Regulation About The Nuclear Security Officer And The Reporting Of Accidents 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 the Reporting of Incident and Other Events (Nuclear Safety Officer-and Reporting Regulation-AtSMV)

Non-official Table of Contents

AtSMV

Date of expiry: 14.10.1992

Full quote:

" Nuclear Safety Officer and Reporting Regulation of 14. October 1992 (BGBl. 1766), which was last amended by Article 1 of the Regulation of 8 June 2008. June 2010 (BGBl. I p. 755) "

:Last modified by Art. 1 V v. 8.6.2010 I 755

For details see the menu under Notes

Footnote

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

Non-Official Table of Contents

Input Formula

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

First Section
Scope

Non-official Table of contents

§ 1 Scope of application

(1) This Regulation shall apply to installations pursuant to Section 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 apply.(3) This Regulation shall not apply:
1.
for installations for the division of nuclear fuel, the maximum power of which is 50 Kilowatt thermal continuous performance does not exceed, as well as
2.
for storage in accordance with § 6 of the Atomic Energy Act and installations in decommissioning pursuant to § 7 (3) of the German Atomic Energy Act Atomic law, provided that
a)
the nuclear fuel from the storage facility or the plant in Decommissioning was removed and
b)
the remaining activity inventory in the case of open radioactive substances is no more than 107times and in the case of enclosed radioactive substances no more than 1010times the free limits set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.

Second section
Core technical Security Officer

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§ 2 Order of the nuclear security officer

(1) The owner an authorisation to operate an installation pursuant to Section 7 (1) of the Atomic Energy Act (operator) has, for the duration of the operation of the plant, a nuclear technical plant pending the granting of a permit to decommission the installation pursuant to Section 7 (3) of the Atomic Energy Act. Security officers (security officers) and their representatives 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: Order is not required.(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 departure of the person in writing. A copy of the advertisement shall be handed out to the security officer and to the operational or personnel council.(3) Only one person may be appointed to the security officer who has no facts in respect of which there are concerns about their reliability and who has the technical expertise required to carry out their duties. 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, the supervisory authority may require that the operator should have another Security officer appointed.(4) To apply appropriately to the representative:
1.
paragraph 1 sentence 2 and 3,
2.
paragraphs 2 and 3, as well as
3.
§ § 3 to 5 and § 10.
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§ 3 obligations of the operator

(1) The operator has to assist the security officer in the performance of his duties and, in particular, to the extent that is required to carry out its duties, to provide technical and auxiliary staff.(2) The operator shall ensure that the safety officer receives the information necessary for the performance of his duties and informs him of administrative acts and other measures concerning his duties or powers. . Non-official table of contents

§ 4 Security officer tasks

(1) The security officer has a location within the operational organization at the site. Without prejudice to the responsibility of the operator
1.
for the evaluation of
a)
Reporting-liable events (§ 6),
b)
Other disturbances in your own asset,
c)
Information about notifiable events in others Installations with a view to their importance for their own plant
and to participate in the performance of these tasks,
2.
in the preparation of these tasks ,
3.
The operator's findings on safety deficiencies, as well as suggestions to remedy the shortcomings or to increase the risk of the safety of the operator. immediately inform
4.
to participate in the planning of changes to the plant or its operation,
5.
checking the reporting of reporting events in accordance with § 10,
6.
at the exchange of experience (2) The Safety Officer has to perform his duties with the Operations or Staff Council and the skilled personnel in the performance of his/her duties.
Work safety, as well as in accordance with other regulations, to cooperate in the plant and to inform them 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. Non-official table of contents

§ 5 Security officer position

(1) The security officer must not perform his or her duties is disabled and is not penalised because of its activities.(1a) The operator shall ensure, by means of internal organisational measures, that the safety officer does not carry out any functions with direct production responsibility.(2) The operator shall, by means of internal organisational measures, ensure that the safety officer can present his proposals and concerns directly to the management if he has not been able to agree with the head of the installation and, because of the particular importance of the matter, it deems it necessary to take a decision by the management. 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 have the following information: 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/her duties according to § 4 shall be defined in detail in the Operations Manual.

Third section
Reporting of accidents, incidents and other events

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§ 6 reporting obligation

(1) The holder of a permit pursuant to § 6 or § 7 (1) or (3) sentence 1 of the Nuclear law (reporting requirements) has to report accidents, incidents or other events that are significant for nuclear safety (notifiable events) of the supervisory authority.(2) Reporting requirements are events that meet the reporting criteria listed in Annexes 1 to 5.(2a) Annex 4 shall apply to installations in decommissioning from the date on which the supervisory authority, at the request of the operator, has determined, by means of an administrative act, that the application criteria set out in the preliminary note to Annex 4 are met.(3) The notifiable person shall immediately notify the entry of a notifiable event to the authority responsible for public safety and order, and to the authority responsible for civil protection, to the extent that this is necessary to protect the Population before life and health hazards is required.(4) (omitted) unofficial table of contents

§ 7 Contents of the written report

(1) The reporting person shall have the right to report to the supervisory authority. in accordance with Article 8 (1) (1) (1) (1) to (4), by means of an official notification form, to describe the notifiable event, its causes and effects, the elimination of the effects and the measures to be taken against repetition, in such a way as to ensure that they are nuclear safety can be adequately assessed. The Supervisory Authority shall disclose an official notification form.(2) In the written notification by telecommunication in accordance with § 8 (1) Nos. 1 and 2, the notifiable person shall provide the information required by the notification form, insofar as information can be made immediately and data is known. Non-official table of contents

§ 7a Electronic communications

(1) The transmission of electronic documents is only allowed when the Supervisory authority has informed the reporting person that access has been opened for this purpose.(2) The parties involved shall take appropriate measures to ensure data protection and data security in accordance with the respective state of the art. In the case of the use of generally accessible networks, encryption methods shall be used which correspond to the state of the art. Non-official table of contents

§ 8 Reporting procedure

(1) Reporting subject events are to be reported
1.
Category S: immediately after being informed by telephone, and in writing by telecommunication transmission; at the latest on the fifth working day after being notified of the addition and, if necessary, correction of the notification by means of the notification form;
2.
category E: no later than 24 hours after Knowledge by telephone and in writing by telecommunication transmission; at the latest on the fifth working day after knowledge supplementation and, if necessary, correction of the message by means of the notification form;
3.
Category N: at the latest on the fifth working day after knowledge by reporting form;
4.
Category V: at the latest on the tenth working day after knowledge by means of the notification form.
The supervisory authority may take more detailed instructions on the notification.(2) If all necessary 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 made 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 justify the reporting obligation.(4) A notifiable event shall fill a number of the reporting criteria listed in Annexes 1 to 5 under different numbers, all of which shall be indicated; in the cases referred to in paragraph 2, at the latest in the final written declaration Message.(5) Where the notification criteria to be specified are assigned to a number of categories referred to in the first sentence of paragraph 1, the form and time limit shall be determined by the category with the shortest reporting period.(6) A notifiable event also includes:
1.
all events that are caused by the first event , as well as
2.
all similar failures, damages, dysfunctions or findings on similar devices, systems, or systems, or Parts of the asset that are determined in the course of investigations into this event.
(7) If, after knowledge of all relevant facts, it becomes clear that a reported event was not subject to reporting, the notifiable person shall notify the Supervisory authority shall, in writing, specify the relevant facts in writing. Non-official table of contents

§ 9 Supplementary obligations of the reporting person

(1) The notifiable person shall show the number of notifiers monthly to the supervisory authority. -events which have been reported since the notification of the previous notification.(2) In the case of events which are subject to reporting requirements and which are responsible for the occurrence of defective parts of the system or in the course of which damage to important parts of the system occurs, the notifying party shall take measures to ensure that a reference is made to the person who is responsible for the occurrence of such damage. Allow subsequent clarification and verification of the exact causes and consequences of the event subject to reporting. In order to provide evidence, it is particularly suitable:
a)
Storage of defective components in unchanged Form,
b)
Production of light images,
c)
Apply a detailed Damage documentation.
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§ 10 Security Officer Audit

The security officer has the To verify the accuracy and completeness of the reporting of an event subject to reporting, to record the result of his examination on the registration form and to provide it with his signature. The same applies to the display in accordance with Section 9 (1).

Fourth Section
Bußmonetary Regulations

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§ 11 Administrative Offences

is a breach of order within the meaning of Section 46 (1) (4) of the Atomic Energy Act, who intentionally or negligently
1.
contrary to § 6, paragraph 1 or paragraph 3, respectively in conjunction with § 7 paragraph 1 sentence 1 or § 8 paragraph 1 sentence 1, also in conjunction with § 1 paragraph 2 or § 8 paragraph 6, or contrary to § § 8 (6) 8 (2) sentence 2 or 3 sentence 3 a notification not correct, not complete or not timely, an advertisement not, not correct, not fully or not in time or a report not correct, not correct, not correct fully or not in time,
1a.
(dropped)
2.
contrary to § 9 (1) an advertisement not, not correct or not in good time, 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 Ratio To

§ 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. Non-official table of contents

Appendix 1 Reporting criteria for notifiable events in assets according to § 7 of the Atomic Energy Act for the splitting of nuclear fuels on the industrial production of electricity

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

Content Directory Preface

1.Radiology and Radiation protection
1.1Radioactive substance derivation
1.2 Release of radioactive substances
1.3contamination
1.4 Discharge of radioactive materials
2.Plant technology and operation
2.1Functional disturbances, damage or outages in the security system or in other safety-related systems or parts of the system
2.2Damages or leakages on piping or containers
2.3 Criticality Disorders
2.4Lots of loads; handling, storage, or transport events
2.5Other events
3.external and intra-plant impacts Events
3.1external actions
3.2 Asset Internal


Preface

The reporting criteria for notifiable events in plants for the splitting of nuclear fuel for the commercial generation of electricity, to the extent that: Examples from the field of plant technology are given, reference to reactor systems with light water reactors. For other types of reactors, the reporting criteria should be applied in accordance with the relevant criteria.
1.
Radiology and Radiation protection If the following criteria relate to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, a mean area of 300 square centimetres shall be used.
1.1
derivation of radioactive material criterion S 1.1.1derivation of radioactive substances with air or water, in which the activity derived within 24 hours is
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
exceeds the maximum activity levies fixed by the competent authority in the calendar year.
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 at which it is to be found that the activity liberated within 24 hours
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
means more than 10% of the maximum permitted by the competent authority for discharges in the calendar year Activity charges.
criterion E 1.2.1Release of radioactive substances into the environment at which it is to be obtained that the released activity is
-
to body doses that amount to more than 10 percent of the limits according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or
-
more than 10 percent of the maximum activity charges specified by the competent authority for derivations in the calendar year.
criterion N 1.2.1Release radioactive substances into the environment which do 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 range marked as a control area, the Location 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, where this is not marked as a blocking area, the local dose rate is the value of 3 millisieverts per hour for greater than 24 hours, or
-
required to set up a new control range.
1.3
Contamination criterion E 1.3.1contamination within the monitoring area, which is 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 values set out in 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 a range which shall be shall not be contaminated, which exceeds a thousandfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and whose total activity in becquerel exceeds the hundredfold of the values set out in Annex III Table 1, column 2 of the Radiation Protection Regulation.
1.4
Disappearance of radioactive material criterion S 1.4.1XX_ENCODE_CASE_One proliferation of radioactive substances from the plant by moving to an area
-
outside of monitoring 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 that has been transferred to it is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and 10 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 a section
-
outside of the monitoring areas on the premises, if the activity that has been moved 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, if the activity that has been moved there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and the simple one of the Values according to Appendix III, Table 1, column 2 of the Radiation Protection Regulation
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 2.1.1function malfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that the number of security steers required for control of the control of faults is no longer available. When this is the case, is defined in the approved operating rules. criterion E 2.1.1
-
dysfunction, damage or outage in the security system (including related auxiliary and secondary systems) with the result that only the interpreters for the control of the accident are still Required number of security devices are available. When this is the case, it is specified in the approved operating rules.
-
Full failure of a security function, which is used exclusively for control purposes. is provided for emergency situations.
criterion N 2.1.1
-
malfunction, damage or failure in the security system (including related auxiliary and auxiliary systems), with the result that at least one security subsystem is not available.
-
dysfunction, damage or failure in any other 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 Malfunction, damage, or outages:
-
single card or transmitter in the reactor protection system , or in the case of technical guidance bodies performing comparable tasks, provided that the failure is self-reporting, is fixed within 8 hours and is not to be reported according to criterion N 2.1.2,
-
in other safety-critical systems that are fixed in less than 24 hours, or outages of these systems for which approved replacement measures are provided, if the respective event is not to be reported according to criterion N 2.1.2.
criterion N 2.1.2damage, failure or finding, with reference to a systematic error
-
on the security system or any other security-related system, or Asset part,
-
on a component, part, or assembly in an operational system when the component, component, or assembly is at comparable conditions and in comparable quality in the security system or in any other important safety system.
criterion N 2.1.3failure of or damage to a facility of the Technical and technical fire protection systems shall not be notified of any failure of or minor damage to individual components of the fire protection system or the fire protection system, by which the fire protection functions shall not be inadmissible Criterion S 2.1.4Functional disturbance of a safety, bubble or relief valve of the pressure-carrying enclosure:
-
Open not provided unless automatic shut-off of the bleed line occurs (except boiling water reactors (SWR)),
-
Do not close after response, unless automatic shut-off of the bleed line occurs (except SWR),
-
Non-opening of a safety valve in case of request.
criterion E 2.1.4Functional disturbance of a safety, bubble or relief valve:
-
unscheduled opening of a print-leading safety, bubble, or relief valve Enclosure, if the incident is not to be reported according to criterion S 2.1.4,
-
Non-closing of a pressure-carrying safety, bubble or relief valve Enclosure, if the incident is not to be reported according to criterion S 2.1.4,
-
Non-opening of a pressure-carrying enclosure in the pressure-carrying enclosure in the Request case,
-
Non-opening of a fresh steam safety valve in the request case (excluding SWR),
-
Non-closing a fresh steam safety valve, unless automatic shutoff occurs,
-
Non-opening of any other safety valve in the event of a request to set up the security system or to another safety-related system, or System part.
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:
-
unscheduled opening of a safety and relief valve (at SWR) if only one valve is affected and it is automatically closed or closed before automatic reactor protection actions are triggered,
-
Non-closing of a Safety and relief valve (at SWR), if only one valve remains open and this valve closes automatically before automatic reactor protection actions are triggered, or is brought to close,
-
unscheduled opening of a pressure-holder blow-off valve (for pressurized water reactors (DWR)) if it closes before the blow-off shut-off valve closes or before clearing or escape alarm for the safety container, whether or not to be closed or closed,
-
Non-closing of a fresh steam safety valve, in which a automatic shut-off of the blow-off line,
-
unscheduled opening or non-closing of a safety valve on any other device of the Safety systems or any other safety-related system or part of the system.
criterion E 2.1.5Safety-and significant exceedingly exceeding of a design value for reactor core, pressure-carrying enclosure, Safety containment or safety-related parts of the fresh steam and feedwater system. criterion N 2.1.6Safety engineering significant deviation from the specified condition in the safety system (including the associated auxiliary and/or auxiliary equipment). (a) or in any other safety-related system or sub-system. Deviations in a number of redundant safety devices which, at the same time, fail to comply with these safety-related devices in accordance with the Safety specifications are also to be reported in accordance with criterion S 2.1.1 or criterion E 2.1.1.
2.2
Damages or leaks to piping or container criteria S 2.2.1leakages that lead to the triggering of a protection action. Not to be reported:
-
the remaining of Safety and relief valves (for SWR),
-
false excitations of protective actions,
-
Leakages in cold plant, which can be quickly prevented (for example, incorrect opening of a fitting with subsequent closing of this or a redundant .
criterion E 2.2.1fracture or crack with leakage, which requires a shutdown of the system for safety reasons, on one of the following systems:
-
Reactor cooling circuit or the directly adjoining systems up to and including the areas, which are charged with reactor coolant pressure,
-
fresh steam system up to the turbine and bypass valves as well as to all against this pressure chamber unlockable pipe sections,
-
on the feedwater system and 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
-
Setting up the security system or any other activity-leading system,
-
Enclosure of the Fresh steam or feedwater system up to and including the outer shut-off valve,
-
enclosure of the fresh steam or feedwater system outside the external Shut-off valve, provided that the damage indicates a lack of design or an unconsidered load.
Not to be reported:
-
individual sealing or flanking layers outside the print-leading enclosure,
-
Tropfleckagen an Seals or flanges within the pressure-carrying enclosure,
-
Stopfbox leakages as part of the design of the stuffing of stuffed buoy within the pressure-carrying leading edge Enclosure,
-
leakage of measuring, dewatering or venting lines in the turbine area.
criterion E 2.2.2Steam boiler heating pipe leakage, which is a waste the asset required. criterion E 2.2.3
-
failure of a pressure vessel, a fitting, or Pump housing,
-
Disassembly of a flywheel,
-
Break 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 vessel, if it is to be concerned that a failure of the container On the basis of this damage, either directly or in a chain of subsequent events, leads to the endangering of a safety-related system or part of the system, or triggers an accident.
2.3
Criticality disturbing criterion S 2.3.1Criticality without sufficient power-off reserve of the rapid shutdown system. criterion E 2.3.1
-
Unallowable Reaction strangles or
-
unallowable deboration in pressurised water reactors.
2.4
crashes of loads; events at Handling, storage, or transport criterion S 2.4.1crash of a load into the fuel-element storage tank or reactor space with the sequence
-
a loss of subcriticality or
-
of a non-lockable larger leakage (more than 0.3 Liters per second.
criterion E 2.4.1crash
-
of a fuel element in the Fuel-element storage basins, the transport or storage containers or the reactor space,
-
of any other load in the fuel-element storage tank or the reactor chamber with the sequence a larger (more than 0.3 liter per second) lockable or low (0.3 liters per second or less) leakage,
-
a heavy load in a Room where a safety-related system or part of the system is located.
criterion N 2.4.1
-
Security-related event in the transport, handling or storage of fuel elements or other radioactive materials within the plant or the Asset facilities.
-
Security-critical event during transport or handling of a load.
-
Security-critical damage to a hoist, or a transport or handling device.
2.5
Other event criteria E 2.5.1Event with automatic response of a print-leading containment safety valve. criterion N 2.5.1Damage to Reactor pressure vessel installations, at the reactor core or on steam generator installation. Non-reporting of individual fuel element damage, provided that they do not exceed cracks or slight deformations and no indication of systematic weak points delivern.criterion N 2.5.2A loose part or a foreign body
-
in the print-leading enclosure or
-
in containment of the other security devices,
if a function that is important to the security is impermissible, or Criterion N 2.5.3Damages caused by a water or condensation impact or systematic damage to suspensions, supports or damping devices in a safety-related manner important pipeline or component. criterion N 2.5.4Damage to reactor coolant pumps that require the installation to be shut down. Criterion N 2.5.5Outage 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:
-
Fast downshifts in start-up phase at low Reactor power (up to 5%),
-
solutions that are operational or provided.
criterion N 2.5.8Safety-related damage to the reactor a load-bearing structure of a building s.criterion N 2.5.9Event, which requires a significant change in the security specifications.
3.
external actions and Internal events
3.1
Impacts of external criterion S 3.1.1Damage caused by earthquakes, aircraft crash or explosion pressure wave to
-
a building in which a security-related system or part of the system
-
a security-critical system or part of the asset with the result that a security facility is requested.
criterion E 3.1.1XX_ENCODE_CASE_One external action, which requires the installation to be shut down or shut down for safety reasons.
3.2
Asset internal event criterion S 3.2.1Internal fire, internal explosion, flooding or any other effect from the inside to an extent to which it is to be provided that the number of security components required for control of the accident does not take place more available. criterion E 3.2.1Plant internal fire, internal explosion, flooding or other effect from within to an extent to obtain that only the interpreters required for the control of the disturbance Number of safety devices available. 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 there is a safety-related facility. Not to be reported are locally limited micro-fires related to change- or maintenance work for which preventive fire protection measures have been taken and which have been used in fire-fighting operations.
unofficial table of contents

Appendix 2 Reporting criteria for notifiable events in assets according to § 7 of the Nuclear Power Supply and disposal law

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


of


1.Radiology and Radiation Protection
1.1Radioactive Substances
1.2Radioactive release Fabrics
1.3contamination
1.4enforced disappearance radioactive substances
2.Plant engineering and operation
2.1 Function disturbances, damages or failures in safety-related systems or plant parts
2.2Damages or leakages to Pipelines or containers of safety-related critical systems
3.external and external actions
3.1external impact
3.2Asset internal Events


1.
Radiology and Radiation Protection at the following Criteria relating to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, shall be based on a mean area of 300 square centimetres.
1.1
derivation of radioactive material criterion S 1.1.1derivation of radioactive substances with air or water, in which the activity derived within 24 hours is
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
exceeds the maximum activity levies fixed by the competent authority in the calendar year.
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 at which it is to be found that the activity liberated within 24 hours
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
means more than 10% of the maximum permitted by the competent authority for discharges in the calendar year Activity charges.
criterion E 1.2.1Release of radioactive substances into the environment at which it is to be obtained that the released activity is
-
to body doses that amount to more than 10 percent of the limits according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or
-
more than 10 percent of the maximum activity charges specified by the competent authority for derivations in the calendar year.
criterion N 1.2.1Release radioactive substances into the environment which do 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 range marked as a control area, the Location 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, where this is not marked as a blocking area, the local dose rate is the value of 3 millisieverts per hour for greater than 24 hours, or
-
required to set up a new control range.
1.3
Contamination criterion E 1.3.1contamination within the monitoring area, which is 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 values set out in 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 a range which shall be shall not be contaminated, which exceeds a thousandfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and whose total activity in becquerel exceeds the hundredfold of the values set out in Annex III Table 1, column 2 of the Radiation Protection Regulation.
1.4
Disappearance of radioactive material criterion S 1.4.1XX_ENCODE_CASE_One proliferation of radioactive substances from the plant by moving to an area
-
outside of monitoring 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 that has been transferred to it is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and 10 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 a section
-
outside of the monitoring areas on the premises, if the activity that has been moved 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, if the activity that has been moved there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and the simple one of the Values according to Appendix III, Table 1, column 2 of the Radiation Protection Regulation
2.
Plant engineering and operation
2.1
dysfunction, damage or outages in safety-related systems or system-side criterion S 2.1.1Functional disturbance, damage or failure of a safety-related equipment, so that a plant condition has occurred, which has a driving effect on the population or the environment or if this is to be provided. criterion E 2.1.1Functional disturbance, damage or failure on a safety-related equipment, if the installation is to be designed for this purpose and if the operation of the installation or the partial installation can not be continued for safety reasons, if the plant is to be operated. Damage or outage
-
of a security-critical facility or
-
a component or a component in any other device of the system or partial system, provided that a corresponding component or component is in a safety-related equipment is used.
Do not report any malfunctions, damage or outages:
-
individual technical components in the control equipment of the safety-related equipment required for the control of malfunction, if the failure is self-reporting, is fixed within 24 hours and is not to be reported according to criterion N 2.1.2,
-
in the other safety-related systems that are in less than 24 hours, or within the allowed repair times specified in the approved operating rules, provided that the function of the system is maintained,
-
of another safety-critical system for which replacement measures are provided for a limited period of time in the approved operating rules, provided that the event is not to be reported according to criterion N 2.1.2,
-
on individual components of the technical or technical fire protection system, by which the fire protection functions do not have been inadmissible if the event is not to be reported in accordance with criterion N 2.1.2.
The competent authority may specify additional plant-specific details for the criterion N 2.1.1. criterion N 2.1.2outage, damage or Findings with reference to a systematic error in an important safety-related establishment. criterion N 2.1.3Safety-related deviation from an officially defined value of the plant technology or the operating system criteria E 2.1.4/N 2.1.4Request of an active security facility 1) .criterion N 2.1.5Overstepping of radioactive substances into a system, component, or component, if the System, component or component not subject to radioactive substances during normal operation. criterion S 2.1.6Criticality event. criterion E 2.1.6Event which violates the safety principles of the safety of criticality Criterion N 2.1.6Event which impairs the security of the criticality but did not violate the safety principles of the security of criticality. criterion N 2.1.7Safety-related event during transport, handling or the storage of radioactive substances on the operating site. criterion N 2.1.8Event which requires a significant change in the safety specifications. criterion N 2.1.9Event in the extension or modification of the installation or the partial installation, which shall: Effects on the proper functioning of a safety-related system or part of the plant may have an impact on existing operations. criterion V 2.1.10Befinding in a safety-related facility prior to the operation of the plant or of the Partial installation, which is based on a design error or a weakness of the quality system. criterion V 2.1.11Event in the construction of the installation or the partial installation, the effect on the proper functioning of a system safety-important system or part of the plant during the future operation (e.g. fire, explosion, flooding, crash of a heavy load).
2.2
Damages or leaks on piping or containers safety-critical system criterion S 2.2.1leakage in an activity-leading system that is driving on the 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 shall not be used for the Criterion N 2.2.1leakage or damage, in particular crack, deformation or undershooting of the nominal wall thickness on a pipeline or a container of a safety-related important or an activity-leading system or asset ls.Not to report individual drip spots are to
-
Seals, flanges, piping, or containers of non-activity-bearing systems and plant parts,
-
Seals and Flank Activity-Leading Systems and Asset Parts.
3.
Impacts of External and internal system events
3.1
Impacts of external criterion S 3.1.1XX_ENCODE_CASE_One earthquake, 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 it is to be provided. criterion E 3.1.1earthquake, aircraft crash, explosion pressure wave or any other external action, provided that the 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 external action, provided that the plant is affected by this and this is not covered by the criteria S 3.1.1 or E 3.1.1.
3.2
Asset internal event criterion S 3.2.1Plant internal fire, plant-internal explosion, heavy chemical Reaction, flooding, the crash of a heavy load or any other effect from the inside, so that a plant condition has occurred, which has a beneficial effect on the population or the environment or in which this is to be obtained. 3.2.1Plant internal fire, internal plant explosion, severe chemical reaction, flooding, the crash of a heavy load or any other effect from the inside, if the operation of the installation or the subplant for safety reasons can not be continued. 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 facility is affected and this is not covered by the criteria S 3.2.1 or E 3.2.1.
1)
The relevant security facility and the associated reporting category shall be determined by the competent authority.
Non-official table of contents

Appendix 3 Reporting criteria for notifiable events in annexes § 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) Table of Contents Preface

1.Radiology and Radiation Protection
1.1Radioactive Substances
1.2Radioactive release Fabrics
1.3contamination
1.4enforced disappearance radioactive substances
2.Plant engineering and operation
2.1 Function faults, damage or failures in the security system or in other safety-related systems or plant parts
2.2 Damages or leakages on piping or containers
2.3Criticality Disorders
2.4crash of loads; handling events, storage, or transport
2.5Other Events
3.Outside and Internal Events Impacts
3.1 Impact from outside
3.2Asset internal events
4. Events before approval to load the


Preface

The nuclear fuel splitting plants operated in the Federal Republic of Germany, which are mainly used for research purposes, differ in their hazard potential as well as in facilities belonging to their safety systems as well as in the number of redundancies of safety-related important systems or parts of the plant. Part clearly from each other. For a uniform application of the individual reporting criteria in these assets, a plant-specific concretization is required.
1.
Radiology and radiation protection In the following criteria reference is made to the values of Appendix III, Table 1, column 4 of the Radiation Protection Regulation, is a central area of 300 square centimetres.
1.1
The derivation of radioactive material criterion S 1.1.1discharges of radioactive substances with air or water, in which the radioactive substances are discharged into the air or water, Activity derived from 24 hours
-
to exceed the limits of body doses in accordance with § 47 Paragraph 1, first sentence, of the Radiation Protection Regulation, or
-
the maximum activity charges laid down by the competent authority in the calendar year exceeds.
criterion E 1.1.1discharges of radioactive substances with air or water, in which the derived activity exceeds the maximum permitted activity levels specified by the competent authority.
1.2
Release of radioactive substance criterion S 1.2.1Release of radioactive substances into the environment at which it is to be found that the activity liberated within 24 hours
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
means more than 10% of the maximum permitted by the competent authority for discharges in the calendar year Activity charges.
criterion E 1.2.1Release of radioactive substances into the environment at which it is to be obtained that the released activity is
-
to body doses that amount to more than 10 percent of the limits according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or
-
more than 10 percent of the maximum activity charges specified by the competent authority for derivations in the calendar year.
criterion N 1.2.1Release radioactive substances into the environment which do 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 range marked as a control area, the Location 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, where this is not marked as a blocking area, the local dose rate is the value of 3 millisieverts per hour for greater than 24 hours, or
-
required to set up a new control range.
1.3
Contamination criterion E 1.3.1contamination within the monitoring area, which is 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 values set out in 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 a range which shall be shall not be contaminated, which exceeds a thousandfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and whose total activity in becquerel exceeds the hundredfold of the values set out in Annex III Table 1, column 2 of the Radiation Protection Regulation.
1.4
Disappearance of radioactive material criterion S 1.4.1XX_ENCODE_CASE_One proliferation of radioactive substances from the plant by moving to an area
-
outside of monitoring 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 that has been transferred to it is 100 times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and 10 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 a section
-
outside of the monitoring areas on the premises, if the activity that has been moved 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, if the activity that has been moved there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and the simple one of the Values according to Appendix III, Table 1, column 2 of the Radiation Protection Regulation
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 2.1.1function malfunction, damage or failure in the security system (including associated auxiliary and secondary systems), with the result that the number of security steers required for control of the control of faults is no longer available. When this is the case, is defined in the approved operating rules. criterion E 2.1.1
-
dysfunction, damage or outage in the security system (including related auxiliary and secondary systems) with the result that only the interpreters for the control of the accident are still Required number of security devices are available. When this is the case, it is specified in the approved operating rules.
-
Full failure of a security device that is responsible for the tightness of the building, which encloses the reactor, is required.
criterion N 2.1.1
-
malfunction, damage or failure in the security system (including related auxiliary and secondary systems), with the result that at least one security subsystem is not available.
-
dysfunction, damage or failure in any other 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 solely for the control of events with a very low probability of occurrence (effects of
or from inside)
Do not report any 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, within 8 hours is fixed and not to be reported according to criterion N 2.1.2,
-
in other safety-critical systems that are fixed in less than 24 hours where the event is not to be reported according to criterion N 2.1.2.
criterion N 2.1.2outage, damage or finding, with reference to a systematic error
-
on the security system or any other security-related system, or Asset part,
-
on a component, part, or assembly in an operational system when the component, component, or assembly is at comparable conditions and in comparable quality in the security system or in any other important safety system.
criterion N 2.1.3failure of or damage to a facility of the Technical and technical fire protection systems shall not be notified of any failure of or minor damage to individual components of the fire protection system or the fire protection system, by which the fire protection functions shall not be inadmissible Criterion N 2.1.4Non-opening or non-closing of a safety valve in another important system or part of the system. criterion E 2.1.5Safety-and significant overrun of interpretive values
-
at the reactor core,
-
in the primary cooling system or Reactor tank,
-
in the building, which is the primary cooling system ,
-
in the case of an experimentation device whose failure is likely to affect the reactor and its safety devices, as well as other safety-related important systems or parts of the system cannot be excluded, as well as
-
in the secondary circuit, provided that these safety-related 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. redundant security devices, which at the same time represent a failure of these security devices in accordance with the security 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 piping or container criterion S 2.2.1leakage at the primary cooling system leading to the triggering of a protective action. Not to be reported are mismanagement of protective actions or leaks in swimming pool reactors.criterion E 2.2.1
-
Break 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 is a deer
-
leakage via lines where the primary coolant loss, with or without re-feeding, is basically limited due to the integration of the primary coolant loss, that the sufficient cooling capacity of the reactor is ensured. Not to be reported are leakages in training, research, isotopes, general atomic reactors (TRIGA reactors).
-
leakage in the secondary circuit, if this safety-related tasks, and in which a shutdown of the installation is required for safety reasons.
criterion N 2.2.1
-
Leakage or damage to a security system setup or other activity-leading system,
-
Leakage or damage to the enclosure of the secondary circuit, provided that it performs safety tasks,
-
Leakage in the secondary circuit where it is necessary for safety reasons to depart the system.
Not to report are individual sealing or flanging systems as well as drip spots outside of the safety system s.criterion E 2.2.3
-
failure of a pressure vessel, of a fitting or pump housing,
-
Explode a flywheel,
-
Break a Pipeline,
if this can cause a malfunction of a system or part of the system which is important in terms of safety. criterion N 2.2.3Damage to a pressure vessel, if it is to be concerned that a failure of the container is The reason for this damage, either directly or in a chain of subsequent events, leads to the endangering of a system or part of the system that is important to safety engineering or triggers a malfunction.
2.3
Criticality disturbing criterion S 2.3.1Criticality without sufficient power-off reserve of the rapid shutdown system. criterion E 2.3.1
-
Unallowable Reaction strangles or
-
improper extraction of neutron absorbing fabrics.
2.4
crashes of loads; events in case of handling, storage or transport criterion S 2.4.1crash of a load in one of the following spatial areas:
-
Reactor basin or reactor vessel,
-
Primary circuit up to and including the first Shut-off,
-
Settling Tank, Fuel Element Storage Basin,
-
Experimenting Facilities,
-
Jet Pipes,
with the consequence of a loss of subcriticality or a non-lockable larger leakage (more than 0.3 litres per second). criterion E 2.4.1crash
-
a fuel element in the fuel element storage basin, in the transport or storage container, or into the reactor tank or reactor vessel,
-
some other load in the fuel-element storage basin, reactor tank or reactor vessel, with the result of a larger (more than 0.3 litres per second) lockable or small (0.3 litres per second or less) of non-lockable leakage,
-
of any other load into a space of the primary circuit up to and including the first shut-off or the experimental equipment or the jet pipes, provided that there is the possibility of loss of coolant in the event of damage, with the consequence of a larger (more than 0.3 litres per second) which can be shut off (0.3 litres per second or less), less) non-lockable leakage,
-
a heavy load in a room in which a safety-related system or part of the system
criterion N 2.4.1
-
Safety-related event during transport, which is Handling or storage of a fuel assembly or other radioactive materials within the installation or plant site.
-
Important safety engineering Event during transport or handling of a load.
-
Security-related damage to a hoist, a transport, or Handling device.
2.5
Other event criteria E 2.5.1
-
Full failure of primary coolant pumps (does not apply to TRIGA and swimming pool reactors).
-
Full blocking of cooling channels by loose parts or foreign bodies.
Criterion N 2.5.1Damage at the reactor core, reactor tank internals, reactor tank assemblies or Non-reporting are individual fuel element damage, provided that they do not exceed cracks or slight deformations and do not indicate systematic weak spots. criterion N 2.5.2A loose part or a foreign body
-
in the reactor tank or reactor vessel, or primary cooling circuit, or
-
in another setup of the security system,
when a safety-related function, such as ensuring the integrity or cooling of the In the case of TRIGA reactors and swimming pool reactors, the detection of a loose part or of a foreign body shall not be reported if it is possible to exclude that this part or this foreign body is also excluded from the unfavorable circumstances than in the current case to
-
an impairment of cooling,
-
having an impairment of the turn-off function or
-
to a fuel-element damage
Criterion N 2.5.3Damage caused by a water or condensation impact or systematic damage to suspensions, supports and damping devices on a safety-related important pipeline or component. criterion N 2.5.4
-
Damage to primary coolant pumps that require a shutdown of the asset.
-
Full failure of primary coolant pumps during the nuclear power operation; in swimming pool reactors, also complete failure of primary coolant pumps shortly after Disconnection of the reactor.
criterion N 2.5.5XX_ENCODE_CASE_One failures of more than one main pump of the secondary circuit during the nuclear power operation, if the secondary circuit truthfully performs safety-related tasks. the power supply, provided that this no longer ensures the electrical supply of an important safety device. criterion N 2.5.7Request or misexcitation of a security subsystem by means of the Reactor protection system.Not to report is a reactor quick shutdown,
-
which without -
-
which is clearly based on a network fault, or automatically performed by the personnel or automatically to protect the experimentation facilities,
-
(does not apply to installations in which the electrical supply of an important safety equipment for post-heat removal is thereby impaired),
-
which takes place in the start-up phase at low reactor output; unless otherwise defined in the operating regulations for the "low reactor power", the reactor output Low performance of less than 5 percent,
-
that occurs at zero power without required forced cooling, or
-
which takes place in the case of personnel training during reactor operation without the forced cooling required.
criterion N 2.5.8Safety engineering significant damage to a load-bearing structure A constructional criterion N 2.5.9Event, which requires a significant change in the security specifications.
3.
external and internal effects Events
3.1
impacts of external criterion S 3.1.1Damage caused by earthquakes, aircraft crash or explosion pressure wave to
-
a building in which a security-related system or part of the system
-
a security-critical system or part of the asset with the result that a security facility is requested.
criterion E 3.1.1XX_ENCODE_CASE_One external action, which requires the installation to be shut down or shut down for safety reasons.
3.2
Asset internal event criterion S 3.2.1Internal fire, internal explosion, flooding or any other effect from the inside to an extent to which it is to be provided that the number of security components required for control of the accident does not take place Criterion E 3.2.1Plant internal fire, internal system explosion, flooding or other effects from the inside to an extent to which it is to be obtained that only the interpreters required for the control of the disturbance are still required Number of safety devices available. 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 preventative scheduled fire protection measures have been taken and their application in fire-fighting was effective,
-
in the field of experimentation facilities, which are based on location, type and Could not affect the availability of a safety-related facility
4.
Events before the approval of the load the reactor criterion V 4.1findings in a system or part which is important in terms of safety and which is based on a design error or a weakness in the quality system. A system or part of the system where this event is of importance for later secure operation.
Table of contents

Appendix 4 Reporting criteria for notifiable events in installations in decommissioning according to § 7 paragraph 3 of the Atomic Energy Act

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

Content Directory Preface

1.Radiology and Radiation protection
1.1Radioactive substance derivation
1.2 Release of radioactive substances
1.3contamination
1.4 Discharge of radioactive materials
2.Plant technology and operation
2.1Functional Disorders, Damage, or Failures in Safety-related Facilities
2.2 Damages or leaks on piping or containers
2.3crash of loads; events in handling, storage, or transport of radioactive substances
2.4Other events
3. Impacts from outside and on-site events
3.1external actions
3.2Asset Internal


Preface

The reporting criteria for notifiable events for decommissioning assets, asset spaces, or Plant parts apply to assets that are used in
1.
for the splitting of nuclear fuel and where the Protection objectives "subkriticality" and "post-heat dissipation" are no longer relevant for the remaining operation of the plant in decommissioning, or
2.
not the division of In the case of nuclear fuels, the protection objective "subcriticality" is no longer relevant,
to the extent that it has already been granted a permit pursuant to Section 7 (3) of the Atomic Energy Act.
Do not present these application criteria, Depending on the type of approval and asset type, the assets 1, 2, or 3 continue to apply.
1.
Radiology and radiation protection If the following criteria relate to the values of Annex III, Table 1, column 4 of the Radiation Protection Regulation, a mean area of 300 square centimetres shall be used.
1.1
derivation of radioactive material criterion S 1.1.1derivation of radioactive substances with air or water, in which the activity derived within 24 hours is
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
exceeds the maximum activity levies fixed by the competent authority in the calendar year.
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 at which it is to be found that the activity liberated within 24 hours
-
to exceed the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation, or
-
means more than 10% of the maximum permitted by the competent authority for discharges in the calendar year Activity charges.
criterion E 1.2.1Release of radioactive substances into the environment at which it is to be obtained that the released activity is
-
to body doses that amount to more than 10 percent of the limits according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or
-
more than 10 percent of the maximum activity charges specified by the competent authority for derivations in the calendar year.
criterion N 1.2.1Release radioactive substances into the environment which do 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 range marked as a control area, the Location 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, where this is not marked as a blocking area, the local dose rate is the value of 3 millisieverts per hour for greater than 24 hours, or
-
required to set up a new control range.
1.3
Contamination criterion E 1.3.1contamination within the monitoring area, which is 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 values set out in 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 a range which shall be shall not be contaminated, which exceeds a thousandfold of the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation and whose total activity in becquerel exceeds the hundredfold of the values set out in Annex III Table 1, column 2 of the Radiation Protection Regulation.
1.4
Disappearance of radioactive material criterion S 1.4.1XX_ENCODE_CASE_One proliferation of radioactive substances from the plant by moving to an area
-
outside of monitoring areas on the premises, provided that the activity which has been 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 which has been 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
-
outside of monitoring areas on the premises, if the activity that has been moved there 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, if the activity that has been moved there is ten times the values set out in Annex III, Table 1, column 4 of the Radiation Protection Regulation, and the simple one of the Values according to Appendix III, Table 1, column 2 of the Radiation Protection Regulation
2.
Plant engineering and operation
2.1
Function disturbances, damage or failures in safety-related equipment criterion N 2.1.1Functional disturbance, damage or failure in a safety-related important Means that must be available for compliance with the protection objectives, with the result that
-
at least one redundancy of a security-critical system is not available or
-
If the malfunction, damage or failure occurs due to safety reasons, the degradation measures are interrupted in accordance with the approved operating rules
Do not report any malfunctions, damage, or outages
-
in the Safety-related facilities which are fixed in less than 24 hours or within the authorised repair times specified in the approved operating rules, provided that the functioning of the system is maintained
-
on safety-related facilities for which replacement measures are provided for a limited period of time in the approved operating rules; if the event is not to be reported in accordance with criterion N 2.1.2.
criterion N 2.1.2outage, damage or findings with reference to a systematic error in an important safety-related device. criterion N 2.1.3failure of or Damage to a device 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-technical fire protection, by means of which the Fire protection functions are not unacceptably affected. criterion N 2.1.4Safety-related significant deviation from the specified condition in a safety-related system or part of the plant or from one in the operating regulations
2.2
Damages or leaks to piping or container criteria N 2.2.1leakage, or Damage to a device that is important for activity conclusion or to any other activity-leading system or other activity-carrying component. Do not report individual drip spots on gaskets and Flanschen.criterion N 2.2.2
-
The failure of a print-leading component with immediate effect on A security-related system or
-
Damage to a pressure-carrying component, to the extent that it is necessary to obtain a failure due to the damage Immediately or in a chain of subsequent events leading to the risk of a safety-related system or part of the system
2.3
Crash of loads; events during handling, storage or transport of radioactive substance criterion N 2.3.1
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Crash of a load that might have caused or could have led to the impairment of a security-related system or asset part.
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Security-related event during the transport or storage of radioactive materials within the plant's site.
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Security-critical damage to a hoist or a transport or handling device
2.4
Other event criterion N 2.4.1Event that requires a significant change in the security specifications. criterion N 2.4.2Damage to a load-bearing structure of a building with the consequence that the availability of a safety-related important system or plant can be impaired. criterion N 2.4.3Ausinterpretative requirement of a safety-related important facility in its security function. to report are requirements that are carried out in a targeted manner by the personnel without a safety requirement or which are clearly attributable to network disturbances.
3.
External and Asset Internal Events
3.1
External criterion impacts 3.1.1XX_ENCODE_CASE_One earthquake, plane crash, explosion pressure wave or other external action, so that a plant condition has occurred,
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where the "Radioactive Substances Inclusion" or the "Radiation Exposure Limit" protection target has been violated and
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which has a beneficial effect on the population or the environment, or where this is to be obtained.
criterion E 3.1.1earthquake, 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 objective "limitation of exposure to radiation" has been infringed or is to be obtained.
3.2
Plant internal event criterion S 3.2.1Plant internal fire, plant internal explosion, heavy chemical reaction, flooding or other action from inside, so that a Asset state has occurred,
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where the containment target is "containment of radioactive substances" or Protection target "limiting 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 inside, so that a plant condition has occurred in which the protection target " containment of radioactive waste substances "or the protection objective" limitation of exposure to radiation " has been infringed or is to be concerned. criterion N 3.2.1Plant internal fire, internal explosion, flooding or any other effect from inside in a room or plant area, in the case of radioactive substances having 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. limited micro-fires in connection with the dismantling, modification or maintenance work for which preventive planned fire protection measures have been taken and the application of which was effective in firefighting.
Non-official Table of Contents

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

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

Content Directory Preface

1.Radiology and Radiation protection
1.1Radioactive substance release
1.2 contaminant
1.3radioactive material spilled
2. Technology and operation
2.1Functional faults, damage or outages in safety-related systems or Facilities
2.2Lots of loads; handling or transport events
2.3 Other Events
3.Outside and Internal Events Impacts
3.1external actions
3.2interior


Preliminary notice

The reporting criteria apply to the storage of nuclear fuel according to § 6 of the Atomic Energy Act. Therefore, the storage of nuclear fuel as well as the storage of solidified high-radioactive fission product solutions and the facilities and activities required for this purpose, including the internal company, are covered. Transports.
1.
Radiology and Radiation Protection The following criteria refer to the values of the Annex III, Table 1, column 4 of the Radiation Protection Regulation shall be based on an averaging area of 300 square centimetres.
1.1
Radioactive release Substance criterion S 1.1.1Release of radioactive substances into the environment in which it is to be found that the activity released within 24 hours of exceeding the limits of the body doses in accordance with § 47 (1) sentence 1 of the Radiation protection regulation. 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 regulation. 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 facility, so that outside the facility an area marked as a control area, the local dose rate exceeds 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, unless it is a lock area , the location dose performance exceeds the value of 3 millisieverts per hour for more than 24 hours, or
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the establishment of a new Control range is required.
1.2
Contamination criterion E 1.2.1contamination within the monitoring area, which is a hundredfold of the values after Annex III, Table 1, column 4 of the Radiation Protection Regulation, and its total activity in Becquerel more than 10 times the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation. within the control area, which exceeds a thousandfold of the values laid down in Annex III, Table 1, column 4 of the Radiation Protection Regulation in an area which cannot be contaminated when the holding is intended to be carried out in accordance with Annex III, and the total activity of which shall be in the range of Becquerel is more than a hundredfold of the values set out in Annex III, Table 1, column 2 of the Radiation Protection Regulation.
1.3
Disappearance of radioactive substance criterion S 1.3.1XX_ENCODE_CASE_One dissemination of radioactive substances from the facility by means of transfer to an area
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outside surveillance areas on the premises, provided that the activity that has been taken there is 100 times the values set out in Appendix 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 grounds, provided that the activity which has been carried out there is one hundred 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 exceeds.
criterion E 1.3.1XX_ENCODE_CASE_One dissemination of radioactive substances from the device by means of ablation into a region
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outside of surveillance areas on the premises, if the activity that has been taken there is ten times the values set out in Appendix 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 grounds, provided that the activity which has been displaced 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.
2.
technique and operation
2.1
malfunction, damage, or Failures in safety-related systems or setup criteria E 2.1.1Functional disturbance, damage or failure of a safety-related important system or an important safety-related facility, so that the system can be used for further processing of the system. Storage in accordance with § 6 of the Atomic Energy Act, an additional measure not previously defined in the approved instructions (safety specifications, operating and testing regulations) is taken. criterion N 2.1.1Functional disorder, Damage or failure of a safety-related important system or an important safety device. Not to be reported are malfunctions, damages or outages
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in other safety-critical systems that are in less than 24 hours or within the be fixed in the approved operating rules, provided that the function of the system is maintained,
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the other safety-related systems for which approved replacement measures are permitted for a limited period of time, provided that the incident is not to be reported according to criterion N 2.1.2,
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reduced dimensions of individual components of the building fire protection as well as the failure of individual components of the decentralized fire-fighting and fire fighting systems. Fire alarm equipment.
criterion N 2.1.2outage, damage or finding with reference to a systematic error in an important safety-related system or an important safety-related device. criterion N 2.1.3
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triggering a pressure switch of the seal systems of the transport or storage containers.
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triggering a pressure switch that is not due to leakages of the lid gaskets, unless the lack of the pressure switch can be found within the approved Fixed repair time fixed
2.2
Lots of loads; handling events or transport criterion E 2.2.1
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Crash of a container loaded with nuclear fuel or solidified cleavage product solutions
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The crash of a heavy load on a container loaded with nuclear fuel or solidified fission product solutions.
criterion N 2.2.1
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Safety-related event during transport or handling of a transport or Storage container.
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Security-critical event during transport or handling of a load.
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Security-critical damage to a hoist or a transport or handling device.
2.3
Other event criteria N 2.3.1Safety-related deviation from a regulatory value of the technology or the operating system. criterion N 2.3.2Security engineering significant damage to a load-bearing structure of a building s.criterion N 2.3.3Event, which requires a significant change in the safety specifications.
3.
external and internal events
3.1
effects of external criterion S 3.1.1XX_ENCODE_CASE_One earthquakes, 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 in which this is to be provided. 3.1.1XX_ENCODE_CASE_One earthquake, plane crash, explosion pressure wave or other external action, provided that the storage in accordance with § 6 of the Atomic Energy Act is continued only with an additional measure not previously set out in the operating rules
3.2
Internal event criterion S 3.2.1Setup internal fire, internal explosion, severe chemical reaction, flooding, or other Effect from the inside so that a condition of the device has occurred which has a beneficial effect on the population or the environment or in which this is to be provided. criterion E 3.2.1interior 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 can only be continued with an additional measure not previously set out in the operating rules. 3.2.1Set-up internal fire, internal explosion, severe chemical reaction, flooding or other action from inside in a room or area of the facility in which radioactive substances with an activity above the values of 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 in connection with the change and Maintenance work, for which preventive fire protection measures have been taken and whose application was effective in fire-fighting.