Risk-informed inservice inspection program

The Nuclear Regulatory Commission (NRC) has developed draft guidance for power reactor licenses on acceptable methods for using probabilistic risk assessment (PRA) information and insights in support of plant-specific applications to change the current licensing basis (CLB) for inservice inspection...

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Bibliographic Details
Published inNuclear engineering and design Vol. 195; no. 2; pp. 211 - 215
Main Authors Mayfield, Michael E, Jackson, Deborah A, Guttman, Jack, Cunningham, Mark
Format Journal Article Conference Proceeding
LanguageEnglish
Published Amsterdam Elsevier B.V 01.02.2000
Elsevier
Subjects
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Inspection
Installations for energy generation and conversion: thermal and electrical energy
Laws and legislation
Piping systems
Probability
Risk assessment
Nuclear safety
Nuclear power plant
Decision making
Inspection
Risk
Safety
In service inspection
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Summary:The Nuclear Regulatory Commission (NRC) has developed draft guidance for power reactor licenses on acceptable methods for using probabilistic risk assessment (PRA) information and insights in support of plant-specific applications to change the current licensing basis (CLB) for inservice inspection (ISI) of piping. This process is also known as risk-informed inservice inspection programs (RI-ISI). The risk-informed inservice inspection process for operating nuclear power plants provides an alternative method for selecting and categorizing piping components that are inspected for the purposes of meeting the requirements of ASME Section XI. A RI-ISI approach will incorporate probabilistic techniques to help define the scope, type and frequency of inservice inspection. The risk-informed process may support a decrease in the number of inspection and inspection intervals but will also identify areas where increased resources should be allocated to enhance safety. The approach discussed in this paper follows the method developed by NRC staff.
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ISSN:0029-5493
1872-759X
DOI:10.1016/S0029-5493(99)00250-2