Analysis of the results of the Midland PRA
Description
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 (≤3%). 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86014763.Files
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- BNL-NUREG--38408
Conference
- Title
- American Society of Mechanical Engineers winter meeting.
- Dates
- 7-12 Dec 1986.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18051253
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURE MODE ANALYSIS; MIDLAND-1 REACTOR; MIDLAND-2 REACTOR; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT
- Descriptors DEC
- ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PROCESS HEAT REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-861211--8.