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Evaluation of Available Data, for, Probabilistic Risk Assessments (PRA) of Fire Events at Nuclear Power Plants (NUREG/CR-4231)

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Publication Information

Manuscript Completed: February 1985
Date Published: May 1985

Prepared by
L. M. Krasner, C. S. Ganti, B. G. Vincent, Factory Mutual Research
P. K. Samanta, J. L. Boccio, Brookhaven National Laboratory

Factory Mutual Research
Norwood, MA 02062

Under Contract to:
Brookhaven National Laboratory
Department of Nuclear Energy
Upton, NY 11973

Prepared for
Division of Engineering
Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555
NRC FIN A3710

Availability Notice


Abstract

Several crucial parameters are needed in the assessment of fire risk in nuclear power plants.   Among those that need to be developed from a data base are: (1) fire frequency, (2) fire detection time, and (3) fire suppressiontime. Currently, the data base for nuclear power plants is not large enough to develop these parameters, considering fuel locationI fuel geometry, combustion properties, enclosure geometry, etc.   This study attempts to augment the nuclear data base by investigating the usefulness of other nonnuclear data bases which contain fire incident loss experience of occupancy classes having somewhat similiar physical features and fire protection engineering systems normally found in nuclear power plants.   This study has found that indeed some useful information can be gleaned from nonnuclear sources; in particular, detection and suppression  times.   However, other fire-risk data needs such as fire frequency and fire size would require other forms of data searches and data analyses that at this stage can only be conceptualized.



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