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:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6539929
- Report Number(s):
- NUREG/CR-5976; EGG-2694; ON: TI93013191
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
RISK ASSESSMENT
BEAVER VALLEY-2 REACTOR
DATA BASE MANAGEMENT
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
PEACH BOTTOM-2 REACTOR
REACTOR COMPONENTS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
MANAGEMENT
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990300 - Information Handling