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Fitzpatrick, R.G.; Bozoki, G.; Sabek, M.
Eighteenth water reactor safety information meeting. Volume 2, Severe accident research, accident management, probabilistic risk assessment topics, individual plant examination program and other issues1991
Eighteenth water reactor safety information meeting. Volume 2, Severe accident research, accident management, probabilistic risk assessment topics, individual plant examination program and other issues1991
AbstractAbstract
[en] The review of the Diablo Canyon Probabilistic Risk Assessment (DCPRA) incorporated some new and innovative approaches. These were necessitated by the unprecedented size, scope and level of detail of the DCPRA, which was submitted to the NRC for licensing purposes. This paper outlines the elements of the internal events portion of the review citing selected findings to illustrate the various approaches employed. The paper also provides a description of the extensive and comprehensive importance analysis applied by BNL to the DCPRA model. Importance calculations included: top event/function level; individual split fractions; pair importances between frontline-support and support-support systems; system importance by initiator; and others. The paper concludes with a brief discussion of the effectiveness of the applied methodology
Primary Subject
Source
Weiss, A.J. (comp.) (Brookhaven National Lab., Upton, NY (USA)); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States); 578 p; Apr 1991; p. 473-491; 18. water reactor safety information meeting; Rockville, MD (United States); 22-24 Oct 1990; CONF-9010185--VOL.2; OSTI as TI91011738; NTIS; INIS; GPO
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
AUXILIARY WATER SYSTEMS, BNL, CONTROL ROOMS, DIABLO CANYON-1 REACTOR, DIABLO CANYON-2 REACTOR, DIESEL ENGINES, ECCS, ELECTRIC GENERATORS, EMERGENCY PLANS, FAILURE MODE ANALYSIS, FEEDWATER, HEAT TRANSFER, HYDRAULICS, LOSS OF COOLANT, PRESSURIZATION, PRIMARY COOLANT CIRCUITS, REACTOR CORE DISRUPTION, REACTOR LICENSING, REACTOR OPERATORS, REACTOR PROTECTION SYSTEMS, RISK ASSESSMENT, SEISMIC EFFECTS, US NRC, VENTILATION
ACCIDENTS, AUXILIARY SYSTEMS, COOLING SYSTEMS, ELECTRICAL EQUIPMENT, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EQUIPMENT, HYDROGEN COMPOUNDS, LICENSING, MOTORS, NATIONAL ORGANIZATIONS, OXYGEN COMPOUNDS, PERSONNEL, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, THERMAL REACTORS, US AEC, US DOE, US ERDA, US ORGANIZATIONS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue