System Analysis and Risk Assessment System (SARA), Version 4.0. Reference manual: Volume 1

Technical Report · Sat Feb 01 04:00:00 EST 1992

OSTI ID:10129320

Russell, K D; Sattison, M B; Skinner, N L; Stewart, H D; Wood, S T ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

This NUREG is the reference manual for the System Analysis and Risk Assessment (SARA) System Version 4.0, a microcomputer-based system used to analyze the safety issues of a family [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. The SARA data base contains PRA data for the dominant accident sequences of a family and descriptive information about the family including event trees, fault trees, and system model diagrams. The number of facility data bases that can be accessed is limited only by the amount of disk storage available. To simulate changes to family systems, SARA users change the failure rates of initiating and basic events and/or modify the structure of the cut sets that make up the event trees, fault trees, and systems. The user then evaluates the effects of these changes through the recalculation of the resultant accident sequence probabilities and importance measures. The results are displayed in tables and graphs.

• 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: 10129320
• Report Number(s): NUREG/CR--5303-Vol.1; EGG--2628-Vol.1; ON: TI92008808
• Country of Publication: United States
• Language: English

Related Subjects

054000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTER GRAPHICS
DATA BASE MANAGEMENT
FAILURE MODE ANALYSIS
FAILURES
FAULT TREE ANALYSIS
HEALTH AND SAFETY
MATHEMATICS AND COMPUTERS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
REACTOR SAFETY
RISK ASSESSMENT
S CODES
SENSITIVITY ANALYSIS
SYSTEMS ANALYSIS