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Results of core damage frequency analysis for the reference plants

F.T. Harper, R.C. Bertucio, M. Drouin, A.M. Kolaczkowski, Timothy A. Wheeler

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Abstract

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine risk from a selected group of nuclear power plants. NUREG-1150 will provide a basis for comparison of NRC research to industry results and resolution of numerous severe accident issues. In support of NUREG-1150, Sandia National Laboratories has directed the production of NUREG/CR-4550. NUREG/CR-4550 includes Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants and a limited reanalysis of the Zion PRA. A brief summary of the current results of these five analyses will be presented in this paper. A paper describing and evaluating the methodology used to perform the four Level 1 PRAs will also be presented at this conference.

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What this paper is about

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine risk from a selected group of nuclear power plants. NUREG-1150 will provide a basis for comparison of NRC research to industry results and resolution of numerous severe accident issues. In support of NUREG-1150, Sandia National Laboratories has directed the production of NUREG/CR-4550. NUREG/CR-4550 includes Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants and a limited reanalysis of the Zion PRA. A brief summary of the current results of these five analyses will be presented in this paper. A paper describing and evaluating the methodology used to perform the four Level 1 PRAs will also be presented at this conference.

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Available abstract

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine risk from a selected group of nuclear power plants. NUREG-1150 will provide a basis for comparison of NRC research to industry results and resolution of numerous severe accident issues. In support of NUREG-1150, Sandia National Laboratories has directed the production of NUREG/CR-4550. NUREG/CR-4550 includes Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants and a limited reanalysis of the Zion PRA. A brief summary of the current results of these five analyses will be presented in this paper. A paper describing and evaluating the methodology used to perform the four Level 1 PRAs will also be presented at this conference.

Key concepts: Nuclear power, Engineering, Probabilistic risk assessment, Environmental science, Nuclear engineering, Forensic engineering, Waste management, Risk assessment

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