The discussions on the assessment criteria for the evaluation of the operator reports, started at the 435th meeting, were completed.

The RSK adopted the catalogue of requirements (see 433rd RSK meeting) for “plant-specific reviews of German nuclear power plants in the light of the events in Fukushima-I”. The catalogue of requirements and an additional explanatory preface can be downloaded from this homepage. This catalogue of requirements shall be used by GRS as a basis for drawing up a list of questions for the operators of German nuclear power plants.

The RSK discussed assessment criteria for the evaluation of the operator reports within the framework of the "Plant-specific safety review of German nuclear power plants in the light of the events in Fukushima-I ".

The discussions have to be continued at the next meeting.

The RSK discussed the indication on the thermal sleeve identified during refuelling outage 2010 in the Grafenrheinfeld nuclear power plant (KKG). Corresponding reports were presented in the RSK Committee on PRESSURE-RETAINING COMPONENTS AND MATERIALS (DKW) the day before the meeting. The statement on the "Evaluation of the three-pillar concept for testing of safety-relevant valves" (in German) was adopted, the consultation on the statement on leakages from steam generator tubes to be postulated.

At this meeting, the RSK consulted on project work on a new KTA safety standard to be adopted in the 65th KTA meeting on 16.11.2010. A statement of the RSK Committee on PRESSURE-RETAINING COMPONENTS AND MATERIALS (DKW) on leakages from steam generator tubes to be postulated was discussed. The consultations are to be continued at the next meeting. Consultation on another statement was postponed to the next meeting for lack of time.

The RSK was informed by the BMU about the request for advice on “Performance of integrated event analyses”. The Standard Projects of the 65th meeting of the KTA on 16.11.2010 were prepared by the RSK.
The RSK adopted the revised version of the “Recommendations for the planning of emergency control measures by the licensees of nuclear power plants” (in German) still to be approved by the SSK.

The RSK was informed about the status of work in the ad hoc working groups on the post-accident phase (“Nachstörfallphase”) and the use of computer-based I&C (“Einsatz rechnerbasierter Leittechnik”).

The RSK adopted the statement on "Steam generator tube degradation due to stress corrosion cracking – cause and identification" (in German). Further, it discussed two questions regarding postulates for the demonstration of core cooling in pressurised water reactors.

On the basis of the evaluation of the operator reports, the RSK prepared the statement "Plant-specific safety review (RSK-SU) of German nuclear power plants in the light of the events in Fukushima-I (Japan)".

The statement was presented to the public by the BMU on 17.05.2011 at a press conference

The 427th RSK meeting was held in Bremen. The RSK adopted the statement “Safety requirements at the interface between systems engineering and civil engineering in nuclear power plants” (in German) and was informed about the revised version of the “Recommendations for the planning of emergency control measures by the licensees of nuclear power plants” prepared by the SSK. The related consultations are to be continued at one of the next meetings.

The BMU informed the RSK on the request for advice on conditions for safe plant operation. The RSK decides to seek advice from the RSK Committee on REACTOR OPERATION (RB).

The RSK closed the discussion on the topics of consultations for 2010 and continued discussions on the statement “Requirements for dowel connections in nuclear power plants”. The RSK asked the Committee on PRESSURE-RETAINING COMPONENTS AND MATERIALS (DKW) to consult on the draft statement on the "Evaluation of the three-pillar concept for testing of safety-relevant valves" of the RSK Committee on REACTOR OPERATION (RB) since the statement might concern issues related to the integrity of the valves.
The RSK started discussions on the statement “Safety requirements at the interface between systems engineering and civil engineering in nuclear power plants”.