Interim reliability evaluation program, Browns Ferry 1

Conference · Wed Dec 31 23:00:00 EST 1980

OSTI ID:5274879

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

Probabilistic risk analysis techniques, i.e., event tree and fault tree analysis, were utilized to provide a risk assessment of the Browns Ferry Nuclear Plant Unit 1. Browns Ferry 1 is a General Electric boiling water reactor of the BWR 4 product line with a Mark 1 (drywell and torus) containment. Within the guidelines of the IREP Procedure and Schedule Guide, dominant accident sequences that contribute to public health and safety risks were identified and grouped according to release categories.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Energy, Inc., Kent, WA (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5274879
• Report Number(s): EGG-M-08381; CONF-810905-29; ON: DE82007349
• Country of Publication: United States
• Language: English

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