Guidelines for reduced seismic loads to assess temporary conditions in nuclear power plants. Final report
- 1. Sargent and Lundy, Chicago, IL (United States)
Description
Utilities do not have uniform guidelines and criteria to treat plant temporary conditions (TCs) or planned changes to safety-related systems. Regulatory review and acceptance criteria and guidelines tend to be overly conservative, leading to costly measures. This report proposes a risk-informed procedure for evaluating TCs using reduced seismic loads and current licensing basis allowables that reduces plant operation and maintenance (O and M) costs, shortens plant outages, and reduces personnel radiation exposure. The project team applied principles in the Nuclear Regulatory Commission (NRC) risk-informed draft regulatory documents to develop reduced seismic loads based on an allowed increase in time-averaged core damage frequency in a refueling cycle. They determined reduction factors as a function of total usage time of the reduction factors within the duration of one refueling cycle. The methodology is capable of application to plants with and without a seismic probabilistic risk assessment (SPRA) model. Models in the guidelines use information available from the seismic IPEEE (Individual Plant Examination for External Events) program for safe shutdown paths. An Expert Task Force provided input to the development of the methodology and reviewed the final product
Availability note (English)
Available from EPRI Distribution Center, 207 Coggins Drive, PO Box 23205, Pleasant Hill, CA 94523 (United States)Additional details
Publishing Information
- Imprint Pagination
- [p. 175]
- Report number
- EPRI-TR--108904
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 30052215
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; ENGINEERED SAFETY SYSTEMS; MODIFICATIONS; PWR TYPE REACTORS; REACTOR FUELING; REACTOR MAINTENANCE; RECOMMENDATIONS; RISK ASSESSMENT; SEISMIC EFFECTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; MAINTENANCE; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Electric Power Research Inst., Palo Alto, CA (United States)