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1986•Transactions of the American Nuclear SocietyRequires access

Smart approach to Level 1 probabilistic risk assessment

F.T. Harper, A.L. Camp

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Abstract

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine the current perception of risk from a selected group of nuclear power plants. NUREG-1150 will provide the base 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 Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants. Due to severe time and resource constraints, it was necessary to produce an efficient or ''smart'' approach to carry out these analyses. The purpose of this paper is to describe and evaluate the methodology selected.

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What this paper is about

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine the current perception of risk from a selected group of nuclear power plants. NUREG-1150 will provide the base 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 Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants. Due to severe time and resource constraints, it was necessary to produce an efficient or ''smart'' approach to carry out these analyses. The purpose of this paper is to describe and evaluate the methodology selected.

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Available abstract

The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine the current perception of risk from a selected group of nuclear power plants. NUREG-1150 will provide the base 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 Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants. Due to severe time and resource constraints, it was necessary to produce an efficient or ''smart'' approach to carry out these analyses. The purpose of this paper is to describe and evaluate the methodology selected.

Key concepts: Nuclear power, Probabilistic risk assessment, Probabilistic logic, Engineering, Risk assessment, Resource (disambiguation), Risk analysis (engineering), Forensic engineering

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