Analysis of core damage frequency: Peach Bottom, Unit 2 external events
Creators
- 1. Sandia National Labs., Albuquerque, NM (USA)
- 2. EQE, Inc., San Francisco, CA (USA)
- 3. ERCE, Inc., Albuquerque, NM (USA)
Description
This report presents the analysis of external events (earthquakes, fires, floods, etc.) performed for the Peach Bottom Atomic Power Station as part of the USNRC-sponsored NUREG-1150 program. Both the internal and external events analyses make full use of recent insights and developments in risk assessment methods. In addition, the external event analyses make use of newly-developed simplified methods. As a first step, a screening analysis was performed which showed that all external events were negligible except for fires and seismic events. Subsequent detailed analysis of fires resulted in a total (mean) core damage frequency of 1.95E-5 per year. The seismic analysis resulted in a total (mean) core damage frequency of 7.66E-5 per year using hazard curves developed by Lawrence Livermore National Laboratory and 3.09E-6 per year using hazard curves developed by the Electric Power Research Institute. Uncertainty analyses were performed, and dominant components and sources of uncertainty were identified. 71 refs., 63 figs., 54 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI91006720; NTIS; INIS; GPO.
Files
Additional details
Additional titles
- Subtitle (English)
- Volume 4, Revision 1, Part 3
Publishing Information
- Imprint Pagination
- 452 p.
- Report number
- NUREG/CR--4550-Vol.4-Rev.1-Pt.3
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22034818
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAILURE MODE ANALYSIS; FIRES; FLOODS; FREQUENCY ANALYSIS; PEACH BOTTOM-2 REACTOR; PROJECTILES; REACTOR COMPONENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; SEISMIC EFFECTS; TORNADOES; WIND
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Secondary number(s)
- SAND--86-2084-Vol.4-Rev.1-Pt.3.