Analysis of the results of the Midland PRA

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:5048951

Bozoki, G; Teichmann, T

This paper presents the results of a limited review of the Midland PRA (MPRA), aimed at facilitating regulatory analyses and at providing insights into safety related plant failures. In particular, stress was laid on the root causes of accident sequences, particularly their failure modes, viz., hardware, human, maintenance, test, and repair. Because this information was difficult to extract in this detailed and sophisticated PRA (and in certain others) a special algorithm was developed to display the leading sequences contributing to core damage and/or to public risk in terms of the above generic failure modes. This was done in a hierarchical fashion to allow tracing the important accident sequences to the systems failures. The weighted core damage frequency (CDF) values of the sequences considered then provided a (quantitative) ranked importance listing of these failure modes, led by hardware failures (in 78%) and human factors (in 37%), etc. Multiple maintenance situations (reflecting on test and maintenance specifications) were also evaluated, but played only a small role (less than or equal to3%). Similar tabulations were also made of the (weighted) importance of the support systems (such as the electric power system, the component cooling water systems, etc.) and of the role of the major systems/functions (e.g., high pressure injection, etc.) contributions to these accident sequences. Finally, the role of certain particular operational and plant features (e.g., loss of offsite power initiators, RCP seal failure, bunkering, etc.) were briefly examined. The methods displayed seem applicable to an important class of extant and projected PRAs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5048951
• Report Number(s): BNL-NUREG-38408; CONF-861211-8; ON: TI86014763
• Resource Relation: Conference: American Society of Mechanical Engineers winter meeting, Anaheim, CA, USA, 7 Dec 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
RISK ASSESSMENT
FAILURE MODE ANALYSIS
MIDLAND-1 REACTOR
MIDLAND-2 REACTOR
PROBABILISTIC ESTIMATION
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
PROCESS HEAT REACTORS
PWR TYPE REACTORS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety