Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix C - sequence quantification

Technical Report · Thu Jul 01 00:00:00 EDT 1982

OSTI ID:5091414

Mays, S E; Poloski, J P; Sullivan, W H; Trainer, J E; Bertucio, R C; Leahy, T J

This report describes a risk study of the Browns Ferry, Unit 1, nuclear plant. The study is one of four such studies sponsored by the NRC Office of Research, Division of Risk Assessment, as part of its Interim Reliability Evaluation Program (IREP), Phase II. This report is contained in four volumes: a main report and three appendixes. Appendix C generally describes the methods used to estimate accident sequence frequency values. Information is presented concerning the approach, example collection, failure data, candidate dominant sequences, uncertainty analysis, and sensitivity analysis.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Energy, Inc., Seattle, WA (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5091414
• Report Number(s): NUREG/CR-2802-App.C; EGG-2199-App.C; ON: DE82020538
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
REACTOR SAFETY
RISK ASSESSMENT
REACTOR ACCIDENTS
RELIABILITY
ACCIDENTS
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ENRICHED URANIUM REACTORS
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