Published September 1992 | Version v1
Report Restricted

Risk evaluation for a B ampersand W Pressurized Water Reactor, effects of fire protection system actuation on safety-related equipment

  • 1. Sandia National Labs., Albuquerque, NM (United States)
  • 2. Science and Engineering Associates, Inc., Albuquerque, NM (United States)

Description

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. This document provides a review of the impact of past occurrences of both types of such events on nuclear power plant safety. 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

Availability note (English)

MF available from INIS under the Report Number; OSTI as TI93001398; NTIS; INIS; GPO.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Subtitle (English)
Evaluation of Generic Issue 57

Publishing Information

Imprint Pagination
242 p.
Report number
NUREG/CR--5790

Optional Information

Contract/Grant/Project number
Contract AC04-76DP00789
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
SAND--91-1535.