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AbstractAbstract
[en] Four Level I probabilistic risk assessments (PRAs) have been completed by Sandia National Laboratories and its contractors in support of the NUREG-1150 program. The applicability of the methodology used and the results from these four analyses are discussed in this paper. The methods used are clearly applicable and reasonably efficient for any light water reactor (LWR) PRA. some of the results have generic applicability, but many are either plant specific or relate only to similar plants or plants with the same system configuration on a particular issue. In this paper, important aspects of systems that affect dominant accident sequences, such as station blackout, and that could be important at other plants are discussed. 12 refs., 2 tabs
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1988; 7 p; International topical meeting on probability, reliability and safety assessment; Pittsburgh, PA (USA); 2-7 Apr 1989; CONF-890405--14; Available from NTIS, PC A02/MF A01 - OSTI; 1 as DE89005205; Portions of this document are illegible in microfiche products.
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