ML22040A180

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Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Thaggard M - Safety Marker Study
ML22040A180
Person / Time
Issue date: 03/08/2022
From: Mark Thaggard
Office of Nuclear Regulatory Research
To:
Office of Nuclear Reactor Regulation
References
Download: ML22040A180 (13)


Text

Perspective on Safety Improvements for Commercial Nuclear Power Plants Mark Thaggard, Director Division of Risk Analysis Office of Nuclear Regulatory Research, U.S. NRC

2 Overview

  • The NRC uses various means to monitor changes in reactor safety
  • Both quantitative and qualitative measures are used to assess safety
  • The NRCs assessment of safety focuses on public health and safety

3 RES Considerations in Looking at Different Measures of Performance

  • What timeframe should we consider?
  • 20 years (2000+)
  • 30 years (1990+)
  • Advancements make it difficult to compare performance measures over time
  • Measures of performance may need to be interpreted using engineering judgment

4 1988-2000 Plant Safety Improvements The period of interest impacts overall conclusions Many safety-significant actions/changes were made

5 1988-2000 Plant Safety Improvements Significant Events

2000-Present: Plant Safety Improvements 6

Improvements made during this period are not as significant as those in the 1990s Not all changes have been fully realized

7 RES Categories of Performance Measures Operational trends Plant risk due to internal events/internal floods Plant risk due to other hazards NRC studies, orders, models, etc.

Industry studies, standards, models, etc.

Other

Safety Measure Trends 8

51 measures Negative Trends Loss of offsite power (LOOP) recovery time Positive Trends Annual scrams NRC reactive inspections Accident sequence precursor (ASP) results Radiation exposure Performance indicators Internal events core damage frequency (CDF)

Reactor coolant pump (RCP) seal performance Loss of offsite power (LOOP) frequency 1

measure 8

measures

Remaining Safety-Related Measures 9

Apparent favorable trends Lower conditional probability that a radiological release would lead to prompt or latent health effects Improvements related to flooding and seismic hazard reevaluations Mitigating strategies improvements (FLEX)

Risk insights from the State-of-the-Art Reactor Consequence Analyses (SOARCA)

Generic Issues Program improvements B.5.b improvements Improvements in consensus standards and regulatory guidance Pressurized-water reactor steam generator performance improvements Improvements in PRA development tools 32 neither favorable or negative trend 9

Some Observations 10

  • Large reduction in average core damage frequency (CDF) (since the IPE results)
  • Limited to contributions from internal events
  • External event hazards can add significantly to plant risk, so it is important to include in discussion of safety trending
  • Reduction in performance issues
  • Risk below NRC safety goals
  • Both the uncertainties and external hazards need to be considered when looking at the safety goal impacts

Conclusions 11

  • Performance measures appear to show improvements in nuclear power plants Could be attributed to initiatives and rules addressing key safety issues (e.g., station blackout (SBO) rule, greater use of risk-informed decisionmaking)
  • Plant safety improvements implemented since the year 2000 have shown a gradual increase in safety, but to a smaller extent than during the previous 10 years
  • Not all safety measures moved in the same positive direction
  • External event impacts are important, and significant uncertainties still exist

Questions 12

13 Mehdi.Reisifard@nrc.gov Branch Chief, Division of Risk Analysis, RES Matthew.Humberstone@nrc.gov Senior Reliability and Risk Analyst Division of Risk Analysis, RES