Trial application of PRATOOL: Performance of sensitivity studies on service water systems
Description
PRATOOL is a computer program developed to supplement the Integrated Reliability and Risk Analysis System (IRRAS) probabilistic risk assessment (PRA) computer program. It is intended to be a tool for performing PRA sensitivity analyses. This will allow a PRA's results to be easily reevaluated to show its sensitivity to changing parameter (system, component type, basic event, etc.) values (i.e., failure rates). This report documents a trial application of PRATOOL. It evaluates the sensitivity of core damage frequency to service water system availability at several nuclear power plants. For the purpose of this trail application of PRATOOL, service water system sensitivity studies were performed using the results of several NUREG- 1150 PRAs. These plants were chosen because their PRAs were already loaded into the IRRAS data base. Therefore, they are readily available for this type of study. PRATOOL contains a small subset of the functions provided by IRRAS. The user can select sets of parameters that will act as the bases for sensitivity analyses. Depending on the PRA used, the parameters selected can include: systems, component types, trains, locations, failure modes, and basic events. It will also perform and AND-ing operation on selected parameters. This allows the user define any number of possible combinations of parameters. The results of the four sensitivity studies would tend to indicate that the SWS availability is important for BWRs but unimportant for PWRs. Both BWRs showed significant increases in CDF if their SWS failure rates are allowed to increase. From the results of the four sensitivity studies, it is interesting to note that no improvements made to any of the SWSs' failure rates would result in a significant decrease on CDF. 10 figs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92003265; NTIS; INIS; US Govt. Printing Office Dep.Files
23022752.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 31 p.
- Report number
- EGG-SSRE--9581
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23022752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FEEDWATER; GRAND GULF-1 REACTOR; GRAND GULF-2 REACTOR; NUCLEAR POWER PLANTS; P CODES; PEACH BOTTOM-1 REACTOR; PEACH BOTTOM-2 REACTOR; PEACH BOTTOM-3 REACTOR; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT; SENSITIVITY; SEQUOYAH-1 REACTOR; SEQUOYAH-2 REACTOR; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).