Development and use of a train-level probabilistic risk assessment
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
The Idaho National Engineering Laboratory examined the potential for the development of train-level probabilistic risk assessment (PRA) databases. These train-level databases will allow the Nuclear Regulatory Commission to investigate effects on plant core damage frequency (CDF) given a train is failed or taken out of service. The intent of this task was to develop user-friendly databases that required a minimalamount of personnel involvement to be usable. It was originally intended that the train-level models would not be expanded to include basic events below the top gate of a train, with the possible exception of including some of the major train-related components (e.g., important pumps and motor-operated valves). It was found that a database similar to the original plant PRA provided the accuracy needed to measure the changes in plant CDF. The Peach Bottom Unit 2 NUREG-1150 PRA (a large fault tree model) and the Beaver Valley Unit 2 IPE (a large event tree model) were selected to demonstrate the feasibility of developing train-level databases. Five different methods for developing train-level databases were hypothesized and are examined. Ultimately, two train-level databases were developed using the Peach Bottom Unit 2 PRA and onetrain-level database was developed using the Beaver Valley Unit 2 IPE. The development, use, limitations, and results of these train-level databases are discussed.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10149692
- Report Number(s):
- NUREG/CR--5976; EGG--2694; ON: TI93013191
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200
220900
99 GENERAL AND MISCELLANEOUS
990300
BEAVER VALLEY-2 REACTOR
COMPONENTS AND ACCESSORIES
DATA BASE MANAGEMENT
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
INFORMATION HANDLING
NUCLEAR POWER PLANTS
PEACH BOTTOM-2 REACTOR
REACTOR COMPONENTS
REACTOR SAFETY
RISK ASSESSMENT