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

Read the untranslated law here: http://www.gesetze-im-internet.de/atsmv/BJNR017660992.html

Regulation about the nuclear security officer and the reporting of accidents and other events (Atomrechtliche security officers and reporting regulation - AtSMV) AtSMV Ausfertigung date: 14.10.1992 full quotation: "Atomrechtliche security officers and reporting regulation of 14 October 1992 (BGBl. I S. 1766), most recently by article 1 of the Decree of 8 June 2010 (BGBl. I p. 755) has been changed" stand: last amended by art. 1 V v. 8.6.2010 I 755 details on the stand number you see in the menu see remarks footnote (+++ text detection from) : 1.7.1993 +++) input formula on the basis of § 12 para 1 sentence 1 No. 1, 7 and 13 and of § 54 para 1 sentence 1 and paragraph 2 sentence 1 of the Atomic Energy Act, as amended by the notice of 15 July 1985 (BGBl. I p. 1565), article 54, paragraph 1, sentence 1 changed by article 2 of the Act of 9 October 1989 (Federal Law Gazette I p. 1830) , the Federal Government enacted: the first section scope article 1 scope of application (1) this Regulation applies to facilities according to § 7 paragraph 1 of the Atomic Energy Act.
(2) according to § 6 of the Atomic Energy Act and for decommissioning facilities according to § 7 paragraph 3 of the Atomic Energy Act articles 6 to 8 shall apply for storage, this Regulation shall not apply article 9, paragraph 2 and article 12 (3): 1. for installations for the fission of nuclear fuel, its maximum rated output does not exceed 50 kilowatt of thermal continuous output, and 2 for storage according to § 6 of the Atomic Energy Act and decommissioning facilities according to § 7 paragraph 3 of the Atomic Energy Act , if a) of nuclear fuel was removed from the facility for the storage or installation in decommissioning and b) the remaining activity inventory open radioactive substances does not exceed the 107fache and wrapped radioactive material not exceeding 1010fache of allowances is table 1 column 2 of the Radiation Protection Ordinance according to annex III.
Second section of nuclear safety officer section 2 has order of nuclear security officers (1) the holder of a permit to operate of a system in accordance with article 7, paragraph 1, of the nuclear energy Act (operator) for the duration of the operation of the system up to the issuing of a permit to the decommissioning of the plant according to § 7 paragraph 3 of the Atomic Energy Act to order a nuclear security officers (Security Officer) and his representative in writing. Are multiple installations on the same site operated by the operator, a common security officer can be ordered. The supervisory authority may exempt the operator from the obligation to appoint a security officer, so far because of the amount or nature of nuclear fuels or an order is not required because certain measures of protection or safety equipment.
(2) the operator shall without delay the appointment of security officers with indication of the internal position, to show any change in this position as well as the withdrawal in writing the supervisory authority. A copy of the display is the safety officer and the operational or personnel Council handed over.
(3) to the security officer, only one person may be ordered against the no evidence of facts, from which arise concerns about their reliability, and which possesses the expertise required for the performance of their duties. When the order is proof of expertise. Facts are known of the supervisory authority from those results, that the security officers possesses not to carry out the tasks required expertise or reliability, it may require that the operator appointed an other security officer.
(4) are on the applicable representative according to: 1 paragraph 1 sentences 2 and 3, 2. paragraphs 2 and 3, and 3. sections 3 to 5 and article 10.

§ 3 obligations of the operator (1) the operator has the security officer in the fulfilment of its tasks to support and it in particular insofar as this is necessary for the performance of his duties, to provide technical and support staff.
(2) the operator must ensure that the safety officer receives the information necessary to carry out its tasks and administrative acts and other measures relating to its duties or powers, be given him notice.

§ 4 duties of safety officers (1) the safety officer has within the operational organisation of the plant without prejudice to the responsibility of the operator 1 for the evaluation of a site) reportable events (§ 6), b) other errors at your home resort, c) to ensure information on notifiable events in other systems in terms of their importance for the own facility and to participate in the implementation of these tasks , 2. in establishing itself from this resulting corrective and improvement measures to participate, 3. the operator insights on safety defects, as well as proposals to remedy the defects or to increase the security forthwith, to join 4. when planning for changes in the system or its operation, to check 5. the message of reportable events in accordance with the § 10, 6 on the exchange of experience with the security officers of other systems of safety-significant operating experience to participate.
(2) the safety officer has to cooperate in carrying out his duties with the operational or personnel Council and specialists for occupational safety, as well as under other provisions of ordered management officer in the system and to inform them of important matters of nuclear safety. He has on his request in matters of nuclear safety to advise the operating or staff Council.

Position of safety officer (1) the safety officer not disabled must § 5 in carrying out its tasks and are not disadvantaged because of his activities.
(1a) the operator has internal organisational measures to ensure that the safety officer performs no functions with direct responsibility for production.
(2) the operator has internal organisational measures to ensure that the security officer immediately can recite his proposals and concerns of the Executive Board, if he could not be agreed with the Director of the plant and he believes a decision of the Executive Board because of the special importance of the thing necessary. Can safety representative on a measure proposed by him to the nuclear security with senior management does not agree, this has communicated the safety officer in writing rejecting the proposal and justified. She shall send the operational or personnel Council and the supervisory authority a copy.
(3) the position of the safety officer and its tasks in accordance with article 4 are set in detail in the manual.
Third section reporting of accidents, incidents and other events § 6 notification (1) the holder of a licence pursuant to article 6 or article 7, paragraph 1 or paragraph 3 sentence 1 of the Atomic Energy Act (notifiable) has to report accidents, incidents or occurrences meaningful nuclear security (notifiable events) of the supervisory authority.
(2) subject are events that meet the requirements in appendices 1 to 5 listed criteria.
(2a) Annex 4 applies to plants in decommissioning from the time for which the supervisory authority at the request of the operator has determined by administrative act, that the application criteria referred to in the introduction to annex 4 are met.
(3) the disclosure has notified to the occurrence of a reportable event of also the authority responsible for public safety and order, as well as the authorities responsible for civil protection, as far as this is necessary for the protection of the population against life and health hazards.
(4) (dropped out) § 7 content of the written notification (1) which is notifiable in the notification to the supervision authority according to § 8 para 1 sentence 1 No. 1 to 4 by means of official notification form the reportable event, its causes and effects, the Elimination of the effects, as well as measures to prevent repetition to describe that in terms of nuclear safety is adequately assessed can be. The supervisory authority has announced an official registration form.
(2) in the written notification through telecommunications moderate transmission pursuant to § 8 para 1 of notifiable do the information required for the registration form No. 1 and 2, as far as information can be provided without delay and data are known.

§ 7a electronic communications (1) the transmission of electronic documents is only admissible if the supervisory authority the notifying parties announced that it opened an access for this.
(2) the bodies involved have the respective State of the art measures to ensure data protection and data security to meet. In the case of the use of accessible networks are to apply encryption methods that correspond to the current state of technology.

§ 8 notification procedure are (1) notifiable events to report 1 category S: immediately after knowledge verbally and in writing by telecommunications moderate transmission; at the latest on the fifth business day after knowing complement and, if necessary, adjustment of message using the login form;
2. category E: no later than 24 hours after knowledge verbally and in writing by telecommunications moderate transmission; at the latest on the fifth business day after knowing complement and, if necessary, adjustment of message using the login form;
3.
Category N: not later than on the fifth working day after knowledge using the login form;
4. category V: no later than on the tenth working day after knowledge using the registration form.
The supervisory authority may make further orders about the message.
(2) within the time limit for the written message using form cannot all information required be made, is to mark the message as preliminary. Once the missing data are known, to submit a completed and marked as final message is the supervisory authority. The final message is no later than two years after the preliminary message to present, unless the authority has because of missing agreed to a later template data.
(3) the classification in which in paragraph 1 sentence 1 above categories and its association with the criteria listed in the annexes 1 to 5 is to make on the basis of the facts known for reporting the message. The registration period begins once reporting knowledge of the facts, which objectively justify the reporting obligation.
(4) a reportable event meets several of the in appendices 1 to 5 criteria listed under different numbers, are all fulfilled criteria to specify; in the cases of paragraph 2 in the final written notification at the latest.
(5) the notification criteria to be associated with multiple categories referred to in paragraph 1 sentence 1, form and time limit the message depend on the category with the shortest deadline.
(6) a reportable event also includes: 1 all events that are caused by the first event (subsequent events), and 2. any similar failures, damage, malfunction or findings to similar facilities, systems or equipment, the investigations to this event is detected.
(7) turns out having knowledge of all relevant facts, that a reported event was not reportable, the disclosure shall in writing this to the supervisory authority, stating the this relevant facts.

§ 9 additional obligations of the notifying parties (1) showing notifiable of supervisors monthly the number of reportable events occurred since the submission of the previous advertisement on.
(2) the disclosure has reportable events for their admission, defective parts are caused by or occur in the course of which damage to safety-important system components to take measures to secure evidence which allow a subsequent clarification and verification of the exact causes and consequences of the reportable event. Are especially suited to the securing of evidence: a) retention defective components in an unchanged form, b) production of photographs, c) creating a detailed damage documentation.

§ 10 to inspection by the safety representative who has security officer the correctness and completeness of the message a reportable event, note the results of the audits on the registration form and to provide with his signature. The same applies to the display according to § 9 para of 1 fourth section fine regulations section 11 offences any person in the sense of § 46 para 1 No. 4 of the nuclear energy Act who intentionally or negligently 1 is, contrary to article 6, paragraph 1 or paragraph 3 respectively in connection with article 7, paragraph 1, sentence 1 or § 8 paragraph 1 sentence 1, also in conjunction with article 1(2) or section 8 paragraph 6 , or contrary to section 8, paragraph 2, sentence 2 or sentence 3 not, incorrectly, incompletely or not in time is a message, not, not properly, not fully or not timely filed a charges or not, incorrectly, incompletely or not timely submit a message, 1a.
(lapsed)
2. contrary to article 9, paragraph 1 a display not, not properly or not timely reimbursed or 3. contrary to section 10 does not or not correctly noted the outcome of the examination.
In the scope of application of this regulation, fifth section final provisions article 12 relationship with other provisions of § 51 sentence 2 of the Radiation Protection Ordinance does not apply.

§ 13 (dropped out) closing formula, in the Federal Council has agreed to.

Annex 1 criteria for notifiable events in facilities according to § 7 of the nuclear energy Act for the fission of nuclear fuel for the commercial generation of electricity (site: BGBl. I 2010, 757-762) table of contents introduction 1 Radiology and radiation protection 1.1 radioactive waste 1.2 release radioactive substances 1.3 contamination 1.4 spread radioactive materials 2. plant engineering and operation 2.1 malfunctions, damages or failures in the security system or the other safety-critical systems or system components 2.2 damage or leaks in pipes or containers 2.3 criticality errors 2.4 crash by Loads; Events during handling, storage or transport 2.5 occurrences 3. influences of external and internal events 3.1 effects of events before you begin taking registration criteria for notifiable events in plants for the fission of nuclear fuel for the commercial generation of electricity, as far as examples from the field of plant engineering supplied by outside 3.2 attachment internal, reference to nuclear facilities with light water reactors. For other reactor types are the criteria to be applied mutatis mutandis.
1. Radiology and radiation protection reference to the values of annex III is made when the following criteria table 1 column 4 of the Radiation Protection Ordinance, is to use an average area of 300 square centimetres.
1.1 disposal of radioactive waste criterion S 1.1.1 exceeds disposal of radioactive waste with air or water, where the activity derived from 24 hours - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance leads or - activity charges laid down by the competent authority, the calendar year maximum.
Criterion E 1.1.1 disposal of radioactive waste with air or water, with the derived activity greater than laid down by the competent authority, maximum activity taxes.
1.2 release of radioactive substances to get criterion S 1.2.1 release of radioactive substances into the environment, where is that 24 hours leads released activity - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance or - is more than 10 percent of activity charges laid down by the competent authority for derivatives, the calendar year maximum.
To get criterion E 1.2.1 release of radioactive substances into the environment, where is that the released activity - leads to body doses, be more than 10 per cent of the limits according to article 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or more than 10 percent activity charges laid down by the competent authority for derivatives, the calendar year maximum.
Criterion N 1.2.1 release of radioactive substances into the environment that does not fall under the criteria of S 1.2.1 or E 1.2.1.
Criterion S 1.2.2 release of radioactive substances within the plant, so that outside of the area designated as a control panel, the dose rate exceeds the value of 3 milliSievert per hour.
Criterion E 1.2.2 release of radioactive substances within the plant, so that - within an area designated as a control panel, as far as this is not marked as block area, the dose rate exceeds the value of 3 milliSievert per hour for more than 24 hours or - to set up a new control area is required.
1.3 contamination criterion E 1.3.1 contamination within the monitoring range, the one hundred times of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than ten times of the values according to annex III.
Criterion N 1.3.1 contamination within the control area, may be in an area that is not contaminated during normal operation, a thousand-fold of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than one hundred times of the values according to annex III.
1.4 spread radioactive material criterion S 1.4.1 proliferation of radioactive materials from the plant through abduction in an area - outside of supervised areas at the premises, provided there was deported activity one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite , if activity there deported one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and ten times of the values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
Criterion E 1.4.1 proliferation of radioactive substances from the plant through abduction in an area - outside of supervised areas at the premises, unless there deported ten times of the values activity according to Appendix III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or
offsite, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and the simple of values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
2. equipment and operation 2.1 malfunctions, damages or failures in the security system or the other safety-critical systems or system components criterion S 2.1.1 malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that the interpretation to the incident control required number of security institutions is no longer available. When this is the case, is laid down in the approved regulations.
Criterion E 2.1.1 - malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that only the required interpretation in accordance with to the mastery of the incident number of security institutions available stands. When this is the case, is laid down in the approved regulations.
-Complete failure of a safety function which is intended exclusively for the control of emergency cases.
Criterion N 2.1.1 - malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that is at least a safety part device unavailable.
-Malfunction, damage or failure in one other important safety system or plant part with the result that the system or a redundant not available is.
-Loss of a safety part device, which is intended exclusively for the control of emergency cases.
Not to report malfunctions, damages or failures are: - individual cards or transmitter in the reactor protection system or control equipment that perform similar functions, unless the failure is even notifying, resolves within 8 hours and is not according to criterion N 2.1.2 to log - in the other safety-critical systems that are fixed, in less than 24 hours, or failures of these systems approved alternative measures are foreseen for the , provided that the particular event is not to be reported according to criterion N 2.1.2.
Criterion N 2.1.2 damage, failure, or findings with reference to a systematic error - security system or to an other safety-important system or part - to a component, a component or a module in an operating system, if the component, the component or Assembly used under similar conditions and of comparable quality in the security system or other safety-important system.
Criterion N 2.1.3 loss of or damage to an institution of technical or constructional fire protection.
Not to report failures are by or minor damage to individual components of plant technical or constructional fire protection that the fire protection capabilities has not unacceptably reduced.
Criterion S 2.1.4 dysfunction of a security, relief - or relief valve of the pressure run ends enclosure: - not the planned opening, if no automatic shut-off of the blow-off circuit (except boiling water reactors (SWR)), not closing after speaking, if no automatic shut-off of the blow-off circuit (except SWR), - do not open of a safety valve in the requirement case.
Criterion E 2.1.4 a security, relief - or relief valve malfunction:-not proposed opening a security, relief - or relief valve of the pressure run ends enclosure, if the incident is not reported to criterion S 2.1.4, not close of security, relief - or relief valve of the pressure run ends enclosure, if the incident is not reported to criterion S 2.1.4, - Nichtöffnen of a relief - or relief valve of the pressure run ends enclosure in the requirement case , - Do not open a live steam safety valve in the requirement case (other than SWR), - not closing a live steam safety valve, if no automatic shut-off, - do not open an other safety valve in the requirement case, a device of the security system or any other safety important system or part.
Not according to criterion E 2.1.4 to report the malfunction referred to in criterion N 2.1.4.
Criterion N 2.1.4 dysfunction of a security, relief - or relief valve:-not proposed opening a security and relief valve (with SWR), if only one valve is affected and this, before automatic reactor protection actions are triggered, automatically closes or is brought to close-not closing a security and relief valve (with SWR), if only one valve remains open and this, before automatic reactor protection actions are triggered, automatically closes or is brought to close , - not-seen opening a Pressurizer off bubble valve (for pressurized water reactors (PWR)), if this, before the valve blow off closes or before repossessions – or escape alarm for the containment vessel is raised independently or brought to the closing, - not closing a live steam safety valve, where an automatic shut-off of the blow-off pipe, - not planned to open or not close of a safety valve to another facility of the security system or other safety-important system or part of the installation.
Criterion E 2.1.5 instructions important exceeded of a design value in reactor core, Druckführender enclosure, inclusion of security or safety-important parts of the steam and feedwater system.
Criterion N 2.1.6 instructions significant deviation from the specified state in the security system (including associated auxiliary and ancillary systems) or other safety-important system or part of the installation.
Variations in several redundant security institutions, which at the same time mean a failure of these security institutions according to the specifications, are also to sign S 2.1.1 criteria or criterion E 2.1.1.
2.2 damage or leaks in pipes or tanks criterion S 2.2.1 leak, which will trigger a protective action.
Not to be reported: - the staying open from safety and relief valves (at SWR), false suggestions of protection actions, - leaks cold system, which quickly eliminated can (for example incorrect opening a faucet with the following closing of this or a redundant fixture).
Criterion E 2.2.1 rupture or tear with leak, requiring a shutdown of the plant for safety reasons, on one of the following systems: - reactor cooling circuit or the immediately subsequent systems-including the areas that reactor coolant pressure are, - steam system up to the turbine and Umleitschnellschlussventilen as well as at all against this pressure Chamber not lockable pipe sections, - on the feed water system, as well as at all against this pressure Chamber not lockable pipe sections.
Criterion N 2.2.1 damage, in particular crack, deformation or below the nominal wall thickness of one - setting up the security system or an other activity leading system, - whichever of the steam or feedwater system by including the external shut-off valve, - whichever of the steam or feedwater system outside the external shut-off valve, if the damage indicates a lack of interpretation or an unconsolidated burden.
Not to be reported:-single seal or flange leakage outside the ends of the pressure run enclosure, - drip leaks at seals and flanges inside the pressure run ends enclosure, - plug book leakage in the context of the interpretation of book plug suction within the print run ends enclosure, - leakage on measurement, drainage or ventilation pipes in the turbine area.
Criterion 2.2.2 E steam generator heating pipe leakage, requiring a shutdown of the plant.
Criterion E 2.2.3 - failure of a pressure vessel, fitting - or pump casing, - disassemble a flywheel, - break a pipe if this can lead to a functional impairment of a safety-important system or component.
To get damage criterion N 2.2.3 at a pressure tank, is that a failure of the container due to this damage directly or in a chain of to increase subsequent events leads to harm a technically important system or part installation or throws a fault.
2.3 criticality errors criterion S 2.3.1 criticality without sufficient shut-off reserve of the instant shut-off System.
Criterion E 2.3.1 - undue Reaktivitätstransiente or invalid Entborierung in pressurized water reactors.
2.4 crash loads; Events during handling, storage or transport criterion S 2.4.1 crash a load in the spent fuel storage pool or the reactor room with the result - a loss of low criticality or - not lockable larger leakage (more than 0.3 litres per second).
Criterion E 2.4.1 crash - a Brennelements in the spent fuel storage pool, the transport or storage containers or the reactor room.
other load in the spent fuel storage pool or the reactor room resulting in a larger (more than 0.3 litres per second) lockable or low (0.3 litres per second or less) not lockable leakage, - a heavy burden in a room where there is a safety-critical system or part of the installation.
Criterion N 2.4.1 - instructions important event in the transport, handling or storage of fuel or other radioactive substances within the facility or the site of the installation.
-Safety-significant event during the transport or handling a load.
-Safety-significant damage on a hoist, or a transport or handling equipment.
2.5 other events criterion E 2.5.1 event with an automatic response to a safety valve of the pressure run ends enclosure.
Criterion N 2.5.1 damage to reactor pressure vessel internals, reactor core or steam generator installations.
Report individual fuel damage are not, unless they go beyond does not have cracks or slight deformations and provide no indication of systematic weaknesses.
Criterion N 2.5.2 a loose part or a foreign body - in the print run enclosure or - in containers of other safety features, if can be an important safety function impermissibly impaired or caused a fuel rod damage of larger-scale.
Criterion N 2.5.3 damage from a water or condensation shock or systematic damage to suspensions, supports or damping equipment on a safety-important pipeline or component.
Criterion N 2.5.4 damage to reactor coolant pumps, which require a shutdown of the plant.
Criterion N 2.5.5 failure by - more than one main feed water or main condensate pump or - 50% of the main cooling water pumps and more.
Criterion N 2.5.6 joint failures of the master and of the reserve power supply, failure of a strand of captive supply.
Criterion N 2.5.7 request or false suggestion of a safeguard of part of the reactor protection system.
Not to be reported: - quick cut-offs in the start-up phase at low reactor power (at up to 5 percent), - operational made or proposed firings.
Criterion N 2.5.8 instructions significant damage on a load-bearing structure of a building.
Criterion N 2.5.9 event that requires a significant change of the security specifications.
3. the effects of external and internal events 3.1 effects of external criterion S 3.1.1 damage from earthquakes, plane crash or explosion pressure wave a building where there is a safety-critical system or part of the installation, - safety-important system or plant part with the result that a safety device is requested.
Criterion E 3.1.1 external impact, which requires the switching off or shutting down the plant for safety reasons.
To get 3.2 attachment internal events criterion S 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other exposure to indoor to an extent, which is that the necessary interpretation to the incident control number of security institutions is no longer available.
Criterion E 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other exposure to indoor to an extent, where to get, that is only the required interpretation in accordance with to the mastery of the incident number of security institutions available.
Criterion N 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other action from the inside, in a room or facility area, in which radioactive material with an activity beyond the table are 1 column 2 of the Radiation Protection Ordinance according to annex III or an important safety device is located.
Report limited ones in connection with modification or maintenance work, for the preventive fire protection measures have been taken and their application was effective when fire-fighting are not fixed.

Appendix 2 reporting criteria for notifiable events in facilities according to § 7 of the nuclear energy Act of nuclear fuel supply and disposal (site: BGBl. I 2010, 763-766) table of contents 1 Radiology and radiation protection 1.1 radioactive waste 1.2 release radioactive substances 1.3 contamination 1.4 spread radioactive substances 2. systems engineering and operation 2.1 malfunctions, damages or failures in safety-critical systems or system components 2.2 damage or leaks in pipes or containers of safety-critical systems 3. influences of external and internal events 3.1 effects of outside 3.2 attachment internal 1 Radiology and radiation events reference on the values of annex III is made when the following criteria table 1 column 4 of the Radiation Protection Ordinance, is to apply an average area of 300 square centimetres.
1.1 disposal of radioactive waste criterion S 1.1.1 exceeds disposal of radioactive waste with air or water, where the activity derived from 24 hours - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance leads or - activity charges laid down by the competent authority, the calendar year maximum.
Criterion E 1.1.1 disposal of radioactive waste with air or water, with the derived activity greater than laid down by the competent authority, maximum activity taxes.
1.2 release of radioactive substances to get criterion S 1.2.1 release of radioactive substances into the environment, where is that 24 hours leads released activity - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance or - is more than 10 percent of activity charges laid down by the competent authority for derivatives, the calendar year maximum.
To get criterion E 1.2.1 release of radioactive substances into the environment, where is that the released activity - leads to body doses, be more than 10 per cent of the limits according to article 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or more than 10 percent activity charges laid down by the competent authority for derivatives, the calendar year maximum.
Criterion N 1.2.1 release of radioactive substances into the environment that does not fall under the criteria of S 1.2.1 or E 1.2.1.
Criterion S 1.2.2 release of radioactive substances within the plant, so that outside of the area designated as a control panel, the dose rate exceeds the value of 3 milliSievert per hour.
Criterion E 1.2.2 release of radioactive substances within the plant, so that - within an area designated as a control panel, as far as this is not marked as block area, the dose rate exceeds the value of 3 milliSievert per hour for more than 24 hours or - to set up a new control area is required.
1.3 contamination criterion E 1.3.1 contamination within the monitoring range, the one hundred times of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than ten times of the values according to annex III.
Criterion N 1.3.1 contamination within the control area, may be in an area that is not contaminated during normal operation, a thousand-fold of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than one hundred times of the values according to annex III.
1.4 spread radioactive material criterion S 1.4.1 proliferation of radioactive materials from the plant through abduction in an area - outside of supervised areas at the premises, provided there was deported activity one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite , if activity there deported one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and ten times of the values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
Criterion E 1.4.1 proliferation of radioactive substances from the plant through abduction in an area - outside of supervised areas at the premises, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and the simple the Values table 1 column 2 exceeding the Radiation Protection Ordinance according to annex III.
2. equipment and operation 2.1 malfunctions, damages or failures in safety-critical systems or system components criterion S 2.1.1
Malfunction, damage or failure at a technically important institution, so that the State of a system which gefahrbringend affects the population or the environment has occurred, or if it is to get.
Criterion E 2.1.1 malfunction, damage or failure at a technically important facility, if the facility for this purpose is and whose occurrence of operating the facility or the line for safety reasons not can be continued.
Criterion N 2.1.1 malfunction, damage or failure - an important safety device or - a component or a component in another facility of the plant or the line, unless a corresponding component or a corresponding construction element in a technically important facility is used.
Not to report malfunctions, damages or failures are: - is to sign individual guidance technical components necessary to cope with incidents guidance technical facilities of the technically important institutions, unless the failure is even notifying, resolves within 24 hours of and not according to criterion N 2.1.2 - are in the other safety-critical systems that fixed in less than 24 hours or within the permitted repair times set out in the approved operating rules , if the function of the system is maintained, - any other safety-important system, alternative measures for a limited period are provided for in the approved operating rules unless the event not according to criterion N 2.1.2 to sign, - were on individual components of technical or constructional fire protection by the fire protection functions not impermissibly affected unless the event not according to criterion N 2.1.2 to report.
The competent authority may define more system-specific details for the criterion N 2.1.1.
Criterion N 2.1.2 failure, damage or findings with reference to a systematic error at a technically important institution.
Criterion N 2.1.3 instructions relevant deviation from an officially set value of equipment or operation.
Criteria E 2.1.4/N 2.1.4 request an active Sicherheitseinrichtung1).
Criterion N 2.1.5 is transfer of radioactive waste in a system, a component or a component, when exerted on the system, the component or the component during normal operation with radioactive substances.
Criterion S 2.1.6 criticality event.
Criterion E 2.1.6 event that has violated the security principles of criticality safety.
Criterion N 2.1.6 event that affected the criticality safety, but not the security principles of criticality safety has violated.
Criterion N 2.1.7 instructions-related event in the transport, handling or storing radioactive waste on the premises.
Criterion N 2.1.8 event that requires a significant change of the security specifications.
Criterion N 2.1.9 event when the extension or modification of the system or the system of part of, the impact on the functioning of a safety-important system or part installation existing operating can have.
Criterion V 2.1.10 findings at a technically important institution prior to operation of the system or the part plant, of a design fault or weakness of the quality assurance system points out.
Criterion can V 2.1.11 event during the erection of the plant or the line that have an impact on the functioning of a safety-important system or plant part in future operation (for example, fire, explosion, flood, crash of a heavy load).
2.2 damage or leaks in pipes or tanks, safety-critical systems criterion S 2.2.1 leak in a leading activity system, which has a gefahrbringend effect on the population or the environment or if it is to get.
Criterion E 2.2.1 rupture or tear with leakage in a system activity leading or in a pipe with security coverage (for example, autoclave), from safety reasons requires the setting of the plant operation.
Criterion N 2.2.1 leak or damage, in particular crack, deformation or below the nominal wall thickness of a pipe or a container of a safety-important an activity leading system or component.
Not to sign individual drip leaks are - seals, flanges, pipes or containers of non-activity-lead systems and activity leading parts, gaskets and flanges systems and system components.
3. the effects of external and internal events 3.1 effects of external criterion S 3.1.1 to get this earthquake, plane crash, explosion pressure wave or other effects from outside, so that the State of a system which gefahrbringend affects the population or the environment has occurred, or in which is.
Criterion E 3.1.1 earthquakes, plane crash, explosion pressure wave or other effects from outside, provided that the operation of the plant or the line for safety reasons can not be continued.
Criterion N 3.1.1 earthquakes, plane crash, explosion pressure wave or other outside exposure, unless the investment thereof affected and this not covered by the criteria of S 3.1.1 or E 3.1.1 is.
3.2 attachment internal criterion S 3.2.1 of attachment internal fire, plant-internal explosion, violent chemical reaction to obtain this flooding, the crash of a heavy burden or an other action from the inside, so that the State of a system which gefahrbringend affects the population or the environment has occurred or where is events.
Criterion E 3.2.1 of attachment internal fire, plant-internal explosion, violent chemical reaction, flooding, the crash of a heavy burden or an other action from the inside, provided that the operation of the plant or the line for safety reasons can not be continued.
Criterion N 3.2.1 of attachment internal fire, plant-internal explosion, violent chemical reaction, flooding, crash of a heavy burden or an other action from the inside, if the investment thereof affected and this not covered by the criteria of S 3.2.1 or E 3.2.1 is.
(1) the relevant safety equipment and the associated alarm category be set by the competent authority.

Appendix 3 reporting criteria for notifiable events in facilities according to § 7 of the nuclear energy Act for the fission of nuclear fuel, which predominantly serve research purposes (site: BGBl. I 2010, 767-772) table of contents introduction 1 Radiology and radiation protection 1.1 radioactive waste 1.2 release radioactive substances 1.3 contamination 1.4 spread radioactive substances 2. equipment and operation 2.1 malfunctions, damages or failures in the security system or the other safety-critical systems or system components 2.2 damage or leaks on pipelines or containers 2.3 criticality errors 2.4 crash loads; Events during handling, storage or transport 2.5 occurrences 3. influences of external and internal events 3.1 the effects of outside 3.2 attachment internal 4. events prior to issuance of the permit for the reactor loading preliminary note the plants in the Federal Republic of Germany for the fission of nuclear fuel, which primarily serve research purposes, differ in their risk potential, related devices to its security system and the number of redundancies of safety-critical systems or system components part clearly. A plant-specific concretisation is required for uniform application of the individual criteria in these plants.
1. Radiology and radiation protection reference to the values of annex III is made when the following criteria table 1 column 4 of the Radiation Protection Ordinance, is to use an average area of 300 square centimetres.
1.1 disposal of radioactive waste criterion S 1.1.1 exceeds disposal of radioactive waste with air or water, where the activity derived from 24 hours - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance leads or - activity charges laid down by the competent authority, the calendar year maximum.
Criterion E 1.1.1 disposal of radioactive waste with air or water, with the derived activity greater than laid down by the competent authority, maximum activity taxes.
1.2 release of radioactive substances to get criterion S 1.2.1 release of radioactive substances into the environment, where is that 24 hours leads released activity - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance or - is more than 10 percent of activity charges laid down by the competent authority for derivatives, the calendar year maximum.
To get criterion E 1.2.1 release of radioactive substances into the environment, where is that the released activity - leads to body doses, be more than 10 per cent of the limits according to article 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or more than 10 percent activity charges laid down by the competent authority for derivatives, the calendar year maximum.
Criterion N 1.2.1
Release of radioactive substances into the environment that does not fall under the criteria of S 1.2.1 or E 1.2.1.
Criterion S 1.2.2 release of radioactive substances within the plant, so that outside of the area designated as a control panel, the dose rate exceeds the value of 3 milliSievert per hour.
Criterion E 1.2.2 release of radioactive substances within the plant, so that - within an area designated as a control panel, as far as this is not marked as block area, the dose rate exceeds the value of 3 milliSievert per hour for more than 24 hours, or - the establishment of a new control area is required.
1.3 contamination criterion E 1.3.1 contamination within the monitoring range, the one hundred times of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than ten times of the values according to annex III.
Criterion N 1.3.1 contamination within the control area, may be in an area that is not contaminated during normal operation, a thousand-fold of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than one hundred times of the values according to annex III.
1.4 spread radioactive material criterion S 1.4.1 proliferation of radioactive materials from the plant through abduction in an area - outside of supervised areas at the premises, provided there was deported activity one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite , if activity there deported one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and ten times of the values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
Criterion E 1.4.1 proliferation of radioactive substances from the plant through abduction in an area - outside of supervised areas at the premises, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and the simple the Values table 1 column 2 exceeding the Radiation Protection Ordinance according to annex III.
2. equipment and operation 2.1 malfunctions, damages or failures in the security system or the other safety-critical systems or system components criterion S 2.1.1 malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that the interpretation to the incident control required number of security institutions is no longer available. When this is the case, is laid down in the approved regulations.
Criterion E 2.1.1 - malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that only the required interpretation in accordance with to the mastery of the incident number of security institutions available stands. When this is the case, is laid down in the approved regulations.
-Complete failure of a safety device that is required for the tightness of the building, which encloses the reactor.
Criterion N 2.1.1 - malfunction, damage or failure in the security system (including associated auxiliary and ancillary systems) with the result that is at least a safety part device unavailable.
-Malfunction, damage or failure in one other important safety system or plant part with the result that the system or a redundant not available is.
-Loss of a safety part device, which is intended exclusively for the control of events with very low probability of occurrence (influences from outside or from inside).
Not to report malfunctions, damages or failures are: - is to report individual cards or transmitter in the reactor protection system and guidance equipment that perform similar functions, unless the failure is even notifying, resolves within 8 hours and not according to criterion N 2.1.2 - are on the other safety-critical systems that fixed in less than 24 hours, or their failures, for the approved alternative measures are intended , if the event is not to be reported according to criterion N 2.1.2.
Criterion N 2.1.2 failure, damage or findings with reference to a systematic error - security system or to an other safety-important system or part - to a component, a component or a module in an operating system, if the component, the component or Assembly used under similar conditions and of comparable quality in the security system or other safety-important system.
Criterion N 2.1.3 loss of or damage to an institution of technical or constructional fire protection.
Not to report failures are by or minor damage to individual components of plant technical or constructional fire protection that the fire protection capabilities has not unacceptably reduced.
Criterion N 2.1.4 not opening or not closing a safety valve on an other safety-important system or part of the installation.
Criterion E 2.1.5 instructions, are significant exceeding design values - in the reactor core, - in the primary cooling system and reactor pool, - at the building, which encloses the primary cooling system, - at an experimental institution whose failure affect the reactor and its safety devices as well as other important safety systems or equipment cannot be ruled out, and, if the secondary circuit, unless this carries out safety-related tasks.
Criterion N 2.1.6 instructions significant deviation from the specified state in the security system (including associated auxiliary and ancillary systems) or other safety-important system or part of the installation.
Variations in several redundant security institutions, which at the same time mean a failure of these security institutions according to the specifications, are also to sign S 2.1.1 criteria or criterion E 2.1.1.
2.2 damage or leaks in pipes or tanks criterion S 2.2.1 leakage to the primary cooling system, which leads to trigger a protective action. False suggestions of protection actions or leaks in swimming pool reactors are not to report.
Criterion E 2.2.1 - break or crack with leakage in the primary cooling system, including the primary heat exchanger, or to the reactor tank or reactor vessel, requiring a shutdown of the plant for safety reasons.
-Leakage lines where due to their involvement the primary coolant loss with or without make-up is always limited that sufficient cooling ability of the reactor remains assured. Not to report leakage during training, research, are isotopes, General Atomic (TRIGA reactors).
-Leakage in the secondary circuit, if this carries out safety-related tasks, and where a shutdown of the plant for safety reasons is required.
Criterion N 2.2.1 - leakage or damage of a security system or an other activity leading system, leakage or damage to an enclosure of the secondary cycle, if this carries out safety-related tasks, - leakage in the secondary circuit, the technical safety reasons a shutdown of the system is required.
Not to sign individual seal or flange leakages, as well as drip leaks are outside the security system.
Criterion E 2.2.3 - failure of a pressure vessel, fitting - or pump housing, - decompose a flywheel, - break a pipe if this can lead to a malfunction of a safety-important system or plant part.
To get damage criterion N 2.2.3 at a pressure tank, is that a failure of the container due to this damage directly or in a chain of to increase subsequent events leads to harm a technically important system or part installation or throws a fault.
2.3 criticality errors criterion S 2.3.1 criticality without sufficient shut-off reserve of the instant shut-off System.
Criterion E 2.3.1 - undue Reaktivitätstransiente or substances illegal extraction of neutron-absorbing.
2.4 crash loads; Events during handling, storage or transport criterion S 2.4.1 crash of a load in one of the following room areas: - reactor tank or reactor vessel, primary circuit-including first barrier - sedimentation tanks, fuel storage pool, - experimental facilities, - nozzles, resulting in a loss of low criticality or not lockable larger leakage (more than 0.3 litres per second).
Criterion E 2.4.1 crash -.
a Brennelements in the spent fuel storage pool, in the transport or storage containers or into the reactor tank or into the reactor vessel, other load in the spent fuel storage pool, reactor tanks or the reactor vessel, resulting in a larger (more than 0.3 litres per second) lockable or low (0.3 litres per second or less) not lockable leakage, - other load in a room area of the primary circuit run up to including the first shut-off or the experimental facilities or the beamlines , if is given the possibility of coolant loss in case of damage, resulting in a larger (more than 0.3 litres per second) lockable or low (0.3 litres per second or less) not lockable leakage, - a heavy burden in a room where there is a safety-critical system or part of the installation.
Criterion N 2.4.1 - instructions important event in the transport, handling and storage of a Brennelements or of other radioactive substances within the facility or the site of the installation.
-Safety-significant event during the transport or handling a load.
-Safety-significant damage on a hoist, a transport or handling equipment.
2.5 other events criterion E 2.5.1 - complete failure of the primary coolant pumps (not applicable for TRIGA - and swimming pool reactors).
-Complete blockade of cooling channels by loose parts or debris.
Criterion N 2.5.1 damage to the reactor core, reactor vessel internals, reactor pool installations, or primary heat exchanger installations.
Sign individual fuel damage are not, unless they go beyond do not have cracks or slight deformations and does not indicate systematic weaknesses.
Criterion N 2.5.2 a loose part or a foreign body - in the reactor tank or reactor vessel or in the primary cooling circuit or - in another institution of the security system, if a safety-important function, such as for example the guarantee of the integrity or cooling of the fuel elements, may be affected.
TRIGA reactors and swimming pool reactors, establish a loose part or a foreign object is not to sign, if cannot be ruled out that could have this part or this foreign body under less favorable circumstances as in this case - impair the cooling - impaired the shut-off or a fuel element damage.
Criterion N 2.5.3 damage from a water or condensation shock or systematic damage to suspension, supports and cushioning devices on a technically important pipeline or component.
Criterion N 2.5.4 - damage to primary coolant pumps that require a shutdown of the plant.
-Complete failure of primary coolant pumps during nuclear power operation; also complete with swimming pool reactors failure of primary coolant pumps shortly after shutdown of the reactor.
Criterion N 2.5.5 failures more than a main pump of the secondary circuit during nuclear power operation, if the secondary circuit carries out safety-related tasks.
Criterion N 2.5.6 is failure of the power supply, if no longer ensures the power supply of a safety-important institution.
Criterion N 2.5.7 request or false suggestion of a safeguard of part of the reactor protection system.
A Reaktorschnellabschaltung is not to report - that without security technical requirement targeted by personnel or automatically to protect who performed experimental facilities, - due to a network error (does not apply for installations where this power supply of a safety-important institution for the subsequent heat dissipation is impaired), - that takes place in the start-up phase at low reactor power; unless otherwise defined in the operating instructions for the "low reactor power", the reactor power is low at a power of less than 5 percent, - is forced cooling required for zero power without or - takes place at staff training on reactor operating without required forced cooling.
Criterion N 2.5.8 instructions significant damage on a load-bearing structure of a building.
Criterion N 2.5.9 event that requires a significant change of the security specifications.
3. the effects of external and internal events 3.1 effects of external criterion S 3.1.1 damage from earthquakes, plane crash or explosion pressure wave a building where there is a safety-critical system or part of the installation, - safety-important system or plant part with the result that a safety device is requested.
Criterion E 3.1.1 external impact, which requires the switching off or shutting down the plant for safety reasons.
To get 3.2 attachment internal events criterion S 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other exposure to indoor to an extent, which is that the necessary interpretation to the incident control number of security institutions is no longer available.
Criterion E 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other effects from the inside to an extent, where to get, that is only the required interpretation in accordance with to the mastery of the incident number of security institutions available.
Criterion N 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other action from the inside of a room or facility area, in which radioactive material with an activity beyond the table are 1 column 2 of the Radiation Protection Ordinance according to annex III or an important safety device is located.
Limited ones - in connection with modification or maintenance work, preventive scheduled fire protection measures were taken for and applying for fire-fighting was effective – in the range of experimental facilities that could affect the availability of a safety-important institution on the basis of location, type and scope are local not to sign.
4. events prior to issuance of the permit for the reactor loading criterion V 4.1 findings on a safety-important system or plant part that indicates a design error or a weakness in the quality assurance system.
Criterion V 4.2 event on a safety-important system or part of the installation, where is this event in terms of the subsequent safe operation of importance.

Appendix 4 criteria for notifiable events in facilities in decommissioning according to § 7 paragraph 3 of the Atomic Energy Act (site: BGBl. I 2010, 773-776) table of contents introduction 1 Radiology and radiation protection 1.1 radioactive waste 1.2 release radioactive substances 1.3 contamination 1.4 spread radioactive substances 2. equipment and operation 2.1 malfunctions, damages or failures on safety important facilities 2.2 damage or leaks in pipes or containers 2.3 crash loads; Events during handling, storage or transport of radioactive substances 2.4 other events 3. influences of external and internal events 3.1 influences from outside 3.2 attachment internal events before you begin the registration criteria for notifiable events in decommissioning plants, plant areas or parts apply to systems, 1st the fission of nuclear fuel were used and where the protection objectives "Under criticality" and "to heat" for the rest of the plant in decommissioning are no longer relevant or 2 were not the fission of nuclear fuel and where the protection objective "Under criticality" no longer relevant is, as far as for this a permit has already been granted according to article 7, paragraph 3, of the nuclear energy Act.
These criteria are not available, appendices 1, 2, or 3 apply depending on the approval and installation type continue to.
1. Radiology and radiation protection reference to the values of annex III is made when the following criteria table 1 column 4 of the Radiation Protection Ordinance, is to use an average area of 300 square centimetres.
1.1 disposal of radioactive waste criterion S 1.1.1 exceeds disposal of radioactive waste with air or water, where the activity derived from 24 hours - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance leads or - activity charges laid down by the competent authority, the calendar year maximum.
Criterion E 1.1.1 disposal of radioactive waste with air or water, with the derived activity greater than laid down by the competent authority, maximum activity taxes.
1.2 release of radioactive substances to get criterion S 1.2.1 release of radioactive substances into the environment, where is that 24 hours leads released activity - to the limit values being exceeded of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance or - is more than 10 percent of activity charges laid down by the competent authority for derivatives, the calendar year maximum.
Criterion to get E 1.2.1 release of radioactive substances into the environment, where is that the released activity -.
leads to body doses, more than 10% of the limit values be more than 10 per cent of set by the competent authority for discharges according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance, or -, is the calendar year maximum activity charges.
Criterion N 1.2.1 release of radioactive substances into the environment that does not fall under the criteria of S 1.2.1 or E 1.2.1.
Criterion S 1.2.2 release of radioactive substances within the plant, so that outside of the area designated as a control panel, the dose rate exceeds the value of 3 milliSievert per hour.
Criterion E 1.2.2 release of radioactive substances within the plant, so that - within an area designated as a control panel, as far as this is not marked as block area, the dose rate exceeds the value of 3 milliSievert per hour for more than 24 hours or - to set up a new control area is required.
1.3 contamination criterion E 1.3.1 contamination within the monitoring range, the one hundred times of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than ten times of the values according to annex III.
Criterion N 1.3.1 contamination within the control area, may be in an area that is not contaminated during normal operation, a thousand-fold of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than one hundred times of the values according to annex III.
1.4 spread radioactive material criterion S 1.4.1 proliferation of radioactive materials from the plant through abduction in an area - outside of supervised areas at the premises, unless there deported activity according to annex III, table 1 column 4 of the Radiation Protection Ordinance exceeds one hundred times of the values and according to annex III, table 1 column 2 of the Radiation Protection Ordinance exceeds one hundred times of the values, or - offsite , if activity there deported one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and ten times of the values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
Criterion E 1.4.1 proliferation of radioactive substances from the plant through abduction in an area - outside of supervised areas at the premises, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and the simple the Values table 1 column 2 exceeding the Radiation Protection Ordinance according to annex III.
2. equipment and operation 2.1 malfunctions, damages or failures in safety-important facilities criterion N 2.1.1 malfunction, damage or failure at a technically important institution that must be available for the compliance with the objectives of protection, with the result that - is at least a redundancy of a safety-major system unavailable or - in the event of malfunction, damage or failure for safety reasons the reduction measures in accordance with the approved operating regulations must be interrupted.
Not to report malfunctions, damages or failures - in the safety-important institutions, which are fixed in less than 24 hours or within the permitted repair times set out in the approved operating instructions if the function of the system is maintained, - safety-important facilities for the in the approved regulations alternative measures are intended for a limited period, provided that the event is not to be reported according to criterion N 2.1.2.
Criterion N 2.1.2 failure, damage or findings with reference to a systematic error at a technically important institution.
Criterion N 2.1.3 loss of or damage to an institution of technical or constructional fire protection.
Not to report failures are by or minor damage to individual components of plant technical or constructional fire protection that the fire protection capabilities has not unacceptably reduced.
Criterion N 2.1.4 instructions significant deviation from the specified state in a technically important system or unit or by a technically important threshold set out in the operating instructions (specifications).
2.2 damage or leaks in pipes or tanks criterion 2.2.1 N leakage or damage to an institution that is essential for the inclusion of activity or an any other activity-leading system or other activity-leading component.
Individual drip leaks at gaskets and flanges are not to report.
Criterion N 2.2.2 - failure of a pressure component with immediate effect on a safety-critical system or - damage in high pressure-bearing components, where to get is that a failure due to this damage directly or in a chain of to increase subsequent events leads to harm a technically important system or component.
2.3 crash loads; Criterion N 2.3.1 - crash of a load, led events during handling, storage or transport of radioactive materials to the detriment of a safety-important system or component, or could have.
-Safety-significant event during the transport or storage of radioactive materials within the plant premises.
-Safety-significant damage on a hoist or a transport or handling equipment.
2.4 other events criterion 2.4.1 N event that requires a significant change of the security specifications.
Criterion 2.4.2 N damage to a load-bearing structure of a building with the result that the availability of a safety-major system or a system can be affected.
Criterion N 2.4.3 Auslegungsgemäße request a safety-important institution in its safety function.
Requirements, specifically performed by personnel without security technical requirement or that clearly attributable to network errors are not to report.
3. effects of external and internal events 3.1 effects of external criterion S 3.1.1 earthquakes, plane crash, explosion pressure wave or other effects from outside, so that the State of a system is entered, - where the protection objective "Inclusion of radioactive materials" or the "Limitation of radiation exposure" target was injured and - has a gefahrbringend effect on the population or the environment or is to get this.
Criterion E 3.1.1 earthquakes, plane crash, explosion pressure wave or other effects from outside, so that the State of a system is entered, where the protection objective "Inclusion of radioactive materials" or the "Limitation of radiation exposure" objective has been violated or is to get this.
3.2 attachment internal events criterion S 3.2.1 of attachment internal fire, plant-internal explosion, violent chemical reaction, flooding or other action from the inside, so that the State of a system is entered, - where the protection objective "Inclusion of radioactive materials" or the "Limitation of radiation exposure" target was injured and - has a gefahrbringend effect on the population or the environment or is to get this.
Criterion E 3.2.1 of attachment internal fire, plant-internal explosion, violent chemical reaction, flooding or other action from the inside, so that the State of a system is entered, where the protection objective "Inclusion of radioactive materials" or the "Limitation of radiation exposure" objective has been violated or is to get this.
Criterion N 3.2.1 of attachment internal fire, plant-internal explosion, flooding or other action from the inside of a room or facility area, in which radioactive material with an activity beyond the table are 1 column 2 of the Radiation Protection Ordinance according to annex III or an important safety device is located.
Report limited ones relating to degradation, modification or maintenance work, for the preventive scheduled fire protection measures were taken and whose application was effective when fire-fighting are not fixed.

Appendix 5 reporting criteria for notifiable events for storage pursuant to section 6 of the nuclear energy Act (site: BGBl. I 2010, 777-779) contents preliminary note 1. Radiology and radiation protection 1.1 release of radioactive substances 1.2 contamination 1.3 spread radioactive substances 2. technology and operation 2.1 malfunctions, damages or failures in safety-critical systems or facilities 2.2 crash loads; Events during handling or transport 2.3 occurrences 3. influences of external and internal events 3.1 the effects of outside 3.2 setting up internal events introduction
The reporting criteria apply to the storage of nuclear fuel according to § 6 of the Atomic Energy Act. Therefore the storing of nuclear fuel as well as keeping of compacted highly radioactive fission product solutions and the necessary facilities for this purpose and activities including the in-house transports are covered.
1. Radiology and radiation protection reference to the values of annex III is made when the following criteria table 1 column 4 of the Radiation Protection Ordinance, is to use an average area of 300 square centimetres.
1.1 release of radioactive substances criterion to get S 1.1.1 release of radioactive substances into the environment, where is that activity released within 24 hours of leads to exceeding the limits of the body doses according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance.
Release of radioactive substances into the environment, where to get is that the released activity leads to body doses, more than 10% of the limit values according to § 47 paragraph 1 sentence 1 of the Radiation Protection Ordinance be criterion E 1.1.1.
Criterion N 1.1.1 release of radioactive substances into the environment that does not fall under the criteria of S 1.1.1 or E 1.1.1.
Criterion S 1.1.2 release of radioactive substances within the facility so that outside of the area designated as a control panel, the dose rate exceeds the value of 3 milliSievert per hour.
Criterion E 1.1.2 release of radioactive substances within the facility so that - within an area designated as a control panel, as far as this is not marked as block area, the dose rate exceeds the value of 3 milliSievert per hour for more than 24 hours, or - the establishment of a new control area is required.
1.2 contamination criterion E 1.2.1 contamination within the monitoring range, the one hundred times of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than ten times of the values according to annex III.
Criterion N 1.2.1 contamination within the control area, may be in an area that is not contaminated during normal operation, a thousand-fold of the values exceeds table 1 column 4 of the Radiation Protection Ordinance according to Appendix III and their overall activity is table 1 column 2 of the Radiation Protection Ordinance in becquerel more than one hundred times of the values according to annex III.
1.3 spread radioactive material criterion S 1.3.1 proliferation of radioactive materials from the establishment by spreading into an area - outside of supervised areas at the premises, provided there was deported activity one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite , if activity there deported one hundred times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and ten times of the values according to annex III table exceeds 1 column 2 of the Radiation Protection Ordinance.
Criterion E 1.3.1 proliferation of radioactive substances from the facility through abduction in an area - outside of supervised areas at the premises, unless there deported ten times of the values activity according to Appendix III table 1 column 4 of the Radiation Protection Ordinance and one hundred times of the values according to annex III table 1 column 2 of the Radiation Protection Ordinance exceeds, or - offsite, unless there deported activity ten times of the values according to annex III table 1 column 4 of the Radiation Protection Ordinance and the simple the Values table 1 column 2 exceeding the Radiation Protection Ordinance according to annex III.
2. technology and operation 2.1 malfunctions, damages or failures in safety-critical systems or facilities criterion E 2.1.1 malfunction, damage or failure of safety-important system or safety-important facility, so that other storage an extra and so far not set out in the approved instructions (specifications, operating and testing) measure must be taken according to § 6 of the Atomic Energy Act.
Criterion N 2.1.1 malfunction, damage or failure of a safety-important or an important safety device.
Not to report malfunctions, damages or failure - on the other safety-critical systems, addressed in less than 24 hours or within the permitted repair times set out in the approved operating instructions if the function of the system is maintained, - are the other important safety systems for the approved alternative measures for a limited period are allowed, unless the incident is not to report according to criterion N 2.1.2 , - lower scale of the individual components of the structural fire protection, as well as the failure of individual components of the local fire-fighting and fire safety equipment.
Criterion N 2.1.2 failure, damage or findings with reference to a systematic error in the technically important system or a safety-important institution.
Criterion N 2.1.3 - triggering a pressure switch of sealing systems for the transport or storage containers.
-Triggering a pressure switch, which is not due to leaks the cover seals, unless the defect on the pressure switch can be rectified within the time allowed by laid down in the approved regulations to repair.
2.2 crash loads; Events during handling or transport is criterion 2.2.1 - crash of a container which is loaded with nuclear fuel or hardened fission product solutions.
-Crash of a heavy load on a container that is loaded with nuclear fuel or hardened fission product solutions.
Criterion N 2.2.1 - instructions important event during the transport or handling of transport or storage tank.
-Safety-significant event during the transport or handling a load.
-Safety-significant damage on a hoist or a transport or handling equipment.
2.3 other events criterion N 2.3.1 instructions relevant deviation from an officially set value of technology or operation.
Criterion N 2.3.2 instructions significant damage on a load-bearing structure of a building.
Criterion N 2.3.3 event that requires a significant change of the security specifications.
3. effects of external and internal events 3.1 effects of external criterion S 3.1.1 is to get this earthquake, plane crash, explosion pressure wave or other effects from outside, so that a condition of the institution has occurred, which has a gefahrbringend effect on the population or the environment, or where.
Criterion E 3.1.1 earthquakes, plane crash, explosion pressure wave or other external impact, that storage can be continued pursuant to section 6 of the nuclear energy act only with a measure of additional, laid down in the regulations, so far.
3.2 setting up internal criterion S 3.2.1 of setting up internal fire, setting up internal explosion, violent chemical reaction to obtain this flooding or other action from the inside, so that a condition of the institution has occurred, which has a gefahrbringend effect on the population or the environment, or where is events.
Criterion E 3.2.1 of setting up internal fire, setting up internal explosion, violent chemical reaction, flooding or other action from the inside, that storage can be continued pursuant to section 6 of the nuclear energy act only with a measure of additional, laid down in the regulations, so far.
Criterion N 3.2.1 of setting up internal fire, setting up internal explosion, violent chemical reaction, flooding or other action from the inside in a room or area of the institution, in which radioactive material with an activity beyond the table are 1 column 2 of the Radiation Protection Ordinance according to annex III or an important safety device is located.
Report limited ones in connection with modification and maintenance, for the preventive fire protection measures have been taken and their application was effective when fire-fighting are not fixed.