Advanced Search

Implementing provisions for the Regulation on the guarantee of nuclear safety and radiation protection

Original Language Title: Durchführungsbestimmung zur Verordnung über die Gewährleistung von Atomsicherheit und Strahlenschutz

Subscribe to a Global-Regulation Premium Membership Today!

Key Benefits:

Subscribe Now for only USD$40 per month.

Implementing provisions for the Regulation on the guarantee of nuclear safety and radiation protection

Unofficial table of contents

AtStrlSVDBest

Date of completion: 11.10.1984

Full quote:

" Implementation of the Regulation on the Safeguarding of Nuclear Safety and Radiation Protection of 11. October 1984 (GBl. GDR 1984 I p. 348) "

Footnote

The law of the former in the acceding area. German Democratic Republic gem. Appendix II. XII Sect. III No 2, in accordance with d. Art. 9 EinigVtr v. 31.8.1990 iVm Art. 1 G v. 23.9.1990 II 885, 1226 mWv 3.10.1990
(+ + + measures due to EinigVtr cf. AtStrlSVDBest Appendix EV + + +)
(+ + + Text proof applicable: 3.10.1990 + + +) Unofficial table of contents

Input formula

On the basis of section 33 of the regulation of 11. October 1984 on the guarantee of nuclear safety and radiation protection (GBl. 30 p. 341), the following shall be determined:

-
On § 3 (3) of the Regulation

Unofficial table of contents

§ 1 Tasks of the responsible employee

(1) In the field of radiation protection, the senior staff member employed as the responsible employee has the following tasks in particular:
1.
to set up radiation protection areas,
2.
to establish radiopartisans,
3.
Carry out information and internal radiation protection training;
4.
to plan and organise radiation protection measures for the respective work tasks,
5.
to draw up the operational radiation protection order or radiation protection instructions,
6.
to direct radiation workers directly,
7.
to arrange for medical, dosimetric and personal dosimetry monitoring and to provide written evidence of such monitoring;
8.
require the provision of necessary individual protection means and ensure that they are used,
9.
to permit the use of radiation devices, protective devices and measuring means only in a technically correct state and to arrange for the proper inclusion of the measuring equipment in the operational measurement system;
10.
to enforce preventive measures to prevent extraordinary events,
11.
to protect radioactive substances and radiation devices against unauthorised access, to control their completeness and to provide proof of their existence,
12.
To arrange for the examination of the tightness of enclosed radiation sources,
13.
inform the superordinate director and the radiation protection officer in the event of defects in radiation protection and to work towards the elimination of the deficiencies,
14.
in the event of changes in the personal or factual conditions, the amendment of the permit shall be made.
(2) In the field of radiation protection, the employee with authority of authority employed as the responsible employee shall, in particular, carry out the tasks referred to in paragraph 1 (5) to (14).

-
On § 4 of the Regulation

Unofficial table of contents

§ 2

The procedure for granting permission in accordance with § § 3 to 14 of this implementing provision shall not apply to the use of nuclear facilities, to mining activities in which radioactive substances are present, and to the production of radioactive materials. The starting material and the use of the resulting radioactively contaminated material.

-
On Article 4 (3) of the Regulation

Unofficial table of contents

§ 3 Documents concerning the granting of authorisation

With the application for approval are
1.
the head of the holding,
2.
the responsible employee and the radiation protection officer as well as their qualifications,
3.
the work project,
4.
the nature and activity or quantity of the radioactive substances, the type and number of radiation devices or enclosed radiation sources, and
5.
the working spaces
, and
6.
the operational radiation protection order, including measures plan to combat extraordinary events in duplicate
. The authorisation shall be subject to these particulars and documents.

-
On § 4 (4) of the Regulation

Unofficial table of contents

§ 4 Consent

The State Office for Nuclear Safety and Radiation Protection shall be responsible for granting consents for the individual stages of the use of radiation facilities and for the transport of radioactive substances, for subprojects or for special work. to be included in the planning at the earliest possible date. Unofficial table of contents

§ 5 Approval of the location

(1) Sites of establishments, buildings and installations from which radioactive substances can enter the environment or which can otherwise contribute to the radiation exposure of individual persons from the population in the vicinity require approval. (2) The operation of radiation facilities and the handling of radioactive materials in residential buildings shall be permitted only under special restrictive conditions. These shall be laid down in the consent. Unofficial table of contents

§ 6 Assent to the task

(1) The task of preparing investments for buildings, spaces and installations in which the use of radiation facilities or a traffic with radioactive substances is provided shall be subject to the agreement. (2) The nature and extent of the investments for the buildings, spaces and installations for which the use of radioactive materials is to be used. The State Office for Nuclear Safety and Radiation Protection shall determine the documents to be provided. Unofficial table of contents

Section 7 Approval of the project

Projects relating to buildings, spaces and installations which provide for the use of radiation facilities or for the transport of radioactive substances shall be subject to the agreement. The application shall be accompanied by the following documents:
1.
Explanation of the work plan and the work technology,
2.
Explanatory notes,
3.
radiation protection technical and safety explanations,
4.
radiation protection calculations,
5.
information on the nature, activity or quantity of the radioactive substances or information on the type of radiation equipment and its operating parameters,
6.
graphic documents, such as the site plan, floor plans or cuts, as well as information on ventilation and ventilation management, water and sewerage management, monitoring equipment and other equipment,
7.
Proof of the guarantee of health and safety at work as well as fire protection.
The State Office for Nuclear Safety and Radiation Protection can call for further documentation, in particular for the optimization of radiation protection measures. The documents must be submitted in duplicate to the State Office for Nuclear Safety and Radiation Protection, which shall keep a copy of the documents. Unofficial table of contents

Section 8 Approval of the set-aside

(1) The closure of installations or workplaces subject to authorisation for the operation of radiological installations containing radioactive substances or in which the traffic is carried out with radioactive substances is subject to approval. (2) With the application for the approval of the set-aside, it must be demonstrated
-
there is a proper disposal or transfer of radioactive substances or radiation equipment,
-
workplaces, work equipment or installations are sufficiently decontaminated;
-
the radiation protection is guaranteed during the decommissioning process.
(3) The continued use of workplaces, work equipment or equipment is subject to approval by the State Office for Nuclear Safety and Radiation Protection. It can commission the radiation protection officer with the release. (4) The decommissioning of radiation facilities that do not contain any radioactive substances is the State Office for Nuclear Safety and Radiation Protection under Communication on the other Whereabouts should be reported. Unofficial table of contents

Section 9 Approval of subprojects and special works

Partial projects and specific works, such as new technologies, industrial search or temporary work, which are intended to operate radiation facilities or a traffic with radioactive substances, require approval. The nature and scope of the documents to be submitted correspond to those in § 7. Consent shall form part of the authorisation granted. Unofficial table of contents

§ 10 Consent to import

(1) Individual imports of radiation equipment or enclosed radiation sources shall be subject to the consent if no authorisation is available in accordance with Article 5 of the Regulation. The application shall be submitted by the import operation. The documents shall be accompanied by the following documents:
-
technical documentation, of the design and function,
-
the purpose of application,
-
the intended operation for use or transport,
-
Radiation protection authorisation or similar documents of the country of manufacture,
-
scheduled operation for maintenance.
(2) The import contract may not be concluded until after the consent has been granted. Unofficial table of contents

Section 11 Amendments

A modification of the authorisation shall be requested prior to the change in terms of human or factual conditions on which a permit is based. Unofficial table of contents

§ 12 decrease

Work equipment, working methods and workplaces for the operation of radiation facilities and the transport of radioactive substances shall be carried out before a permit has been issued with a view to ensuring the protection of radiation by the State Office for nuclear safety and radiation protection. It can commission the radiation protection officer or the responsible employee with the acceptance.

-
On § 4 (5) of the Regulation

Unofficial table of contents

§ 13 Registration

(1) The traffic with enclosed radiation sources or the operation of radiation facilities shall be subject to registration if:
-
unified operational documents confirmed by the State Office for Nuclear Safety and Radiation Protection, in particular the radiation protection technical project, the operating instructions and the occupational radiation protection order, are available,
-
proof is provided that the holding is carried out in accordance with the operational documents,
-
A responsible employee is named and
-
the compliance with the radiation protection requirements is demonstrated by a decrease.
(2) The registration shall be subject to stomatological radiographs and measuring, control and regulating devices using enclosed sources of radiation, if this is shown in the radiation protection type approval. (3) The State Office for Nuclear safety and radiation protection are to be sent in duplicate with the endorsement note of the responsible employee in the context of the radiation protection type approval. A copy is sent back to the company with a registration note. (4) The registration is bound to:
1.
the operation,
2.
the responsible staff,
3.
the work project,
4.
the nature, activity or quantity of the radioactive substances or the nature and activity of the sources of radiation and the type and characteristics of the radiation equipment and the number thereof,
5.
the working spaces.
(5) A change in the human or factual conditions underlying the registration and the decommissioning of registered radiation facilities and enclosed radiation sources shall be the State Office for Nuclear Safety and Radiation protection shall be notified within 14 days of change.

-
On § 4 (6) of the Regulation

Unofficial table of contents

§ 14 Registration

(1) The application shall be subject to
-
radiation sources for the display control of radiation measuring instruments,
-
radiation sources for teaching purposes,
-
Radiation facilities for educational purposes and
-
ionization smoke detectors,
(2) The application shall be made by means of a written notification from the State Office for Nuclear Safety and Radiation Protection by means of a form through the establishment. Unless otherwise specified, the purchase of products subject to notification shall be notified to the State Office for Nuclear Safety and Radiation Protection within 4 weeks.

-
To § 4 (7) and § 5 of the Regulation

Unofficial table of contents

§ 15 Permission for special radiation equipment

The use of radiation devices, the acceleration voltage of which does not exceed 5 kV for charged particles, is permitted without the approval, registration, registration and type approval.

-
On § 6 (2) of the Regulation

Unofficial table of contents

§ 16 Powers and duties of inspectors and authorised doctors

(1) The inspectors of the State Office for Nuclear Safety and Radiation Protection shall be entitled to:
1.
To enter buildings, spaces, facilities, laboratories and other workplaces at any time in the performance of their duties and to carry out tests, measurements or sampling, in principle the legislation and the operational provisions to health, work and fire protection,
2.
to consult or request documents relating to nuclear safety and radiation protection, to require information and assessments, and to make required documentation,
3.
call for the elimination of defects in the guarantee of nuclear safety and radiation protection from the heads of the establishments and the staff responsible,
4.
to impose conditions on the heads of undertakings and to commission them, in the event of serious breaches of the laws of nuclear safety and of radiation protection or of direct hazards to persons or property, and the environment, the continuation of the to prohibit the work or activity of radiation workers and operators, or to block premises and installations;
5.
in the event of exceptional events for the purpose of initiating necessary acts for the prevention of risks to life and health or for the prevention of serious damage, to the extent that the operation does not take these measures into account, self-perception,
6.
request the initiation of disciplinary measures in the event of breaches of legislation and operational provisions or non-fulfilment of conditions and instructions issued by the head of the establishment, a warning with the order fee in accordance with section 30 (3) (b) of the German law. 5 of the Regulation, or to propose to the President of the State Office for Nuclear Safety and Radiation Protection, in accordance with Article 30 of the Regulation, the initiation of a disciplinary criminal procedure.
(2) The authorized physicians of the State Office for Nuclear Safety and Radiation Protection have the right to:
1.
to monitor radiation protection physicians with regard to radiation protection control of radiation workers and operators,
2.
to see the health records of radiation workers and operators,
3.
medical examinations in the State Office for Nuclear Safety and Radiation Protection, or in health facilities defined for this purpose, and to initiate radiation protection medical reports or senior reports.
(3) On the issue of instructions or implementation of measures pursuant to paragraph 1 (5) and (2) (3), the head of the establishment shall be informed immediately.

-
On Article 6 (3) of the Regulation

-
State personal dosimetry monitoring

Unofficial table of contents

§ 17

(1) Personally dosimetry monitoring of the external radiation exposure of radiation workers of categories A and B according to § 31 shall be carried out with personal dosemeters provided by the State Office for Nuclear Safety and Radiation Protection, and will be evaluated. The personal dosimeters are usually to be worn on the chest side of the upper body. If X-ray protective clothing is worn, the personal dosemeters shall be placed under this clothing. (2) The evaluation of the personal dosimeters shall be carried out monthly for category A radiation workers. The evaluation of the passenger dosemeters can take place at a greater time interval for category B radiation workers. (3) Propositions at the time of the evaluation of the personal dosimeters and for the monitoring of further persons to external Exposure to radiation shall be taken during the granting of the permit. Unofficial table of contents

§ 18

Personnel dosimetry monitoring of the internal radiation exposure of radiation workers, particularly in the working spaces of Classes I and II, in accordance with § 34 and in nuclear facilities, shall be carried out by the State Office for Nuclear Safety and Radiation protection by means of full-body measurement or measurement of excreting samples. The State Office for Nuclear Safety and Radiation Protection can also carry out these tasks to the holding. The nature and scope of the monitoring shall be based on the work plan and the results of the monitoring measurements in accordance with § 21. In special cases, the State Office for Nuclear Safety and Radiation Protection may stipulate that the internal radiation exposure shall be determined on the basis of the measurement of the activity concentration of the air at representative workplaces. Unofficial table of contents

§ 19

(1) Radiation workers shall be informed of the results of personal dosimetry monitoring. The radiation exposure determined by the person-dosimetry monitoring shall be evaluated by the responsible employee with the radiation workers and shall be registered in a loading register. Dose values for individual persons below the recording threshold shall be negligible in the determination of the individual exposure to radiation. (2) If radiation workshops are used in radiation protection areas of other holdings, then the to ensure that the personnel dosimetry is monitored and the results of the monitoring are registered. Unofficial table of contents

§ 20

(1) The following information shall be provided to the State Office for Nuclear Safety and Radiation Protection on persons dosimetrically to be monitored by the State Office:
1.
Name, birth name, first name,
2.
Number of persons,
3.
learned profession, current activity,
4.
Start of the duties subject to supervision, prior operation in which the person dosimetry was monitored,
5.
type of work, type of radiation and quality, or the nature of the radioactive substances and the handling of these characteristics.
(2) The State Office for Nuclear Safety and Radiation Protection informs the company of radiation exposure in previous activities. (3) The termination of the activity of personnel dosimetrically to be monitored shall be the State Office for To communicate nuclear safety and radiation protection. The results of personal dosimetry monitoring are kept by the State Office for Nuclear Safety and Radiation Protection 50 years after the end of the work.

-
On § 7 (1) of the Regulation

Unofficial table of contents

Section 21 Monitoring measurements

(1) establishments in which nuclear energy is applied shall comply with the rules on operational measurement and must have all the means of measurement necessary to ensure operational supervision. The measurement results are to be registered, evaluated and kept. (2) For the monitoring measurements, the measuring task is to be used with appropriate and calibrated measuring instruments. The provisions of the Office for Standardization, Measurements and Testing of Goods relating to the State and Operational Testing of Means of Measurement are to be observed. (3) Measurements are regular and in the case of changes that substantially increase the radiation protection situation. as well as for exceptional events. In order to assess the radiation protection situation, it is necessary to measure local doses and local dose rates in radiation protection areas and adjacent areas. In addition, in the case of the operation of nuclear installations and radiation equipment which may contain enclosed radiation sources or produce radioactive substances, as well as in the case of the transport of radioactive substances, the use of measuring equipment and methods shall be used which shall: allow surface contamination and activity concentrations in air and water to be determined or the tightness of enclosed radiation sources to be tested. (5) The release of radioactive substances with the waste air or waste water or otherwise in The environment is to be monitored by measurement. The results must be registered and stored. (6) In order to determine or limit the individual exposure to radiation, personal dosimeters, individual dose-rate warns or individual procedures for individual doses are to be determined. Determination of the incorporation. (7) When leaving radiation protection areas in which open radioactive substances may be handled or where open radioactive substances may be present, persons and persons (8) In justified cases, the monitoring of measurement can be replaced by an estimate. This procedure is subject to confirmation by the State Office for Nuclear Safety and Radiation Protection. (9) Stories for the storage of measurement results are made in legislation or in the granting of permission.

-
On Article 7 (2) and (3) of the Regulation

Unofficial table of contents

Section 22 Rights and obligations of the radiation protection officer

(1) The radiation protection officer shall monitor compliance with the provisions of radiation protection in his area of responsibility. He has to advise the head of the company on questions of radiation protection and to control the staff responsible for the performance of their duties. (2) The radiation protection officer shall be entitled to all At any time, to enter workplaces and installations within its sphere of competence for the purpose of radiation protection control, to require information, reports and assessments of radiation protection and to inspect all the radiation protection products. (3) The radiation protection officer has in his To carry out regular inspections and report to the head of the holding at least annually on the radiation protection situation. The number and extent of the control measures shall be determined when the permit is granted. (4) The radiation protection officer shall keep a control book in which all checks, the deficiencies found to be remedied, shall be carried out. (5) The radiation protection officer shall be involved in the planning and preparation of new work projects involving radiation protection issues, to be added. He has to participate in the definition of radiation workers and to confirm the Occupational Radiation Protection Ordinance. (6) The radiation protection officer has in the case of detected defects in radiation protection or in case of non-compliance with the Radiation protection regulations of the senior staff to demand the timely elimination of defects and compliance with the radiation protection regulations. (7) The radiation protection officer has at the risk of danger to persons and property To block premises, facilities and facilities. Such measures shall be brought to the attention of the Head of the Company and the State Office for Nuclear Safety and Radiation Protection without delay. (8) The Radiation Protection Officer shall be obliged to do so by the State Office for Nuclear Safety and Security and Report on radiation protection at the request of the control activity and give opinions, opinions or opinions on problems related to its activity as radiation protection officer. (9) The work tasks of the Radiation protection officers as well as his rights and obligations are in his function plan . If the radiation protection officer exercises the control activity on a side-by-side basis, it shall carry out his other operational tasks. (10) The rights and obligations of the control officers responsible for nuclear safety shall be the result of the legislation.

-
On § 8 of the Regulation

Unofficial table of contents

Section 23 Radiation protection medical examination and monitoring and establishment of radiation protection doctors

(1) Radiation workshops and operators shall be subject to radiation protection and surveillance examinations prior to admission and continuation of their activities and, after exceptional events, to radiation protection. The managers of the establishments must ensure participation. (2) The radiation protection doctors are appointed by the head of the Department of Health and Social Affairs of the county council (district doctor) on a proposal from the directors of the occupational health and safety inspections of the To use councils of the counties and to designate the State Office for Nuclear Safety and Radiation Protection. The assignment of the radiation protection doctors to the enterprises is to be carried out at the request of the heads of the establishments of the directors of the labour market inspections of councils of the districts. In their area of responsibility, radiation protection physicians should not act as responsible employees. As radiation protection physicians, specialists with state qualification records of the State Office for Nuclear Safety and Radiation Protection are to be used.

-
On § 10 of the Regulation

Unofficial table of contents

Section 24 Right-of-justification procedure

The justification of a type of application of nuclear energy shall be decided on the basis of the legislation in force for the preparation of an investment project, a production intake or an import. The radiation hazards to be taken into consideration will be assessed by the State Office for Nuclear Safety and Radiation Protection in the course of the authorisation procedure. If no authorisation is provided for, the assessment shall be carried out within the framework of the granting of the authorisation.

-
On Article 11 of the Regulation

Unofficial table of contents

§ 25 Primary limit values

(1) In the case of the application of atomic energy, the following primary limit values shall apply to the individual radiation exposure of the radiation-based workers in 12 consecutive months:
50 mSv as effective equivalent dose,
500 mSv as an equivalent dose for the organs and tissues
and
150 mSv as an equivalent dose for the eye lens.


In the case of incorporations, the dose equivalent to 50 years is replaced by the dose equivalent to the equivalent dose. For women under the age of 45, the additional limit value is 13 mSv for the equivalent dose of the uterus in three consecutive months. (2) In the application of atomic energy, individual radiation levels of individual persons from the Population per year as the limit of effective dose equivalent of 5 mSv and as a limit of equivalent dose for organs and tissues 50 mSv. In addition, it should be secured that the average effective dose equivalent per year over a period of time is limited to 1 mSv from 50 years. Unofficial table of contents

Section 26 Secondary limit values

(1) In the case of external irradiation, the limit values in accordance with section 25 (1) shall be deemed to have been complied with if the following secondary limit values are complied with:
-
in the case of photon radiation from 10 keV to 10 MeV for the maximum surface dose on the body's body and head: 50 mSv per year.For women under 45 years of age 13 mSv in 3 consecutive months;
-
in the case of neutron radiation, up to 20 MeV for the maximum equivalent dose under the assumption of reference conditions according to table Appendix 1: 50 mSv per year.For women under 45 years of age 13 mSv in 3 consecutive months;
-
At photon radiation from 10 keV to 10 MeV and at neutron radiation up to 20 MeV for the maximum equivalent dose at the hands: 500 mSv per year;
-
in the case of photon radiation below 10 keV and for beta radiation for the maximum surface dose: 500 mSv per year; and
-
for the eye lens: 150 mSv per year.
Secondary limit values shall be laid down for radiation energies outside the said energy ranges and other types of radiation in the case of the granting of the permit. (2) The secondary limit values referred to in paragraph 1 shall be those for the verification of compliance with the secondary limits referred to in paragraph 1 The necessary calculation bases and measurement specifications shall be set in standards. Compliance with the limit values can also be demonstrated with the radiation exposures indicating the passenger dosimeters used in the state surveillance. (3) In the case of internal irradiation, the limit values of the radiation exposure in accordance with § 25 shall apply. Paragraph 1 shall be deemed to have been complied with if column 3 of Table 1 in Annex 2, Column 4 limits of the annual activity intake ALI for inhalation and for ingestion are not exceeded. (4) For a radionuclide mixture of known percentage composition:
 N 
1 ------ p (deep) i
------------ = > ----------
ALI (deep) Gem. ------ ALI (deep) i
i = 1
with
ALI (deep) Gem.
-
Limit of annual activity intake for the radionuclide mixture
p (deep) i
-
relative proportion of the i-th radionuclide in the total activity of the mixture
ALI (deep) i
-
Limit of annual activity intake for i-th radionuclide
N
-
Number of radionuclides in the mixture.
(5) In the case of combined external and internal irradiation, the primary limit values for radiation workers shall be considered to be complied with if the following conditions are met at the same time:
 N 
H (deep) d ------ I (deep) j
------------ + > ---------- < 1
50 mSv ------ ALI (deep) j =
j = 1
H (deep) s
---------- < 1
500 mSv =
with
I (deep) j
-
Annual activity intake of the j-th radionuclide
ALI (deep) j
-
Limit of annual activity intake of the j-th radionuclide
H (deep) d
-
maximum surface dose of the body's body body for photon radiation in the energy range from 10 keV to 10 MeV or Maximum dose equivalent for neutrons up to 20 MeV under reference conditions according to para. 1
H (deep) s
-
Surface dose for photon radiation below 10 keV and beta radiation.
(6) For the external irradiation of individual persons from the population, a limit value of 50 mSv per year shall apply as secondary limit values 1/10 of the limit values according to para. 1 and for the eye lens. The additional requirement in section 25 (2) shall apply mutatily. (7) For the internal irradiation of individual persons from the population, if no other provisions are made in legislation or in the granting of the permit, 1/100 of the Values as set out in paragraph 3. If only adults are affected, 1/10 and as an average over a period of 50 years shall be 1/50 of the given values. (8) In the case of combined external and internal irradiation of individuals from the population, paragraph 5 shall apply mutatically. , Unofficial table of contents

§ 27 Derived limit values

(1) If derived limit values are specified for the mean value of a variable over a given time interval, the actual value of the limited quantity may fluctuate by this mean value over shorter time intervals. (2) For external photon irradiation With photon energies up to 3 MeV, derived limit values can be given as a free-in-air energy dose or energy dose rate under the condition of the secondary electron equilibrium. Air, water or soft tissue may be used as the reference substance for the energy dose. In the derivation of the limit values, an equivalent dose in Sv may be equated to an energy dose in Gy measured freely in air. (3) The limit value for the mean annual activity concentration in air DAC is that activity concentration of a radionuclide in air,
-
which at a breathing rate of 1.2 m (high) 3 h (high)-i within a working year of 2000 h leads to an annual activity of activity at the level of the ALI; or
-
which, in the case of a submersion within a working year of 2,000 hours, leads to a radiation exposure which corresponds to the limit values in § 25 (1).
The following shall apply:
-
for all radionuclides except noble gas DAC*) = ALI/2.400 in Bq m (high) -3 with ALI for inhalation according to Appendix 2, Table 1, column 3,
-
For noble gases, the DAC for submersion indicated in Annex 2, Table 2, column 3.
(4) In the case of the DAC of radionuclide mixtures of known percentage composition, § 26 (4) shall apply. (5) If no other provisions are made in legislation or in the granting of permission, the primary limit values shall apply to: individual persons from the population as being observed when the mean annual activity concentration in air
-
for all radionuclides other than noble gases 1/100 DAC,
-
for noble gases 1/40 or the average value per year over a period of 50 years 1/200 of the values given in Annex 2, Table 2, column 3a
(6) For surface contamination, the limit values set out in Table 3 of Appendix 2 shall apply. For tritium, the values given in Table 3 for beta surface contamination are to be multiplied by a factor of 100. In the event of compliance with the limit values of surface contamination, the radiation exposures caused by these contamination levels need not be taken into account in the detection of compliance with the limit values in accordance with § 25. (7) Based on job-related analyses, which lead to specific load models, can be derived from deviating surface contamination limits and authorized by the State Office for Nuclear Safety and Radiation Protection.
-----
*) This value does not take into account the external radiation exposure. Unofficial table of contents

§ 28 Free limits

(1) Radioactive material shall be considered as optional:
-
as the limit for the activity, the values set out in Table 1, column 5 of Annex 2. If several radionuclides are present at the same time, the following condition must be observed:

 N 
------ A (deep) i
> ---------- < 1
------ F (deep) i =
i = 1
with
A (deep) i
-
Activity of the i-th radionuclide
F (deep) i
-
Free limit for the i-th radionuclide
N
-
Number of radionuclides present at the same time
-
as the free limit of the activity concentration 100 Bq/g or in the case of solid natural radioactive substances, 500 Bq/g.
(2) For radioactively contaminated material, an activity concentration of 0.2 Bq/g shall be considered as the free limit. If this is exclusively the radionuclide of the natural decay series in the radioactive equilibrium, this value applies to radium. (3) For radioactive starting material, the free limit for the activity 5 MBq or as a free limit for the radioactive material is considered to be a free limit for the active material. relative mass fraction of uranium or thorium 0.01%. (4) Radioactive discards are considered as free limits of the activity concentration
-
Introduction to the communal sewerage:
for radionuclides with half-lives < = 60 Tagepro cbm ejection of the ALI according to Appendix 2 Table 1, column 4 or Section 26 (4); for radionuclides with half-life times > 60 Tagepro cbm ejection 1/10 of the ALI according to Appendix 2, Table 1, column 4, or Section 26 (4);
-
Discharge into water:
per cbm eject 1/100 of the ALI according to Appendix 2 Table 1, column 4 or Section 26 (4);
-
Levy in the atmosphere:
Radionuclides other than Edelgaseim Auslitter 1/10 of the DAC according to § 27 (3) and 4; Edelgaseim Auslitter 1/10 of the DAC for submersion according to Appendix 2, Table 2, column 3a or Section 27 (4);
-
Landfill of solid discards:
0.2 Bq/g. If these only contain radionuclides of the natural decay series in the radioactive equilibrium, this value applies to radium.
In so doing, the discards resulting from the use of nuclear installations or radiation installations or from the traffic with radioactive material may not exceed the values set out in Table 1, column 5, in Annex 2, Table 1. Waste is subject to the free limits for radioactive material. (6) For foodstuffs contaminated with radioactivity, an activity concentration which is 5 x 10 (high) -3 times the level in Annex 2, Table 1, column 4 or 4, respectively, is considered to be the free limit. § 26 (4) is divided by the average annual per capita consumption in kg of the food in question. (7) For radiolabelled medicinal products and for radionuclide labelled medicinal products, a free-limit shall be considered to be Activity concentration, which is 10 (high) -8 times the values given in Appendix 2, Table 1, column 3, per gram. (8) The free limits laid down in paragraphs 1 to 7 shall apply in each case. The establishment of free borders shall not affect the granting of authorisation by other authorities, in particular to the introduction of waste water into the aquatic environment by the competent water management directorate or into the sewerage system by the relevant VEB Water supply and wastewater treatment.

-
On § 12 of the Regulation

Unofficial table of contents

§ 29 Implementation of the optimization

(1) Optimisation of radiation protection measures shall be carried out within the framework of the authorisation procedure or in the case of the granting of authorisation. Documents necessary for this purpose must be submitted to the State Office for Nuclear Safety and Radiation Protection. This optimization shall be deemed to exist if the relevant authorized limit values or specifications set by the State Office for Nuclear Safety and Radiation Protection are set in standards, other legislation, in directives or in the granting of the (2) In the application of atomic energy, companies have on their own responsibility to examine further possibilities for the optimization of radiation protection measures in their areas and to take measures to reduce them. of the risk of radiation.

-
On § 13 of the Regulation

Unofficial table of contents

§ 30 Radiation loads under special conditions

(1) Under special conditions, radiation exposure in individual cases shall not exceed twice and during lifetime no more than five times the limit values in accordance with section 25 (1). (2) Under special conditions, Radiation pollution of the careful examination and prior confirmation by the head of the company as well as the reporting to the State Office for Nuclear Safety and Radiation Protection. If special radiation exposure is planned, they must be confirmed by the State Office for Nuclear Safety and Radiation Protection. (3) Radiation workers, who are to be exposed to radiation exposure under special conditions, shall be included in the Thoroughly identify actions to be carried out, inform them of existing sources of danger, and inform them of any measures to keep the exposure to radiation as low as possible. Radiation loads under special conditions require the consent of the radiation workshop. The State Office for Nuclear Safety and Radiation Protection, the radiation protection physician and the radiation workers concerned shall be informed of the radiation exposure which has occurred. (4) Radiation loads under special conditions shall not be permitted. to be suspended:
-
Radiation workers who have been exposed to exposure to radiation in the event of exceptional events exceeding five times the annual limit values in accordance with Article 25 (1),
-
Women with a age of less than 45 years.

-
On § 14 (1) of the Regulation

Unofficial table of contents

Section 31 Categories for radiation-based workers

(1) For radiation workers, categories A and B shall be defined:
1.
Category A radiation workers are active in working conditions where exposure to radiation may exceed 3/10 of the limit values in accordance with Article 25 (1),
2.
Category B radiation workers are active in working conditions in which the radiation exposure cannot exceed 3/10 of the limit values in accordance with Article 25 (1).
(2) Students and apprentices between the completed 16. and 18. For the purpose of training, life-year may only be employed under working conditions in which the radiation exposure cannot exceed 1/10 of the limit values in accordance with Article 25 (1). In exceptional cases, with the consent of the State Office for Nuclear Safety and Radiation Protection, an application may be made under conditions in which the radiation exposure cannot exceed 3/10 of the limit values in accordance with Article 25 (1). (3) The definition of the categories of radiation workers shall not be taken into account by the radiation exposure which may occur in the event of exceptional events.

-
On § 15 of the Regulation

Unofficial table of contents

§ 32 Characterization of radiation protection areas

(1) Radiation protection areas shall be set up where, within one year, radiation exposures may be established which exceed 1/10 of the limit values in accordance with Section 25 (1). In the case of radiation protection areas which extend beyond the premises, the holding must have the necessary powers for protective measures. (2) In accordance with practical requirements, radiation protection areas shall be subdivided into:
-
Radiation protection area I, in which, within one year, radiation exposure may be achieved exceeding 3/10 of the limit values in accordance with Article 25 (1), and
-
Radiation protection area II in which, within one year, radiation exposures cannot be achieved which do not exceed 3/10 of the limit values in accordance with Article 25 (1), unless a classification in the grounds mentioned in paragraph 3 above is established in the Radiation protection area I is necessary.
(3) In the definition of radiation protection areas, it is possible to use as far as possible structural limitations. (4) Radiation protection areas are to be marked and to be provided with the radiation warning sign at the access points. Measures shall be taken against unintended and unauthorised access. Within radiation protection areas, sites with a particular risk of radiation are to be marked with the radiation warning sign. Residence restrictions may be laid down for these bodies. In the event of a contamination risk, facilities for contamination control, decontamination and the change of clothing must be provided. (5) The access to radiation protection areas is in principle only permitted for:
-
radiation workers for the purpose of carrying out professional activities,
-
patients on radiological measures,
-
Apprentices, students and other workers on qualification measures in the event of compliance with the conditions referred to in § 31 (2),
-
Visitors under the conditions laid down in the grant of the permit. Visits are only permitted under conditions in which the radiation exposure cannot exceed 1/10 of the values in accordance with § 25 (2). Workers who rarely have to enter radiation protection areas in order to carry out specific activities can be treated in the same way as visitors.

-
On § 16 (1) of the Regulation

Unofficial table of contents

§ 33 Organisational radiation protection measures

(1) When dealing with radioactive substances, only the necessary activities and radionuclides are to be used with the lowest possible half-life time. Radioactive substances may only be present in the workplace for as long as the work project requires. Measures must be taken to avoid contamination. (2) In radiation protection areas where the possibility of supplying radioactive substances to the human body is possible, food, drink and smoking are the use of Health care products and cosmetics, and other acts which encourage such a supply, are prohibited. Under special arrangements, drinking can be permitted. The prohibition does not apply to the production of radioactive material. (3) In the case of traffic with radioactive material and radioactive material, the measures are to be taken in the form of work organisation and hygiene measures, which include a supply of radioactive material. radioactive substances to a minimum. Unofficial table of contents

§ 34 Laboratory Classes

(1) Working spaces for the handling of open radioactive material shall be divided into the following classes, depending on the free limit and the activity with which the work is dealt with in the working spaces:
Free limits for radioactive material Work space activity limit
Class I Class II Class III
5 kBq over 0.5 GBq up to 0.5 GBq up to 0.5 MBq
50 kBq over 5 GBq up to 5 GBq up to 5 MBq
> 50 kBq over 50 GBq up to 50 GBq up to 50 MBq
3 (deep) H over 5 TBq up to 5 TBq up to 5 GBq
(2) Higher activities may be authorised for the storage of open radioactive material in work spaces. (3) Paragraphs 1 and 2 shall not apply to the transport of radioactive raw materials. (4) The requirements for Construction and equipment for the work rooms are separately regulated. Unofficial table of contents

§ 35 Surface contamination

(1) Surface contamination should not exceed the values set out in Table 3 of Appendix 2. (2) Surface contamination exceeds the surface contamination level.
-
the values set out in Annex 2, Table 3, points 1 to 4, after repeated humidification of decontamination with mild decontamination agents
-
or the values indicated in Table 3 (4) to (6) after repeated normal washing or the values set out in Table 3, point 7, after decontamination with soap and brush without damage to the skin,
further measures shall be determined in accordance with an assessment of the expected exposure to radiation, taking as far as possible a consideration of the actual conditions of the load. In doing so, directives of the State Office for Nuclear Safety and Radiation Protection or stipulations must be taken into account when granting permission. Unofficial table of contents

Section 36 Examination of enclosed radiation sources

(1) Reclosed sources of radiation shall be tested for integrity, tightness, contamination and compliance with the specified period of use. (2) The test distances and the type of testing shall be regulated separately. (3) Depending on the The working situation shall, where appropriate, lead to a denser sequence of tests in order to ensure the tightness and exclusion of contamination. (4) When it is examined that enclosed radiation sources are damaged, leak-proof, or is contaminated, in accordance with the provisions concerning the behaviour of (5) The enclosed radiation sources are to be equated with those radioactive substances which meet the requirements of enclosed radiation sources.

-
Pursuant to Article 16 (2) of the Regulation

Unofficial table of contents

§ 37 Protections

Workplaces and equipment for the application of atomic energy must be equipped to the necessary extent with technical equipment designed to prevent accidental exposure to radiation (protective equipment). Protective devices must be designed redundantly and inevitably, and must be checked at regular intervals for their effectiveness. These controls shall be recorded. In the event of defects which have occurred, the responsible employee shall, in coordination with the radiation protection officer, decide whether and under which conditions a further operation can be carried out. In the case of repair and maintenance work, protective devices must not be permanently removed or rendered ineffective. Unofficial table of contents

§ 38 Maintenance

The managers of the establishments in which radiation installations are used shall be responsible for their maintenance. Technical inspections shall be carried out within the time limits specified in the radiation protection type approval by a holding which is in possession of a permit issued by the State Office for Nuclear Safety and Radiation Protection to carry out Repair and maintenance work.

-
On Article 16 (3) of the Regulation

Unofficial table of contents

Section 39 Radiation Protection Order

(1) In the operational radiation protection order, taking into account the specific conditions of use and work tasks, the regulations on work behaviour, work organisation, maintenance technologies and the Radiation protection monitoring, including the authorized and operational limit values or reference thresholds, and their application. (2) The occupational radiation protection order shall be subject to confirmation by the State Office for Nuclear Safety and radiation protection or can be specified by it and is up to date , If necessary, the occupational radiation protection order of the responsible employee shall be specified by radiation protection instructions for individual work projects. The radiation protection instructions shall be confirmed by the radiation protection officer. Unofficial table of contents

§ 40 Belehrungen

(1) Radiation workshops and operators must be informed of the risks involved in the application of nuclear energy, their obligations in radiation protection and the occupational radiation protection order, before commenting work on the protection of nuclear energy. and proper conduct, especially in extraordinary events, are taught in an active way. The teachings are to be supplemented by practical exercises. In the case of visitors who enter radiation protection areas, it is appropriate to proceed with the procedure. The managers of the establishments shall ensure the implementation of these teachings. In the case of the teachings, the occupational safety and fire protection arrangements adopted for the given working area must be taken into account. (2) Radiation workshops and operators shall be at intervals of 3 months and shall be resumed at the time of resumption of the to lecture on radiation protection after a prolonged period of interruption of work. Teaching must be carried out even if changes in the radiation protection situation are to be expected in the introduction of new areas of work or by changing the working methods. Unofficial table of contents

Section 41 obligations of radiation workers and operators

Radiators and operators shall scrupulously respect the radiation protection rules and limit values and conditions of nuclear safe operation of nuclear installations, and shall carry out their work in such a way that they do not endanger themselves and others. They are obliged to report defects in radiation protection and extraordinary events occurring to the responsible employee or radiation protection officer immediately.

-
On Article 16 (4) and (5) of the Regulation

Unofficial table of contents

Section 42 Verification of records and storage

(1) The receipt, use and whereabout of radioactive substances shall be subject to proof. In the event of a loss of radioactive material, it is necessary to proceed in accordance with the provisions on behaviour in the event of exceptional events. (2) Radioactive materials and radioactive waste are difficult to store in special storage rooms and containers. to store combustible building materials under closure. Radioactive materials and radioactive waste must not be kept together:
1.
fire-hazardous substances,
2.
explosive substances,
3.
aggressive chemicals (e.g. acids),
4.
Food and drink products, commodities, feedingstuffs, medicinal products and substances treated as such, preparations and articles, health-care products, pesticides.
(3) Explosive substances may only be stored in neighbouring rooms with the consent of the local fire-protection organs. The requirements for the storage spaces and storage containers for radioactive materials and radioactive waste are separately regulated. (4) Storage spaces and containers are to be found in the occupational radiation protection regulations Periodically check for integrity and contamination at intervals. (5) Storage spaces and containers shall be marked with the radiation warning sign. (6) The permitted activity in storage rooms shall be defined as a function of the construction and equipment of these spaces in the storage rooms. Permission documents are established.

-
On § 20 of the Regulation

Unofficial table of contents

Section 43 Claims to ensure nuclear safety

(1) For nuclear installations, the requirements for ensuring nuclear safety and for the protection of accidents are to be deducted from the results of the analysis of the course of possible incidents (incident analyses). Failure analyses shall be carried out on the responsibility of the heads of the establishments, on the basis of scientific and technical knowledge of triggering events, the conduct of operations and the reliability of components and equipment; Operational experience with comparable installations shall be taken into account. (2) Incident analysis shall include:
1.
Selection of triggering events that affect nuclear safety (output events),
2.
Investigation of the malfunction processes taking into account the initial state of the nuclear installation, the operation of operating and safety equipment and the actions of the operator and
3.
Determination of the incident effects as a function of the fault sequences.
(3) As a result of the incident analysis, incidents shall be determined for each nuclear installation by the State Office for Nuclear Safety and Radiation Protection (interpretative cases), for which it is necessary to demonstrate that the safety-related design of the nuclear plant and (4) provisions relating to the nature and extent of incident analysis, the failure of interpretations and their permissible levels of interference are avoided by the operator's actions. Impact and claims to ensure nuclear safety Security shall be made in legislation or in the granting of authorisation. Unofficial table of contents

§ 44 Quality Assurance for Nuclear Facilities

(1) For the project planning, production, installation, commissioning and operation of a nuclear installation and for the nuclear safety essential components, the complex measures coordinated with each other in quality assurance systems shall be the (2) A system of quality assurance must be included:
1.
Definition of quality and reliability values to ensure nuclear safety,
2.
measures for the preparation of binding working documents, such as standards and technical documentation for ensuring quality-oriented work, and stipulations for the timely handover of these working documents to the working persons,
3.
testing and control rules, such as methods for accurate error detection and verification of the accuracy of the test and measurement equipment used,
4.
stipulations on the quality-of-work of the work,
5.
procedures for the assessment and improvement of identified defects and for the clarification of causes of failure,
6.
Lay down the responsibility for the implementation of the individual quality assurance measures.
(3) The results of the quality checks shall be evaluated on a regular basis, and inadequacies in the quality system shall be rectified without delay. (4) Claims to be made beyond the provisions laid down in special legislation shall be made available to: Quality assurance will be established when the approval is granted.

-
On Article 21 of the Regulation

Unofficial table of contents

Section 45 Claims for the location of nuclear facilities

The location of a nuclear installation shall be determined in such a way that:
1.
the frequency of natural events or external civilizations which can cause nuclear accidents does not exceed fixed limits,
2.
the environmental conditions do not inadmissibly affect the functioning of systems and measures designed to ensure nuclear safety,
3.
a protected area can be set up if the nature of the nuclear facility requires that, and
4.
be able to take the necessary measures to protect against the effects of nuclear accidents in the environment.
More detailed provisions shall be made in legislation or in the granting of authorisation.

-
On § 23 of the Regulation

Unofficial table of contents

Section 46 Requirements for the operation of nuclear installations

(1) For each nuclear plant, on the basis of incident analyses, conditions of nuclear safety shall be provided by limit values for operating parameters and conditions for the condition and operational capability of important safety devices (2) The operation of a nuclear plant shall be drawn up in accordance with the operating rules to which the limit values and conditions of nuclear-safe operation are to be taken in a suitable form. (3) The operation of a nuclear plant shall be limited to the operation of the nuclear plant only for the operation of the nuclear plant. Limit values and conditions of nuclear safe operation allowed. The observance of the limit values and conditions of nuclear safe operation must be monitored. (4) In the event of deviations from the limits and conditions of nuclear safe operation, the safety of nuclear safety shall be immediately followed by the restoration of nuclear safety. (5) The facilities essential to the nuclear safety of a nuclear facility must be monitored. Quality assurance measures, including functional and repeatable tests, must be carried out in good time and in full. Deviations from the normal functioning during operation and in tests recognized deviations from the required properties shall be recorded, investigated and eliminated. (6) The results of the monitoring shall be documented and regularly updated. in order to identify influences on nuclear safety and to improve measures to ensure nuclear safety.

-
On Article 26 of the Regulation

Unofficial table of contents

Section 47 Notification of the radiation protection doctor and release after extraordinary events

(1) If, in the event of exceptional events, there is a suspicion that a worker has received a radiation exposure above the limit values laid down in Article 25 (1), the radiation protection doctor must be notified. (2) After an extraordinary event The State Office for Nuclear Safety and Radiation Protection shall require the State Office for Nuclear Safety and Radiation Protection to use the blocked facilities, workplaces, technical facilities and equipment before they are further used. It can commission the radiation protection officer with the release.

-
On Article 27 (1) of the Regulation

Unofficial table of contents

Section 48 Qualifications

(1) State qualification certificates shall be issued by the State Office for Nuclear Safety and Radiation Protection. (2) Qualified qualifications may be declared invalid if the invitation to visit Continuing education events are not being followed. State qualification certificates can be issued for a limited period. Their validity will be extended after the visit of continuing training events.

-
On Article 27 (5) of the Regulation

Unofficial table of contents

Section 49 Operating trainings

The operational training courses are to be carried out on the basis of the framework programmes set by the State Office for Nuclear Safety and Radiation Protection. In special cases, the programmes for the operational training are to be coordinated with the State Office for Nuclear Safety and Radiation Protection.

-
On § 29 of the Regulation

Unofficial table of contents

§ 50 involvement of the control body in research and development projects

(1) For research and development projects, the State Office for Nuclear Safety and Radiation Protection is at an early stage, but no later than at the stage of the preparation of studies, forecasts or specifications concerning appropriate research and development projects. (2) In the case of registration, the State Office for Nuclear Safety and Radiation Protection shall establish the
-
which research and development projects are to be included in the control of the State Office for Nuclear Safety and Radiation Protection, and for which subjects and studies are to be submitted to it for further consideration,
-
To which defenses it is to be invited and
-
What work results should be submitted to it.
(3) The State Office for Nuclear Safety and Radiation Protection has to submit proposals for the modification of research and development projects if it finds that:
-
in the research and development projects, nuclear safety and radiation protection are not taken into account or are not taken into account in a socially necessary scale; and
-
the results achieved do not meet the requirements of nuclear safety and radiation protection.
On the basis of the proposals, the heads of establishments shall take the necessary measures. Unofficial table of contents

Section 51 Final determination

This implementing provision shall enter into force on 1 February 1985. Unofficial table of contents

Final formula

The President of the State Office for Nuclear Safety and Radiation Protection of the German Democratic Republic Unofficial table of contents

Appendix 1 Neutron flux density in cm (high) -2 x s (high) -1 for an equivalent dose rate * 1) of 1 mySv x h (high) -1 and effective quality factor Q as a function of neutron energy

Neutron energy * 2) in MeV Neutron flux density in cm (high) -2 x s (high) -1 for 1 mySv x h (high) -1 effective quality factor Q* 3)
2.5E-08 (thermal) 26.0 2.3
1.E-07 24.0 2
1.E-06 22.0 2
1.E-05 23.0 2
1.E-04 24.0 2
1.E-03 27.0 2
1.E-02 28.0 2
2.E-02 17.0 3.3
5.E-02 8.5 5.7
1.E-01 4.8 7.4
5.E-01 1.4 11
1.E00 0.85 10.6
2.E00 0.70 9.3
5.E00 0.68 7.8
1.E01 0.68 6.8
2.E01 0.65 6.0
5.E01 0.61 5.0
1.E02 0.56 4.4
2.E02 0.51 3.8
5.E02 0.36 3.2
1.E03 0.22 2.8
2.E03 0.16 2.6
3.E03 0.14 2.5

* 1) Authorised works of maximum equivalent dose performance that occur in body-like phantoms in the case of frontal parallel radiation incident of monoenergetic neutrons (broad bundles).
* 2) 2.5E-08 = 2.5 x 10 (high) -8.
* 3) Maximum dose of equivalent dose divided by the dose of energy in the depth in which the maximum dose of equivalent dose occurs. Unofficial table of contents

Appendix 2

(Contents: tables not displayable,
Fundstelle: GBl. I 1984, No 30, p. 358-372,
with regard to of the individual amendments. Footnote) Unofficial table of contents

Annex EV Excerpt from EinigVtr Annex II, Chapter XII, Section III
(BGBl. II 1990, 889, 1226)

Section III
The following law of the German Democratic Republic shall remain in force with the following measures:
1.
...
2.
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. 196), with the following proviso: the provisions shall apply to mining and other activities, insofar as radioactive substances, in particular radon products, are present. The competent authorities shall replace the State Office for Nuclear Safety and Radiation Protection, or the President of that Office, as referred to in the continuing regulations.
...