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Title: Approach for Czech regulatory body to LBB

Conference ·
OSTI ID:489307
 [1]
  1. State Office for Nuclear Safety (SONS), Prague (Czech Republic)

At present there are two NPPs equipped with PWR units in Czech Republic. The Dukovany NPP is about ten years in operation (four units 440 MW - WWER model 213) and Temelin NPP is under construction (two units 1000 MW-WWER model 320). Both NPPs were built to Soviet design and according to Soviet regulations and standards but most of equipment for primary circuits was supplied by home manufactures. The objective for the Czech LBB programme is to prove the LBB status of the primary piping systems of these NPPs and the LBB concept is a part of strategy to meet western style safety standards. The reason for the Czech LBB project is a lack of some standard safety facilities, too. For both Dukovany and Temolin NPPs a full LBB analysis should be carried out. The application of LBB to the piping system should be also a cost effective means to avoid installations of pipe whip restraints and jet shields. The Czech regulatory body issued non-mandatory requirement {open_quotes}Leak Before Break{close_quotes} which is in compliance with national legal documents and which is based on the US NRC Regulatory Procedures and US standards (ASME, CODE, ANSI). The requirement has been published in the document {open_quotes}Safety of Nuclear Facilities{close_quotes} No. 1/1991 as {open_quotes}Requirements on the Content and Format of Safety Reports and their Supplements{close_quotes} and consists of two parts (1) procedure for obtaining proof of evidence {open_quotes}Leak Before Break{close_quotes} (2) leak detection systems for the pressurized reactor primary circuit. At present some changes concerning both parts of the above document will be introduced. The reasons for this modifications will be presented.

Research Organization:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle Memorial Inst., Columbus, OH (United States)
OSTI ID:
489307
Report Number(s):
NUREG/CP-0155; CONF-9510432-; ON: TI97004806; TRN: 97:011447
Resource Relation:
Conference: Seminar on leak before break in reactor piping and vessels, Lyon (France), 9-11 Oct 1995; Other Information: PBD: Apr 1997; Related Information: Is Part Of Proceedings of the seminar on leak before break in reactor piping and vessels; Faidy, C. [ed.] [Electricite de France, Villeurbanne (France)]; Gilles, P. [ed.] [Framatome, Paris (France)]; PB: 773 p.
Country of Publication:
United States
Language:
English