SARA (System Analysis and Risk Assessment): An NRC risk management tool

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:5253646

Sattison, M B; Robinson, R C

The System Analysis and Risk Assessment (SARA) system is being developed at the Idaho National Engineering Laboratory under the direction and guidance of the Office of Nuclear Regulatory Research. The objective of this project is to provide a personal computer (PC)-based, user-friendly system for the computation and analysis of information on nuclear power plant risk characteristics. The latest released version of SARA (Version 2.0) contains the probabilistic risk assessment (PRA) results from four of the five plants included in the NUREG-1150 study. These plants are: Surry;Peach Bottom;Sequoyah;and Grand Gulf.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5253646
• Report Number(s): EGG-M-22487; CONF-8710111-44; ON: DE88006755
• Resource Relation: Conference: 15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
PWR TYPE REACTORS
S CODES
DATA BASE MANAGEMENT
DECISION MAKING
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
MANAGEMENT
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
PERSONAL COMPUTERS
PROBABILITY
REACTOR ACCIDENTS
RELIABILITY
SENSITIVITY ANALYSIS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
US NRC
ZION-1 REACTOR
ZION-2 REACTOR
ACCIDENTS
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled