Evaluation of severe accident risks: Quantification of major input parameters

Technical Report · Sun Mar 01 00:00:00 EST 1992

OSTI ID:5759468

Breeding, R J; Harper, F T; Brown, T D; Gregory, J J; Payne, A C; Gorham, E D ^[1]; Murfin, W ^[2]; Amos, C N ^[3]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)
3. Science Applications International Corp., Albuquerque, NM (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 so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover 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 were assessed. Much of the 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 Structural Response Panel.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5759468
• Report Number(s): NUREG/CR-4551-Vol.2-Rev.1-Pt.3; SAND-86-1309-Vol.2-Rev.1-Pt.3; ON: TI92010407
• Country of Publication: United States
• Language: English

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