Key Benefits:
191. Ordinance of the Federal Minister of Agriculture, Forestry, Environment and Water Management, the Federal Minister for Economic Affairs and Labour, the Federal Minister of Transport, Innovation and Technology, the Federal Minister for Education, Science and Technology Culture and the Federal Minister for Health and Women on General measures for the protection of persons against damage caused by ionizing radiation (General Radiation Protection Ordinance-AllgStrSchV)
Pursuant to sections 10a (2), 13 (1), 13a (3), 17 (2), 19 (1), 20 (1), 20 (1), 23 (1) and (2), 25 (4) (4) (1), 26 (5), 32 (6), 34 (7), 35e, 35f (5), 36 (1) and (3) and 36b (1) StrSchG, BGBl). No 227/1969, as last amended by the Federal Law BGBl. I n ° 137/2004,
1. |
as far as businesses are concerned, the 1994 Commercial Code, BGBl. No 194/1994, by the Federal Minister for Economic Affairs and Labour, in agreement with the Federal Minister for Agriculture, Forestry, the Environment and Water Management, |
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2. |
with regard to rail, road, air and maritime transport and workers ' protection for businesses, which are the Federal Law on Transport-Labour Inspections (VAIG 1994), BGBl. No 650/1994, by the Federal Minister of Transport, Innovation and Technology, in agreement with the Federal Minister for Agriculture, Forestry, the Environment and Water Management, |
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3. |
with regard to the nuclear reactors and the particle accelerators in the universities and research institutes of the Austrian Academy of Sciences and with regard to radiological emergency situations, to the extent that schools which are Federal School Supervision Act, BGBl. No 240/1962, are affected by the Federal Minister of Education, Science and Culture in agreement with the Federal Minister for Agriculture, Forestry, the Environment and Water Management, |
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4. |
with regard to the interests of § § 35 and 36 StrSchG, which relate to matters relating to the handling of radiation sources in the field of medicine, by the Federal Minister for Health and Women, |
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5. |
, incidentally, the Federal Minister for Agriculture, Forestry, the Environment and Water Management, |
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a) |
with regard to § § 23, 32 (4) and 33 (3) of the StrSchG, in agreement with the Federal Minister of Finance and, in so far as they are business-related companies, with the Federal Minister for Economic Affairs and Labour, |
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b) |
as regards Section 36 of the StrSchG, members of the Federal Army or the Military Administration or military installations and facilities, in agreement with the Federal Minister for National Defense, |
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ordering: |
table of contents |
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Paragraph |
Object/Label |
Part 1 |
|
1. Section principles, scope of application |
|
§ 1. |
Scope |
§ 2. |
Justification |
§ 3. |
Tuning |
Section 2 General radiation protection provisions |
|
§ 4. |
Safety analysis, incident analysis, emergency planning |
§ 5. |
Quality assurance, quality control |
3. Section Exceptions to the obligation to notify and to notify, type approvals |
|
§ 6. |
Derogations from the obligation to grant authorisation |
§ 7. |
Exemptions from reporting requirements |
§ 8. |
Type approvals |
Part 2 |
|
1. Section General protections |
|
§ 9. |
Dose terms |
§ 10. |
Dose by ionizing radiation |
§ 11. |
Categories of professionally radiated persons |
§ 12. |
Maximum authorised dose for persons exposed to radiation |
§ 13. |
Expositions particularly approved |
§ 14. |
Maximum authorised dose for individuals of the population |
§ 15. |
Responsibility of the holder of the authorization |
§ 16. |
Radiation protection teachings and work instructions |
2. Section Radiation Areas |
|
§ 17. |
Radiation area, control and monitoring area |
§ 18. |
Requirements for control and surveillance areas |
§ 19. |
Temporary abolition of radiation areas |
§ 20. |
Access for visitors and persons responsible for non-authorisation activities |
§ 21. |
Access to official bodies and qualified experts |
§ 22. |
Radiation applications |
§ 23. |
Personal protective equipment |
§ 24. |
Radioactivity monitoring of the environment |
3. Section Physical Control |
|
§ 25. |
Personal dosimetry |
§ 26. |
Incorporation monitoring |
§ 27. |
Evaluation of dosimetric measurements |
§ 28. |
Determination of the effective dose and the dose of equivalents |
§ 29. |
Monitoring of jobs |
§ 30. |
Meters |
§ 31. |
Records |
Section Medical Examinations |
|
§ 32. |
Aptitude investigation |
§ 33. |
Control investigation |
§ 34. |
Immediate investigation |
§ 35. |
Final investigation |
§ 36. |
Medical certificate |
§ 37. |
Authorised Doctors |
§ 38. |
Duties of the holder of the authorization |
§ 39. |
Accounting of medical radiation protection investigations |
Section 5. Persons responsible for the exercise of radiation protection |
|
§ 40. |
Obligations and rights |
§ 41. |
Education and training in the medical field |
§ 42. |
Education and training in the non-medical sector |
§ 43. |
Education and training in the field of research reactors |
6. section Protection of external workers, radiation protection passport |
|
§ 44. |
Obligations of the holder of an external company's consent |
§ 45. |
Obligations of the holder of the authorization, in whose control area external workers are active |
§ 46. |
Obligations of external workers |
§ 47. |
Content and form of the radiation protection passport |
§ 48. |
Exhibition, registration and evidence of radiation protection passports |
§ 49. |
Management of the radiation protection pass |
§ 50. |
Special arrangements for certain occupational groups |
Part 3 |
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1. Section General provisions |
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§ 51. |
Scope |
§ 52. |
Open and enclosed radioactive substances |
§ 53. |
Labelling of radioactive substances |
§ 54. |
Storage facilities |
§ 55. |
Transport of radioactive materials within establishments |
§ 56. |
Cleaning and repair work |
§ 57. |
Contamination |
§ 58. |
Decontamination |
§ 59. |
Recording and reporting obligations |
§ 60. |
Transboundary movements of radioactive substances subject to notification |
§ 61. |
Radioactive substances in or radioactive contamination of materials intended for recycling and re-use |
2. Section of Radioactive Substances |
|
§ 62. |
Nature |
§ 63. |
Leak testing |
§ 64. |
High-level radioactive sources |
§ 65. |
Non-medical use of surrounded radioactive substances |
§ 66. |
Operating rules |
3. Section Offene radioactive substances |
|
§ 67. |
Handling of open radioactive substances |
§ 68. |
Protection against contamination |
§ 69. |
Workplace types |
§ 70. |
Workplaces of Type C |
§ 71. |
Workplaces of Type B |
§ 72. |
Workplaces of Type A |
§ 73. |
Application of open radioactive substances in the environment |
4. Subsection of radioactive substances |
|
§ 74. |
Discharge of liquid and gaseous radioactive substances |
5. Section Radioactive Waste |
|
§ 75. |
General provisions |
§ 76. |
Collection of radioactive waste, waste categories |
§ 77. |
Temporary storage of radioactive waste in establishments |
§ 78. |
Discharge of radioactive waste |
§ 79. |
Release |
Part 4 |
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1. Section for non-medical X-ray equipment |
|
§ 80. |
General provisions |
§ 81. |
Requirements |
§ 82. |
Operating rules |
§ 83. |
Specific provisions for full protection institutions |
2. Section particle accelerator for non-medical applications |
|
§ 84. |
General provisions |
§ 85. |
Requirements |
§ 86. |
Operating rules |
Part 5 |
|
§ 87. |
General provisions |
§ 88. |
Operational and behavioural rules |
§ 89. |
Security measures |
§ 90. |
Recording and reporting obligations |
§ 91. |
Changes in the scope of the Regulation |
Part 6 |
|
§ 92. |
Central dose register |
§ 93. |
Central radiation sources-register |
§ 94. |
Central Incident Register |
Part 7 |
|
§ 95. |
Transitional provisions |
§ 96. |
In-force pedals |
Part 1
General provisions
Section 1
Principles, scope of application
Scope
§ 1. (1) This Regulation provides for the protection of the life or health of persons, including their descendants, against damage caused by ionizing radiation in relation to exposure to radiation sources, as well as the handling of such exposures. Radiation sources. Exceptions are those that are included in the Medical Radiation Protection Ordinance, BGBl. II No 409/2004.
(2) It also regulates
1. |
the requirements for radiation protection officers and other persons entrusted with the exercise of radiation protection, |
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2. |
the protection of external workers, |
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3. |
general requirements for the operation of the Central Radiation Protection Register, |
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4. |
Reporting requirements for transboundary movements of radioactive substances. |
(3) The following Directives are transposed into Austrian law by this Regulation:
1. |
Council Directive 96 /29/EURATOM of 13 May 1996 laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation, OJ L 327, 30.12.1996, p. No. OJ L 159/1, 29. 6. 1996, CELEX No 31996L0029, |
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2. |
Council Directive 90 /641/EURATOM of 4 December 1990 on the protection of external workers exposed to exposure to ionizing radiation in use in the field of control, OJ L 136, 30.4.1990, p. No. OJ L 349/21, p. 12. 1990, CELEX No 31990L0641, and |
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3. |
Council Directive 2003 /122/EURATOM of 22 December 2003 on the control of highly radioactive enclosed radiation sources and non-herrenless radiation sources, OJ L 327, 28.12.2003, p. No. L 346/57 of 31 December 2006 12. 2003, CELEX No 32003L0122. |
Justification
§ 2. (1) The expositions of persons according to § 1 (1) must be of sufficient value in total. The total potential of the benefit, including the benefit to the company, shall be weighed against the injury caused by exposure to the individual. Consideration shall be given to the efficacy, benefit and risks of available alternative methods which serve the same purpose, but which are not associated with any or lesser exposure.
(2) In particular, all new categories and types of transition with radiation sources must be justified before they are generally applied. They have to be in line with the state of the art; in addition, existing types of transition must be reviewed as soon as new important findings on their effectiveness or consequences are obtained.
(3) It is also necessary, in particular in the context of authorisations for types of construction, to consider whether the use of radioactive substances, in particular those used in consumer goods and mass products, is not intended to be used in accordance with the intended purpose of can be excluded from adequate security and continuous monitoring of radioactive substances is ensured up to and including safe disposal.
(4) Where a method of handling is not generally justified, a specific case may nevertheless be justified on a case-by-case basis, in particular circumstances to be assessed on a case-by-case basis.
(5) It is not permissible for a type of change to be justified.
Tuning
§ 3. (1) When dealing with radiation sources, the exposure of individual persons and the general population as a whole shall be kept as low as possible and justifiable according to the state of the art taking into account economic and social factors. is.
(2) Within the dose limits according to § § 12 to 14, the competent authority may set dose limits for certain activities in order to optimise radiation protection.
(3) Where it is necessary for reasons of radiation protection, the competent authority may, in compliance with due diligence, also prescribe measures beyond the provisions of this Regulation, provided that it is objectively justified; are appropriate and suitable.
(4) The Authority may authorise other arrangements or derogations from the provisions of this Regulation other than those prescribed by this Regulation, provided that the radiation protection is taken into account to the same extent.
(5) The optimization process includes the selection of the technical equipment and, if appropriate, the selection of technical assistance facilities as well as the establishment of organizational measures to reduce exposure.
Section 2
General radiation protection provisions
Safety analysis, incident analysis, emergency planning
§ 4. (1) The preliminary safety analyses, security analyses, incident analyses and emergency planning as defined in § 36 (1) Z 10, required in accordance with § § 5 (5), 6 (5), 7 (5), 10 (5), 10 (3), 20 (3) and 26b (1) and (2) of the StrSchG Due to the special conditions of the transition with radiation sources, StrSchG must be created by the approval advertiser or can be created by qualified experts.
(2) In the event of changes in the nature of the handling of radiation sources or other changes to the boundary conditions, the said analyses and emergency planning shall be adapted accordingly.
(3) The essential contents of these analyses and contingency planning shall be included in the submissions in accordance with § 16. These copies shall also be handed out on request to competent relief and rescue organisations.
Quality assurance, quality control
§ 5. (1) The holder of the authorization shall, taking into account the safety analysis by means of quality assurance programmes, ensure that installations and equipment are properly operated. In particular,
1. |
to prepare written instructions for periodic reviews of safety-relevant facilities; and |
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2. |
carry out regular checks on the state of radioactive substances and their safe custody or have them carried out. |
(2) Quality assurance programmes shall, at most, also have potential exposures, in particular in the application of radiological or radioactive substances in the non-medical field, when used outside of radiation applications. consideration.
(3) The holder of the authorization shall ensure the orderly retention of the records of measures taken in relation to quality control. Records shall be kept for the entire service life of a device, equipment or plant and for 7 years beyond the end of the service life.
Section 3
Exemptions from the obligation to notify and to notify, type approvals
Derogations from the obligation to grant authorisation
§ 6. (1) According to § 13 of the German StrSchG (StrSchG), the obligation to make permits in accordance with § § 7 or 10 StrSchG shall be exempted:
1. |
the handling of radioactive substances, the activity of which is subject to the free limits referred to in Appendix 1 Table 1, column 2, does not exceed: |
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2. |
the handling of radioactive substances, the specific activity of which does not exceed the free limits laid down in Annex 1, Table 1, column 3; |
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3. |
the handling of radioactive substances not listed in Appendix 1 with a half-life of up to 1 hour, the activity of which is the free limit of 5-10 6 Do not exceed Becquerel; |
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4. |
the handling of radioactive substances not listed in Appendix 1, having a half-life of more than 1 hour, the activity of which |
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a) |
in the case of radionuclides with a core charge number of 1 to 81, the free limit of 5-10 4 Becquerel or |
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b) |
in the case of radionuclides with a core charge number above 81, the free limit of 5-10 3 Do not exceed Becquerel; |
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5. |
the handling of a number of radioactive substances if the sum of the quotients of the activity or the specific activity of each substance and the corresponding free limit according to Z 1 to Z 4 is less than or equal to 1; |
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6. |
the handling of noble gases obtained from the air, provided that the isotope ratio in the gas corresponds to that in the air; |
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7. |
the handling of radiation sources, if their design is approved in accordance with Section 19 (1) of the German StrSchG (StrSchG) or has been approved in accordance with Section 20 (1) of the StrSchG and has been exempted from an individual authorization pursuant to paragraph 5 of this Regulation; |
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8. |
the operation of radiation facilities, provided that they are not intended to produce ionizing radiation, but where ionizing radiation occurs in a parasitic way when the local dose rate is 0.1 metres away from the source from the touchable surface of the device is not more than 1 microsievert per hour. |
(2) The exceptions referred to in paragraph 1 (1) to (6) shall not apply to:
1. |
the deliberate addition of radioactive substances in the manufacture of medicinal products and not the Food Law-LMG 1975, BGBl. No 86/1975, consumer goods subject to or placing on the market of such products, and |
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2. |
the deliberate administration of radioactive substances to persons and, where the radiation protection is affected by humans, to animals for the purpose of medical or veterinary diagnosis, treatment or research. |
(3) The exceptions referred to in paragraph 1 shall not apply:
1. |
for the disposal of solid, liquid or gaseous waste originating in an activity subject to authorisation in accordance with Articles 6, 7 or 10 of the StrSchG; |
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2. |
for the disposal of equipment containing radioactive substances, even if |
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a) |
in accordance with Section 19 (1) of the StrSchG, or |
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b) |
in accordance with § 20 of the German StrSchG and exempted from an individual authorization pursuant to paragraph 5 of this Regulation |
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Exemptions from reporting requirements
§ 7. (1) According to Article 25 (4) (1) of the German StrSchG, no notification shall be required:
1. |
the handling of radioactive substances, which is exempted from the obligation to comply with the provisions of Section 6; |
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2. |
the handling of equipment containing enclosed radioactive materials and the design of which is authorised in accordance with § 19 of the German StrSchG (StrSchG), unless a notification requirement exists on the basis of the type approval; |
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3. |
the operation |
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a) |
Cathode ray tubes intended for the display of images, or of radiation devices operated at a voltage of not more than 30 kV, if the local dose rate is 0.1 metres from the touchable surface of the Apparatus shall not exceed 1 microsievert per hour, |
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b) |
all other radiation equipment to which this Regulation applies, if its type is approved in accordance with Section 19 of the StrSchG, unless a notification requirement exists on the basis of the type-approval; |
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4. |
Materials released for disposal or further use, such as inactive substances, provided that no further checks have been made by the competent authority. |
(2) The possession of radiation facilities does not require any notification in accordance with § 25 (6) of the StrSchG, if the radiation device is in an inoperative state, which cannot be eliminated without special expertise.
Type approvals
§ 8. (1) In the case of equipment containing radiation sources, the local dose rate at a distance of 0.1 metres from the surface of the device is not, and is not, 1 microsievert per hour when used in accordance with the intended use, provided that it is radioactive material the activity of which is less than 10 times the free limits of Appendix 1, Table 1, column 2, the types of which can be approved in accordance with Section 19 (1) of the StrSchG.
(2) Anyone who places on the market permitted types of equipment containing radioactive substances in accordance with § 19 or § 20 StrSchG shall have the names and addresses of the recipients of such equipment on a quarterly basis as well as the extent of the supplies to the approval authority. report.
(3) Provided that the placing on the market is carried out by intermediaries, the names and addresses of the recipients of such equipment as well as the extent of the supplies to the approval authority shall also be reported on a quarterly basis.
Part 2
Protection of life and health
Section 1
General safeguards
Dose terms
§ 9. In the provisions of this Regulation, the term dose refers to equivalent doses. Radiative and tissue weighting factors are the Appendix 2 See. The effective dose is the sum of those according to Appendix 2 lit. D weighted mean equivalent doses in the individual organs and tissues.
Dose by ionizing radiation
§ 10 (1) When determining the dose, consideration should be given to exposure to radiation from the outside and to the inclusion of radioactive substances. Exposures which are not from a work or a handling of radiation sources within the meaning of § 2 (1) and (2) (1) respectively. 45 StrSchG may be disregarded in the determination of the dose. In particular, these are expositions within the framework of
1. |
an own medical examination or treatment, |
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2. |
a knowingly and willful assistance, which must not, however, be part of an occupation, in the support and care of patients undergoing medical examination or treatment, or |
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3. |
participation in a medical or biomedical research programme. |
(2) The competent authority may, in the event of a subliminal measurement or reasonable doubt as to the accuracy of the measurement, establish a replacement dose to be identified as such in the records to be recorded. The Authority shall inform the Central Dose Register pursuant to § 35a StrSchG as well as the dose measuring point of such a determination.
Categories of professionally radiated persons
§ 11. (1) For control and surveillance purposes, a distinction is made between two categories of persons exposed to radiation:
1. |
Category A: persons exposed to radiation who, in the course of their professional activities, may be exposed for a period of 12 consecutive months to an exposure at which an effective dose of 6 millisievert or one an equivalent dose of 45 millisievert for the eye lens or an equivalent dose of 150 millisievert for the skin or the hands, forearms, feet and ankles can be exceeded; |
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2. |
Category B: professionally exposed persons who, in the course of their professional activities, may be exposed for a period of 12 consecutive months to an exposure at which an effective dose of 1 millisievert or one An equivalent dose of 15 millisievert for the eye lens or an equivalent dose of 50 millisievert for the skin or hands, forearms, feet and ankles, but not the dose levels of Z 1 can be exceeded. |
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The dose equivalent for the skin shall be independent of the exposed area for the median dose on each surface of 1 cm 2 . |
(2) The classification of persons exposed to occupational exposure to categories A or B shall be classified by the competent authority in the context of the authorization procedure or in the case of an upright radiation protection authorisation within the framework of the next Review according to § 17 StrSchG on the basis of the local situation and the activities to be carried out. The documents required for the classification, in particular with regard to the respective local exposure to radiation and the need to stay in such places for occupationally exposed persons, shall be submitted by the holder of the authorization to: To be made available.
(3) Persons exposed to radiation in category B, where physical control according to § § 25, 26 and 29 has shown that the values laid down in paragraph 1 (1) (1) have been exceeded, may in future only be considered as professional in the field of radiation radiation exposed persons of category A, provided that an examination in accordance with § 32 results in their health suitability.
Maximum authorised dose for persons exposed to radiation
§ 12. (1) Insofar as § 13 does not determine something else, the effective dose in the case of persons exposed to radiation may not, as a rule, exceed 20 millisievert for a period of 12 consecutive months.
(2) In justified exceptional cases, an effective dose of 50 millisievert shall be allowed in individual years for professionally radiated persons in category A, provided that in 60 consecutive months an effective dose of 100 millisieverts is permitted. Millisievert is not exceeded.
(3) Without prejudice to para. 1 and 2, the equivalent dose may be administered over a period of 12 consecutive months.
1. |
for the eye lens 150 millisievert; |
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2. |
for the skin or the hands, forearms, feet and ankles 500 millisievert |
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, the limit value for the skin, irrespective of the exposed surface area, for the median dose on each surface of 1 cm 2 shall apply. |
(4) For women of childbearing potential, the cumulative dose of the uterus should not exceed 2 millisievert over a month.
Expositions particularly approved
§ 13. (1) In exceptional circumstances, with the exception of radiological emergencies, which are to be assessed on a case-by-case basis, the competent authority may, where necessary to carry out specific work operations, individual -willing to grant occupational exposure to certain workers who exceed the dose limits laid down in § 12. The prerequisite for this is that these exposures are limited in time and limited to certain areas of work and are within the exposure limits set by the competent authorities for this particular case. The following conditions shall be taken into account:
1. |
Only professionally exposed persons of category A, who have been shown to have voluntarily declared themselves ready to carry out these works, may be subject to particularly authorised exposure to radiation; |
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2. |
the holder of the authorization shall carefully identify the exposures to be expected, carefully justify these exposures in advance and in detail with the workers voluntarily working, their representatives, the authorised doctor and the to discuss radiation protection officers; |
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3. |
the workers concerned must be adequately informed in advance of the risks associated with such exposure and shall be informed of the precautions to be taken during these operations; the holder of the authorization shall be entitled to: convinced that the persons concerned have understood the information and teachings; |
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4. |
all exposures associated with specially approved exposures shall be entered separately in the special records referred to in § 31. |
(2) Expositions as referred to in paragraph 1 shall be excluded:
1. |
Apprentices and students in the course of their training; |
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2. |
Women of childbearing age; |
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3. |
persons who have received an effective single dose of more than 10 millisievert in the previous 12 months; |
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4. |
Persons who have already received an infested or emergency effective dose of more than 100 millisieverts. |
(3) The exceedance of dose limit values in accordance with § 12 within the framework of particularly bewildered exposures alone is not sufficient justification to exclude the worker without her consent from her normal employment or to exclude her from a to other places of work.
Maximum authorised dose for individuals of the population
§ 14. (1) For individuals of the population, the limit value of the effective dose is 1 millisievert per year. The competent authority may, in special circumstances, allow a higher effective dose per year, provided that the average over five consecutive years does not exceed 1 millisievert per year.
(2) Without prejudice to paragraph 1, for individuals of the population, the limit of dose equivalent for the eye lens shall be 15 millisieverts per year; the limit of the dose equivalent for the skin 50 millisieverts per year averaged over any given Skin area of 1 cm 2 , regardless of the exposed surface.
Responsibility of the holder of the authorization
§ 15. (1) In accordance with Section 3 (2) of the StrSchG, the holder of the authorization-with regard to Z 1 as well as the authorization-holder-shall be responsible for carrying out the necessary radiation protection measures, which include in particular:
1. |
the prior critical examination of planning for installations from the point of view of radiation protection; |
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2. |
the establishment of the necessary technical and other measures for the protection of radiation for the individual operations and the monitoring of their compliance with the necessary extent; |
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3. |
the preparation of working instructions within the meaning of section 16 (3); |
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4. |
the instruction of persons working in radiation areas and the management of records of such training; |
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5. |
-the training of other persons entering radiation areas on a case-by-case basis; |
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6. |
care for the facilities, equipment and equipment intended for radiation protection, including the regular verification of their functioning and the correct use, as well as the regular calibration or calibration of the measuring instruments; |
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7. |
the arrangement that it shall be notified without delay of any significant incident relating to radiation protection and any deficiencies affecting radiation protection. |
(2) The holder of the authorization shall assist the radiation protection officer in all questions relating to radiation protection and may entrure him with the tasks referred to in paragraph 1. In any case, this assignment must be carried out if the holder of the authorization does not himself have the training required in accordance with § § 41 to 43. The responsibility of the radiation protection officer and, if applicable, the other persons responsible for the exercise of radiation protection shall be regulated in writing by the holder of the authorization.
(3) An assignment in accordance with paragraph 2 of this article shall lead to administrative criminal responsibility of the authorized person for compliance with the radiation protection regulations only under the conditions and under the conditions laid down in § 9 of the Administrative Code Act 1991. BGBl. No 52/1991.
Radiation protection teachings and work instructions
§ 16. (1) The training of persons working in radiation areas, to be carried out in accordance with Article 29 of the StrSchG, shall be subject to the necessary extent, in particular prior to the commence of their activities, and shall continue to be carried out at regular intervals and on a given occasion, such as: Incidents or accidents, but at least once a year. The instruction has
1. |
the general procedures in the field of radiation protection and the precautions to be taken, in particular those relating to the operating and working conditions in question, taking account both of the activities carried out in the General as well as any type of workplace or activity which is that can be assigned to the people who have been instructed, |
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2. |
the essential contents of safety and incident analyses and emergency planning, |
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3. |
the health risks associated with the activity concerned; |
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4. |
the importance of compliance with the technical and organisational requirements, |
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5. |
in the case of female workers, the need for early notification of pregnancy with regard to the risks of exposure to the unborn child and the risks of contamination of the infant in the case of a radioactive Contamination of breastfeeding |
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shall be included. |
(2) The content and the date of the submissions referred to in paragraph 1 shall be kept in keeping with records which are to be underwritten by both the person under the record and the person who has been instructed to do so. The records shall be kept for at least seven years for inspection by the competent authority.
(3) The holder of the authorization shall draw up written work instructions, which shall also take into account the essential contents of the instructions, and demonstrably hand over the persons concerned. Written work instructions are generally to be written in German. In the case of persons who are not or only to an insufficient extent the German language, the written work instructions must also be written in their mother tongue or in another language sufficient to provide sufficient information to the person who is not in writing. is well-ruled. In any case, the holder of the authorization or a person expressly instructed by him in writing shall convince himself that the instructions for the work have also been understood.
Section 2
Radiation areas
Radiation area, control and monitoring area
§ 17. (1) An area in which persons may receive an effective dose of more than 1 millisievert per year or more than one tenth of the dose equivalent to the ophthalmic lens, skin or extremities permitted under section 12 (3) shall be considered to be: Radiation area.
(2) The part of a radiation area in which persons in the performance of their professional activity or in the course of their training have an effective dose of more than 6 millisieverts per year or more than three tenths of the allowable dose of The equivalent dose for the eye lens, the skin or the extremities can be obtained as a control area.
(3) The part of a radiation area in which persons, in the course of their professional activity or in the course of their training, have an effective dose of more than 1 millisievert per year or more than one tenth of the permitted levels in accordance with Article 12 (3). The equivalent dose for the eye lens, the skin or the extremities, but not more than the doses referred to in paragraph 2, shall be considered as a monitoring area.
(4) Areas in which only radiation facilities are operated shall not be considered to be radiation areas when the radiation facilities are switched off, provided that technical and organisational measures ensure that the radiation facilities are not The operating state of the radiation device can be clearly identified by optical or acoustic displays and an unintended commissioning is to be ruled out. This regulation does not apply to radiation facilities where activation products can be produced on the basis of the acceleration energy.
Requirements for control and surveillance areas
§ 18. (1) The following requirements shall apply to the control sector:
1. |
The control area shall be demarcted and, as such, shall be marked with the radiation warning sign and the further information referred to in Appendix 3 shall be identified. |
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2. |
Access shall be restricted to persons who have received the appropriate instructions. Access controls shall be carried out in accordance with the procedures laid down by the holder of the authorization. In order to avoid the spread of radioactive contamination, it is necessary to provide for metrological facilities in the access and disposal of persons and goods. |
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3. |
With regard to the sources of radiation and the activities relating to them, the radiation risks must be in the form of written work instructions within the meaning of section 16 (3). |
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4. |
The jobs are to be monitored in accordance with § 29. |
(2) The following requirements shall apply to the monitoring area:
1. |
The jobs are to be monitored in accordance with § 29. |
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2. |
To the extent that this is necessary for reasons of radiation protection, the provisions of paragraph 1 (1) (1) and (3) shall also apply. |
(3) The limits of the control area and of the monitoring area shall be determined by the authorization authority within the framework of the authorization procedure. In the case of variable sources of radiation, the holder of the authorization shall ensure that the limits of the control and surveillance area laid down in the authorization procedure are respected and that the measures required pursuant to paragraphs 1 and 2 of this Article shall be taken into account. is complied with.
Temporary abolition of radiation areas
§ 19. (1) Control and surveillance areas or parts of such areas may be temporarily lifted by the holder of the authorization in order to allow foreign workers to carry out unauthorised activities or non-business persons access to: provided that the dose rate in these areas does not exceed 0.5 microsievert per hour and any radioactive contamination of accessible or touchable surfaces does not exceed the values set out in Table 1, column 5 of Annex 1.
(2) The temporary lifting of a radiation area or parts thereof is permissible on compliance with all the following conditions:
1. |
Compliance with the values referred to in paragraph 1 shall be carried out before the repeal by means of measurements; |
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2. |
the lifting of the radiation areas and the measurements carried out for this purpose shall be documented by the holder of the authorization and shall be brought to the attention of the Authority at the request of the Authority; |
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3. |
the external workers or non-working persons have been shown to be in the management of the radiation protection in the holding in question and to inform them that they have been temporarily lifted up the radiation area; |
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4. |
at least one of the persons who are to be admitted must be equipped with a person dosemeter with which the dose can be immediately determined after leaving the radiation area; |
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5. |
the records kept are to be kept for at least 7 years. |
Access for visitors and persons responsible for non-authorisation activities
§ 20. (1) The holder of the authorization of a holding may allow visitors as well as persons to carry out unauthorised activities for the short-term access to a radiation area which cannot be temporarily lifted in accordance with § 19, provided that: is ensured that the effective dose during the visit does not exceed 10 microsievert.
(2) In the event of access by visitors or persons for the execution of activities not subject to authorisation in a radiation area, the following requirements shall be ensured:
1. |
the persons who have been admitted must be shown to be in the conduct of radiation protection in the holding in question and to be informed of the fact that they are entering a radiation area; |
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2. |
they shall be accompanied throughout their stay by the holder of the authorization or any other competent person to be determined by the holder of the authorization; |
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3. |
at least one of the persons who are to be admitted must be equipped with a person dosemeter with which the dose can be immediately determined after leaving the radiation area; |
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4. |
the results of the measurement shall be documented by the holder of the authorization and shall be brought to the attention of the Authority at the request of the Authority; |
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5. |
the records kept are to be kept for at least 7 years. |
Access to official bodies and qualified experts
§ 21. (1) Public authorities and qualified experts in public authority shall be regarded as persons exposed to radiation and shall be subject to physical control, provided that they are carried out in the performance of their duties by staying in radiation areas may be exposed to exposure at which the maximum permissible dose levels for individuals of the population can be exceeded in accordance with § 14. If the dose values laid down in § 11 (1) (1) (1) can be exceeded, they shall also be subject to medical supervision.
(2) If there are no grounds for this, the persons referred to in paragraph 1 shall be accompanied by the holder of the authorization or any other competent person to be determined by him during the entire period of their stay in the radiation area.
(3) Persons in accordance with paragraph 1 shall immediately determine, record and store the dose in their activities by means of a further dosimeter after leaving the respective radiation area, until the evaluation of the person assigned to the person concerned has been assigned. There is a person dosimeter.
Radiation applications
§ 22. (1) Radiation application spaces shall be enclosed spaces and shall be marked by the radiation warning sign in accordance with Appendix 3, with the words "CAUTION RADIATION".
(2) The operation of the radiation sources and the shielding must be coordinated with each other in such a way that in the vicinity of the radiation application space the in Appendix 4 do not exceed the local dose level.
(3) Radiation applications for non-medical applications shall be subject to the following requirements:
1. |
The switch position or The control device for the radiation source must be located in a secondary space to the radiation application space. |
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2. |
The operation of the device and, if it can be switched separately, the beam exit must in each case be indicated by a clearly perceptible, optical or acoustic signal in the radiation application space itself, at the access points to this and at the switching station. . |
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3. |
In the case of the operation of radiation devices, the opening of the doors to the radiation application space must result in an interruption of the beam exit, whereby the reconnection of the installation must not be possible merely by closing the doors. In the operation of installations with enclosed radioactive substances which have a radiation exit window, the opening of the doors to the radiation application space must result in an automatic closing of the radiation exit window. In the case of installations which do not have such a device, the radiation application space must be provided with an access securing device which prevents unintentional entering. The radiation application space must be able to be abandoned at any time. Taking into account the size of the radiation application space, the clarity of the radiation application area and the radiation intensities to be applied, the Authority shall have the number of emergency switches required for interrupting the operation. the radiation exit, or To prescribe the closing of the radiation exit window. |
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4. |
In the case of radiation devices, the determination of the necessary protective layers should be based on the maximum weekly operating load and, in the case of X-ray devices, the nominal voltage. |
(4) In the case of radiation applications in which particle accelerators are operated, a corresponding protection must in particular be used against
1. |
X-rays, as well as the scattered radiation generated by the X-rays and the X-rays emitted from the accelerators ' shields, |
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2. |
direct electron beams and the photon radiation emitted from the impinsion points of the same, |
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3. |
x-ray braking generated by the braking of electron beams, |
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4. |
Neutron radiation and other operating-related particle radiation as well as neutron capture gamma radiation and |
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5. |
Activation products |
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shall be guaranteed. |
Personal protective equipment
§ 23. (1) For the protection of persons exposed to radiation, personal protective equipment must be kept in stock in the extent necessary for radiation protection. It must comply with the requirements of the PSA safety ordinance, BGBl. No 596/1994, in the current version. Radiation protection clothing and accessories for the reduction of radiation exposure must have a permanent marking with a lead equivalent.
(2) The protective equipment shall be kept ready for use in the proper condition. It shall be used by the persons concerned.
Radioactivity monitoring of the environment
§ 24. The competent authority may, taking into account the extent and nature of the handling of radioactive substances or the occurrence of radioactive substances produced by activation processes, in accordance with the possible exposure to radiation outside of Areas of radiation shall oblige the holder of the authorization to carry out contamination or local dose performance measurements to the extent necessary, in particular with regard to air, water and soil, in such a way as to determine the extent to which they are to be measured, what cases are reported to be reported.
(2) The results of the measurements referred to in paragraph 1 shall be kept by the holder of the authorization to keep those records for 30 years and, at the request of the competent authority, to the authority appointed for the purposes of the protection of workers and to the competent authority, and the competent institution of the accident insurance and the records of the authority responsible for the large-scale surveillance of the air, water and soil in accordance with Section 37 (1) of the StrSchG, or of any of the above-mentioned documents Location to be transmitted. In the event of the dissolution of a holding, such records shall be submitted to the competent authority or to a body designated by that authority.
Section 3
Physical control
Personal dosimetry
§ 25. (1) The external exposure resulting from the transition to radiation sources shall be determined in the case of persons exposed to radiation at persons dosemeters. For this purpose, during the activity in the radiation region, a dosimeter is always to be carried at a point on the body stem which is representative of the radiation exposure, usually at the front of the trunk. If this type of exposure cannot be sufficiently accurately determined, additional dosimeters shall be used. This shall apply in particular where:
1. |
the types of radiation or radiation energy are so different that exposure to a single dosemeter cannot be determined sufficiently accurately; or |
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2. |
different body points are given very different doses; or |
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3. |
the scope of a dosemeter is limited in such a way as to ensure that the person dose determined does not correspond to the full dose of person received; or |
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4. |
very different radiation incidence directions are available. |
(2) Provided that other methods allow a reliable determination of the individual dose and due to the particular circumstances of the workplace conclusions on a radiation-friendly behaviour of those working at this workplace are not possible , the Authority may allow exemptions from surveillance with personal dosemeters for persons exposed to occupational exposure to category B.
(3) For the individual measurements referred to in paragraph 1, dosimeters shall be used, the indication of which shall not be without damage or damage. cannot be deleted without special aids. These dosimeters shall be obtained from a dose-measuring point authorised for this purpose in accordance with Section 34 of the StrSchG and shall be exchanged at regular intervals, which shall normally be a calendar month, and shall be immediately available to this dose-measuring point for the purpose of: Evaluation to be transmitted.
(4) In so far as it is necessary for reasons of radiation protection or the securing of evidence, other persons who are only temporarily or temporarily in radiation areas shall also be equipped with personal dosemeters.
(5) In special cases, in particular where, for reasons of radiation protection, more detailed knowledge of the dose contributions by individual operations is required, the measurements referred to in paragraph 1 shall be based on two independent procedures shall be made. One measurement shall be carried out in accordance with the procedure referred to in paragraph 3, and the other measurement shall allow the determination of the person dose received at any time.
(6) To the extent that it requires the type of activity, dosimeters shall be used which emit an audible or visual warning signal (warning dosimeters) when the dose or dose rate values are exceeded.
(7) If a dosimeter in accordance with paragraph 1 cannot be evaluated as a result of loss or damage, the authorized dose-measuring point for the period in question shall be set off against aliquot shares of the maximum annual dose permissible under section 12 (1), unless plausible and comprehensible information can be provided to enable the dose to be determined. If there is a reasonable suspicion that the non-evaluability of the dosimeter has been deliberately brought about, the dose measuring point shall immediately notify the competent authority in order to be able to take these measures within the meaning of section 10 (2).
(8) The authorised dose-measuring points shall be submitted by the holder of the authorization in accordance with Appendix 5 lit. A to be made available. In the event of an accident-related exposures or emergency exposure, the holder of the authorization shall also provide all the necessary information for the dose determination.
(9) The holder of the authorization shall immediately inform the radiation protection officer and the professionally exposed persons of the results of the measurement of personal dose in accordance with paragraphs 1, 4 and 5. If occupational health care is established in accordance with the provisions on the protection of workers in the workplace, access to the results of the measurement of personal dose is also to be granted on request to the competent occupational health worker. If deviations from the results can be detected, in particular increased exposure values compared to the long-term average, the reasons for these deviations shall be determined without delay and measures for the optimization of the Radiation protection. The exceeding of the maximum permissible doses in accordance with § 12 shall be notified immediately by the holder of the authorization to the competent authority.
Incorporation monitoring
§ 26. (1) If a professionally exposed person is engaged in the course of their work activities with open radioactive substances, routine incorporation monitoring shall be carried out if the effective follow-up dose is due to the inclusion of such substances in this way. may exceed the limit value for individuals of the population in accordance with Section 14 (1).
(2) The import surveillance shall be carried out by the holder of the authorization if the relevant requirement in accordance with Appendix 5 lit. E is determined. The incorporation monitoring shall be carried out by an authorized dose measurement point in accordance with § 34 StrSchG. The determination of doses due to the inclusion of radioactive substances has been carried out in accordance with the Appendix 6 shall be carried out.
(3) Where it is necessary for reasons of radiation protection or the protection of evidence, the competent authority may, in consultation with a authorised dose-measuring point to be appointed by the holder, the holder of the authorization and the use of Measuring devices for the measurement of the activity for the monitoring of the inside of the occupationally exposed persons of one's own plant. In the case of measurement use, calibration and evaluation, the operational measuring activity for the surveillance of the ink is to be monitored and monitored by the authorized dose measuring point designated by the holder of the authorization on the basis of a contractual agreement. control. The metrological control of the measuring equipment in accordance with the provisions of the measure and calibration law, BGBl. No 152/1950, remains unaffected by this.
(4) The type of incorporation measurements depends on the type of radioactive substances used to circumvent the occupationally exposed persons, and according to the metrological requirements for the identification of incorporated activities. The monitoring interval depends on the physical half-life time and the biological behavior of a radionuclide. The type of the incorporation measurement and the monitoring interval are in each case prescribed by the exporting authorized dose measuring point according to the state of the art.
(5) If incorporated radioactive substances are detected in the case of incorporation measurements, the following dose shall be determined according to the state of the art from the authorized dose measurement site. If a measurement is not sufficient for the determination of the subsequent dose or if a subsequent dose is to be assumed which is higher than the limit value for an individual of the population in accordance with Section 14 (1), additional incorporation measurements shall be carried out.
(6) If, as a result of an incident, an incorporation is to be assumed in the case of a professionally exposed person, an incorporation measurement of special occasion and a follow-up dose estimation shall be carried out without delay.
(7) The authorised dose measurement points shall be the data referred to in Appendix 5 lit by the holder of the authorization. A and D shall be made available.
(8) The holder of the authorization shall immediately inform the radiation protection officer and the professionally exposed persons of the results of the inspection of the inspection. If occupational health care is established in accordance with the provisions on the protection of workers in the workplace, access to the results of the surveillance of the incorporation must also be granted on request to the responsible occupational health worker. If deviations from the results can be detected, in particular increased exposure values compared to the long-term average, the reasons for these deviations shall be determined without delay and measures for the optimization of the Radiation protection. The exceeding of the maximum permissible doses in accordance with § 12 shall be notified immediately to the competent authority.
Evaluation of dosimetric measurements
§ 27. (1) The evaluation of personal dosimetry according to § 25 (1) and (2) as well as the in-corporal supervision pursuant to § 26 (1) may only be carried out by an authorized dose measurement point according to § 34 StrSchG.
(2) The dose-measuring point shall carry out the determination of the exposure in accordance with § 25 on the basis of the operational parameters listed in Appendix 2 and in accordance with § 26 according to the state of the art. The evaluations have the following appendix 5 lit. B required data to be included.
(3) The results according to § 25 (1) and § 26 (1), (5) and (6) shall be transmitted to the holder of the authorization and to the central dose register until at least 6 weeks after the end of the respective measurement period. Specified replacement doses pursuant to section 25 (7) shall be specifically marked.
(4) In order to calculate an overall exposure (external and internal exposure), an effective follow-up dose determined in accordance with section 26 is always attributed to the year of the incorporation. However, in the case of effective secondary doses close to the limit value in accordance with Section 12 (1), the Authority may allow the respective exposure of each subsequent year to be determined and credited to the corresponding year.
(5) If, on the basis of the evaluation of the dosimetry of persons, there is a suspicion of exceeding the maximum permissible doses in accordance with § 12, the dose measuring point shall immediately inform the holder of the authorization as well as the central dose register.
Determination of the effective dose and the dose of equivalents
§ 28. (1) The evaluation of the personal dose measurements in accordance with § 25 states that in the monitoring period a person dose of 5 millisievert for the whole body, of 15 millisieverts for the eye lens and 50 millisieverts for the skin or the hands, forearms, When feet and ankles have not been exceeded, the measured values of the person dose shall be considered as effective dose or dose. as an equivalent dose.
(2) If the dose values referred to in paragraph 1 above have been exceeded, the holder of the authorization shall make a review to determine whether:
1. |
there are no misindication (e.g. by dosimeter failure) or non-intended use (e.g. dosimeter not worn on the body), and |
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2. |
, taking into account the exposure conditions and the location of the dosimeter, it may be estimated that the actual dose is no greater than the dose of personal dose. |
(3) Meeting the conditions set out in paragraph 2 above, the determined values of the person dose shall be deemed to be effective dose, or as an equivalent dose.
If at least one of the conditions referred to in paragraph 2 does not apply, the holder of the authorization shall immediately arrange for the determination of the exposure according to the state of the art, taking into account the conditions of exposure. Such an investigation shall also be carried out in any case if, on the basis of the measured values, there is a suspicion of exceeding the maximum permissible doses in accordance with § 12. The competent authority may, in justified cases, order such a determination of exposure.
(5) The holder of the authorization shall have the Central Dose Register and the relevant dose measurement point from the outcome of the review as referred to in paragraph 2 and/or the exposure assessment referred to in paragraph 4 shall be immediately informed of the existence of the existence of the exposition.
Monitoring of jobs
§ 29. (1) In radiation areas, the local dose rate or local dose is to be measured in so far as it is necessary for the determination of the radiation exposure.
(2) In radiation areas in which open radioactive substances are handled, it is necessary to determine, at least daily after completion of the work, whether contamination has been caused. In the case of activities in which the air can be contaminated in the working spaces by radioactive gases, vapours or dusts, it is also necessary to check for contamination in the extent necessary for the determination of the exposure to radiation.
(3) The date and the result of the measurements and findings referred to in paragraphs 1 and 2 shall be recorded and shall be kept for at least 7 years.
Meters
§ 30. The radiation measuring instruments used to carry out the physical control in accordance with § § 25, 26 and 29 must be suitable for the purpose of measurement and must always be in a functional state.
Records
§ 31. (1) The results of the personal dosimetry and the surveillance of the records in accordance with § § 25 and 26 shall be subject to records by the holder of the authorization. After 1. Jänner 2009 shall be kept for at least 7 years. In the meantime, the records shall be kept until the person concerned is 75. It should have been completed or completed, but at least 30 years after the termination of the activity associated with exposure to radiation. On request, they shall be required to submit to the competent authority, the authority appointed for the purposes of the protection of workers and the competent institution of the accident insurance; the persons being monitored shall be included in these records. .
(2) In the records referred to in paragraph 1, accident-related and emergency-related and specially approved exposures shall be listed separately. In addition, in the event of an accident or emergency and in the case of specially approved exposures, the circumstances and the measures taken shall be recorded.
(3) If a person exposed to an occupational exposure is out of a holding, the holder of the authorization shall, on request, have a statement of the doses received. If these records are no longer complete in the case of the holder of the authorization, they shall be requested by the Central Dose Register.
Section 4
Medical examinations
Aptitude investigation
§ 32. (1) For persons of category A exposed to radiation, their health suitability must be determined by a medical examination in advance. In the sense of Section 30 (2) of the StrSchG, the testimony of the result of the investigation may not be older than two months at the time the activity was taken. All relevant information, including workplace conditions, shall be made available to the authorised medical practitioner responsible for the investigation. The medical examination shall include:
1. |
Family and home-based history; |
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2. |
professional history on the basis of actual work processes and conditions; |
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3. |
a general clinical examination, in the case of possible contact with open radioactive substances, with particular attention to the skin; |
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4. |
Laboratory tests: differential blood count and thrombocytes, urinstatus. |
(2) If the nature of the activity, the result of the history, the outcome of the clinical examination or any other examination results require, further partial investigations should be carried out.
(3) In the event of an earlier transition with open radioactive substances, there is the possibility of an even demonstrable inclusion of such substances, the control measures necessary to establish such an incorporation, such as: To arrange whole body measurements, organ measurements or excretion analyses. These control measures shall be carried out in accordance with Article 26.
Control investigation
§ 33. (1) The health status of persons of category A who are exposed to radiation shall be periodically monitored by medical examinations. These control studies shall include:
1. |
interim anamnesis on the basis of the actual work processes and conditions; |
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2. |
a general clinical examination, in the case of possible contact with open radioactive substances, with particular attention to the skin; |
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3. |
Assessment of the results of physical control; |
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4. |
Laboratory tests: differential blood count and thrombocytes, urinstatus. |
(2) With regard to any further partial investigations which may be necessary, Section 32 (2) shall apply.
(3) The control tests shall be carried out in the case of persons exposed to occupational exposure to category A at intervals of one year. In accordance with the requirements of radiation protection, the competent authority may order shorter distances. Within these intervals further investigations should be carried out on a case-by-case basis, if this is necessary because of the result of the previous examination or after a disease for the determination of the further health suitability.
Immediate investigation
§ 34. (1) Where a person has suffered impairment of health as a result of exposure to radiation, the medical examination must be carried out without delay. In any case, an investigation shall be made if the person has received a single dose greater than the maximum permissible dose per year for persons exposed to radiation in accordance with section 12 (2) or (3). The reporting requirements according to § 31 StrSchG are to be perceived.
(2) The medical examinations shall be carried out in accordance with § 33 (1) and (2). If necessary, the authorised doctor shall have the state of the scientific knowledge necessary to carry out such examination procedures, such as, for example, the measurement of the size of the incorporation or biological dosimetry.
(3) The person authorised by the authorised doctor as a result of this medical examination as regards any radiation damage which has occurred and the suitability for employment as a person exposed to radiation health assessment shall be communicated by the holder of the authorization to the competent authority.
(4) If necessary, the authorised medical practitioner shall arrange for appropriate treatment or post-examination.
Final investigation
§ 35. (1) Any person exposed to occupational exposure to category A, whose activity as such person ends or whose employment ends, shall be subject to a medical examination (final examination); the approved physician shall also be responsible for: to determine the extent to which further medical check-ups are necessary.
(2) With regard to the scope of the final examination, the principles of investigation shall be applied in accordance with § 33 (1) and (2).
(3) For persons exposed to radiation,
1. |
whose effective dose did not exceed 2 millisievert in the last year, or |
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2. |
the employment relationship of which ends without the fact that their property is terminated as a person exposed to radiation, |
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an aptitude or control investigation, not exceeding 12 months, shall be considered to be an end-examination in accordance with paragraph 1. |
Medical certificate
§ 36. (1) On the basis of the result of a medical examination in accordance with § § 32 to 34, the authorised physician must carry out a health assessment and be able to record it in a medical certificate. In this case, it should be noted whether the person under investigation is suitable for health reasons, is suitable or unsuitable for the intended activity, and where appropriate, time-specific or activity-specific restrictions are to be pronounced.
(2) On the basis of the result of a medical examination in accordance with § 35, the authorised physician must make a health assessment and, in a medical certificate, to determine whether a radiation damage has been detected in the person under examination. and whether a follow-up examination is required.
(3) The authorized physician must submit the medical certificate in accordance with paragraph 1 or 2 of the authorization holder to the holder of the authorization. This person has to hand over a copy of this certificate to the person under investigation. At the request of the person under examination, the authorised physician shall explain the medical data collected and the result of the medical examination.
(4) If the person under investigation or the official doctor does not consider the health assessment established pursuant to para. 1 and 2 to be incorrect, they may request a decision of the competent authority. The Authority shall have at least two medical experts to hear in this procedure.
Authorised Doctors
§ 37. (1) The medical examinations according to § § 32 to 35 and the issuing of certificates pursuant to § 36 are to be carried out by the doctors, occupational health services or hospitals authorized pursuant to § 35 para. 1 of the StrSchG. The doctors carrying out the examinations have the successful completion of a special training and periodic training in accordance with Section 35 (1) of the StrSchG in accordance with Article 35 (1) of the StrSchG (German StrSchG). Appendix 7 Proof. The authority may, if the evidence of participation in the training events does not take place or not fully, revoke the authorisation or provide it with appropriate conditions.
(2) The bodies referred to in paragraph 1 must keep accurate records of the medical examinations and the resulting health assessments and must keep them up until the person under investigation is 75. It should have been completed or completed, but at least 30 years after the end of the activity associated with radiation exposure. In the event of a revocation or a deletion of the authorization, such records shall be submitted to the competent authority or to a body designated by that authority.
The records referred to in paragraph 2 shall be submitted to the person concerned, to the competent authority, to the authority responsible for the performance of the protection of workers, and to the competent institution of the accident insurance, on request, the Personal medical data of the medical examinations may only be available to doctors. The health assessments according to § 36 shall also be submitted to the Central Dose Register.
Duties of the holder of the authorization
§ 38. (1) Persons who are responsible for carrying out the medical examinations in accordance with § § 32 (1) and 33 (1) of the StrSchG must keep the medical certificates for at least 7 years. They shall have the certificates at the request of the competent authority, the authority appointed to carry out the protection of workers, the institution of the accident insurance and, where the establishment is in operation, occupational health and safety services in accordance with the Worker protection legislation is to be submitted to the competent occupational health worker.
(2) If a worker is out of his/her employment relationship, he shall, at his request, be followed by copies of his medical certificates. If these records are no longer fully available to the employer, they shall be requested by the Central Dose Register. In the event of an operating closure or in the event of a deletion of all authorisations, the holder of the authorization shall transmit the records to the central dose register.
(3) The holder of the authorization shall ensure that the authorised medical practitioner is informed of the results of the physical check.
(4) If a person can no longer be obliged by the employer for an end or post-examination within the meaning of § 35, the employer shall report this to the competent authority. The Authority shall order this investigation. If an end-or post-examination cannot be carried out, the result of the last aptitude test or inspection shall be considered as a result of the final examination.
Accounting of medical radiation protection investigations
§ 39. (1) The authorized physicians, occupational health services or hospitals have the costs of the medical examinations in accordance with § § 32 to 35, insofar as they have carried out the examinations themselves, using special forms with the Insurance institution shall be paid to the public in accordance with the rates of remuneration in force at this institution; this shall apply in the same way to other doctors, hospitals or medical-diagnostic laboratories with regard to the costs incurred by the institution concerned. carried out by them on behalf of the authorised doctors or hospitals Partial investigations.
(2) The settlement between the insurance institution and the competent institutions of the accident insurance as well as the federal government, represented by the Federal Minister for Agriculture, Forestry, Environment and Water Management, has To be performed in a quarterly manner. In so far as the persons investigated are obliged to bear part of the costs of the medical examinations themselves in accordance with Section 32 (4) of the StrSchG, they shall have the replacement of the part of the costs incurred on them by means of an invitation to the insurance institution. to be paid to the public.
Section 5
Persons responsible for the exercise of radiation protection
Obligations and rights
§ 40. (1) The radiation protection officer shall carry out the tasks assigned to him by the holder of the authorization pursuant to § 15 (2), in which case he shall apply as appropriate for the concrete execution of tasks for which he is to be considered as a person, , in particular, the person responsible for the protection of radiation.
(2) In order to carry out their duties, the necessary time and access to all the necessary information and documents shall be granted to the radiation protection officer and to the other persons responsible for the exercise of radiation protection. Where necessary, a minimum period shall be established by the competent authority.
(3) In operation, safety and occupational health care is established in accordance with the provisions on the protection of workers, the radiation protection officer and the other persons responsible for the exercise of radiation protection shall be responsible for the safety and health of the persons concerned. competent security professionals and occupational health professionals.
Education and training in the medical field
§ 41. (1) The radiation protection officers to be ordered for the handling of radiation sources in human, dental or veterinary medicine, or other persons to be entrusted with the exercise of radiation protection, have to prove that:
1. |
the successful conclusion |
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a) |
a university education in the direction of human, dental or veterinary medicine, or |
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b) |
a training of relevant scientific or technical direction at a university, university of applied sciences or higher vocational education or vocational training; or |
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c) |
training in radiological and technical service in accordance with the Federal Act on the regulation of high-quality medical-technical services (MTD Act), BGBl. No. 460/1992, as last amended by the Federal Law BGBl. I No 70/2005, |
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and |
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2. |
the successful completion of a radiation protection training in accordance with Appendix 8 , provided that the person concerned has not already successfully completed a teaching on the subject areas listed in Annex 8 within the framework of his/her training in accordance with Z 1. |
(2) If the intended activity relates solely to nuclear-medical laboratory methods, proof of successful completion of a training in the medical-technical laboratory service shall be sufficient in accordance with the Federal Act on the Regulation of high-end medical-technical services (MTD), BGBl. No. 460/1992, as last amended by the Federal Law BGBl. I No 70/2005, and a radiation protection training pursuant to Annex 8.
(3) In addition, the Authority may require employment to the extent of up to one year in which sufficient practical experience could be obtained for the activity concerned. Practical experience acquired in the course of training must be taken into consideration.
(4) Radiological protection officers and other persons responsible for the exercise of radiation protection shall have the successful participation in training courses on the subject areas listed in Appendix 8, to the extent of at least 8 hours in At intervals of not more than 5 years, provided that their activity is restricted to the ordination of a physician or dentist established, to the extent of at least 4 hours. If proof of participation in the training events is not or is not completed, the Authority may revoke the recognition or impose conditions on it.
(5) Persons who fulfil the training requirements for radiation protection officers in the field of human or dental medicine may also be assigned to radiation protection officers or other persons responsible for the exercise of radiation protection in the veterinary medicinal products shall be ordered provided that they have the appropriate radiation protection training in accordance with Annex 8 lit. B Z 2 to 4 have successfully completed.
Education and training in the non-medical sector
§ 42. (1) The radiation protection officers to be ordered for the treatment of radiation sources for non-medical purposes have the successful conclusion
1. |
an education of relevant scientific or technical direction at a university, university of applied sciences or higher vocational education and training |
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2. |
a radiation protection training in accordance with Appendix 8, provided that the person concerned has not already successfully completed, in the course of the training referred to in Z 1, a teaching on the areas listed in Annex 8, |
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Proof. |
(2) If the intended activity relates only to non-destructive testing using X-ray equipment or radioactive substances enclosed in radiation applications, it shall be sufficient to provide evidence of at least three-and-a-half-year-olds. Training, as provided for in the technical field, or comparable training and radiation protection training in accordance with Appendix 8.
(3) If the intended activity relates only to measuring devices for thickness, density or weight per unit area, level indicators, fire warning devices, devices for the derivation of static electricity, and the like, the proof of a relevant vocational training as well as radiation protection training according to Appendix 8.
(4) Persons who have an education according to § 41 paragraph 1 Z 1 lit. c) may also be appointed to radiation protection officers in the non-medical field, provided that they have the corresponding radiation protection training according to Appendix 8 lit. C have completed successfully.
(5) If the intended activity relates to the handling of highly radioactive sources within the meaning of Article 64 (1), the competent authority may, taking into account the requirements of radiation protection, prove that a successful To apply for a training in the relevant scientific or technical direction at a university or university of applied sciences.
(6) The persons responsible for the management of radiation sources for non-medical purposes with the exercise of radiation protection shall have the expertise required for the activity in question, as well as a Evidence of radiation protection in accordance with Appendix 8.
(7) In addition, the Authority may require employment to the extent of up to one year in which sufficient practical experience could be acquired for the activity in question. Practical experience acquired in the course of training must be taken into consideration.
(8) Radiological protection officers and other persons responsible for the exercise of radiation protection shall have the successful participation in training courses on the subject areas listed in Appendix 8, to the extent of at least 8 hours in At intervals of not more than 5 years, in the case of an activity referred to in paragraph 3, to the extent of at least 4 hours. If proof of participation in the training events is not or is not completed, the Authority may revoke the recognition or impose conditions on it.
Education and training in the field of research reactors
§ 43. (1) The radiation protection officers to be appointed for the operation of research reactors shall have completed the successful completion of the operation.
1. |
an education of relevant scientific or technical direction at a university or university of applied sciences, and |
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2. |
a radiation protection training in accordance with Appendix 8, provided that the person concerned has not already successfully completed, in the course of the training referred to in Z 1, a teaching on the areas listed in Annex 8, |
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Proof. |
(2) The persons responsible for the operation of research reactors with the exercise of radiation protection shall have the successful conclusion
1. |
an education in the relevant scientific or technical direction at a university or university of applied sciences or at a vocational higher education institution; and |
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2. |
a radiation protection training in accordance with Appendix 8, provided that the person concerned has not already successfully completed, in the course of the training referred to in Z 1, a teaching on the areas listed in Annex 8, |
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Proof. |
(3) If no radiation protection training required under paragraph 1 or 2 is offered in Austria, comparable training courses in other Member States of the European Union may be recognised by the competent authority. However, in such cases, the Authority shall be satisfied that the person concerned has sufficient knowledge of the Austrian radiation protection rules.
(4) In addition, it is necessary to provide evidence of an employment of at least two years in which sufficient practical experience could be obtained for the activity in question.
(5) Radiological protection officers and other persons responsible for the exercise of radiation protection shall have the successful participation in training courses on the subject areas listed in Appendix 8, to the extent of at least 8 hours in at intervals of not more than 5 years. If proof of participation in the training events is not or is not completed, the Authority may revoke the recognition or impose conditions on it.
6.
Protection of external workers, radiation protection passport
Obligations of the holder of an external company's consent
§ 44. The holder of an external undertaking's licence shall be responsible for the compliance with the conditions laid down in the agreement, directly or through contractual arrangements with the holder of the authorization, in the control sector of which external workers are active. Radiation protection measures relating to the external labour force working in this area of control, in particular with a view to ensuring:
1. |
compliance with the general principles of radiation protection, in particular compliance with dose limits in accordance with § § 10 to 12; |
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2. |
the instruction of the external workers on the general principles of radiation protection and the handing over of written work instructions to that effect; |
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3. |
the determination of the suitability for health and the carrying out of physical and medical supervision of the external workers and the fulfilment of the recording requirements in accordance with § § 25 to 39; |
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4. |
the proper management of the radiation protection pass according to § 49. |
Obligations of the holder of the authorization, in whose control area external workers are active
§ 45. (1) The holder of the authorization, in whose control area external workers are active, shall be responsible for the compliance of the external undertaking with the holder of the authorization of the external undertaking, directly or through contractual arrangements. Radiation protection measures arising directly from the nature of the control area, its special risk situations and the specific requirements of the use of external workers. In particular, it has to be satisfied with any external working force working in the control sector that:
1. |
which possesses the health suitability necessary for the activity to be carried out; |
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2. |
which, in addition to a briefing on the general principles of radiation protection, has received a special instruction in respect of the characteristics of the control area and the activity to be carried out, and it shall provide the necessary written information work instructions have been brought to the attention of: |
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3. |
it has the necessary personal protective equipment or has been made available to it; |
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4. |
The general principles of radiation protection, in particular the dose limits according to § § 10 to 12, are complied with. |
(2) The holder of the authorization shall ensure that the exposure of that worker in a manner appropriate to the nature of the activity is clearly monitored individually and clearly for the duration of the activity in that control area.
(3) In the context of the radiation protection passport, the holder of the authorization, in whose control area external workers are employed, shall perform the following tasks:
1. |
Verification of the radiation protection pass submitted by the passport holder: |
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a) |
Validity, |
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b) |
Compliance with the personal data of the holder (conformity with the data of an official photo ID), |
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c) |
Employers, |
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d) |
current dose levels, |
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e) |
the result of medical checks, |
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f) |
Respiratory protection, as well as |
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g) |
Radiation protection teachings and training already carried out; |
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2. |
Registration of further radiation protection instructions in the radiation protection pass; |
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3. |
Registration of the individual exposure after the completion of the activity of the external worker in the control area in the radiation protection passport or immediate written notice of the individually determined exposure to the Marketing authorisation holder of the external company. |
Obligations of external workers
§ 46. (1) Each external worker shall, within the limits of its possibilities, contribute to the safe collection of exposures in foreign control areas, the relevant records in the radiation protection passport through its timely submission. , the current exposure value shall be made known to the holder of the external undertaking by presenting the radiation protection pass immediately after it has been updated by the holder of the authorization of the external control area , and all instructions and work instructions are followed .
(2) If the holder of a radiation protection passport is not used as an external labour force, he shall have the radiation protection passport to be observed. In the case of renewed employment as an external labour force, he has to pass the radiation protection pass to the employer.
Content and form of the radiation protection passport
§ 47. (1) The radiation protection passport shall be
1. |
in the format 125x88 mm; |
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2. |
provided with a cover made of resistant material, durable against tearing and creases, with a top cover in yellow colour and the inscription "Radiation Protection Pass"; |
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3. |
with concealed thread stitching and using forgery-proof paper |
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. |
(2) The radiation protection passport must provide room for the following entries:
1. |
First name (s), surname, social security number, date of birth, place of birth, sex, citizenship, principal residence, signature of the passport holder; |
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2. |
Room for registration by the Authority; |
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3. |
-activities in foreign control areas; |
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4. |
the name and address (company stamp) of the external company; |
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5. |
the name and address of the holder of the authorization and of the person responsible for the management of the radiation protection passport; |
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6. |
Duration of activity in the foreign control area; |
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7. |
Measurements of external and internal exposure in the control area; |
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8. |
Monthly balancing of the effective dose and, where appropriate, the dose of equivalent doses for extremities, skin and eyes; |
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9. |
Annual reporting of the effective dose; |
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10. |
exceedance of dose limits; |
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11. |
Results of the medical examinations according to § § 32 to 35; |
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12. |
Training and teachings on radiation protection; |
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13. |
Fitness for respiratory protection; |
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14. |
Training and teachings on respiratory protection; |
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15. |
Previous expositions of the Passinoher. |
Exhibition, registration and evidence of radiation protection passports
§ 48. (1) The Federal Minister of Agriculture, Forestry, Environment and Water Management is responsible for the exhibition, registration and evidence holding of radiation protection passports in accordance with § 35f StrSchG.
(2) The registration includes an identification of the passport holder, the assignment of an ongoing passport number as well as a continuous identification of all radiation protection passes of a person. The personal data, including the continuous passport number and the continuous identification of all radiation protection passes of a person, including the date of registration (date of issue), must be recorded in a register.
(3) The period of validity of a radiation protection passport shall be no more than 10 years from the date of registration.
(4) If the period of validity of the radiation protection pass has expired or if the passport does not have sufficient room for further entries, the holder of the external company's authorization shall issue a new passport immediately at the registration office. -.
(5) In the following cases, the registration office shall, on the basis of the notification by the holder of the authorization within the meaning of section 49 (4), immediately carry out a new exhibition or update of the radiation protection pass:
1. |
in the event of loss of passport; |
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2. |
in the case of unusefulness of the passport; |
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3. |
if you change the data contained in the passport to the passport holder. |
Management of the radiation protection pass
§ 49. (1) If the holder of the authorization of an external company intends to employ a person as an external worker and if that person does not yet have a radiation protection pass according to § 47, such a person is from the registration office pursuant to § 48 (1), paragraph 1. The beginning of this occupation shall be entered by the holder of the authorization in the radiation protection passport.
(2) The current entries in the radiation protection pass must be carried out in such a way that, at all times, an updated filled-out radiation protection pass can be submitted by the passport holder prior to access to control areas. Periods during which the passport holder was not active in control areas shall be marked accordingly.
(3) The radiation protection pass shall be held by the holder of the external company's authorization. The holder of the authorization shall pass the radiation protection pass to the passport holder prior to the start of the activity in the control area and shall be returned to the holder after the end of the activity for the purpose of entry and storage. Similarly, if the radiation protection pass is required by its holder on the occasion of a medical check-up, the procedure must be followed.
(4) After an activity in a foreign control area has been completed, the holder of the external company's authorization shall ensure that the exposures ascertained there are registered in the radiation protection passport or, failing that, ensure that they are taken into account for this purpose. shall be sent to him in writing immediately by the holder of the external control unit. If this information is not transmitted in spite of repeated requests, the Central dose register shall be accompanied by the name, address and telephone number of the defaulting holder of the authorization and a presentation of the facts of the case in this respect. to inform.
(5) The holder of the authorization of the external company shall carry out a monthly accounting of the data in accordance with Section 47 (2) Z 7 for each external worker and shall enter the monthly dose values in the radiation protection pass. The measured dose values shall be transmitted by the external company's holder of the authorization to the Central Dose Register within two weeks. Furthermore, for each calendar year in which the radiation protection pass is valid, the holder of the authorization of the external company shall determine the effective dose in accordance with § 47 (2) Z 9 and enter the dose in the radiation protection passport.
(6) The exceeding of the maximum permissible doses in accordance with § 12 shall be notified without delay by the holder of the authorization of the external company to the competent authority.
(7) If the radiation protection pass is lost or unusable, and if the data contained in the radiation protection pass are changed to the passport holder or to the employer, the holder of the external company's authorization shall send a notification to the registration office. In the event of changes to data concerning the holder of the authorization or employer (Section 47 (2) (4) and (5)), the holder of the consent of the external company shall enter the updated data in the radiation protection passport.
(8) If an external labour force is not employed by the company or if it is no longer employed as a person exposed to radiation, the holder of the authorization shall note this in the radiation protection passport, the radiation protection pass to the passport holder and to notify the Registry of this.
Special arrangements for certain occupational groups
§ 50. For workers carrying out installation and service activities at facilities for the production and measurement of ionizing radiation, and employed by external companies, which are responsible for the management of the radioactive waste In agreement with the holder of the authorization in whose control the labour force is active, it shall be permissible for the exposure of these workers to be carried out with the aid of directly readable persons dosemeters of the external company is determined. The following rules shall apply:
1. |
The personal dosemeter must comply with the requirements for the intended use. |
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2. |
The person dosemeter provided by the external company must be personally assigned to the worker; it must be sufficient and must not be able to be deleted by unauthorized persons. |
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3. |
The working force must be classified as a professionally exposed person in category A and must be subject to medical and physical supervision. In any case, in addition to the person dosemeter which can be read directly, a personal dosemeter according to § 25 must be worn. |
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4. |
The external labour force must independently carry out a dose protocol in the form of monthly lists through the exposures during its operations in foreign control areas, in which they each have the duration and place of the work immediately after the completion of the work. Use as well as the dose of dosimeter reading of the dose at the beginning and end of the activity. The dose protocol for the current month shall be considered to be a supplement to the radiation protection passport and shall be attached to it. |
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5. |
The marketing authorisation holder of the external company has to evaluate the dose protocol monthly and, within the meaning of § 49 (5), the accounting, the registration in the radiation protection pass and the transmission of the dose values to the central dose register , The dose protocol should be kept for 7 years. |
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Thus, the obligation to register the individual exposure after the completion of the activity of the external worker in the radiation protection pass pursuant to § 45 (3) Z 3 is no longer necessary for the holder of the approval of the control area. |
Part 3
Radioactive substances
Section 1
General provisions
Scope
§ 51. The provisions of this Part shall be applied to radioactive substances only in so far as the handling of such substances is subject to the obligation to notify or to the possession of the same under the Radiation Protection Act or this Regulation.
Open and enclosed radioactive substances
§ 52. (1) Radioactive substances shall be considered to be enclosed if their structure prevents any spread of the radioactive substances into the environment in the event of their intended use.
(2) Radioactive substances which are not to be regarded as enclosed in accordance with paragraph 1 shall be considered to be open radioactive substances.
Labelling of radioactive substances
§ 53. (1) Radioactive substances shall be labelled in accordance with paragraphs 2 and 3; this shall also apply to their containers, unless § § 54 (2) Z 1, 55 (2) (2) Z 1 or 76 (7) applies.
(2) The labelling must allow the identification of the radioactive substances at all times. It shall contain at least the radiation warning sign referred to in Appendix 3 with the words "RADIOACTIVE", the indication of the radionuclide and the activity at the time of its measurement or determination.
(3) The labelling particulars referred to in paragraph 2 shall be clearly visible to the radioactive substances, to the extent that this is possible on the basis of their nature and size, and their containers, as well as to articles or equipment containing radioactive substances and be permanently attached. All essential information on the radioactive substance must also be recorded on a related accompanying sound.
(4) Where radioactive substances are used in the course of work operations using the necessary security measures, it is not necessary to identify the radioactive substances for the duration of such operations. In these operations, a person familiar with these security measures shall be present.
Storage facilities
§ 54. (1) Radioactive substances shall be kept under closure during the period during which they are not used, in facilities intended solely for the storage of such substances, such as cabinets, safes or constructional devices. These bodies must ensure that, for maximum content and the establishment of a closed facility, persons cannot be exposed to higher exposure than one-twentieth or, if these facilities are located in control areas, Sixths of the maximum authorised dose for persons exposed to radiation according to § 12 (1). In no case shall the local dose rate of the escaping radiation exceed 200 microsieverts per hour at a distance of 0.1 metres and 25 microsieverts per hour at a distance of 1 metre from the surface of the device. Where storage facilities are located in their own premises, which are only used for the storage of radioactive substances, the limit of the local dose rate can be set at a distance of 0.1 metres from the surface, and that of each individual may be deleted by each individual. Installation of local dose rate at 1 meter from the surface is up to 100 microsieverts per hour.
(2) Facilities for the storage of radioactive substances must also comply with the following requirements:
1. |
they must be marked "RADIOACTIVE" by means of the radiation warning sign in accordance with Appendix 3; |
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2. |
they may only be accessible to persons authorised to deal with such substances; |
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3. |
they must be sufficiently protected against the action of fire; |
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4. |
in the case of the storage of radioactive substances which may also pose a hazard to radiation other than radiation, a reference must be made to this effect. |
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These requirements also apply to rooms which are used exclusively for the storage of radioactive substances. |
(3) Rooms in which radioactive substances are stored must be equipped in such a way as to ensure that the location of the site in the vicinity of these rooms does not exceed the local dose levels set out in Appendix 4.
(4) If several radioactive substances are stored in a device as referred to in paragraph 1, they shall, if necessary, be shielded in such a way that the shielding of the other substances is not impaired by the introduction or removal of a substance. The individual radioactive substances shall be stored in their own containers or compartments, in so far as they are not equipment which are approved in accordance with § 19 of the German StrSchG (German StrSchG). The label of the containers or compartments must show the number, activity and otherwise required data of the custody of the radioactive substances.
(5) If radioactive substances are capable of causing contamination of the air, appropriate ventilation means, if necessary with filter systems, must be present. If necessary, measuring instruments are to be provided for monitoring the air activity.
(6) Rooms or facilities for the storage of radioactive substances must be designed in such a way as to ensure that the radioactive substances are secured against unauthorized access.
(7) Suitable records shall be kept on the storage of radioactive substances. The nature and extent of the records shall be determined by the competent authority in a modest manner.
Transport of radioactive materials within establishments
§ 55. (1) The transport of radioactive substances within establishments shall be limited as far as possible; in any event, it shall be carried out in such a way as to minimise the exposure of persons to radiation as a result of this, and also to: any other risk is avoided.
(2) Radioactive substances may only be transported in protective containers, which meet the following requirements:
1. |
they must be marked "RADIOACTIVE" by means of the radiation warning sign in accordance with Appendix 3; |
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2. |
they must be of such a nature as to enable the persons employed by the carriage to comply with the necessary distance; |
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3. |
They must absorb alpha and beta radiation entirely and weaken other radiation in such a way that the local dose rate is neither 2 millisievert per hour in 0.1 meter distance from the surface nor 0.1 millisievert per hour at 1 meter distance. from its surface; |
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4. |
they must comply with the requirements laid down in Article 67 (3) for the transport of open pulverulent, liquid or gaseous radioactive materials. |
Cleaning and repair work
§ 56. (1) In rooms where the radioactive substances are treated with open radioactive substances, or in which radioactive substances produced by activation processes occur, attention should be paid to the strictest cleanliness, in particular the possible freedom of dust.
(2) Cleaning instruments for such spaces, such as vacuum cleaners, brushes or brooms, may not be used in other rooms. Suitable, easily decontaminable devices must be available for the storage of such equipment. These appliances and equipment shall be labelled and shall be authorised only for persons authorised to deal with open radioactive substances, and those who are responsible for cleaning with such cleaning equipment and shall be subject to special conditions of protection. shall be accessible.
(3) Special work instructions shall be drawn up for the cleaning of the premises referred to in paragraph 1, including their facility; these cleaning works may only be carried out in accordance with these instructions from those who have been instructed to do so.
(4) The provisions of paragraphs 2 and 3 shall also apply to maintenance and repair work. Tools and materials which have been introduced into such spaces in the course of such works shall be checked for contamination after completion of the work.
Contamination
§ 57. (1) For the management of radioactive substances, where the risk of contamination by these substances cannot be excluded, appropriate operating and behavioural rules should be laid down, in particular as regards the determination of the The extent of contamination, the way in which the decontamination of persons, working spaces, workplaces, equipment, equipment and garments, as well as the review of these measures are concerned.
(2) After the occurrence of a contamination, care must be taken to ensure that the contamination remains limited. The contaminated area shall be marked without delay by the radiation warning sign in accordance with Appendix 3, with the words "CONTAMINATION". All persons not engaged in decontamination shall be kept away from the contaminated area.
(3) In the case of large-scale contamination, in particular in cases where it is assumed that a rapid and sufficient decontamination cannot be achieved by simple means, the holder of the authorization or the holder of the authorization shall be immediately immediately informed of such contamination. in accordance with Section 15 (2), to notify persons who have the necessary measures to take the necessary measures.
Decontamination
§ 58. (1) Decontamination is any reduction or disposal of contamination; decontamination measures are considered to be treated with open radioactive substances.
(2) Where there has been a contamination of areas, objects, clothing or parts of the skin, which shall be the subject of: Appendix 9 , the measures for decontamination must be taken immediately; such measures are not required in the interior of closed working chambers, such as glove boxes or hot cells.
(3) Only persons who have the necessary knowledge and are particularly instructed may be used to decontaminate the decontamination. The number of persons employed in the individual case with such work shall always be kept as small as possible; these persons shall use the protective equipment necessary for their work against contamination.
(4) In order to decontaminate the decontamination, the use of tools, equipment and other tools provided exclusively for these purposes shall be as soon as possible to decontaminate or to be used as radioactive waste Dispose of waste.
(5) If it is not possible to reduce the contamination to the values indicated in Appendix 9, the contaminated area must be left, if necessary also its environment. The Authority shall be notified of such an incident, which shall be responsible for the further measures to be taken.
Recording and reporting obligations
§ 59. (1) In respect of the reference, possession, use, storage, transfer (recycling) and the release of radioactive materials, including radioactive waste, the holder of the authorization shall keep records containing the following information: have:
1. |
for open radioactive substances: radionuclide, indication of activity with reference date, physical and chemical characteristics, date of reference, name and address of the manufacturer or supplier; further location of storage or use, deprivation of date, Quantity and type of use, as well as information on transmission, disposal, derivation or delivery on other permitted routes, including date and quantity. |
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2. |
for radioactive substances enclosed: identification number or other identification of the radiation source, radionuclide, indication of activity with reference date, physical and chemical characteristics, date of reference, name and address of the manufacturer, or Suppliers, place of storage or use, details of operational control such as the verification of the presence, proper storage, the functioning of all safety devices and the leak tests carried out, and Information on the transfer or disposal. |
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3. |
The name and address of the purchaser shall be recorded in the case of the transfer of radioactive substances, including radioactive waste. |
(2) The Authority may, in justified cases, in particular where the radioactive substances are open-ended with half-life of less than 24 hours, allow simplifications to be made in the records referred to in paragraph 1.
(3) These records shall be kept for at least 7 years.
(4) Once a year, the holder of the authorization shall submit a report (the balance of activity) to the Central Radiation Sources Register, the reference, the further and the levy, and the amount of radioactive material stored, including radioactive waste. .
(5) The transmission to the Central Radiation Source Register in accordance with paragraph 3 is preferably to be carried out in electronic form using the interfaces provided by the Central Radiation Source Register. The above-mentioned information can be transmitted in a different manner.
(6) The provisions of Section 64 (5) relating to highly radioactive sources of radiation shall remain unaffected.
Transboundary movements of radioactive substances subject to notification
§ 60. (1) A transboundary movement of radioactive substances within the meaning of this Regulation shall apply:
1. |
import into the scope of this Regulation from a State which is not a Member State of the European Communities, |
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2. |
the export from the scope of this Regulation to a State which is not a Member State of the European Communities, or |
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3. |
the cross-border movement of goods from a Member State of the European Communities within the scope of this Regulation or into a Member State of the European Communities from the scope of this Regulation. |
(2) Anyone who intends to spend radioactive substances covered by the scope of this Regulation in a State which is not a Member State of the European Union or from such a State to the territory of the country shall have this in good time before the Transfer to the Central Radiation Source Register. This shall not apply to the transit of such substances. This report shall contain:
1. |
the name and address of the reporting person; |
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2. |
in the case of the name and address of the supplier, manufacturer, |
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3. |
the export name and address of the consignee, |
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4. |
Indication of the radionuclides and their activity, |
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5. |
Indication of whether it is an open or enclosed radioactive substance, |
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6. |
in the case of enclosed radioactive substances, the identification number of the radiation source, provided that such a source has been awarded. |
(3) The messages to the Central Radiation Source Register within the meaning of paragraph 2 are preferably to be carried out in electronic form using the interfaces provided by the Central Radiation Source Register. The above-mentioned information can be transmitted in a different manner. If it is intended to carry out or carry out several radioactive substances within a period of up to one year, the messages can be summarised in a collecting message.
(4) In addition, within 21 days of the end of each quarter, the obligation to transmit a summary report to the Central Radiation Sources Register shall be submitted to the Central Radiation Source Register in accordance with the provisions of paragraph 2, covering the shipments in the quarter, including:
1. |
the name and address of the reporting person; |
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2. |
in the case of imports, the name and address of the suppliers, or manufacturer, |
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3. |
in the case of exports, the name and address of the recipients |
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4. |
Total activity per radionuclide delivered to the respective recipient or obtained from the respective supplier and the number of deliveries, |
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5. |
the highest individual activity of each radionuclide delivered to the respective recipient or obtained by the respective supplier, |
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6. |
Indication of whether the radioactive substances are open or enclosed; |
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7. |
in the case of enclosed radioactive substances, the identification numbers of the radiation sources, provided that they have been assigned. |
(5) In the case of shipments of radioactive substances between the Member States of the European Union, the standard declaration provided for in Council Regulation (EURATOM) No 1493/93 of 8 June 1993 on the movement of radioactive substances between the Member States of the European Union is subject to the provisions of Council Regulation (EEC) No 1493/93 of 8 June Member States, OJ No. L 148/1, Annex 1, to the Central Radiation Sources Register.
(6) Any other reporting obligations to the Central Radiation Protection Register in accordance with StrSchG or the regulations established thereon shall remain unaffected by the provisions of paragraphs 1 to 7.
(7) The reporting obligation under (2) and (4) shall not apply
1. |
According to the legal provisions of the Federal Constitutional Law on Cooperation and Solidarity in the posting of units and individuals abroad (CFE-BVG), BGBl. I n ° 38/1997, persons who have been sent and |
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2. |
These are the legal provisions of the Federal Act concerning the residence of foreign troops on Austrian territory (Tops Residence Act-TrAufG), BGBl. I n ° 57/2001, subject to foreign troops. |
Radioactive substances in or radioactive contamination of materials intended for recycling and re-use
§ 61. (1) Any natural or legal person who collects, acts and processes substances which, according to current knowledge, are to be assumed to be able to contain radioactive substances or that they may be radioactively contaminated, shall have: ensure that these materials are free from radioactive substances and free from radioactive contamination, with due regard to the free values set out in Appendix 1. This applies in particular to residues for recycling and re-use. Contractual agreements shall be deemed to be appropriate measures in the meaning of this provision that, in the event of non-compliance with the guaranteed specification, the placing on the market shall be subject to the necessary protection, safety and disposal measures for the costs of any necessary measures. , as well as certificates of trustworthy institutions or metrological proof.
(2) If, in connection with the measures referred to in paragraph 1, the possession of radioactively contaminated or contaminated material is detected, the owner shall properly dispose of the material at his own expense. However, this provision does not in any way affect any private-law compensation claims against those natural or legal persons who have made such materials.
(3) In the case of shipments of radioactive substances in residues or radioactive waste to the supplier, this shall be considered as a shipment of radioactive waste in accordance with the Regulation on the supervision and control of shipments radioactive waste from the, into or through the federal territory (Radioactive Waste-Shipments Regulation), BGBl. II No 44/1997.
(4) Where a natural or legal person is identified in connection with the handling of materials intended for re-use and re-use of materials contaminated with radioactive substances or contaminated with radioactivity, which exceeds the free values referred to in Appendix 1, shall immediately inform the competent authority. The competent authority shall report this to the Central Radiation Source Register.
(5) The notification referred to in paragraph 4 shall contain, to the extent that this may be collected, the following information:
1. |
the name and address of the location to be found; |
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2. |
the name and address of the issuing body; |
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3. |
detected radionuclides, including their activity, |
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4. |
description, quantity and weight of the secured material, |
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5. |
the type of sealing of this material in order to avoid further contamination, |
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6. |
Indication of where this material to be classified as radioactive waste has been taken. |
Section 2
Radioactive Substances Enclosed
Nature
§ 62. (1) Reclosed radioactive substances must be in a form which is chemically and mechanically as stable as possible.
(2) In the case of emanating radioactive substances, the activity of which is less than 200 Megabecquerel, a molten glass container is permitted as a casing. Such sealed radioactive substances may only be used for laboratory work; during the period in which they are not used, they shall be kept in sealed metal containers intended exclusively for this purpose.
(3) If only gamma radiation is to be used for radioactive substances, an inactive envelope shall prevent the escape of beta radiation or, if this is not technically possible, keep it as low as possible.
(4) If, in the case of enclosed alpha or beta-radiators, the radiation is used only within a casing, the casing must absorb the entire alpha or beta radiation.
(5) A certificate issued by the manufacturer or supplier must be available from the manufacturer or supplier in respect of each enclosed radioactive substance whose activity exceeds the hundred thousand times the free limits set out in Annex 1, Table 1, columns 2 and 3. In a given distance or in the activity at a specified date, this certificate shall also provide information on the physical and chemical status of the radioactive substance and, where appropriate, on the physical and chemical status of the radioactive substance. the type and wall thickness of the casing or to contain the type of matrix material. If the local dose rate without shielding is more than 1 millisievert per hour at a distance of 1 metre, the local dose rate shall, in any case, be indicated by the manufacturer or supplier. This information must be accompanied by the audit report of an accredited testing body, and the competent authority may recognise audit reports of appropriate other bodies.
Leak testing
§ 63. (1) Reclosed radioactive substances are periodically recurring in time intervals to be determined by the competent authority in accordance with the requirements of radiation protection-at any rate, however, in the event of suspicion of possible damage. to their proper condition, in particular to contamination caused by the leakage of the casing or matrix.
(2) Reclosed radioactive substances which no longer comply with the requirements laid down in § 62 shall be excluded from further use and shall be protected against the requirements of radiation protection in the light of the requirements of the Directive. They may not be used again until after a repair has been carried out, an examination results that the requirements of § 62 are fulfilled.
(3) The examinations referred to in paragraph 1 and paragraph 2, second sentence, shall be carried out by accredited bodies. In the case of radioactive substances with a free-limit as defined in Appendix 1, Table 1, column 2 greater than/equal to 10 4 Becquerel, the local dose rate of which is less than 1 millisievert per hour without shielding at a distance of 1 metre, may be carried out by qualified persons who may also be members of the company. These tests shall be carried out in accordance with the rules of technology in force in Austria.
(4) records shall be kept of the results of the examinations referred to in paragraph 1 and (2), second sentence; the holder of the authorization shall keep the records for 7 years and, at the request of the competent authority, who shall be responsible for the performance of the To present workers ' protection to the competent authority and to the competent institution of the accident insurance.
High-level radioactive sources
§ 64. (1) A sealed source of radiation containing a radionuclide whose radioactivity at the time of manufacture or, if not known, at the time of the first placing on the market of the value specified in Table 1, column 4, in Appendix 1 is or is higher, is considered to be a highly radioactive radiation source.
(2) The prerequisite for the granting of an authorisation to deal with highly radioactive sources of radiation by the competent authorization authority is the verifiable conclusion of an insurance policy or the presentation of a bank guarantee, which guarantees the safety of the safety of the radioactive waste. Disposal of the highly radioactive source of radiation also in the event of a payment inability of the holder of the authorization to ensure, through the consent. This obligation shall not apply if:
1. |
the federal government, a country, a community association, or a local community with more than 50 000 inhabitants, is or is not a member of the public |
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2. |
A local authority according to Z 1 has issued a liability declaration to the advertiser. |
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The obligation to provide financial security pursuant to the Atomic Liability Act 1999, BGBl. I No 170/1998, shall be without prejudice to this. |
(3) The manufacturer shall assign an unmistakable identification number for each source of radiation, or the supplier shall ensure that a non-confusing identification number has been allocated to a source of radiation imported from third countries. As far as possible, this number shall be engraved on the radiation source or stamped into it. It is also to be engraved on or imprinted on the protective container. If reusable transport containers are used again, these must have minimum information on the type and activity of the radiation source. Each source of radiation delivered and each delivered protective container shall be subject to a photograph of the type of radiation source and of the type of protection vessel on which the essential characteristics of an associated protective device or protective equipment are also included. , as well as plans and cutting drawings where necessary. In addition, each source of radiation delivered shall be connected to a radiation source certificate, from which the identification number, the type and activity of the radioactive substance, date, procedure and result of the leak test must be produced.
(4) The owner shall ensure that each radiation source is accompanied by the corresponding radiation source certificate and the photographic documentation provided for in paragraph 3.
(5) The holder of the authorization of high-level radioactive sources shall be responsible for the handling of special work instructions, including regular maintenance, periodic inspections and safe storage, in particular in the case of: of a mobile use, to be included. It also has all those persons who are entrusted with the handling of highly radioactive sources of radiation to undergo extensive theoretical and practical instruction. In particular, the teachings must also refer to the contents of the safety analysis, the incident analysis and the emergency planning. The teachings shall be repeated at regular intervals and immediately after an event which has resulted in the risk of higher exposure to radiation or of an actual higher exposure to radiation. The extent and duration of these teachings shall be subject to written records kept for at least 7 years.
(6) Without prejudice to the provisions of § 59, the holder of the authorization shall keep records of highly radioactive sources of radiation, which shall be carried out in accordance with Appendix 10 provided for. These records may be recorded on the standard recording sheet according to Appendix 10.
(7) Without prejudice to the provisions of § 54 paragraph 2 lit. 3 are highly radioactive sources of radiation in containers of type B in accordance with the European Convention on the International Carriage of Dangerous Goods by Road (ADR-BGBl. No 522/1973, idgF) are to be kept in lockable, non-combustible installations in which there may be no significant bursts of fire. Storage facilities for other highly radioactive radiation sources must be designed to be at least fire-retardant.
(8) The holder of the authorization shall inform the Central Radiation Source Register of the following information on highly radioactive sources of radiation:
1. |
the holder of the authorization, the number of business and the date of the authorization; |
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2. |
the identification number of the high-level radioactive source, |
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3. |
Characteristics and use of the highly radioactive radiation source, |
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4. |
the location of the transfer or storage of the high-level radioactive source; |
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5. |
Information on the relationship, transfer or disposal, possibly loss or theft of the highly radioactive radiation source. |
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The reports shall be reported once a year and immediately |
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1. |
after the acquisition of the radiation source, |
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2. |
in the case of a transfer of the radiation source |
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3. |
in the event of any repatriation to the manufacturer or the placing on the market, |
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4. |
in their removal and |
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5. |
in any modification of the information to be communicated |
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to make it. They shall be transmitted in electronic form using interfaces made available by the Central Radiation Source Register. The standard recording sheet of the installation 10 can be used for conventional transmission. |
Non-medical use of surrounded radioactive substances
§ 65. (1) Reclosed radioactive substances shall be used with protective containers, from which, through the radiation discharge opening, unweakened radiation can escape only in a particular direction. The radiation exit opening must have an electrically or mechanically lockable closure, the opening state of which can be clearly seen. It must be ensured that the closure is closed automatically in the event of a power failure.
(2) The protective containers must ensure that, when the radiation outlet is closed, the dose rate of the emerging radiation at a distance of 1 metre from the radiation source is 25 microsieverts per hour and a maximum of 100 microsieverts per hour. per hour.
(3) Where the use of enclosed radioactive substances with protective containers is not possible for reasons which are in the nature of the application, they may be used outside the protective containers. However, sealed radioactive substances shall not be removed from the protective containers only immediately prior to their use; once they have been used, they shall be immediately re-established in the protective containers.
(4) In the case of the handling of radioactive substances enclosed outside of protective containers, appropriate aids are to be used which provide the necessary protective distance, such as grasping and distancing tools or carrying devices. These gripping and distancing devices are in each case to be stored in common with the protective containers and must be carried along in the case of transport from and to the application locations. If, as a result of the necessary protection distance, a safe handling with these auxiliary means is no longer ensured, suitable remote control devices must be provided. In any case, radioactive substances may not be affected by the hands of the enclosed radioactive substances.
(5) As far as possible, enclosed radioactive substances, the dose rate of which exceeds 1 millisievert per hour at a distance of 1 metre, must be mechanically connected to the protective containers; they may only be provided by Bowden cables or other Remote control devices can be brought into the working position.
Operating rules
§ 66. (1) Reclosed radioactive substances, the dose rate of which is more than 1 millisievert per hour at a distance of more than 1 millisievert, shall, to the extent permitted by the type of use, be used in radiation applications in accordance with § 22 and from secondary rooms to be used in operate. After completion of work with enclosed radioactive substances, it is necessary to check whether the enclosed radioactive substances are in the protective position before entering the radiation application spaces by measuring the position of the local dose.
(2) The following provisions shall apply to the use of enclosed radioactive substances outside radiation applications:
1. |
In accordance with § 3 (1), all persons have to stay sufficiently far from the enclosed radioactive substances and from scattering objects in accordance with the optimization bid of § 3 (1); |
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2. |
the area of control shall be defined, identified and monitored within the meaning of section 18 (1); in this area only persons exposed to radiation shall be allowed to reside and only for as long as this is for compelling reasons, such as for work according to § § 18 (1). Paragraph 3, second sentence, is required; |
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3. |
in the case of work carried out in control areas, the necessary protective layers must be present between the object and the workers, taking into account any scattered radiation (Skyshine) which may occur; |
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4. |
the enclosed radioactive substances may not be brought into the working position until all preparatory work has been completed; |
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5. |
appropriate measuring instruments must be available for the control of radiation protection measures; persons exposed to radiation must in any case also bear warning dosimeters; |
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6. |
the duration of the radiation application shall be kept as short as possible; |
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7. |
all necessary precautions for the protection of the general population must be taken. |
(3) appropriate technical standards or other relevant technical regulations shall be used for the determination of the necessary shielding.
(4) In the case of work with enclosed radioactive substances in which inadmissible exposure of the employees in such cases can be avoided only if a particular mode of operation is complied with, the working method shall be carried out prior to commencement of this work. of spotlight attriads (blind experiments).
Section 3
Open radioactive substances
Handling of open radioactive substances
§ 67. (1) In the selection of open radioactive substances for certain uses, consideration shall be given to the least possible hazard potential.
(2) In the selection and design of the working methods with open radioactive substances, provision should be made for exposure to be kept as low as possible due to external exposure to radiation and to the inclusion of radioactive substances. In particular, appropriate measures shall be taken to prevent the uncontrolled spread of these substances, such as by scattering or spilling, of the formation of radioactive gases, vapours, aerosols or dusts; before commencement of work with such substances, If possible, it is possible to carry out the planned working method using inactive substances (blind experiments).
(3) Open pulverulent, liquid or gaseous radioactive substances must either be stored in unbreakable vessels or the vessels shall be required to meet their fragility or to the possibility of an occurrence of A reduction in strength in unbreakable, dense, sealable containers which, in the case of liquid substances, have to contain so much absorbent material that it can absorb the entire amount of liquid. Care must be taken to ensure that the storage vessels do not have an inadmissible overpressure.
(4) Open radioactive substances must not be touched with bare hands, solutions should not be pipetted with the mouth. Work in which the air must be expected to be contaminated with radioactive contamination must be carried out under a suction hood if the nature of the work does not require any further protective measures. Air drawn from suction hoods, digestories, closed working chambers or working spaces may only be discharged into the open air under the conditions laid down in § 74.
(5) At workplaces, radioactive substances may be present only in such quantities and only in such quantities as they are required for the operation; unneeded open radioactive substances shall be available in accordance with the provisions in force in this regard; true.
(6) Work equipment, materials and other objects used in a workplace shall be removed only in such a way as to prevent any inadmissible contamination from outside the workplace.
(7) Radioactive waste shall be collected and stored separately in accordance with section 76 (1).
Protection against contamination
§ 68. (1) In the case of work with open radioactive substances, clothing and equipment, such as working coats, work suits, protective gloves, headgear, shall be required to protect against contamination or incorporated into the radioactive material, Protective goggles, breathing apparatus, liquid impervious aprons or foot coverings are worn.
(2) Clothing and equipment for protection against contamination must be checked to the extent necessary for contamination. If their contamination exceeds the values set out in Appendix 9, they must not be used. They must be kept separately and decontaminated or treated as radioactive waste.
(3) The installation and laying down and storage of clothing and equipment for protection against contamination as well as of street clothing must be carried out in suitable changing rooms in such a way that contamination of the street clothing does not occur.
(4) In the event of damage or pathological conditions of the skin on the hands or forearms of which the protective function of the skin is reduced against the exposure of open radioactive substances, the work with such substances, even when using such substances, has Contamination protection gloves, to be kept down.
Workplace types
§ 69. (1) For the Appendix 11 in accordance with this Annex, the use of types C, B or A shall be set up; the values given in Appendix 11 shall correspond to the activities of radioactive substances, including the activities of radioactive substances in the manner of the transfer must be handled only at a workplace which is at least equal to the requirements of the type concerned. The competent authority may allow the establishment of a workplace where only storage in transport containers complying with the transport requirements in accordance with Section 55 does not result in the use of radioactive substances from it. shall be added and shielded in such a way as to ensure that the location dose values listed in Appendix 4 are not exceeded. In duly substantiated exceptional cases, the Authority may also allow workplace equipment deviating from the requirements of § § 70 to 72 if this treatment is only temporarily carried out and compliance with the dose limit values in accordance with § § 12 to 14 is ensured.
(2) Rooms and buildings in which workstations are set up in accordance with paragraph 1 shall be so shielded that the local dose levels set out in Appendix 4 shall not be exceeded outside these workstations.
Workplaces of Type C
§ 70. (1) Type C workstations and, where necessary, spaces in which such jobs are established shall meet the following requirements:
1. |
they must be labelled "RADIOACTIVE" by means of the radiation warning sign in accordance with Appendix 3. Access may be granted only to persons authorised for this purpose; |
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2. |
they must be sufficiently ventilated and illuminated; |
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3. |
Walls, floors and furnishings must have smooth surfaces and must be easy to clean; only the necessary equipment must be present; |
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4. |
Working surfaces must be smooth and correspondingly resistant; they must not absorb liquids; |
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5. |
appropriate washing facilities and, if necessary, shower facilities must be available; |
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6. |
there must be a laboratory washbasin, which can be used to decontaminate objects; |
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7. |
if necessary, appropriate shielding against radiation must be available for the protection of persons. |
(2) In rooms where Type C workstations are located, no objects may be introduced which are not strictly necessary for carrying out work, in particular no food, smoking products, medicinal products or cosmetics. In such rooms, paper towels and paper towels are to be kept and used in a suitable manner; paper towels and paper towels used are to be treated like radioactive waste.
(3) In workplaces of type C, the working surfaces shall be kept free of all objects and substances which are not required for the work.
(4) At workplaces, the surfaces shall be tested at regular intervals and, moreover, where there is a need for contamination.
(5) Prior to leaving jobs in which open radioactive substances are being handled, the necessary extent to consider whether a radioactive contamination of the hands, other parts of the body or clothing, in particular: of the footwear. If the plant is exceeded in Appendix 9 lit. C and D are the necessary decontamination measures to be carried out. The washing facilities are to be used prior to breaks and before working hours.
(6) The transfer of objects from radiation areas shall be inadmissible if their contamination exceeds the values set out in Appendix 9.
Workplaces of Type B
§ 71. (1) Type B workstations must be provided in their own premises, only for those purposes; they may only be accessible to persons authorised to do so. For Type B jobs and for spaces in which such jobs are established, the provisions for Type C jobs (§ 70) and in addition to the provisions of this section shall apply.
(2) Rooms in which Type B workstations are arranged must form a separate fire section. They must be clearly separated from one another by means of constructional or installation measures.
(3) The surface of the floors shall not absorb liquids; it must be correspondingly resistant and liquid-impermeable. Walls must be up to 3 metres in height with a washable, resistant and liquid-impermeable protective layer; if the room height is lower, the ceiling must also comply with these requirements.
(4) In addition to the hand-wash basin, Type B workstations shall be equipped with a laboratory basin exclusively for the decontamination of objects; this shall be indicated with a stop;
(5) After completion of the work, but at least daily at the end of the work, the workstations shall be tested for possible contamination.
(6) Work in which contamination of the air may occur must be carried out in a closed working chamber with negative pressure or an isotope discharge cabinet. When using an isotope deduction cabinet, attention must be paid to the necessary air supply; however, under no circumstances can excess pressure be created in the room. After appropriate filtering, the exhaust air is to be removed into the open air. In the event of suspicion of contamination of the room air, corresponding control measurements shall be carried out. These closed working chambers must meet the following requirements:
1. |
As long as there are open radioactive substances in the chambers, the negative pressure must be at least 100 Pascal; the negative pressure must be constantly indicated by pressure gauges; |
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2. |
The air is to be removed via filters directly attached to the chambers, if necessary also via further filter stages, and to lead directly into the open air as a further air. The effectiveness of the filters shall be periodically checked; contaminated filter materials shall be disposed of as radioactive waste; |
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3. |
for the installation and discharge of the open radioactive substances and the objects required for the intended handling of such substances, the chambers shall be equipped with locks. |
(7) In the case of work with open radioactive substances, equipment such as distance tools or manipulators shall be used to ensure the necessary distance to these substances.
(8) protective clothing and protective equipment must be clearly marked in such a way as to indicate their provision for type B workplaces; they must in no case be carried outside the spaces belonging to the workplaces of Type B.
Workplaces of Type A
§ 72. (1) Type A workstations must be provided in their own premises, only for those purposes; they may only be accessible to persons authorised to do so. In the case of Type A jobs and spaces in which such jobs are established, the provisions relating to jobs of types C and B (§ § 70 and 71) and in addition the provisions of this section shall apply.
(2) The surfaces of the floors and walls of rooms in which Type A workstations are designed shall not absorb liquids; they must be impermeable to liquid and therefore resistant. The rooms may only be accessible via changing rooms with showers.
(3) Rooms with workplaces of type A are to be ventilated continuously and appropriately artificially while maintaining a sufficient vacuum. In the case of spaces that are in communication with one another, the negative pressure must increase from spaces to lower spaces with greater risk of contamination. The negative pressure in the working chambers and working spaces must also be ensured in the event of a failure of the normal power supply. The air drawn off is to be diverted to the outside via filters whose effectiveness is to be tested periodically. Contaminated filter materials are to be disposed of as radioactive waste.
(4) In rooms with Type A workplaces, the air shall be tested at regular intervals and, moreover, in the case of contamination requirements; records shall be kept of the results of the measurements.
(5) Type A jobs shall also be monitored if necessary outside the operating period.
(6) protective clothing and protective equipment must be clearly marked in such a way as to indicate that they are intended for workplaces of Type A; they must not be worn outside the spaces belonging to the workplaces of Type A and are not intended to be covered by such equipment. shall be kept separately.
(7) In the case of works with a greater risk of an incorporation or contamination risk, respiratory protection devices or tightly closing protective suits equipped with respiratory protection must be worn.
(8) Persons working in protective suits must always be in optical and acoustic connection with another person.
Application of open radioactive substances in the environment
§ 73. (1) The use of open radioactive substances outside installations or facilities specially equipped for this purpose shall in any case be justified in accordance with § 2.
(2) The application shall in any case be carried out in such a way that the annual exposure of individuals to the population by irradiation from the outside and through any incidental incorporations by this application does not result in an effective dose of 0.3 millisievert exceeds. To the extent that this is necessary for reasons of radiation protection, the Authority shall set a lower dose limit.
Section 4
Disposal of radioactive substances
Discharge of liquid and gaseous radioactive substances
§ 74. (1) Where radioactive substances are discharged in liquid form with the operating water or in the form of aerosols, gases or vapours with the exhaust air from installations approved for radiation protection, the quantity of activity delivered shall be limited in such a way that: the annual exposure of individuals to the population on the basis of this derivation does not exceed an effective dose of 0.3 millisievert.
(2) In order to comply with the dose limit value of paragraph 1, the competent authority shall, in accordance with the state of the art, determine the emission limit values for the exposure path and for the place of stay, the residence period and the habits of life of a reference person are to be used to conservative parameters. In this connection, the Authority may assume that the exposure limit value of paragraph 1 is complied with, in any case, if the waste water and the exhaust air are in accordance with Appendix 12 shall not be exceeded in the annual average.
(3) Where this is necessary for reasons of radiation protection, the Authority shall establish a dose limit which is lower than that of paragraph 1. In setting such dose limits, the Authority shall, in particular, take care to ensure that the total dose limit laid down in paragraph 1 is not exceeded in the case of a number of exposure installations authorised for exposure to radiation exposure of the population.
(4) Records shall be kept of the radioactive substances emitted. These must be provided by the nuclide, the result of the activity determination, the date of delivery, the beginning and the end of the levy, the name and address of the person who carried out the measurement, and the name of the derivative. Include through.
(5) Radioactive substances shall be considered as such only up to the time of discharge.
Section 5
Radioactive waste
General provisions
§ 75. (1) Radioactive waste within the meaning of this Regulation shall be materials containing or contaminated by radioactive substances and originating in the management of radiation sources; and
1. |
which are no longer used or used in accordance with their intended purpose or in any other permitted manner, and which the owner or proprietor intends to dispose of or has been disposed of, or |
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2. |
their conditioning and proper storage as radioactive waste is offered in the public interest. |
(2) If radioactive waste is intended for discharge or release in accordance with § § 74 or 79, these shall be considered as radioactive waste only up to the time of this derivative or release.
(3) Taking into account the principles of waste prevention, the minimisation of waste volume and the recycling of radioactive substances
1. |
the authorization authority for the use of radioactive substances subject to authorisation in accordance with § § 6, 7 or 10 of the StrSchG, |
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2. |
the competent authority responsible for the location of the user of a type-approved device according to § § 19 or 20 StrSchG, which contains radioactive substances, |
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to submit a disposal concept for the authorization. |
(4) The disposal concept referred to in paragraph 3 shall contain at least the following information:
1. |
the nature and maximum quantity of the radioactive waste, in particular the indication of the nuclides, the expected activities and volumes per unit of time; |
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2. |
the type of disposal envisaged |
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a) |
by recycling, or |
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b) |
by derivation or release in accordance with § § 74 or 79 following a possible decay of the activity or |
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c) |
by means of a holding which is authorized for conditioning, storage and subsequent disposal, or |
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d) |
by a withdrawal from the manufacturer or supplier; |
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3. |
the procedure in the event of any operational setting or termination of the transfer with radioactive substances. |
(5) Rules governing the emission of pollutants to the environment shall remain unaffected.
Collection of radioactive waste, waste categories
§ 76. (1) Radioactive waste, unless it is delivered in accordance with § § 74 or 79, and provided that the body responsible for conditioning and intermediate storage until the subsequent disposal does not determine otherwise, shall be separated in accordance with the following categories: shall be collected and marked:
1. |
liquid-combustible; |
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2. |
liquid-non-combustible; |
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3. |
Fixed-combustible; |
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4. |
Fixed-non-combustible; |
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5. |
gaseous; |
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6. |
biogenic waste; |
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7. |
the radioactive substances which are surrounded by waste; |
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8. |
bulky wastes; |
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9. |
compound waste; |
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10. |
hazardous waste, in particular infectious material, pyrophoric material, explosive material, highly reactive material, substances that emit corrosive gases during storage or combustion, substances used in the storage of radionuclides in the gas phase . |
(2) Radioactive waste shall also be collected and marked separately in accordance with the following categories:
1. |
wastes containing radionuclides having half-life periods of less than 100 days, wherein impurities with longer-lived radionuclides may not exceed one tenth of the free-limit in accordance with Article 6 (1) Z 1 and 2, |
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2. |
wastes containing radionuclides having half-life periods of more than 100 days. |
The competent authority may, taking into account operational circumstances and local circumstances, authorise the separation and collection of radioactive waste in accordance with categories other than those specified in paragraphs 1 and 2.
(4) Radioactive waste containing alpha-radiators shall be separately collected, separately stored and marked.
(5) Where it is intended to release radioactive waste in accordance with Section 79, the authority responsible for granting such clearance may allow the collection and separation of such waste in accordance with the categories applicable to inactive waste. are carried out.
(6) The collection of radioactive waste is to be carried out on the basis of hazardous chemical reactions. If a release of radioactivity (e.g. due to corrosion of the containers) cannot be ruled out, periodic checks shall be carried out to the extent necessary.
(7) In rooms which are not exclusively used for storage, radioactive waste is to be collected in containers suitable for this purpose and exclusively for this purpose. The dose and dose benefit limits are to be complied with in accordance with § 54 (1). The collection containers shall be marked "RADIOACTIVE" by means of the radiation warning sign in accordance with Appendix 3.
Temporary storage of radioactive waste in establishments
§ 77. (1) The temporary storage of radioactive waste in establishments shall be understood as meaning:
1. |
their storage until they are delivered to a body approved by the authorities for re-use or to a body approved by the authorities for conditioning or recovery; |
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2. |
their storage until they are returned to the supplier, or |
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3. |
their storage up to the end of a period of activity determined by the competent authority in accordance with § § 74 or 79. |
(2) The temporary storage shall be carried out in lockable spaces intended for the purpose of storage only if the competent authority does not permit an exception. The provisions of § 54 (1) to (3) and (6) apply in respect of these rooms.
(3) Rooms for the storage of open radioactive materials must at least be fitted with a liquid-impermeable, easily decontaminatable floor. With regard to local conditions, the authority has to decide whether these rooms are to be constructed as separate fire sections and to what extent they have to be equipped with a washing facility for cleaning hands. Rooms for the storage of radioactive waste, which contain alpha-radiators, are in any case to be designed in a fire-resistant way.
(4) If, for reasons of radiation protection, the granting authority has the right to establish maximum periods for temporary storage in accordance with paragraphs 1 and 2 (1) and (2) of this Article.
Discharge of radioactive waste
§ 78. (1) Radioactive waste which is not derived in accordance with § 74 or released in accordance with § 79 shall be subject to an officially approved facility for re-use or re-use or to an officially approved facility for conditioning, Interim storage and subsequent disposal. They may also be returned to the manufacturer or the supplier of the radioactive substances, which in turn is contractually obliged to dispose of the radioactive substances in relation to the donor.
(2) Anyone who makes radioactive waste as referred to in paragraph 1 shall ensure that the accompanying documents required by the transport regulations in additional accompanying documents for each transport container are accompanied by information on nuclides, their activity and Waste category is included.
(3) In order to ensure the disposal of radioactively contaminated animal carcasses, the competent authority may conclude a civil agreement with an officially approved facility for the purpose of conditioning the authorisation holder. before open radioactive substances are allowed to be administered to animals.
Release
§ 79. (1) The competent authority must assume that the conditions for the approval of the release pursuant to Section 13a (2) of the StrSchG have been met, according to which only an effective dose of the order of 10 for individuals of the population shall be granted. Microsievert may occur in the calendar year if:
1. |
for an unrestricted release of |
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a) |
solid substances, compliance with the free values set out in Annex 1, Table 1, column 6, as well as those in Appendix 1 lit. A mentioned provisions and, where a solid surface is present, compliance with the values of surface contamination of Appendix 1, Table 1, column 5, |
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b) |
liquid substances, compliance with the values of Appendix 1, Table 1, column 6, |
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c) |
Building debris and soil excavation with an expected mass of more than 1000 tonnes in the calendar year of compliance with the free values set out in Table 1, Table 1, column 7, and compliance with the values set out in Appendix 1, lit. A and F, |
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d) |
Land surface compliance with the free values set out in Annex 1, Table 1, column 8, and the one in Appendix 1 lit. E mentioned provisions, |
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e) |
Buildings for re-use and re-use, compliance with the free values set out in Annex 1, Table 1, column 9, and compliance with the values set out in Appendix 1 lit. A and D, |
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2. |
for a limited release of |
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a) |
solid materials for disposal as inactive waste, compliance with the free values set out in Table 1, table 1, column 10, as well as those in Appendix 1 lit. A and C, and, where there is a solid surface, compliance with the values of surface contamination of Appendix 1, Table 1, column 5, |
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b) |
Buildings for demolitions are to comply with the free values set out in Table 1, Table 1, column 11, and compliance with the values set out in Appendix 1 lit. A and D, |
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c) |
Scrap metal for recycling shall comply with the free values set out in Table 1, Table 1, column 12, as well as the one in Appendix 1 lit. A and G, and, where a solid surface is present, compliance with the values of surface contamination of Appendix 1, Table 1, column 5, |
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is demonstrated. In the case of Z 2 lit. a must have no evidence that an effective dose of 10 microsieverts in the calendar year is exceeded at the site of the disposal facility for individuals of the population. |
(2) Insofar as the provisions of Appendix 1, as required pursuant to paragraph 1, have been laid down. C to E are not available on a case-by-case basis or for individual radionuclides no free values are established, for substances that do not exceed the free limits of Appendix 1, Table 1, column 3, the proof that for individuals of the population only an effective dose can occur in the order of 10 microsieverts in the calendar year, and may also be conducted in other appropriate ways.
(3) For each substance quantity or subset which is used as a non-active substance due to the release of the release, it is to be recovered, removed, possessed or passed on to third parties, the conformity with the Determine the prescriptions. The results of the free measurements required for this purpose shall be recorded and shall be kept for at least 7 years for inspection by the competent authorities.
(4) The competent authority shall determine the measures taken to comply with the requirements set out in paragraphs 1 and 2 and the determination referred to in paragraph 3 above.
(5) On request, the competent authority shall determine whether certain conditions of paragraphs 1 and 2 are met on individual questions on which the issue of the release is subject. These findings shall be based on the procedure for the approval of the release. The communication with which the release is granted shall contain these findings.
(6) If radioactive substances, including radioactive waste, are released, the markings in accordance with Appendix 3 shall be removed or permanently covered immediately before disposal.
Part 4
Radiation facilities
Section 1
Non-medical X-ray equipment
General provisions
§ 80. (1) Non-medical X-ray devices are stationary or spatially variable radiation devices which are used for the generation of X-rays and are not used in human, dental or veterinary medicine.
(2) X-ray equipment for non-medical use must be operated in radiation applications, provided that:
1. |
they are not a full protection body within the meaning of Section 83; or |
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2. |
this is not ruled out by the nature of the application. |
(3) For each X-ray facility, the accompanying documents must be made available on the occasion of placing on the market from the placing on the market and available for the entire service life. The accompanying documents shall include at least:
1. |
an instruction manual in German, which clearly describes the intended use of the service provider; |
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2. |
information on the technical data of the X-ray equipment required for the assessment of the radiation protection measures to be taken; |
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3. |
a description of instrument-specific radiation protection measures; |
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4. |
a maintenance manual. |
Requirements
§ 81. (1) In the case of X-ray equipment, provided that it is not the case in accordance with paragraph 2 or § 83, the tube protection housing shall ensure that during operation of the X-ray tube with nominal voltage and permanent current intensity when closed Radiation exit window the local dose rate at 1 meter distance from the focal spot does not exceed the following values:
1. |
2.5 millisieverts per hour for X-ray equipment with nominal voltages of up to 200 kilovolts; |
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2. |
10 millisieverts per hour for X-ray equipment with nominal voltages of more than 200 kilovolts; such devices must correspond to the requirement of Z 1 after downrules to tube voltages below 200 kilovolt. |
(2) In the case of X-ray equipment for crystallography, micro-radiography, X-ray spectral analysis or for similar applications, provided that the equipment is not in accordance with § 83, the tube protection case shall ensure that during the Operation of the X-ray tube with nominal voltage and permanent current intensity when the radiation exit window is closed, the dose rate of the emerging radiation does not exceed 50 centimetres from the focal spot 10 microsieverts per hour.
(3) In the case of X-ray equipment, if it is not the case in accordance with § 83, there must be possible connection possibilities for additional devices, such as door contacts, with which the high voltage is remote-operated during operation in radiation application areas. but it cannot be switched on again.
Operating rules
§ 82. (1) No persons shall be allowed to stay in radiation applications during the operation of the X-ray equipment.
(2) The following provisions shall apply to the operation of X-ray equipment outside of radiation applications, unless they are full-protection:
1. |
All persons have to stay sufficiently far from the X-ray tube and from scattering objects according to the optimization offer of § 3 (1); |
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2. |
The control area shall be demarcted, marked and monitored within the meaning of section 18 (1). In this area, only professionally exposed persons may be present and only as long as this is necessary for compelling reasons; likewise, any areas with absolute prohibition of access must be identified and monitored; |
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3. |
in the case of work carried out in control areas, the necessary protective layers must be present between the object and the workers; |
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4. |
the X-ray equipment shall not be put into operation until all preparatory work has been completed; |
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5. |
for the control of radiation protection measures, appropriate measuring instruments must be available; in the case of the operation of non-medical X-ray equipment in the context of non-destructive testing, warning dosimeters shall be borne by the operating personnel; |
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6. |
the cross-section of the useful beam shall be limited by appropriate insertion to the extent strictly necessary for the application; |
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7. |
the exposure time shall be kept as short as possible by the use of suitable image receivers; |
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8. |
all necessary precautions for the protection of the general population must be taken; |
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9. |
in so far as the X-ray equipment is used for the transmission of transport vehicles and their cargo, in particular with regard to contraband, appropriate measures shall be taken to ensure that no persons shall be present in the Irradiated area. |
(3) appropriate technical standards may be used for the determination of the necessary shielding.
(4) The duty cycle shall be documented and the competent authority may prescribe the affixing of an operating hour counter.
Specific provisions for full protection institutions
§ 83. (1) Full protection devices are X-ray equipment in which the protective housing, in addition to the tube, also completely encloses the object to be examined or the object to be treated, and the shielding of which ensures that in 10 centimetres The distance from the outer surface of the protective housing 3 microsieverts per hour is not exceeded.
(2) In the case of full protection devices, it must be ensured that the X-ray tube or the X-ray source can only be operated when the protective housing is closed, or that in the case of examination procedures which have a continuous operation, the X-ray radiators require that the protective housing-which is operated during the X-ray source-can only be opened when the radiation exit window of the X-ray source is closed, and in this case microsieverts per hour are not available in the interior of the protective housing 3. shall be exceeded.
(3) In justified cases, the Authority may also authorise X-ray equipment as a full protection facility which exceeds the limit values set out in paragraphs 1 and 2 by no more than 1,5 times.
Section 2
Particle accelerators for non-medical applications
General provisions
§ 84. (1) Particle accelerators within the meaning of the following provisions are radiation devices which are used for the generation of medium-and high-energy beams by acceleration of particles and are used in the non-medical field.
(2) Particle accelerators are basically to be operated in radiation applications. If this is ruled out by the nature of the application provided, the Authority may allow exceptions to this, provided that the equipment is equipped with fixed radiation sources which absorb the useful radiation to a sufficient extent.
(3) Particle accelerators shall be provided with a nameplate on which clearly the name or mark of the manufacturer or supplier, the manufacturing number, and the maximum dose rate of the X-ray, electron or other Particle radiation in the central beam of the useful beam bundle must be indicated at a certain distance from the beam exit window. In addition to the original documents, from the manufacturer or supplier
1. |
a sufficient extract from the operating instructions for the safe operation, |
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2. |
information on the technical data of the particle accelerator required for the assessment of the radiation protection measures to be taken, and |
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3. |
a description of instrument-specific radiation protection measures; |
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in the German language. |
Requirements
§ 85. (1) In the case of X-radiation operation, the primary X-ray radiation in the part shielded by the radiation limiting means shall be so weakened that the dose rate in the shielded area is two per cent of the dose rate in the screened area. The axis of the useful beam does not exceed the normal irradiation distance at the same distance from the divergence point of the useful beam of rays.
(2) In the case of the operation of particle accelerators, activation processes and, as a result, the occurrence of artificially generated radioactive substances are to be expected, corresponding protective measures should be provided.
(3) Particle accelerators must be equipped with operating devices,
1. |
which can be spatially separated from the accelerators; |
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2. |
with which the total duration of irradiation can be adjusted and where this value remains displayed during irradiation; and |
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3. |
which automatically switch off the radiation after the set duration of irradiation has expired. |
(4) If a particle accelerator has a plurality of operating devices, they must be mutually locked in such a way that the switching on is only possible from one location.
(5) The beam operation must be able to be prevented at any time by manual operation (e.g. emergency stop) as well as automatically terminated under certain conditions, for example when opening the doors of the radiation application space. The continuation of the irradiation may only be possible from the operating device and only after the elimination of the switch-off condition.
(6) It is necessary to indicate to the operating device whether the particle accelerator is switched on and whether radiation is emitted. The device must have appropriate connections, which allow the display to be displayed at spatially separated points, whether the particle accelerator emits radiation.
Operating rules
§ 86. (1) There shall be no persons in the radiation application space during the irradiation.
(2) The provisions of Section 82 (2) shall apply mutas to the operation of particle accelerators outside of radiation applications.
(3) The operating hours shall be documented and the competent authority may prescribe the affixing of an operating hour counter.
Part 5
Research reactors
General provisions
§ 87. (1) Research reactors are installations which serve scientific research or training in which fissile material is treated in a quantity and manner in such a way that a chain reaction takes place. They are mainly used as neutron sources and for the production of artificial radioactive substances.
(2) The technical management of research reactors may only be entrusted to persons who, from the point of view of radiation protection, possess the expertise required for the operation of the research reactor.
(3) If, in addition to the radiation protection officer, other persons are entrusted with the perception of radiation protection, these are to be grouped together in a radiation protection department under the direction of the radiation protection officer. This division must be available to assist staff and technical equipment and equipment in the extent necessary for the performance of their duties.
Operational and behavioural rules
§ 88. (1) For each research reactor, general operational and behavioural rules shall be drawn up in writing by the technical management, in agreement with the persons responsible for the exercise of radiation protection, who shall have at least those provisions: during and after carrying out work on safety and protection measures to be taken and the standards of conduct to be observed, as well as the way in which operating disturbances, incidents or radiation accidents are carried out.
(2) The general operating and behavioural rules must be shown to be brought to the attention of a research reactor before commensurate with the activities of a research reactor and to be placed or proposed in the establishment at appropriate places.
(3) Special operational and behavioural requirements should be drawn up in agreement with the persons responsible for the exercise of radiation protection, in order to ensure that the persons concerned can be identified before the start of the work. are to be followed.
Security measures
§ 89. (1) In research reactors, arrangements must be made in terms of personnel and material to minimise their effects in the event of incidents or accidents occurring.
(2) provisions within the meaning of paragraph 1, the extent of which results from the size and nature of a research reactor, are in particular technical safety and protective equipment, alarm and reporting systems, the provision of operational staff, First aid equipment, work equipment and protective equipment, as well as suitable measuring equipment. The functioning of these facilities and the availability of the staff shall be reviewed at regular intervals.
(3) In the event of incidents or accidents, the procedure shall be governed by an emergency plan which shall be subject to approval by the Authority. The emergency plan shall, in particular, include provisions on alert, notifications, technical measures to prevent the extension of the consequences of incidents or radiation accidents, measurement of the radiation level, demarcation and identification of the area the risk of radiation, the use of operational staff, measures for first-aid performance, localisation of the damage caused, decontamination, proof-of-evidence, determination of collection places for the employees in and outside the country of the reactor building, accommodation of persons in To include hospitals and the request for extra-operational assistance.
(4) In the case of a research reactor, the contingency plan must be brought to the attention of the extent to which it is required to carry out its activities in the extent necessary to that effect. The time intervals to be determined by the Authority shall be subject to the holding of emergency exercises to keep records of the course and the success of such exercises.
Recording and reporting obligations
§ 90. (1) Each research reactor shall keep records which are relevant for the assessment of the safety of the operation from the point of view of radiation protection. The records shall also contain those data necessary for the reconstruction of the causes and the flow of incidents or accidents. Records shall be kept for at least 30 years and shall be submitted, at the request of the authority, to the authority appointed for the purposes of the protection of workers and to the competent institution of the accident insurance.
(2) incidents and radiation accidents must be reported without delay. The notification shall contain the information necessary for the assessment of the situation, such as deficiencies, local dose rate, concentration of radioactivity in the environment, meteorological data and persons affected.
(3) In the event of incidents or accidents, a written report shall be submitted, which shall in particular provide information on the causes, the sequence, the consequences and the measures taken.
(4) Each initial operational critical of a research reactor within the framework of an approved amended performance shall be reported at least 6 weeks in advance; changes in dates shall be announced immediately.
(5) Reports and reports pursuant to para. 2 to 4 shall be reimbursed to the authorization authority and to the authority appointed for the performance of the protection of workers. Notifications pursuant to paragraph 2 shall also be reimbursed to the district administrative authority if there is an impact on areas outside the facility.
Changes in the scope of the Regulation
§ 91. (1) The documents to be included in the application for the grant of the authorisation to implement the implementing measures in the context of a change in the scope of a research reactor pursuant to Section 5 (5) of the StrSchG have at least to contain:
1. |
a description of the proposed changes to the research reactor together with the associated plans; |
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2. |
information on the intended change in use of the research reactor; |
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3. |
the provisional amendments to the safety report; |
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4. |
the announcement of any modified ownership and ownership of the premises adjacent to the site; |
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5. |
the notification of the plan verfishers, the undertakings provided for the changes to the research reactor and for the supply of new or modified parts of the investment in safety terms, and the nature of the verification of such assets; |
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6. |
Publication of the timetable for the implementation of the implementation measures in the context of the change of the research reactor. |
(2) The provisional amendments to the safety report referred to in paragraph 1 Z 3 must contain at least:
1. |
a detailed description of the proposed changes to the research reactor, with particular regard to the modified or new investment parts and systems which are relevant to the safety of the research reactor; |
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2. |
the interpretation of the amended installation and its parts, including any amended security criteria, including a presentation of the manner in which it will be complied with; |
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3. |
adaptations of the safety analyses for normal and abnormal operating conditions in relation to the changes to the installation; |
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4. |
information on the modified safety specifications in relation to the changes to the installation; |
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5. |
a quality control programme for the production of modified and new parts and systems of safety engineering, as well as for the establishment of measures in the context of the modification of the plant; |
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6. |
Information on the organisation of personnel during the implementation of the change. |
(3) The provisional amendments to the safety report must also provide that, when the project is drawn up, the safety criteria relating to the planned changes to the research reactor have been carefully analysed and for which the safety criteria for the project are to be assessed. protection of the life or health of people, including their progeny, is adequately taken into account.
The Authority shall also prescribe, in the communication with which the implementation of the implementation measures is authorised in the course of a change in the scope of a research reactor, the manner in which it is carried out during the implementation of the In the context of the proposed amendment, the measures to be taken to monitor whether the research reactor will be amended in accordance with the legislation and the modest prescriptions will be carried out.
(5) The documents to be included in the application for the granting of the change in the scope of the operating licence pursuant to Section 6 (5) of the StrSchG shall have at least the final amendments to the security report, in which the information provided by the provisional Safety report on the completion of the measures taken in the course of the changes to the research reactor and indicated, such as the legislation and the conditions and conditions of the authorization to carry out the Measures taken within the framework of the approved amendment have been complied with and, as amended, the amended version Research reactor is to be operated.
(6) The amendments to the final safety report shall include in particular:
1. |
the adaptation of the implementation of the security criteria, as a result of the changes made; |
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2. |
Adaptation of safety analyses for normal and abnormal operating conditions as a result of the changes made; |
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3. |
information on the modified safety specifications in relation to the changes to the installation; |
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4. |
the results of the quality checks referred to in paragraph 2 (5); |
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5. |
the personnel organisation, as amended, for the changed operation of the installation and the qualification of the existing staff, in particular with regard to changes in safety technology and radiation protection measures; |
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6. |
the programme for the commissioning of the plant after the completion of the changes; |
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7. |
the principles applicable to the adaptation of the operating rules, as amended. |
(7) The Authority shall also prescribe in the communication that the change in the scope of the operating licence is granted that the modified research reactor shall not take place until after the establishment of the adaptation of the general operating and behavioural rules shall be put into operation in accordance with § 88 and after the emergency plan approved by the Authority has been approved in accordance with section 89 (3).
Part 6
Central radiation protection registers
Central dose register
§ 92. (1) The Central Dose Register shall be subject to the following tasks:
1. |
Collection, storage and processing as well as long-term archiving of data from physical control and medical examinations; |
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2. |
Identification of dose overshoots when a professionally exposed person is dosimetrically monitored at several workplaces; |
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3. |
Exchange of information to authorities, other institutions as well as persons exposed to radiation in the sense of § 35a (1) sentence 3 and 4 of the StrSchG; |
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4. |
Provision of data for statistical evaluations for national and international purposes. |
(2) From 1. The following data are to be transmitted to the Central Dose Register in January 2006:
1. |
the results of the physical check referred to in Article 27 (3) of the authorized dose measurement points in the scope of the in Appendix 5 lit. A and B, |
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2. |
by authorised doctors, occupational health services and hospitals, the health assessments pursuant to section 37 (3) of the scope of Annex 5 lit. A and C |
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3. |
the holder of the authorization shall be the result of the verification of the dose values in accordance with § 28 (5) and the information relating to the management of radiation protection passports in accordance with § 49, |
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4. |
the replacement doses fixed in accordance with Article 10 (2) shall be drawn up by the competent authority. |
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The data shall be transmitted to the Central Dose Register within four weeks of the date of their survey; in the case of exceedances of the maximum authorised doses and in the event of accidental exposure or emergency exposure, the transmission shall, on the other hand, be without delay. |
(3) All data shall, as far as possible, be transmitted in electronic form to the Central Dose Register using interfaces provided by the Central Dose Register. For conventional transmission, the forms specified by the Central Dose Register for this purpose can be used for conventional transmission.
(4) Exceedances of maximum doses permitted in accordance with § 12 shall be notified without delay by the Central Dose Register to the competent authority and to the authority appointed for the purposes of the protection of workers.
(5) The data from physical control collected at the authorised dose-measuring points by 31 December 2005 shall be available to the Central Dose Register by 31 December 2008.
Central radiation sources-register
§ 93. (1) The collection and storage of data on radioactive substances present in Austria, including source-free radiation sources and radioactively contaminated material within the meaning of § 61, shall be the responsibility of the Central Radiation Sources Register.
(2) From 1. The following data are to be transmitted to the Central Radiation Source Register in January 2006:
1. |
by the holder of the authorization, the annual activity balances pursuant to § 59 (4) and the reports on highly radioactive sources of radiation in accordance with § 64 (8), |
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2. |
Reports by the competent authority on the discovery of radioactive substances in accordance with Section 26 (1) of the StrSchG and of radioactively contaminated material in accordance with Section 61 (4). |
(3) The competent authorities of those States which were the starting point of a delivery subject to a notification in accordance with Section 61 (4) shall be informed of the incident by the Central Radiation Source Register.
(4) The competent Austrian authorities shall be granted access to the reading of the data stored in the Central Radiation Sources Register to the extent of their local competence. Foreign authorities shall provide the Central Radiation Source Register with information on the fulfilment of their obligations on the basis of a reasoned written request. To the extent that Austria has entered into international commitments in connection with the collection of radiation sources, the necessary information shall also be exchanged with these bodies to the extent necessary.
Central Incident Register
§ 94. (1) The holder of the authorization shall submit a report to the Central Accident Register at the Federal Minister for Agriculture, Forestry, Environment and Water Management concerning incidents no later than four weeks after the occurrence of the event. The report shall contain detailed information on the causes and expiry of the incident, information on any exposure of employees or third parties, contamination of the premises or areas of non-business, information on: the measures taken and information on preventive measures to prevent the recurrence of such an accident. Information that is only available later will be immediately available.
(2) These data are to be anonymized and made available to interested persons in a suitable form.
Part 7
Final provisions
Transitional provisions
§ 95. (1) Those who are appointed as radiation protection officers or other persons responsible for the exercise of radiation protection at the time of entry into force of this Regulation shall be subject to proof of this activity in the amount previously exercised by the person concerned. a radiation protection training within the meaning of § § 41 to 43. With regard to the training referred to in Appendix 8, the first proof shall be up to 1. January 2011.
(2) Those who are authorized to carry out the investigations pursuant to § § 30, 31 and 33 of the StrSchG at the time of entry into force of this Regulation in accordance with § 35 of the German StrSchG (StrSchG) shall, in respect of this activity, be subject to the evidence of a previously exercised Training in accordance with § 37 (1) liberated. With regard to the training referred to in Appendix 7, the first proof shall be up to 1. Jänner 2010.
(3) Non-medical radiation sources whose operation is legally approved in accordance with § § 6, 7 or 10 StrSchG or whose design has been approved in accordance with § § 19 or 20 StrSchG may continue to be operated until 31 December 2009, provided that they are Requirements of the Radiation Protection Ordinance 1972, BGBl. No. 47/1972. After that period, these facilities shall comply with the requirements of this Regulation for a further operation.
(4) The use of radiation sources legally granted in accordance with § § 6, 7 or 10 of the StrSchG, for which radiation applications are required in accordance with § § 22, 54 (3) and 69 Radiation application spaces, storage rooms for radioactive substances or workplaces of types A, B or C , in rooms which do not comply with the provisions of this Regulation in respect of the local dose levels outside these premises in accordance with Annex 4, until 31 December 2006, provided that the provisions of the Radiation Protection Regulation are complied with in 1972 . Storage facilities according to § 54 (1) as well as protective containers according to § § 55 (2) and 65 (2), which do not comply with the provisions of the Radiation Protection Ordinance 1972 but do not comply with the provisions of this Regulation, may be held until 31 December 2006. continue to be used.
(5) Those who, at the time of entry into force of this Regulation, have a final approval pursuant to § § 6, 7 or 10 StrSchG or for a device containing radioactive substances, via a legally binding type approval pursuant to § § 19 or 20 StrSchG or in accordance with § 20 of the StrSchG type-approved device containing radioactive substances, the disposal concept shall be submitted to the competent authority in accordance with Section 75 (3) and (4) until 31 December 2008.
(6) By way of derogation from § 9, the measured variables listed in Appendix 2 shall be no later than 1. Use January 2008 for measurements of personal dose, local dose and local dose rate. This shall be without prejudice to the measurement of the local dose or the local dose rate, using other measures other than those referred to in Appendix 2, to carry out a conversion to the measures referred to in Appendix 2, if these measurements are used to demonstrate that the Dose limits according to § § 12 to 14 shall not be exceeded.
(7) Personal dosimeters issued by authorised dose measuring points for individual monitoring of external radiation in accordance with § 25 shall not be required at the latest by the time of 1. Jänner 2008 the one in Appendix 2 lit. E mentioned operational variables. All other persons dosimeters and all local dosimeters, which indicate other sizes, may be used indefinitely if they were first served before 1 July 2006.
(8) At the time of entry into force of this Regulation, the validity of radiation protection passes shall remain valid until the period of validity of the radiation protection pass has expired or the passport does not have sufficient room for further entries. , but at the latest by 31 December 2006.
In-force pedals
§ 96. (1) This Regulation shall enter into force on the first day of the month following that of the event.
(2) With the entry into force of this Regulation, the Radiation Protection Regulation (BGBl) shall enter into force. No. 47/1972, except for force.
Pröll Bartenstein Gorbach Gehrer Rauch-Kallat