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

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

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 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.

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 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.

The RSK specified the tasks for the ad hoc working group ERL (use of computer-based I&C). It was informed on the background and objectives of the statements on "Steam generator tube degradation – cause and identification" and on "Leakages from steam generator tubes to be postulated; multiple tube rupture/leak opening of wall thickness-reduced steam generator tubes" by the chairman of the RSK Committee on PRESSURE-RETAINING COMPONENTS AND MATERIALS (DKW).