Generic event trees and the treatment of dependencies and non-proceduralized actions in a low power and shutdown Probabilistic Risk Assessment
Creators
- 1. Science Applications International Corp., Albuquerque, NM (United States)
- 2. Sandia National Labs., Albuquerque, NM (United States)
- 3. Science and Engineering Associates, Inc., Albuquerque, NM (United States)
Description
Sandia National Laboratories was tasked by the US Nuclear Regulatory Commission to perform a Probabilistic Risk Assessment (PRA) of a boiling water reactor (BWR) during low power and shutdown (LP ampersand S) conditions. The plant chosen for the study was Grand Gulf Nuclear Station (GGNS), a BWR 6. In performing the analysis, it was found that in comparison with full-power PRAs, the low decay heat levels present during LP ampersand S conditions result in a relatively large number of ways by which cooling can be provided to the core. In addition, because of the less stringent requirements imposed on system configurations possible is large and the availability of plant systems is more difficult to specify. These aspects of the LP ampersand S environment led to the development and use of ''generic'' event trees in performing the analysis. The use of ''generic'' event trees, in turn, had a significant impact on the nature of the human reliability analysis (HRA) that was performed. This paper describes the development of the event trees for the LP ampersand S PRA and important aspects of the resulting HRA
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94003233; NTIS; US Govt. Printing Office Dep.Files
25034355.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- SAND--93-2218C
Conference
- Title
- 2. Probabilistic safety assessment and management conference (PSAM).
- Dates
- 20-24 Mar 1994.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25034355
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FAILURE MODE ANALYSIS; GRAND GULF-1 REACTOR; GRAND GULF-2 REACTOR; HEAT TRANSFER; HUMAN FACTORS; HYDRAULICS; REACTOR SAFETY; REACTOR SHUTDOWN; RELIABILITY; RISK ASSESSMENT
- Descriptors DEC
- BWR TYPE REACTORS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; REMOVAL; SAFETY; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-940312--42.