Development and use of a train-level probabilistic risk assessment

Technical Report · Thu Apr 01 04:00:00 EST 1993

OSTI ID:6539929

Smith, C L; Fowler, R D; Wolfram, L M ^[1]

---

1. 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: NRC; 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

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990300 -- Information Handling
BEAVER VALLEY-2 REACTOR
BWR TYPE REACTORS
DATA BASE MANAGEMENT
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAULT TREE ANALYSIS
MANAGEMENT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PEACH BOTTOM-2 REACTOR
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
RISK ASSESSMENT
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS