Published December 1992 | Version v1
Report Restricted

Risk evaluation for a Westinghouse PWR, effects of fire protection systems actuation on safety-related equipment

  • 1. Sandia National Labs., Albuquerque, NM (United States)
  • 2. ERCE, Inc., Albuquerque, NM (United States)

Description

Nuclear power plants have experienced actuations of fire protection systems (FPSs) under conditions for which these systems were not intended to actuate and also have experienced advertent actuations with the presence of a fire. These actuations have often damaged nearby plant equipment. A review of the impact of past occurrences of both types of such events, a quantification of the risk of FPS actuation, a sensitivity study of the quantification of the risk of FPS actuation and risk calculations in terms of person-REM have been performed. Thirteen different scenarios leading to actuation of fire protection systems due to a variety of causes were identified. A quantification of these thirteen scenarios, where applicable, was performed on a 3-loop Westinghouse Pressurized water Reactor (PWR). These scenarios ranged from inadvertent actuation caused by human error to hardware failures, and include seismic root causes and seismic/fire interaction. This report estimates the contribution of FPS actuations to core damage frequency and risk

Availability note (English)

MF available from INIS under the Report Number; OSTI as TI93005844; NTIS; INIS; GPO.

Files

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Additional details

Additional titles

Subtitle (English)
Evaluation of Generic Issue 57

Publishing Information

Imprint Pagination
227 p.
Report number
NUREG/CR--5789

Optional Information

Contract/Grant/Project number
Contract AC04-76DP00789
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
SAND--91-1534.