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Regulation on the Nuclear Safety Officer and on the reporting of incidents and other events

Original Language Title: Verordnung über den kerntechnischen Sicherheitsbeauftragten und über die Meldung von Störfällen und sonstigen Ereignissen

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Regulation on the Nuclear Safety Officer and on the reporting of incidents and other events (Nuclear Safety Officer and Reporting Ordinance-AtSMV)

Unofficial table of contents

AtSMV

Date of completion: 14.10.1992

Full quote:

" Nuclear Safety Officer-and Reporting Regulation of 14. October 1992 (BGBl. 1766), as last amended by Article 1 of the Regulation of 8 June 2010 (BGBl I). 755).

Status: Last amended by Art. 1 V v. 8.6.2010 I 755

For more details, please refer to the menu under Notes

Footnote

(+ + + Text evidence from: 1.7.1993 + + +) 

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Input formula

Pursuant to section 12 (1), first sentence, no. 1, 7 and 13, and the first sentence of Article 54 (1) and (2), first sentence, of the Atomic Energy Act, as amended by the Notice of 15 July 1985 (BGBl. 1565), § 54 (1) sentence 1 as amended by Article 2 of the Law of 9. October 1989 (BGBl. I p. 1830), the Federal Government decrees:

First section
Scope

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§ 1 Scope

(1) This Regulation shall apply to installations according to § 7 (1) of the Atomic Energy Act. (2) For storage in accordance with § 6 of the Atomic Energy Act and for installations in decommissioning pursuant to Section 7 (3) of the Atomic Energy Act, § § 6 to 8, § 9 (2) and § 12. (3) shall apply. does not apply:
1.
for installations for the division of nuclear fuel, the maximum output of which does not exceed 50 kilowatts of thermal continuous power, and
2.
for storage in accordance with § 6 of the Atomic Energy Act and annexes to decommissioning pursuant to Section 7 (3) of the Atomic Energy Act, provided that:
a)
the nuclear fuel has been removed from the storage facility or the plant in decommissioning; and
b)
the remaining activity inventory in the case of open radioactive substances no more than the 10 7 , and in the case of enclosed radioactive substances, no more than 10 10 the limits of the free limits laid down in Annex III, Table 1, column 2 of the Radiation Protection Regulation.

Second section
Nuclear Safety Officer

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§ 2 Order of the Nuclear Safety Officer

(1) The holder of a permit to operate an installation according to § 7 paragraph 1 of the Atomic Energy Act (operator) has for the duration of the operation of the plant until the granting of a permit to decommission the plant according to § 7 paragraph 3 of the Atomic Energy Act a nuclear safety officer (safety officer) and his representative in writing. If several plants are operated by the operator on the same site, a joint safety officer can be appointed. The supervisory authority may exempt the operator from the obligation to appoint a safety officer, in so far as the quantity or nature of the nuclear fuel or of certain protective measures or safety devices means that: (2) The operator shall immediately notify the Supervisory Authority of the appointment of the Safety Officer, indicating the position within the company, any change in this position and the withdrawal in writing. A copy of the advertisement shall be handed out to the security officer and the operational or personnel council. (3) Only one person may be appointed to the security officer who has no facts from which concerns have been raised against her. reliability, and which has the technical expertise required to carry out its tasks. The proof of the subject is to be provided on the display of the order. Where the supervisory authority is aware of facts which result from the fact that the safety officer does not possess the specialist or reliability required to carry out his duties, it may require that the operator should have another Security officer appointed. (4) To be applied to the representative accordingly:
1.
(1), second sentence and third sentence,
2.
paragraphs 2 and 3, and
3.
§ § 3 to 5 and § 10.
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§ 3 Duties of the operator

(1) The operator shall assist the safety officer in the performance of his duties and, in particular, as far as is necessary for the performance of his duties, to provide technical and auxiliary staff. (2) The operator has ensure that the safety officer receives the information necessary for the performance of his duties and that he or she is informed of administrative acts and other measures relating to his duties or powers. Unofficial table of contents

§ 4 Tasks of the security officer

(1) The safety officer shall, within the operational organisation at the site of the installation, be without prejudice to the responsibility of the operator
1.
for the evaluation of
a)
notifiable events (§ 6),
b)
other disturbances in the plant's own plant,
c)
Information about notifiable events in other installations with regard to their importance for their own plant
to participate in and participate in the implementation of these tasks,
2.
to assist in the preparation of remedial measures and improvement measures,
3.
inform the operator without delay of any safety deficiencies, or proposals to remedy the deficiencies or to increase safety,
4.
to participate in the planning of changes to the plant or its operations,
5.
to verify the reporting of events subject to reporting requirements in accordance with § 10,
6.
To participate in the exchange of experience with the security officers of other plants via safety-related operational experience.
(2) In the performance of his duties, the Security Officer shall cooperate with the operational or staff counsel and the occupational safety and safety officers, as well as in accordance with other regulations, in the plant and shall cooperate with him/her in the course of such tasks. on important matters relating to nuclear safety. He has to advise the operational or staff council at its request in matters relating to nuclear safety. Unofficial table of contents

§ 5 Position of the security officer

(1) The safety officer shall not be impeded in the performance of his duties and shall not be penalised because of his/her activities. (1a) The operator shall, by means of internal organisational measures, ensure that the The operator has no direct production responsibility functions. (2) The operator has to ensure, through internal organisational measures, that the safety officer is directly responsible for his proposals and concerns. May present management if he does not agree with the head of the plant , and because of the particular importance of the matter, he was able to consider a decision of the Executive Board. If the safety officer fails to agree with the management of a nuclear safety measure he is proposing, the safety officer shall inform the security officer in writing of the rejection of the proposal and shall be required to: Reasons. It has to send a copy to the operational or staff council and the supervisory authority. (3) The position of the security officer and his duties in accordance with § 4 shall be defined in detail in the Operations Manual.

Third Section
Notification of accidents, incidents and other events

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§ 6 Reporting obligation

(1) The holder of an authorisation pursuant to § 6 or § 7 (1) or (3) sentence 1 of the Atomic Energy Act (reporting requirements) has accidents, incidents or other events (notifiable events) that are significant for the nuclear safety of the nuclear safety. (2) Reporting requirements are events that meet the reporting criteria listed in Appendixes 1 to 5. (2a) Annex 4 applies to installations in decommissioning from the date on which the supervisory authority, at the request of the operator, by: Administrative act has established that the above mentioned in the preliminary remark to Appendix 4 (3) The notifiable person shall immediately have the occurrence of a notifiable event, including the authority responsible for the public safety and order, and the authority responsible for civil protection, without delay. , to the extent that this is necessary for the protection of the population from the risks of life and health. (4) (omitted) Unofficial table of contents

§ 7 Content of the written notice

(1) In the notification to the supervisory authority referred to in the first sentence of Article 8 (1) (1) (1) to (4), the notifiable person shall have the notifiable event, its causes and effects, the correction of the effects and arrangements against it, by means of an official notification form. to describe repetitions in such a way that they can be adequately assessed in terms of nuclear safety. The supervisory authority shall disclose an official notification form. (2) In the written notification by telecommunication in accordance with § 8 (1) No.1 and 2, the notifiable person shall provide the information required by the notification form, insofar as information is provided. can be made immediately and data is known. Unofficial table of contents

§ 7a Electronic Communications

(1) The transmission of electronic documents shall not be allowed until the supervisory authority has informed the reporting person that access has been opened for this purpose. (2) The bodies involved shall have the relevant state of the art To take measures to ensure data protection and data security. In the case of the use of generally accessible networks, encryption methods shall be used which correspond to the state of the art. Unofficial table of contents

§ 8 Reporting procedure

(1) Reporting events are to be reported
1.
Category S: immediately after knowledge, by telephone and in writing by means of telecommunications transmission; at the latest on the fifth working day after being aware of completion and, if necessary, correction of the notification by means of the notification form;
2.
Category E: at the latest 24 hours after knowledge, by telephone and in writing by means of telecommunications transmission; at the latest on the fifth working day after knowledge of completion and, if necessary, correction of the notification by means of the notification form;
3.
Category N: at the latest on the fifth working day after knowledge by means of the registration form;
4.
Category V: at the latest on the tenth working day after knowledge by means of the registration form.
The supervisory authority may make more detailed instructions on the notification. (2) If the required information cannot be provided within the time limit for the written notification by means of the notification form, the notification shall be deemed to be provisional. As soon as the missing data are known, the supervisory authority shall be required to submit a fully-completed and definitively marked message. The final notification shall be submitted no later than two years after the provisional notification, unless the supervisory authority has agreed to a subsequent submission due to a lack of data. (3) The classification in the categories referred to in the first sentence of paragraph 1, and the allocation to the reporting criteria listed in Annexes 1 to 5 shall be carried out on the basis of the facts known in the case of a refund of the notification. The notification period shall begin as soon as the notifiable person becomes aware of the facts which objectively establish the obligation to notify. (4) A notifiable event shall fill a number of the numbers listed in Annexes 1 to 5 under different numbers in annexes 1 to 5. In the cases referred to in paragraph 2, no later than the final written notification. (5) If the notification criteria to be specified are assigned to a number of categories in accordance with the first sentence of paragraph 1, the form shall be set out in the form of: and the time limit for notification by category with the shortest reporting period. (6) To be notifiable event also includes:
1.
all events that are caused by the first event (follow-up events), and
2.
all similar failures, damages, malfunctions or findings on similar devices, systems or parts of equipment identified in the course of investigations relating to this event.
(7) If, in the knowledge of all relevant facts, it becomes clear that a reported event was not subject to reporting, the reporting body shall inform the supervisory authority in writing, indicating the facts relevant to the event. Unofficial table of contents

§ 9 Supplementary obligations of the reporting person

(1) The notifiable person shall show the supervisory authority monthly the number of notifiable events which have occurred since the notification of the previous notification. (2) The notifiable person shall have events which are subject to reporting requirements and for the entry into which they have been registered. shall be responsible for defective parts of the plant or in the course of which damage to important parts of the plant shall occur, to take measures to ensure that the precise causes and consequences of the problem are to be clarified and checked at a later date. Permit a notifiable event The following are particularly suitable for the protection of evidence:
a)
Storage of defective components in unmodified form,
b)
Production of light images,
c)
Create a detailed damage documentation.
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Section 10 Examination by the security officer

The security officer shall check the accuracy and completeness of the notification of a notifiable event, to record the result of his examination on the registration form and to provide it with his signature. The same applies to the advertisement in accordance with § 9 paragraph 1.

Fourth Section
Fines

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§ 11 Administrative Offences

Contrary to the provisions of Section 46 (1) (4) of the Atomic Energy Act, those who intentionally or negligently act
1.
contrary to § 6 (1) or (3), in connection with the first sentence of Article 7 (1) or the first sentence of Article 8 (1), in connection with § 1 (2) or 8 (6), or in breach of § 8 (2) sentence 2 or sentence 3, a report not, not correct, does not make complete or non-timely notification of an advertisement, not correct, not fully or not refunded in good time or a notification not, not correct, not complete or not presented in good time,
1a.
(dropped)
2.
Contrary to § 9 para. 1, an advertisement is not reimbursed, not correct or not timely, or
3.
Contrary to § 10, the result of the examination is not or is not correctly noted.

Fifth Section
Final provisions

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§ 12 Relationship with other provisions

§ 51 sentence 2 of the Radiation Protection Regulation shall not apply within the scope of this Regulation. Unofficial table of contents

§ 13 (omitted)

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Final formula

The Federal Council has agreed. Unofficial table of contents

Annex 1 Reporting criteria for notifiable events in installations according to § 7 of the Atomic Energy Act for the division of nuclear fuel for the industrial production of electricity

(Fundstelle: BGBl. I 2010, 757-762)

Content Directory Preface

1. Radiology and radiation protection
1.1 Disposal of radioactive substances
1.2 Release of radioactive substances
1.3 Contamination
1.4 Disappearance of radioactive substances
2. Plant engineering and operation
2.1 Dysfunction, damage or outages in the safety system or in other safety-related systems or parts of the plant
2.2 Damage or leakages to pipes or containers
2.3 Criticality disorders
2.4 Crash of loads; events during handling, storage or transport
2.5 Other events
3. External effects and events internal to the system
3.1 External effects
3.2 Asset Internal Events


Preliminary remarks

The reporting criteria for notifiable events in installations for the separation of nuclear fuels for the industrial production of electricity, as far as examples from the field of plant technology are specified, relate to reactor installations with Light water reactors. In the case of other types of reactor, the reporting criteria shall be applied in accordance with
1.
Radiology and radiation protection In the following criteria reference is made to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, is to be based on a mean area of 300 square centimetres.
1.1
Derivation of radioactive substance criterion S 1.1.1discharges of radioactive substances with air or water, in which the activity derived within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
the maximum activity charges laid down by the competent authority in the calendar year exceed the maximum permitted activity.
Criterion E 1.1.1discharges of radioactive substances with air or water, in which the derived activity exceeds the maximum permitted activity levies laid down by the competent authority.
1.2
Release of radioactive substance criterion S 1.2.1Release of radioactive substances into the environment in which the activity is to be obtained that the activity released within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion E 1.2.1Release of radioactive substances into the environment in which it is to be found that the released activity
-
leads to body doses exceeding 10% of the limit values in accordance with § 47 (1) sentence 1 of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion N 1.2.1Release of radioactive substances into the environment which does not fall within the scope of criteria S 1.2.1 or E 1.2.1. criterion S 1.2.2Release of radioactive substances within the plant, so that outside a control area Area the local dose rate exceeds the value of 3 millisieverts per hour. criterion E 1.2.2Release of radioactive substances within the plant, so that
-
within a range marked as a control area, to the extent that it is not marked as a restricted area, the local dose rate exceeds the value of 3 millisieverts per hour for more than 24 hours, or
-
the establishment of a new control area is required.
1.3
Contamination criterion E 1.3.1contamination within the surveillance zone, which exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and whose total activity in becquerel exceeds 10 times the total Values according to Annex III, Table 1, column 2 of the Radiation Protection Regulation. criterion N 1.3.1XX_ENCODE_CASE_One contamination within the control area, which is in an area which cannot be contaminated when the operation is intended, the thousandfold of the values. pursuant to Annex III, Table 1, column 4 of the Radiation Protection Regulation , and whose total activity in becquerel is more than one hundred times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.4
Spilling of radioactive substance criterion S 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of control areas on the premises, provided that the activity which has been carried out there is a hundred times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and a hundredfold of the values set out in Annex III, Table 1 Column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity carried out there is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and ten times the values set out in Annex III, Table 1, column 2 of the Radiation protection regulation.
Criterion E 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of surveillance areas on the premises, provided that the activity carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity which has been carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and the simple of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation exceeds.
2.
Plant engineering and operation
2.1
Dysfunction, damage or outages in the security system or in other safety-related systems or system-side criterion S 2.1.1Functional disturbance, damage or failure in the security system (including related ancillary services) and secondary systems), with the result that the number of security steerers required for the control of accidents is no longer available. When this is the case, is laid down in the approved operating rules.
-
Dysfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that only the number of security subdevices required for the control of faults is still available is. When this is the case, it is laid down in the approved operating rules.
-
Complete failure of a security function, which is intended solely for the control of emergency situations.
Criterion N 2.1.1
-
Dysfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that at least one security subsystem is not available.
-
Malfunction, damage or failure in another safety-related system or part of the system, with the result that the system or a redundant system is not available.
-
Failure of a security steeper, which is intended solely for the control of emergency situations.
Not to be reported are malfunctions, damage or outages:
-
individual cards or transmitters in the reactor protection system or in control equipment performing comparable tasks, provided that the failure is self-reporting, is fixed within 8 hours and not to be reported according to criterion N 2.1.2 is,
-
in other safety-related systems, which are fixed in less than 24 hours, or failures of such systems for which authorised replacement measures are provided, provided that the event does not report according to criterion N 2.1.2 is.
Criterion N 2.1.2Damage, failure or finding, with reference to a systematic error
-
on the security system or on any other safety-related system or part of the system,
-
a component, a component or an assembly in an operating system where the component, component or assembly is subject to comparable boundary conditions and comparable quality in the safety system or in any other safety-important system is used.
Criterion N 2.1.3failure of or damage to an installation of the industrial or technical fire protection. Not to be reported are failures of or minor damage to individual components of the plant engineering or construction engineering Fire protection, by which the fire protection functions are not unacceptably affected. criterion S 2.1.4Functional disturbance of a safety, bubble or relief valve of the pressure-carrying enclosure:
-
unintended opening provided that there is no automatic shut-off of the blow-off pipe (excluding boiling water reactors (SWR)),
-
Non-closing after response, unless automatic shut-off of the blow-off line is carried out (excluding SWR),
-
Non-opening of a safety valve in the event of a request.
Criterion E 2.1.4Functional disturbance of a safety, bubble or relief valve:
-
non-scheduled opening of a safety, bubble or relief valve of the pressure-carrying enclosure, provided that the incident is not to be reported in accordance with criterion S 2.1.4,
-
Non-closing of a safety, bubble or relief valve of the pressure-carrying enclosure, provided that the incident is not to be reported in accordance with criterion S 2.1.4,
-
Non-opening of a discharge valve of the pressure-carrying enclosure in the event of a request,
-
Non-opening of a fresh steam safety valve in the event of a request (excluding SWR),
-
Non-closing of a fresh steam safety valve, provided that no automatic shut-off is carried out,
-
Non-opening of any other safety valve in the event of a request to a device of the security system or to another system or part of the system which is important in terms of safety and security.
Not to be reported in accordance with criterion E 2.1.4 are the malfunctions mentioned in criterion N 2.1.4. criterion N 2.1.4Functional disturbance of a safety, bubble or relief valve:
-
non-scheduled opening of a safety and relief valve (in the case of SWR) if only one valve is affected and this valve is automatically closed or closed before automatic reactor protection operations are triggered,
-
Non-closing of a safety and relief valve (in the case of SWR) when only one valve has been left open and before automatic reactor protection operations are triggered, it closes or is brought to a close,
-
non-scheduled opening of a pressure-holder blow-off valve (for pressurised water reactors (DWR)), if it closes automatically before the blow-off valve closes or before the safety container is released or before the removal or escape alarm is triggered; or to be brought to a close,
-
Non-closing of a fresh steam safety valve, in which an automatic shut-off of the blow-off pipe is carried out,
-
non-scheduled opening or non-closing of a safety valve on any other device of the safety system or any other safety-related system or part of the plant.
Criterion E 2.1.5Safety-related significance exceeding a design value in the case of a reactor core, pressure-carrying enclosure, safety containment or parts of the fresh steam and feedwater system, which are important in terms of safety and safety, criterion N 2.1.6Safety-related significant deviation from the specified condition in the safety system (including associated auxiliary and secondary systems) or in another system or part of the system, which is important for safety reasons. redundant security devices, which at the same time as a failure of these security components in accordance with the safety specifications, they must also be reported in accordance with criterion S 2.1.1 or criterion E 2.1.1.
2.2
Damage or leakages to piping or container criterion S 2.2.1leakages, which lead to the triggering of a protective action. Do not report:
-
the disclosure of safety and relief valves (in the case of SWR),
-
Mismanagement of protective actions,
-
Leakages with cold installation, which can be quickly stopped (for example, faulty opening of a fitting with subsequent closing of this or a redundant fitting).
Criterion E 2.2.1Break or Riss with leakage, which for safety reasons requires a run-off of the system, on one of the following systems:
-
the reactor cooling circuit or the directly adjoining systems up to and including the areas which are exposed to reactor coolant pressure,
-
Fresh steam system up to the turbine and bypass valves as well as to all pipe sections that cannot be shut off against this pressure space,
-
on the feedwater system as well as on all pipe sections that cannot be shut off against this pressure space.
Criterion N 2.2.1Damage, in particular crack, deformation or undershooting of the nominal wall thickness at a
-
the establishment of the security system or any other activity-bearing system;
-
Enclosure of the fresh steam or feedwater system up to and including the external shut-off valve,
-
Enclosure of the fresh steam or feed-water system outside the external shut-off valve, provided that the damage indicates a lack of design or an untaken-up load.
Not to be reported:
-
individual sealing or flanking layers outside the pressure-carrying enclosure,
-
Drip spots on gaskets or flanges within the pressure-carrying enclosure,
-
Stuffing box leakages within the scope of the design of the stuffing box suction within the pressure-carrying enclosure,
-
Leaks on measuring, dewatering or venting lines in the turbine area.
Criterion E 2.2.2Steam boiler heating pipe leakage, which requires a run-off of the plant.
-
Failure of a pressure vessel, a fitting or pump housing,
-
Disassemble a flywheel mass,
-
Breaking a pipeline,
if this can result in a functional impairment of a safety-related system or part of the system. criterion N 2.2.3Damage to a pressure container, if it is to be obtained that a failure of the container due to this Damage directly or in a chain of subsequent events leading to the endangering of a safety-related system or part of the system leads or causes a malfunction.
2.3
Criticality disturbingcriterion S 2.3.1Criticality without sufficient power-off reserve of the rapid shutdown systems.criterion E 2.3.1
-
Inadmissible strangeness of reactivity, or
-
unauthorised deboration in pressurised water reactors.
2.4
Crash of loads; events in handling, storage or transport criterion S 2.4.1crash of a load into the fuel-element storage tank or the reactor chamber with the result
-
a loss of subcriticality, or
-
a non-lockable larger leakage (more than 0.3 litres per second).
Criterion E 2.4.1crash
-
of a fuel element in the fuel-element storage tank, the transport or storage container or the reactor space,
-
any other load in the fuel-element storage basin or the reactor chamber, with the consequence of a greater leakage (more than 0.3 litres per second) of leakage (0.3 litres per second or less) of leakage,
-
a heavy load into a room in which a safety-related system or part of the system is located.
Criterion N 2.4.1
-
Safety-related event in the transport, handling or storage of fuel elements or other radioactive materials within the plant or plant site.
-
Important safety-related event during transport or handling of a load.
-
Safety-related damage to a hoist, or to a transport or handling device.
2.5
Other event criterion E 2.5.1Event with automatic response of a safety valve of the pressure-carrying enclosing. criterion N 2.5.1Damage to reactor pressure vessel internals, reactor core or steam generator installation. Not to be reported individual fuel element damage, provided that they do not exceed cracks or slight deformations and do not provide any indication of systematic weak points. criterion N 2.5.2A loose part or a foreign body
-
in the pressure-carrying enclosure, or
-
in the closure of the other security establishments,
if an important safety function is inadmissible or a fuel rod damage of a larger scale can be caused. criterion N 2.5.3Damage caused by a water or condensation strike or systematic damage Suspensions, supports or damping devices on a safety-related pipeline or component. criterion N 2.5.4Damages to reactor coolant pumps requiring the installation to be shut down. criterion N 2.5.5Failure of
-
more than one main feed water or main condensate pump, or
-
50 percent of the main cooling water pumps and more.
Criterion N 2.5.6Common failures of the main and the reserve network connection, failure of a strand of the self-supply supply.criterion N 2.5.7Request or misexcitation of a security steeper by the reactor protection system.Not to be reported are:
-
Rapid shut-down in the start-up phase with low reactor output (up to 5 percent),
-
Solutions carried out or provided for in operation.
Criterion N 2.5.8Safety engineering significant damage to a load-bearing structure of a building construction criterion N 2.5.9Event, which requires a significant change in the safety specifications.
3.
External effects and events internal to the system
3.1
Effects of external criterion S 3.1.1Damage caused by earthquakes, aircraft crash or explosion pressure wave
-
a building in which there is a security-related system or part of the system;
-
a safety-related system or part of the system, with the result that a security device is requested.
Criterion E 3.1.1effect from the outside, which requires the installation to be switched off or shut down for safety reasons.
3.2
Unit internal event criterion S 3.2.1Plant internal fire, internal explosion, flooding or any other effect from within to an extent to which it is to be provided that the number of interpreters required for the control of the disturbance Safety steeper equipment is no longer available. criterion E 3.2.1Plant internal fire, internal explosion, flooding or any other effect from the inside to an extent to which it is to be provided that only the interpretative according to Required number of control Criterion N 3.2.1Plant internal fire, plant internal explosion, flooding or other action from inside, in a room or plant area, in which radioactive substances with an activity above the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or in which a safety-related facility is located. Not to be reported are locally limited micro-fires related to change or Maintenance work, for preventive fire protection measures , and whose application was effective in fighting fires.
Unofficial table of contents

Annex 2 Reporting criteria for notifiable events in annexes according to § 7 of the Nuclear Fuel Supply and Disposal Atomic Law

(Fundstelle: BGBl. I 2010, 763-766)

table of contents

1. Radiology and radiation protection
1.1 Disposal of radioactive substances
1.2 Release of radioactive substances
1.3 Contamination
1.4 Disappearance of radioactive substances
2. Plant engineering and operation
2.1 Functional faults, damage or failures in safety-related systems or parts of the system
2.2 Damage or leakages to pipelines or containers of safety-related systems
3. External effects and events internal to the system
3.1 External effects
3.2 Asset Internal Events


1.
Radiology and radiation protection In the following criteria reference is made to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, is to be based on a mean area of 300 square centimetres.
1.1
Derivation of radioactive substance criterion S 1.1.1discharges of radioactive substances with air or water, in which the activity derived within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
the maximum activity charges laid down by the competent authority in the calendar year exceed the maximum permitted activity.
Criterion E 1.1.1discharges of radioactive substances with air or water, in which the derived activity exceeds the maximum permitted activity levies laid down by the competent authority.
1.2
Release of radioactive substance criterion S 1.2.1Release of radioactive substances into the environment in which the activity is to be obtained that the activity released within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion E 1.2.1Release of radioactive substances into the environment in which it is to be found that the released activity
-
leads to body doses exceeding 10% of the limit values in accordance with § 47 (1) sentence 1 of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion N 1.2.1Release of radioactive substances into the environment which does not fall within the scope of criteria S 1.2.1 or E 1.2.1. criterion S 1.2.2Release of radioactive substances within the plant, so that outside a control area Area the local dose rate exceeds the value of 3 millisieverts per hour. criterion E 1.2.2Release of radioactive substances within the plant, so that
-
within a range marked as a control area, to the extent that it is not marked as a restricted area, the local dose rate exceeds the value of 3 millisieverts per hour for more than 24 hours, or
-
the establishment of a new control area is required.
1.3
Contamination criterion E 1.3.1contamination within the surveillance zone, which exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and whose total activity in becquerel exceeds 10 times the total Values according to Annex III, Table 1, column 2 of the Radiation Protection Regulation. criterion N 1.3.1XX_ENCODE_CASE_One contamination within the control area, which is in an area which cannot be contaminated when the operation is intended, the thousandfold of the values. pursuant to Annex III, Table 1, column 4 of the Radiation Protection Regulation , and whose total activity in becquerel is more than one hundred times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.4
Spilling of radioactive substance criterion S 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of control areas on the premises, provided that the activity which has been carried out there is a hundred times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and a hundredfold of the values set out in Annex III, Table 1 Column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity carried out there is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and ten times the values set out in Annex III, Table 1, column 2 of the Radiation protection regulation.
Criterion E 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of surveillance areas on the premises, provided that the activity carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity which has been carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and the simple of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation exceeds.
2.
Plant engineering and operation
2.1
Malfunction, damage or outages in safety-related systems or system-side criterion S 2.1.1Functional disturbance, damage or failure at a safety-related important facility, so that a plant condition has occurred, which has a beneficial effect on the population or the environment, or where it is to be provided. criterion E 2.1.1Functional disturbance, damage or failure in a safety-related facility if the installation is to be designed for this purpose and in the event of the operation of the plant or of the partial plant Criterion N 2.1.1Functional disturbance, damage or failure
-
a safety-related body, or
-
one component or one component in another device of the installation or the partial installation, provided that a corresponding component or a corresponding component is used in a device which is important in terms of safety.
Not to be reported are malfunctions, damage or outages:
-
of individual technical components in the control equipment of the safety-related equipment required for the control of faults, provided that the failure is self-reporting, is fixed within 24 hours and does not Criterion N 2.1.2 is to be reported,
-
in other safety-related systems, which shall be fixed in less than 24 hours or within the permissible repair times specified in the approved operating rules, provided that the functioning of the system is maintained,
-
other safety-related important system for which replacement measures are provided for in the approved operating rules for a limited period, provided that the event is not to be reported in accordance with criterion N 2.1.2,
-
on individual components of the fire protection or building fire protection system, which do not inadmissibly affect the fire protection functions, provided that the event is not to be reported in accordance with criterion N 2.1.2.
The competent authority may, for the purposes of criterion N 2.1.1, lay down additional requirements specific to the plant. criterion N 2.1.2outage, damage or finding, indicating a systematic error in an important safety-related setting. N 2.1.3Safety-related deviation from an officially established value of the plant technology or the operating system. Criteria E 2.1.4/N 2.1.4Request of an active safety device 1) Criterion N 2.1.5Overflow of radioactive substances into a system, component or component if the system, component or component is not subjected to radioactive substances during normal operation. 2.1.6Criticality event criterion E 2.1.6Event that violates the safety principles of criticality safety criterion N 2.1.6Event which impairs the security of criticality, but does not affect the safety principles of the Breach of criticality hat.criterion N 2.1.7Safety-related event in the case of transport, handling or storage of radioactive substances on the operating site. criterion N 2.1.8Event which requires a significant change in the safety specifications. Installation or partial installation, which may have an impact on the proper functioning of a system or part of the system, which is important in terms of safety engineering, in existing operations. criterion V 2.1.10Befinding in a safety-related facility before the plant or the partial installation, which shall be placed on a Interpretation errors or a weakness of the quality assurance system. criterion V 2.1.11Event in the establishment of the installation or the partial installation, the effect on the proper functioning of a system which is of safety engineering or part of the plant in the future (for example, fire, explosion, flooding, crash of a heavy load).
2.2
Damage or leaks to pipelines or containers of safety-related important system criterion S 2.2.1leakage in an activity-bearing system which has a beneficial effect on the population or the environment or if this is to be done Criterion E 2.2.1fracture or crack with leakage in an activity-carrying system or in a pipeline with safety containment (for example, autoclaves), which for safety reasons, the adjustment of the plant operation Criterion N 2.2.1XX_ENCODE_CASE_CAPS_LOCK_On leakage or damage, in particular Riss, Deforming or Underwriting of the nominal wall thickness on a pipeline or a container of a safety-related or an activity-carrying system or plant eils.Not to be reported are individual drip spots on
-
Seals, flanges, pipes or containers of non-activity-bearing systems and plant parts,
-
Gaskets and flanges of activity-leading systems and plant parts.
3.
External effects and events internal to the system
3.1
Effects of the external criterion S 3.1.1earthquake, aircraft crash, explosion pressure wave or other external action, so that a plant condition has occurred which has a driving effect on the population or the environment or in which this has occurred. Criterion E 3.1.1earthquake, plane crash, explosion pressure wave or other external action, if the operation of the installation or the partial installation cannot be continued for safety reasons. criterion N 3.1.1earthquake, plane crash, explosion pressure wave or other action from the outside, provided that the facility is affected by it and this is not covered by the criteria S 3.1.1 or E 3.1.1.
3.2
Plant internal event criterion S 3.2.1Plant internal fire, plant internal explosion, severe chemical reaction, flooding, the crash of a heavy load, or any other effect from inside, so that a plant condition has occurred, the have a driving effect on the population or the environment, or in which this is to be obtained. criterion E 3.2.1Internal fire, plant-internal explosion, severe chemical reaction, flooding, the crash of a heavy load, or a Other effects from the inside, if the operation of the plant or the part of the plant is Criterion N 3.2.1Plant internal fire, internal plant explosion, severe chemical reaction, flooding, crash of a heavy load or any other effect from the inside, provided that the installation which is not covered by the criteria S 3.2.1 or E 3.2.1.
1)
The relevant safety establishment and the relevant reporting category shall be determined by the competent authority.
Unofficial table of contents

Annex 3 Reporting criteria for notifiable events in annexes according to § 7 of the Atomic Energy Act for the division of nuclear fuels, which are mainly used for research purposes

(Fundstelle: BGBl. I 2010, 767-772) Content Directory Preface

1. Radiology and radiation protection
1.1 Disposal of radioactive substances
1.2 Release of radioactive substances
1.3 Contamination
1.4 Disappearance of radioactive substances
2. Plant engineering and operation
2.1 Dysfunction, damage or outages in the safety system or in other safety-related systems or parts of the plant
2.2 Damage or leakages to pipes or containers
2.3 Criticality disorders
2.4 Crash of loads; events during handling, storage or transport
2.5 Other events
3. External effects and events internal to the system
3.1 External effects
3.2 Asset Internal Events
4. Events prior to authorisation to load the reactor


Preliminary remarks

The nuclear fuel-splitting plants operated in the Federal Republic of Germany, which are mainly used for research purposes, differ both in their hazard potential and in the facilities belonging to their safety systems. as well as in the number of redundancies of important systems or parts of the system, in part clearly different from each other. In order to ensure uniform application of the individual reporting criteria in these systems, a plant-specific concretization is required.
1.
Radiology and radiation protection In the following criteria reference is made to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, is to be based on a mean area of 300 square centimetres.
1.1
Derivation of radioactive substance criterion S 1.1.1discharges of radioactive substances with air or water, in which the activity derived within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
the maximum activity charges laid down by the competent authority in the calendar year exceed the maximum permitted activity.
Criterion E 1.1.1discharges of radioactive substances with air or water, in which the derived activity exceeds the maximum permitted activity levies laid down by the competent authority.
1.2
Release of radioactive substance criterion S 1.2.1Release of radioactive substances into the environment in which the activity is to be obtained that the activity released within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion E 1.2.1Release of radioactive substances into the environment in which it is to be found that the released activity
-
leads to body doses exceeding 10% of the limit values in accordance with § 47 (1) sentence 1 of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion N 1.2.1Release of radioactive substances into the environment which does not fall within the scope of criteria S 1.2.1 or E 1.2.1. criterion S 1.2.2Release of radioactive substances within the plant, so that outside a control area Area the local dose rate exceeds the value of 3 millisieverts per hour. criterion E 1.2.2Release of radioactive substances within the plant, so that
-
within a range marked as a control area, to the extent that it is not marked as a restricted area, the local dose rate exceeds the value of 3 millisieverts per hour for more than 24 hours, or
-
the establishment of a new control area is required.
1.3
Contamination criterion E 1.3.1contamination within the surveillance zone, which exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and whose total activity in becquerel exceeds 10 times the total Values according to Annex III, Table 1, column 2 of the Radiation Protection Regulation. criterion N 1.3.1XX_ENCODE_CASE_One contamination within the control area, which is in an area which cannot be contaminated when the operation is intended, the thousandfold of the values. pursuant to Annex III, Table 1, column 4 of the Radiation Protection Regulation , and whose total activity in becquerel is more than one hundred times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.4
Spilling of radioactive substance criterion S 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of control areas on the premises, provided that the activity which has been carried out there is a hundred times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and a hundredfold of the values set out in Annex III, Table 1 Column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity carried out there is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and ten times the values set out in Annex III, Table 1, column 2 of the Radiation protection regulation.
Criterion E 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of surveillance areas on the premises, provided that the activity carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity which has been carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and the simple of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation exceeds.
2.
Plant engineering and operation
2.1
Dysfunction, damage or outages in the security system or in other safety-related systems or system-side criterion S 2.1.1Functional disturbance, damage or failure in the security system (including related ancillary services) and secondary systems), with the result that the number of security steerers required for the control of accidents is no longer available. When this is the case, is laid down in the approved operating rules.
-
Dysfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that only the number of security subdevices required for the control of faults is still available is. When this is the case, it is laid down in the approved operating rules.
-
Complete failure of a safety device which is necessary for the tightness of the building enclosing the reactor.
Criterion N 2.1.1
-
Dysfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that at least one security subsystem is not available.
-
Malfunction, damage or failure in another safety-related system or part of the system, with the result that the system or a redundant system is not available.
-
Failure of a security subsystem, which is intended exclusively for the control of events with a very low probability of occurrence (effects from the outside or from the inside).
Not to be reported are malfunctions, damage or outages:
-
individual cards or transmitters in the reactor protection system and in control equipment performing comparable tasks, provided that the failure is self-reporting, is fixed within 8 hours and does not report according to criterion N 2.1.2 is,
-
in other safety-related systems, which shall be fixed in less than 24 hours, or the outages for which approved replacement measures are provided, provided that the event is not to be reported in accordance with criterion N 2.1.2.
Criterion N 2.1.2outage, damage or finding, with reference to a systematic error
-
on the security system or on any other safety-related system or part of the system,
-
a component, a component or an assembly in an operating system where the component, component or assembly is subject to comparable boundary conditions and comparable quality in the safety system or in any other safety-important system is used.
Criterion N 2.1.3failure of or damage to an installation of the industrial or technical fire protection. Not to be reported are failures of or minor damage to individual components of the plant engineering or construction engineering Fire protection, by which the fire protection functions are not unacceptably affected. criterion N 2.1.4Non-opening or non-closing of a safety valve on another system or part of the system, which is important in terms of safety and security. 2.1.5Safety-related and significant exceedation of Interpretation values
-
the reactor core,
-
in the primary cooling system or Reactor tanks,
-
in the building that encloses the primary cooling system,
-
in the case of an experimentation device in whose failure the reactor and its safety devices as well as other systems or plant parts which are important in terms of safety are not excluded, and
-
in the case of a secondary circuit, provided that such safety tasks are carried out.
Criterion N 2.1.6Safety-related significant deviation from the specified condition in the safety system (including associated auxiliary and secondary systems) or in another system or part of the system, which is important for safety reasons. A number of redundant safety devices, which at the same time represent a failure of these security components in accordance with the safety specifications, must also be reported in accordance with criterion S 2.1.1 or criterion E 2.1.1.
2.2
Damage or leakages to pipelines or container criterion S 2.2.1leakages on the primary cooling system, which leads to the triggering of a protective action. Not to be reported are incorrect excitations of protective actions or leaks in swimming pool reactors.criterion E 2.2.1
-
Breakage or crack with leakage in the primary cooling system, including the primary heat exchanger, or at the reactor tank or reactor vessel, which, for safety reasons, requires a run-off of the installation.
-
Leakage via lines in which, due to their integration of the primary coolant loss with or without re-feeding, it is basically so limited that the sufficient cooling capacity of the reactor is ensured. Leakages are not to be reported during training, research, isotopes, general atomic reactors (TRIGA reactors).
-
Leakage in the secondary circuit, provided that the safety-related tasks are carried out, and in which a shutdown of the installation is required for safety reasons.
Criterion N 2.2.1
-
Leakage or damage to the establishment of the security system or any other activity-carrying system;
-
Leakage or damage to the enclosure of the secondary circuit, provided that such safety tasks are carried out;
-
Leakage in the secondary circuit, in which, for safety reasons, the installation is required to run down.
Not to be reported are individual sealing or flanking layers as well as drip spots outside the safety system. criterion E 2.2.3
-
Failure of a pressure vessel, a fitting or pump housing,
-
Disassemble a flywheel mass,
-
Breaking a pipeline,
if this can result in a malfunction of a system or part of the system which is important for safety reasons. criterion N 2.2.3Damage to a pressure container, if it is to be obtained that failure of the container due to this damage The following events are to be taken directly or in a chain to the risk of a safety-related system or part of the system or cause a malfunction.
2.3
Criticality disturbingcriterion S 2.3.1Criticality without sufficient power-off reserve of the rapid shutdown systems.criterion E 2.3.1
-
Inadmissible strangeness of reactivity, or
-
unauthorised collection of neutrons absorbing substances.
2.4
Crash of loads; events in handling, storage or transport criterion S 2.4.1crash of a load into one of the following areas:
-
reactor tank or reactor vessel,
-
Primary circuit up to and including the first barrier,
-
Paddling basin, fuel-element storage basin,
-
experimentation facilities,
-
Jet pipes,
with the consequence of a loss of the undercriticality or of a non-lockable major leakage (more than 0.3 litres per second).
-
of a fuel element in the fuel-element storage tank, in the transport or storage container, or into the reactor tank or into the reactor vessel,
-
any other load in the fuel-element storage tank, reactor tank or reactor vessel, with the consequence of a larger leakage (more than 0.3 litres per second) of leakage (0.3 litres per second or less) of leakage,
-
any other load in a space area of the primary circuit, including the first shut-off or the experimental equipment or the jet pipes, provided that the possibility of loss of coolant in the event of damage is caused, with the result that: a greater leakage (more than 0.3 litres per second) of leakage (0.3 litres per second or less) of leakage which cannot be blocked,
-
a heavy load into a room in which a safety-related system or part of the system is located.
Criterion N 2.4.1
-
Safety-related event during the transport, handling or storage of a fuel or other radioactive materials within the plant or plant site.
-
Important safety-related event during transport or handling of a load.
-
Safety-related damage to a hoisting tool, a transport or handling device.
2.5
Other event criterion E 2.5.1
-
Complete failure of the primary coolant pumps (does not apply to TRIGA and swimming pool reactors).
-
Complete blockage of cooling channels by loose parts or foreign bodies.
Criterion N 2.5.1Damage at the reactor core, reactor tank internals, reactor tank installations or primary heat exchanger units. Individual fuel element damage should not be reported unless they exceed cracks or slight deformations and do not have to be reported. pointing to systematic weaknesses. criterion N 2.5.2A loose part or a foreign body
-
in the reactor tank or reactor vessel or in the primary cooling circuit, or
-
in another establishment of the security system,
if a safety-related function, such as ensuring the integrity or cooling of the fuel elements, can be impaired. In TRIGA reactors and swimming pool reactors, the determination of a loose part or of a not to report foreign bodies if it can be excluded that this part or this foreign body is also to be found in less favourable circumstances than in the current case
-
an impairment of cooling,
-
an impairment of the switch-off function, or
-
To a fuel element damage
could have led. criterion N 2.5.3damage caused by a water or condensation impact or systematic damage to suspensions, supports and damping devices on a pipeline or component of important safety technology N 2.5.4
-
Damage to primary coolant pumps, which require a shutdown of the plant.
-
Complete failure of primary coolant pumps during the nuclear power operation; in the case of swimming pool reactors, complete failure of primary coolant pumps shortly after the reactor has been shut down.
Criterion N 2.5.5XX_ENCODE_CASE_One failures of more than one main pump of the secondary circuit during the nuclear power operation, provided that the secondary circuit performs safety-related tasks. criterion N 2.5.6Failure of the supply of the mains, provided that this electrical supply of a device which is important for safety reasons is no longer guaranteed. criterion N 2.5.7Request or misexcitation of a safety device by the reactor protection system.Not to be reported is a Rapid reactor shutdown,
-
which is carried out in a targeted manner by the personnel or automatically for the protection of experimentation facilities, without the need for safety,
-
which is clearly attributable to a network malfunction (does not apply to installations in which the electrical supply of a safety-related equipment for post-heat dissipation is thereby impaired),
-
which is carried out in the start-up phase at low reactor output; unless otherwise defined in the operating rules for the "low reactor power", the reactor output is low at less than 5% power,
-
which takes place at zero power without the necessary forced cooling, or
-
which is carried out in the case of personnel training in reactor operation without the necessary forced cooling.
Criterion N 2.5.8Safety engineering significant damage to a load-bearing structure of a building construction criterion N 2.5.9Event, which requires a significant change in the safety specifications.
3.
External effects and events internal to the system
3.1
Effects of external criterion S 3.1.1Damage caused by earthquakes, aircraft crash or explosion pressure wave
-
a building in which there is a security-related system or part of the system;
-
a safety-related system or part of the system, with the result that a security device is requested.
Criterion E 3.1.1effect from the outside, which requires the installation to be switched off or shut down for safety reasons.
3.2
Unit internal event criterion S 3.2.1Plant internal fire, internal explosion, flooding or any other effect from within to an extent to which it is to be provided that the number of interpreters required for the control of the disturbance Safety steeper equipment is no longer available. criterion E 3.2.1Plant internal fire, plant internal explosion, flooding or other effects from the inside to an extent to which it is to be provided that only the interpretative according to Required number of control Criterion N 3.2.1Plant internal fire, plant internal explosion, flooding or any other effect from inside in a room or plant area in which radioactive substances with an activity above of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or in which a safety-related facility is located.
-
in connection with changes or maintenance work for which preventive plan fire protection measures have been taken and whose application has been effective in fire-fighting,
-
in the field of experimentation facilities, which could not affect the availability of a safety-related facility on the ground, type and scope.
4.
Events prior to approval of the loading of the reactor criterion V 4.1Befinding in a safety-related system or part of the plant, which indicates a design error or a weakness in the quality system. 4.2Event on a safety-related important system or part of the plant, insofar as this event is of importance with regard to the later safe operation.
Unofficial table of contents

Annex 4 Reporting criteria for notifiable events in installations in decommissioning pursuant to § 7 (3) of the Atomic Energy Act

(Fundstelle: BGBl. I 2010, 773-776)

Content Directory Preface

1. Radiology and radiation protection
1.1 Disposal of radioactive substances
1.2 Release of radioactive substances
1.3 Contamination
1.4 Disappearance of radioactive substances
2. Plant engineering and operation
2.1 Malfunctions, damage or failures in safety-related facilities
2.2 Damage or leakages to pipes or containers
2.3 Crash of loads; events in the handling, storage or transport of radioactive substances
2.4 Other events
3. External effects and events internal to the system
3.1 External effects
3.2 Asset Internal Events


Preliminary remarks

The reporting criteria for notifiable events for installations located in decommissioning, plant areas or plant parts shall apply to installations which:
1.
the division of nuclear fuels and in which the protection objectives of "sub-criticality" and "post-heat dissipation" are no longer relevant for the residual operation of the plant in decommissioning, or
2.
were not responsible for the division of nuclear fuels and where the objective of "subcriticality" is no longer relevant,
as long as this has already been granted for the approval pursuant to Section 7 (3) of the Atomic Energy Act.
If these application criteria are not available, attachments 1, 2, or 3 will continue to apply, depending on the type of approval and plant type.
1.
Radiology and radiation protection In the following criteria reference is made to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, is to be based on a mean area of 300 square centimetres.
1.1
Derivation of radioactive substance criterion S 1.1.1discharges of radioactive substances with air or water, in which the activity derived within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
the maximum activity charges laid down by the competent authority in the calendar year exceed the maximum permitted activity.
Criterion E 1.1.1discharges of radioactive substances with air or water, in which the derived activity exceeds the maximum permitted activity levies laid down by the competent authority.
1.2
Release of radioactive substance criterion S 1.2.1Release of radioactive substances into the environment in which the activity is to be obtained that the activity released within 24 hours
-
to exceed the limits of the body doses in accordance with the first sentence of Article 47 (1) of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion E 1.2.1Release of radioactive substances into the environment in which it is to be found that the released activity
-
leads to body doses exceeding 10% of the limit values in accordance with § 47 (1) sentence 1 of the Radiation Protection Regulation, or
-
more than 10 per cent of the maximum activity levies fixed by the competent authority for discharges in the calendar year.
Criterion N 1.2.1Release of radioactive substances into the environment which does not fall within the scope of criteria S 1.2.1 or E 1.2.1. criterion S 1.2.2Release of radioactive substances within the plant, so that outside a control area Area the local dose rate exceeds the value of 3 millisieverts per hour. criterion E 1.2.2Release of radioactive substances within the plant, so that
-
within a range marked as a control area, to the extent that it is not marked as a restricted area, the local dose rate exceeds the value of 3 millisieverts per hour for more than 24 hours, or
-
the establishment of a new control area is required.
1.3
Contamination criterion E 1.3.1contamination within the surveillance zone, which exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and whose total activity in becquerel exceeds 10 times the total Values according to Annex III, Table 1, column 2 of the Radiation Protection Regulation. criterion N 1.3.1XX_ENCODE_CASE_One contamination within the control area, which is in an area which cannot be contaminated when the operation is intended, the thousandfold of the values. pursuant to Annex III, Table 1, column 4 of the Radiation Protection Regulation , and whose total activity in becquerel is more than one hundred times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.4
Spilling of radioactive substance criterion S 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of control areas on the premises, provided that the activity carried out there exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and the hundredfold of the values set out in Annex III Table 1, column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity carried out there is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and ten times the values set out in Annex III, Table 1, column 2 of the Radiation protection regulation.
Criterion E 1.4.1XX_ENCODE_CASE_One dissemination of radioactive substances from the plant by means of a transfer into an area
-
out of surveillance areas on the premises, provided that the activity carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or
-
outside the operating site, provided that the activity which has been carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and the simple of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation exceeds.
2.
Plant engineering and operation
2.1
Functional disturbances, damages or failures in safety-related equipment criterion N 2.1.1Functional disturbance, damage or failure at a safety-related facility which is available for compliance with the protection objectives , with the consequence that
-
at least one redundancy of a safety-related system is not available, or
-
if the malfunction, damage or failure is due to safety reasons, the dismantling measures must be interrupted in accordance with the approved operating rules.
Not to be reported are malfunction, damage or outages
-
in the safety-related facilities, which shall be fixed in less than 24 hours or within the permissible repair times specified in the approved operating rules, provided that the functioning of the system is maintained,
-
in the case of safety-related facilities for which replacement measures are provided for in the approved operating rules for a limited period, provided that the event is not to be reported in accordance with criterion N 2.1.2.
Criterion N 2.1.2outage, damage or finding with reference to a systematic error in an important safety-related establishment. criterion N 2.1.3failure of or damage to an installation of the plant-engineering or construction-technical Fire protection es.Not to be reported are failures of or minor damage to individual components of the technical or technical fire protection system, by which the fire protection functions are not unacceptably compromised. criterion N 2.1.4Safety-related significant deviation from the specified condition in a safety-related important system or part of the system or from a safety-related limit value set in the operating rules (safety specifications).
2.2
Damage to or leakage of piping or container criterion N 2.2.1leakage or damage to a facility that is important for activity containment or to any other activity-carrying system or other activity-carrying capacity Componente.Not to be reported are individual drip spots on gaskets and flanschen.criterion N 2.2.2
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failure of a pressure-carrying component with immediate effect on a safety-related system, or
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Damage to a pressure-carrying component, to the extent to which it is to be provided that a failure on the basis of this damage directly or in a chain of subsequent events to be assumed to endanger a system or part of the system which is important in terms of safety and security .
2.3
Crash of loads; events in the handling, storage or transport of radioactive substance criterion N 2.3.1
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Crash of a load that has or could have led to the impairment of a safety-related system or part of the system.
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Safety-related event during the transport or storage of radioactive materials within the plant site.
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Safety-related damage to a hoist or to a transport or handling device.
2.4
Other event criterion N 2.4.1Event, which requires a significant change in the safety specifications. criterion N 2.4.2damage to a load-bearing structure of a building with the consequence that the availability of a safety-related Criterion N 2.4.3Ausinterpretative requirement of a safety-related facility in its safety function. Requirements not to be reported by the personnel without the need for a safety function are not required. safety-related requirements, or are clearly attributable to network disruptions.
3.
External effects and events internal to the system
3.1
Effects of external criterion S 3.1.1earthquake, aircraft crash, explosion pressure wave or other external action, so that a plant condition has occurred,
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in respect of which the protection objective "containment of radioactive substances" or the protection objective "limitation of exposure to radiation" has been infringed, and
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which has a beneficial effect on the population or the environment, or in which it is to be provided.
Criterion E 3.1.1XX_ENCODE_CASE_One earthquake, plane crash, explosion pressure wave or other external action, so that a plant condition has occurred, in which the protection objective "containment of radioactive substances" or the protection target " limitation of the Radiation exposure " has been infringed or is to be obtained.
3.2
Plant internal event criterion S 3.2.1Plant internal fire, internal plant explosion, severe chemical reaction, flooding or other action from inside, so that a plant condition has occurred,
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in respect of which the protection objective "containment of radioactive substances" or the protection objective "limitation of exposure to radiation" has been infringed, and
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which has a beneficial effect on the population or the environment, or in which it is to be provided.
Criterion E 3.2.1Plant internal fire, internal plant explosion, severe chemical reaction, flooding or other action from the inside, so that a plant condition has occurred, in which the protection objective "containment of radioactive substances" or the Criterion N 3.2.1Plant internal fire, plant-internal explosion, flooding or other action from inside in a room or plant area, in the radioactive waste water, or in the area of the radioactive waste, in the radioactive waste water, or in the area of the radioactive waste water. Substances with an activity above the values according to Appendix III Table 1 Column 2 of the Radiation Protection Ordinance or in which a safety-related facility is located. Not to be reported are locally limited micro-fires in connection with mining, modification or maintenance work, for which Preventive planned fire protection measures have been taken and their application was effective in fighting fires.
Unofficial table of contents

Annex 5 Reporting criteria for notifiable events in the case of storage in accordance with § 6 of the Atomic Energy Act

(Fundstelle: BGBl. I 2010, 777-779)

Content Directory Preface

1. Radiology and radiation protection
1.1 Release of radioactive substances
1.2 Contamination
1.3 Disappearance of radioactive substances
2. Technology and operation
2.1 Dysfunction, damage or outages in safety-related systems or devices
2.2 Crash of loads; events during handling or transport
2.3 Other events
3. External effects and internal events
3.1 External effects
3.2 Provisioning Internal Events


Preliminary remarks

The reporting criteria are valid for the storage of nuclear fuel according to § 6 of the Atomic Energy Act. The collection therefore covers the storage of nuclear fuels as well as the storage of solidified highly radioactive fission product solutions and the facilities and activities required for this purpose, including intra-company transports.
1.
Radiology and radiation protection In the following criteria reference is made to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, is to be based on a mean area of 300 square centimetres.
1.1
Release of radioactive substance criterion S 1.1.1Release of radioactive substances into the environment in which it is to be obtained that the activity released within 24 hours of exceeding the limits of the body doses in accordance with § 47 (1) Criterion E 1.1.1Release of radioactive substances into the environment in which it is to be obtained that the released activity leads to body doses which exceed 10% of the limit values in accordance with § 47 (1) sentence 1 of the Radiation protection ordinance. criterion N 1.1.1Release of radioactive substances into the environment which is not subject to the criteria S 1.1.1 or E 1.1.1. criterion S 1.1.2Release of radioactive substances within the device, so that outside a range marked as a control area, the local dose rate is the value of 3 millisieverts per hour. criterion E 1.1.2Release of radioactive substances within the facility, so that
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within a range marked as a control area, to the extent that it is not marked as a restricted area, the local dose rate exceeds the value of 3 millisieverts per hour for more than 24 hours, or
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the establishment of a new control area is required.
1.2
Contamination criterion E 1.2.1contamination within the surveillance zone, which exceeds the hundredfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and whose total activity in becquerel exceeds 10 times the total Values according to Annex III, Table 1, column 2 of the Radiation Protection Regulation. criterion N 1.2.1XX_ENCODE_CASE_One contamination within the control area, which is in an area which cannot be contaminated when the operation is intended, the thousandfold of the values. pursuant to Annex III, Table 1, column 4 of the Radiation Protection Regulation , and whose total activity in becquerel is more than one hundred times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.3
Spilling of radioactive substance criterion S 1.3.1XX_ENCODE_CASE_One dissemination of radioactive substances from the facility by means of transfer into an area
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out of control areas on the premises, provided that the activity which has been carried out there is a hundred times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and a hundredfold of the values set out in Annex III, Table 1 Column 2 of the Radiation Protection Regulation, or
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outside the operating site, provided that the activity carried out there is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and ten times the values set out in Annex III, Table 1, column 2 of the Radiation protection regulation.
Criterion E 1.3.1XX_ENCODE_CASE_One dissemination of radioactive substances from the facility by means of a transfer into an area
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out of surveillance areas on the premises, provided that the activity carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or
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outside the operating site, provided that the activity which has been carried out there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and the simple of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation exceeds.
2.
Technology and operation
2.1
Malfunction, damage or failure in safety-related systems or equipment criterion E 2.1.1Functional disturbance, damage or failure of a safety-related important system or a safety-related important system Establishment, so that for further storage in accordance with § 6 of the Atomic Energy Act an additional measure not previously defined in the approved action instructions (safety specifications, operating and testing regulations) will be taken Criterion N 2.1.1Functional disturbance, damage or failure of a Safety-related important system or safety-related equipment. Not to be reported are malfunctions, damages or failures
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in other safety-related systems, which shall be fixed in less than 24 hours or within the permissible repair times specified in the approved operating rules, provided that the functioning of the system is maintained,
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other safety-related systems for which authorised replacement measures are permitted for a limited period, provided that the incident is not to be reported in accordance with criterion N 2.1.2;
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Reduced dimensions of individual components of the building fire protection system as well as the failure of individual components of the decentralized fire-fighting and fire alarm systems.
Criterion N 2.1.2outage, damage or finding with reference to a systematic error in a system which is important in terms of safety engineering or a safety-related important device. criterion N 2.1.3
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Triggering of a pressure switch of the sealing systems of the transport or storage containers.
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Triggering of a pressure switch, which is not due to leakages of the cover seals, unless the defect on the pressure switch can be fixed within the permissible repair time specified in the approved operating rules .
2.2
Crash of loads; events in handling or transport criterion E 2.2.1
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Crashing of a container loaded with nuclear fuel or solidified cleavage product solutions.
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Crashing of a heavy load on a container loaded with nuclear fuel or solidified cleavage product solutions.
Criterion N 2.2.1
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Important safety-related event during transport or handling of a transport or storage container.
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Important safety-related event during transport or handling of a load.
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Safety-related damage to a hoist or to a transport or handling device.
2.3
Other event criterion N 2.3.1Safety technology-relevant deviation from an officially established value of the technology or the operating system criterion N 2.3.2Safety engineering significant damage to a supporting structure of a Bauwerks.criterion N 2.3.3Event, which requires a significant change in the safety specifications.
3.
External effects and internal events
3.1
Effects of external criterion S 3.1.1earthquake, plane crash, explosion pressure wave or other external action, so that a condition of the device has occurred which has a driving effect on the population or the environment or to obtain this. criterion E 3.1.1earthquake, plane crash, explosion pressure wave or other external action, provided that the storage in accordance with § 6 of the Atomic Energy Act only with an additional, so far not in the operating regulations may be continued.
3.2
Internal event criterion S 3.2.1Set-up internal fire, internal explosion, severe chemical reaction, flooding or other action from the inside, so that a condition of the device has occurred which is (e) 3.2.1Set-up internal fire, internal explosion, severe chemical reaction, flooding or any other effect from the inside, provided that: the storage in accordance with § 6 of the Atomic Energy Act only with an additional, so far not Criterion N 3.2.1Set-up internal fire, internal explosion, severe chemical reaction, flooding or any other effect from inside in a room or area the facility in which radioactive substances with an activity above the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation, or in which a safety-related facility is located, are not to be reported. Locally limited micro-fires related to change and Maintenance work for which preventive fire protection measures have been taken and whose application has been effective in the fire-fighting operation.