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AbstractAbstract
[en] This paper presents a critical review of a recently proposed procedure for a quantitative common cause failure analysis (CCF). Limitations of the methodology, resulting from the quality of the data base, and the lack of guidance for event interpretation, are highlighted. It is suggested that a more detailed understanding of the characteristics of common cause failure mechanisms would be advantageous to understanding vulnerabilities to CCFs. It is recognized that progress in improving the estimates of common cause failure probabilities will, in the short term, be limited. Therefore a review process, based on the assessment of the adequacy of the defensive strategy in place at a plant is proposed as a supplement to the current approach based on a review of historical events, to identify, in a more complete fashion, potential CCF mechanisms
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Secondary Subject
Source
Molina, T. (ed.); Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (United States); 475 p; Feb 1991; p. 207-219; Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations; Santa Fe, NM (United States); 4-6 Sep 1990; SAND--90-2797; CONF-9009346--; OSTI as TI91008351; NTIS; INIS
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
AVAILABILITY, BWR TYPE REACTORS, DATA BASE MANAGEMENT, EPRI, FAILURE MODE ANALYSIS, FAILURES, FAULT TREE ANALYSIS, FORECASTING, HUMAN FACTORS, MATHEMATICAL MODELS, PROBABILISTIC ESTIMATION, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR SAFETY, RELIABILITY, RESEARCH PROGRAMS, RISK ASSESSMENT, US NRC
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INIS VolumeINIS Volume
INIS IssueINIS Issue