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PSAM 16 Conference Paper Overview

Welcome to the PSAM 16 Conference paper and speaker overview page.

Lead Author: Matthew Humberstone Co-author(s): Keith Compton, Keith.Compton@nrc.gov Trey Hathaway, Alred.Hathaway@nrc.gov Kurt Vedros, Kurt.Vedros@inl.gov
The Impact of External Hazards and FLEX Credit in the Application of LMP for Operating Reactors
As part of the Nuclear Regulatory Commission’s (NRC’s) effort to provide resources to longer-term, forward looking research projects with potential regulatory benefits, a future focused research (FFR) project was established to study the implementation of the Licensing Modernization Project (LMP) methodology for the operating reactors. This research effort used the LMP methodology and applied the NRC’s Level 3 probabilistic risk assessment (PRA) model results to gain feasibility insights. The initial phase of this effort used results from a limited scope of the NRC’s level 3 PRA model to explore key risk-insights of the licensing basis for reactors licensed under Title 10 of the Code of Federal Regulations (10 CFR) Part 50. The next phase of this effort addressed in this paper uses the expanded results from the NRC’s level 3 PRA model that includes model enhancements. This paper compares the results derived from the level 1, level 2, and level 3 PRA models for internal events and internal floods with the results that include external events. Moreover, the paper uses this comparison to gain insights on the impact of modeling external hazards, identify implementation challenges, and explore the feasibility of using results that consider the impact of external hazards in the LMP framework. These PRA results are used in the context of the frequency consequence (F-C) curve to both gain experience with the overall LMP methodology’s risk-informed performance-based guidance and to identify key risk-insights on operating reactor technology. Furthermore, these insights provide an example of a “safety case” for operating plants which include discussions on the risk-important plant events, potential risk ranking of SSCs, and a risk-informed defense-in-depth evaluation of the plant. Insights may also support future studies to highlight portions of Part 50 that are the best candidates for further risk-informed considerations.

Paper MA29 Preview

Author and Presentation Info

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Lead Author Name: Matthew Humberstone (Matthew.Humberstone@nrc.gov)

Bio: Dr. Matthew Humberstone is a Senior Reliability and Risk Analyst in the Division of Risk Analysis at the United States Nuclear Regulatory Commission (USNRC). Dr. Humberstone works in the Performance and Reliability Branch in the Office of Nuclear Regulatory Research (RES) which uses risk assessments and insights to support a broad range of regulatory applications. Dr. Humberstone joined the US NRC’s Nuclear Safety Professional Development program in 2010 and has held several different positions supporting several high-priority projects while at the NRC. Dr. Humberstone received his bachelor’s degree in engineering physics from New Mexico State University, a master's degree in statistics from the University of Tennessee, and a master’s degree and Ph.D. in nuclear engineering from the University of Tennessee.

Country: United States of America
Company: US NRC
Job Title: Senior Reliability and Risk Analyst

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