Steam generator replacements on the French 900 MW PWR nuclear power plants. Improvement of the performances

Steam Generator Replacements (SGR) have already been performed on 7 of the 54 PWR Nuclear Power Plants the (NPP) in France; further SGRs are scheduled on other NPPs. The present paper is divided in 3 major parts: The first part describes the results from on the different SGR performed and the optimal goals set for the next scheduled operations. The second part describes the main evolutions in the technical process, which is briefly summarized by the following items: Cutting off primary piping. Decontamination. Metrology and welding. Single reference for all tool sets. Non-destructive testing. Worn Steam Generator Storage Building. The third part describes the software programs specifically developed for: Space and packing management at the reactor cavity level Managing the overall SGR by means of a 4 dimensional software which allows the implementation team to visualize the 3 dimensional work phases linked to the planning. All the items shortly described in this paper will be used in the next SGR scheduled on Tricastin Unit 1 in December 1998 and on Gravelines Unit 4 in autumn 2000. (author)