Interim reliability evaluation program, Browns Ferry 1

Conference · Thu Jan 01 00:00:00 EST 1981

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
• Resource Relation: Conference: ANS/ENS topical meeting on probabilistic risk assessment, Post Chester, NY, USA, 20 Sep 1981
• 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
RELIABILITY
RISK ASSESSMENT
FAILURES
FAULT TREE ANALYSIS
REACTOR SAFETY
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled