Review of the Byron/Braidwood Units 1 and 2 auxiliary feedwater system reliability analysis
Technical Report
·
OSTI ID:5486787
This report presents the results of a review of the Auxiliary Feedwater System Reliability Analysis for Byron Units 1 and 2/Braidwood Units 1 and 2. The objective of this report is to estimate the probability that the Auxiliary Feedwater System will fail to perform its mission for each of three different initiators: (1) loss of main feedwater with offsite power available, (2) loss of offsite power, (3) loss of all 460 VAC power. The scope, methodology, and failure data are prescribed by NUREG-0611, Appendix III. The results are compared with those obtained in NUREG-0611 for other Westinghouse plants.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5486787
- Report Number(s):
- NUREG/CR-3096; BNL-NUREG-51633; ON: DE84004652
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BRAIDWOOD-1 REACTOR
BRAIDWOOD-2 REACTOR
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PERFORMANCE
POWER REACTORS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BRAIDWOOD-1 REACTOR
BRAIDWOOD-2 REACTOR
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PERFORMANCE
POWER REACTORS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS