Change Of The General Regulation Of Radiation Protection

Original Language Title: Änderung der Allgemeinen Strahlenschutzverordnung

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76. Regulation of the Federal Minister for agriculture and forestry, environment and water management, the Federal Minister of health, the Federal Minister for transport, innovation and technology, the Federal Minister of economy, family and youth, as well as of the Federal Minister for science and research, which modifies the General radiation protection Ordinance

On the basis of sections 10a, paragraph 2, 13 para 1, 13a para of 3, 17 para of 2, 19, paragraph 1, 20 para of 1, 23 para 1 and 2, 25 par. 4 Z 1, 26 para of 5, 32 paragraph of 6, 34 para 7, 35e, 35f para 5, 36 para 1 and 3 as well as 36 b paragraph 1 Radiation Protection Act, Federal Law Gazette No 227/1969, as last amended by Federal Law Gazette I no. 13/2006 and the Federal Ministry of law 2009 , Federal Law Gazette I no. is 3/2009,.



1 insofar as businesses, the GewO 1994, BGBl. No. 194/1994, subject, by the Federal Ministry of economy, family and youth in agreement with the Federal Minister of agriculture and forestry, environment and water management, 2nd in terms of railway, road, air and maritime transport and the protection of workers for businesses that no. 650/1994, subject to the Federal Act on the transport Labour Inspectorate (REBRA 1994), BGBl. , by the Federal Minister for transport, innovation and technology in agreement with the Federal Minister of agriculture and forestry, environment and water management, 3. with regard to the nuclear reactors and accelerator in the area of the universities and the research institutions of the Austrian Academy of Sciences, the Federal Minister for science and research in consultation with the Federal Minister of agriculture and forestry, environment and water management, 4. with regard to those requirements of §§ 35 and 36 StrSchG that affect the Affairs of the Arcade with sources in the field of medicine, from the Federal Minister of health, 5.
              Otherwise prescribed by the Federal Ministry of agriculture and forestry, environment and water management: the General radiation protection Ordinance, Federal Law Gazette II No. 191/2006, is amended as follows:

1. the table of contents is as follows:



Table of contents







Clause





Subject / title







1 part general provisions







1 section principles, scope of application







§ 1.





Scope of application







§ 2.





Justification







§ 3.





Optimization







2. cut out requirements for the safe use of radiation sources







§ 4.





Security analysis, fault analysis, emergency planning







§ 5.





Nuclear safety of nuclear installations







3. cut down exemptions from the authorisation and registration, type approvals







§ 6.





Exemptions from the permit requirement







§ 7.





Exceptions to the obligation to report







§ 8.





Type approvals







2 part protection of life and health







1 section General protections







§ 9.





Determination of the dose







§ 10.





Dose of ionising radiation







§ 11.





Categories of persons occupationally exposed to radiation







§ 12.





Maximum permissible dose for occupationally exposed persons







§ 13.





Specially authorized exposures







§ 14.





Maximum permissible dose for individuals of the population







§ 15.





Responsibility of the holder of the authorization







§ 16.





Radiation protection instructions and work instructions







2. section blasting areas







§ 17.





Blasting area, controlling, and monitoring area







§ 18.





Requirements for control and monitoring areas







§ 19.





Access by persons not occupationally exposed to radiation radiation areas







§ 20.





Workplace persons of category B in blasting areas







§ 21.





Access to official institutions and qualified experts







section 22.





Radiation treatment rooms







section 23.





Personal protective equipment







§ 24.





Radioactivity monitoring of the environment







3. section physical control







§ 25.





Personal dosimetry







section 26.





Intake monitoring







§ 27.





Evaluation of the dosimetric measurements







section 28.





Determination of Effektivdosis and the equivalent dose







section 29.





Monitoring of work places







section 30.





Measuring instruments







§ 31.





Records







4 section medical examinations







§ 32.





Suitability investigation







§ 33.





Check-up







§ 34.





Sofortuntersuchung







section 35.





Final examination







section 36.





Medical certificate







section 37.





Authorized doctors







section 38.





Duties of the holder of the authorization







§ 39.





Settlement of medical radiation protection surveys







5 article persons entrusted with the perception of radiation protection







section 40.





Obligations and rights







section 41.





Education and training in the medical field







§ 42.





Education and training in the non-medical area







§ 43.





Education and training in the field of research reactors







§ 43a.





Recognition of training







6 article protection of external workers, radiation protection password







§ 44.





Obligations of the holder of the authorization of an external company







§ 45.





Obligations of the holder of the authorization in its control panel, external workers will be working







§ 46.





Obligations of external labor







§ 47.





Content and form of the passport of radiation protection







section 48.





Exhibition, registration and evident attitude of the radiation passes







paragraph 49.





Management of radiation safety passport







§ 50.





Special rules for certain professions







3. part of radioactive substances







1 article General provisions







§ 51.





Scope of application







§ 52.





Open and sealed radioactive materials







section 53.





Labelling of radioactive substances







§ 54.





Storage facilities







Article 55.





Carriage of radioactive substances within plants







Article 56.





Cleaning and repair work







§ 57.





Contamination







section 58.





Decontamination







section 59.





Recording and reporting obligations







section 60.





Notifiable transboundary movement of radioactive waste







section 61.





Radioactive substances in or radioactive contamination of materials that are designed for the recycling and usage







2. section sealed radioactive materials







§ 62.





Texture







section 63.





Leak test







section 64.





Highly radioactive sources







section 65.





Non-medical application of sealed radioactive materials







§ 66.





Operating rules







3. section open radioactive substances







section 67.





Handling open radioactive substances







section 68.





Protection against contamination







section 69.





Workstation types







Article 70.





Jobs of the type C







§ 71.





Jobs of the type B







section 72.





Jobs of type A







Article 73.





Application of open radioactive substances into the environment







4. cut off disposal of radioactive waste







section 74.





Liquid and gaseous radioactive waste







5. section radioactive waste







§ 75.





General terms and conditions







section 76.





Collection of radioactive waste, waste categories







§ 77.






Temporary storage of radioactive waste in plants







§ 78.





Delivery of radioactive waste







section 79.





Release







4. part of radiation facilities







1. section Nichtmedizinische X-ray equipment







section 80.





General terms and conditions







Article 81.





Requirements







Article 82.





Operating rules







section 83.





Special provisions for full protection facilities







2. section particle accelerator for non-medical use







§ 84.





General terms and conditions







§ 85.





Requirements







§ 86.





Operating rules







5. part research reactors







section 87.





General terms and conditions







§ 88.





Construction of research reactors







§ 89.





Operating organization







§ 89a.





Nuclear safety







§ 89 b.





Commissioner for nuclear safety







§ 89c.





Operating rules







Article 90.





Recording and reporting requirements







section 91.





Decommissioning concept







§ 91a.





Decommissioning







6. part central register of radiation protection







section 92.





Central dose register







Article 93.





Central Register of radioactive sources







§ 94.





Central Register of incident







7 final provisions part







section 95.





Transitional provisions







§ 96.





In force





2. the point is Z 4 at the end of section 1 subsection 2 by the word 'and' replaced and added following Z 5:



"5. the nuclear installations concerning nuclear safety requirements."

3. paragraph 1 para 3:

"(3) by this regulation, the following guidelines be implemented into Austrian law:"



1. Directive 96/29/EURATOM laying down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionising radiations, OJ No. L 159 of the 29.06.1996 p. 1, as amended by the amending OJ L 314 of the 04.12.1996 p. 20, 2. Directive 90/641/EURATOM on the protection of external workers, are exposed to an exposure to ionizing radiation for use in the Control Panel, OJ No. L 349 of the 13.12.1990 p. 21, 3. Directive 2003/122/EURATOM on the control of high-activity sealed radioactive sources and orphan sources, OJ No. L 346 of 31.12.2003 S. 57, 4. directive 2009/71/EURATOM on a Community framework for the nuclear safety of nuclear installations, OJ "No. L 172 of 2009 S. 18."

4. the heading 1 part 2 section is: "Requirements for the safe handling of radioactive sources".

5. paragraph 5 including heading:

"Nuclear safety of nuclear installations

§ 5 (1) to ensure of the safety of nuclear installations has to comply with the requirements laid down in the 5th part of this regulation the grant seekers in the course of construction, as well as the holder of the authorization for operation and decommissioning of such a plant.

(2) nuclear installations within the meaning of this regulation are, if necessary, together with an interim storage facility for spent nuclear fuel and radioactive waste on the site of the plant. research reactors "

6 paragraph 6 including heading:

"Exemptions from the permit requirement

Pursuant to § 13 para 1 are StrSchG § 6 (1) of the approval in accordance with sections 7 or 10 StrSchG except:



1. the handling of radioactive substances, whose activity is the allowances in accordance with Appendix 1 table 1 column 2 or whose specific activity the allowances in accordance with Appendix 1 table 1 column 3 does not exceed;

2. the handling of radioactive substances, which in table 1 of annex 1 not stated or for which there no allowances laid down provided that their activity or specific activity does not exceed the following values: a) for alpha emitters or radionuclides that decay by spontaneous fission: 103 becquerel or 1 becquerel per gram, b) for beta and gamma emitters, if not under lit. (c) are called: 105 becquerel or 102 becquerel per gram, c) for electron capture spotlight and beta emitter with a maximum beta energy by 0.2 Megaelektronenvolt: 108 becquerel or 105 becquerel per gram.

3. the handling of multiple radioactive substances, provided that the sum of the ratios of the activity or the specific activity of each individual substance and the corresponding allowance pursuant to Nos. 1 and 2 is less than or equal to one;

4. dealing with noble gases from the air, as long as the isotope ratio is similar to that in the gas in the air;

5. dealing with radiation sources, their Bauart was admitted to StrSchG according to § 19;

6. the operation of radiation facilities, which are non-ionizing radiation producing their operation one but parasitically occurs when such, provided that the dose rate is not more than 1 micro sievert per hour in 0.1 metres distance from the accessible surface of the device.

(2) the exceptions referred to in paragraph 1 No. 1 to 3 shall not apply for



1. the deliberate addition of radioactive substances in the production of medicines, as well as the placing on the market of such products;

2. the deliberate addition of radioactive substances in the production of consumer goods, as well as the placing on the market of such products;

"3. the deliberate administration of radioactive substances to persons and, if the radiation of people is concerned, animals for the purpose of medical or veterinary diagnosis, treatment or research."

7 paragraph 7 subsection 1:

"(1) in accordance with § 25 para 4 Z 1 StrSchG require any message:"



1. the handling of radioactive substances, except is Z 1 to 4 from the permit requirement referred to in article 6, paragraph 1;

2. the use of radiation sources, their Bauart, approved StrSchG according to § 19 if a notification is not due to the pattern approval;

3. the operation of cathode ray tubes for representing particular images or of radiation facilities, operated with a voltage of not more than 30 kV, provided that the dose rate is not more than 1 micro sievert per hour in 0.1 metres distance from the accessible surface of the device."

8. in article 8, the sales designation (1) and paragraph 2 and 3 are eliminated.

9 § 9 including heading is as follows:

"Determination of the dose

§ 9. The determination of the dose has to be specified and basis of calculation in annex 2 and annex 6."

10 § 10 para 1 second sentence reads:

"Exposures that do not result from a dealing with sources in the sense of § 2 para 45 StrSchG, are to make in determining the dose out."

11. in article 10, paragraph 1, third sentence is replaced the phrase "In particular exposures are" by the phrase "expositions are to leave as well disregard".

12 paragraph 10 section 2:

"(2) the competent authority may lay down a replacement dose when measuring or justified doubts about the authenticity of the dose value. She's the holder of the authorization to communicate the set value the Central dose register as well as the dose-measuring point. Replacement doses are as such."

13 section 11 including heading is as follows:

"Categories of persons occupationally exposed to radiation

§ 11 (1) for control and monitoring purposes is distinguished between two categories of occupationally exposed persons:



1. category A: occupationally exposed persons, expected to go out is that they can get a higher effective dose than 6 milliSievert, or a higher dose than 45 milliSievert equivalent within the framework of their professional activity over a period of 12 consecutive months for the lens of the eye or 150 milliSievert for the skin or the hands, forearms, feet and ankles.

2. category B: occupationally exposed persons who are not class A.

The equivalent dose for the skin called applies to the average dose to any surface of 1 cm2 regardless of the area exposed.

(2) the classification of the occupationally exposed persons in categories A or B is to make StrSchG in the case of activities subject to approval by the competent authority as part of the approval process or an upright radiation protection regulatory approval within the framework of the next review in accordance with article 17.

(3) in the case of this classification are in particular the nature of the arcade usually occur expositions and the specific situation into account. Little likely exposure scenarios and exposure caused by gross negligence or wilful conduct, are out.

(4) the permit holder has any information required in addition to the classification, especially about the individual activities and stay durations in blasting areas, at the request of the authority available to.


(5) the holder of an authorization, intends to perform actions not subject to authorisation in blasting areas by workplace parties, that may require a classification of the individuals in the category B, he has the authority to request such a classification by presenting all the information necessary for assessing dose. The Authority grants this request, she administrative decision to determine that the planned activity must be carried out by persons of category B. The authority is however argued that



1 a classification in category A would be required, so she has the request noting that apply are the provisions for external workers be dismissed;

2. no classification as occupationally exposed person is required, so she has to determine this administrative decision.

(6) is for professionally exposed persons of category B exceeding Z 1 set values detected in paragraph 1, the holder of the authorization has to notify the competent authority immediately, to clarify the causes and, if possible, to put corrective measures.

(7) If no corrective measures can be used, the competent authority shall check the concerned dealing on its justification. This dealing despite potentially higher doses remains justified, only professionally exposed persons of category A may be involved."

14. in article 12, paragraph 2, the phrase "from 50 milliSievert" is replaced by the phrase "of up to 50 milliSievert".

15 paragraph 4 deleted § 12.

16. in article 15, paragraph 1, the word order - with regard to subpara 1 of also the permit recruiters - is eliminated.

17 § 15 para 1 subpara 1 is:



"1. to ensure of the proper operation of the equipment and apparatus;"

18. in article 16, paragraph 1, the phrase "such as to incidents or accidents" is replaced by the phrase "such as the introduction of new processes or after incidents".

19 paragraph 16 paragraph 3:

"(3) the permit holder has to create written work instructions corresponding to the radiation risks of the respective activity has been shown to explain the persons concerned to provide, and to ensure that those affected have understood the instructions. The work instructions must include in particular also for the activity of necessary precautionary and protective measures."

20 paragraph 17 section 4:

"(4) areas, which operate exclusively radiation facilities, are only during operation of this equipment radiation areas. Activation products, generated during operation but the affected areas remain even after blasting areas, until the activation products are gone as far, that they be accepted from point of view of radiation protection aside."

21 paragraph 19 including heading:

"Access by persons not occupationally exposed to radiation radiation areas

Regulations in written form are section 19 (1) for the entry of persons not occupationally exposed to radiation to blasting areas by the holder of the authorization to meet. This, in particular the type and content of any teachings for persons occurring to and the nature and extent of any access controls are set. It is also making an assessment of the associated boxes. These access rules and dose assessments shall be provided at the request of the authority.

(2) an effective dose by more than 10 micro sievert is a such access or to expect an effective dose by more than 100 micro sievert per year, as a result of multiple access appropriate records to emerge from where also the actually encountered cans are in. These records are kept for at least 7 years and to submit at the request of the authority.

(3) the provisions of paragraphs 1 and 2 do not apply to medical exposure and helping people in the medical radiation protection regulation."

22 paragraph 20 including heading:

"Non persons of category B in blasting areas

Section 20 (1) perform non occupationally exposed persons of category B in a radiation field, has a holder of the responsible for the blasting area authorization for it to make sure that these people get the same protection as members. This is true both for subject to approval for actions not subject to approval.

(2) if the activity of outside persons on the basis of in-House approval carried or is an activity not subject to authorization, the holder of the authorization referred to in paragraph 1 has in particular before making a radiation protection training of such persons in accordance with article 16 and in accordance with § 25 and, if necessary, to determine their exposure through a personal dosimetry a monitoring of incorporation in accordance with section 26.

(3) the activity of outside persons but not on the basis of in-house, but a separate radiation protection regulatory approval is carried, may be waived by an instruction and an exposure determination in accordance with paragraph 2. Prerequisite for this is that possible exposure can arise only because of the immediate occupation of outside people."

23 paragraph 25 paragraph 8:

"(8) the permit holder has the particulars given in Appendix 5 of the dose-measuring points lit. To convey (A) in the current form. In the case of accidental exposure has to provide all the information necessary for the dose determination. the holder of the authorization of the dose measurement point"

24 paragraph 26 paragraph 7:

"(7) the permit holder has the particulars given in Appendix 5 of the dose-measuring points lit. To submit A and D in the current form. In the case of accidental exposure has to provide all the information necessary for the dose determination. the holder of the authorization of the dose measurement point"

25 paragraph 28 para 2 to 4:

"(2) evaluates to an exceeding of dose values referred to in paragraph 1, can malfunction of face down or a faulty evaluation be excluded, the dose-measuring point has to notify the holder of the authorization and the Central dose register it immediately. Malfunction or incorrect evaluation, the competent authority is to communicate, which then set a replacement dose within the meaning of § 10 para 2 has.

(3) can be excluded to a malfunction or failure analysis, has to clarify whether the person concerned has actually received the registered dose the holder of the authorization without delay. If there is reasonable doubt, the holder of the authorization has carried out an assessment of the dose actually received. A representation of the facts as well as the result of the dose assessment together with the underlying assumptions are to bring to the competent authority.

(4) the competent authority has either a replacement dose within the meaning of § 10 section 2 or the individual dose determined by the dose measurement body as effective dose or equivalent dose set on the basis of the submitted documents or their own surveys. The set values are the holder of the authorization, to inform the Central dose register as well as the competent point of dose measurement."

26 paragraph 5 deleted § 28.

27 paragraph 31:

"Article 31 (1) of the results of the personal dosimetry and monitoring of incorporation pursuant to §§ 25 and 26 are to keep a record of the holder of the authorization and store for at least 7 years. Records from the period before January 1, 2006 are however to be kept until the person concerned completed or completed would the 75th year of life, but at least for for 30 years after termination of activity associated with radiation exposure. On request are all records of the competent approval authority, to submit the Authority appointed to carry out the protection of workers and the competent institution of the accident insurance; Insight into these records to provide is the monitored person.

(2) in the records referred to in paragraph 1, caused by an accident and specially authorised exposures are separated to lead. For such expositions are also the circumstances and any actions taken to record.

(3) an occupationally exposed person leaves a company, the holder of the authorization request to follow a list of the received doses has her. These records when the holder of the authorization are not more fully, they are from the Central dose register request."

28 in the § 32 para 1 No. of 4 and 33 par. 1 Z 4 is the phrase "laboratory tests: part WBC and platelets, urine status" replaced by the phrase "Complete blood count and semi-quantitative study of urine using test strips".

29 § 37 para 1 second sentence reads:

"Who the doctors carrying out investigations of the appropriations in accordance with article 35, paragraph 1 StrSchG competent authority the successful completion of specific training in accordance with Annex 7, as well as the successful participation in training events to to prove the stated areas of expertise to the extent of at least 8 hours at intervals of not more than 5 years in the annex 7."

30 the following paragraph 4 is added to § the 37:


"(4) a person who intends the holding of courses for the training referred to in paragraph 1, required the prior recognition of training by the Federal Minister of health. This Article 43a paragraph 2 to 6 is to apply mutatis mutandis."

31 paragraph 43 par. 3 and 4:

"(3) the competent authority may recognise radiation protection training completed abroad and meet the qualifications required in accordance with paragraphs 1 and 2. In such cases, however, the authority has to convince that the person concerned possesses sufficient knowledge of the Austrian radiation protection regulations.

(4) Moreover are. an employment of adequate practical experience for the eligible activity could be purchased, to the extent of at least two years, as well as comprehensive knowledge of radiation protection of plant in which the activity is recorded to prove"

32. in section 43 para. 5, the phrase "of at least 8 hours' is replaced by the phrase"of at least 40 hours".

33. According to article 43, the following article 43a including heading shall be inserted:

"Recognition of training

§ 43a. (1) a person who intends the holding of courses to the radiation protection training according to annex 8, requires the prior recognition of training by the Federal Minister of health to provide training in accordance with § 41 or by the Federal Ministry of agriculture and forestry, environment and water management to provide training in accordance with the sections 42 or 43.

(2) for this purpose are documents, which content and scope of training, provided speakers, as well as the way of determining the successful completion of the training emerge, to deliver to the authority referred to in paragraph 1.

(3) the authority has to examine the documents and to pronounce the recognition in sufficient quality of education by way of an. The recognition is limited to no more than ten years.

(4) the documents are to update, taking into account the developments in radiation protection if necessary. In order to check this update obligation, the authority may require the submission of current documents at any time.

(5) the authority has the recognition be revoked if the quality of education is no longer given.

(6) the authority has to bring the authorities responsible for radiation protection legal permits recognition in accordance with paragraph 3 and revocations in accordance with paragraph 5."

34. paragraph 49 paragraph 5:

"(5) the holder of the authorization of the external company has to undertake an assessment of the data according to § 47 para. 2 Z 8 monthly for each external labour and to enter the monthly dose values in the radiation pass. The accounting produces a result that determined dose differs significantly from the corresponding with the personal dosimeter referred to in section 25, has to proceed the holder of the authorization of the external company, as well as, where appropriate, the competent authority, by analogy with application of the rules of § 28 para 3 and 4. In addition the holder of the authorization of the external company for each calendar year in which the radiation pass is valid to determine the Effektivdosis according to § 47 para. 2 Z 9 and enter this in the radiation pass."

35. first sentence reads § 50:

"For external workers who perform installation and servicing facilities for generating or measuring ionizing radiation, it is allowed that the exposure of these workers with the help of directly readable person dosimeters of the external company is determined in agreement with the holder of the authorization in whose control area the workers operate."

36. paragraph 50 Z 5:



"5. the holder of the authorization of the external company has to evaluate the dose log monthly and to meet the requirements of § 49 5. The dose Protocol is to store 7 years."

37. paragraph 51 including heading:

"The scope of application

§ 51. The provisions of this part apply to radioactive substances only in so far, when dealing with this subject to the radiation protection regulatory authorisation or notification."

38. paragraph 59 paragraph 4 to 6:

"(4) for sealed radioactive materials have



1 approval holders, with the exception of holders of a type approval, for each calendar year a report (activity record) from the cover, the further and levy, as well as the inventory of radioactive substances at the end of the year emerge, to deliver to the central register of radioactive sources, holder of a type approval and any intermediary, the type-approved devices in transport bring 2., for any device placed preferably continuously, but at least for each calendar year , the Central radiation sources register to submit the following information: name and address of the Subscriber, type and serial number of the device, number of the certificate of design as well as radionuclide and activity together with the reference time.

(5) the transmission has been in electronic form by using of the central register of sources available to be provided interfaces and input masks at the latest two months after the end of each calendar year.

(6) the provisions of § 64 paragraph 8, 10 and 11 concerning high-activity sealed radioactive sources remain unaffected."

39. in article 60, paragraph 3 the word "Interfaces" replaces "electronic forms" and the phrase "up to one year" 'up to three years' by the phrase the word order.

40. in article 60, paragraph 5 "to transmit" is appended after the phrase the word sequence "or to generate on the Web portal of the central register of sources".

41. in article 61, paragraph 3, the phrase is "regulation on the supervision and control of shipments of radioactive waste from, into or through the Federal territory (radioactive waste shipment regulation), Federal Law Gazette II No. 44/1997" by the phrase "radioactive waste shipment regulation 2009, Federal Law Gazette II No. 47/2009" replaced.

42. paragraph 63 para 3:

"Second sentence (3) the tests referred to in paragraph 1 and paragraph 2 may by experts, who also are members of the operation may be, be made, provided that the sources"



1 radioactive substances, their allowance in accordance with Appendix 1 table is greater than or equal to 104 becquerel 1 column 2, and 2. distance without shielding exhibit a dose rate in 1 meter of less than 1 milliSievert per hour.

Accredited bodies are to be used in all other cases. The authority may admit in some cases but also here that these tests be performed by experts, such as medical physicist. The leak tests are performed according to the State of the art."

43. paragraph 64 together with the heading:

"High-activity sources

64. (1) a sealed source containing a radionuclide whose radioactivity at the time of manufacture or, if this is not known, at the time of the first placing on the table corresponds to specified value 1 column 4 in Appendix 1 or higher, is considered highly radioactive sealed source. For radio-nuclides, for in Appendix 1 table 1 column 4 values listed are not, the corresponding activity value is one-hundredth of the A1 value in accordance with the regulations of the International Atomic Energy Agency for the safe transport of radioactive material (IAEA safety requirements no. TS-R-1, Edition 2009, section IV).

(2) for devices that contain multiple homogeneous sources, whose overall activity is decisive for the classification of the device as a highly radioactive source.

(3) a prerequisite for issuing a permit for the handling of highly radioactive sources by the competent approval authority is proven insurance or the template of a bank guarantee, which ensure the safe disposal of highly radioactive source in the event of insolvency of the holder of the authorization, through the grant seekers. This obligation shall not, if



1 the Federal Government, a country, a community association or a municipality with more than 50 000 inhabitants permit advertisers or 2. liability issued a statement against the permit recruiters has a local authority in accordance with no. 1.

The commitment to the financial guarantee according to the nuclear liability Act 1999, Federal Law Gazette I no. 170/1998, remains unaffected.


(4) the manufacturer has a unique identification number for each source to forgive, or has to make sure that this is a unique identification number allotted to the supplier for a radioactive source imported from third countries. This number is - as far as possible - to engrave on the radiation source or to inculcate in them. It is engraved on the protective container or inculcate. Reusable containers are used, the nature and activity of the source of the minimum information must exhibit. Each delivered radiation source and each delivered protective container a photography of the radiation source type and the type of protective container, on the even must the essential characteristics of an associated guard or protective equipment must be visible and necessary plans and drawings be connected. Furthermore, is to join a radiation source certificate to each delivered radiation source, the identification number, the type and activity of the radioactive substance, date, procedure and result of the leak test must emerge from the.

(5) the owner shall ensure that the corresponding certificate of radiation sources, as well as the photo documentation referred to in paragraph 4 are attached to each source.

(6) the holder of the permit has to conclude an agreement in principle for each high-activity source with the manufacturer or supplier to the later withdrawal of the radiation source. In justified individual cases, the authority may allow exceptions to this obligation.

(7) the holder of the authorization of highly radioactive sources has special procedures for handling to create rules about the regular maintenance, carried out regular checks and safe storage, especially for a mobile usage, have to contain. He has all those people he entrusted with the handling of highly radioactive sources, to undergo a comprehensive theoretical and practical instruction or to undergo further. The teachings must refer in particular to the content of the safety analysis, the failure analysis and emergency planning. The teachings are periodically and immediately after an event that had a higher radiation exposure risk or actual radiation exposure resulted to repeat. There are written records to lead, to be kept at least 7 years are about the extent and the duration of these teachings.

(8) without prejudice to the provisions of section 59, the holder of the authorization of highly radioactive sources has to keep records that contain the information provided for in annex 10. These records can be made to the standard registration form in accordance with annex 10.

(9) without prejudice to the provisions of § 54 para 2 lit. 3 are highly radioactive sources, the are in containers of type B in accordance with the European Agreement concerning the international carriage of dangerous goods by road (ADR - BGBl. No. 522/1973, as amended) are to be kept in locked, non-flammable devices, in which no significant fire loads must not be. Storage facilities for other highly radioactive sources must be at least fire retardant.

(10) the permit holder has following information about highly radioactive sources to be communicated to the central register of sources:



1 approval holders, 2. reference number and date of approval, 3. identification number, 4. characteristics and use, 5th place of the handling or storage, 6 information on reference, disclosure, or disposal, any loss or theft.

(11) the notifications referred to in paragraph 10 are once a year, as well as immediately after



1. the acquisition, 2. redistribution, to make 3 return to the manufacturers or distributors, 4. the removal of highly radioactive source, and 5 any other change in the information to be communicated."

44. paragraph 74 including heading:

"The disposal of liquid and gaseous radioactive waste

74. (1) radioactive substances with operating wastewater or the exhaust air are derived from radiation protection legally approved equipment, so the derived quantity of activity is to limit that the annual exposure of members of the public on the basis of these derivatives does not exceed an effective dose of 0.3 milliSievert.

(2) the authority shall set lower dose limits in individual cases, if several such facilities contribute to the exposure of the population.

(3) to comply with the dose limit of 1 or 2, are to be determined by the authority in some cases discharge limits.

(4) compliance with the dose limit for the planned derivation limits pursuant to par. 3, using conservative assumptions for the route of exposure, the place to stay, is to prove the duration of the stay and the habits of a reference person. The authority may require that this proof is taught by the permit advertisers or permit holder.

(5) the proposed derivation limit not over the values of annex 12 is or for several installations do not have the appropriate fraction of these values can be assumed adherence to the dose limit of paragraph 1 or paragraph 2. In these cases, the values of annex 12 or corresponding fraction thereof are to set discharge limits. An explicit proof of compliance with the dose limit pursuant to paragraph 4 is not required.

(6) derivatives are records to do, containing in particular the type and activity of radioactive substances derived, as well as the timing of individual derivatives.

(7) radioactive substances are considered the derivation such only up to the time."

45. § 76 para 2 No. 1 is:



"1. wastes containing radionuclides with half-lives of less than 100 days, where contamination with length Alder-any radionuclides shall not exceed one-tenth of the allowance Z 1 according to article 6, paragraph 1," 46. In § 78 para 2 and 3 receive the designation (3) and (4); of paragraph 1 is replaced by the following paragraphs 1 and 2:

"(1) radioactive waste, which are derived or released pursuant to section 79 or according to radioactive waste shipment regulation 2009, Federal Law Gazette II No. 47/2009, the country spent, not in accordance with section 74 are para to pass 1 StrSchG responsible for setting up the nuclear engineering Seibersdorf GmbH as referred to in section 36 c.

(2) as an alternative to paragraph 1 radioactive waste also to the manufacturer or the supplier of the radioactive substances can be reset, unless contractually undertakes to the dealer for the proper removal."

47. paragraph 79 subsection 3:

"(3) before each release is the compliance with the requirements set out in the notice of approval to determine. Furthermore are records to lead. These records are for at least 7 years to be kept."

48. the 5th part is as follows:

"Part 5

Research reactors

General terms and conditions

87. (1) research reactors are equipment for the purpose of scientific research or education, in which fissile material in quantities and type is handled, that a chain reaction can take place, and that serve primarily as a neutron source, and for the production of artificial radioactive substances.

(2) the competent authority has to inform the public about their supervisory activity in the field of nuclear safety and to comply with the reporting obligation referred to in article 9 paragraphs 1 and 3 of Directive 2009/71/EURATOM.

Construction of research reactors

88. (1) the search for a location for the construction of a research reactor has according to the regulations of the IAEA safety standards, NS-R-4: safety of research reactors, Vienna 2005, to be carried out. This concerns in particular the areas of site selection and assessment, while underlying criteria, the evaluation of external site-related hazards, in particular as a result of meteorological extreme events, earthquakes or human influences, and the assessment of the effects of the planned installation on environment and population.

(2) the interpretation of a research reactor has according to the international regulations of IAEA safety standards, NS-R-4: safety of research reactors, Vienna 2005, to be carried out. This concerns in particular General and special safety requirements on the design.

(3) in the case of the construction approval process are the provisions of the IAEA safety standards, NS-R-4: safety of research reactors, Vienna 2005, to take into account.

Operating organization

Section 89 (1) the permit holder has to determine the operating organization. In particular, belonging to the following groups of function is to set the distribution of the key tasks and the transfer of responsibilities:



1 reactor management, these are all weisungsbefugten supervisor of the reactor operators;

2. reactor operators, these are those individuals who are authorized to operate the reactor within the given framework and monitor;

3. radiation safety officer and persons entrusted with the perception of radiation protection;

4. responsible for nuclear safety and the Deputy Chairman.

Significant changes of the operating organisation are to bring to the competent authority.


(2) the officer to be ordered for the operation of a research reactor for nuclear safety, their deputies and the reactor management have



1. the successful completion of a) training relevant scientific or technical direction at a university or University of applied sciences, and b) training in the field of nuclear safety in accordance with annex 13, as far as the person concerned not already has completed a teaching on the areas listed in annex 13 in the framework of the training referred to in subpara 1 with success, 2. one relevant activities, practical experience for the intended task could be purchased at the , to the extent of at least 18 months, of which at least 6 months in the relevant appendix, otherwise in a comparable system, as well as 3 comprehensive knowledge of the nuclear safety of the plant, in particular operating rules and security report, to prove.

(3) the reactor operators required for the operation of a research reactor have



1. the successful completion of a) training relevant scientific or technical direction at a University, technical college or a vocational high school and b) training in the field of nuclear safety in accordance with annex 13, as far as the person concerned not already has completed a teaching on the areas listed in annex 8 within the framework of the training referred to in subpara 1 with success, as well as 2.
              a minimum 6-month employment in the relevant or a similar plant of two months in the reactor room, where practical experience for the intended task, as well as plant-specific knowledge could be acquired, to prove.

(4) the competent authority may recognise training concerning nuclear safety, which have been completed abroad and meet the training required pursuant to paragraph 2 and 3. In such cases, however, the authority has to convince that the person concerned possesses sufficient knowledge of the Austrian radiation protection regulations.

(5) personnel for nuclear safety and their deputies and the reactor management have to successful participation in training events to prove the stated areas of expertise to the extent of at least 40 hours in the annex 13 in 5 years. Reactor operators have to successful participation in training events to prove the stated areas of expertise to the extent of at least 8 hours in the annex 13 in 5 years. The authority may, when proof of attendance at the training sessions or not completely withdraw recognition or with corresponding requirements.

Nuclear safety

§ 89a. (1) the achievement of proper operating conditions, the prevention of accidents and the mitigation of road traffic accidents is considered nuclear safety within the meaning of this regulation, so that the staff of the plant as well as the population be protected from dangers of ionising radiation from the plant.

(2) the permit holder has to set up a management system with the aim of ensuring nuclear security at any time and to apply. This system has to take into account the requirements of the nuclear safety in accordance with paragraph 3 to 10. The system requires the permission of the competent authority and is to check this regularly.

(3) the permit holder has to provide permanently adequate human and financial resources to ensure safe operation.

(4) the permit holder has to provide plant engineering facilities to ensure safe operation and to keep their effects as low as possible for the occurrence of accidents. The functioning of these bodies is to review in the context of field tests at regular intervals and be documented in a manual test.

(5) the permit holder has set up quality assurance systems and to apply that best support the optimization of radiation protection and nuclear safety.

(6) in addition, which has to carry authorization by appropriate measures for a high safety culture in all areas and organizational levels of the investment concern.

(7) the permit holder has lit a security report with the in annex 14. Creating A named content which requires the permission of the competent authority. The safety report must be updated when significant changes require it.

(8) the procedure for accidents is to regulate through an emergency plan. The emergency plan has lit in annex 14. Referred to in B points to include.

(9) at intervals to be determined by the competent authority are emergency drills on their history and success records are to lead to hold.

(10) the permit holder has a periodic security check with the content in accordance with annex 14 lit every ten years. (C) carry out and to present the results of the competent authority. Deadline for the first submission of the results of the periodic safety review is ten years after the granting of the operating permit. For installations whose operating permit dated prior to January 1, 2002, the date is December 31, 2014. The competent authority shall evaluate the results of the periodic safety review and decision to determine whether the conditions for the continued operation of the plant are given.

Commissioner for nuclear safety

§ 89 b. (1) ensuring the nuclear security of a research reactor has the authority as part of the approval process in accordance with § 6 StrSchG appointed a Commissioner for nuclear safety with the proven consent. This person must possess the necessary reliability.

(2) the permit holder has to instruct the Commissioner for nuclear safety, which are to meet to ensure of nuclear safety in the research reactor with those tasks. These tasks include in particular:



1. the periodic review of the technical facilities pursuant to section 89a (4), 2. immediate notification to the holder of the authorization of encountered defects in nuclear safety, 3. the development of improvements and retrofitting measures based on scan results, own operating experience and the exchange of experience with the Commissioner for nuclear safety of comparable systems, 4. the creation and constant updating of the safety report in accordance with § 89a section 7 and of the emergency plan in accordance with section 89a para 8 in collaboration with the radiation protection Commissioner , 5 the evaluation of accidents which fall under notifiable events and other errors, 6 the participation to the elaboration of regulations pursuant to section 89 c, as well as in the accomplishment of recording and notification obligations in accordance with article 90 for the field of nuclear safety and 7 participation in the plans to change the system or its operation.

(3) the jurisdiction of the Commissioner for nuclear safety and its substitutes is to regulate in writing of the holder of the authorization. Concerning the administrative-criminal liability § 15 ABS. 3 is to apply mutatis mutandis.

(4) the permit holder has to make all required administrative and technical requirements available to the Commissioner for nuclear safety and its deputies for the fulfilment of their tasks, as well as to give the required time and access to all relevant information and documents.

(5) a change in the person of the Commissioner for nuclear safety is to announce without delay by the holder of the authorization of the competent authority.

(6) with regard to the compulsory attendance of the Commissioner for nuclear security and his Deputy, the rules are according to § 15 StrSchG to be applied mutatis mutandis.

(7) the Commissioner for nuclear safety no longer has the required reliability the competent authority of whose order has to withdraw.

Operating rules

§ 89c. (1) the reactor management has in consultation with the radiation protection Commissioner and the Commissioner for nuclear safety, in addition to the procedures pursuant to § 16 para 3, to establish internal rules for the operation of the research reactor in accordance with paragraph 2 and 3. It is to ensure that all affected persons become party to these rules.

(2) the following points must be included in the General operating rules:



1 operating organization, 2. internal rules of undertakings, in which rules for the operation of the system are set, in particular operating the reactor room, radiation protection, maintenance, fire protection and access rules, 3. organisational and technical safety requirements for the operation of the plant, 4. the procedure for the routine use of the research reactor and the associated facilities, such as for scientific experiments, 5. instruction manuals for all safety-critical systems, 6 safety-relevant limit values ,

7.
Measures for security-related events, 8 criteria for notifiable events, 9 event detection and description of a procedure for accidents and to perpetuating measures.


(3) for specific activities, which are not covered by the General operating rules such as maintenance or repairs, are cause-related to create specific operating rules.

Recording and reporting requirements

§ 90. (1) the permit holder has to make sure that running those records be maintained, which are decisive for the safety of the operation from the point of view of radiation protection and nuclear safety. The records have also those details to contain that are required for the reconstruction of the causes and course of the reportable events, within the meaning of annex 15. The records are to be kept at least 30 years and to submit on request of the competent authority, the Authority appointed to carry out the protection of workers and the competent institution of the accident insurance.

(2) notifiable events are to report to the competent authority without delay. The message must contain the information necessary for the assessment of the situation. In addition, the reporting requirements to the Central incident register according to § 94 apply.

(3) the reporting requirements in the event of a radiological emergency intervention regulation, Federal Law Gazette II No. 145/2007, as well as the provisions of incident information regulation, Federal Law Gazette No. 391/1994, in the currently valid version shall remain unaffected.

Decommissioning concept

91. (1) in accordance with § 5 ABS. 2 Z 1 StrSchG for a research reactor to tasks closure concept has to contain at least:



1. Description of the system, the location and the environment and operating history, as far as for the decommissioning is relevant, including a Dosisleistungs - and contamination Atlas of plant, 2 description of decommissioning in particular the safety precautions and security measures during the closure, 3. Description of the closure procedure of in particular the planned decommissioning and dismantling techniques, 4. estimation of the radioactive inventory and any other hazardous materials, 5. Description and classification of radioactive waste, and their planned treatment and interim storage , 6 describes of how to release of radioactive substances, 7 planned discharges during the decommissioning, environment monitoring, 9 8 programme.
Measures for workers and radiation protection during the closure, 10 description of the responsibilities for the decommissioning, 11 provided for reporting to the competent authorities.

(2) the decommissioning concept is to update at regular intervals and if necessary.

(3) the permit holder has to make appropriate financial provision for the decommissioning of the plant. The calculations underlying this provision are to be the competent authority regularly to update and to bring the authority.

Decommissioning

§ 91a. "The closure has on the basis of the current concept of closure pursuant to § 91 and in accordance with the provisions of the IAEA safety standards, NS-R-4: safety of research reactors, Vienna 2005, to be carried out."

49. paragraph 2 is the No. 3 § 92. The previous No. 4 is called "3.".

50. in article 92 par. 2, last sentence is omitted the phrase "or emergency exposures".

51. in article 92 par. 4, the phrase "as well as the dose referred to in article 28, paragraph 1" is inserted after the phrase "maximum permissible dose".

52. § 93 par. 2 No. 1 is:



"1. from the holder of the authorization the reports pursuant to section 59 para 4, § 60 and § 64 para 10," 53. section 94 including heading is:

"Central incident register

Section 94 (1) events that are on the international nuclear and radiological event scale (INES) with level 1, has the Central incident register the holder of the authorization period of four weeks to submit a report. For events that require an immediate reporting to the competent authority, this report with the assistance of the Agency is to create.

(2) the report shall contain at least the following information:



1. causes and sequence of the event, 2. any exposure of persons, 3. any contamination and releases, 4th made arrangements and 5.
Measures for the prevention of such events.

(3) the event with INES level is 2 or greater to evaluate, the holder of the authorization has incident register to submit, which must include at least the following content within 24 hours an initial message to the Central:



1 institution, from which the message originates: name, address, telephone and fax number, E-Mail address, 2. contact person for inquiries, 3. grant holders, 4. competent authority, 5. Description of the event: a) nature of the event, b) exact location (address, coordinates if known), c) date of the event (date, time), d) suspected or identified cause, e) expiry of the event, f) any exposures of people and g) any contamination and releases as well as 6 measures taken or planned.

(4) the transmission of reports to the central registry of the incident is in electronic form, using the Central incident register available making the interfaces, and input masks. Later available information is in the same way to deliver promptly.

(5) reports to the central registry of the incident are anonymized to make available to interested persons in an appropriate manner.

(6) any reporting requirements under the intervention regulation, Federal Law Gazette II No. 391/1994, in the amended remain unaffected no. 145/2007, or the incident information Ordinance, BGBl.."

54. the section 95 be added following paragraph 9 to 11:

"(9) the competent authority has to make StrSchG a reclassification of all occupationally exposed persons in categories A or B, taking into account the requirements stated in section 11 subsection 3 at least in the context of the next review in accordance with article 17.

(10) these courses without official recognition in accordance with § 37 para 4 or 43a who carries out training in accordance with sections 37, 41, 42 or 43 to the date January 1, 2012, may continue until 31 December 2012 at the latest.

(11) a person who operates a research reactor to the date January 1, 2012, has to present the operating organisation referred to in article 89, paragraph 1 the competent authority without delay and to appoint the Commissioner for nuclear safety in accordance with paragraph 89 b. The competent authority shall



"1. to check if the training requirements in accordance with section 89, paragraph 2 and 3 of the designated personnel are met, and, if necessary, additional training to prescribe 2. commensurate with the holder of the authorization period for updating in the §§ 89, 89a, put 89 b and 91 referred to documents such as safety report, emergency plan, decommissioning concept, as well as for the availability of the safety management system in accordance with section 89a, paragraph 2."

55. conditioning 1 first paragraph reads:

"to §§ 6 para 1, 8 para of 1, 61 (1) and 4, 62 para of 5, 63 para of 3, 64 para 1 as well as 79 par. 1 and 2"

56. in Appendix 1, table 1 - the text section on column 2 and 3 eliminates explanations.

57. the title of Appendix 5 is "Specifications for the physical checks and medical examinations".

58. Unit 5 lit. A is as follows:

"A. person and the holder of the authorization monitored information on the

To the person being monitored:

Name, first name, maiden name, title,

Social security number (if this is not known: date of birth, place of birth),

Gender, nationality,

Employment, accident insurance institutions,

Category A / B / others,

Activities in accordance with the table below.

 







Nuclear material



Core material

Nuclear facilities - their own staff

Core systems - external workforce

Nuclear research

Decommissioning

Radioactive waste - treatment

Radioactive waste - storage

Transport in the area of nuclear installations

Nuclear materials - other







Medicine



X-ray Diagnostics

Interventional Radiology

Cardiology

Surgical Radiology

Radiation therapy

Dental X-ray

Nuclear medicine

Veterinary medicine

Other medical activities









Industry



Industrial radiography - stationary

Industrial radiography - mobile

Borehole investigations

Transport of radioactive material

Radio chemical manufacturing

Industrial radiation

Accelerator

Chemical industry

Luminising

Other industrial activities







Natural radioactivity



Tag construction - coal

Tag construction - other than coal

Oil and gas industry

Swiss tunnelling society - coal

Swiss tunnelling society - other than coal

Uranium mining

Civil Aviation

Show caves and-bergwerke

Waterworks

Other activities with natural radiation exposure









Research etc.



Training facilities

Research General

Security, Executive, inspection







Military



Nuclear-powered ships

Other military areas









Other



Activities not listed here





 





To the holder of the authorization:


Name and address of the holder of the authorization."

59. in annex 5 lit. Second paragraph is replaced by the phrase "Annex 6, tables 3 and 4, respectively" the phrase "Annex 6, tables 1 or 2" S.

60. in annex 7 is the heading "Training for authorized doctors". The heading for the section A "A. training for authorized doctors" as well as the entire part B accounts for.

61. in annex 8, the phrase "to sections 41 to 43" is replaced by the phrase "to sections 41, 42, 43 and 43a".

62. plant 8 lit. D is as follows:

"D. radiation protection training according to § 43

Training for persons successfully completed higher education in the period of at least 60 hours, for people with successful completion of a vocational high school in the period of at least 120 hours:



"- Foundations of nuclear physics, including the physics of ionizing radiation - fundamentals of radiation protection - reactor physics - foundations of reactor technology and nuclear safety - handling of radioactive substances - radioactive waste - radiation biology - dosimetry - national and international legislation on the area of radiation protection and nuclear safety - gauges - radiation and emission monitoring - fire protection - emergency planning - access control" 63. Appendix 1 first paragraph is:

"To section 74 para 5"

64. in annex 12 eliminates the paragraph before the heading "A. guideline values for activity concentration in air".

65. following equipment 13 be added to 15:

"Annex 13

to § 89

Training in the field of nuclear safety

Personnel for nuclear safety, their deputies, the reactor management and reactor operators have the following training to prove successful completion:

Extent: For persons with completed university education 80 hours for persons completing a vocational higher school of 120 hours



-Basics of nuclear physics including physics of ionizing radiation - nuclear physics - energy release and thermal-hydraulics - foundations of reactor technology and nuclear safety - radiation protection - safety at work - national and international legislation in the field of radiation protection and nuclear safety - reactor waiting and waiting for technology - plant operation and control - access control - fire protection system 14

to section 89a para 6 and 7

Content security report, emergency plan and periodic safety review

A. content of the safety report

General description of the research reactor;

Aspects of system planning, in particular, security objectives and technical design;

Site characteristics;

Current description of the system, in particular by



-Building and structures, - reactor, - cooling systems and related systems, security equipment, - rule - and control systems - electrical power supply, - aid systems, including fuel storage and handling, ventilation and fire safety;

Explanation of the management and operational safety, in particular



-Description of the use of the reactor, radiation - protection, - description of the operating organization, - education and training, - operating instructions, maintenance programs, - Wiederholprüfpläne in particular inspection manual;

Representation of the backup status of the installation;

Safety / accident analysis, in particular



-Based based incident spectrum (identification and classification of accidents), estimates of source terms, - assessment of the radiological impact of accidents on people and the environment, - probabilistic safety analysis, - description of the results based on the safety objectives and requirements for the design and the permitted releases or discharges of radioactive substances;

Excerpt from the set-aside concept;

Overview of emergency planning;

Emergency plan.

 

B. contents of the emergency plan



-Description of the plant and equipment in terms of incidents, including an inventory of equipment and their location, - specifications for the detection and classification of an incident, - definition of responsibilities, in particular that of the operating organization, in accidents, - presentation of procedures at accidents, in particular the alarm procedures, - summary of reporting requirements to the authorities, including the establishment of relevant contact information and reporting channels, - arrangements to ensure the reliability of all communication channels , - Agreements with external usage organisations and authorities with regard to assistance at accidents, in particular as regards the provision of additional staff resources, - facilities for first and subsequent estimates of radiological effects, including the radiological environmental monitoring - protection measures for minimizing the radiation exposure of persons, in particular defining a collection point for the workers inside and outside of the reactor building and measures to the delineation and identification of the range of the radiation hazard and decontamination , - Measures to ensure medical care of injured persons, in particular their accommodation in hospitals, - technical measures to prevent the expansion of the consequences of accidents, in particular measures to reduce the release and spread radioactive material, - targets for reducing the dose for internal usage personnel, - provisions regarding public information, - arrangements for the resumption of normal operation after an incident, measures for the securing of evidence - rules relating to training of personnel and holding of exercises , - Regulations regarding the review and update of the emergency plan.

 

C. content of the periodic safety review

Security report in the current version;

Presentation of the current state of systems, structures and components in particular



-Results of the repeat tests, - maintenance, - quality condition, - aging processes;

-Proof that the safety requirements are met, evaluation of operating experience, in particular



-Presentation of occupational safety, - experience reflux from the operation of the system, - taking into account operating experience of comparable facilities and new research results;

Final overall assessment of the security status of the system by the holder of the authorization, if necessary with indication of possible measures to improve the security.

 

Annex 15

§ 90

Notifiable events

Reportable events within meaning of article 90 are in particular:



-Unauthorized discharges of radioactive effluent - release of radioactive substances into the environment or within the plant - contamination in the area under surveillance, that exceed 100 times the values in annex 9 - contamination in the Control Panel, which exceed the 1000 times the values in annex 9 - malfunctions, damages or failures of safety-critical systems or system components - damage or leaks on safety important pipelines or containers - criticality errors - crash loads with safety-significant impact on the operation of the reactor - instructions important events handling ", Storage or transport of fuel - instructions important influences from outside (eg earthquake or flood) - instructions important internal events (E.g. fire or attachment internal flooding) - dose exceeded" Berlakovich Stöger Bures Mitterlehner Töchterle