Implementing provisions for the Regulation on nuclear safety and radiation protectionNon-official table of contents
Date of completion: 11.10.1984
" Implementing provisions for the Regulation on the guarantee of nuclear safety and radiation protection of 11. October 1984 (GBl. DDR 1984 I p. 348) "
In the joined area, the law of the former was the former. 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 evidence applicable: 3.10.1990 + + +) unofficial table of contents
based on § 33 of the regulation of 11. October 1984 on the guarantee of nuclear safety and radiation protection (GBl. No 30 p. 341) is intended to:
- Table of contents
To § 3 (3) of the Regulation
§ 1 Tasks of the responsible employee
(1) In the field of radiation protection, the executive officer employed as the responsible employee has the following tasks in particular:
- Set up radiation protection areas,
- Radiation workshops set,
- Belehrungen and Incompany Radiation Protection Training ,
- Planning and organizing radiation protection measures for each work item
- to work out the operational radiation protection order or radiation protection instructions,
- Radiation Workshop directly to guide,
- the medical, dosimetric and person dosimetric
- To demand the provision of necessary individual protection means and to use them for the purposes of monitoring and/or monitoring the use of individual protective equipment.
- To allow the use of radiation devices, protective devices and measuring equipment only in a technically sound condition, as well as the proper functioning of the system. To encourage the inclusion of the measuring equipment in the operational measurement system,
- Preventive measures to prevent exceptional events
- To protect radioactive substances and radiation devices against unauthorized access, to control their completeness, and to provide proof of their Inventory,
- causing the leakage of enclosed radiation sources,
- To inform the superconductor and the Radiation Protection Officer in the event of defects in radiation protection and to work towards the elimination of the defects,
- in case of changes in the personal or factual requirements the change of the permission to arrange.
(2) The employee appointed as the responsible employee with In the field of radiation protection, the power of instructions shall, in particular, be assigned to the tasks referred to in paragraph 1 (5) to (14).
To § 4 of the Regulation
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The procedure for granting permission in accordance with § § 3 to 14 of this implementing provision does not apply to the Use of nuclear facilities, for mining activities in which radioactive materials are present, as well as for the extraction of radioactive material and the use of the resulting radioactive contaminated material.
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To § 4 (3) of the Regulation
§ 3 Documents to be issued Approval
The application for approval is
- the leader of the Operation,
- the responsible employee and the radiation protection officer as well as their qualification,
- the work project,
- the type and activity or quantity of the radioactive substances, the type and the number radiation or enclosed radiation sources and
- working spaces
as well as
- the operational radiation protection order, including the action plan to combat exceptional Events in duplicate
. The approval is bound to this information and documents.
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To § 4 (4) of the Regulation
§ 4 consent
To issue consent to each stage of the use of radiation facilities and to traffic with radioactive materials, to The State Office for Nuclear Safety and Radiation Protection is to be included in the planning process at the earliest possible date. Non-official table of contents
§ 5 Approval of location
(1) Locations of establishments, buildings, and installations from which radioactive substances are placed in the If the environment is located or which can otherwise contribute to the radiation exposure of individual persons from the population in the area, consent must be given.(2) The operation of radiation facilities and the handling of radioactive substances in residential buildings shall only be permitted under special restrictive conditions. These shall be laid down in the consent. Non-official table of contents
§ 6 Approval of the task
(1) Tasks to prepare investments for buildings, rooms, 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 documents to be provided for the consent shall be determined by the State Office for Nuclear Safety and Radiation Protection. unofficial table of contents
§ 7 consent to the project
Projects for buildings, rooms, and facilities where the use of radiation equipment or a traffic with radioactive substances is provided for, the consent shall be required. The application must be accompanied by the following documents:
- Presentation of the work plan and the Work technology,
- constructional explanations,
- radiation protection engineering and safety explanations,
- radiation protection calculations,
- information about type, Activity or quantity of radioactive substances or information on the type of radiation equipment and its operating parameters,
- drawing documentation, such as the site plan, Floor plans or sections, as well as aeration and ventilation information, water and sewerage management, monitoring equipment and other equipment,
- 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 further documents in particular for the optimisation of radiation protection measures. The documents must be submitted in duplicate to the State Office for Nuclear Safety and Radiation Protection, which shall remain a copy of the documents. Non-official table of contents
§ 8 Consent for decommissioning
(1) The decommissioning of assets or workplaces subject to approval for the operation of radiation installations containing radioactive substances or in which the transport of radioactive substances is carried out shall be subject to the agreement of the Member States.(2) With the request for consent to set aside, it is necessary to prove that
- is a proper disposal or transmission of radioactive substances or radiation equipment,
- workplaces, equipment or installations are sufficiently decontaminated,
- Radiation protection is ensured during the decommissioning.
(3) The further use of workplaces, work equipment or facilities requires 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 installations which do not contain any radioactive substances shall be reported to the State Office for Nuclear Safety and Radiation Protection in the form of a communication on the further whereabout. Non-official table of contents
§ 9 Assent for subprojects and special works
Subprojects and special work, such as new technologies, Industrial search or temporary work, where the operation of radiation facilities or a traffic with radioactive materials is intended, require approval. The nature and scope of the documents to be submitted correspond to those in § 7. Consent shall be part of the authorisation granted. Non-official table of contents
§ 10 Approval of import
(1) Individual imports of radiation devices or enclosed radiation sources require the Consent if there is no authorisation pursuant to § 5 of the Regulation. The application shall be submitted by the import operation. It must be accompanied by the following documents:
- technical documentation, of the type and function
- application purpose,
- intended operation for use or Traffic,
- Radiation protection approval or similar documents of the country of origin,
- scheduled operation for maintenance.
(2) The import contract must not be completed until the import consent has been granted. Non-official table of contents
§ 11 Changes
Before you change the human or factual requirements that are based on a permit , a change of authorisation shall be requested. Non-official table of contents
§ 12 acceptance
Working materials, working methods and workplaces for the operation of radiation facilities and transport of radioactive substances shall be removed prior to the granting of a permit 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.
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To § 4 paragraph 5 of the Regulation
§ 13 Registration
(1) The traffic with enclosed radiation sources or the operation of radiation facilities is subject to registration if
- unified and confirmed by the State Office for Nuclear Safety and Radiation Protection Application documents, in particular the radiation protection technical project, the operating instructions and the occupational radiation protection order, are available,
- the proof is provided. is that the operation is in accordance with the operational documents,
- a responsible employee is named and
- a decrease in the compliance of the radiation protection requirements.
(2) The registration is subject to stomatological X-ray equipment and measurement, control and Control devices using enclosed radiation sources, if this is shown in the radiation protection type approval.(3) The State Office for Nuclear Safety and Radiation Protection shall send the documents specified in the framework of the radiation protection type approval to the responsible employee in duplicate with the endorsement of the responsible employee. A copy with a registration note is returned to the company.(4) The registration is bound to:
- the operation,
- the responsible contributor,
- the work project,
- the type, activity or amount of radioactive substances or the type and activity of the enclosed radiation sources and the type and characteristics of the radiation devices as well as their Number,
- the workrooms.
(5) A change in the human or material requirements underlying the registration, and the decommissioning of the registered radiation facilities and enclosed radiation sources shall be notified to the State Office for Nuclear Safety and Radiation Protection within 14 days of change.
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To § 4 (6) of the Regulation
§ 14 Application
(1) The application is subject to
- radiation sources for display control of radiation meters,
- Radiation sources for educational purposes,
- Radiation devices for educational purposes and
- Ionization Smoke Detector,
if this is shown in the Radiation Protection Type approval.(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 registration must be notified to the State Office for Nuclear Safety and Radiation Protection within 4 weeks.
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To § 4 (7) and § 5 of the Ordinance
§ 15 Permission for Special Radiation Devices
The use of radiation devices, whose acceleration voltage does not exceed 5 kV for charged particles, is permitted without the approval, registration, registration and type approval.
- Non-official table of contents
To § 6 para. 2 of the Regulation
§ 16 Powers and duties of inspectors and authorized doctors
(1) The inspectors of the State Office for Nuclear safety and radiation protection are authorized:
- Buildings, spaces, facilities, laboratories and other to enter workplaces at any time in the performance of their duties and to carry out tests, measurements or sampling, and in principle, the legislation and the operational provisions relating to health, safety and fire protection
- See or request documents on nuclear safety and radiation protection, require information and assessments, and require the necessary information to be provided. To make documentation,
- by the heads of the companies and the responsible employees the elimination of defects in the guarantee of nuclear safety and radiation protection,
- to impose conditions on the heads of the establishments and to hire them, in the event of serious breaches of nuclear safety legislation and the radiation protection or direct hazards to persons or property, the environment, the continuation of work or the activities of radiation workers and operators, or spaces and installations. locking,
- in exceptional events to initiate unnecessarily necessary actions to avert threats to life and health or to prevent to give instructions for serious damage, if the operation cannot carry out these measures yourself,
- in the case of infringements of the law and of the law, to require the initiation of disciplinary measures, to issue a warning with the order of the order pursuant to Article 30 (5) of the Regulation or to request the initiation of disciplinary measures by the head of the establishment, or the non-compliance of the conditions of the company's head of business. Presidents of the State Office for Nuclear Safety and Radiation Protection in accordance with § 30 of the Regulation to propose the initiation of a disciplinary criminal proceedings.
(2) The doctors of the State Office for Nuclear Safety and Radiation Protection Have the right:
- Radiological protection doctors with regard to radiation protection control of Supervising radiation workers and operators,
- See the health records of radiation workers and operators,
- Medical examinations to be carried out by the State Office for Nuclear Safety and Radiation Protection or in health facilities defined for this purpose and radiological protection medical
() The issuing of instructions or the implementation of measures pursuant to the provisions of the first paragraph of paragraph 1. 5 and para. 2, para. 3.
To § 6 para. 3 of the Regulation
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State personaldosimetric Monitoring
(1) People's dosimetric monitoring of the external radiation load of Radiation workshops of categories A and B according to § 31 are carried out with personal dosemeters, which are made available and evaluated by the State Office for Nuclear Safety and Radiation Protection. 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 passenger dosemeters shall be carried out monthly for category A radiation workers. The evaluation of the passenger dosemeters can be carried out at a greater time interval for the category B radiation workers.(3) The time interval for the evaluation of personal dosimeters and for the monitoring of other persons on external radiation exposure shall be taken in the case of the granting of the permit. Non-official table of contents
The person dosimetry monitoring of the internal radiation exposure of radiation workers, particularly in The State Office for Nuclear Safety and Radiation Protection is 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. Non-official table of contents
(1) Radiation workshops are to be informed about the results of personal dosimetry monitoring. The radiation exposure determined by the person-dosimetry monitoring shall be evaluated by the responsible employee with the beam-workers and registered in a loading register. Dose values for individual persons below the recording threshold are negligible in the determination of the individual radiation exposure.(2) If radiation workers are used in radiation protection areas of other holdings, the delegating operation shall ensure that the person dosimetric monitoring is carried out and the results of the monitoring are registered. Non-official table of contents
(1) About person-dosimetrically-to-be-monitored workers are the State Office for Nuclear Safety and Radiation protection must be provided with the following information:
- Name, birth name, first name,
- person measure,
- learned profession, current activity,
- The beginning of the watchful activity, previous operation in which the person dosimetric monitoring took place,
- type of work, beam type 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 during previous activities.(3) The Office for Nuclear Safety and Radiation Protection shall be notified of the termination of the activity of personnel dosimetrically to be monitored. The results of the personnel dosimetric monitoring are kept by the State Office for Nuclear Safety and Radiation Protection 50 years after the completion of the work.
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To § 7 para. 1 of the Regulation
§ 21 monitoring measurements
(1) establishments in which atomic energy is applied have the rules on comply with the operational measurement system and must have all the means of measurement necessary to ensure operational monitoring. The measurement results must be registered, evaluated and kept.(2) For monitoring measurements, suitable and calibrated measuring instruments are to be used for the measurement task. The provisions of the Office for Standardization, Measurements and Testing of Goods relating to the State and Operational Testing of Means of Measurement must be observed.(3) Measurements shall be carried out on a regular basis and in the event of changes which may have a significant effect on the radiation protection situation and in the event of exceptional events. Provisions for this are to be found in the occupational radiation protection order.(4) In order to assess the radiation protection situation, local doses and local dose services should be measured in radiation protection areas and in 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 means and methods of measurement shall be used which shall: allow surface contamination and concentrations of activity in air and water to be determined or the tightness of enclosed radiation sources to be tested.(5) The emission of radioactive substances with the waste air or the waste water or otherwise into the environment shall be monitored by measurement. The results are to be registered and kept.(6) In order to determine or limit the individual exposure to radiation, it is necessary, if necessary, to use individual dosemeters, individual dose rate warns or methods for the individual determination of the incorporation. Provisions shall be laid down in the case of the granting of the permit.(7) When leaving radiation protection areas in which open radioactive substances may be handled or in which open radioactive substances may be present, persons and objects shall be tested for contamination.(8) In justified cases, the monitoring of measurement can be replaced by an estimation. This procedure is subject to confirmation by the State Office for Nuclear Safety and Radiation Protection.(9) The requirements for the storage of measurement results shall be made in legislation or in the granting of permission.
To § 7 (2) and (3) of the Regulation
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§ 22 Rights and obligations of the radiation protection officer
(1) The radiation protection officer has complied with the Control of radiation protection in its area of competence. 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 as well as the responsible staff.(2) The radiation protection officer shall be entitled to enter all workplaces and facilities of his or her area of responsibility at any time for the purpose of radiation protection control, to request information, reports and assessments on radiation protection; and To inspect all documents relating to radiation protection.(3) The radiation protection officer shall carry out regular checks in his area of responsibility and report to the head of the holding at least annually on the radiation protection situation. Provisions on the number and scope of control measures shall be taken in the case of the granting of the authorisation.(4) The radiation protection officer shall keep a control book in which all the checks, the deficiencies identified, the measures taken to remedy the situation, the time limit for the elimination of the deficiencies and special events must be entered.(5) The radiation protection officer shall be assisted in the planning and preparation of new work projects involving radiation protection issues. It has to participate in the definition of the radiation workshop and to confirm the Occupational Radiation Protection Ordinance.(6) In the event of deficiencies identified in radiation protection or in the event of non-compliance with radiation protection provisions, the radiation protection officer shall have the correct and timely removal of the deficiencies and compliance with the radiation protection provisions by the senior staff members. to call for radiation protection provisions.(7) The radiation protection officer shall be able to block premises, facilities and installations at the risk of danger to persons and property. Such measures shall be brought to the attention of the head of the holding and the State Office for Nuclear Safety and Radiation Protection immediately.(8) The radiation protection officer shall be obliged to report to the State Office for Nuclear Safety and Radiation Protection on request concerning the control activities and assessments, opinions or opinions on problems relating to his activities to be considered as radiation protection officer.(9) The tasks of the radiation protection officer and his/her rights and obligations shall be defined in his functional 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 Commissioner for Nuclear Safety shall be derived from the legislation.
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To § 8 of the Regulation
§ 23 Radiation Protection Medical Suitability And Monitoring Investigations and Establishment of Radiation Protection Physicians
(1) Radiation-based and operator-related have been subject to radiation protection and surveillance examinations before taking up and continuing their activities, and following exceptional events. The heads of the companies have to ensure participation.(2) Radiation physicians shall be appointed by the head of the Department of Health and Social Affairs of the Council of the District (District Doctor) on a proposal from the Directors of the Labour Inspections of the councils of the counties and the State Office for To name 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 companies of the directors of the labour market inspections of the 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.
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To § 10 of the Regulation
§ 24 Justification procedure
The justification of a type of application of atomic energy is based on the legislation in force for the preparation of an investment project, a production facility 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 approval is provided, the assessment will take place as part of the approval.
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To § 11 of the Regulation
§ 25 Primary limits
(1) The application of atomic energy applies to the individual radiation exposure of the radiation workers in 12 consecutive Months, the following primary limits:
|50 mSv as effective equivalent dose,|
|500 mSv as equivalent dose for the Organs and tissues|
|150 mSv as an equivalent dose for the eye lens.|
In the case of incorporations, the following steps are taken: Dose of equivalent dose is the 50-year follow-up dose. For women under 45 years of age, 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 shall be considered as the limit value of the effective dose equivalent of 5 mSv and as a limit of the dose equivalent for organs and tissue 50 mSv. In addition, it must be secured that the average value of the effective equivalent dose per year is limited to 1 mSv over a period of 50 years. Non-official table of contents
§ 26 Secondary limit values
(1) On external irradiation, the limit values in accordance with § 25 (1) shall be deemed to be complied with if the the following secondary limit values are observed:
- for 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;
- for neutron radiation up to 20 MeV for the maximum dose equivalent 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;
- with photon radiation from 10 keV to 10 MeV and at neutron radiation up to 20 MeV for maximum equivalent dose at the hands: 500 mSv per year;
- with photon radiation below 10 keV and for beta radiation for maximum surface dose: 500 mSv per year and
- for the eye lens: 150 mSv per year.
For radiation energies outside of the mentioned energy ranges and other types of radiation, secondary limit values will be used in the granting of the Permission set.(2) The necessary calculation bases and technical regulations for the verification of compliance with the secondary limit values referred to in paragraph 1 shall be set in standards. Compliance with the limit values can also be demonstrated with the radiation exposures which indicate the person dosimeters used in the state surveillance.(3) In the case of internal irradiation, the limit values of the radiation exposure in accordance with section 25 (1) shall be deemed to have been complied with if the column 3 or 3 of Table 1 in Table 1 of Appendix 2 Column 4 limits of the annual activity intake ALI for inhalation and for ingestion not shall be exceeded.(4) For a radionuclide mixture of known percentage composition:
1 ------ p (deep) i
------------ = > ----------
ALI (deep) Gem. ------ ALI (deep) i
i = 1
- ALI (deep) Gem.
- annual activity intake limit for radionuclide
- p (deep) i
- relative share of i-th Radionuclides in the total activity of the mixture
- ALI (deep) i
- Anniversary activity feed limit for the i-th radionuclide
- number of radionuclides in mixture.
(5) Combined outer and inner irradiation, the primary limit values for radiation workers shall be deemed to be observed if the following conditions are met at the same time:
H (deep) d ------ I (deep) j
------------ + > ---------- < 1
50 mSv ------ ALI (deep) j =
j = 1
H (deep) s
---------- < 1
500 mSv =
- I (deep) j
- Annual Activity Feed of the j-th radionuclides
- ALI (deep) j
- Year-of-year radionuclide limit
- H (deep) d
- Maximum surface dose on the body's body for photon radiation in the energy range of 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 shall be considered as secondary limits 1/10 of the limit values according to para. 1 and for the eye lens. mSv per year. The additional requirement in Section 25 (2) shall apply mutatily.(7) For 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 referred to in paragraph 3. If only adults are affected, 1/10 and 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 individual persons from the population, paragraph 5 shall apply mutaficiently. unofficial table of contents
§ 27 Derived limits
(1) Are derived limits for the mean of a size over a given Time interval, the actual value of the limited size may fluctuate over shorter time intervals by this mean value.(2) In the case of external photon irradiation with photon energies up to 3 MeV, derived limit values can be given as free in air energy dose or energy dose performance under the condition of the secondary electron balance. Air, water or soft tissue may be used as the reference substance for the energy dose. When the limit values are derived, an equivalent dose in Sv may be equated with an energy dose in Gy that is measured freely in air.(3) The limit value for the mean annual activity concentration in air DAC is the activity concentration of a radionuclide in air,
- which leads at a breathing rate of 1.2 m (high) 3 h (high)-i within a working year of 2,000 h to an annual activity intake at the level of the ALI or
- which leads to a radiation exposure during a submersion within a working year of 2,000 hours, which corresponds to the limit values in § 25 para. 1.
- for all radionuclides except EdelgasenDAC*) = 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 given in Appendix 2, Table 2, column 3.
(4) For the DAC of radionuclide mixes of known The percentage composition shall apply in accordance with Section 26 (4).(5) If no other provisions are made in legislation or in the granting of a permit, the primary limit values for individual persons from the population shall be deemed to have been complied with if the mean annual activity concentration in air
- for all radionuclides except noble gases 1/100 DAC,
- for noble gases 1/40 resp. the average value per year over a period of 50 years is not more than 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 when proof of compliance with the limit values in accordance with § 25.(7) On the basis of job-related analyses, which lead to specific load models, different surface contamination limit values can be derived and authorized by the State Office for Nuclear Safety and Radiation Protection .
*) The external radiation load is not included in this value. Non-official table of contents
§ 28 Free limits
(1) For radioactive material, you can choose:
- as the free limit for the activity, the values set in Appendix 2, Table 1, column 5. If more than one radionuclide is present at the same time, the following condition must be met:
------ A (deep) i
> ---------- < 1
------ F (deep) i =
i = 1
- A (deep) i
- activity of i-th radionuclides
- F (deep) i
- Free-bound for the i-th radionuclide
- number of radionuclides at the same
- as free-limit of the activity concentration 100 Bq/g or in the case of solid natural radioactive substances 500 Bq/g.
2) Radioactively contaminated material shall be subject to the following conditions: as a free limit, an activity concentration of 0.2 Bq/g. If this exclusively contains radionuclides 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 the free limit for the relative mass fraction of uranium or thorium is 0.01%. (4) Radioactive discards are considered to be the free limit of the activity concentration.
- Introduction to communal sewerage:
- for radionuclides with half-life times < = 60 tagepro cbm ejection 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)
- Introduction to Waters:
- per cbm ejection 1/100 of the ALI according to Appendix 2 Table 1, column 4, or Section 26 (1) 4;
- emit into the atmosphere:
- Radionuclides other than Edelgaseim ejection 1/10 of the DAC according to § 27 para. 3 resp. 4; Edelgaseim Auslitter 1/10 of the DAC for submersion according to Appendix 2, Table 2, column 3a or Section 27 (1) 4;
- solid discards landfill:
- 0, 2 Bq/g. If these only contain radionuclides of the natural decay series in the radioactive equilibrium, this value shall apply to radium
use of nuclear installations or radiation equipment or the transport of such radionuclides shall be subject to the following conditions: radioactive material shall not exceed the values laid down in Annex 2, Table 1, column 5, each week.(5) Radioactive waste shall be subject to the free limits of radioactive waste.(6) In the case of 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. Section 26 (4) divided by the average annual per capita consumption in kg of the food in question.(7) For radiolabeled medicinal products and for medicinal products labelled with radionuclides, an activity concentration which is 10 (high) -8 times the values given in Annex 2, Table 1, column 3, per gram shall be considered as the free-limit.(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.
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To § 12 of the Regulation
§ 29 Performance of optimization
(1) Optimisation of radiation protection measures must 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 Permission to be complied with.(2) In the application of atomic energy, companies have to examine further possibilities for the optimization of radiation protection measures in their areas and consequent measures to reduce the risk of radiation.
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To § 13 of the Regulation
§ 30 Exposure to radiation under special conditions
(1) Under special conditions, radiation exposure may not exceed twice and during lifetime no more than five times the limit values in accordance with § 25 (1). .(2) Under special conditions, radiation exposure shall be subject to careful examination and prior confirmation by the head of the establishment and the reporting to the State Office for Nuclear Safety and Radiation Protection. If special radiation loads are 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 thoroughly informed in the actions to be carried out, to inform them of existing sources of danger and to inform them of any measures taken, with which the radiation exposure can be kept 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 are to be informed of the radiation exposure that has occurred.(4) Radiation loads under special conditions shall not be suspended:
- Radiation workers, which have been exposed to radiation exposures exceeding five times the annual limit values in accordance with Article 25 (1) of this Directive in the event of exceptional events.
- Women with a life age under 45 years.
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To § 14 paragraph 1 of the Regulation
§ 31 Categories for Radiation Workers
(1) For radiation workers, categories A and B are set:
- Category A radiation workers are working in working conditions where radiation exposure can exceed 3/10 of the limit values in accordance with Article 25 (1),
- Category B radiators are active in working conditions where radiation exposure does not exceed 3/10 of the limit values in accordance with Section 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 take place under conditions in which the radiation exposure may not exceed 3/10 of the limit values in accordance with § 25 (1).(3) In the definition of the categories of radiation workers, the exposure to radiation which may occur in the event of extraordinary events shall not be taken into account.
To § 15 of the Regulation
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§ 32 Characterization of Radiation Protection Areas
(1) Radiation protection areas are to be set up where within one year may result in radiation exposures exceeding 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) According to the practical requirements, radiation protection areas are divided into
- Radiation Protection Area I, where within a year radiation exposure can be achieved that exceed 3/10 of the limit values in accordance with § 25 (1), and
- Radiation Protection Area II, which can be used within one year to produce radiation exposures that do not exceed 3/10 of the limit values in accordance with § 25 (1), if not from the ()
the definition of radiation protection areas, it is possible to use as far as possible structural limitations.(4) Radiation protection areas shall be marked and shall 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. Where there is a risk of contamination, facilities must be provided for contamination control, decontamination and clothing changes.(5) In principle, access to radiation protection areas is only permitted for
- Conduct of professional activities,
- Patients on radiological measures,
- Apprentices, students, and other workers to qualify for qualification in compliance with the conditions set out in § 31 (2),
- Visitors to the conditions set out when permission is granted. 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 on an equal footing.
- Non-official Table of Contents
To § 16 para. 1 of the regulation
§ 33 Organisational Radiation Protection Measures
(1) Only the absolutely necessary handling of radioactive substances Use activities and radionuclides with as low a half-life as possible. 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 provided, food, drink and smoking, the use of health care products and cosmetics, and other acts which are such supply shall be prohibited. Under special arrangements, drinking can be permitted. The ban does not apply to the extraction of radioactive material.(3) In the case of the transport of radioactive material and radioactive material, work organisational and hygienic measures must be taken which limit the supply of radioactive substances to a minimum. Non-official table of contents
§ 34 Lab Classes
(1) Working spaces for dealing with open radioactive material are used in accordance with the The free boundary and the activity that is handled in the work rooms is divided into the following classes:
| Free limits for radioactive material|| Activity Limit for Work Spaces|
| Class I|| Class II|| Class III|
|5 kBq||over 0.5 GBq||to 0.5 GBq||to 0.5 MBq|
|50 kBq||over 5 GBq||to 5 GBq|| to 5 MBq|
|> 50 kBq||over 50 GBq||to 50 GBq|| up to 50 MBq|
|3 (deep) H||over 5 TBq||up to 5 TBq|| to 5 GBq|
(2) For storage of open radioactive material in work rooms, higher activities can be approved in the permit.(3) Paragraphs 1 and 2 shall not apply to the transport of radioactive raw materials.(4) The requirements for the construction and equipment for the working spaces shall be regulated separately. Non-official table of contents
§ 35 Surface contamination
(1) Surface contamination should not have the values set out in Table 3 of Appendix 2 shall be exceeded.(2) Surface contamination
- exceeds the values given in Appendix 2, Table 3, points 1 to 4. after multiple humid decontamination with mild decontamination agents
- or the values indicated in Table 3 (4) to (6) after multiple normal washing or Table 3, point 1. 7 values after decontamination with soap and brush without damage to the skin,
are further measures according to an assessment of the expected radiation exposure, taking as far as possible a consideration of the real Conditions to be determined. 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
§ 36 Test of Enclosed Radiation Sources
(1) Enclosed Sources of Radiation are Intactness, Poetry, To check contamination and compliance with the specified period of use.(2) The test distances as well as the type of examination shall be regulated separately.(3) As a function of the working situation, a denser sequence of tests shall be made, where appropriate, in order to ensure the tightness and exclusion of contamination.(4) If it is found that the enclosed radiation sources are damaged, leaked or contaminated, it is necessary to proceed in accordance with the provisions relating to the behaviour in the event of exceptional events.(5) The enclosed radiation sources shall be equivalent to those radioactive substances which meet the requirements of enclosed radiation sources.
To § 16 para. 2 of the Regulation
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§ 37 Protection Facilities
Working sites and work equipment for the application of nuclear energy are required to be used to equip with technical equipment 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. Non-official table of contents
§ 38 Maintenance
The managers of the establishments in which radiation facilities are used have 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.
-unofficial Table of contents
To § 16 para. 3 of the Regulation
§ 39 Radiation Protection Order
(1) In the occupational radiation protection order, taking into account the concrete conditions of use and work tasks, the regulations on the working behaviour, the work organisation, maintenance technologies and radiation protection monitoring, including 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 may be prescribed by it and shall be kept 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. Non-official table of contents
§ 40 teachings
(1) Radiation workshops and operators need to be informed of the hazards associated with the The application of atomic energy, its obligations in radiation protection as well as on the basis of the occupational radiation protection order on protective measures and proper conduct, in particular in the case of extraordinary events, are to be informed in an active manner. 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 and guidelines must be taken into account.(2) Radiation workers and operators shall be lecturing on radiation protection at intervals of 3 months and in the case of resumption of activity 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. Non-official table of contents
§ 41 Obligations of radiators and operators
Radiation and operators have the following: to comply scrupulously with radiation protection regulations and limit values and conditions of nuclear safe operation of nuclear installations, and to carry out their work in such a way that they do not endanger themselves and others. You are obliged to report any defects in radiation protection and extraordinary events occurring to the responsible employee or radiation protection officer immediately.
-Non-official table of contents
To § 16 (4) and (5) of Regulation
§ 42 Verification and retention
(1) On the entry, use and The fate of radioactive substances shall be documented. In the event of the loss of radioactive substances, it is necessary to proceed in accordance with the provisions relating to behaviour in the event of exceptional events.(2) Radioactive materials and radioactive waste are to be kept under closure in special storage rooms and containers made of hard-combustible building materials. Radioactive materials and radioactive waste must not be stored together:
- fire-hazardous fabrics,
- explosive materials,
- aggressive chemicals (e.g. acids),
- Food and drink products, commodities, feedingstuffs, Medicinal products and similar substances, preparations and articles, health care products, pesticides.
(3) Explosive substances may only be used with the consent of the local fire-fighting organs in neighbouring rooms. shall be kept. The requirements for the storage spaces and storage containers for radioactive materials and radioactive waste are separately regulated.(4) In the time intervals to be determined in the occupational radiation protection order, storage spaces and storage containers shall be regularly checked for integrity and contamination. The examination shall be subject to proof.(5) Storage spaces and storage containers shall be marked with the radiation warning sign.(6) The permitted activity in storage rooms is defined as a function of the construction and equipment of these spaces in the permit documents.
- Non-official table of contents
To § 20 of the Regulation
§ 43 Claims to ensure nuclear safety
(1) For nuclear installations, the requirements for ensuring the To derive nuclear safety and protection 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 must be taken into account.(2) Incident analysis includes:
- Selection of triggering events that are related to nuclear safety influence (output events),
- Investigation of the incident sequences, taking into account the initial state of the nuclear plant, the function of operation and Safety devices and actions of the operator and
- Determination of the effects of the accident in dependence on the incident sequences.
(3) In the The result of the incident analyses 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 installation and the Actions of the operator to avoid unauthorised radiation loads for the operating personnel and persons in the environment.(4) The nature and extent of incident analysis, the failure of interpretations and their permissible effects, as well as claims to ensure nuclear safety, shall be set out in legislation or in the granting of authorisation. . Non-official table of contents
§ 44 Quality assurance for nuclear plants
(1) For the project planning, production, construction, commissioning and operation of a nuclear installation and of components essential to nuclear safety shall be laid down in quality assurance systems, the complex measures to be taken to ensure the quality required.(2) A quality assurance system must be included:
- Quality and quality specifications Reliability to ensure nuclear safety,
- Measures to develop binding working documents, such as standards and technical documentation for the securing of quality-oriented work, and provisions for the timely handover of these working documents to the working persons,
- Testing and Control rules, such as methods for exact error detection and for checking the correctness of the test and measurement equipment used,
- quality management of the work,
- procedures for assessing and rectifying identified defects and providing information about the causes of errors,
- considerations of responsibility for the implementation of the individual quality assurance measures.
(3) The results of the quality checks are to be evaluated on a regular basis, Any inadequacies in the quality assurance system must be rectified without delay.(4) The requirements for quality assurance in excess of the provisions laid down in special legislation shall be laid down in the granting of the permit.
-unofficial table of contents
To § 21 of the Regulation
§ 45 exposures to the site for core assets
The location of a core asset should be set to
- the frequency of natural events or external civilizational influences, the nuclear hawaria can cause fixed limits,
- the environment conditions the function of systems and measures to ensure nuclear safety
- a protected area can be set up if the nature of the core facility requires that, and
- to the extent necessary, measures can be taken to protect against the effects of nuclear accidents in the environment.
Further stipulations will be made in
- A non-official table of contents
To § 23 of the Regulation
§ 46 Requirements for the operation of nuclear plants
(1) For each nuclear facility, nuclear safety conditions are based on incident analysis Limit values for operating parameters and conditions for the condition and operational capability of important safety devices.(2) Operating rules shall be drawn up for the operation of a nuclear installation in which the limit values and conditions of the nuclear-safe operation are to be included in a suitable form.(3) The operation of a nuclear installation shall be permitted only for the conditions determined by the limit values and conditions of nuclear safe operation. Compliance with the limit values and conditions of nuclear safe operation must be monitored.(4) In the event of deviations from the limit values and conditions of nuclear safe operation, the measures necessary for the restoration of nuclear safety shall be implemented without delay.(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 case of tests detected deviations from the required properties shall be recorded, investigated and eliminated.(6) The results of the monitoring must be documented and evaluated on a regular basis, in order to identify influences on nuclear safety and to improve measures to ensure nuclear safety.
-Non-official table of contents
To § 26 of the Regulation
§ 47 Notification of the radiation protection doctor and release after extraordinary events
(1) In the event of exceptional events, the radiation protection doctor shall be notified of the suspicion that a worker has received a radiation exposure above the limit values laid down in § 25 (1).(2) In the event of an exceptional event, installations, workplaces, technical facilities and work equipment shall be subject to approval by the State Office for Nuclear Safety and Radiation Protection before they are further used. It can commission the radiation protection officer with the release.
- A non-official table of contents
To § 27 para. 1 of the Regulation
§ 48 Qualifications
(1) State qualification certificates are issued by the State Office for Nuclear Safety and Radiation Protection.(2) Qualified qualifications issued may be declared invalid if the invitation to attend further training events is not followed. State qualification certificates can be issued for a limited period. Your validity will be extended after continuing training events.
- A non-official table of contents
To § 27 paragraph 5 of the Regulation
§ 49 Operational trainings
The company training courses are based on the state-of-the-art nuclear safety and radiation protection office to implement framework programmes. In special cases, the programs for the operational training are to be coordinated with the State Office for Nuclear Safety and Radiation Protection.
- Non-official Table of Contents
To § 29 of the Regulation
§ 50 Integration of the Control Body in Research and Development Projects
(1) On Research and Development Projects The State Office for Nuclear Safety and Radiation Protection shall be informed at an early stage, but at the latest in the phase of the preparation of studies, forecasts or specifications, on the relevant research and development projects.(2) In the case of registration, the State Office for Nuclear Safety and Radiation Protection shall be responsible,
- which research and development projects will be included in the control of the State Office for Nuclear Safety and Radiation Protection and for which topics and studies it documents
- what work results are to be presented to it.
The decisions taken are to be communicated to the state organs or businesses.(3) The State Office for Nuclear Safety and Radiation Protection shall 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 not or not in the to the extent to which the results achieved are socially necessary and
- the results achieved do not meet the requirements of nuclear safety and radiation protection .
The heads of the establishments shall, on the basis of the proposals, initiate the necessary measures. Non-official table of contents
§ 51 Final determination
This implementation specification occurs on the 1. February 1985, in force. Non-official table of contents
The President of the State Office for Nuclear Safety and Radiation Protection of the German Democratic Republic Republic of Non-official 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 the 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)|
|1.E-03|| 27, 0||2|
* 1) Authorized works of maximum equivalent dose performance in body-like phantoms in the frontal parallel radiation incident of monoenergetic neutrons
* 2) 2.5E-08 = 2.5 x 10 (high) -8.
* 3) Maximum equivalent dose rate divided by the amount of energy absorbed in the depth in which the maximum dose of equivalent dose occurs. unofficial table of contents
(contents: non-representable tables,
find: GBl. I 1984, No 30, pp. 358-372,
of the individual amendments, cf. Footnote) unofficial table of contents
appendix EV extract from EinigVtr Appendix II, Chapter XII, Section III
(BGBl. II 1990, 889, 1226)
, the following law of the German Democratic Republic shall remain in force:
- Regulation on ensuring nuclear safety and radiation protection from 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 this Office, as referred to in the continuing regulations.