Advanced Test Reactor outage risk assessment
Description
Beginning in 1997, risk assessment was performed for each Advanced Test Reactor (ATR) outage aiding the coordination of plant configuration and work activities (maintenance, construction projects, etc.) to minimize the risk of reactor fuel damage and to improve defense-in-depth. The risk assessment activities move beyond simply meeting Technical Safety Requirements to increase the awareness of risk sensitive configurations, to focus increased attention on the higher risk activities, and to seek cost-effective design or operational changes that reduce risk. A detailed probabilistic risk assessment (PRA) had been performed to assess the risk of fuel damage during shutdown operations including heavy load handling. This resulted in several design changes to improve safety; however, evaluation of individual outages had not been performed previously and many risk insights were not being utilized in outage planning. The shutdown PRA provided the necessary framework for assessing relative and absolute risk levels and assessing defense-in-depth. Guidelines were written identifying combinations of equipment outages to avoid. Screening criteria were developed for the selection of work activities to receive review. Tabulation of inherent and work-related initiating events and their relative risk level versus plant mode has aided identification of the risk level the scheduled work involves. Preoutage reviews are conducted and post-outage risk assessment is documented to summarize the positive and negative aspects of the outage with regard to risk. The risk for the outage is compared to the risk level that would result from optimal scheduling of the work to be performed and to baseline or average past performance
Availability note (English)
Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE98056069; NTIS; US GOVT. PRINTING OFFICE DEP.
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INEEL/CON--97-01463
Conference
- Title
- Conference on integrating safety analysis into safety management
- Dates
- 15-19 Jun 1998
- Place
- Park City, UT (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29064334
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATR REACTOR; FUEL STORAGE POOLS; MATERIALS HANDLING; REACTOR MAINTENANCE; REACTOR SHUTDOWN; RECOMMENDATIONS; RISK ASSESSMENT
- Descriptors DEC
- ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; MAINTENANCE; MATERIALS TESTING REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SHUTDOWN; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-94ID13223
- Funding organization
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- Secondary number(s)
- CONF-980616--