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Title: The risk management implications of NUREG--1150 methods and results

Abstract

This report describes the potential uses of NUREG-1150 and similar Probabilistic Risk Assessments (PRAs) in NRC and industry risk management programs. NUREG-1150 uses state-of-the-art PRA techniques to estimate the risk from five nuclear power plants. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. While the development of plant-specific risk management strategies is beyond the scope of this document, examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management from prevention of initiating events though reduction of offsite consequences are discussed, with particular attention given to the early phase of accidents. 14 refs., 9 figs., 28 tabs.

Authors:
; ;  [1]
  1. Sandia National Labs., Albuquerque, NM (USA)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USNRC
OSTI Identifier:
5559609
Report Number(s):
NUREG/CR-5263; SAND-88-3100
ON: TI90000558; TRN: 89-027163
DOE Contract Number:  
AC04-76DP00789
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; GRAND GULF-1 REACTOR; RISK ASSESSMENT; GRAND GULF-2 REACTOR; PEACH BOTTOM-1 REACTOR; PEACH BOTTOM-2 REACTOR; PEACH BOTTOM-3 REACTOR; SEQUOYAH-1 REACTOR; SEQUOYAH-2 REACTOR; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; CONTAINMENT SYSTEMS; EMERGENCY PLANS; FAILURE MODE ANALYSIS; FISSION PRODUCT RELEASE; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MANAGEMENT; N CODES; NUCLEAR POWER PLANTS; QUALITY ASSURANCE; REACTOR COMPONENTS; REACTOR MAINTENANCE; REACTOR SAFETY; ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; CONTAINMENT; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MAINTENANCE; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 990220 - Computers, Computerized Models, & Computer Programs- (1987-1989); 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Camp, A. L., Maloney, K. J., and Sype, T. T. The risk management implications of NUREG--1150 methods and results. United States: N. p., 1989. Web. doi:10.2172/5559609.
Camp, A. L., Maloney, K. J., & Sype, T. T. The risk management implications of NUREG--1150 methods and results. United States. https://doi.org/10.2172/5559609
Camp, A. L., Maloney, K. J., and Sype, T. T. 1989. "The risk management implications of NUREG--1150 methods and results". United States. https://doi.org/10.2172/5559609. https://www.osti.gov/servlets/purl/5559609.
@article{osti_5559609,
title = {The risk management implications of NUREG--1150 methods and results},
author = {Camp, A. L. and Maloney, K. J. and Sype, T. T.},
abstractNote = {This report describes the potential uses of NUREG-1150 and similar Probabilistic Risk Assessments (PRAs) in NRC and industry risk management programs. NUREG-1150 uses state-of-the-art PRA techniques to estimate the risk from five nuclear power plants. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. While the development of plant-specific risk management strategies is beyond the scope of this document, examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management from prevention of initiating events though reduction of offsite consequences are discussed, with particular attention given to the early phase of accidents. 14 refs., 9 figs., 28 tabs.},
doi = {10.2172/5559609},
url = {https://www.osti.gov/biblio/5559609}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 1989},
month = {Fri Sep 01 00:00:00 EDT 1989}
}