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Risk Evaluation for a B&W Pressurized Water Reactor, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 (NUREG/CR-5790)

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Publication Information
Abstract

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NUREG/CR-5790 (PDF - 5.35 MB)

Publication Information

Manuscript Completed: February 1992
Date Published: September 1992

Prepared by
J. Lambright, J. Lynch*, S. Ross*, E. Klamerus, S. Daniel

Sandia National Laboratorles
Albuquerque, NM 87185

Prepared for
Division of Systems Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
NRC FIN L1334

*Science and Engineering Associates, Inc.
Albuquerque, NM 87110

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Abstract

Nuclear power plants have experienced inadvertent actuations of fire protection systems (FPS) under conditions for which these systems were not intended to actuate. They have also experienced advertent actuations with the presence of a fire. These actuations have-often damaged plant equipment.

A review of the impact of past occurrences of both types of such events on nuclear power plant safety has been performed. Thirteen different scenarios leading to actuation of fire protection systems due to a variety of causes were identified. These scenarios ranged from inadvertent actuation caused by human error to hardware failure and includes seismic root causes and seismic/fire interaction. A quantification of these thirteen scenarios, where applicable, was performed on a Babcock and Wilcox Pressurized Water Reactor (lowered loop design). This report estimates the contribution of FPS actuations to core damage frequency and to risk.