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Nuclear Power Plant Fire Protection - Fire-Hazards Analysis (Subsystems Study Task 4) (NUREG/CR-0654)
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Publication Information
Dennis L. Berry Earl E. Minor
Manuscript Submitted: January 1979
Date Published: September 1979
Sandia Laboratories Albuquerque, New Mexico 87185
operated by Sandia Corporation.
for the
U.S. Department of Energy
Prepared for
Engineering Methodology Standards Branch
Office of Standards Development
U.S. Nuclear Regulatory Commission
Washington, DC 20555
Under Interagency Agreement DOE 40-550-75
NRC FIN No. A-1080
Availability
Notice
Abstract
This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant
safety. By combining and simplifying a number of available
analysis techniques and by demonstrating the technical merit of
each technique, this report develops a conservative fire-hazards
analysis method which can be easily used by both designers and
regulators. As described, a suitable analysis method for nuclear power plants should involve three phases. These are: (1) a deterministic evaluation of passive fire barriers under
limiting fuel load and ventilation conditions; (2) a
probabilistic evaluation of supplementary fire protection
measures (e.g., suppressions systems); and (3) a subjective
evaluation of unquantified fire hazard conditions (e.g., cable arrangements). An example of each analysis phase is provided.
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