The RSK discussed the draft of the guideline on the probabilistic safety analysis submitted by the m BMU, including the appendant method volumes and the data volume. In future, these regulations shall be the basis for the safety reviews of the nuclear power plants in accordance with Section 19 a of the Atomic Energy Act (AtG). The discussion of the RSK did not lead to any general safety concerns regarding the drafts submitted. The BMU received particular information with regard to amendments, supplements and reviews for its further proceeding.

Within the framework of the revision of the nuclear rules and regulations (summary report of the 368th RSK Meeting on 11.12.2003), the RSK discussed in detail the topic area "object and purpose of postulates" and also addressed, in particular, postulated leaks and breaks. It dealt with conditions and use case of the postulates in connection, among other things, with safety analyses for the release of pipe insulation material. The statements elaborated during the meeting will be laid down in a paper.

The RSK discussed and adopted the following statements:

Project SR 2318 of the BMU "Assessment of the informational value of ultra-sonic and eddy-current examinations of austenitic RPV cladding" (in German),
"Safety aspects of the use of high burn-up fuel elements under reactivity-initiated accident (RIA) conditions", and
Gases in a repository (in German).

At the 385th meeting on 20./21.07.2005, the RSK adopted the recommendation "Requirements for safety analyses on loss-of-coolant accidents".

At the 384th meeting on 07.07.2005, the RSK discussed and adopted the statements prepared by its Committee on
PLANT- AND SYSTEMS-ENGINEERING (AST) - "Switch-off of the main coolant pumps during ATWS events at nuclear power plants with pressurised water reactor" (in German) which includes some new stipulations compared to the statement "ATWS events" (of the RSK of 03.05.2001, 340th meeting),

At the 383rd meeting on 02.06.2005, the RSK discussed safety-relevant questions related to the decommissioning and dismantling of the Stade nuclear power plant and adopted a respective statement (in German) prepared by its Committees on SUPPLY AND WASTE HANDLING (VE) and on REACTOR OPERATION (RB).
Another focal point of the meeting was the continuation of the discussions of the RSK on the topic areas/modules of the new nuclear rules and regulations planned by the BMU.

This meeting concentrated on the formation of opinion of the RSK on the topics/modules of the revision of the nuclear rules and regulations performed on behalf of the BMU (http://regelwerk.grs.de).

The RSK discussed and adopted a statement on safety-related aspects of conceptual questions on the final disposal of irradiated fuel elements using canisters emplaced in bore holes by means of a comparison with the concept of drift emplacement of thick-walled containers (in German).

The RSK discussed the nuclear-specific safety-related questions of a capacity increase of the uranium enrichment facility in Gronau applied for especially regarding the question to which extent the technical and organisational measures provided are in compliance with the state of the art in science and technology. On this issue, a draft of a statement was available which included the review results of the Committee on SUPPLY AND WASTE HANDLING (VE) and gave answers to the questions posed by the BMU.

At this meeting, the RSK discussed first of all internal issues. This was followed by an in-depth discussion of further chapters of the RSK recommendation on ageing management at nuclear power plants, which is at issue. The discussions on this recommendation shall be concluded at the 374th meeting. Regarding the requirements on the verification of the effective emergency core cooling during loss-of-coolant accidents involving the release of insulation material, the RSK discussed the currently available results of its Committee on PLANT AND SYSTEMS ENGINEERING (AST).