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10 CFR 50.69. 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NESCC November 3, 2014. Stephen Dinsmore Senior Reliability and Risk Analyst Division of Risk Assessment Office of Nuclear Reactor Regulation - PowerPoint PPT Presentation
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10 CFR 50.69
Stephen Dinsmore
Senior Reliability and Risk Analyst
Division of Risk Assessment
Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
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50.69 Risk-Informed Categorization and Treatment of Structures, Systems and
Components for Nuclear Power Reactors
NESCCNovember 3, 2014
10 CFR 50.69 Overview
• Voluntary alternative rule• Determine safety significance of SSCs after defining the
population of safety-related components• Modify special treatment requirements on SSCs based
on their safety significance• Treatment of low-safety-significance SSCs being
addressed in draft new inspection manual procedure 37060
• Vogtle Submitted Pilot Application August 31, 2012• NRR SER in final review phase
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10 CFR 50.69Four-Box Categorization
10 CFR 50.69Categorization Process
• Minimum of a Level 1, internal events PRA – External events and Shutdown using PRA or using conservative
evaluations– Non-PRA functions and defense-in-depth addressed with questions that
Integrated Decision-making Panel answers
• Active component significance based on – Risk increase caused if component failed (Risk Achievement Worth) and – Nominal contribution to current risk (Fussel-Vessly)– Quantitative sensitivity studies for key uncertainties
• Passive component pressure retaining (rupture) significance based on consequences of failure
• Performance monitoring linked to unreliability increases• Change-in-risk primarily verifies categorization and subsequent
monitoring guideline values
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