Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 1, Main report
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
This document presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in this document 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.
- 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:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5282295
- Report Number(s):
- NUREG/CR-5604-Vol.1; EGG--2608-Vol.1; ON: TI92013992
- Country of Publication:
- United States
- Language:
- English
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Technical Report
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Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:5334200
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Tue Mar 31 23:00:00 EST 1992
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
C CODES
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPES
POWER REACTORS
PROBABILITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
RUPTURES
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS