Evaluation of severe accident risks: Quantification of major input parameters. Experts` determination of source term issues: Volume 2, Revision 1, Part 4

Technical Report · Mon Jun 01 00:00:00 EDT 1992

OSTI ID:10154955

Harper, F T; Breeding, R J; Brown, T D; Gregory, J J; Jow, H N; Payne, A C; Gorham, E D ^[1]; Amos, C N ^[2]; Helton, J ^[3]; Boyd, G ^[4]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Science Applications International Corp., Albuquerque, NM (United States)
3. Arizona State Univ., Tempe, AZ (United States)
4. Safety and Reliability Optimization Services, Inc., Knoxville, TN (United States)

In support of the Nuclear Regulatory Commission`s (NRC`s) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported in NUREG-1150, the Severe Accident Risk Reduction Program (SAARP) has completed a revised calculation of the risk to the general public from severe accidents at five nuclear power plants: Surry, Sequoyah, Zion, Peach Bottom and Grand Gulf. The emphasis in this risk analysis was not on determining a point estimate of risk, but to determine the distribution of risk, and to assess the uncertainties that account for the breadth of this distribution. Off-site risk initiation by events, both internal to the power station and external to the power station. Much of this important input to the logic models was generated by expert panels. This document presents the distributions and the rationale supporting the distributions for the questions posed to the Source Term Panel.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 10154955
• Report Number(s): NUREG/CR-4551-Vol.2-Rev.1-Pt.4; SAND-86-1309-Vol.2-Rev.1-Pt.4; ON: TI92016045
• Resource Relation: Other Information: PBD: Jun 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ZION-1 REACTOR
RISK ASSESSMENT
ZION-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
FISSION PRODUCT RELEASE
IODINE
DECONTAMINATION
SOURCE TERMS
CONCRETES
REACTOR SAFETY
REACTOR ACCIDENTS
FISSION PRODUCTS
AEROSOLS
CONTAINMENT
220900
210100
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED