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Additional resources for Generic Safety Issues for Nuclear Power Plants with PHWR's - IAEA TECDOC-1554

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Due to above mentioned Responsible Organisation was required to replace the all the original coolant channels by others without Stellite-6. This task is gradually going on at each programmed outage and up to now 152 channels have been replaced, representing more than 60 % of their total number. The CANDU reactors cooling channels (pressure tubes) are degraded in way which could not be predicted in the original design. It is known that the degradation mechanisms are: hydrogen uptake, blister formation, rolled joint cracking, sag/deformation and fuel-bundle bearing-pad fretting.

Efforts were made by KANUPP to locate these leaking points in the past but no result could generally be achieved. It was only late 2000 that some success was achieved in identifying the leaking coil during a special test performed with coolant temperature 5250F. A large number of leaking coils were identified. KANUPP has isolated these coils by cutting and welding the corresponding lines. The problem has not yet been resolved and further efforts are underway to arrest the issue. 23 Romania The ageing problems as part of the safety requirements for the systems and components were part of the current licensing concerns, and are reflected in the license requirements for unit 1 and the generic requirements for unit 2.

ATOMIC ENERGY REGULATORY BOARD, Safety Guide, “Life Management of NPPs” AERB/NPP/SG/O-14. 24 ISSUE TITLE: Inadequacy of reliability data (GL 4) ISSUE CLARIFICATION Description of issue This issue is also applicable to NPPs with LWR. g. PSA) of a nuclear power plant. The type and degree of detail of the database is determined by the intended use of the evaluation. For a general evaluation, a generic data base might be sufficient. But for a systematic evaluation of the level of plant safety and/or for an optimal maintenance programme, a plant specific database is generally required.

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Generic Safety Issues for Nuclear Power Plants with PHWR's - IAEA TECDOC-1554

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