Radiation Protection Register

(1) In the Radiation Protection Register pursuant to Section 12c of the Atomic Energy Act, the following are entered:

1.: the dose values determined in the context of occupational exposure to radiation pursuant to section 41 (7) sentence 1 or 2, section 58 (4), section 59 (3), section 95 (10) and § 103 (1), as well as the relevant findings of the competent authority,
2.: Information on registered radiation passes pursuant to § 40 (2) sentence 1 or § 95 (3) and
3.: the personal data (surname, first name, date and place of birth, sex), employment characteristics and exposure conditions as well as the address of the person responsible for radiation protection in accordance with § 31 (1) or the pledge pursuant to section 95 (1) or § 103 (1).

The data referred to in paragraph 1 shall be transmitted to the radiation protection register in each case.

1.: the measuring points pursuant to section 41 (3) sentence 1 or (6) sentence 1 within the monthly period,
2.: the competent authority or the body designated by it pursuant to Article 96 (3) sentence 1 within a period of one month,
3.: the Federal Aviation Office or the body designated by it pursuant to section 103 (8) sentence 1 at least twice a year and
4.: the competent authority shall immediately, with regard to its findings and the information on registered radiation passes,

where new or modified data are available. The competent authority may arrange for a measurement point to be transmitted to the radiation protection register in the case of results recorded in the case of a body dose obtained earlier; it may have records of the person responsible for radiation protection requested by the competent authority. (3) The Federal Office for Radiation Protection (Bundesamt für Strahlenschutz), the Federal Office for Radiation Protection, is responsible for the Data transmitted in the Radiation Protection Register on a personal basis, evaluates it shall inform the competent authority if it considers it necessary in the light of the results of the evaluation. (4) Information from the Radiation Protection Register shall be given as far as this is necessary for the performance of the tasks of the recipient is required:

1.: data relating to persons who are responsible for the protection of persons who are responsible for the protection of radiation,
2.: a carrier of the statutory accident insurance cover relating to data relating to persons insured with him, on request,
3.: a competent authority, a measuring point or a body designated by the competent authority on request; the competent authority may supply information from the radiation protection register to the person responsible for radiation protection through persons who are active in the field of radiation protection; , to the extent that this is necessary for the performance of their duties, data relating to the radiation protection officer and to the competent doctor referred to in Article 64 (1) sentence 1.

The person concerned shall receive information from the radiation protection register on the data stored on his/her person on request. (5) Universities, other institutions conducting scientific research, and public bodies may, upon request, Information is provided in so far as this is necessary for the implementation of certain scientific research in the field of radiation protection and does not preclude Section 12c (3) of the Atomic Energy Act. If a request for information on personal data is requested, a written consent of the person concerned shall be attached. If the information is to be provided without the consent of the person concerned, the information required for the examination of the conditions pursuant to Section 12c (3) sentence 2 of the Atomic Energy Act must be made; to Section 12c (3) sentence 3 of the Atomic Energy Act is to be made credible that: the purpose of scientific research in the use of anonymized data cannot be achieved with reasonable effort. Personal data may only be used for the research work for which it has been transmitted; the use for other research or dissemination shall be determined in accordance with the rates 2 and 3 and shall be subject to the consent of the Federal Office for Radiation Protection. (6) The personal data stored in the Radiation Protection Register shall be deleted 100 years after the birth of the data subject. (7) The measuring points, the competent authorities or the bodies designated by them. begin with the transmission at the time that the Federal Office for Radiation Protection determines . The Federal Office for Radiation Protection shall determine the data format and the method of transmission.

Chapter 2
Powers of the Authority

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Section 113 Order of measures

(1) The competent authority may order those measures which are necessary for the implementation of § § 4, 5, 6, 30 to 88. It may also order the necessary measures for the implementation of § § 93 to 104. In so far as the measures do not object to the elimination of a risk to life, health or significant environmental goods, a time limit shall be set for implementation. (2) The order shall be subject to measures for the implementation of the provisions of Part 2 of the Treaty. Persons responsible for radiation protection in accordance with § 31. In urgent cases, it may also be addressed to the radiation protection officer. The person responsible shall immediately inform the person responsible for radiation protection. In the case of measures for the implementation of the provisions of Part 3, the arrangement shall be addressed to the pledge pursuant to § 95 (1), § 97 (1), § 100 (1) or § 103 (1). (3) In the case of the variable handling of radioactive substances or in the operation of The arrangement can also be directed to those in whose control area the handling or operation takes place. The person responsible for the activities referred to in the first sentence of the first sentence must take the necessary measures to point out that the measures have been complied with. (4) It is necessary to ensure that persons who are involved in the fields of activity , in which activities pursuant to § 2 (1) No. 1 or work pursuant to § 2 (1) No. 2 are exercised in connection with Section 95 (2), the limit values of § 55 (1) to (4) or § 95 (4), (7) or (8) may be exceeded the competent authority shall arrange for such persons to be examined by a doctor in accordance with § 64 (1) sentence 1. Unofficial table of contents

Section 114 Public exemptions from radiation protection regulations

The competent authority may, on a case-by-case basis, permit the waived of the provisions of Sections 34 to 92, 95 to 104, with the exception of the dose limit value schemes, if:

1.: a device, an installation, any other device, an activity or a work shall be tested or the compliance with the requirements would require a disproportionate effort, provided that in both cases the security of the equipment, the the installation, the other device or the activity or the work and the radiation protection shall be ensured in a different way; or
2.: the safety of the equipment, the installation, the other device, an activity or a work is not adversely affected by the deviation and the radiation protection is ensured.

Chapter 3
Formal requirements

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§ 115 Electronic Communications

(1) The recording, accounting and retention obligations under this Regulation may be fulfilled electronically. In the context of an authorization pursuant to § § 3, 4, 6, 7 or § 9 of the Atomic Energy Act or a plan determination decision in accordance with § 9b of the Atomic Energy Act, this applies only if the competent authority of electronic recording, bookkeeping or storage in writing or in electronic form. (2) Obligations for participation, reporting or notification can be fulfilled in electronic form if the recipient has access to it, and the procedure and the data transmission system shall be determined. In this context, appropriate measures must be taken to ensure data protection and data security, which in particular ensure the confidentiality and integrity of the data; in the case of use in general, the following measures must be taken to ensure the confidentiality and integrity of the data. accessible networks shall be used as encryption methods. If a transmitted electronic document is not suitable for processing for the recipient, it shall inform the sender without delay, stating the technical conditions applicable to the reception. (3) By way of derogation from § 17 (1) sentence 1 the first half-sentence of the Atomic Energy Act may be granted an authorisation or general authorisation pursuant to this Regulation also in electronic form. In this case, the electronic document shall be accompanied by a permanently verifiable signature in accordance with Article 37 (4) of the Administrative Procedure Act.

Chapter 4
Irregularities

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§ 116 Administrative Offences

(1) Contrary to the provisions of Section 46 (1) (4) of the Atomic Energy Act, those who intentionally or negligently act

1.

without authorisation after

a): Section 7 (1) deals with other radioactive substances or with nuclear fuel,
b): Section 11 (1) establishes a facility designated there,
c): Section 11 (2) operates an installation for the production of ionizing radiation, or modifies the plant or its operation,
d): § 15 para. 1 in a foreign facility or establishment a person under his supervision employed or performing a task itself,
e): Section 16 (1) other radioactive substances or nuclear fuels are transported,
f): § 19 (1) or (2) of other radioactive substances or nuclear fuels,
g): § 23 (1) radioactive substances or ionizing radiation used for the purpose of medical research in humans,
h): Section 106 (1), first sentence, also in conjunction with the second sentence, added radioactive substances or activates the products mentioned therein; or
i): Article 108, first sentence, of the consumer goods referred to in this Regulation or from the scope of this Regulation to a State which is not a Member State of the European Communities,

1a.

, contrary to § 12 (1) or § 20 (1) sentence 1 or paragraph 3, an indication is not reimbursed, not correct, not complete, not in the prescribed manner or not in good time,

1b.

Contrary to Article 12 (2), proof does not or does not result in time,

1c.

Contrary to Article 20 (2), the provision of care is not or is not adequately met,

2.

takes over core materials contrary to § 17 paragraph 3,

3.

a fully-fledgable edition in accordance with section 26 (1) sentence 2 no. 3

4.

, contrary to Article 27 (1) (1) or (2), quality control is not carried out or is not carried out in good time

5.

Contrary to Article 27 (1) (3) or (4), in connection with the second sentence of paragraph 2, the letter of admission or an instruction manual shall not be handed over or shall not be handed over in good time,

6.

Contrary to the first sentence of Article 27 (2), there is no proof of the approval certificate or a test finding,

7.

Contrary to Article 27 (3), an amendment is made

8.

Contrary to Article 27 (4), an apparatus is used or a protective measure does not meet or does not meet in time,

9.

Contrary to Article 27 (5), an apparatus shall not or shall not be shut down in time or shall not take a protective measure in due time,

10.

, contrary to the provisions of Article 27 (6), first sentence, an apparatus shall not be examined or not

11.

Contrary to Article 27 (7), an apparatus shall not be returned or not returned in time or shall not be returned in time,

12.

an enforceable arrangement according to § 40 (5) or § 113 (4),

12a.

does not make a communication, not correct, not complete or timely, contrary to Article 51 (1) sentence 2,

12b.

Contrary to § 59 (3) sentence 2, a communication does not make, not correct, not complete or not timely,

13.

Contrary to Section 69 (3) sentence 1, it is not ensured that radioactive substances are transported by persons mentioned there,

14.

Contrary to Section 69 (4), it does not ensure that radioactive substances are handed over to the recipient or to an authorized person,

15.

Contrary to Section 93, it is not ensured that the dose limit specified in § 95 (4) sentence 1 or 2, paragraph 5, sentence 1, para. 7 or 8, is not exceeded,

16.

Contrary to Section 93, it is not ensured that the dose limit value referred to in § 103 (2) sentence 1, paragraph 3, sentence 1 or paragraph 5, is not exceeded,

17.

Contrary to § 95 (1) sentence 1, even in conjunction with sentence 3, § 95 (1) sentence 2 or 10 sentence 1, an estimation shall not be carried out, not properly or not in time, or repeatedly or not repeated in time, or the radon 222 exposure, which potential alpha-energy exposure or body dose not determined correctly or not in time,

18.

, contrary to Section 95 (2) sentence 1, an indication is not reimbursed, not correct, not complete or not in good time,

19.

Contrary to Section 95 (3), the person concerned does not ensure that a person carries out a work only if it is in possession of a radiation passport,

20.

Contrary to Section 95 (9), the working conditions are not designed, not correct or not in good time,

21.

, contrary to Article 95 (11), first sentence, allows employment or continued employment,

22.

, contrary to § 95 (11) sentence 4, a medical certificate shall not be handed over or shall be handed

23.

Contrary to § 96 (1) sentence 1, a result of the investigation is not drawn up, not correct or not in good time,

24.

Contrary to § 96 (2) (1) (a), a record is not retained, not completely or not for the prescribed period,

25.

Contrary to Article 96 (2) (1) (b), a record is not deleted or not deleted in time

26.

, contrary to Article 96 (2) (1) (c), a record is not submitted or not submitted in due time or not, or filed in due time,

27.

Contrary to § 96 para. 2 no. 2 or § 100 para. 1 a communication does not make, not correct, not complete or not in good time,

28.

, contrary to § 96 (3) sentence 1, a determined dose is not transmitted, not correct or not in good time,

29.

an enforceable arrangement according to § 96 (4) or (5), § 97 (3) sentence 1, § 99 sentence 2, § 101 (2) sentence 3 or § 102,

30.

, contrary to Section 97 (2) sentence 2, materials are mixed or diluted,

31.

Contrary to § 97 (4) sentence 1 or 2, arrears shall not be insured or provided,

31a.

Contrary to § 97 (5), arrears in the domestic market,

32.

, contrary to § 98 (1) sentence 3, residues in need of surveillance have been recovered or disposed of,

33.

, contrary to § 99 sentence 1 or § 101 (2) sentence 1, an advertisement is not reimbursed, not correct, not complete or not in good time,

34.

Contrary to § 100 (2) sentence 1, subsection 3 sentence 2 or paragraph 4 sentence 1, a residue concept or a balance sheet does not, not correct, not complete or not prepared in good time, not or not in time or not, or not, or not in good time,

35.

Contrary to § 101 (1) sentence 1, an impurity is not removed, not in the prescribed manner or not in due time,

36.

Contrary to § 103 (1) sentence 1, the effective dose referred to therein shall not be determined, not properly or not in time,

37.

Contrary to § 103 (6) sentence 1, the flying staff is not informed, not correct or not in good time,

38.

, contrary to § 103 (6) sentence 3 or 4, a record is not recorded, not correct or not complete, not stored or not stored for at least five years, or not presented in due time,

39.

Contrary to Section 103 (7) No. 1, the results of the dose determination are not shown, not correct or not in good time,

40.

Contrary to § 103 (7) (2) (a), a record is not retained, not completely or not for the prescribed period,

41.

Contrary to § 103 (7) (2) (b), a record is not deleted or not deleted in time

42.

Contrary to § 103 (7) (2) (c), a record is not submitted or not submitted in due time, or not deposited in due time,

43.

Contrary to § 103 (7) (3), a communication does not make, not correct, not complete or not in good time,

44.

, contrary to § 103 (8) sentence 1, the determined dose is not transmitted, not correct or not in good time,

45.

Contrary to § 103 (9) sentence 1, employment or continued employment is permitted,

46.

, contrary to § 103 (9) sentence 3, a medical certificate shall not be sent or sent in due time,

47.

Contrary to § 105 sentence 1, also in conjunction with sentence 2, radioactive substances are added or delivered, placed on the market or activated, or

48.

Contrary to Section 111 (4) sentence 1, a measurement, a determination or a medical examination shall not be tolerated.

(2) In the sense of Section 46 (1) (4) of the Atomic Energy Act, who acts as a person responsible for radiation protection or negligently or negligently.

1.: an enforceable arrangement in accordance with Section 12 (3) or section 74 (1) sentence 1,
1a.: Contrary to § 31 (2) sentence 1, the required number of radiation protection officers shall not be ordered or not ordered in the prescribed manner,
2.: Contrary to § 31 (4) sentence 1, a communication does not make, not correct, not complete or not in good time,
3.: Contrary to § 33 (1) (1) (a), (b), aa, dd, ff or gg or point (c), it does not ensure that a provision of § 29 (1) sentence 1, § 31 (2) sentence 2 or (3), § 32 (3), § 34 sentence 1, § 49 (1) sentence 1 or subsection (2), § 50 1 sentence 1, paragraph 2 or 3, of § 61 (3) sentence 2, § 69a or § 83 (4) sentence 1, or
4.: Contrary to § 33 (1) (1) (b) (cc), in conjunction with § 5 sentence 1, it does not ensure that a dose limit value for the planning or establishment of an installation or installation referred to in § 47 (1) sentence 1 is not exceeded,
5.: Contrary to Section 33 (1) (3), it does not ensure that the necessary measures are taken against an unintentional critic of nuclear fuel.

(3) In the sense of Section 46 (1) (4) of the Atomic Energy Act, who acts as radiation protection officer or radiation protection officer intentionally or negligently

1.: contrary to § 33 (1) (2) (a), (b), (aa), (bb), (aaa), double letter (cc), (bb), (bb), double letter (e), (bb), (b), (f), (f), (c), (c), (c), (c), (c), (c), (c), (c), d or paragraph 2 no. 1 point (a) does not ensure that a provision of section 29 (2) sentence 4, § 35, § 36 (1) sentence 1, subsection 2 sentence 1 or 2 or paragraph 4 sentence 1, § 37 para. 1 sentence 1 or para. 2, § 38 (1) sentence 1 to 3, para. 2 to 4, § 39, § 40 para. 1 Sentence 1, para. 2, sentence 1, para. 3 or 4, § 41 (1) sentence 1 or sentence 2, paragraph 2, sentence 1 to 4, paragraph 4, sentence 1, paragraph 5, 6 or Paragraph 9, sentence 1 or sentence 2, § 42 (1) sentence 1 to 6, § 43, § 44 (1) sentence 1 to 3, paragraph 2 sentence 1, paragraph 3 sentence 3, para. 4 or 5, § 45 para. 1 or 3, § 48 para. 1 no. 1 sentence 1, § 57 sentence 1, § 58 para. 4, § 59 paragraph 2 sentence 1 or paragraph 3 sentence 1 or sentence 3, § 60 para. 1 or 2, § 65, § 66 para. 2 sentence 1, para. 5 or para. 6 sentence 1 or 2, § 67, § 68, paragraph 1, 1a sentence 1 or sentence 2 or para. 3 to 6, § 69 para. 1, 2 sentence 1 or 4 or para. 5, § 70 (1) sentence 1, point 2 or sentence 4, paragraph 2 sentence 1 or sentence 2, paragraph 3, 4 or paragraph 6, § 72 sentence 1 or 3, § 73 para. 1, 2 sentence 1, para. 3 or 4, § 74 para. 2 or 3, § 75 para. 1 to 3, § 79 sentence 1, § 80 para. 1 sentence 1, para. 2 sentence 2 or para. 3 Sentence 1, § 81 (1) sentence 1 or 2, subsection 2 sentence 1 or 2, para. 3, subsection 5 sentence 1 or 2 or para. 6 sentence 1, § 82 (1), (2) or (3), § 83 (4) sentence 2 to 4, paragraph 5 sentence 1, paragraph 6 or 7 sentence 1 to 4, § 84, § 85 para. 1, 2 or 3 sentence 1 or 3, section 87 (1) sentence 2 or (3) to (7), § 88 (1), 2 sentence 1 or (3) or (4), § 89 (2), § 92a sentence 2 or § 92b (1) or (2).
2.: contrary to Article 33 (1) (2) (b), double letter bb, bb, double letter cc triple letter ccc, double letter gg triple letter bbb, point c double letter bb or para. 2 no. 1 letter a not ensuring that a Notification pursuant to § 42 (2) sentence 1, § 48 (1) sentence 1 no. 2, § 66 (6) sentence 3, § 70 (1) sentence 1 no. 1 or 3 or sentence 3 or § 89 (1) number 1 or point 2 is made or
3.: Contrary to § 33 (1) (2) (b), double letter cc, triple letter aaa, double letter ee triple letter aaa or para. 2 no. 1 point (a), respectively in conjunction with § 5 sentence 1, does not ensure that a clause in § 46 (1) or (2), § 55 (1) Sentence 1, para. 2, 3 or 4, § 56 sentence 1 or § 58 (1) sentence 2 of the above-mentioned dose limit or a dose limit value specified in § 47 (1) sentence 1 for the operation of an installation or device is not exceeded.

(4) In the sense of Section 46 (1) (4) of the Atomic Energy Act, anyone who intentionally or negligently does not inform the person responsible for radiation protection in accordance with Section 113 (2) sentence 3, or who does not inform it in good time, is in order to act as a radiation protection officer. (5) Contrary to the provisions of Section 46 (1) No. 4 of the Atomic Energy Act, who, in accordance with § 64 (1) sentence 1, intentionally or negligently acts as a doctor,

1.: Contrary to Section 61 (1) sentence 2, a requested document shall not be handed over or shall be handed over
2.: , contrary to § 61 (3) sentence 1, a medical certificate shall not be sent or sent in due time,
3.: , contrary to § 64 (3) sentence 1, 3 or 4, a health file does not, either correctly or incompletely, does not, or not, or is not retained for the prescribed period, or is not destroyed in time,
4.: , contrary to § 64 (4) sentence 1, a health file is not presented or not presented in time or not, or is not handed over in good time, or
5.: Contrary to § 64 (5), the health records are not granted or are not granted in time.

(6) The responsibility for the prosecution and prosecution of administrative offences referred to in paragraph 1 (16) and (36) to (46) shall be transferred to the Federal Aviation Office.

Chapter 5
Final provisions

Unofficial table of contents

Section 117 Transitional provisions

(1) A permit issued before 1 August 2001 for the carriage or transboundary movement of other radioactive substances shall be valid as an authorisation in accordance with § 16 or § 19 with all secondary provisions. An authorisation granted before 1 August 2001 for the handling of other radioactive substances, for the establishment or operation of installations for the production of ionizing radiation shall be deemed to be an authorisation in accordance with § 7, § 11 (1) or (2) with all Secondary provisions on the condition that the limits of § § 46 and 55 are not exceeded. In these authorisations to limit the discharges of radioactive substances with air and water from radiation protection areas, the concentrations of activity in accordance with Article 46 (3) or (4) of the Radiation Protection Ordinance of 30 June 1989 shall be taken up to as of 1 August 2003, the values of Annex VII, Part D. The competent authority has authorised, in accordance with Article 46 (5) of the Radiation Protection Regulation as amended on 30 June 1989, higher concentrations or duties of activity and has been submitted within the limits of three months from the date of entry into force of this Regulation, a request for the re-establishment of values , these activity concentrations or duties shall continue to apply as far as the stock of the decision. If no application is submitted in accordance with the fourth sentence, the values of Annex VII, Part D. shall apply after three months from the date of entry into force of this Regulation, instead of the approved higher values. Radiation protection regulation as amended on 30 June 1989 requires lower activity concentrations or duties, these lower fixed compositions shall continue. (2) Activities which are carried out in accordance with § 4 (1) in conjunction with Annex II No. 1 or § 17 para. 1 of the Radiation Protection Regulation of 30 June 1989, and after 1 August 2001, a permit pursuant to § 7 (3) authorisations pursuant to § 3 or § 5 of the X-ray Ordinance of 8 January 1987 for installations for the production of ionizing products, may be continued if the application for authorization has been submitted by 1 August 2003. Radiation falling within the scope of this Regulation after 1 August 2001 shall continue to be considered as authorisations in accordance with Section 11 (2). Activities which have been indicated in accordance with Article 4 (1) of the X-ray Regulation of 8 January 1987 and which fall within the scope of this Regulation after 1 August 2001 may be continued if the application for authorisation has been submitted by 1 August 2001. In 2003. Paragraph 1 shall apply accordingly. (3a) (omitted) (3b) (omitted) (3c) (omitted) (4) A release according to § 29, in the case of which the up to and including 31. The values of Annex III, Table 1, columns 5, 6 or column 9, shall continue to apply from 1 December 2013 to the values of Annex III, Table 1, columns 5, 6, 9a, 9b, 9c, or column 9d. . The first sentence shall also apply to shares which have been continued pursuant to Section 117 (10) since 1 August 2001. (5) Results pursuant to Article 41 (7), second sentence, which have been recorded before 1 November 2011, shall be valid for 30 years after the date of the respective statement. (6) The manufacture of consumer goods, which was approved in accordance with Section 4 (4) (2) (b), (c), (d) of the Radiation Protection Ordinance of 30 June 1989 and which requires a permit pursuant to § 106, may be made until the decision on the application shall be continued provisionally if the application for authorisation has been submitted by 1 November 2001. The use, storage and disposal of consumer goods within the meaning of the first sentence and of consumer goods which have been manufactured without authorisation before 1 August 2001 shall continue to be subject to no authorisation. Authorisations pursuant to § 3 of the Radiation Protection Ordinance of 30 June 1989 on the manufacture of consumer goods are provisionally continued. Such authorisation shall be issued on 1 November 2001, unless:

1.: before that date, an authorisation shall be requested in accordance with Section 106; the provisional authorisation shall continue to apply after that date and shall be issued when the application has been made, or
2.: the provisional authorisation shall be temporary; the authorisation shall then be issued at the previous date.

Authorisations pursuant to § 3 of the Radiation Protection Ordinance of 30 June 1989 for the addition of radioactive substances in the manufacture of medicinal products within the meaning of the Medicines Act shall continue to apply with all secondary provisions. The sentences 1 to 4 shall apply accordingly in the case of activation. Other products which comply with the requirements of Annex III, Part A, No. 5, 6 or 7 of the Radiation Protection Regulation of 30 June 1989 and which have been acquired before 1 August 2001 may continue to be used for approval and display-free use. (7) An authorisation granted before 1 August 2001 for the type of devices containing radioactive substances shall continue to apply until the date of expiry of the period specified in the authorisation certificate. For the use and storage of devices containing radioactive substances and for which a type approval has been granted before 1 August 2001, the provisions of section 4 (1), 2 sentence 2 and 5 in conjunction with Annex II (2) or (3) shall apply. and Annex III, Part B, No. 4, Section 29 (1), first sentence, § 34 and 78 (1) (1) of the Radiation Protection Ordinance of 30 June 1989 and, after the end of this type of approval, also § 23 (2) sentence 3 of the Radiation Protection Ordinance of 30 June 1989; § 31 (1) (1) of the Radiation Protection Regulation. 1 sentence 2 to 4, para. 2 to 5, § § 32, 33 and 35 of this Regulation shall apply accordingly. Devices whose type approval was expired before 1 August 2001 and which were further operated in accordance with § 23 (2) sentence 3 in conjunction with § 4 of the Radiation Protection Ordinance of 30 June 1989 may continue to be operated without authorization. . The first and second sentences are also valid for ionization smoke detectors, for which the manufacturer or the distribution company was notified in accordance with Annex III, Part B, No. 4 of the Radiation Protection Regulation of 30 June 1989. (8) One before 19 August 2005 (9) § 27 (6) shall not apply to any devices which have the following conditions: Construction according to § 22 in conjunction with Annex VI No. 6 of the Radiation Protection Ordinance of 30 June 1989 , and not for devices of which the type referred to in Article 22 is approved in conjunction with Annex VI (1) to (5) of the Radiation Protection Regulation of 30 June 1989, if the activity inserted is 10 times the free limits of Appendix III (10) Regulations for the release of radioactive substances and of movable objects, buildings, ground surfaces, installations or parts of installations which are activated or contaminated with radioactive substances and from activities. come under Article 2 (1) (a), (c) and (d), which were granted in the period before 1 August 2001 Authorisations or other administrative decisions shall be provisionally continued as cleays. Such a release shall be issued on 1 August 2004, unless:

1.: before that date, a release shall be requested within the meaning of section 29; the provisionally continuing release shall then continue to apply after that date and shall be issued if the decision on the application has become unchallenged, or
2.: the approval or administrative decision on which the provisional release is based is limited to a limited period, and the release shall then be issued at the earlier date specified in the authorisation or administrative decision.

Exemption regulations in approvals pursuant to § § 6, 7 (3) or § 9 of the Atomic Energy Act and § 3 of the Radiation Protection Ordinance of 30 June 1989, which have the object of decommissioning plants and facilities, shall continue to apply indefinitely. (11) The radiation protection officer appointed before 1 August 2001 shall be deemed to have acquired and certify the required subject-specific customer in radiation protection within the meaning of section 30 (1). An appointment to the Radiation Protection Officer before 1 August 2001 shall continue to apply, provided that the update of the technical customer pursuant to Section 30 (2) of the order before 1976 until 1 August 2003, when ordering between 1976 and 1989, is valid until 1 August 2003. August 2004, when ordering from 1989 to 1 August 2006. A certificate of proof issued before 1 August 2001 shall continue to apply, provided that the updating of the technical certificate for the acquisition of the certificate before 1976 until 1 August 2003, in the case of acquisition between 1976 and 1989, shall be valid until 1 August 2004, in the case of acquisitions after 1989 to 1 August 2006. The sentences 1 to 3 apply accordingly to the doctors according to § 64 (1) sentence 1, for radiation protection officers who own the required subject in radiation protection and who have not ordered radiation protection officers, and for persons who have the necessary expertise in radiation protection. Prior to August 1, 2001, the subject of the certificate was acquired, but not as a radiation protection officer. (12) In the case of persons working before 1 July 2002 within the meaning of Section 82 (1) (2) and (2) (4), the knowledge shall be deemed to apply in accordance with Section 30 (4) sentence 2 , but only after 1 July 2004, if the competent authority pursuant to Section 30 (1) gives them the possession of the (13) The jurisdiction in accordance with national law for measuring points pursuant to § 63 (3) sentence 1 of the Radiation Protection Ordinance of 30 June 1989 shall continue as a provision within the meaning of Section 41 (1) sentence 4. The provision of measuring points pursuant to § 63 (6) sentence 1 of the Radiation Protection Ordinance of 30 June 1989 shall be considered as a provision within the meaning of section 41 (1) sentence 4. (14) In the case of approval procedures for storage, which were initiated before 1 August 2001 Irradiated nuclear fuel according to § 6 of the Atomic Energy Act at the respective sites of the nuclear power plants approved in accordance with § 7 of the Atomic Energy Act or before 1 August 2001, planning procedures for the establishment and operation of plants commenced on the freezing and disposal of radioactive waste in which a discussion date , the applicant may provide proof of compliance with the limit values laid down in Section 47 (1) by the fact that, on the basis of the general administrative provision relating to Section 45 of the Radiation Protection Regulation, the applicant states: " Radiation exposure through the discharge of radioactive substances from nuclear installations or facilities of 21 February 1990 " (BAnz. No 64a of 31 March 1990), compliance with the dose limit of § 47 (1) (1) of this Regulation and the partial body dose limit values of § 45 (1) of the Radiation Protection Regulation of 30 June 1989 with the institutions of Appendix X Table X2 at Compliance with Annex X, Table X1, footnote 1 and Annex X, Table X2, and with the assumptions used to determine the exposure to radiation from Annex XI of the Radiation Protection Regulation of 30 June 1989 and the dose factors of the Federal Gazette No 185a of the Published on 30 September 1989. The values and relationships in Annex II to Council Directive 96 /29/EURATOM of 13 May 1996 laying down the basic safety standards for the protection of the health of the Workers and the general public against the dangers arising from ionizing radiation (OJ C 327, 28.4.2002, EC No L 159 p. 1). For purposes other than those referred to in the first sentence of the first subparagraph, the determination of the exposure to radiation from discharges to the end of one year after the entry into force of the general administrative provisions in section 47 (2), second sentence, shall be the same as those referred to in sentences 1 and 2. Dose limits and calculation methods authoritative. (15) In the authorisation procedure for the storage of irradiated nuclear fuels, begun before 1 August 2001, in accordance with § 6 of the Atomic Energy Act at the respective sites of the nuclear fuel law according to § 7 of the Atomic Energy Act approved nuclear power plants or started before the entry into force of this Regulation Planning procedures for the establishment and operation of installations for the purpose of ensuring and for the disposal of radioactive waste during which a meeting has been held, the applicant may provide evidence of adequate provision against accidents pursuant to section 49 (2), by complying with the dose value of § 49 (1) (1) of this Regulation and the partial body dose values of § 28 (3) with the institutions of Appendix X Table X2, taking into account Annex X, Table X1 Footnote 1 and Annex X Table X2 of the Radiation Protection Regulation of 30 June 1989 and the Dose factors derived from the compilation published in Federal Gazette No. 185a of 30 September 1989. The values and relationships in Annex II to Council Directive 96 /29/EURATOM of 13 May 1996 laying down the basic safety standards for the protection of the health of the Workers and the general public against the dangers arising from ionizing radiation (OJ C 327, 28.4.2002, EC No L 159 p. 1). The references mentioned above may be used for installations for the purpose of ensuring and for the disposal of radioactive waste the basis for calculation of the recast of Chapter 4 "Calculation of the exposure of accidents" of the sources of disturbance calculation for the purposes of Guidelines for the assessment of the design of nuclear power plants with DWR according to § 28 (3) of the Radiation Protection Ordinance, as amended by the Federal Gazette No. 222a of 26 November 1994. For the storage of irradiated nuclear fuel in accordance with § 6 of the Atomic Energy Act at the respective sites of the nuclear power plants approved in accordance with § 7 of the Atomic Energy Act, the evidence can be subject to separate requirements for these nuclear power plants. Activities carried out by the Federal Ministry for Nuclear Safety and Radiation Protection in the Federal Gazette (Bundesanzeiger) are based on the calculation bases referred to in sentence 3. (16) Until the entry into force of the Administrative provisions concerning the prevention of accidents pursuant to § 50 (4) shall be applied in the planning of the provisions of § 50 (1) to (3) (17) High-level radioactive sources, which do not exceed the effective dose of 50 millisievert caused by the release of radioactive substances into the environment. (17) have been placed on the market before 31 December 2005, no marking shall be required in accordance with Section 68 (1a) sentence 1. They may be submitted by 30 December 2007 without the documentation of the manufacturer provided for in Article 69 (2) sentence 4. As from 31 December 2007, they may not be issued by way of derogation from the fourth sentence of Article 69 (2) if they are accompanied by appropriate written documents for the identification of the source of radiation and of their kind. (18) Authorizations of doctors within the meaning of § 71 Paragraph 1, first sentence, of the Radiation Protection Regulation of 30 June 1989 shall continue to apply as authorisations pursuant to Section 64 (1) sentence 1. (19) Provisions of experts pursuant to § 76 (1) sentence 1 of the Radiation Protection Regulation of 30 June 1989 and provisions of Experts according to § 18 of the X-ray Ordinance of 8 January 1987 for X-ray equipment and Interference radiators in the field of energy greater than one Megaelectronvolt shall continue to be considered as provisions in accordance with § 66 (1) sentence 1. (20) The continuation of work pursuant to Article 95 (2), which began before 1 August 2001, shall be the competent authority until 1 August 2003. Authority to view. Approvals according to § 3 of the Radiation Protection Ordinance of 30 June 1989 on the handling of radioactive substances, which is a work in need of display in accordance with § 95 (2) sentence 1, shall be continued as an indication in accordance with Section 95 (2), unless an authorisation pursuant to § 106 is required. Secondary provisions granted under such authorisations shall be considered as orders in accordance with Section 96 (4). (21) The measures listed in Annex VI, Part A, No. 1 and 2 shall be valid no later than 1 August 2011 for measurements of the dose, local dose, and Use of the local dose rate in accordance with § 67. This shall be without prejudice to measurements of the local dose or local dose rate, using other measures other than those referred to in Annex VI, Part A, No 2, to carry out a conversion to the measures referred to in Annex VI, Part A, No 2, where such measurements are taken to prove that the limits of the body dose are not exceeded in accordance with § § 46, 47, 55 and 58. (22) Values of body dose or personal dose determined by 1 August 2001 shall be considered to be values of body dose in accordance with Annex VI, Part B or the dose of persons referred to in Annex VI, Part A, No 1. (23) Equipment procured before 1 April 1977, Ceramic articles, porcelain products, glassware or electronic components, with which according to § 11 of the First Radiation Protection Ordinance of 15. It was not allowed to be dealt with without authorisation in October 1965, and may continue to be used and removed without authorisation if, at the time of procurement, these objects comply with the provisions of Section 11 of the First Radiation Protection Regulation of 15 October 2008. (24) Ceramic objects or porcelain products which were used before 1 June 1981 and whose uranium-containing glaze corresponds to Annex III, Part A, No. 6 of the Radiation Protection Regulation of 30 June 1989, may continue to be used. shall be used and disposed of. Unofficial table of contents

Section 118 delimitation to other regulations, restoration of legacies

(1) On the basis of the provisions of Article 3 of the agreement of 6 September 1990 (BGBl. 8851), the area referred to in Article 9 (2) shall apply to the remediation of the legacy of previous activities and work, and to the decommissioning and rehabilitation of the uranium ore mining facilities and sites referred to in Article 9 (2). Annex II, Chapter XII, Section III (2) and (3) of the Agreement, the following provisions shall be continued:

1.: Regulation on the guarantee of nuclear safety and radiation protection of 11. October 1984 (GBl. No 30 p. 341), together with the implementing provisions for the Regulation on the protection of nuclear safety and radiation protection from 11. October 1984 (GBl. 30 p. 348; Ber. GBl. I 1987 No 18 p. 196) and
2.: Arrangement to ensure radiation protection in the case of semi-industrial and industrial settling plants and in the use of materials deposited therein on 17 November 1980 (GBl. 34 p. 347).

Moreover, the provisions of this Regulation shall be replaced by the provisions referred to in points 1 and 2. Licences granted on the basis of the provisions referred to in points 1 and 2 after the entry into force of the agreement on the entry into force of the agreement, or prior to that date, but continuing to apply, and which relate to one of the fields of work listed in Annex XI to this Regulation, the following shall be deemed to constitute an indication in accordance with Article 95 (2) sentence 1. (2) For occupational radiation protection of employees § § 5, 6, 15, 30, 34 to 45, 54 to 64, 67 and 68, § § 111 to 115 as well as the related regulations of § 116 (1) (1) (1) (1) (1) (1) (1) (1) (1) (1)) shall apply to the decommissioning and refurbishment of the uranium ore mining industry. (d) No 12 and 44, (2) (4) and (5) and (3) to (5); provided that the employees are not limited only to: If the internal exposure is determined, employment in the control area within the meaning of Section 40 (3) may only be permitted. In the case of application of the regulations referred to in the first sentence, the operating manager shall be in accordance with Section 3 (1) of the Regulation on the Safeguarding of Nuclear Safety and Radiation Protection of 11. October 1984 shall be the same as those responsible for radiation protection in accordance with § § 31 to 33. The responsible employee in accordance with § 3 (3) of the Regulation on the Safeguarding of Nuclear Safety and Radiation Protection of 11. October 1984 and the Commissioner for Control in accordance with Section 7 (2) of the Regulation on the Safeguarding of Nuclear Safety and Radiation Protection of 11 October 1984. October 1984 shall be the same as the radiation protection officer in accordance with § § 31 to 33. The plants and facilities of the uranium ore mining industry are the same as plants and facilities according to § 15 of this Regulation. The corresponding provisions of the occupational radiation protection schemes referred to in paragraph 1 (1) and (2) shall be repeal. (3) For the monitoring of emissions and immission in the decommissioning and refurbishment of the operating facilities, and The premises of uranium ore mining are to be applied in accordance with Article 48 (1), (2) and (4). (4) For occupational radiation protection of workers, the reorganization of the legacy of previous activities and work shall be carried out in accordance with the provisions of Article 3 of the The provisions of Part 3, Chapters 1 and 2, with the exception of § 95 (2) sentence 3 and 4, para. 4 sentence 3 and 4, § 96 (1) sentence 2, para. 3 sentence 1, first alternative corresponding application. Radon 222 exposure is to be converted into a value of the effective dose. An indication in accordance with Article 95 (2) sentence 1 shall not be required if the refurbishment is carried out on the basis of a permit in accordance with the regulations referred to in paragraphs 1 and 2. Paragraph 1 shall also apply to the restoration of the legacy of previous activities and work within the other scope of this Regulation. (5) By way of derogation from paragraph 1, the provisions of Chapter 3 of Part 3 shall apply mutatily if: Residues within the meaning of Annex XII, Part A, or other materials as defined in § 102 of the legacies of previous activities and works, or from the decommissioning and remediation of the plants and premises of the uranium ore mining industry, of the polluted land, also for the purpose of refurbishment of the land, are removed, it is because the residues or materials are used in the remediation of other legacies. This also applies to residues resulting from the remediation of previous activities and works falling within the scope of this Regulation. (6) (omitted) Unofficial table of contents

Annex I (to § § 8, 12, 17, 21)
Approval-free activities

(Fundstelle: BGBl. I 2001, 1766;
with regard to of the individual amendments. Footnote) Part A:
The use of substances in humans is free of approval in accordance with § 8 (1) if the specific activity of the substances does not exceed 500 microbecquerels per gram. Part B:
Licence-free according to § 8 (1), § 17 (1) or § 21

1.: the handling of substances the activity of which does not exceed the free limits of Annex III, Table 1, column 2;
2.: the handling of substances the specific activity of which does not exceed the free limits of Annex III, Table 1, column 3;
3.: the use, storage and disposal of medicinal products placed on the market in accordance with the second sentence of Article 2 (1) of the Regulation on radioactive medicinal products or medicinal products treated with ionising radiation (AMRadV),
4.: the use of devices whose design is authorised in accordance with Section 25 in conjunction with Annex V, Part A, with the exception of the installation, removal or maintenance of such devices,
5.: the storage of devices of which the type is authorised in accordance with § 25 in conjunction with Annex V, Part A, provided that the total activity of the radioactive substances does not exceed a thousandfold of the free limits laid down in Annex III, Table 1, column 2;
6.: the extraction, use and storage of noble gases obtained from the air, if the isotope ratio in the gas corresponds to that in the air; or
7.: the use and storage of consumer goods, of medicinal products within the meaning of the Medicines Act, of plant protection products within the meaning of the Plant Protection Act, of pesticides and of substances according to § 1 (1) to (5) of the Fertiliser Act, the manufacture of which is approved in accordance with § 106 or its shipment pursuant to § 108, or the manufacture of which is not authorized pursuant to Section 106 (3) or the shipment of which requires no authorization pursuant to § 108 sentence 2 or 3; § 95 in conjunction with Annex XI, Part B shall remain unaffected.

Part C:
Approval and display-free according to § 12a is the operation of plants, the

1.: the type referred to in § 25, in conjunction with Annex V, Part B, is approved; or
2.: The potential difference is not more than 30 kilovolts and in which under normal operating conditions the local dose rate does not exceed 1 microsievert by hour at a distance of 0.1 metres from the touchable surface.

Unofficial table of contents

Annex II (to § § 9, 14, 107)
Documents required for examination of permit applications

Source of the original text: BGBl. I 2001, 1767 Part A: Application documents for approvals according to § § 7 and 106

1.: Plans, drawings and descriptions necessary for the examination of the conditions of approval,
2.: information to verify that the conditions set out in Article 9 (1) (3), (5), (8) and (9) are met,
3.: information enabling the protection of the radiation protection officer and the radiation protection officer to be examined in the light of the reliability and the required technical knowledge,
4.: proof of the provision for the fulfilment of statutory claims for damages,
5.: in connection with the application in the human person, information which makes it possible to ascertain whether the conditions of Section 9 (3) are met,
6.: in connection with the application to the animal, information which makes it possible to ascertain whether the conditions set out in Article 9 (4) are met and
7.: In connection with the use of radioactive substances in medical devices in medicine as defined in the Medical Devices Act, information on the purpose of the irradiation device, which makes it possible to check whether the medical device is intended for use in the medical device. the intended use is appropriate.

Part B: Application documents for authorisations pursuant to § 11 (2)

1.: A safety report describing the plant and its operations and presenting the site plans and summary drawings, as well as the effects and risks associated with the plant and the operation, and which are described in section 14 (1) (5) of the German law. of equipment and measures to be provided,
2.: supplementary plans, drawings and descriptions of the installation and its parts,
3.: information to verify that the conditions set out in Article 14 (1) (3), (8) and (9) are met,
4.: information enabling the protection of the radiation protection officer and the radiation protection officer to be examined in the light of the reliability and the required technical knowledge,
5.: proof of the provision for the fulfilment of statutory claims for damages,
6.: in connection with the application to the human person, information enabling the examination to be carried out as to whether the requirements of section 14 (2) are met,
7.: in connection with the application to the animal in the veterinary medicinal product, information enabling the test to be carried out as to whether the conditions set out in Article 14 (3) are met and
8.: in connection with the operation of installations for the production of ionizing radiation in medicine, as defined in the Medical Devices Act, information on the purpose of the plant to check whether the medical device is intended for use in the intended use is suitable.

Unofficial table of contents

Annex III (to § § 3, 8, 10, 18, 20, 29, 43, 44, 45, 50, 53, 65, 66, 68, 70, 71, 105, 106, 107, 117)
Free limits, free values for different release types, values of surface contamination, list of radionuclides in radioactive equilibrium

(Fundstelle: BGBl. I 2001, 1768-1801;
with regard to of the individual amendments. Footnote)

Table 1: Free limits, free values for different release methods, values of surface contamination

Explanation of column 1:

Radionuclides with the label:

a)

"+", "+ +" or "sec" are the parent nuclides in equilibrium with the daughter nuclides indicated in Table 2; the exposure to radiation by these daughter nuclides is already available at the free limits, free-gas values or values of surface contamination. ,

b)

"*)" are not limited to naturally occurring radionuclides,

c)

"**)"

: Uran in the chemical form UO3, UF4, UCI4 and hexavalent uranium compounds,

d)

"***)"

: Uran in all the compounds not mentioned under **).

Explanation of columns 2 and 3:

In the case of a plurality of radionuclides, the sum of the ratios of the present activity (Ai) or specific activity (Ci) and the respective free limits FGi of the individual radionuclides according to column 2 or 3 shall be calculated (summary formula), where i is the respective radionuclides. This sum shall not exceed 1:

Radionuclides do not need to be taken into account in the sum formation if the proportion of the unaccounted nuclides in the total sum of the associated ratios Ai/FGi or Ci/FGi does not give the relative error of the total sum of 10% exceeds.

If no free limits are given in columns 2 or 3 for radionuclides, these are to be calculated on a case-by-case basis. Otherwise, the following values of the free limits may be used:

a): for alpha-radionuclides or radionuclides which decompose by spontaneous fission: 10 ³ Bq and 1 Bq/g,
b): for beta and gamma-ray radiators, unless they are referred to in point (c): 10 ⁵ Bq and 10 ² Bq/g,
c): for electron capture radiators and beta radiators with a maximum beta-limit energy of 0.2 mega-electronvolts: 10 ⁸Bq and 10 ⁵ Bq/g.

Explanation of column 3a:

The values of column 3a are those activity values when a radioactive substance enclosed is a highly radioactive radiation source (HRQ) within the meaning of section 3 (2) (29) (b) (bb). The HRQ value is 1/100 of the A1 value of section 2.2.7.2.2.1 of the Appendix to the publication of the recast of Annexes A and B to the European Convention on the International Carriage of Dangerous Goods by Road (ADR) of 25 June 2007. November 2010 (BGBl. II p. 1412-investment band). To the extent that no value is given in column 3a for a radionuclide, one hundredth of the A1 value shall be used.

Explanation of column 4:

In the case of measurements in accordance with § 44, the averaging area shall be up to 300 cm2.

In the case of a plurality of radionuclides, the sum of the ratios of the existing activity per unit area (As, i) and the respective values of the surface contamination (Oi) of the individual radionuclides according to Table 1, column 4 shall be calculated (empirical formula), wherein i is the respective radionuclide. This sum shall not exceed 1:

Radionuclides need not be taken into account in the sum formation if the proportion of the unaccounted nuclides in the total sum of the associated ratio numbers As, i/Oi does not exceed the relative error of the total sum of 10%.

In determining the surface contamination for traffic areas or jobs in accordance with § 44 (2) (1) and (2), the festive surface activity and the activity which has penetrated the surface shall not be included, provided that it is ensured. is that it is not possible to endanger the activity of this activity as a result of redistribution or inclusion.

If no maximum permitted surface contamination levels are indicated for radionuclides, these are to be calculated on a case-by-case basis. Otherwise, the following values of surface contamination may be used:

a): for alpha-radionuclides or radionuclides, which decay by spontaneous fission: 0.1 Bq/cm ²,
b): for beta and gamma-ray radiators, unless they are referred to in point (c): 1 Bq/cm ²,
c): for electron capture radiators and beta radiators with a maximum beta-limit energy of 0.2 mega-electronvolts: 100 Bg/cm ².

Explanation of column 5:

In the case of measurements in accordance with § 44, M: 3 kg ≤ M ≤ 300 kg shall apply to the underlying mean mass M: For a mass < 3 kg, the specific activity is not to be determined separately for measurements according to § 44. If the mass to be expected in the calendar year is less than 100 tonnes, in the case of those radionuclides in which the free values of column 5 are marked with a high one, the free values of Table 3 may be used instead of The free values of Table 1, column 5, of a clearance are used.

Explanation of columns 6 and 9a to 9d:

The term "t/a" shall be used as an abbreviation for "tonnes in the calendar year".

Explanation of column 8 and 10:

The values of surface contamination take into account the activity that has penetrated into the topmost layer of the soil or the building; it is an activity value projected onto the surface.

Explanations of columns 5 to 10a can be found in § 29 and Annex IV.

²

²

²
Table 1 Free limits, surface contamination values and free values Release Radionuclide free limit unrestricted release of half-life Activity in Bqspecific activity in Bq/gActivity HRQ/1/ 100 A1 in BqSurface contamination in Bq/cm Solid and liquid substances in Bq/gBauschutt, ground excavation of more than 1 000 t/a in Bq/gGround areas in Bq/gBuildings Again-, onward-application in Bq/cm fixed Substances up to 100 t/a for disposal in landfill sites in Bq/gsolid and liquid substances up to 100 t/a for disposal in incinerator, in Bq/gFixed Substances up to 1 000 t/a for disposal in landfill sites In Bq/gsolid and liquid substances up to 1 000 t/a for disposal in combustion applications. in Bq/gBuildings for demoliation in Bq/cm Metal scrap for recycle in Bq/g 1233a456789a9b9c9d1010a11

H-3

1 E + 9

1 E + 6

4 E + 11

1 E + 2

1 E + 3

6 E + 1

1 E + 3

6 E + 4

1 E + 6

6 E + 3

1 E + 6

4 E + 3

1 E + 3

12.3

Be-7

1 E + 7

1 E + 3

2 E + 11

1 E + 2

3 E + 1

8 E + 1

3 E + 2

4 E + 2

9 E + 1

4 E + 1

6 E + 2

3 E + 2

53.3

Be-10

1 E + 6

1 E + 4

1.6E + 6

C-11

1 E + 6

1 E + 1

20.4

C-11
Monoxide,
Dioxide

1 E + 9

1 E + 1

20.4

C-14

1 E + 7

1 E + 4

4 E + 11

1 E + 2

8 E + 1

1 E + 1

4 E-2

1 E + 3

4 E + 3

1 E + 4

4 E + 2

1 E + 4

6 E + 3

8 E + 1

5.7E + 3

C-14
Monoxide

1 E + 11

1 E + 8

5.7E + 3

C-14
Dioxide

1 E + 11

1 E + 7

5.7E + 3

N-13

1 E + 9

1 E + 2

< 10

O-15

1 E + 9

1 E + 2

< 10

F-18

1 E + 6

1 E + 1

2 E + 4

1 E + 1

109.7

Ne-19

1 E + 9

1 E + 2

< 10

Na-22

1 E + 6

1 E + 1

5 E + 9

1 E-1

4 E-3

4 E-1

1 E-1

2.6

Na-24

1 E + 5

1 E + 1

2 E + 9

1 E + 1

7 E + 2

1 E + 1

15.0

Mg-28 +

1 E + 5

1 E + 1

20.9

Al-26

1 E + 5

1 E + 1

7,2E + 5

Si-31

1 E + 6

1 E + 3

6 E + 9

1 E + 2

1 E + 3

1 E + 2

2 E + 7

1 E + 3

2.6

Si-32

1 E + 6

1 E + 3

4 E + 11

4 E + 2

1 E + 3

4 E + 2

9 E + 2

101.0

P-32

1 E + 5

1 E + 3

5 E + 9

1 E + 2

2 E + 1

2 E-2

1 E + 2

1 E + 3

4 E + 5

2 E + 1

14.3

P-33

1 E + 8

1 E + 5

4 E + 11

1 E + 2

2 E + 2

8 E-2

1 E + 3

1 E + 5

2 E + 4

1 E + 5

6 E + 5

2 E + 2

25.3

S-35

1 E + 8

1 E + 5

4 E + 11

1 E + 2

6 E + 1

5 E + 2

1 E-2

1 E + 3

5 E + 3

2 E + 4

5 E + 2

2 E + 3

2 E + 5

6 E + 2

87.5

S-35
organic

1 E + 8

1 E + 5

87.5

S-35
Gas

1 E + 9

1 E + 6

87.5

Cl-36

1 E + 6

1 E + 4

1 E + 11

1 E + 2

3 E-1

¹⁾

3 E-1

3 E + 1

3 E-1

3 E + 1

1 E + 1

3.0E + 5

Cl-38

1 E + 5

1 E + 1

2 E + 9

1 E + 1

2 E-1

4 E + 4

1 E + 1

37,2

Cl-39

1 E + 5

1 E + 1

56.0

Ar-37

1 E + 8

1 E + 6

4 E + 11

35.0

Ar-39

1 E + 4

1 E + 7

269.0

Ar-41

1 E + 9

1 E + 2

3 E + 9

1.8

K-40 *)

1 E + 6

1 E + 2

9 E + 9

1 E + 1

8 E-1

2 E + 1

1,3E + 9

K-42

1 E + 6

1 E + 2

2 E + 9

1 E + 1

1 E + 2

8 E-1

1 E + 1

1 E + 4

1 E + 2

12.4

K-43

1 E + 6

1 E + 1

7 E + 9

1 E + 1

2 E-1

2 E + 3

1 E + 1

22.2

K-44

1 E + 5

1 E + 1

22.2

K-45

1 E + 5

1 E + 1

17.8

Ca-41

1 E + 7

1 E + 5

2 E + 1

2 E + 2

1 E + 3

2 E + 1

1 E + 2

1,0E + 5

Ca-45

1 E + 7

1 E + 4

4 E + 11

1 E + 2

7 E + 1

4 E + 2

4 E-2

1 E + 3

5 E + 3

1 E + 4

5 E + 2

4 E + 3

6 E + 4

6 E + 2

163.0

Ca-47

2 E-1

4 E + 2

4.5

Ca-47 +

1 E + 6

1 E + 1

3 E + 10

1 E + 1

4.5

Sc-43

1 E + 6

1 E + 1

3.9

Sc-44

1 E + 5

1 E + 1

2.4

Sc-44m

1 E + 7

1 E + 2

3.9

Sc-46

1 E + 6

1 E + 1

5 E + 9

3 E-1

1 E-1

4 E-2

1 E + 1

3 E-1

83.8

Sc-47

1 E + 6

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

6 E + 3

1 E + 2

3.4

Sc-48

1 E + 5

1 E + 1

3 E + 9

1 E + 1

7 E-2

3 E + 2

1 E + 1

43.7

Sc-49

1 E + 5

1 E + 3

57.2

Ti-44 +

1 E + 5

1 E + 1

47.3

Ti-45

1 E + 6

1 E + 1

3.1

V-47

1 E + 5

1 E + 1

32.6

V-48

1 E + 5

1 E + 1

4 E + 9

8 E-2

3 E-2

4 E + 1

16.0

V-49

1 E + 7

1 E + 4

330.0

Cr-48

1 E + 6

1 E + 2

21.6

Cr-49

1 E + 6

1 E + 1

42.0

Cr-51

1 E + 7

1 E + 3

3 E + 11

1 E + 2

5 E + 2

9 E + 2

1 E + 2

2 E + 3

1 E + 3

27.7

Mn-51

1 E + 5

1 E + 1

2 E-1

5 E + 4

1 E + 1

46.2

Mn-52

1 E + 5

1 E + 1

3 E + 9

1 E + 1

6 E-2

9 E + 1

1 E + 1

5.6

Mn-52m

1 E + 5

1 E + 1

9 E-2

5 E + 4

1 E + 1

21.0

Mn-53

1 E + 9

1 E + 4

1 E + 2

6 E + 1

¹)

6 E + 1

1 E + 3

6 E + 2

4 E + 3

6 E + 1

4 E + 2

2 E + 4

1 E + 4

3.7E + 6

Mn-54

1 E + 6

1 E + 1

1 E + 10

4 E-1

3 E-1

9 E-2

1 E + 1

312.2

Mn-56

1 E + 5

1 E + 1

3 E + 9

1 E + 1

1 E-1

9 E + 3

1 E + 1

2.6

Fe-52

1 E + 6

1 E + 1

3 E + 9

1 E + 2

1 E + 1

7 E-2

2 E + 3

1 E + 1

8.3

Fe-55

1 E + 6

1 E + 4

4 E + 11

1 E + 2

2 E + 2

1 E + 3

1 E + 4

7 E + 3

1 E + 4

2 E + 4

1 E + 4

2.7

Fe-59

1 E + 6

1 E + 1

9 E + 9

2 E-1

6 E-2

1 E + 1

3 E + 1

1 E + 1

45.1

Fe-60 +

1 E + 5

1 E + 2

1,0E + 5

Co-55

1 E + 6

1 E + 1

5 E + 9

1 E + 1

1 E-1

1 E + 3

1 E + 1

17.5

Co-56

1 E + 5

1 E + 1

2 E-1

6 E-2

2 E-2

0.4

78.8

Co-57

1 E + 6

1 E + 2

1 E + 11

1 E + 1

2 E + 1

8 E-1

1 E + 1

1 E + 2

5 E + 1

1 E + 2

2 E + 1

271.3

Co-58

1 E + 6

1 E + 1

1 E + 10

9 E-1

2 E-1

8 E-2

1 E + 1

3 E + 1

70.8

Co-58m

1 E + 7

1 E + 4

4 E + 11

1 E + 2

1 E + 4

1 E + 3

1 E + 9

1 E + 4

8.9

Co-60

1 E + 5

1 E + 1

4 E + 9

1 E-1

9 E-2

3 E-2

4 E-1

0.6

5.3

Co-60m

1 E + 6

1 E + 3

1 E + 2

1 E + 3

6 E + 1

1 E + 3

7 E + 7

1 E + 3

10.5

Co-61

1 E + 6

1 E + 2

1 E + 1

1 E + 2

1 E + 1

5 E + 5

1 E + 2

1.7

Co-62m

1 E + 5

1 E + 1

8 E-2

7 E + 4

1 E + 1

14.0

Ni-56

1 E + 6

1 E + 1

6.1

Ni-57

1 E + 6

1 E + 1

3.6E + 1

Ni-59

1 E + 8

1 E + 4

1 E + 2

3 E + 2

¹⁾

3 E + 2

1 E + 3

3 E + 3

1 E + 4

3 E + 2

3 E + 3

9 E + 4

1 E + 4

7.5E + 4

Ni-63

1 E + 8

1 E + 5

4 E + 11

1 E + 2

3 E + 2

1 E + 3

1 E + 4

6 E + 4

1 E + 3

6 E + 3

4 E + 4

1 E + 4

100.0

Ni-65

1 E + 6

1 E + 1

4 E + 9

1 E + 1

4 E-1

1 E + 1

3 E + 4

1 E + 1

2.5

Ni-66

1 E + 7

1 E + 4

54.6

Cu-60

1 E + 5

1 E + 1

23.0

Cu-61

1 E + 6

1 E + 1

3.4

Cu-64

1 E + 6

1 E + 2

6 E + 10

1 E + 1

1 E + 2

1 E + 1

2 E + 4

1 E + 2

12.7

Cu-67

1 E + 6

1 E + 2

61.9

Zn-62

1 E + 6

1 E + 2

9.1

Zn-63

1 E + 5

1 E + 1

38.1

Zn-65

1 E + 6

1 E + 1

2 E + 10

5 E-1

4 E-1

1 E-2

1 E + 1

2 E + 1

5 E-1

244.0

Zn-69

1 E + 6

1 E + 4

3 E + 10

1 E + 2

1 E + 4

1 E + 2

7 E + 9

1 E + 4

56.0

Zn-69m

6 E-1

1 E + 1

7 E + 3

13.8

Zn-69m +

1 E + 6

1 E + 2

3 E + 10

1 E + 1

1 E + 2

7 E + 3

1 E + 2

13.8

Zn-71m

1 E + 6

1 E + 1

3.9

Zn-72

1 E + 6

1 E + 2

46.5

Ga-65

1 E + 5

1 E + 1

15.0

Ga-66

1 E + 5

1 E + 1

9.4

Ga-67

1 E + 6

1 E + 2

78.3

Ga-68

1 E + 5

1 E + 1

68.3

Ga-70

1 E + 6

1 E + 3

21.2

Ga-72

1 E + 5

1 E + 1

4 E + 9

1 E + 1

8 E-2

1 E + 3

1 E + 1

14.1

Ga-73

1 E + 6

1 E + 2

4.9

Ge-66

1 E + 6

1 E + 1

2.3

Ge-67

1 E + 5

1 E + 1

18.7

Ge-68 +

1 E + 5

1 E + 1

270.8

Ge-69

1 E + 6

1 E + 1

39,0

Ge-71

1 E + 8

1 E + 4

4 E + 11

1 E + 2

4 E + 3

5 E + 1

1 E + 3

1 E + 4

9 E + 7

4 E + 3

11.2

Ge-75

1 E + 6

1 E + 3

83.0

Ge-77

1 E + 5

1 E + 1

11.3

Ge-78

1 E + 6

1 E + 2

88.0

As-69

1 E + 5

1 E + 1

15.1

As-70

1 E + 5

1 E + 1

53.0

As-71

1 E + 6

1 E + 1

64.0

As-72

1 E + 5

1 E + 1

26.0

As-73

1 E + 7

1 E + 3

4 E + 11

1 E + 2

4 E + 1

4 E + 2

1 E + 3

2 E + 4

1 E + 2

80.3

As-74

1 E + 6

1 E + 1

1 E + 10

¹⁾

3 E-1

1 E-1

1 E + 1

1 E + 2

1 E + 1

17.8

As-76

1 E + 5

1 E + 2

3 E + 9

1 E + 1

1 E + 2

5 E-1

1 E + 1

4 E + 3

1 E + 2

26.4

As-77

1 E + 6

1 E + 3

2 E + 11

1 E + 2

1 E + 3

3 E + 1

1 E + 2

1 E + 5

1 E + 3

38.8

As-78

1 E + 5

1 E + 1

1.5

Se-70

1 E + 6

1 E + 1

41.1

Se-73

1 E + 6

1 E + 1

7.1

Se-73m

1 E + 6

1 E + 2

39,0

Se-75

1 E + 6

1 E + 2

3 E + 10

1 E + 1

7 E-1

4 E-3

4 E + 1

7 E + 1

1 E + 1

5 E + 1

120,0

Se-79

1 E + 7

1 E + 4

6.5E + 4

Se-81

1 E + 6

1 E + 3

18.0

Se-81m

1 E + 7

1 E + 3

57.3

Se-83

1 E + 5

1 E + 1

22.4

Br-74

1 E + 5

1 E + 1

25.3

Br-74m

1 E + 5

1 E + 1

41.5

Br-75

1 E + 6

1 E + 1

1.6

Br-76

1 E + 5

1 E + 1

16.0

Br-77

1 E + 6

1 E + 2

57.0

Br-80

1 E + 5

1 E + 2

17.6

Br-80m

1 E + 7

1 E + 3

4.4

Br-82

1 E + 6

1 E + 1

4 E + 9

1 E + 1

4 E + 2

1 E + 1

35.3

Br-83

1 E + 6

1 E + 3

2.4

Br-84

1 E + 5

1 E + 1

31.8

Kr-74

1 E + 9

1 E + 2

11.5

Kr-76

1 E + 9

1 E + 2

14.6

Kr-77

1 E + 9

1 E + 2

1.2

Kr-79

1 E + 5

1 E + 3

34.9

Kr-81

1 E + 7

1 E + 4

4 E + 11

2.1E + 5

Kr-81m

1 E + 10

1 E + 3

1.3E + 1

Kr-83m

1 E + 12

1 E + 5

1.8

Kr-85

1 E + 4

1 E + 5

1 E + 11

10.8

Kr-85m

1 E + 10

1 E + 3

8 E + 10

4.5

Kr-87

1 E + 9

1 E + 2

2 E + 9

76.3

Kr-88

1 E + 9

1 E + 2

2.8

Rb-79

1 E + 5

1 E + 1

23.0

Rb-81

1 E + 6

1 E + 1

4.6

Rb-81m

1 E + 7

1 E + 3

30.3

Rb-82m

1 E + 6

1 E + 1

6.3

Rb-83 +

1 E + 6

1 E + 2

86.2

Rb-84

1 E + 6

1 E + 1

32.8

Rb-86

1 E + 5

1 E + 2

5 E + 9

1 E + 1

2 E + 1

5 E-2

1 E + 1

1 E + 2

6 E + 1

1 E + 3

2 E + 1

18.7

Rb-87 *)

1 E + 7

1 E + 4

4,8E + 10

Rb-88

1 E + 5

1 E + 1

17.8

Rb-89

1 E + 5

1 E + 1

15.2

Sr-80

1 E + 7

1 E + 3

1.8

Sr-81

1 E + 5

1 E + 1

22.2

Sr-82 +

1 E + 5

1 E + 1

25.5

Sr-83

1 E + 6

1 E + 1

32.4

Sr-85

1 E + 6

1 E + 2

2 E + 10

4 E-1

1 E-1

3 E + 1

4 E + 1

5 E + 1

64.9

Sr-85m

1 E + 7

1 E + 2

5 E + 10

1 E + 1

1 E + 2

1 E + 1

2 E + 5

1 E + 2

67.7

Sr-87m

1 E + 6

1 E + 2

3 E + 10

1 E + 1

1 E + 2

7 E-1

1 E + 1

5 E + 4

1 E + 2

2.8

Sr-89

1 E + 6

1 E + 3

1 E + 2

2 E + 1

3 E-2

1 E + 1

1 E + 3

7 E + 4

2 E + 1

50.5

Sr-90 +

1 E + 4

1 E + 2

3 E + 9

6 E-1

¹⁾

6 E-1

2 E-3

3 E + 1

4 E + 1

6 E-1

3 E + 1

28,5

Sr-91

1 E + 5

1 E + 1

3 E + 9

1 E + 1

3 E-1

1 E + 1

6 E + 3

1 E + 1

9.5

Sr-92

1 E + 6

1 E + 1

1 E + 10

1 E + 1

2 E-1

1 E + 4

1 E + 1

2.7

Y-86

1 E + 5

1 E + 1

14.7

Y-86m

1 E + 7

1 E + 2

48,0

Y-87 +

1 E + 6

1 E + 1

80.3

Y-88

1 E + 6

1 E + 1

106.6

Y-90

1 E + 5

1 E + 3

3 E + 9

1 E + 2

1 E + 3

6 E + 2

1 E + 2

2 E + 6

1 E + 3

64.1

Y-91

1 E + 6

1 E + 3

6 E + 9

1 E + 2

2 E + 1

1 E + 2

1 E + 3

5 E + 4

3 E + 1

58.5

Y-91m

1 E + 6

1 E + 2

2 E + 10

1 E + 2

4 E-1

1 E + 1

9 E + 4

1 E + 2

49,7

Y-92

1 E + 5

1 E + 2

1 E + 1

1 E + 2

9 E-1

1 E + 1

5 E + 4

1 E + 2

3.5

Y-93

1 E + 5

1 E + 2

1 E + 1

1 E + 2

1 E + 1

4 E + 4

1 E + 2

10.1

Y-94

1 E + 5

1 E + 1

18.7

Y-95

1 E + 5

1 E + 1

10.3

Zr-86

1 E + 7

1 E + 2

16.5

Zr-88

1 E + 6

1 E + 2

83.4

Zr-89

1 E + 6

1 E + 1

78.4

Zr-93

1 E + 2

1 E + 1

2 E + 1

1 E + 2

8 E + 2

8 E + 3

8 E + 1

8 E + 2

3 E + 3

1 E + 1

1.5E + 6

Zr-93 +

1 E + 7

1 E + 3

1 E + 2

1 E + 1

8 E + 2

1 E + 3

8 E + 1

8 E + 2

1 E + 1

1.5E + 6

Zr-95

1 E + 6

1 E + 1

2 E + 10

5 E-1

9 E-2

1 E-1

1 E + 1

2 E + 1

6 E-1

64.0

Zr-97

1 E-1

1 E + 3

16.8

Zr-97 +

1 E + 5

1 E + 1

4 E + 9

1 E + 1

16.8

Nb-88

1 E + 5

1 E + 1

14.3

Nb-89

1 E + 5

1 E + 1

2.0

Nb-90

1 E + 5

1 E + 1

14.6

Nb-93m

1 E + 7

1 E + 4

4 E + 11

1 E + 2

4 E + 2

5 E + 2

1 E + 4

4 E + 3

1 E + 4

4 E + 4

4 E + 2

16.1

Nb-94

1 E + 6

1 E + 1

7 E + 9

2 E-1

1 E-1

5 E-2

5 E-1

1 E + 1

4 E-1

2.0E + 4

Nb-95

1 E + 6

1 E + 1

1 E + 10

3 E-1

1 E-1

1 E + 1

6 E + 1

1 E + 1

35.0

Nb-97

1 E + 6

1 E + 1

9 E + 9

1 E + 1

3 E-1

1 E + 1

5 E + 4

1 E + 1

74.0

Nb-98

1 E + 5

1 E + 1

9 E-2

2 E + 4

1 E + 1

51.0

Mon-90

1 E + 6

1 E + 1

3 E-1

9 E + 3

1 E + 1

5.7

Mon-93

1 E + 8

1 E + 3

4 E + 11

1 E + 2

¹⁾

2 E-1

8 E + 1

4 E + 1

3 E + 2

3 E + 1

2 E + 3

2 E + 2

3.5E + 3

Mon-99

1 E + 6

1 E + 2

1 E + 10

1 E + 1

1 E + 2

1 E + 1

4 E + 3

1 E + 2

66.0

Mon-101

1 E + 6

1 E + 1

2 E-2

2 E + 4

14.6

Mo-101 +

1 E + 1

14.6

Tc-93

1 E + 6

1 E + 1

2.7

Tc-93m

1 E + 6

1 E + 1

43.5

Tc-94

1 E + 6

1 E + 1

4.9

Tc-94m

1 E + 5

1 E + 1

53.0

Tc-95

1 E + 6

1 E + 1

20.0

Tc-95m +

1 E + 6

1 E + 1

60.0

Tc-96

1 E + 6

1 E + 1

4 E + 9

1 E + 1

9 E-2

2 E + 2

1 E + 1

4.3

Tc-96m

1 E + 7

1 E + 3

4 E + 9

1 E + 2

1 E + 3

1 E + 2

1 E + 6

1 E + 3

52.0

Tc-97

1 E + 8

1 E + 3

1 E + 2

¹⁾

8 E-2

8 E + 1

7 E + 1

6 E + 1

7 E + 2

4 E + 2

4.0E + 6

Tc-97m

1 E + 7

1 E + 3

4 E + 11

1 E + 2

8 E + 1

1 E-2

1 E + 2

1 E + 3

2 E + 2

3 E + 2

5 E + 2

1 E + 3

92.2

Tc-99

1 E + 7

1 E + 4

4 E + 11

1 E + 2

6 E-1

¹⁾

6 E-1

7 E + 1

7 E-1

6 E-1

7 E + 1

4 E + 1

2.1E + 5

Tc-99m

1 E + 7

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

7 E + 4

1 E + 2

6.0

Tc-101

1 E + 6

1 E + 2

14.2

Tc-104

1 E + 5

1 E + 1

18.2

Ru-94

1 E + 6

1 E + 2

51.8

Ru-97

1 E + 7

1 E + 2

5 E + 10

1 E + 1

1 E + 2

1 E + 1

3 E + 3

1 E + 2

2.9

Ru-103 +

1 E + 6

1 E + 2

2 E + 10

1 E + 1

2 E-1

1 E + 1

3 E + 1

5 E + 1

1 E + 1

9 E + 1

4 E + 1

39,3

Ru-105

1 E + 6

1 E + 1

1 E + 10

1 E + 1

3 E-1

1 E + 4

1 E + 1

4.4

Ru-106 +

1 E + 5

1 E + 2

2 E + 9

1 E + 1

3 E-1

7 E + 1

1 E + 2

2 E + 1

5 E + 1

373.6

Rh-99

1 E + 6

1 E + 1

4.7

Rh-99m

1 E + 6

1 E + 1

16.0

Rh-100

1 E + 6

1 E + 1

20.8

Rh-101

1 E + 7

1 E + 2

3.3

Rh-101m

1 E + 7

1 E + 2

4.4

Rh-102

1 E + 6

1 E + 1

206.0

Rh-102m

1 E + 6

1 E + 2

2.9

Rh-103m

1 E + 8

1 E + 4

4 E + 11

1 E + 2

1 E + 4

7 E + 3

1 E + 3

1 E + 9

1 E + 4

56.1

Rh-105

1 E + 7

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

2 E + 4

1 E + 2

35.5

Rh-106m

1 E + 5

1 E + 1

2.2

Rh-107

1 E + 6

1 E + 2

21.7

Pd-100

1 E + 7

1 E + 2

3.7

Pd-101

1 E + 6

1 E + 2

8.5

Pd-103 +

1 E + 8

1 E + 3

4 E + 11

1 E + 2

3 E + 2

2 E + 1

1 E + 2

1 E + 3

2 E + 5

3 E + 2

17.0

Pd-107

1 E + 8

1 E + 5

6.5E + 6

Pd-109

1 E + 6

1 E + 3

2 E + 10

1 E + 2

1 E + 3

3 E + 2

1 E + 2

5 E + 6

1 E + 3

13.4

Ag-102

1 E + 5

1 E + 1

13.0

Ag-103

1 E + 6

1 E + 1

1.1

Ag-104

1 E + 6

1 E + 1

69.2

Ag-104m

1 E + 6

1 E + 1

33.5

Ag-105

1 E + 6

1 E + 2

2 E + 10

5 E-1

1 E-1

1 E + 1

3 E + 1

4 E + 1

9 E + 1

4 E + 1

41.3

Ag-106

1 E + 6

1 E + 1

24.0

Ag-106m

1 E + 6

1 E + 1

8.3

Ag-108m +

1 E + 6

1 E + 1

7 E + 9

2 E-1

1 E-1

7 E-3

5 E-1

1 E + 1

8 E-1

127.0

Ag-110m

1 E + 6

1 E + 1

4 E + 9

8 E-2

5 E-1

249.9

Ag-110m +

1 E-1

8 E-2

7 E-3

5 E-1

6 E-1

5 E-1

249.9

Ag-111

1 E + 6

1 E + 3

1 E + 2

4 E + 1

4 E-1

1 E + 2

7 E + 2

1 E + 3

2 E + 2

9 E + 3

4 E + 1

7.5

Ag-112

1 E + 5

1 E + 1

3.1

Ag-115

1 E + 5

1 E + 1

20.0

Cd-104

1 E + 7

1 E + 2

57.7

Cd-107

1 E + 7

1 E + 3

6.5

Cd-109 +

1 E + 6

1 E + 4

3 E + 11

1 E + 2

2 E + 1

3 E-2

4 E + 1

8 E + 2

4 E + 3

8 E + 1

4 E + 2

4 E + 3

2 E + 1

453.0

Cd-113 *)

1 E + 6

1 E + 3

9,0E + 15

Cd-113m

1 E + 6

1 E + 3

14.6

Cd-115

1 E + 6

1 E + 2

3 E + 10

1 E + 1

1 E + 2

6 E-1

1 E + 1

2 E + 3

1 E + 2

53.4

Cd-115m

1 E + 6

1 E + 3

5 E + 9

1 E + 1

4 E-2

1 E + 2

7 E + 2

2 E + 2

7 E + 1

2 E + 3

44,8

Cd-115m +

1 E + 2

2 E + 1

7 E + 2

2 E + 2

7 E + 1

2 E + 1

44,8

Cd-117

1 E + 6

1 E + 1

2.4

Cd-117m

1 E + 6

1 E + 1

3.3

In-109

1 E + 6

1 E + 1

4.2

In-110

1 E + 5

1 E + 1

69.1

In-111

1 E + 6

1 E + 2

3 E + 10

1 E + 1

1 E + 2

7 E-1

1 E + 1

2 E + 3

1 E + 2

2.8

In-112

1 E + 6

1 E + 2

14.4

In-113m

1 E + 6

1 E + 2

4 E + 10

1 E + 1

1 E + 2

9 E-1

1 E + 1

1 E + 5

1 E + 2

99.5

In-114

1 E + 5

1 E + 3

< 10

In-114m +

1 E + 6

1 E + 2

1 E + 11

1 E + 1

3 E-2

1 E + 1

1 E + 2

4 E + 1

2 E + 1

3 E + 2

1 E + 1

49.5

In-115 *)

1 E + 6

1 E + 2

4,0E + 14

In-115m

1 E + 6

1 E + 2

7 E + 10

1 E + 1

1 E + 2

1 E + 1

6 E + 4

1 E + 2

4.5

In-116m

1 E + 5

1 E + 1

54.0

In-117

1 E + 6

1 E + 1

43.1

In-117m

1 E + 6

1 E + 2

1.9

In-119m

1 E + 5

1 E + 2

18.0

Sn-110

1 E + 7

1 E + 2

4.0

Sn-111

1 E + 6

1 E + 2

35.3

Sn-113

1 E + 7

1 E + 3

4 E + 10

1 E + 1

9 E-1

7 E + 1

115,1

Sn-113 +

1 E + 1

9 E-1

1 E-1

6 E + 1

8 E + 1

2 E + 1

7 E + 1

115,1

Sn-117m

1 E + 6

1 E + 2

13.6

Sn-119m

1 E + 7

1 E + 3

293.0

Sn-121

1 E + 7

1 E + 5

27.0

Sn-121m +

1 E + 7

1 E + 3

50.0

Sn-123

1 E + 6

1 E + 3

129.2

Sn-123m

1 E + 6

1 E + 2

40.1

Sn-125

1 E + 5

1 E + 2

4 E + 9

1 E + 1

¹⁾

7 E-1

2 E-1

1 E + 1

6 E + 1

2 E + 1

6 E + 2

2 E + 1

9.6

Sn-126 +

1 E + 5

1 E + 1

1,0E + 5

Sn-127

1 E + 6

1 E + 1

2.1

Sn-128

1 E + 6

1 E + 1

59.1

Sb-115

1 E + 6

1 E + 1

32.1

Sb-116

1 E + 6

1 E + 1

16.0

Sb-116m

1 E + 5

1 E + 1

60.0

Sb-117

1 E + 7

1 E + 2

2.8

Sb-118m

1 E + 6

1 E + 1

5.0

Sb-119

1 E + 7

1 E + 3

38,5

Sb-120m

1 E + 6

1 E + 1

5.8

Sb-122

1 E + 4

1 E + 2

4 E + 9

1 E + 1

1 E + 2

5 E-1

1 E + 1

1 E + 3

1 E + 2

2.7

Sb-124

1 E + 6

1 E + 1

6 E + 9

5 E-1

4 E-2

9 E-1

2 E + 1

5 E-1

60.3

Sb-125 +

1 E + 6

1 E + 2

2 E + 10

1 E + 1

8 E-1

5 E-1

8 E-2

4 E + 1

1 E + 1

2 E + 1

2.8

Sb-126

1 E + 5

1 E + 1

12.4

Sb-126m

1 E + 5

1 E + 1

19.0

Sb-127

1 E + 6

1 E + 1

3.9

Sb-128m

1 E + 5

1 E + 1

9.0

Sb-129

1 E + 6

1 E + 1

4.3

Sb-130

1 E + 5

1 E + 1

40.0

Sb-131

1 E + 6

1 E + 1

23.0

Te-116

1 E + 7

1 E + 2

2.5

Te-121

1 E + 6

1 E + 1

16.8

Te-121m

1 E + 6

1 E + 2

154.0

Te-123 *)

1 E + 6

1 E + 3

1,2E + 13

Te-123m

1 E + 7

1 E + 2

8 E + 10

1 E + 1

7 E-3

1 E + 1

1 E + 2

4 E + 1

3 E + 1

2 E + 2

1 E + 1

119.7

Te-125m

1 E + 7

1 E + 3

2 E + 11

1 E + 2

6 E + 1

2 E-2

1 E + 2

1 E + 3

5 E + 2

1 E + 3

2 E + 4

6 E + 1

57.4

Te-127

1 E + 6

1 E + 3

2 E + 11

1 E + 2

1 E + 3

5 E + 1

1 E + 2

9 E + 5

1 E + 3

9.4

Te-127m +

1 E + 7

1 E + 3

2 E + 11

1 E + 2

2 E + 1

3 E + 1

1 E + 2

3 E + 2

1 E + 3

3 E + 1

3 E + 2

3 E + 3

5 E + 1

109.0

Te-129

1 E + 6

1 E + 2

7 E + 9

1 E + 1

1 E + 2

7 E + 5

1 E + 2

69.6

Te-129m +

1 E + 6

1 E + 3

8 E + 9

1 E + 1

2 E + 1

1 E + 1

2 E + 2

3 E + 2

7 E + 1

3 E + 1

8 E + 2

2 E + 1

33.6

Te-131

1 E + 5

1 E + 2

1 E + 1

1 E + 2

6 E-1

1 E + 1

3 E + 5

1 E + 2

25.0

Te-131m

1 E + 6

1 E + 1

7 E + 9

2 E-1

1 E + 3

30.0

Te-131m +

1 E + 1

30.0

Te-132

1 E + 7

1 E + 2

5 E + 9

1 E + 2

9 E-2

2 E + 2

1 E + 2

76.3

Te-133

1 E + 5

1 E + 1

2 E-1

2 E + 5

1 E + 1

12.5

Te-133m

1 E + 5

1 E + 1

9 E-2

2 E + 4

55.4

Te-133m +

1 E + 1

55.4

Te-134

1 E + 6

1 E + 1

3 E-1

7 E + 4

1 E + 1

41.8

I-120

1 E + 5

1 E + 1

1.4

I-120m

1 E + 5

1 E + 1

53.0

I-121

1 E + 6

1 E + 2

2.1

I-123

1 E + 7

1 E + 2

6 E + 10

1 E + 1

1 E + 2

1 E + 1

3 E + 4

1 E + 2

13.2

I-124

1 E + 6

1 E + 1

4.2

I-125

1 E + 6

1 E + 3

2 E + 11

1 E + 1

9 E-2

1 E + 1

8 E + 2

1 E + 3

8 E + 1

1 E + 2

1 E + 4

59.4

I-126

1 E + 6

1 E + 2

2 E + 10

1 E + 1

5 E-1

2 E-1

1 E + 1

4 E + 1

5 E + 1

1 E + 1

3 E + 2

13.0

I-128

1 E + 5

1 E + 2

25.0

I-129

1 E + 5

1 E + 2

6 E-2

¹⁾

6 E-2

6 E-1

6 E-2

4 E-1

1.6E + 7

I-130

1 E + 6

1 E + 1

2 E + 3

1 E + 1

12.4

I-131

1 E + 6

1 E + 2

3 E + 10

1 E + 1

6 E-1

2 E-1

1 E + 1

5 E + 1

7 E + 1

2 E + 1

6 E + 2

8.0

I-132

1 E + 5

1 E + 1

4 E + 9

1 E + 1

1 E-1

8 E + 3

1 E + 1

2.3

I-132m

1 E + 6

1 E + 2

83.6

I-133

1 E + 6

1 E + 1

7 E + 9

4 E-1

1 E + 1

3 E + 3

20.8

I-133 +

1 E + 1

20.8

I-134

1 E + 5

1 E + 1

3 E + 9

1 E + 1

8 E-2

2 E + 4

1 E + 1

52.0

I-135

1 E-1

4 E + 3

6.6

I-135 +

1 E + 6

1 E + 1

6 E + 9

1 E + 1

6.6

Xe-120

1 E + 9

1 E + 2

40.0

Xe-121

1 E + 9

1 E + 2

38.8

Xe-122 +

1 E + 9

1 E + 2

20.1

Xe-123

1 E + 9

1 E + 2

2.1

Xe-125

1 E + 9

1 E + 3

16.8

Xe-127

1 E + 5

1 E + 3

36.4

Xe-129m

1 E + 4

1 E + 3

8.9

Xe-131m

1 E + 4

4 E + 11

11.9

Xe-133

1 E + 4

1 E + 3

2 E + 11

5.3

Xe-133m

1 E + 4

1 E + 3

2.2

Xe-135

1 E + 10

1 E + 3

3 E + 10

9.1

Xe-135m

1 E + 9

1 E + 2

15.3

Xe-138

1 E + 9

1 E + 2

14.1

Cs-125

1 E + 4

1 E + 1

45.0

Cs-127

1 E + 5

1 E + 2

6.3

Cs-129

1 E + 5

1 E + 2

4 E + 10

1 E + 1

1 E + 2

9 E-1

1 E + 1

5 E + 3

1 E + 2

32.1

Cs-130

1 E + 6

1 E + 2

29.2

Cs-131

1 E + 6

1 E + 3

3 E + 11

1 E + 2

9 E + 2

2 E + 2

3 E + 1

1 E + 2

1 E + 3

2 E + 5

9 E + 2

10.0

Cs-132

1 E + 5

1 E + 1

1 E + 10

1 E + 1

3 E-1

1 E + 1

4 E + 2

1 E + 1

6.5

Cs-134

1 E + 4

1 E + 1

2 E-1

1 E-1

5 E-2

6 E-1

1 E + 1

2 E-1

2.1

Cs-134m

1 E + 5

1 E + 3

4 E + 11

1 E + 2

1 E + 3

2 E + 1

1 E + 2

1 E + 6

1 E + 3

2.9

Cs-135

1 E + 7

1 E + 4

4 E + 11

1 E + 2

2 E + 1

4 E-1

1 E + 2

3 E + 2

3 E + 3

3 E + 1

3 E + 2

9 E + 3

2 E + 1

2.0E + 6

Cs-136

1 E + 5

1 E + 1

¹⁾

1 E-1

4 E-2

6 E + 1

1 E + 1

13.2

Cs-137 +

1 E + 4

1 E + 1

2 E + 10

5 E-1

4 E-1

6 E-2

1 E + 1

6 E-1

30.2

Cs-138

1 E + 4

1 E + 1

9 E-2

3 E + 4

1 E + 1

32.2

Ba-126

1 E + 7

1 E + 2

100.0

Ba-128

1 E + 7

1 E + 2

2.4

Ba-131 +

1 E + 6

1 E + 2

2 E + 10

1 E + 1

¹⁾

5 E-1

2 E-1

1 E + 1

4 E + 1

6 E + 1

1 E + 1

3 E + 2

9 E + 1

11.5

Ba-131m

1 E + 7

1 E + 2

14.5

Ba-133

1 E + 6

1 E + 2

4 E + 1

8 E + 1

1 E + 1

10.5

Ba-133m

1 E + 6

1 E + 2

38.9

Ba-135m

1 E + 6

1 E + 2

28.7

Ba-137m

1 E + 6

1 E + 1

2.6

Ba-139

1 E + 5

1 E + 2

83.1

Ba-140 +

1 E + 5

1 E + 1

5 E + 9

8 E-2

3 E-2

1 E + 1

5 E + 1

1 E + 1

12.8

Ba-141

1 E + 5

1 E + 1

18.3

Ba-142

1 E + 6

1 E + 1

10.7

La-131

1 E + 6

1 E + 1

59.0

La-132

1 E + 6

1 E + 1

4.8

La-135

1 E + 7

1 E + 3

19.4

La-137

1 E + 7

1 E + 3

6.0E + 4

La-138 *)

1 E + 7

1 E + 1

1,0E + 11

La-140

1 E + 5

1 E + 1

4 E + 9

1 E + 1

1 E-1

4 E + 2

1 E + 1

40.3

La-141

1 E + 5

1 E + 2

3.9

La-142

1 E + 5

1 E + 1

92.5

La-143

1 E + 5

1 E + 2

14.2

Ce-134

1 E + 7

1 E + 3

75.9

Ce-135

1 E + 6

1 E + 1

17.8

Ce-137

1 E + 7

1 E + 3

9.0

Ce-137m

1 E + 6

1 E + 3

34.4

Ce-139

1 E + 6

1 E + 2

7 E + 10

1 E + 1

7 E-1

1 E + 1

1 E + 2

4 E + 1

1 E + 2

137.6

Ce-141

1 E + 7

1 E + 2

2 E + 11

1 E + 1

7 E + 1

1 E + 1

1 E + 2

8 E + 1

1 E + 3

7 E + 1

32.5

Ce-143

1 E + 6

1 E + 2

9 E + 9

1 E + 1

1 E + 2

9 E-1

1 E + 1

5 E + 3

1 E + 2

33.0

Ce-144 +

1 E + 5

1 E + 2

2 E + 9

1 E + 2

4 E-1

3 E + 1

1 E + 2

2 E + 2

1 E + 1

284.8

Pr-136

1 E + 5

1 E + 1

13.1

Pr-137

1 E + 6

1 E + 2

76.6

Pr-138m

1 E + 6

1 E + 1

2.0

Pr-139

1 E + 7

1 E + 2

4.5

Pr-142

1 E + 5

1 E + 2

4 E + 9

1 E + 1

1 E + 2

4 E + 4

1 E + 2

19.1

Pr-142m

1 E + 9

1 E + 7

14.6

Pr-143

1 E + 6

1 E + 4

3 E + 10

1 E + 2

4 E + 1

2 E + 1

1 E + 2

1 E + 4

6 E + 5

4 E + 1

13.6

Pr-144

1 E + 5

1 E + 2

17.3

Pr-145

1 E + 5

1 E + 3

6.0

Pr-147

1 E + 5

1 E + 1

13.6

Nd-136

1 E + 6

1 E + 2

50.7

Nd-138

1 E + 7

1 E + 3

5.1

Nd-139

1 E + 6

1 E + 2

29.7

Nd-139m

1 E + 6

1 E + 1

5.5

Nd-141

1 E + 7

1 E + 2

2.5

Nd-147

1 E + 6

1 E + 2

6 E + 10

1 E + 1

5 E + 1

7 E-1

1 E + 1

1 E + 2

5 E + 1

1 E + 3

5 E + 1

Nd-149

1 E + 6

1 E + 2

6 E + 9

1 E + 1

1 E + 2

7 E-1

1 E + 1

7 E + 4

1 E + 2

1.7

Nd-151

1 E + 5

1 E + 1

12.4

Pm-141

1 E + 5

1 E + 1

20.9

Pm-143

1 E + 6

1 E + 2

265.0

Pm-144

1 E + 6

1 E + 1

1.0

Pm-145

1 E + 7

1 E + 3

17.7

Pm-146

1 E + 6

1 E + 1

5.5

Pm-147

1 E + 7

1 E + 4

4 E + 11

1 E + 2

2 E + 2

2 E + 1

1 E + 3

1 E + 4

2 E + 4

6 E + 3

2.6

Pm-148

1 E + 5

1 E + 1

5.4

Pm-148m +

1 E + 6

1 E + 1

41.3

Pm-149

1 E + 6

1 E + 3

2 E + 10

1 E + 2

1 E + 3

2 E + 1

1 E + 2

7 E + 4

1 E + 3

53.1

Pm-150

1 E + 5

1 E + 1

2.7

Pm-151

1 E + 6

1 E + 2

28.0

Sm-141

1 E + 5

1 E + 1

10.2

Sm-141m

1 E + 6

1 E + 1

22.6

Sm-142

1 E + 7

1 E + 2

72.4

Sm-145

1 E + 7

1 E + 2

340.0

Sm-146

1 E + 5

1 E + 1

1.0E + 8

Sm-147 *)

1 E + 4

1 E + 1

1.1E + 11

Sm-151

1 E + 8

1 E + 4

4 E + 11

1 E + 2

5 E + 2

4 E + 1

1 E + 3

1 E + 4

3 E + 4

7 E + 3

93.0

Sm-153

1 E + 6

1 E + 2

9 E + 10

1 E + 1

1 E + 2

1 E + 1

1 E + 2

4 E + 4

1 E + 2

46.8

Sm-155

1 E + 6

1 E + 2

22.4

Sm-156

1 E + 6

1 E + 2

9.4

Eu-145

1 E + 6

1 E + 1

5.9

Eu-146

1 E + 6

1 E + 1

4.5

Eu-147

1 E + 6

1 E + 2

24.6

Eu-148

1 E + 6

1 E + 1

55.6

Eu-149

1 E + 7

1 E + 2

93.1

Eu-150

1 E + 6

1 E + 1

35.8

Eu-152

1 E + 6

1 E + 2

1 E + 10

2 E-1

7 E-2

8 E-1

1 E + 1

5 E-1

13.3

Eu-152m

1 E + 6

1 E + 2

8 E + 9

1 E + 1

1 E + 2

7 E-1

1 E + 1

1 E + 4

1 E + 2

9.3

Eu-154

1 E + 6

1 E + 1

9 E + 9

2 E-1

6 E-2

7 E-1

1 E + 1

5 E-1

8.8

Eu-155

1 E + 7

1 E + 2

2 E + 11

1 E + 1

3 E + 1

2 E + 1

1 E + 2

3 E + 2

3 E + 1

4.8

Eu-156

1 E + 6

1 E + 1

15.2

Eu-157

1 E + 6

1 E + 2

15.2

Eu-158

1 E + 5

1 E + 1

46.0

Gd-145

1 E + 5

1 E + 1

23.9

Gd-146 +

1 E + 6

1 E + 1

48,3

Gd-147

1 E + 6

1 E + 1

38.1

Gd-148

1 E + 4

1 E + 1

90.0

Gd-149

1 E + 6

1 E + 2

9.5

Gd-151

1 E + 7

1 E + 2

120,0

Gd-152 *)

1 E + 4

1 E + 1

1.1E + 14

Gd-153

1 E + 7

1 E + 2

1 E + 11

1 E + 1

2 E + 1

1 E + 1

1 E + 2

3 E + 2

2 E + 1

239.5

Gd-159

1 E + 6

1 E + 3

3 E + 10

1 E + 2

1 E + 3

1 E + 2

7 E + 4

1 E + 3

18.5

Tb-147

1 E + 6

1 E + 1

1.7

Tb-149

1 E + 6

1 E + 1

4.1

Tb-150

1 E + 6

1 E + 1

3.7

Tb-151

1 E + 6

1 E + 1

17.6

Tb-153

1 E + 7

1 E + 2

2.3

Tb-154

1 E + 6

1 E + 1

21.0

Tb-155

1 E + 7

1 E + 2

5.3

Tb-156

1 E + 6

1 E + 1

5.4

Tb-156m

1 E + 7

1 E + 3

5.4

Tb-157

1 E + 7

1 E + 4

99.0

Tb-158

1 E + 6

1 E + 1

150.0

Tb-160

1 E + 6

1 E + 1

1 E + 10

6 E-1

2 E-1

7 E-2

1 E + 1

2 E + 1

6 E-1

72.1

Tb-161

1 E + 6

1 E + 3

6.9

Dy-155

1 E + 6

1 E + 1

10.0

Dy-157

1 E + 6

1 E + 2

8.1

Dy-159

1 E + 7

1 E + 3

144.4

Dy-165

1 E + 6

1 E + 3

9 E + 9

1 E + 2

1 E + 3

1 E + 1

1 E + 2

9 E + 5

1 E + 3

2.4

Dy-166

1 E + 6

1 E + 3

9 E + 9

1 E + 1

1 E + 4

81.5

Dy-166 +

1 E + 1

1 E + 3

81.5

Ho-155

1 E + 6

1 E + 2

48,0

Ho-157

1 E + 6

1 E + 2

12.6

Ho-159

1 E + 6

1 E + 2

33.0

Ho-161

1 E + 7

1 E + 2

2.5

Ho-162

1 E + 7

1 E + 2

15.0

Ho-162m

1 E + 6

1 E + 1

68.0

Ho-164

1 E + 6

1 E + 3

29.0

Ho-164m

1 E + 7

1 E + 3

37,0

Ho-166

1 E + 5

1 E + 3

4 E + 9

1 E + 2

1 E + 3

1 E + 1

1 E + 2

7 E + 4

1 E + 3

26.8

Ho-166m

1 E + 6

1 E + 1

1,2E + 3

Ho-167

1 E + 6

1 E + 2

3.1

Er-161

1 E + 6

1 E + 1

3.2

He-165

1 E + 7

1 E + 3

10.3

Er-169

1 E + 7

1 E + 4

4 E + 11

1 E + 2

5 E + 1

1 E + 3

1 E + 4

2 E + 6

1 E + 2

9.4

He-171

1 E + 6

1 E + 2

8 E + 9

1 E + 1

1 E + 2

7 E-1

1 E + 1

2 E + 4

1 E + 2

7.5

He-172

1 E + 6

1 E + 2

49,0

Tm-162

1 E + 6

1 E + 1

21.6

Tm-166

1 E + 6

1 E + 1

7.7

Tm-167

1 E + 6

1 E + 2

9.3

Tm-170

1 E + 6

1 E + 3

3 E + 10

1 E + 2

4 E + 1

1 E + 2

1 E + 3

9 E + 3

7 E + 1

128.6

Tm-171

1 E + 8

1 E + 4

4 E + 11

1 E + 2

5 E + 2

6 E + 1

1 E + 3

1 E + 4

6 E + 4

7 E + 2

1.9

Tm-172

1 E + 6

1 E + 2

63.6

Tm-173

1 E + 6

1 E + 2

8.2

Tm-175

1 E + 6

1 E + 1

15.2

Yb-162

1 E + 7

1 E + 2

18.9

Yb-166

1 E + 7

1 E + 2

56.7

Yb-167

1 E + 6

1 E + 2

17.7

Yb-169

1 E + 7

1 E + 2

32.0

Yb-175

1 E + 7

1 E + 3

3 E + 11

1 E + 2

1 E + 3

1 E + 2

1 E + 4

1 E + 3

4.2

Yb-177

1 E + 6

1 E + 2

1.9

Yb-178

1 E + 6

1 E + 3

74.0

Lu-169

1 E + 6

1 E + 1

1.4

Lu-170

1 E + 6

1 E + 1

2.0

Lu-171

1 E + 6

1 E + 1

8.2

Lu-172

1 E + 6

1 E + 1

6.7

Lu-173

1 E + 7

1 E + 2

1.4

Lu-174

1 E + 7

1 E + 2

3.3

Lu-174m

1 E + 7

1 E + 2

142.0

Lu-176 *)

1 E + 6

1 E + 2

3.6E + 10

Lu-176m

1 E + 6

1 E + 3

3.7

Lu-177

1 E + 7

1 E + 3

3 E + 11

1 E + 2

1 E + 3

1 E + 2

1 E + 4

1 E + 3

6.7

Lu-177m

1 E + 6

1 E + 1

160.1

Lu-178

1 E + 5

1 E + 2

28.4

Lu-178m

1 E + 5

1 E + 1

22.7

Lu-179

1 E + 6

1 E + 3

4.6

Hf-170

1 E + 6

1 E + 2

16.0

Hf-172 +

1 E + 6

1 E + 1

1.9

Hf-173

1 E + 6

1 E + 2

23.6

Hf-175

1 E + 6

1 E + 2

70.0

Hf-177m

1 E + 5

1 E + 1

51.0

Hf-178m

1 E + 6

1 E + 1

31.0

Hf-179m

1 E + 6

1 E + 1

25.0

Hf-180m

1 E + 6

1 E + 1

5.5

Hf-181

1 E + 6

1 E + 1

2 E + 10

4 E-1

2 E-1

1 E + 1

8 E + 1

1 E + 1

42.4

Hf-182

1 E + 6

1 E + 2

9.0E + 6

Hf-182m

1 E + 6

1 E + 1

61.5

Hf-183

1 E + 6

1 E + 1

64.0

Hf-184

1 E + 6

1 E + 2

4.1

Ta-172

1 E + 6

1 E + 1

37,0

Ta-173

1 E + 6

1 E + 1

3.6

Ta-174

1 E + 6

1 E + 1

1.0

Ta-175

1 E + 6

1 E + 1

10.5

Ta-176

1 E + 6

1 E + 1

8.1

Ta-177

1 E + 7

1 E + 2

56.6

Ta-178

1 E + 6

1 E + 1

2.5

Ta-179

1 E + 7

1 E + 3

665.0

Ta-180 *)

1 E + 6

1 E + 1

> E + 13

Ta-180m

1 E + 7

1 E + 3

8.2

Ta-182

1 E + 4

1 E + 1

9 E + 9

5 E-1

2 E-1

6 E-2

1 E + 1

5 E-1

114.4

Ta-182m

1 E + 6

1 E + 2

16.0

Ta-183

1 E + 6

1 E + 2

5.0

Ta-184

1 E + 6

1 E + 1

8.7

Ta-185

1 E + 5

1 E + 2

49,0

Ta-186

1 E + 5

1 E + 1

10.5

W-176

1 E + 6

1 E + 2

2.5

W-177

1 E + 6

1 E + 1

2.3

W-178 +

1 E + 6

1 E + 1

22.0

W-179

1 E + 7

1 E + 2

38.0

W-181

1 E + 7

1 E + 3

3 E + 11

1 E + 2

6 E + 1

2 E + 1

5 E + 1

1 E + 3

4 E + 2

2 E + 3

6 E + 1

121.2

W-185

1 E + 7

1 E + 4

4 E + 11

1 E + 2

8 E + 2

1 E + 4

3 E + 3

1 E + 4

4 E + 5

7 E + 2

75.1

W-187

1 E + 6

1 E + 2

2 E + 10

1 E + 1

1 E + 2

5 E-1

1 E + 1

4 E + 3

1 E + 2

23.8

W-188 +

1 E + 5

1 E + 2

69.0

Re-177

1 E + 6

1 E + 1

14.0

Re-178

1 E + 6

1 E + 1

13.2

Re-181

1 E + 6

1 E + 1

20.0

Re-182

1 E + 6

1 E + 1

64.0

Re-184

1 E + 6

1 E + 1

38.0

Re-184m

1 E + 6

1 E + 2

165.0

Re-186

1 E + 6

1 E + 3

2 E + 10

1 E + 2

1 E + 3

2 E + 1

1 E + 2

4 E + 4

1 E + 3

90.6

Re-186m

1 E + 7

1 E + 3

2.0E + 5

Re-187 *)

1 E + 9

1 E + 6

5.0E + 10

Re-188

1 E + 5

1 E + 2

4 E + 9

1 E + 1

1 E + 2

5 E + 4

1 E + 2

17.0

Re-188m

1 E + 7

1 E + 2

18.6

Re-189 +

1 E + 6

1 E + 2

24.3

Os-180

1 E + 7

1 E + 2

21.7

Os-181

1 E + 6

1 E + 1

1.8

Os-182

1 E + 6

1 E + 2

22.1

Os-185

1 E + 6

1 E + 1

1 E + 10

5 E-1

3 E-1

1 E-1

1 E + 1

3 E + 1

5 E-1

94.0

Os-189m

1 E + 7

1 E + 4

6.0

Os-191

1 E + 7

1 E + 2

1 E + 11

1 E + 1

9 E + 1

1 E + 1

1 E + 2

3 E + 3

9 E + 1

15.4

Os-191m

1 E + 7

1 E + 3

4 E + 11

1 E + 2

1 E + 3

2 E + 2

1 E + 3

2 E + 6

1 E + 3

13.1

Os-193

1 E + 6

1 E + 2

2 E + 10

1 E + 1

1 E + 2

3 E + 4

1 E + 2

30.0

Os-194 +

1 E + 5

1 E + 2

6.0

Ir-182

1 E + 5

1 E + 1

15.0

Ir-184

1 E + 6

1 E + 1

3.0

Ir-185

1 E + 6

1 E + 1

14.0

Ir-186

1 E + 6

1 E + 1

15.8

Ir-187

1 E + 6

1 E + 2

10.5

Ir-188

1 E + 6

1 E + 1

41.5

Ir-189 +

1 E + 7

1 E + 2

13.3

Ir-190 +

1 E + 6

1 E + 1

7 E + 9

8 E-2

6 E-2

5 E + 1

1 E + 1

11.8

Ir-192

1 E + 4

1 E + 1

1 E + 10

3 E-1

1 E-1

1 E + 1

3 E + 1

74.0

Ir-192m

1 E + 7

1 E + 2

241.0

Ir-193m

1 E + 7

1 E + 4

10.6

Ir-194

1 E + 5

1 E + 2

3 E + 9

1 E + 1

¹⁾

1 E + 1

2 E + 4

1 E + 2

171.0

Ir-194m

1 E + 6

1 E + 1

19.2

Ir-195

1 E + 6

1 E + 2

2.5

Ir-195m

1 E + 6

1 E + 2

3.8

Pt-186

1 E + 6

1 E + 1

2.0

Pt-188 +

1 E + 6

1 E + 1

10.2

Pt-189

1 E + 6

1 E + 2

11.0

Pt-191

1 E + 6

1 E + 2

4 E + 10

1 E + 1

1 E + 2

1 E + 1

3 E + 3

1 E + 2

2.8

Pt-193

1 E + 7

1 E + 4

4 E + 11

50.0

Pt-193m

1 E + 7

1 E + 3

4 E + 11

1 E + 2

1 E + 3

7 E + 1

1 E + 2

1 E + 5

1 E + 3

4.3

Pt-195m

1 E + 6

1 E + 2

4.0

Pt-197

1 E + 6

1 E + 3

2 E + 11

1 E + 2

1 E + 3

2 E + 1

1 E + 2

2 E + 5

1 E + 3

18.3

Pt-197m

1 E + 6

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

5 E + 5

1 E + 2

94.4

Pt-199

1 E + 6

1 E + 2

30.8

Pt-200

1 E + 6

1 E + 2

12.5

Au-193

1 E + 7

1 E + 2

17.7

Au-194

1 E + 6

1 E + 1

39.5

Au-195

1 E + 7

1 E + 2

183.0

Au-198

1 E + 6

1 E + 2

1 E + 10

1 E + 1

1 E + 2

6 E-1

1 E + 1

2 E + 3

1 E + 2

2.7

Au-198m

1 E + 6

1 E + 1

2.3

Au-199

1 E + 6

1 E + 2

1 E + 11

1 E + 1

1 E + 2

6 E-1

1 E + 1

9 E + 3

1 E + 2

3.1

Au-200

1 E + 5

1 E + 2

48,4

Au-200m

1 E + 6

1 E + 1

18.7

Au-201

1 E + 6

1 E + 2

26.4

Hg-193

1 E + 6

1 E + 2

3.5

Hg-193m

1 E + 6

1 E + 1

11,1

Hg-194 +

1 E + 6

1 E + 1

367,0

Hg-195

1 E + 6

1 E + 2

9.5

Hg-195m +

1 E + 6

1 E + 2

40.0

Hg-197

1 E + 7

1 E + 2

2 E + 11

1 E + 1

1 E + 2

3 E + 4

1 E + 2

64.1

Hg-197m

1 E + 6

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

3 E + 4

1 E + 2

23.8

Hg-203

1 E + 5

1 E + 2

5 E + 10

1 E + 1

¹⁾

1 E + 1

7 E + 1

1 E + 2

2 E + 1

1 E + 1

2 E + 2

46.6

Tl-194

1 E + 6

1 E + 1

33.0

Tl-194m

1 E + 6

1 E + 1

32.8

Tl-195

1 E + 6

1 E + 1

1.1

Tl-197

1 E + 6

1 E + 2

2.8

Tl-198

1 E + 6

1 E + 1

5.3

Tl-198m

1 E + 6

1 E + 1

1.9

Tl-199

1 E + 6

1 E + 2

7.4

Tl-200

1 E + 6

1 E + 1

9 E + 9

1 E + 1

2 E-1

1 E + 3

1 E + 1

26.1

Tl-201

1 E + 6

1 E + 2

1 E + 11

1 E + 1

1 E + 2

1 E + 1

1 E + 4

1 E + 2

73.1

Tl-202

1 E + 6

1 E + 2

2 E + 10

1 E + 1

¹⁾

5 E-1

2 E-1

1 E + 1

4 E + 1

6 E + 1

1 E + 1

3 E + 2

1 E + 2

12.2

Tl-204

1 E + 4

1 E + 11

1 E + 2

4 E + 1

4 E-2

1 E + 2

9 E + 2

9 E + 3

9 E + 1

9 E + 2

3 E + 3

3 E + 2

3.8

Pb-195m

1 E + 6

1 E + 1

15.7

Pb-198

1 E + 6

1 E + 2

2.4

Pb-199

1 E + 6

1 E + 1

1.5

Pb-200

1 E + 6

1 E + 2

21.5

Pb-201

1 E + 6

1 E + 1

9.4

Pb-202

1 E + 6

1 E + 3

3.0E + 5

Pb-202m

1 E + 6

1 E + 1

3.6

Pb-203

1 E + 6

1 E + 2

4 E + 10

1 E + 1

1 E + 2

9 E-1

1 E + 1

3 E + 3

1 E + 2

51.9

Pb-205

1 E + 7

1 E + 4

1.5E + 7

Pb-209

1 E + 6

1 E + 5

3.3

Pb-210 +

3 E-2

3 E + 1

8 E + 1

6 E-2

22.3

Pb-210 + +

1 E + 4

1 E + 1

1 E + 10

2 E-2

1 E + 1

6 E-2

22.3

Pb-211

1 E + 6

1 E + 2

36.1

Pb-212

1 E + 7

1 E + 2

1 E + 1

1 E-1

2 E + 3

1 E + 1

10.6

Pb-212 +

1 E + 5

1 E + 1

7 E + 9

10.6

Pb-214

1 E + 6

1 E + 2

26.8

Bi-200

1 E + 6

1 E + 1

36.4

Bi-201

1 E + 6

1 E + 1

1.8

Bi-202

1 E + 6

1 E + 1

1.7

Bi-203

1 E + 6

1 E + 1

11.8

Bi-205

1 E + 6

1 E + 1

15.3

Bi-206

1 E + 5

1 E + 1

3 E + 9

1 E + 1

7 E-2

9 E + 1

1 E + 1

6.2

Bi-207

1 E + 6

1 E + 1

7 E + 9

2 E-1

5 E-2

5 E-1

1 E + 1

6 E-1

31.6

Bi-210

1 E + 6

1 E + 3

1 E + 10

1 E + 2

1 E + 3

3 E + 1

1 E + 4

1 E + 3

5.0

Bi-210m

1 E + 5

1 E + 1

6 E + 9

3.0E + 6

Bi-212

2 E-1

3 E + 4

60.6

Bi-212 +

1 E + 5

1 E + 1

7 E + 9

1 E + 1

60.6

Bi-213

1 E + 6

1 E + 2

45.6

Bi-214

1 E + 5

1 E + 1

19.9

Po-203

1 E + 6

1 E + 1

1 E-1

4 E + 4

1 E + 1

36.0

Po-205

1 E + 6

1 E + 1

1 E-1

1 E + 4

1 E + 1

1.8

Po-206

1 E + 6

1 E + 1

8.8

Po-207

1 E + 6

1 E + 1

2 E-1

5 E + 3

1 E + 1

5.8

Po-208

1 E + 4

1 E + 1

2.9

Po-209

1 E + 4

1 E + 1

102.0

Po-210

1 E + 4

1 E + 1

4 E + 11

4 E-2

1 E + 1

138.4

At-207

1 E + 6

1 E + 1

1.8

At-211

1 E + 7

1 E + 3

2 E + 11

1 E + 1

1 E + 3

1 E + 1

3 E + 5

1 E + 3

7.2

Rn-220 +

1 E + 7

1 E + 4

< 10

Rn-222 +

1 E + 8

1 E + 1

3 E + 9

3.8

Fr-222

1 E + 5

1 E + 3

14.4

Fr-223

1 E + 6

1 E + 2

21.8

Ra-223 +

1 E + 5

1 E + 2

4 E + 9

5 E-1

4 E-1

1 E-2

3 E + 1

6 E + 1

1 E + 1

2 E + 1

3 E + 2

5 E-1

11.4

Ra-224

1 E-1

3 E + 2

3.7

Ra-224 +

1 E + 5

1 E + 1

4 E + 9

1 E + 1

3.7

Ra-225

1 E + 5

1 E + 2

2 E + 9

1 E-1

2 E-1

1 E-1

5 E + 1

9 E + 1

1 E + 1

3 E + 1

8 E + 1

4 E-1

14.8

Ra-226 +

3 E-2

5 E-1

4 E-1

4 E-2

5 E-1

9 E-1

4 E-1

1.6E + 3

Ra-226 + +

1 E + 4

1 E + 1

2 E + 9

1 E-2

4 E-1

4 E-2

5 E-1

5 E-2

1.6E + 3

Ra-227

1 E + 6

1 E + 2

1 E + 1

1 E + 2

1 E + 1

3 E + 5

1 E + 2

42.2

Ra-228 +

1 E + 5

1 E + 1

6 E + 9

7 E-2

1 E-1

4 E-1

7 E-1

5.8

Ac-224

1 E + 6

1 E + 2

2.9

Ac-225 +

1 E + 4

1 E + 1

10.0

Ac-226

1 E + 5

1 E + 2

29.0

Ac-227 +

1 E + 3

1 E-1

21.8

Ac-227 + +

7 E-3

6 E-1

2 E-1

4 E-1

3 E-2

21.8

Ac-228

1 E + 6

1 E + 1

6 E + 9

1 E + 1

2 E-1

7 E + 3

1 E + 1

6.1

Th-226

3 E + 1

1 E + 2

1 E + 7

31.0

Th-226 +

1 E + 7

1 E + 3

1 E + 1

1 E + 3

31.0

Th-227

1 E + 4

1 E + 1

1 E + 11

1 E-1

2 E-1

1 E-1

1 E + 1

6 E + 1

3 E-1

18.7

Th-228 +

1 E + 4

5 E + 9

1 E-1

7 E-2

1 E-1

4 E-1

1.9

Th-229 +

1 E + 3

5 E + 10

1 E-1

2 E-2

1 E-1

9 E-1

1 E-1

7,9E + 3

Th-230

1 E + 4

1 E + 11

1 E-1

5 E-2

1 E-1

5 E-1

5 E-2

3 E-1

7.5E + 4

Th-231

1 E + 7

1 E + 3

4 E + 11

1 E + 2

1 E + 3

4 E + 1

1 E + 2

3 E + 5

1 E + 3

25.5

Th-232

1 E + 4

1 E + 1

1 E-1

3 E-2

1 E-1

7 E-1

7 E-2

7 E-1

3 E-1

1,4E + 10

Th-232sec

1 E + 3

1 E-1

2 E-2

7 E-1

7 E-2

7 E-1

1 E-1

1,4E + 10

Th-234 +

1 E + 5

1 E + 3

3 E + 9

1 E + 2

1 E + 1

1 E + 2

9 E + 2

1 E + 3

3 E + 2

4 E + 3

1 E + 1

24.1

Pa-227

1 E + 6

1 E + 3

38.3

Pa-228

1 E + 6

1 E + 1

22.0

Pa-230

1 E + 6

1 E + 1

2 E + 10

4 E-1

1 E-1

1 E + 1

2 E + 2

1 E + 1

17.4

Pa-231

1 E + 3

4 E + 10

1 E-2

7 E-3

4 E-3

1 E-2

1 E-1

1 E-2

1 E-1

2 E-1

3.3E + 4

Pa-232

1 E + 6

1 E + 1

1.3

Pa-233

1 E + 7

1 E + 2

5 E + 10

1 E + 1

2 E + 1

4 E-1

1 E + 1

8 E + 1

1 E + 2

2 E + 1

4 E + 2

6 E + 1

27.0

Pa-234

1 E + 6

1 E + 1

6.7

U-230 + (M) * *)

1 E + 5

1 E + 1

4 E + 11

1 E-1

3 E-1

2 E-1

1 E-1

1 E + 1

8 E + 1

9 E-1

20.8

U-230 + (S) * **)

1 E + 5

1 E + 1

3 E + 11

1 E-1

3 E-1

2 E-1

1 E-1

1 E + 1

8 E + 1

9 E-1

20.8

U-231

1 E + 7

1 E + 2

1 E + 1

1 E + 2

1 E + 1

1 E + 4

1 E + 2

4.2

U-232 (M) * *)

1 E + 4

1 E + 1

4 E + 11

1 E-1

6 E-2

5 E-2

1 E-1

5 E-1

8 E-1

68.9

U-232 (S) * **)

1 E + 4

1 E + 1

1 E + 11

1 E-1

6 E-2

5 E-2

1 E-1

5 E-1

8 E-1

68.9

U-232 +

1 E + 3

1 E-1

4 E-2

5 E-1

3 E-1

68.9

U-233

1 E + 4

1 E + 1

4 E + 11

4 E-1

3 E-1

1 E + 1

5 E-1

1 E + 1

1.6E + 5

U-234

1 E + 4

1 E + 1

4 E + 11

5 E-1

4 E-1

1 E + 1

6 E-1

1 E + 1

2.5E + 5

U-235 +

1 E + 4

1 E + 1

3 E-1

¹⁾

3 E-1

4 E-1

1 E + 1

8 E-1

7.0E + 8

U-236

1 E + 4

1 E + 1

4 E + 11

5 E-1

4 E-1

1 E + 1

6 E-1

1 E + 1

2.3E + 7

U-237

1 E + 6

1 E + 2

1 E + 1

1 E + 2

1 E + 1

3 E + 3

1 E + 2

6.8

U-238 +

1 E + 4

1 E + 1

6 E-1

4 E-1

1 E + 1

6 E-1

1 E + 1

4,4E + 9

U-238sec

1 E + 3

9 E-3

3 E-1

3 E-2

3 E-1

4 E-2

4,4E + 9

U-239

1 E + 6

1 E + 2

4 E + 6

1 E + 2

23.5

U-240

1 E + 7

1 E + 3

1 E + 1

1 E + 3

7 E-1

1 E + 1

9 E + 3

1 E + 3

14.1

U-240 +

1 E + 6

1 E + 1

7 E-1

14.1

Np-232

1 E + 6

1 E + 1

14.7

Np-233

1 E + 7

1 E + 2

36.2

Np-234

1 E + 6

1 E + 1

4.4

Np-235

1 E + 7

1 E + 3

396.2

Np-236

1 E + 7

1 E + 3

22.5

Np-236m

1 E + 5

1 E + 2

1,2E + 5

Np-237 +

1 E + 3

2 E + 11

1 E-1

9 E-2

1 E-1

6 E-1

2.1E + 6

Np-238

1 E + 6

1 E + 2

2.1

Np-239

1 E + 7

1 E + 2

7 E + 10

1 E + 1

1 E + 2

1 E + 1

6 E + 3

1 E + 2

2.4

Np-240

1 E + 6

1 E + 2

1 E + 1

2 E-1

4 E + 4

1 E + 1

65.0

Pu-234

1 E + 7

1 E + 2

1 E + 1

1 E + 2

1 E + 1

8 E + 4

1 E + 2

8.8

Pu-235

1 E + 7

1 E + 2

1 E + 1

1 E + 2

1 E + 1

1 E + 6

1 E + 2

25.3

Pu-236

1 E + 4

1 E + 1

3 E + 11

1 E-1

2 E-1

1 E-1

1 E + 1

7 E-1

2.9

Pu-237

1 E + 7

1 E + 3

2 E + 11

1 E + 2

¹⁾

1 E + 2

5 E + 2

1 E + 3

1 E + 2

2 E + 3

5 E + 2

45.3

Pu-238

1 E + 4

1 E + 11

1 E-1

4 E-2

8 E-2

6 E-2

1 E-1

3 E-1

87.7

Pu-239

1 E + 4

1 E + 11

1 E-1

4 E-2

8 E-2

4 E-2

1 E-1

5 E-1

2 E-1

2.4E + 4

Pu-240

1 E + 3

1 E + 11

1 E-1

4 E-2

8 E-2

4 E-2

1 E-1

6 E-1

2 E-1

6.6E + 3

Pu-241

1 E + 5

1 E + 2

4 E + 11

1 E + 1

1 E + 2

4 E + 1

1 E + 2

9 E + 1

1 E + 1

14.4

Pu-242

1 E + 4

1 E + 11

1 E-1

4 E-2

1 E-1

5 E-1

3 E-1

3.8E + 5

Pu-243

1 E + 7

1 E + 3

1 E + 2

1 E + 3

2 E + 1

1 E + 2

7 E + 5

1 E + 3

5.0

Pu-244 +

1 E + 4

4 E + 9

1 E-1

4 E-2

1 E-1

3 E-1

8,3E + 7

Pu-245

1 E + 6

1 E + 2

10.5

Pu-246

1 E + 6

1 E + 2

10.9

Am-237

1 E + 6

1 E + 2

73.0

Am-238

1 E + 6

1 E + 1

1.6

Am-239

1 E + 6

1 E + 2

11.9

Am-240

1 E + 6

1 E + 1

50.8

Am-241

1 E + 4

1 E + 11

1 E-1

5 E-2

6 E-2

1 E-1

3 E-1

432.6

Am-242

1 E + 6

1 E + 3

1 E + 2

1 E + 3

3 E + 1

1 E + 2

3 E + 5

1 E + 3

16.0

Am-242m +

1 E + 4

1 E + 11

1 E-1

5 E-2

9 E-2

7 E-2

1 E-1

3 E-1

141.0

Am-243 +

1 E + 3

5 E + 10

1 E-1

5 E-2

9 E-2

5 E-2

1 E-1

9 E-1

3 E-1

7,4E + 3

Am-244

1 E + 6

1 E + 1

10.1

Am-244m

1 E + 7

1 E + 4

26.0

Am-245

1 E + 6

1 E + 3

2.1

Am-246

1 E + 5

1 E + 1

39,0

Am-246m

1 E + 6

1 E + 1

25.0

Cm-238

1 E + 7

1 E + 2

2.4

Cm-240

1 E + 5

1 E + 2

27.0

Cm-241

1 E + 6

1 E + 2

32.8

Cm-242

1 E + 5

1 E + 2

4 E + 11

8 E-1

7 E-1

4 E-1

8 E + 1

1 E + 2

2 E + 1

5 E + 1

4 E + 1

162.8

Cm-243

1 E + 4

9 E + 10

1 E-1

7 E-2

1 E-1

7 E-2

1 E-1

4 E-1

29.1

Cm-244

1 E + 4

1 E + 1

2 E + 11

1 E-1

8 E-2

1 E-1

1 E + 1

5 E-1

18.1

Cm-245

1 E + 3

9 E + 10

1 E-1

4 E-2

5 E-2

1 E-1

6 E-1

3 E-1

8,5E + 3

Cm-246

1 E + 3

9 E + 10

1 E-1

5 E-2

1 E-1

3 E-1

4,7E + 3

Cm-247 +

1 E + 4

3 E + 10

1 E-1

5 E-2

1 E-1

4 E-2

1 E-1

3 E-1

1.6E + 7

Cm-248

1 E + 3

2 E + 8

1 E-2

3 E-2

1 E-2

1 E-1

2 E-1

8 E-2

3.4E + 5

Cm-249

1 E + 6

1 E + 3

64.2

Cm-250

1 E + 3

1 E-1

1.1 E + 4

Bk-245

1 E + 6

1 E + 2

4.9

Bk-246

1 E + 6

1 E + 1

1.8

Bk-247

1 E + 4

1.4E + 3

Bk-249

1 E + 6

1 E + 3

4 E + 11

1 E + 1

3 E + 1

2 E + 1

8 E + 1

9 E + 2

1 E + 3

3 E + 2

7 E + 2

1 E + 3

2 E + 2

320.0

Bk-250

1 E + 6

1 E + 1

3.2

Cf-244

1 E + 7

1 E + 4

19.7

Cf-246

1 E + 6

1 E + 3

1 E + 1

1 E + 3

1 E + 1

4 E + 4

1 E + 3

35.7

Cf-248

1 E + 4

1 E + 1

4 E + 11

5 E-1

4 E-1

1 E + 1

2 E + 1

333.5

Cf-249

1 E + 3

3 E + 10

1 E-1

7 E-2

6 E-2

1 E-1

4 E-1

350.6

Cf-250

1 E + 4

1 E + 1

2 E + 11

1 E-1

1 E + 1

9 E-1

13.1

Cf-251

1 E + 3

7 E + 10

1 E-1

7 E-2

5 E-2

1 E-1

4 E-1

898,0

Cf-252

1 E + 4

1 E + 1

5 E + 8

1 E-1

2 E-2

2 E-1

1 E-1

1 E + 1

2.6

Cf-253 +

1 E + 5

1 E + 2

4 E + 11

1 E-1

1 E + 2

7 E + 1

1 E + 2

1 E + 3

4 E + 1

17.8

Cf-254

1 E + 3

1 E + 7

1 E-1

1 E + 1

7 E-1

60.5

Es-250

1 E + 6

1 E + 2

8.6

Es-251

1 E + 7

1 E + 2

33.0

Es-253

1 E + 5

1 E + 2

5 E + 1

1 E + 2

4 E + 2

20.4

Es-254 +

1 E + 4

1 E + 1

4 E-1

3 E-1

1 E + 1

275.7

Es-254m

4 E-1

2 E + 3

39,3

Es-254m +

1 E + 6

1 E + 2

39,3

Fm-252

1 E + 6

1 E + 3

25.4

Fm-253

1 E + 6

1 E + 2

3.0

Fm-254

1 E + 7

1 E + 4

1 E + 2

1 E + 4

3 E + 1

1 E + 2

2 E + 6

1 E + 4

3.2

Fm-255

1 E + 6

1 E + 3

1 E + 1

1 E + 3

1 E + 1

9 E + 4

1 E + 4

20.1

Fm-257

1 E + 5

1 E + 1

100.5

Md-257

1 E + 7

1 E + 2

Md-258

1 E + 5

1 E + 2

Table 2 List of radionuclides in table 1 in radioactive Balance with the specified daughter nuclides

Mother nuclide	Daughter nuclide
Mg-28 +	Al-28
Ca-47 +	Sc-47
Ti-44 +	Sc-44
Fe-60 +	Co-60m
Zn-69m +	Zn-69
Ge-68 +	Ga-68
Rb-83 +	Kr-83m
Sr-82 +	Rb-82
Sr-90 +	Y-90
Y-87 +	Sr-87m
Zr-93 +	Nb-93m
Zr-97 +	Nb-97, Nb-97m
Mo-101 +	Tc-100
Tc-95m +	Tc-95
Ru-103 +	Rh-102m
Ru-106 +	Rh-106
Pd-103 +	Rh-106
Ag-108m +	Ag-108
Ag-110m +	Ag-110
Cd-109 +	Ag-109m
Cd-115m +	In-115m
In-114m +	In-114
Sn-113 +	In-113m
Sn-121m +	Sn-121
Sn-126 +	Sb-126m
Sb-125 +	Te-125m
Te-127m +	Te-127
Te-129m +	Te-129
Te-131m +	Te-131
Te-133m +	Te-133
I-133 +	Xe-133, Xe-133m
I-135 +	Xe-135, Xe-135m
Xe-122 +	I-122
Cs-137 +	Ba-137m
Ba-131 +	Cs-131
Ba-140 +	La-140
Ce-144 +	Pr-144, Pr-144m
Pm-148m +	Pm-148
Gd-146 +	Eu-146
Dy-166 +	Ho-166
Hf-172 +	Lu-172
W-178 +	Ta-178
W-188 +	Re-188
Re-189 +	Os-189m
Os-194 +	Ir-194
Ir-189	Os-189m
Ir-190 +	Os-190m
Pt-188 +	Ir-188
Hg-194 +	Au-194
Hg-195m +	Hg-195
Pb-210 +	Bi-210
Pb-210 + +	Bi-210, Po-210
Pb-212 +	Bi-212, Tl-208, Po-212
Bi-212 +	Tl-208, Po-212
Rn-220 +	Po-216
Rn-222 +	Po-218, Pb-214, Bi-214, Po-214
Ra-223 +	Rn-219, Po-215, Pb-211, Bi-211, Tl-207, Po-211
Ra-224 +	Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
Ra-226 +	Rn-222, Po-218, Pb-214, Bi-214, Po-214
Ra-226 + +	Rn-222, Po-218, Pb-214, Bi-214, Pb-210, Bi-210, Po-210, Po-214, Po-214, Po-214, Po-214
Ra-228 +	Ac-228
Ac-225 +	Fr-221, At-217, Bi-213, Po-213, Tl-209, Pb-209
Ac-227 +	Fr-223
Ac-227 + +	Fri-223, Th-227, Ra-223, Rn-219, Po-215, Pb-211, Bi-211, Tl-207, Po-211
Th-226 +	Ra-222, Rn-218, Po-214
Th-228 +	Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
Th-229 +	Ra-225, Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209
Th-232sec	Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212, Po-212, Po-212, Po-212, Po-212
Th-234 +	Pa-234m, Pa-234
U-230 +	Th-226, Ra-222, Rn-218, Po-214
U-232 +	Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212
U-235 +	Th-231
U-238 +	Th-234, Pa-234m, Pa-234
U-238sec	Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Pb-210, Bi-210, Po-210, Po-214
U-240 +	Np-240, Np-240m
Np-237 +	Pa-233
Pu-244 +	U-240, Np-240m, Np-240
Am-242m +	Np-238, Am-242
Am-243 +	Np-239
Cm-247 +	Pu-243
Cf-253 +	Cm-249
Es-254 +	Bk-250
Es-254m +	Bk-250, Fm-254

Table 3

Release of selected radionuclides
for free-giving masses up to 100 tonnes in the calendar year

If the mass to be expected in the calendar year is up to 100 tonnes, for the radionuclides in column 1 of the following table, instead of the free values of Table 1, column 5 of this Regulation, the free values of column 2 of this table may be used for the the unrestricted release of:

Radionuclide Unrestricted Release of solid and liquid substances with a mass to be expected to be released in the calendar year of up to 100 t/a in Bq/g 12

Cl-36	3
Mn-53	6 E + 2
Ni-59	3 E + 3
As-74	1 E + 1
Sr-90 +	6
Mon-93	4 E + 1
Tc-97	6 E + 1
Tc-99	6
Sn-125	6 E + 1
I-129	6 E-1
Cs-136	9
Ba-131 +	4 E + 1
Ir-194	6
Hg-203	7 E + 1
Tl-202	4 E + 1
U-235 +	3
Pu-237	5 E + 2

Unofficial table of contents

Annex IV (to § 29)
Release considerations

(Fundstelle: BGBl. I 2001, 1802-1803;
with regard to of the individual amendments. Footnote) Part A: General

1.

Unless otherwise specified in the following Parts B to G, the following shall apply:

a): The method for the verification of compliance with the free values depends on the type and nature of the substances.
b): The verification of compliance with the respective free values and, if there is a solid surface area where contamination measurement is possible, the compliance with the surface contamination levels, shall be carried out on the basis of measurements; in the Individual cases may also be approved by the competent authority.
c): The average mass to be used for the determination of the specific activity must not exceed 300 kg.
d): The averaging area for surface contamination may be up to 1 000 qcm.
e): In the case of a number of radionuclides, the sum of the ratios Ci /Ri from the specific activity (Ci) to be released and the respective free-gas values (Ri) of the individual radionuclides in accordance with Annex III, Table 1, column 5, 6, 7, 9a, 9b, 9c, 9d or column 10a to be calculated (empirical formula), where i is the respective radionuclide. This sum shall not exceed 1: PDF document is displayed in your own window In the case of a plurality of radionuclides, the sum of the ratios of As, i /Oi from the existing activity per unit area (As, i) and the respective values of the surface contamination (Oi) of the individual radionuclides according to Appendix III, Table 1, column 4, 8 or column 10 (summary formula): PDF document is displayed in your own window Nuclides need not be taken into account in the sum formation if the share of the unaccounted nuclides in the total sum of the allocated ratios Ci /Ri or As, i /Oi does not give the relative error of the total of 10 percent exceeds.
f): Where radionuclides are present in the radioactive balance, the subsidiary nuclides listed in Table 2 of Annex III shall not be taken into account in the sum formulae referred to in point (e).
g): Where, in Annex III, Table 1, column 5, 6, 8, 9a, 9b, 9c, 9d, 10 or column 10a for radionuclides, no free values are given, they shall be calculated on a case-by-case basis. In the case of radionuclides whose half-life is less than 7 days, or in the case of small masses, the corresponding free limits of Appendix III, Table 1, column 3 may be used as the free values of columns 5, 9a or column 9b.

2.

To the extent that proof that only an effective dose of 10 microsieverts in the calendar year can occur for individuals of the population is carried out on a case-by-case basis, the assumptions of Annex VII, Part B and C, in particular the provisions of Annex VII, Part B, Table 1, column 1 to 7, on condition that the routes of exposure laid down in Annex VII, Part A, are relevant for the individual case in accordance with Article 29 (2) sentence 3. The release of liquid substances on a case-by-case basis pursuant to Article 29 (2), third sentence, shall be based on the values of Annex VII, Part D, Table 4, column 3, in so far as they could be derived. In the event of a release of land, only such exposure paths shall be disregarded, which are excluded on the basis of the existing location characteristics, in particular the geographical location and the geogenic conditions.

Part B: Unrestricted Release
Unconditional release does not require any provisions regarding the future use, use, recovery, recycling, disposal or final whereabouts of the substances for which an effective determination pursuant to Article 29 (3) is made. . The values of Annex III, Table 1, column 5 shall apply to:

1.: solid substances,
2.: Construction debris and excavation, if the mass to be released is not more than 1 000 tonnes in the calendar year, and
3.: Oils and oil-containing liquids, organic solvents and coolants.

Part C: Release for disposal

1.

A release for disposal requires that the substances for which an effective determination has been made in accordance with Article 29 (3) be deposited or installed in a landfill or disposed of in an incineration plant. Recovery or re-use outside a landfill or incineration plant, as well as the re-entry of substances into the economic cycle, must be excluded.

2.

The values of Annex III, Table 1, column 9a to 9d shall not apply to construction debris and excavation of the soil if the mass to be released may be more than 1 000 tonnes in the calendar year.

3.

As landfill sites for the disposal of released substances, only those disposal facilities are suitable, which at least meet the requirements of the landfill classes pursuant to § 2 number 7 to 10 of the Landfill Ordinance of 27 April 2009 (BGBl. 900), as last amended by Article 5 (11) of the Regulation of 26 November 2010 (BGBl I). 1643), and an annual capacity of at least 10 000 tonnes in the calendar year (Mg/a) or 7 600 cubic metres per calendar year (m³ /a) for the quantity of waste deposited, averaged over the last three years, .

4.

By way of derogation from point 2 and part A (1) (e), first sentence in the case of several radionuclides, the sum of the ratios of Ci /Ri from the group shall be released and disposed of in a calendar year more than 1 000 tonnes. the specific activity (Ci) to be released and the individual rates (Ri) of each radionuclide i in accordance with Annex III, Table 1, column 9c or column 9d, multiplied by one thousandth of the mass to be released. This sum shall not exceed 1: PDF document is displayed in your own window By way of derogation from point 1 (e) of Part A (1) (e) (1) for a number of radionuclides, if both masses of radionuclides under the conditions of column 9a and column 9c for disposal are to be released in a landfill in a calendar year, the first sentence of point 1 shall be: Sum of the products of the ratios Ci /Ri from the specific activity (Ci) to be released and the individual rates (Ri) of the individual radionuclides in accordance with Annex III, Table 1, column 9a, multiplied by one hundredth of the the mass to be released and the product of the ratios Ci /Ri from the specific Activity (Ci) and the respective free-gas rate (Ri) of the individual radionuclides according to Appendix III, Table 1, column 9c, multiplied by one thousandth of the mass to be released. This sum shall not exceed 1: PDF document is displayed in your own window In the case of a release for disposal in an incineration plant in accordance with the provisions of column 9b or column 9d, the rates 3 and 4 shall apply accordingly, d. h. for the sum: PDF document is displayed in your own window Where:

Ci: Mean specific activity of the radionuclide i released and released in the current calendar year in Bq/g and Ci < Ri
M: Mass of substances released and released in the current calendar year in tonnes
Ri: The release value according to Appendix III, Table 1, column 9a, 9b, 9c or column 9d for the respective radionuclide i in Bq/g.

Part D: Release of buildings

1.: The term "building" comprises individual buildings, rooms, parts of space and components.
2.: The free measurement of a building is to be carried out in principle on the standing structure. The measurements may be carried out on the basis of a suitable sampling procedure.
3.: The central area to be used may be up to 1 sqm.
4.: If a subsequent re-use or re-use of the building cannot be ruled out, the surface contamination values shall not exceed the values of Annex III, Table 1, column 8.
5.: If the building is to be demolited after the free measurement, the surface contamination values shall not exceed the values of Annex III, Table 1, column 10. In duly substantiated cases, the competent authority may allow larger averaging areas of 1 m2.
6.: After the release of a building, in particular due to demolition of a building debris, no separate release is required.
7.: In the case of volume-borne activity by activation, the parts B, C or F are used.

Part E: Release of ground surfaces

1.

For surface-based free values, the averaging area for surface contamination may be up to 100 square meters. Alternatively, in the case of mass-based release values, the average mass to be used for the determination of the specific activity may be up to one tonne.

2.

Only the contamination caused by the facilities or facilities on the premises shall be taken into account.

3.

To the extent that, in Annex III, Table 1, column 7, no free values are indicated, it is necessary to demonstrate that a small dose is to be expected for individuals of the population in individual cases. In this case, the uses of the ground surfaces to be released must be taken into account in accordance with the respective location conditions and the exposure paths which are relevant in this case.

4.

The proof referred to in point 3 shall be provided on the basis of measurements taken by means of dose calculations.

5.

The free values of Appendix III, Table 1, column 7, can be converted into area-based free values according to the following equation: O (deep) i = R (deep) i x p x d.Where:

O (deep) i: the release value for soil surfaces for the respective radionuclide i in Bq/qcm,
R (deep) i: the soil release value for the respective radionuclide i in Bq/g in accordance with Annex III, Table 1, column 7,
p: the mean soil density in g/cm3 in depth d and
d: the mean penetration depth in cm.

Part F: Release of construction debris and excavation

1.: The values of Annex III, Table 1, column 6 shall apply to construction debris and excavated excavated work, or to the demolition of buildings or parts of the plant, provided that the conditions of a free measurement of the standing structure are in accordance with D are not fulfilled.
2.: In the case of a free measurement of construction debris and excavation of the soil, the mean mass may be up to 1 tonne. In duly substantiated cases, the competent authority may authorise higher averaging.

Part G: Release of scrap metal for re-cycling

1.: A release of scrap metal for the recycle requires that the scrap metal for which an effective determination has been made in accordance with § 29 (3) be melted.
2.: The values of Annex III, Table 1, column 10a do not apply to composite materials consisting of metallic and non-metallic components.
3.: Only those melting plants are suitable in which a mixing ratio of 1:10 of released metal scrap to other metals can be guaranteed or which have a throughput of at least 40 000 tonnes in the calendar year.

Unofficial table of contents

Annex V (to § 25)
Requirements for the type approval of devices

(Fundstelle: BGBl. I 2001, 1804;
with regard to of the individual amendments. Footnote)

Part A:: Equipment and other devices into which radioactive substances are inserted

1.

Only other radioactive substances may be inserted in accordance with Article 2 (1) of the Atomic Energy Act, which

a): and
b): Covered with contact

2.

The local dose rate at a distance of 0.1 m from the touchable surface of the device shall not exceed 1 microsievert by hour under normal operating conditions.

3.

The device shall be designed in such a way as to ensure a safe containment of the radioactive substances during the intended operation within the intended useful life and, in addition to the acceptance test by the manufacturer and, where appropriate, to In accordance with § 27 (6), there is no need for further leak tests on the radioactive substances inserted into the device.

4.

The activity of the radioactive substances inserted into the device shall not exceed ten times the free limits of Annex III, Table 1, column 2.

5.

There must be an adequate quality assurance programme which is based on international or national standards.

Part B:: Installations for the production of ionizing radiation

The local dose rate at a distance of 0.1 m from the touchable surface of the device shall not exceed 1 microsievert by hour under normal operating conditions.

Part C:: Application documents for type approval pursuant to § 25

1.

Drawings required for type-examination,

2.

descriptions of the design, the mode of operation and the purpose of use and, if necessary, indications concerning the type of recurrent leak test in accordance with Article 27 (6),

3.

Information on quality assurance and

4.

Information on the recycling of the device containing radioactive substances to the authorisation holder or to the disposal of such equipment.

Unofficial table of contents

Annex VI (to § § 3, 47, 49, 55, 95, 117)
Dosimetry sizes, tissue and radiation weighting factors

Source of the original text: BGBl. I 2001, 1805-1807

Part A:: Measured variables for external radiation

Measurement variables for external radiation are

1.: for personal dosimetry, the low-person dose H (deep) p (10) and the surface-to-person dose H (deep) p (0.07). The depth-of-person dose H (deep) p (10) is the equivalent dose in the body at the support point of the person dosimeter in a depth of 10 millimetres. The surface-to-person dose H (deep) p (0.07) is the equivalent dose of 0.07 millimeter deep in the body at the carrying point of the person dosimeter;
2.: for local dosimetry, the ambient equivalent dose H* (10) and the directional equivalent dose H ' (0.07, omega). The ambient equivalent dose H* (10) at the point of interest in the actual radiation field is the dose equivalent of the dose equivalent to the dose of H* (10). aligned and expanded radiation field at a depth of 10 millimetres on the radius of the ICRU sphere, which is oriented opposite to the direction of incidence of the radiation. The directional equivalent dose H ' (0.07, omega) at the point of interest in the actual radiation field is the equivalent dose, which in the associated flared radiation field is 0.07 millimeter deep on a fixed direction Omega. oriented radius of the ICRU sphere would be created.

Where:

-: an expanded radiation field is an idealized radiation field, in which the particle flux density and the energy and direction distribution of the radiation at all points of a sufficiently large volume have the same values as the actual radiation field. Radiation field at the point of interest,
-: an expanded and directional field is an idealized radiation field that is expanded and in which the radiation is additionally oriented in one direction,
-: the ICRU sphere is a spherical phantom of 30 centimetres in diameter of ICRU soft tissue (tissue equivalent material of density 1 g/cm3, composition: 76.2% oxygen, 11.1% carbon, 10.1% hydrogen, 2.6% nitrogen).

The unit of the equivalent dose is the Sievert (unit character Sv).

Part B:: Calculation of body dose

1.

Calculation of the organdosis H (deep) TThe Organdosis H (deep) T, R is the product of the absorbed dose of the tissue or organ T, the organ-absorbed dose D (deep) T, R generated by the radiation R, and the radiation weighting factor W (deep) R according to Part C Number 1:

 H (deep) T, R = W (deep) R x D (deep) T, R.

: If the radiation is composed of species and energies with different values of W (deep) R, then the individual contributions are added. For the entire Organdosis H (deep) T, the following applies:

 H (deep) T = sum W (deep) R D (deep) T, R. 
 R

: The unit of the Organdosis is the Sievert (unit symbol Sv). As far as values or limits for the organdosis of the skin are established in § § 36, 46, 47, 49, 54, 55 and 58, they refer to the local skin dose. The local skin dose is the product of the averaged energy dose of the skin in 0.07 mm tissue depth with the radiation weighting factor according to Part C. The averaging area is 1 qcm, independent of the exposed skin area.
2.: Calculation of the effective dose EThe effective dose E is the sum of the organdoses H (deep) T multiplied by the associated tissue weighting factor W (deep) T as defined in Part C, point 2. In this case, all the organs listed in Part C, point 2, and To sum the fabric.

 E = Total W (deep) T H (low) T = Total W (low) T Total W (deep) R D (deep) T, R. 
 T T R

: The unit of effective dose is the Sievert (unit character Sv). In determining the effective dose, the skin's energy dose is 0.07 millimeter of tissue depth over the entire skin.
3.: Calculation of exposure to radiation by incorporated or submersionIn the calculation of the exposure to radiation by means of incorporation or submersion, the dose coefficients from the compilation in the Federal Gazette No. 160a and b of 28 August 2001 are Part II or III, unless the competent authority decides otherwise.
4.: Calculation of the outer radiation exposure of the unborn child The organdosis of the mother's uterus is considered to be the equivalent dose of the unborn child in the case of external exposure.
5.: Calculation of the internal radiation exposure of the unborn child Inner radiation exposure is considered to be the effective follow-up dose of the pregnant woman due to the activity intake, as a dose of the unborn child, to the extent that the competent authority nothing else.

Part C:: Values of the radiation weighting factor and the tissue weighting factor

1.

Radiation weighting factor W (deep) RThe values of the radiation weighting factor W (deep) R depend on the nature and quality of the external radiation field or on the nature and quality of the radiation emitted by an incorporated radionuclide.

Type and energy range radiation weighting factor W (deep) R

Photons, all energies		1
Electrons and muons, all energies		1
Neutrons, energy	< 10 keV	5
	10 keV to 100 keV	10
	> 100 keV up to 2 MeV	20
	> 2 MeV to 20 MeV	10
	> 20 MeV	5
Protons, except recoil protons, energy > 2 MeV		5
Alpha particles, split fragments, heavy nuclei		20

For the calculation of organdoses and the effective dose for neutron radiation, the steady function

: W (deep) R = 5 + 17e (high)-(In (2E (deep) n)) (high) 2/6

, where E (deep) n is the numerical value of the neutron energy in MeV. For the radiation types and energies not included in the table, W (deep) R can be equated with the mean quality factor Q-at a depth of 10 mm in an ICRU sphere.

2.

Tissue weighting factor W (deep) T

Tissue or organetissue weighting factors W (deep) T

Germ glands	0.20
Bone marrow (red)	0.12
Thick intestine	0.12
Lungs	0.12
Stomach	0.12
Bubble	0.05
Chest	0.05
Liver	0.05
Esophagus	0.05
Thyroid	0.05
Skin	0.01
Bone surface	0.01
Other organs or tissues ¹¹⁾ , ²²⁾	0.05

22): In the exceptional cases where a single one of the other organs or tissues receives an equivalent dose above the highest dose level in one of the 12 organs or tissues for which a weighting factor is indicated, a weighting factor should be used. of 0.025 for this organ or tissue, and a weighting factor of 0.025 for the mean organdosis of the remaining organs or tissues.
11): For calculation purposes other organs or tissues are put together as follows: adrenal gland, brain, small intestine, kidney, muscle, pancreas, spleen, thymus gland and uterus.

Part D:: Calculation of the organ follow-up dose and the effective follow-up dose

1.

Calculation of the organ-Follow-up dose H (deep) T (Tau) The organ-Follow-up dose H (deep) T (Tau) is the time integral of the organ dose rate in the tissue or organ T, which a person receives as a result of an incorporation of radioactive substances:

 t (deep) O + Tau 
 H (deep) T (Tau) = ...  H (deep) T (t) dt 
 t (deep) O

for an incorporation at time t (deep) O with

H (deep) T (t): Mean organ dose rate in tissue or organ T at time t
Tau: Period indicated in years on which the integration is successful. If no value is given for tau, for adults a period of 50 years and for children of the period from their respective age up to the age of 70 is basically to be legend.The unit of Organ-Follow-up dose is the Sievert (unit character Sv).

2.

Calculation of the effective follow-up dose E (deep) (Tau) The effective follow-up dose E (deep) (Tau) is the sum of the organ secondary doses H (deep) T (Tau), each multiplied by the associated tissue weighting factor W (deep) T according to Part C, point 2. Part C, point 2, to sum up the organs and tissues.

 E (Tau) = Sum W (deep) T H (deep) T (Tau) 
 T

: The unit of the effective follow-up dose is the Sievert (unit symbol Sv). H (deep) T (Tau) and Tau see number 1.

Unofficial table of contents

Annex VII (to § § 29 and 47)
Assumptions in the determination of radiation exposure

(Fundstelle: BGBl. I 2001, 1808-1825;
with regard to of the individual amendments. Footnote)

Part A:: Exposure paths

1.

In the case of discharge with air:

1.1

Exposure to beta-radiation within the exhaust-air vane

1.2

Exposure due to gamma radiation from the exhaust air vane

1.3

Exposure to gamma radiation of the radioactive substances deposited on the ground

1.4

Exposure to the intake of radioactive substances with food (ingestion) on the way

1.4.1: Air-Plant
1.4.2: Air-fodder plant-cow-milk
1.4.3: Air-fodder plant-animal-meat
1.4.4: Air-breast milk
1.4.5: Air-Food-breast milk

1.5

Exposure to exposure of radioactive substances to the respiratory air (inhalation).

2.

When draining with water:

2.1

Exposure through stay on sediment

2.2

Exposure to the intake of radioactive substances with food (ingestion) on the way

2.2.1: Drinking water
2.2.2: Water-fish
2.2.3: Cattle drowns-cow milk
2.2.4: Cattle ranch-animal-meat
2.2.5: Beregnung-Fodder plant-Kuh-milk
2.2.6: Beregnung-Fodder plant-Animal-Meat
2.2.7: Beregnung plant
2.2.8: Breast milk as a result of the intake of radioactive substances by the mother over the above-mentioned ingestion pathways.

Exposure paths shall not be taken into account or additional exposure paths shall be taken into account where this is due to the local characteristics of the site or the nature of the facility or body.

Part B:: Life habits

Table 1
Average consumption rates of the reference person in kg/a
1	2	3	4	5	6	7	8
Age group	< = 1 year	> 1-< = 2 years	> 2-< = 7 years	> 7-< = 12 years	> 12-< = 17 years	> 17 years
Food
Drinking water	55 3)	100	100	150	200	350	2
Breast milk, milk-based products with drinking water	200 3, 4)	-	-	-	-	-	1.6
Milk, milk products	45	160	160	170	170	130	3
Fish 5)	0.5	3	3	4.5	5	7.5	5
Meat, sausages, eggs	5	13	50	65	80	90	2
3) Quantity in (l/a) The annual drinking water quantity of the infant is 55 l/a, 160 l/a, if it is assumed that the infant is not breastfed, but only receives dairy products which are produced supraregional and are to be regarded as non-contaminated. It is assumed that 0.2 kg of concentrate (equivalent to 1 l of milk) is dissolved in 0.8 l of water. 4) Depending on the nuclide composition, the most unfavourable dietary variant should be used. 5) The share of freshwater fish in the total fish consumption is on average approx. 17% and should be adapted to regional specificities.
Average consumption rates of the reference person in kg/a
Cereals, cereal products	12	30	80	95	110	110	2
Domestic fresh fruit, fruit products, juices	25	45	65	65	60	35	3
Potatoes, root vegetables, juices	30	40	45	55	55	55	3
Leafy vegetables	3	6	7	9	11	13	3
Vegetables, vegetable products, juices	5	17	30	35	35	40	3

Table 2
Age group	< = 1 year	> 1-< = 2 years	> 2-< = 7 years	> 7-< = 12 years	> 12-< = 17 years	> 17 years
Breathing rate in cbm/year	1 100	1 900	3 200	5 640	7 300	8 100

Table 3
Periods of stay						Duration
Exposure paths a) Beta radiation within the exhaust air vane						1 year
b) Gamma radiation from the exhaust air vane						1 year
c) Gamma radiation of the radioactive substances deposited on the ground						1 year
d) Inhalation of radioactive substances						1 year
e) Stay on Sediment						1 000 hours

Part C:: Other assumptions

1.

In order to determine the exposure to radiation, the dose coefficients from the compilation in Federal Gazette No 160a and b of 28 August 2001, Part I, II, IV and V, shall be used.

2.

In order to determine the exposure to radiation, models which describe a state of equilibrium are to be assumed. The expected fluctuations of radioactive discharges are to be taken into account by a suitable choice of the calculation parameters.

3.

In the case of discharges with air, the dispersion calculation shall be based on the Gaussian model and a long-standing weather statistics. On a case-by-case basis, the competent authority may order or permit the application of other procedures to take account of the specific features of the site or of the installation or establishment. In the case of discharges with water, the calculation of long-time mean values of the water management of the curator shall be used.

4.

The determination of parameter values is to be taken in conjunction with the calculation models in such a way that an underestimation of the radiation exposure is not to be expected in the overall result. If parameters are to be taken into account for the determination of the radiation exposure, the numerical values of which are subject to a fluctuation range, extreme values of the individual parameters may only be selected in justified exceptional cases.

Part D:: Maximum permitted activity concentration from radiation protection areas

In the case of several radionuclides, the sum of the ratio numbers from the mean, annual concentration of the radionuclides is in air, or in water in Bq/cbm (C-(deep) i, a) and the calculated mean annual concentration value of the respective radionuclide (C (deep) i) of Table 4 or 5 (empirical formula), where i is the respective radionuclide. This sum shall not exceed 1:

 - 
 C (deep) i, a 
 Total ----------- < = 1. 
 i C (deep) i

Subsidiary nuclides shall be taken into account.

1.

Maximum permitted activity concentration in the air from radiation protection areas

1.1

InhalationThe activity of the radionuclide i on an annual average in cubic metres of air

1.1.1: for locomotor streams Q < = 10 (high) 4 cbm h (high) -1 shall not be higher than 10 times the respective values of Table 4, column 2 or table 6, column 2, or
1.1.2: 10 (high) 4 cbm h (high) -1 < Q < = 10 (high) 5 cbm h (high) -1 shall not be higher than the respective values of column 2 of Tables 4 or 6;

1.2

SubmersionThe activity of the radionuclide i on an annual average in cubic metres of air

1.2.1: for locomotor streams Q < = 10 (high) 4 cbm h (high) -1 shall not be higher than 10 times the values of Table 5, column 2, or
1.2.2: For further air currents 10 (high) 4 cbm h (high) -1 < Q < = 10 (high) 5 cbm h (high) -1 shall not be higher than the values of Table 5 column 2.

2.

Maximum permitted activity concentration in the water, which is initiated from radiation protection areas in sewer

2.1

IngestionThe activity of the radionuclide i in the annual average in the cubic meter of water may

2.1.1: for waste water volumes < = 10 (high) 5 cbm a (high) -1 shall not be higher than 10 times the respective values of Table 4, column 3 or Table 6, column 4, or
2.1.2: for wastewater quantities > 10 (high) 5 cbm a (high) -1 shall not be higher than the respective values of Table 4, column 3 or Table 6, column 4.

Table 4 Activity concentration C (deep) i from radiation protection areas (for Annex VII, Part D, Nos 1.1 and 2)
Radionuclide		C (deep) i
A = Aerosol (air) E = elemental (air) O = organic		in the air in Bq/cbm	in water in Bq/cbm

1		2	3
H-3	A	1 E + 2	1 E + 7
H-3	O		7 E + 6
Be-7	A	6 E + 2	5 E + 6
Be-10	A	1	6 E + 4
C-11	A	6 E + 2	3 E + 6
C-14	A	6	6 E + 5
F-18	A	5 E + 2	2 E + 6
Na-22	A	1	4 E + 4
Na-24	A	9 E + 1	3 E + 5
Mg-28	A	2 E + 1	7 E + 4
Al-26	A	5 E-1	1 E + 4
Si-31	A	3 E + 2	5 E + 5
Si-32	A	3 E-1	1 E + 5
P-32	A	1	3 E + 4
P-33	A	2 E + 1	3 E + 5
S-35	A	2 E + 1	7 E + 5
S-35	O		1 E + 5
Cl-36	A	1 E-1	1 E + 4
Cl-38	A	5 E + 2	6 E + 5
Cl-39	A	6 E + 2	9 E + 5
K-42	A	2 E + 2	2 E + 5
K-43	A	2 E + 2	4 E + 5
K-44	A	1 E + 3	9 E + 5
K-45	A	2 E + 3	1 E + 6
Ca-41	A	3	3 E + 5
Ca-45	A	2	8 E + 4
Ca-47	A	2 E + 1	7 E + 4
Sc-43	A	2 E + 2	5 E + 5
Sc-44	A	1 E + 2	3 E + 5
Sc-44m	A	2 E + 1	4 E + 4
Sc-46	A	5	8 E + 4
Sc-47	A	4 E + 1	1 E + 5
Sc-48	A	3 E + 1	7 E + 4
Sc-49	A	7 E + 2	9 E + 5
Ti-44	A	3 E-1	2 E + 4
Ti-45	A	3 E + 2	6 E + 5
V-47	A	8 E + 2	1 E + 6
V-48	A	1 E + 1	6 E + 4
V-49	A	8 E + 2	2 E + 6
Cr-48	A	1 E + 2	6 E + 5
Cr-49	A	8 E + 2	1 E + 6
Cr-51	A	8 E + 2	3 E + 6
Mn-51	A	6 E + 2	8 E + 5
Mn-52	A	2 E + 1	7 E + 4
Mn-52m	A	8 E + 2	1 E + 6
Mn-53	A	2 E + 2	2 E + 6
Mn-54	A	2 E + 1	2 E + 5
Mn-56	A	2 E + 2	3 E + 5
Fe-52	A	4 E + 1	7 E + 4
Fe-55	A	2 E + 1	1 E + 5
Fe-59	A	8	2 E + 4
Fe-60	A	1 E-1	1 E + 3
Co-55	A	5 E + 1	2 E + 5
Co-56	A	5	4 E + 4
Co-57	A	3 E + 1	3 E + 5
Co-58	A	2 E + 1	1 E + 5
Co-58m	A	2 E + 3	4 E + 6
Co-60	A	1	2 E + 4
Co-60m	A	2 E + 4	4 E + 7
Co-61	A	6 E + 2	1 E + 6
Co-62m	A	1 E + 3	1 E + 6
Ni-56	A	3 E + 1	2 E + 5
Ni-57	A	5 E + 1	1 E + 5
Ni-59	A	8 E + 1	1 E + 6
Ni-63	A	3 E + 1	6 E + 5
Ni-65	A	3 E + 2	4 E + 5
Ni-66	A	2 E + 1	3 E + 4
Cu-60	A	7 E + 2	1 E + 6
Cu-61	A	4 E + 2	1 E + 6
Cu-64	A	3 E + 2	2 E + 6
Cu-67	A	5 E + 1	4 E + 5
Zn-62	A	5 E + 1	2 E + 5
Zn-63	A	7 E + 2	1 E + 6
Zn-65	A	3	3 E + 4
Zn-69	A	1 E + 3	3 E + 6
Zn-69m	A	9 E + 1	7 E + 5
Zn-71m	A	2 E + 2	6 E + 5
Zn-72	A	2 E + 1	1 E + 5
Ga-65	A	1 E + 3	2 E + 6
Ga-66	A	5 E + 1	7 E + 4
Ga-67	A	1 E + 2	5 E + 5
Ga-68	A	5 E + 2	7 E + 5
Ga-70	A	2 E + 3	2 E + 6
Ga-72	A	5 E + 1	9 E + 4
Ga-73	A	2 E + 2	3 E + 5
Ge-66	A	3 E + 2	1 E + 6
Ge-67	A	1 E + 3	1 E + 6
Ge-68	A	3	7 E + 4
Ge-69	A	1 E + 2	4 E + 5
Ge-71	A	2 E + 3	7 E + 6
Ge-75	A	8 E + 2	2 E + 6
Ge-77	A	9 E + 1	3 E + 5
Ge-78	A	3 E + 2	7 E + 5
As-69	A	1 E + 3	1 E + 6
As-70	A	4 E + 2	7 E + 5
As-71	A	8 E + 1	3 E + 5
As-72	A	3 E + 1	8 E + 4
As-73	A	3 E + 1	3 E + 5
As-74	A	2 E + 1	9 E + 4
As-76	A	3 E + 1	9 E + 4
As-77	A	8 E + 1	3 E + 5
As-78	A	3 E + 2	4 E + 5
Se-70	A	3 E + 2	9 E + 5
Se-73	A	1 E + 2	6 E + 5
Se-73m	A	1 E + 3	3 E + 6
Se-75	A	2	4 E + 4
Se-79	A	4 E-2	5 E + 3
Se-81	A	2 E + 3	3 E + 6
Se-81m	A	6 E + 2	2 E + 6
Se-83	A	8 E + 2	2 E + 6
Br-74	A	6 E + 2	1 E + 6
Br-74m	A	4 E + 2	6 E + 5
Br-75	A	5 E + 2	1 E + 6
Br-76	A	7 E + 1	2 E + 5
Br-77	A	3 E + 2	1 E + 6
Br-80	A	2 E + 3	2 E + 6
Br-80m	A	4 E + 2	6 E + 5
Br-82	A	5 E + 1	1 E + 5
Br-83	A	7 E + 2	2 E + 6
Br-84	A	7 E + 2	9 E + 5
Rb-79	A	1 E + 3	2 E + 6
Rb-81	A	6 E + 2	2 E + 6
Rb-81m	A	3 E + 3	8 E + 6
Rb-82m	A	2 E + 2	1 E + 6
Rb-83	A	2 E + 1	8 E + 4
Rb-84	A	2 E + 1	4 E + 4
Rb-86	A	1 E + 1	3 E + 4
Rb-87	A	8 E-1	6 E + 4
Rb-88	A	1 E + 3	8 E + 5
Rb-89	A	2 E + 3	2 E + 6
Sr-80	A	2 E + 2	2 E + 5
Sr-81	A	7 E + 2	1 E + 6
Sr-82	A	3	1 E + 4
Sr-83	A	8 E + 1	3 E + 5
Sr-85	A	4 E + 1	1 E + 5
Sr-85m	A	6 E + 3	2 E + 7
Sr-87m	A	1 E + 3	4 E + 6
Sr-89	A	4	3 E + 4
Sr-90	A	1 E-1	4 E + 3
Sr-91	A	6 E + 1	2 E + 5
Sr-92	A	1 E + 2	3 E + 5
Y-86	A	5 E + 1	1 E + 5
Y-86m	A	9 E + 2	2 E + 6
Y-87	A	7 E + 1	2 E + 5
Y-88	A	8	1 E + 5
Y-90	A	2 E + 1	3 E + 4
Y-90m	A	3 E + 2	5 E + 5
Y-91	A	4	3 E + 4
Y-91m	A	3 E + 3	1 E + 7
Y-92	A	1 E + 2	2 E + 5
Y-93	A	5 E + 1	6 E + 4
Y-94	A	8 E + 2	9 E + 5
Y-95	A	2 E + 3	2 E + 6
Zr-86	A	6 E + 1	1 E + 5
Zr-88	A	1 E + 1	3 E + 5
Zr-89	A	5 E + 1	1 E + 5
Zr-93	A	1	4 E + 5
Zr-95	A	6	1 E + 5
Zr-97	A	3 E + 1	4 E + 4
Nb-88	A	9 E + 2	1 E + 6
Nb-89	A	2 E + 2	3 E + 5
Nb-90	A	4 E + 1	8 E + 4
Nb-93m	A	2 E + 1	6 E + 5
Nb-94	A	8 E-1	6 E + 4
Nb-95	A	2 E + 1	2 E + 5
Nb-95m	A	4 E + 1	1 E + 5
Nb-96	A	4 E + 1	1 E + 5
Nb-97	A	6 E + 2	1 E + 6
Nb-98m	A	4 E + 2	7 E + 5
Mon-90	A	8 E + 1	5 E + 5
Mon-93	A	2 E + 1	1 E + 5
Mo-93m	A	2 E + 2	1 E + 6
Mon-99	A	3 E + 1	2 E + 5
Mon-101	A	1 E + 3	2 E + 6
Tc-93	A	7 E + 2	3 E + 6
Tc-93m	A	1 E + 3	4 E + 6
Tc-94	A	2 E + 2	7 E + 5
Tc-94m	A	5 E + 2	7 E + 5
Tc-95	A	2 E + 2	9 E + 5
Tc-95m	A	3 E + 1	2 E + 5
Tc-96	A	4 E + 1	1 E + 5
Tc-96m	A	4 E + 3	9 E + 6
Tc-97m	A	8	1 E + 5
Tc-97	A	2 E + 1	9 E + 5
Tc-98	A	8 E-1	4 E + 4
Tc-99	A	3	9 E + 4
Tc-99m	A	2 E + 3	4 E + 6
Tc-101	A	2 E + 3	4 E + 6
Tc-104	A	8 E + 2	9 E + 5
Ru-94	A	5 E + 2	1 E + 6
Ru-97	A	3 E + 2	7 E + 5
Ru-103	A	1 E + 1	1 E + 5
Ru-105	A	2 E + 2	3 E + 5
Ru-106	A	6 E-1	1 E + 4
Rh-99	A	4 E + 1	2 E + 5
Rh-99m	A	6 E + 2	2 E + 6
Rh-100	A	7 E + 1	2 E + 5
Rh-101	A	7	2 E + 5
Rh-101m	A	1 E + 2	5 E + 5
Rh-102	A	2	5 E + 4
Rh-102m	A	5	7 E + 4
Rh-103m	A	1 E + 4	2 E + 7
Rh-105	A	9 E + 1	2 E + 5
Rh-106m	A	2 E + 2	6 E + 5
Rh-107	A	2 E + 3	3 E + 6
Pd-100	A	4 E + 1	1 E + 5
Pd-101	A	4 E + 2	1 E + 6
Pd-103	A	8 E + 1	4 E + 5
Pd-107	A	6 E + 1	2 E + 6
Pd-109	A	8 E + 1	1 E + 5
Ag-102	A	1 E + 3	2 E + 6
Ag-103	A	1 E + 3	2 E + 6
Ag-104	A	7 E + 2	2 E + 6
Ag-104m	A	9 E + 2	2 E + 6
Ag-105	A	1 E + 1	2 E + 5
Ag-106	A	2 E + 3	2 E + 6
Ag-106m	A	9	9 E + 4
Ag-108m	A	4 E-1	4 E + 4
Ag-110m	A	1	4 E + 4
Ag-111	A	3	6 E + 4
Ag-112	A	1 E + 2	2 E + 5
Ag-115	A	9 E + 2	1 E + 6
Cd-104	A	7 E + 2	2 E + 6
Cd-107	A	4 E + 2	1 E + 6
Cd-109	A	4	4 E + 4
Cd-113	A	1 E-1	9 E + 3
Cd-113m	A	2 E-1	7 E + 3
Cd-115	A	3 E + 1	6 E + 4
Cd-115m	A	5	2 E + 4
Cd-117	A	2 E + 2	3 E + 5
Cd-117m	A	1 E + 2	3 E + 5
In-109	A	6 E + 2	2 E + 6
In-110	A	2 E + 2	6 E + 5
In-111	A	1 E + 2	4 E + 5
In-112	A	4 E + 3	7 E + 6
In-113m	A	1 E + 3	3 E + 6
In-114m	A	2	2 E + 4
In-115m	A	5 E + 2	9 E + 5
In-116m	A	6 E + 2	2 E + 6
In-117	A	1 E + 3	3 E + 6
In-117m	A	4 E + 2	6 E + 5
In-119m	A	1 E + 3	2 E + 6
Sn-110	A	1 E + 2	3 E + 5
Sn-111	A	2 E + 3	4 E + 6
Sn-113	A	1 E + 1	1 E + 5
Sn-117m	A	1 E + 1	1 E + 5
Sn-119m	A	2 E + 1	2 E + 5
Sn-121	A	1 E + 2	3 E + 5
Sn-121m	A	4	2 E + 5
Sn-123	A	3	4 E + 4
Sn-123m	A	1 E + 3	2 E + 6
Sn-125	A	1 E + 1	3 E + 4
Sn-126	A	1	2 E + 4
Sn-127	A	2 E + 2	4 E + 5
Sn-128	A	3 E + 2	6 E + 5
Sb-115	A	2 E + 3	4 E + 6
Sb-116	A	2 E + 3	3 E + 6
Sb-116m	A	5 E + 2	2 E + 6
Sb-117	A	2 E + 3	6 E + 6
Sb-118m	A	2 E + 2	7 E + 5
Sb-119	A	5 E + 2	1 E + 6
Sb-120	A	3 E + 1	1 E + 5
Sb-122	A	3 E + 1	5 E + 4
Sb-124	A	4	4 E + 4
Sb-124m	A	5 E + 3	1 E + 7
Sb-125	A	3	8 E + 4
Sb-126	A	4 E-1	4 E + 4
Sb-126m	A	1 E + 3	2 E + 6
Sb-127	A	2 E + 1	5 E + 4
Sb-128	A	6 E + 1	1 E + 5
Sb-129	A	1 E + 2	2 E + 5
Sb-130	A	5 E + 2	1 E + 6
Sb-131	A	6 E + 2	8 E + 5
Te-116	A	2 E + 2	6 E + 5
Te-121	A	7 E + 1	3 E + 5
Te-121m	A	4	3 E + 4
Te-123	A	7 E-2	3 E + 4
Te-123m	A	6	5 E + 4
Te-125m	A	8	7 E + 4
Te-127	A	2 E + 2	6 E + 5
Te-127m	A	2	2 E + 4
Te-129	A	7 E + 2	1 E + 6
Te-129m	A	4	2 E + 4
Te-131	A	8 E + 2	1 E + 6
Te-131m	A	2 E + 1	4 E + 4
Te-132	A	9	2 E + 4
Te-133	A	8 E + 2	1 E + 6
Te-133m	A	2 E + 2	3 E + 5
Te-134	A	4 E + 2	8 E + 5
I-120	E	5 E + 1	2 E + 5
I-120m	E	1 E + 2	4 E + 5
I-121	E	2 E + 2	1 E + 6
I-123	E	7 E + 1	4 E + 5
I-124	E	1	7 E + 3
I-125	E	5 E-1	2 E + 4
I-126	E	3 E-1	4 E + 3
I-128	E	4 E + 2	2 E + 6
I-129	E	3 E-2	4 E + 3
I-130	E	8	4 E + 4
I-131	E	5 E-1	5 E + 3
I-132	E	5 E + 1	3 E + 5
I-132m	E	5 E + 1	4 E + 5
I-133	E	3	2 E + 4
I-134	E	2 E + 2	8 E + 5
I-135	E	1 E + 1	9 E + 4
Cs-125	A	1 E + 3	2 E + 6
Cs-127	A	7 E + 2	5 E + 6
Cs-129	A	3 E + 2	2 E + 6
Cs-130	A	2 E + 3	3 E + 6
Cs-131	A	6 E + 2	2 E + 6
Cs-132	A	1 E + 2	3 E + 5
Cs-134	A	2	2 E + 4
Cs-134m	A	6 E + 2	4 E + 6
Cs-135	A	4	2 E + 5
Cs-135m	A	2 E + 3	7 E + 6
Cs-136	A	1 E + 1	6 E + 4
Cs-137	A	9 E-1	3 E + 4
Cs-138	A	6 E + 2	8 E + 5
Ba-126	A	2 E + 2	3 E + 5
Ba-128	A	2 E + 1	4 E + 4
Ba-131	A	4 E + 1	2 E + 5
Ba-131m	A	4 E + 3	2 E + 7
Ba-133	A	4	4 E + 4
Ba-133m	A	7 E + 1	2 E + 5
Ba-135m	A	8 E + 1	3 E + 5
Ba-139	A	4 E + 2	6 E + 5
Ba-140	A	6	3 E + 4
Ba-141	A	8 E + 2	1 E + 6
Ba-142	A	1 E + 3	3 E + 6
La-131	A	1 E + 3	3 E + 6
La-132	A	1 E + 2	2 E + 5
La-135	A	2 E + 3	3 E + 6
La-137	A	4	8 E + 5
La-138	A	2 E-1	1 E + 4
La-140	A	3 E + 1	4 E + 4
La-141	A	2 E + 2	2 E + 5
La-142	A	3 E + 2	5 E + 5
La-143	A	1 E + 3	1 E + 6
Ce-134	A	2 E + 1	3 E + 4
Ce-135	A	6 E + 1	1 E + 5
Ce-137	A	2 E + 3	3 E + 6
Ce-137m	A	7 E + 1	1 E + 5
Ce-139	A	2 E + 1	3 E + 5
Ce-141	A	9	1 E + 5
Ce-143	A	4 E + 1	7 E + 4
Ce-144	A	6 E-1	1 E + 4
Pr-136	A	2 E + 3	2 E + 6
Pr-137	A	1 E + 3	2 E + 6
Pr-138m	A	3 E + 2	9 E + 5
Pr-139	A	1 E + 3	3 E + 6
Pr-142	A	4 E + 1	6 E + 4
Pr-142m	A	3 E + 3	4 E + 6
Pr-143	A	1 E + 1	6 E + 4
Pr-144	A	1 E + 3	1 E + 6
Pr-145	A	1 E + 2	2 E + 5
Pr-147	A	1 E + 3	2 E + 6
Nd-136	A	5 E + 2	9 E + 5
Nd-138	A	9 E + 1	1 E + 5
Nd-139	A	2 E + 3	4 E + 6
Nd-139m	A	2 E + 2	4 E + 5
Nd-141	A	5 E + 3	1 E + 7
Nd-147	A	1 E + 1	7 E + 4
Nd-149	A	3 E + 2	6 E + 5
Nd-151	A	2 E + 3	3 E + 6
Pm-141	A	2 E + 3	2 E + 6
Pm-143	A	2 E + 1	5 E + 5
Pm-144	A	4	1 E + 5
Pm-145	A	1 E + 1	6 E + 5
Pm-146	A	2	9 E + 4
Pm-147	A	7	3 E + 5
Pm-148	A	1 E + 1	3 E + 4
Pm-148m	A	6	6 E + 4
Pm-149	A	4 E + 1	7 E + 4
Pm-150	A	2 E + 2	3 E + 5
Pm-151	A	6 E + 1	1 E + 5
Sm-141	A	2 E + 3	2 E + 6
Sm-141m	A	8 E + 2	1 E + 6
Sm-142	A	3 E + 2	4 E + 5
Sm-145	A	2 E + 1	4 E + 5
Sm-146	A	3 E-3	6 E + 2
Sm-151	A	9	6 E + 5
Sm-153	A	5 E + 1	1 E + 5
Sm-155	A	2 E + 3	3 E + 6
Sm-156	A	1 E + 2	3 E + 5
Eu-145	A	5 E + 1	2 E + 5
Eu-146	A	4 E + 1	1 E + 5
Eu-147	A	3 E + 1	2 E + 5
Eu-148	A	1 E + 1	1 E + 5
Eu-149	A	1 E + 2	9 E + 5
Eu-150	A	7 E-1	3 E + 4
Eu-152	A	9 E-1	5 E + 4
Eu-152m	A	1 E + 2	2 E + 5
Eu-154	A	7 E-1	4 E + 4
Eu-155	A	5	2 E + 5
Eu-156	A	1 E + 1	4 E + 4
Eu-157	A	8 E + 1	1 E + 5
Eu-158	A	5 E + 2	8 E + 5
Gd-145	A	1 E + 3	2 E + 6
Gd-146	A	5	9 E + 4
Gd-147	A	7 E + 1	2 E + 5
Gd-148	A	1 E-3	5 E + 2
Gd-149	A	4 E + 1	2 E + 5
Gd-151	A	3 E + 1	4 E + 5
Gd-153	A	1 E + 1	3 E + 5
Gd-159	A	1 E + 2	2 E + 5
Tb-147	A	3 E + 2	6 E + 5
Tb-149	A	7	4 E + 5
Tb-150	A	2 E + 2	4 E + 5
Tb-151	A	1 E + 2	3 E + 5
Tb-153	A	1 E + 2	4 E + 5
Tb-154	A	8 E + 1	2 E + 5
Tb-155	A	2 E + 2	5 E + 5
Tb-156	A	3 E + 1	1 E + 5
Tb-156m	A	2 E + 2	6 E + 5
Tb-157	A	3 E + 1	2 E + 6
Tb-158	A	8 E-1	4 E + 4
Tb-160	A	5	6 E + 4
Tb-161	A	3 E + 1	1 E + 5
Dy-155	A	4 E + 2	9 E + 5
Dy-157	A	8 E + 2	2 E + 6
Dy-159	A	9 E + 1	9 E + 5
Dy-165	A	5 E + 2	7 E + 5
Dy-166	A	2 E + 1	5 E + 4
Ho-155	A	1 E + 3	2 E + 6
Ho-157	A	6 E + 3	2 E + 7
Ho-159	A	5 E + 3	1 E + 7
Ho-161	A	4 E + 3	6 E + 6
Ho-162	A	1 E + 4	3 E + 7
Ho-162m	A	1 E + 3	4 E + 6
Ho-164	A	4 E + 3	7 E + 6
Ho-164m	A	3 E + 3	4 E + 6
Ho-166	A	4 E + 1	6 E + 4
Ho-166m	A	3 E-1	2 E + 4
Ho-167	A	4 E + 2	1 E + 6
Er-161	A	5 E + 2	1 E + 6
He-165	A	3 E + 3	5 E + 6
Er-169	A	3 E + 1	2 E + 5
He-171	A	1 E + 2	2 E + 5
He-172	A	3 E + 1	9 E + 4
Tm-162	A	2 E + 3	3 E + 6
Tm-166	A	2 E + 2	4 E + 5
Tm-167	A	3 E + 1	2 E + 5
Tm-170	A	5	6 E + 4
Tm-171	A	3 E + 1	6 E + 5
Tm-172	A	3 E + 1	5 E + 4
Tm-173	A	2 E + 2	3 E + 5
Tm-175	A	1 E + 3	3 E + 6
Yb-162	A	2 E + 3	4 E + 6
Yb-166	A	4 E + 1	1 E + 5
Yb-167	A	5 E + 3	1 E + 7
Yb-169	A	1 E + 1	1 E + 5
Yb-175	A	4 E + 1	2 E + 5
Yb-177	A	4 E + 2	9 E + 5
Yb-178	A	4 E + 2	6 E + 5
Lu-169	A	8 E + 1	3 E + 5
Lu-170	A	4 E + 1	1 E + 5
Lu-171	A	4 E + 1	2 E + 5
Lu-172	A	2 E + 1	9 E + 4
Lu-173	A	1 E + 1	3 E + 5
Lu-174	A	8	3 E + 5
Lu-174m	A	8	1 E + 5
Lu-176m	A	3 E + 2	4 E + 5
Lu-177	A	3 E + 1	1 E + 5
Lu-177m	A	2	5 E + 4
Lu-178	A	1 E + 3	2 E + 6
Lu-178m	A	8 E + 2	2 E + 6
Lu-179	A	2 E + 2	4 E + 5
Hf-170	A	9 E + 1	2 E + 5
Hf-172	A	1	5 E + 4
Hf-173	A	2 E + 2	5 E + 5
Hf-175	A	3 E + 1	2 E + 5
Hf-177m	A	3 E + 2	1 E + 6
Hf-178m	A	1 E-1	1 E + 4
Hf-179m	A	9	7 E + 4
Hf-180m	A	2 E + 2	6 E + 5
Hf-181	A	7	7 E + 4
Hf-182	A	1 E-1	2 E + 4
Hf-182m	A	7 E + 2	2 E + 6
Hf-183	A	5 E + 2	1 E + 6
Hf-184	A	9 E + 1	2 E + 5
Ta-172	A	8 E + 2	2 E + 6
Ta-173	A	2 E + 2	4 E + 5
Ta-174	A	7 E + 2	1 E + 6
Ta-175	A	2 E + 2	6 E + 5
Ta-176	A	1 E + 2	4 E + 5
Ta-177	A	3 E + 2	9 E + 5
Ta-178	A	4 E + 2	1 E + 6
Ta-179	A	6 E + 1	1 E + 6
Ta-180m	A	7 E + 2	2 E + 6
Ta-182	A	3	6 E + 4
Ta-182m	A	1 E + 3	6 E + 6
Ta-183	A	2 E + 1	6 E + 4
Ta-184	A	7 E + 1	2 E + 6
Ta-185	A	6 E + 2	1 E + 6
Ta-186	A	1 E + 3	2 E + 6
W-176	A	6 E + 2	1 E + 6
W-177	A	1 E + 3	2 E + 6
W-178	A	3 E + 2	5 E + 5
W-179	A	2 E + 4	3 E + 7
W-181	A	4 E + 2	1 E + 6
W-185	A	6 E + 1	2 E + 5
W-187	A	1 E + 2	2 E + 5
W-188	A	3 E + 1	4 E + 4
Re-177	A	2 E + 3	4 E + 6
Re-178	A	2 E + 3	3 E + 6
Re-181	A	1 E + 2	2 E + 5
Re-182	A	2 E + 1	6 E + 4
Re-184	A	2 E + 1	1 E + 5
Re-184m	A	5	5 E + 4
Re-186	A	3 E + 1	5 E + 4
Re-186m	A	1	3 E + 4
Re-187	A	7 E + 2	1 E + 7
Re-188	A	4 E + 1	5 E + 4
Re-188m	A	2 E + 3	2 E + 6
Re-189	A	6 E + 1	9 E + 4
Os-180	A	2 E + 3	6 E + 6
Os-181	A	4 E + 2	1 E + 6
Os-182	A	8 E + 1	2 E + 5
Os-185	A	2 E + 1	2 E + 5
Os-189m	A	4 E + 3	4 E + 6
Os-191	A	2 E + 1	1 E + 5
Os-191m	A	2 E + 2	8 E + 5
Os-193	A	6 E + 1	1 E + 5
Os-194	A	4 E-1	3 E + 4
Ir-182	A	1 E + 3	2 E + 6
Ir-184	A	2 E + 2	6 E + 5
Ir-185	A	2 E + 2	4 E + 5
Ir-186	A	9 E + 1	2 E + 5
Ir-187	A	4 E + 2	8 E + 5
Ir-188	A	7 E + 1	2 E + 5
Ir-189	A	6 E + 1	4 E + 5
Ir-190	A	1 E + 1	9 E + 4
Ir-190m	A	3 E + 2	9 E + 5
Ir-192	A	5	7 E + 4
Ir-192m	A	9 E-1	7 E + 4
Ir-193m	A	3 E + 1	3 E + 5
Ir-194	A	4 E + 1	6 E + 4
Ir-194m	A	3	5 E + 4
Ir-195	A	4 E + 2	7 E + 5
Ir-195m	A	2 E + 2	4 E + 5
Pt-186	A	7 E + 2	1 E + 6
Pt-188	A	6 E + 1	1 E + 5
Pt-189	A	5 E + 2	8 E + 5
Pt-191	A	2 E + 2	3 E + 5
Pt-193	A	2 E + 1	2 E + 6
Pt-193m	A	1 E + 2	2 E + 5
Pt-195m	A	9 E + 1	1 E + 5
Pt-197	A	2 E + 2	2 E + 5
Pt-197m	A	9 E + 2	9 E + 5
Pt-199	A	2 E + 3	2 E + 6
Pt-200	A	9 E + 1	6 E + 4
Au-193	A	3 E + 2	7 E + 5
Au-194	A	1 E + 2	3 E + 5
Au-195	A	2 E + 1	4 E + 5
Au-198	A	4 E + 1	9 E + 4
Au-198m	A	2 E + 1	7 E + 4
Au-199	A	4 E + 1	2 E + 5
Au-200	A	8 E + 2	1 E + 6
Au-200m	A	4 E + 1	1 E + 5
Au-201	A	2 E + 3	3 E + 6
Hg-193	A	4 E + 2	3 E + 6
Hg-193	O	9 E + 2	1 E + 6
Hg-193m	A	1 E + 2	3 E + 5
Hg-193m	O	2 E + 2	8 E + 5
Hg-194	A	1	1 E + 5
Hg-194	O	4 E-1	7 E + 3
Hg-195	A	4 E + 2	9 E + 5
Hg-195	O	9 E + 2	3 E + 6
Hg-195m	A	6 E + 1	2 E + 5
Hg-195m	O	2 E + 2	4 E + 5
Hg-197	A	1 E + 2	4 E + 5
Hg-197	O	4 E + 2	9 E + 5
Hg-197m	A	6 E + 1	2 E + 5
Hg-197m	O	2 E + 2	6 E + 5
Hg-199m	A	9 E + 2	2 E + 6
Hg-199m	O	2 E + 3	3 E + 6
Hg-203	A	1 E + 1	2 E + 5
Hg-203	O	1 E + 1	6 E + 4
Tl-194	A	5 E + 3	1 E + 7
Tl-194m	A	1 E + 3	2 E + 6
Tl-195	A	2 E + 3	4 E + 6
Tl-197	A	2 E + 3	4 E + 6
Tl-198	A	4 E + 2	2 E + 6
Tl-198m	A	6 E + 2	2 E + 6
Tl-199	A	1 E + 3	4 E + 6
Tl-200	A	2 E + 2	7 E + 5
Tl-201	A	5 E + 2	1 E + 6
Tl-202	A	1 E + 2	3 E + 5
Tl-204	A	1 E + 1	7 E + 4
Pb-195m	A	1 E + 3	3 E + 6
Pb-198	A	4 E + 2	2 E + 6
Pb-199	A	7 E + 2	3 E + 6
Pb-200	A	9 E + 1	4 E + 5
Pb-201	A	2 E + 2	9 E + 5
Pb-202	A	2	3 E + 4
Pb-202m	A	3 E + 2	1 E + 6
Pb-203	A	1 E + 2	6 E + 5
Pb-205	A	4 E + 1	4 E + 5
Pb-209	A	5 E + 2	2 E + 6
Pb-210	A	7 E-3	1 E + 2
Pb-211	A	3	3 E + 5
Pb-212	A	2 E-1	6 E + 3
Pb-214	A	2	3 E + 5
Bi-200	A	8 E + 2	2 E + 6
Bi-201	A	4 E + 2	9 E + 5
Bi-202	A	5 E + 2	1 E + 6
Bi-203	A	1 E + 2	3 E + 5
Bi-205	A	3 E + 1	1 E + 5
Bi-206	A	2 E + 1	6 E + 4
Bi-207	A	1	9 E + 4
Bi-210	A	4 E-1	6 E + 4
Bi-210m	A	1 E-2	4 E + 3
Bi-212	A	1	3 E + 5
Bi-213	A	1	4 E + 5
Bi-214	A	2	6 E + 5
Po-203	A	7 E + 2	3 E + 6
Po-205	A	4 E + 2	3 E + 6
Po-207	A	3 E + 2	2 E + 6
Po-210	A	8 E-3	3 E + 1
At-207	A	1 E + 1	4 E + 5
At-211	A	3 E-1	7 E + 3
Fr-222	A	3	1 E + 5
Fr-223	A	2 E + 1	3 E + 4
Ra-223	A	4 E-3	2 E + 2
Ra-224	A	1 E-2	3 E + 2
Ra-225	A	4 E-3	1 E + 2
Ra-226	A	4 E-3	2 E + 2
Ra-227	A	8 E + 1	8 E + 5
Ra-228	A	2 E-3	3 E + 1
Ac-224	A	3 E-1	9 E + 4
Ac-225	A	4 E-3	2 E + 3
Ac-226	A	3 E-2	6 E + 3
Ac-227	A	7 E-5	3 E + 1
Ac-228	A	9 E-1	1 E + 5
Th-226	A	5 E-1	2 E + 5
Th-227	A	3 E-3	3 E + 1
Th-228	A	9 E-4	2 E + 2
Th-229	A	2 E-4	8 E + 1
Th-230	A	4 E-4	2 E + 2
Th-231	A	9 E + 1	2 E + 5
Th-232	A	3 E-4	2 E + 2
Th-234	A	5	2 E + 4
Pa-227	A	5 E-1	2 E + 5
Pa-228	A	5 E-1	7 E + 4
Pa-230	A	4 E-2	3 E + 4
Pa-231	A	3 E-4	7 E + 1
Pa-232	A	4	1 E + 5
Pa-233	A	8	9 E + 4
Pa-234	A	8 E + 1	2 E + 5
U-230	A	2 E-3	1 E + 3
U-231	A	8 E + 1	3 E + 5
U-232	A	1 E-3	4 E + 2
U-233	A	4 E-3	2 E + 3
U-234	A	4 E-3	2 E + 3
U-235	A	4 E-3	3 E + 3
U-236	A	4 E-3	3 E + 3
U-237	A	2 E + 1	1 E + 5
U-238	A	5 E-3	3 E + 3
U-239	A	1 E + 3	3 E + 6
U-240	A	5 E + 1	7 E + 4
Np-232	A	3 E + 2	1 E + 7
Np-233	A	1 E + 4	4 E + 7
Np-234	A	5 E + 1	1 E + 5
Np-235	A	5 E + 1	1 E + 6
Np-236	A	5 E-3	5 E + 3
Np-237	A	7 E-4	4 E + 2
Np-238	A	1 E + 1	9 E + 4
Np-239	A	3 E + 1	1 E + 5
Np-240	A	3 E + 2	1 E + 6
Pu-234	A	1	4 E + 5
Pu-235	A	2 E + 4	4 E + 7
Pu-236	A	9 E-4	4 E + 2
Pu-237	A	9 E + 1	8 E + 5
Pu-238	A	3 E-4	2 E + 2
Pu-239	A	3 E-4	2 E + 2
Pu-240	A	3 E-4	2 E + 2
Pu-241	A	2 E-2	2 E + 4
Pu-242	A	3 E-4	2 E + 2
Pu-243	A	4 E + 2	9 E + 5
Pu-244	A	3 E-4	2 E + 2
Pu-245	A	6 E + 1	1 E + 5
Pu-246	A	4	3 E + 4
Am-237	A	1 E + 3	5 E + 6
Am-238	A	2 E + 2	4 E + 6
Am-239	A	1 E + 2	3 E + 5
Am-240	A	7 E + 1	2 E + 5
Am-241	A	4 E-4	2 E + 2
Am-242	A	2	2 E + 5
Am-242m	A	4 E-4	3 E + 2
Am-243	A	4 E-4	3 E + 2
Am-244	A	1 E + 1	2 E + 5
Am-244m	A	2 E + 2	2 E + 6
Am-245	A	6 E + 2	1 E + 6
Am-246	A	4 E + 2	1 E + 6
Am-246m	A	1 E + 3	2 E + 6
Cm-238	A	7	1 E + 6
Cm-240	A	1 E-2	4 E + 3
Cm-241	A	9 E-1	8 E + 4
Cm-242	A	6 E-3	2 E + 3
Cm-243	A	5 E-4	3 E + 2
Cm-244	A	6 E-4	3 E + 2
Cm-245	A	4 E-4	2 E + 2
Cm-246	A	4 E-4	2 E + 2
Cm-247	A	4 E-4	3 E + 2
Cm-248	A	1 E-4	6 E + 1
Cm-249	A	9 E + 2	2 E + 6
Cm-250	A	2 E-5	1 E + 1
Bk-245	A	2 E + 1	1 E + 5
Bk-246	A	9 E + 1	2 E + 5
Bk-247	A	5 E-4	1 E + 2
Bk-249	A	2 E-1	4 E + 4
Bk-250	A	4 E + 1	6 E + 5
Cf-244	A	3	9 E + 5
Cf-246	A	7 E-2	2 E + 4
Cf-248	A	4 E-3	6 E + 2
Cf-249	A	5 E-4	1 E + 2
Cf-250	A	1 E-3	2 E + 2
Cf-251	A	5 E-4	1 E + 2
Cf-252	A	2 E-3	2 E + 2
Cf-253	A	2 E-2	9 E + 3
Cf-254	A	8 E-4	8 E + 1
Es-250	A	6 E + 1	4 E + 6
Es-251	A	2 E + 1	5 E + 5
Es-253	A	1 E-2	5 E + 3
Es-254	A	4 E-3	6 E + 2
Es-254m	A	7 E-2	2 E + 4
Fm-252	A	1 E-1	2 E + 4
Fm-253	A	8 E-2	4 E + 4
Fm-254	A	5 E-1	2 E + 5
Fm-255	A	1 E-1	3 E + 4
Fm-257	A	5 E-3	9 E + 2
Md-257	A	1	3 E + 5
Md-258	A	6 E-3	1 E + 3

Table 5 Activity concentration C (deep) i from radiation protection areas (to Appendix VII, Part D, point 1.2) RadionuclidC (deep) i in the air in Bq/cbm 12

C-11	3 E + 3
N-13	2 E + 3
O-15	1 E + 3
Ar-37	2 E + 8
Ar-39	6 E + 3
Ar-41	2 E + 2
Kr-74	2 E + 2
Kr-76	5 E + 2
Kr-77	2 E + 2
Kr-79	9 E + 2
Kr-81m	5 E + 6
Kr-81	4 E + 4
Kr-83m	4 E + 6
Kr-85	4 E + 3
Kr-85m	1 E + 3
Kr-87	2 E + 2
Kr-88	1 E + 2
Xe-120	6 E + 2
Xe-121	1 E + 2
Xe-122	3 E + 3
Xe-123	3 E + 2
Xe-125	9 E + 2
Xe-127	9 E + 2
Xe-129m	1 E + 4
Xe-131m	2 E + 4
Xe-133	7 E + 3
Xe-133m	7 E + 3
Xe-135m	5 E + 2
Xe-135	9 E + 2
Xe-138	2 E + 2

Table 6 Activity concentration C (deep) i from radiation protection areas (to Appendix VII, Part D, No. 1.1 and 2) Radionuclide gemischC (deep) i in the air in Bq/cbm radionuclide mixture (deep) i in water in Bq/cbm 1234

Any mixture	1 E-5	Any mixture	1 E + 1
Any mixture if Ac-227 and Cm-250 cannot be taken into account	1 E-4	Any mixture, if Po-210, Ra-228, Ac-227, Cm-250 can be disregarded	5 E + l
Any mixture if Ac-227, Th-229, Th-230, Th-232, Pa-231, Pu-238, Pu-239, Pu-240, Pu-242, Pu-244, Am-241, Am-242m, Am-243, Cm-245, Cm-246, Cm-247, Cm-248, Cm-250 cannot be taken into account.	5 E-4	Any mixture, if Po-210, Ra-228, Ac-227, Th-229, Pa-231, Cm-248, Cm-250, Bk-247, Cf-249, Cf-251, Cf-254 cannot be taken into account	1 E + 2
Any mixture, if Ac-227, Th-228, Th-229, Th-230, Th-232, Pa-231, U-232, Np-237, Pu-236, Pu-238, Pu-239, Pu-240, Pu-242, Pu-244, Am-241, Am-242m, Am-243, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cm-250, Bk-247, Cf-249, Cf-251, Cf-254. cannot be taken into account	1 E-3	Any mixture if Sm-146, Gd-148, Pb-210, po-210, ra-223, ra-224, ra-225, ra-226, ra-228, ac-227, th-228, th-229, th-230, th-232, Pa-231, U-232, Np-237, Pu-236, Pu-238, Pu-239, Pu-240, Pu-242, Pu-244, Am-241, Am-242m, Am-243, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cm-250, Bk-247, Cf-248, Cf-249, Cf-250, Cf-251, Cf-252, Cf-254, Es-254, Fm-257, can be disregarded	1 E + 3

Unofficial table of contents

Annex VIII (to § § 61, 62, 63)
Medical certificate according to § § 60, 61 StrlSchV

(Fundstelle: BGBl. I 2001, 1826;
with regard to of the individual amendments. Footnote)

 --------------------------------- 
I staff number I responsible for radiation protection 
(company, office, etc.)  I I I I I I I I I I I I I I I I I I 
 I ------------------------------- I 
 I, where appropriate, Registered No  I 
 I of the Radiation Pass I 
 I I I I I I I I I I I I I I I I I I 
 --------------------------------- 
 Name ....................... 
 First name ....................... 
 .  on ....................... 
 Street ....................... 
 Place of residence ....................... 
 ()  male ()  female 
 was from me 
 on the ................ 
Assessment 
------------------------------------------------------------------------ 
There is currently a job in the field of ionising 
Radiation 
I do not have any health concerns () 
II Health concerns 
 Activity in which the risk of incorporation 
 or contamination () 
 (e.g. handling of open radioactive substances) 
 Activity in the control sector, where the risk 
 the irradiation is external () 
 (e.g. handling of enclosed radioactive substances, 
 Photon radiation, neutron radiation, electron beams) 
Note: The assessment does not include other occupational health 
 Check-ups according to other legislation. 
  
 Holds the person responsible for radiation protection or the professional 
 Exposed person who is exposed to radiation by the physician according to § 64 (1) 
 Sentence 1 in the certificate according to § 61 of the assessment 
 , the decision of the competent authorities may 
 Authority to be applied for.  (Section 62 (1)) 
------------------------------------------------------------------------ 
Remarks: 
  

  
Next assessment or investigation: 
  
------------------------------------------------------------------------ 
Place, date Signature stamp with address of the 
 Doctor in accordance with § 64 (1) sentence 1

Unofficial table of contents

Annex IX (to § 68)
Radiolabel

Source of the original text: BGBl. I 2001, 1827 ... (Radiation sign not representable)
Hallmark: black
Background: yellow Unofficial table of contents

Appendix X (to § § 72 to 79)
Radioactive waste: designation, accounting, transport notification

(Fundstelle des Originaltextes: BGBl. I 2001, 1828-1831;
with regard to of the individual amendments. Footnote)

Part A: designation of radioactive waste
The designation of radioactive waste shall be carried out in accordance with the following coded information on the processing status, designation and treatment
Processing State		Label			Treatment
Code		Code			Code
1. Processing state
Code				Processing State
R				Rhabfall
Z				Intermediate
C				Conditioned waste (waste collection)
2. Name of the waste
Code	Label	Code	Label		Code	Label
A	Solid wastes inorganically	B	Solid waste organically		C	Liquid wastes inorganically
AA	Metals	PR	Readily flammable substances		CA	Chemical waste water
AAA	Ferritic metals	BAA	Paper		CAA	Operating waste water
AAB	Austenitic metals	BAB	Textiles		CAB	Process effluents
AAC	Non-ferrous metals	BAC	Wood		CAC	Decontamination effluents
AAD	Heavy metals	BAD	Plaster wool		CAD	Laboratory effluents
AAE	Light metals	BAE	Pulp		CAE	Evaporators concentrate
AAF	Galvanized steel	BAF	Slide		CAF	Heavy water (D (deep) 2O)
AAG	contaminated plant parts	BAG	Polyethylene		CAG	Acid
AAH	Sleeves and structural parts				CAH	Liquor
		BB	Substances which are difficult to burn
AB	Non-metals	BBA	Plastics (without PVC)		CB	sludges/suspensions
ABA	Building debris	BBB	PVC		CBA	Slurbations
ABB	Gravel, sand	BBC	Rubber		CBB	ion exchange/resin suspension
ABC	Earth	BBD	Activated carbon		CBC	Precipitation sludges
ABD	Glass	BBE	ion exchange resins		CBD	Swamp sludges
ABE	Ceramics	BBF	Paints, Colors		CBE	Decor residue
ABF	Insulation material	BBG	Chemicals		CBF	Feed sewage sludges
ABG	Cable	BBH	Kehricht
ABH	Glass wool				CC	Biological effluents
ABI	Graphite	BC	Filters		CCA	Medical effluents
ABJ	Asbestos, asbestos cement	BCA	Lab Filter		CCB	Pharmaceutical effluents
ABK	Chemicals	BCB	Air filter elements		CCC	Fecal effluents
		BCC	Boxing Filter
AC	Filters				CD	Cleavage product concentrates
ACA	Lab Filter	BD	Biological waste
ACB	Air filter elements	BDA	Kadaver
ACC	Boxing Filter	BDB	Medical waste
ACD	Filter candles
		BZ	Unsorted waste
AD	Filter Aids
ADA	ion exchangers
ADB	Kieselgur
ADC	Silica gel
ADD	Molecular sieve
Code	Label	Code	Label
AE	Other	D	Liquid waste organically
AEA	Ash	DA	Oils
AEB	Slag	DAA	Lubricating oils
AEC	Filter dust, fly ash	DAB	Hydraulic oils
AED	Salts	DAC	Transformer oils
AF	Nuclear fuel
AFA	Nuclear fuel unirradiated	DB	Solvent
AFB	Nuclear fuel irradiated	DBA	Alkanes
AFC	Reworked uranium	DBB	TBP
AFD	Reworked plutonium	DBC	Scintillation solution
AZ	Unsorted waste	DBD	Labelled liquids
		DBE	Kerosene
		DBF	Alcohols
		DBG	Aromatic hydrocarbons
		DBH	Halogenated hydrocarbons

		DC	Emulsions

		E	Gaseous wastes

		F	Mixed Waste (A-D)
		FA	ion exchangers/filter aids, salts
		FB	Ion exchange/filter aids, salts, solid wastes

		G	Radiation sources
		GA	Neutron sources
		GB	Gamma sources
		GC	Test radiators
		DG	Various sources
3. Treatment of waste
A waste is either as untreated waste (rust fall) before or as intermediate or end product of a previous process engineering treatment.
Code	Treatment
000	uninvolved
001	Sort
002	Decontaminate
003	Crushing
004	Pre-pressing
005	Burn
006	Pyrolysis
007	Evaporate/Distillation/Rectify
008	Decanting
009	Filter
010	Melting
011	Compact and dimensionally stable
012	Cementing
013	Bituminate
014	Vitriles
015	Drying
016	Compacting and cementing
017	Compacting and drying
018	Burning and compacting
019	Burning and compacting and cementing
020	Dewatering
021	Processes without physical or chemical change
022	Other business

Indicate the relevant procedure for the physical/chemical status of the waste to be identified, or the combination of procedures, if not already specified in the previously recorded predecessor. Part B: accounting of radioactive waste

1.

Identification Any radioactive waste incurred, which can be identified as a declarable unit and which is no longer subject to any operational change, shall be recorded and documented in the documentation with a unique identifier for each container or unit on the market. The identification has to be made by the following combination of letters and numbers:

: AA/BBB/CCCC/D/EEEFFF

The first two digits (AA) are letters and, in coded form, denote the erfasser of the data, the digits three to five (BBB) are also letters and represent the combination of the characteristic letters of the data. To be delivered/abducted (hereinafter referred to as the "polluter") of the waste, the digits six to nine are digits (CCCC) and the year in which the waste is recorded, the tenth digit (D) designates the State of processing (see Part A, No. 1), which can be used for internal encodings in the eleven to thirteen (EEE) positions and the digits fourteen to sixteen (FFF) stand for a serial number (if necessary, EEEFFF can be merged into a serial number). For the detection by the polluter, the letter E shall be used. Letters for other Erfasser are determined on request by the Federal Office for Radiation Protection. The German Federal Office for Radiation Protection also defines the characteristic letter combination BBB.

Example 1:

E 1) /KKW 2 )/1993 3) /R 4 )/000001 5)

1): E is responsible for the detection by the polluter.
2): KKW stands for the nuclear power plant as the "polluter" (alternatively XXX for the identification letter combination of another polluter).
3): 1993 stands for the year of collection.
4): R stands for the processing state (see Part A, No. 1).
5): 000001 stands for the current number within the year.

2.

Labelling of waste material The identification of a unit in the documentation is usually not identical with the labelling of the waste product. The labelling of the waste products to be delivered to a federal plant for the purpose of securing and disposal of radioactive waste shall be carried out in accordance with the following uniform system 6) :the combination of the characteristics of the polluter according to the following conditions: Determination by the Federal Office for Radiation Protection (Bundesamt für Strahlenschutz), serial number (seven-digit).

Example 2:

KKW 1 )/0000001 2)

1): KKW stands for the nuclear power plant as the "polluter" (alternatively XXX for the identification letter combination of another polluter).
2): 0000001 stands for the serial number.

3.

Identification of container containers intended for the collection or transport of radioactive waste must be provided with an unmistakable and permanent identification number.

4.

If a cross is entered in the following table, the indication of the type of waste in question shall be recorded, where applicable. For irradiated nuclear fuel as specified in paragraph 1, only the data set out in point 2 to point 18 shall apply.

Number	Indication per container or unit		Processing status of waste according to Appendix X Part A
			R	Z	C
1	Identifier		X	X	X
2	Origin (appendix/operating steep/system/other)		X
3	Designation in accordance with Annex X, Part A		X	X	X
4	Date of the seizage		X	X	X
5	Waste mass in kg		X	X	X
6	Container mass in kg			X	X
7	GebindeVolume in cbm			X	X
8	Container Type		X	X	X
9	Container labeling		X	X	X
10	Location dose rate to mSv/h	Surface	X	X	X
11	Location dose rate to mSv/h	1 m distance	X	X	X
12	Date of measurement of the local dose rate		X	X	X
13	Total Activity	Beta/Gamma- Radiators in Bq	X	X	X
14	Total Activity	Alpha- Radiators in Bq	X	X	X
15	Nuclear fuel in g		X	X	X
16.1	Activity of radionuclides to be taken into account in Bq 7)	No. 1	X	X	X
16.2		No. 2	X	X	X
16.n		N ° N	X	X	X
17	Activity reference date		X	X	X
18	Type of activity determination 8)		X	X	X
19	Reset Sample No.		X	X	X
20	Date of recording		X	X	X
21	Debiting Reference		X	X	X
22	Waste product 9)				X
23.1	Material composition 10) in kg	No. 1			X
23.2		No. 2			X
23.n		N ° N			X
24.1	Identification of the processed rust or intermediate product 9, 11)	No. 1		X	X
24.2		No. 2		X	X
24.n		N ° N		X	X
25	Classification of container 9)				X
26	Tightness of Packaging 9)				X
27	Detailed treatment procedures			X	X
28	Date of execution			X	X
29	Place of execution			X	X
30	Performer			X	X
31	Product control for the End Storage	Date of control			(x)
32	Product control for the End Storage	Reference			(x)
33	Staging Location		X	X	X
34	Invitation Date		X	X	X
(x) In the case of interim storage, only if required by the interim storage permit.
----------
6) Waste products originating from the reprocessing of spent fuel elements from nuclear power plants in the Federal Republic of Germany in plants of the Ausland may differ from this marking. 7) Specification of the respective equipment (conditioning site, interim storage facility, land register, final storage). 8) If the nature of the activity determination is not given under no. 16.1 to 16.n in terms of nuclide: M = measurement, B = calculation, A = estimation. 9) Designation or classification according to the definition by the Federal Office for Radiation Protection (Bundesamt für Strahlenschutz). 10) Subject to the provisions and conditions laid down in the plan determination decision for the proposed Federal End-of-State Camp. 11) Indicate the identifiers of the rohabfalls processed to the intermediate product, or the identifiers of the intermediate products processed to the waste product.

Part C:: Transport notification to the nuclear regulatory authority prior to the transport of radioactive waste

The declaration of transport to the nuclear regulatory authority prior to the transport of radioactive waste to section 75 (2) shall contain the following information:

1.: Date, place of departure and destination of the transport,
2.: the owner of the waste to be transported,
3.: Disposal of the waste to be transported in accordance with section 69 (3),
4.: the consignor of the waste to be transported in accordance with the rules relating to the transport of dangerous goods;
5.: the carrier/carrier and the number and date of issue of the transport permit;
6.: the recipient and the number and the date of issue of the authorisations pursuant to § § 6, 7 or 9 of the Atomic Energy Act or § § 7 or 11 (2) of this Regulation,
7.: Acceptance of the recipient,
8.: the type and number of containers/packaging to be transported,
9.: The nature, mass or volume and total activity of the other radioactive substances and the total mass of the nuclear fuel in accordance with Article 2 (1) sentence 2 of the Atomic Energy Act.

Unofficial table of contents

Annex XI (to § § 93, 95, 96)
Fields of work in which significantly increased exposures may occur due to natural terrestrial radiation sources

(Fundstelle: BGBl. I 2001, 1832;
with regard to of the individual amendments. Footnote)

Part A:: Working fields with increased radon 222 exposures

Working in

1.: Underground mines, shafts and caves, including visitor mines,
2.: Radon-healing baths and healing pollen,
3.: Plants for water extraction, treatment and distribution.

Part B:: Fields of work with increased exposures by uranium and thorium and their decay products

1.

Grinding and alternating current welding with thorised welding electrodes,

2.

Handling and storage of thorn gas glowing stockings,

3.

Use of thorium or uranium in the natural isotope composition, including the resulting daughter nuclides, if present, for chemical-analytical or chemical-preparative purposes.

4.

Handling, in particular assembly, disassembly, processing and inspection of products made of thorated alloys,

5.

Extraction, use and processing of pyrochlorores,

6.

Use and processing of slag from the smelting of copper slate ores.

Unofficial table of contents

Annex XII (to § § 97 to 102)
Recovery and disposal of residues in need of monitoring

(Fundstelle: BGBl. I 2001, 1833-1834;
with regard to of the individual amendments. Footnote)

Part A:: List of residues to be taken into consideration

1.

sludges and deposits from the extraction, processing and processing of crude oil and natural gas;

2.

Non-processed phosphogypsum, sludge from the preparation thereof and dusts and slags from the processing of crude phosphate (phosphorite);

3.

a)

Side rock, sludges, sands, slags and dusts

-: From the extraction and treatment of bauxite, Columbit, pyrochlore, microlyth, euxenite, copper slate, tin, rare earths and uranium ores
-: from the further processing of concentrates and residues resulting from the extraction and treatment of these ores and minerals, and

b)

Minerals corresponding to the ores mentioned above, which are produced in the extraction and processing of other raw materials;

4.

Dusts and sludges from flue gas cleaning in the primary distribution in pig iron and non-ferrous metallurgy.

Residues within the meaning of § 97 are also

a): the materials referred to in points 1ff., if the seizage of these materials is brought about in a purposefully effective manner,
b): Shaped pieces from the in numbers 1ff. as well as
c): Excavated or worn-out soil and construction debris from the demolition of buildings or other structural installations, if these residues are in accordance with the provisions of 1 et seq. in accordance with § 101 after termination of work or in accordance with Section 118 (5) of the Land of Land.

No residues within the meaning of section 97 are materials according to points 1 to 4,

a): whose specific activity for each radionuclide in the nuclide chains U-238sec and Th-232sec is less than 0.2 becquerel per gram (Bq/g), or
b): the technological processes referred to in these countries are used as raw materials.

The daughter nuclides to be considered in the nuclide chains U-238sec 12) and Th-232sec as well as in the case of Pb-210 + + are listed in Table 2 of Annex III.

Part B:: Monitoring limits for residues according to Part A

1.

In the recovery or disposal of residues, the largest specific activity of the radionuclides of the nuclide chains U-238sec and Th-232sec in becquerel by grams (Bq/g) shall apply to representative values of C (deep) U238max and C (deep) Th232max. the following summation formula: C (deep) U238max + C (deep) Th232max < = Cmit the monitoring limit C = 1 Bq/g.

2.

By way of derogation from point 1, C = 0.5 Bq/g, if:

a)

more than 5 000 tonnes of residues shall be deposited in the catchment area of a usable aquilot in the calendar year; or

b)

Building materials

aa): in the case of recovery in house construction, more than 20 per cent arrears or
bb): in the field of road, road, landscape or water construction in the field of sports and playgrounds or in other areas, more than 50 per cent of residues

is added.

The first sentence shall not apply to the exploitation of slag in road, road, landscape or water construction in other areas.

3.

By way of derogation from point 1, C = 5 Bq/g shall apply in the case of the underground recovery or disposal of residues.

4.

If the largest specific activity of the radionuclides of the Pb-210 + + is increased by a factor A greater than 5 in relation to the largest specific activity of the remaining radionuclides of the U-238sec-nuclide chain, the following shall apply by way of derogation from paragraphs 1 to 3 below: Empirical formula :R x C (deep) U238max + C (deep) Th232max < = C.The factor R assumes the value of 0.5 during the over-day recovery or disposal. For the subday recovery or disposal, the factor R can be found in the table below.

Factor Afactor R

5 < A < = 10	0.3
10 < A < = 20	0.2
20 < A	0.1
12) Expositions from the radionuclides of the U-235 series of decay are taken into account and do not have to be considered separately.

5.: By way of derogation from paragraphs 1 and 2, the conditions C (deep) U238max < = 0,2 Bq/g and C (deep) Th232max < = 0,2 Bq/g, if in the case of landfilling or exploitation in road, road or landscaping, including in the area of sports and playgrounds, in the catchment area an area of more than 1 hectare is occupied by a useful aquifers. If the specific activity for each radionuclide is one of the nuclide chains U-238sec or Th-232sec below 0.2 becquerel by gram (Bq/g), the unaccounted for the nuclide chain.

Part C:: Conditions for dismissal from the supervision of the joint landfilling of residues with other residues and waste in need of monitoring (Section 98 (2))

In the case of decisions pursuant to Section 98 (2) concerning the dismissal of residues from the surveillance for the purpose of joint landfilling with other residues and waste, the competent authority may, under the following conditions, assume that: Radiation exposures, which may occur as a result of this joint landfill, will not exceed an effective dose of 1 millisievert in the calendar year, even without further measures for individuals of the population:

1.: For the mean values C (high) M (deep) U238max and C (high) M (deep) Th232max of the specific activities of the radionuclides of the nuclide chains U-238sec and Th-232sec in Becquerel by gram (Bq/g) the following empirical formula applies: C (high) M (deep) U238max + C (high) M (deep) Th232max < = C(high) M.The averages C (high) M (deep) U238max and C (high) M (deep) Th232max of the specific activities may be considered to be the total activity of the monitoring residues in need of disposal within 12 months of the landfill. Part A and B of this Appendix divided by the total mass of all within this waste and waste disposal shall be determined at the disposal site. In the determination of the total activity, the greatest activity of the radionuclides of the nuclide chains U-238sec and Th-232sec is to be based on each of the following values:

C (high) M = 0,05 Bq/g	for landfills with a surface area of more than 15 hectares,
C (high) M = 0,1 Bq/g	for landfills with an area of up to 15 hectares,
C (high) M = 1 Bq/g	irrespective of the landfill site for landfills, where, due to the specific site conditions, groundwater charges can be excluded, and
C (high) M = 5 Bq/g	in the case of the underground elimination.

: In this case, the specific activity must not contain any radionuclide of the nuclide chains U-238sec and Th-232sec 10 becquerel by grams (Bq/g) or in the case of landfill sites for waste requiring special surveillance, 50 becquerels exceeding grams (Bq/g).
2.: If the largest specific activity of the radionuclides of the Pb-210 + + is increased by a factor A greater than 5 in relation to the specific activity of the remaining radionuclides of the U-238sec-nuclide chain in a residue batch, it may be used in the determination of the Total activity according to point 1, the activity of the radionuclides of the nuclide chain U-238sec for this batch is multiplied by a factor R. In the case of disposal of landfill sites, the factor R shall be 0.3. For the underground elimination, the factor R shall be taken from the table in Part B, point 4 of this Annex. If the specific activity for each radionuclide is one of the nuclide chains U-238sec or T-232sec in individual residues below 0.2. Becquerel by grams (Bq/g), the particular nuclide chain for this batch shall not be taken into account in the calculation of the total activity referred to in point 1.

Part D:: Principles for the determination of radiation exposures in the case of residues according to Part A

1.

Realistic exposure paths and exposure assumptions should be used in determining the exposure of individuals to radiation. In so far as the exposure paths are taken into account in accordance with Annex VII, Part A, the assumptions of Annex VII, Part B, Table 1, columns 1 to 7 and Table 2, shall be taken as a basis.

2.

In the case of the recovery of residues, in the determination of the exposure of individuals to the population, all exposures shall be included which are on the intended route of recovery, in particular through the production and placing on the market of products and the removal of other residues resulting from the removal of the product.

3.

In the event of the elimination of residues, the determination of the exposure of individuals to the population shall include all exposures on the intended disposal route by means of the treatment, storage and deposit of the Residues may occur.

4.

In the case of land contaminated by residues, the determination of the exposure to radiation in accordance with Section 101 (1) sentence 2 shall include all exposures which, in the case of realistic exploitation assumptions, shall be taken taking into account the natural nature of the natural gas. Location ratios may occur.

In this case, the dose coefficients from the compilation in Federal Gazette No 160a and (b) of 28 August 2001 are to be used. In the case of section 98 (2) sentence 2, the dose coefficients from the compilation in Federal Gazette No 160a and (b) of 28 August 2001 are to be used in Part I and III. Unofficial table of contents

Appendix XIII (to § § 51 and 53)
Information of the population

Source of the original text: BGBl. I 2001, 1835

Part A:: Information in case of a radiological emergency situation

(on § 51)

1.

The information to the general public shall be based on the following information, insofar as these are relevant in the event of a specific event:

a): information on the emergency situation and, where possible, on the characteristics of the emergency situation (such as origin, spread, probable development);
b): Protective instructions which, depending on the case, include, in particular, the restriction of the consumption of certain foodstuffs, which may be contaminated, simple hygiene and decontamination rules, the remaining in the house, the distribution and use of protective active substances, as well as arrangements for the evacuation of the substance, and, where appropriate, special instructions for certain groups of the population;
c): recommendations for cooperation within the framework of the instructions and calls made by the competent authorities;
d): Designation of the authorities responsible for public safety or order and civil protection.

2.

If the emergency situation is preceded by an advance warning level, the population, which may be affected in the event of a radiological emergency situation, is already receiving information and instructions at this stage, such as:

-: the invitation to switch on radio or television sets;
-: preparatory instructions for institutions which have to carry out specific Community tasks;
-: Recommendations for particularly affected professions.

3.

In addition to this information and instructions, the basic concepts of radioactivity and its effects on humans and the environment will be recalled, depending on the time available.

Part B:: Information in preparation for a radiological emergency situation

(on § 53)
The information must extend to:

1.: the name of the marketing authorisation holder and the indication of the location,
2.: the designation of the body providing the information;
3.: a general description of the nature and purpose of the installation and activity;
4.: Basic concepts of radioactivity and the effects of radioactivity on humans and the environment,
5.: radiological emergencies and their consequences for the population and the environment, including planned rescue and protection measures;
6.: adequate information as to how the persons concerned are to be warned and kept informed of the course of a radiological emergency situation,
7.: adequate information as to how the persons concerned should act and behave in the event of a radiological emergency situation,
8.: confirmation that the holder of the authorisation has taken appropriate measures at the site, including the link with the authorities responsible for public security or public order and civil protection, in order to ensure that the holder of the authorisation holder has a right to to be equipped with a radiological emergency and to keep their effects as low as possible,
9.: Notice of non-operational alarm and security plans drawn up for impact outside the site,
10.: Designation of the authorities responsible for public safety or order and civil protection.

Unofficial table of contents

Annex XIV (to section 48 (4)))
Federal guidelines for emission and immission monitoring

(Fundstelle des Originaltextes: BGBl. I 2001, 1836;
with regard to of the individual amendments. Footnote)
Control Environment Area

German Weather Service	Air, precipitation
Bundesanstalt für Geirrigkunde	Inland waters: surface water, sediment
Federal Office for Maritime Navigation and Hydrography	Coastal waters: surface water, sediment
Max Rubner-Institut, Federal Research Institute for Food and Food,	Soil plants, vegetation, animal feed of plant and animal origin
Johann Heinrich von Thünen-Institut, Bundesforschungsinstitut für Ländliche Räume, Wald und fishery,	Fish and fishery products
Federal Office for Radiation Protection	Local dose, local dose rate soil surface, groundwater, drinking water, sewage, sewage sludge, further air

Unofficial table of contents

Appendix XV (to § § 70, 70a and 71)
Standard recording sheet for high-level radioactive sources (HRQ)

(... non-representable standard collection sheet;
Fundstelle: BGBl. I 2005, 2404;
with regard to of the individual amendments. Footnote) Unofficial table of contents

Annex XVI (to § 4 (3))

(Fundstelle: BGBl. I 2011, 2047)
List of non-justified types of activity

Part A:: Use of radioactive substances or ionising radiation for the investigation or treatment of humans (medicine)

1.

Using

a): Iod-131 in the form of I-131-Orthoiodohippuric acid (IOH) and
b): Iod-125 in the form of I-125-Iothalamate (IOT), I-125-Orthoiodohippuric acid and I-125-diethylenetriaminepentaacetic acid (DTPA)

to study the kidneys,

2.

Use of iodine-125 in the form of I-125 fibrinogen for the study of deep vein thrombosis,

3.

Use of radium-226 in enclosed form for the treatment of human beings.

Part B:: Use of radioactive substances or ionising radiation outside medicine

1.

Use of overvoltage arresters with radioactive substances on high-voltage power poles,

2.

Use of open radioactive substances for leakage (water, heating, ventilation) or residence time spectroscopy, insofar as these substances are not subsequently collected again,

3.

Use of uranium-containing or thorium-containing substances in the production of colours for glazes, in so far as a contact of the product with food cannot be ruled out,

4.

Use of tritium gas sources for residual light amplification, unless necessary in the light of all the circumstances of the individual case in order to carry out the tasks of a host of public authority,

5.

Use of devices with firmly adhering radioactive luminescent colours, with the exception of

a): Plaques with tritium-containing luminescent colours in the professional, non-accessible area, and
b): Emergency equipment in aircraft with an airfare-related type approval,

6.

Use of high-level radioactive sources in the investigation of containers and vehicles outside the material test,

7.

Use of ionisation smoke detectors with a type approval pursuant to Annex VI, point 1 of the Radiation Protection Regulation, in the version valid until 30 July 2001,

8.

Use of enclosed radioactive substances or ionizing radiation in humans for access control or search of objects that a person is hiding on or in their body, unless the application is

a): is subject to a law and, taking into account all the circumstances of the individual case, is necessary for the discharge of public tasks, or
b): is absolutely necessary in the Division of the Federal Ministry of Defence for the purpose of defence or the fulfilment of intergovernmental obligations.