Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 3, Appendices I--M
Technical Report
·
OSTI ID:10143498
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in this report provides a state- of-the-art method for identifying and evaluating plant-specific hardware designs, human performance issues, and accident consequence factors relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B & W) nuclear power plant. The results from this application are described in detail. For this particular B & W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3, provides appendices I-M for the report. Topics are: Consequence Calculations; External events analysis of ISLOCA sequences; Review of Pressure Fragility Calculations; Uncertainty Analysis; and Steam Propagation Analysis for the B & W Plant Auxiliary Building.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10143498
- Report Number(s):
- NUREG/CR--5604-Vol.3; EGG--2608-Vol.3; ON: TI92013990
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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FAILURE MODE ANALYSIS
FIRES
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