ML22140A335

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Humberstonem-hv-w12
ML22140A335
Person / Time
Issue date: 03/08/2022
From: Matthew Humberstone
NRC/RES/DRA
To:
Office of Nuclear Reactor Regulation
References
Download: ML22140A335 (15)


Text

Matthew Humberstone, PhD US NRC Licensing Modernization Project for Operating Reactors

Project Overview

  • The Licensing Modernization Project (LMP) for operating reactors leverages the NRCs Level 3 probabilistic risk assessment (PRA) (L3PRA) model to test the feasibility of the LMP methodology for use beyond the original intent.
  • LMP methodology
  • Licensing approach for nonlight-water reactors
  • Uses L3PRA results
  • NRC L3PRA model
  • Pressurized-water reactors
  • Initially had only internal events results available
  • Has expanded to include external hazards and other enhancements

Future Focused Research Project Scope NRC Regulatory Needs Support Proposals Phase 2 Expanded Insights L3PRA Model Enhancements Phase 1 Feasibility Limited Scope

Objectives Study LMP Feasibility The LMP methodology is feasible for light-water reactors (LWRs)

Pilot LMP Used the L3PRA model results to pilot the LMP Identify Issues/Challenges Identified insights on implementation of the LMP Use L3PRA Results Used L3PRA results for Phase 1 and Phase 2 Glean LWR Risk Insights LWR safety profile consistent with NRC expectations Communication Shared progress/results

Technical Approach NRC L3PRA Model

- Severe Accident Research

- LWR Experience LMP Methodology

- Risk-Informed, Performance-Based

- Non-LWR licensing

L3PRA Process 6

Cutsets ~50,000 Plant Damage States (PDS): 368 Release Categories: 16 1

L3PRA

Release Category

Release Category Contributions

LMP Frequency-Consequence Curve

Phase 1 Results

Initial Phase 2 Insights Changes to the NRCs L3PRA model results vary External events FLEX credit, etc.

No impact Different impacts on release categories/accidents Loss-of-coolant accidents Loss of offsite power Station blackout 8

6 2

Phase 2 Results

Conclusions

  • LMP methodology is useful beyond the original intent
  • Insights gained to support future non-LWR licensing
  • Operating reactors safety profile is consistent with current NRC expectations
  • Several opportunities are being explored to leverage LMP methods and tools

Next Steps

  • Continue Phase 2 research Enhanced model results Accident sequence evaluations Uncertainty impacts
  • Engagement with NRC technical staff on future needs Supporting future regulatory work
  • Continue communication effort