A probabilistic evaluation of the safety of Babcock and Wilcox nuclear reactor power plants with emphasis on historically observed operational events
Description
This report summarizes a study performed by Brookhaven National Laboratory for the Office of Nuclear Reactor Regulation, Division of Engineering and System Technology (A/D for Systems), US Nuclear Regulatory Commission. This study was requested by the NRC to assist their staff in assessing the risk significance of features of the Babcock and Wilcox (B and W) reactor plant design in the light of recent operational events. This study focuses on a critical review of submissions from the B and W Owners Group (BWOG) and as an independent assessment of the risk significance of ''Category C'' events at each operating B and W reactor. Category C events are those in which system conditions reach limits which require significant safety system and timely operator response to mitigate. A precursor study for each of the major B and W historical Category C events also was carried out. In addition, selected PRAs for B and W reactor plants and plants with other pressurized water reactor (PWR) designs were reviewed to appraise their handling of Category C events, thereby establishing a comparison between the risk profiles of B and W reactor plants and those of other PWR designs. The effectiveness of BWOG recommendations set forth in Appendix J of the BWOG SPIP (Safety and Performance Improvement Program) report (BAW-1919) also was evaluated. 49 refs., 21 figs., 52 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A08/MF A01 - US Govt. Printing Office. - OSTI as TI89009355.
Files
Additional details
Publishing Information
- Imprint Pagination
- 160 p.
- Report number
- NUREG/CR--5206
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20052934
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CRYSTAL RIVER-3 REACTOR; EVALUATION; MILLSTONE-3 REACTOR; OCONEE-3 REACTOR; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR OPERATORS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SENSITIVITY ANALYSIS; TRANSIENTS; ZION-1 REACTOR
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; PERSONNEL; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- BNL-NUREG--52161.