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Title: Loss of spent fuel pool cooling PRA: Model and results

This letter report documents models for quantifying the likelihood of loss of spent fuel pool cooling; models for identifying post-boiling scenarios that lead to core damage; qualitative and quantitative results generated for a selected plant that account for plant design and operational practices; a comparison of these results and those generated from earlier studies; and a review of available data on spent fuel pool accidents. The results of this study show that for a representative two-unit boiling water reactor, the annual probability of spent fuel pool boiling is 5 {times} 10{sup {minus}5} and the annual probability of flooding associated with loss of spent fuel pool cooling scenarios is 1 {times} 10{sup {minus}3}. Qualitative arguments are provided to show that the likelihood of core damage due to spent fuel pool boiling accidents is low for most US commercial nuclear power plants. It is also shown that, depending on the design characteristics of a given plant, the likelihood of either: (a) core damage due to spent fuel pool-associated flooding, or (b) spent fuel damage due to pool dryout, may not be negligible.
Authors:
; ; ; ;
Publication Date:
OSTI Identifier:
578718
Report Number(s):
INEL--96/0334
ON: DE98050286; TRN: 98:004283
DOE Contract Number:
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Sep 1996
Research Org:
Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL STORAGE POOLS; ACCIDENTS; BWR TYPE REACTORS; SPENT FUEL STORAGE; MATHEMATICAL MODELS; SAFETY ANALYSIS; REACTOR ACCIDENTS; FAILURE MODE ANALYSIS; REACTOR SAFETY; RISK ASSESSMENT