Core damage frequency observations and insights of LWRs based on the IPEs
- Sandia National Labs., Albuquerque, NM (United States)
- and others
Seventy-eight plants are expected to submit Individual Plant Examinations (IPEs) for severe accident vulnerabilities to the US Nuclear Regulatory Commission (NRC). The majority of the plants have elected to perform full Level 1 probabilistic risk assessments (PRAs) to meet the intent of the IPEs. Because of this, it is possible to compare the results from the IPE submittals to determine general observations and {open_quotes}lessons learned{close_quotes} from the IPEs. The IPE Insights Program is performing this evaluation, and preliminary results are presented in this paper. The core damage frequency and core damage sequences are identified and compared for pressurized water reactors and boiling water reactors. Examination of the results indicates that variations among plant results are due to a combination of actual plant design/operational features and analysis approaches. The findings are consistent with previous NRC studies, such as WASH-1400 and NUREG-1150.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab. (BNL), Upton, NY (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 90933
- Report Number(s):
- NUREG/CP-0140-Vol.1; ON: TI95011672; TRN: 95:005143-0017
- Resource Relation:
- Other Information: PBD: Apr 1995; Related Information: Is Part Of Twenty-second water safety information meeting: Proceedings: Volume 1: Plenary session; Advanced instrumentation and control hardware and software; Human factors research; IPE and PRA; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 391 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Severity of radionuclide releases: A comparative study of Mark-I containments
Summary of core damage frequency from internal initiators: Peach Bottom