Level III probabilistic risk assessment for N Reactor

Technical Report · Sun Apr 01 04:00:00 EDT 1990

OSTI ID:6491934

Camp, A L; Kunsman, D M; Miller, L A; Sprung, J L; Wheeler, T A; Wyss, G D ^[1]

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1. Sandia National Labs., Albuquerque, NM (USA)

A Level III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The objectives of the PRA are to assess the risks to the public and the Hanford site workers posed by the operation of N Reactor, to compare those risks to proposed DOE safety goals, and to identify changes to the plant that could reduce the risk. The scope of the PRA is comprehensive, excluding only sabotage and operation errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study of five commercial nuclear power plants. The structure of the probabilistic models allowed complex interactions and dependencies between systems to be explicitly considered. Latin Hypercube sampling techniques were used to develop uncertainty distributions for the risks associated with postulated core damage events initiated by fire, seismic, and internal events as well as the overall combined risk. The combined risk results show that N Reactor meets the primary DOE safety goals and compared favorably to the plants considered in the NUREG-1150 analysis. 36 figs., 81 tabs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA); Sandia National Labs., Albuquerque, NM (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC06-87RL10930; AC04-76DP00789
• OSTI ID: 6491934
• Report Number(s): WHC-MR-0045-Vol.1; SAND--89-2102-Vol.1; ON: DE91002589
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
CONTAINMENT
DATA COVARIANCES
DOSES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
ENVIRONMENTAL EFFECTS
FAILURE MODE ANALYSIS
FIRES
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
HEAT TRANSFER
HYDRAULICS
L CODES
LWGR TYPE REACTORS
M CODES
MECHANICS
N CODES
N-REACTOR
NATIONAL ORGANIZATIONS
OCCUPATIONAL EXPOSURE
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
RADIATION DOSES
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SOURCE TERMS
STANDARDS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
T CODES
US DOE
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS