Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix B - system descriptions and fault trees
Description
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 B provides a description of Browns Ferry, Unit 1, plant systems and the failure evaluation of those systems as they apply to accidents at Browns Ferry. Information is presented concerning front-line system fault analysis; support system fault analysis; human error models and probabilities; and generic control circuit analyses
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A22/MF A01 - GPO as DE82020536.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 508 p.
- Report number
- NUREG/CR--2802-App.B
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14732107
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BROWNS FERRY-1 REACTOR; FAULT TREE ANALYSIS; REACTOR SAFETY; RELIABILITY; RISK ANALYSIS
- Descriptors DEC
- BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; MIXED SPECTRUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2199-App.B.