Precursors to potential severe core damage accidents, 1985, a status report: Main report and Appendixes A, B and C
Description
As reported in licensee event reports (LERs), 63 operational events that occurred at commercial light-water reactors during 1985 are considered to be precursors to potential severe core damage. These are described along with associated significance estimates, categorization, and subsequent analyses. This study is a continuation of the work presented in NUREG/CR-2497 and NUREG/CR-3591, which evaluated the 1969 to 1981 events. The current study incorporates improvements that evolved since issue of the earlier reports, primarily in the areas of plant-class modeling and the review of reactor-trip-related events, in the assessment of the operational events that occurred during 1985. The report sequentially discusses (1) the general rationale for this study, (2) the program methods for LER review and documentation, (3) the development of event-tree-based core damage models, (4) the use of the conditional probability of subsequent severe core damage estimates to rank precursor events, and (5) the application of program results to current concerns pertaining to nuclear power plant risk assessment
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A11/MF A01 - GPO as TI87003939.
Files
Additional details
Publishing Information
- Imprint Pagination
- 238 p.
- Report number
- NUREG/CR--4674-Vol.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18057519
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FAULT TREE ANALYSIS; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR LICENSING; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; LICENSING; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/NOAC--232/V1.