ML21025A003

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Risk-Informed Process for Evaluations (RIPE) - NEI Public Meeting Presentation Slides
ML21025A003
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 01/26/2021
From: Anderson V, Mauer A
Nuclear Energy Institute
To:
Plant Licensing Branch IV
Lingam S, NRR/DORL/LPL4, 301-415-1564
Shared Package
ML20025A005 List:
References
EPID L-2019-LRO-0074
Download: ML21025A003 (11)


Text

©2021 Nuclear Energy Institute Andrew Mauer Technical Advisor Victoria Anderson Technical Advisor Public Meeting on Risk-Informed Process for Evaluations January 26, 2021

©2021 Nuclear Energy Institute 2 Industry appreciates the continued effort to focus NRC and licensee resources on the most safety significant issues RIPE and the VLSSIR process are viewed as examples of the NRC becoming a modern, risk-informed regulator We look forward to providing input over the course of this year to realize and maximize the use of these processes across the NRC Introduction

©2021 Nuclear Energy Institute 3 Development of streamlined licensing actions using a risk-informed approach is appropriate We appreciate the significant amount of effort that went into complete the initial phase of RIPE and for your consideration of stakeholder comments Industry will be issuing RIPE IDP guidance and completing a submittal template We also appreciate the NRCs acknowledgement and commitment to expanding the use of RIPE to allow use by licensees with TS-425 Insights Regarding RIPE Process

Comparison of PRA Acceptability by Program Internal Events PRA Internal Fire PRA External Hazards PRA RIPE Capability Category I (Screening)

Qualitative of N/A Qualitative of N/A TSTF-425 Capability Category II Qualitative/

Bounding Qualitative/

Bounding TSTF-505 Capability Category II Capability Category II Site specific (Qualitative/

Bounding or Capability Category II Increasing PRA Rigor

Concept For RIPE Using TS-425

Licensee risk informed application status TSTF-425 approved Submitted quantitative seismic risk evaluation 50.54(f) resolution 50.69 approved (no fire or seismic model used)

Can RIPE be used?

Yes What should be referenced in RIPE submittal?

TSTF-425 LAR and SE Quantitative seismic risk evaluation for 50.54(f) resolution Description of seismic and internal events findings not closed in a formal finding closure Example 1: Issue Involving Seismic Considerations

Licensee risk informed application status TSTF-425 approved NFPA 805 approved and implemented Can RIPE be used?

Yes What should be referenced in RIPE submittal?

TSTF-425 LAR and SE NFPA 805 LAR and SE Description of fire and internal events findings not closed in a formal finding closure Example 2: Issue Involving Fire Considerations

Licensee risk informed application status TSTF-425 approved NFPA 805 approved and implemented Can RIPE be used?

No Example 3: Issue Involving External Flood Considerations

PRA Technical Adequacy Documentation for RIPE Plant with TSTF-505 Plant with TSTF-425 PRA Scope used in IDP evaluation Describe for the specific submittal PRA Scope for Approved Applications Describe scope of PRA from TSTF-505 Application Describe scope of PRA from TSTF-425 Application Describe scope of PRA from other applications, if applicable PRA Technical Adequacy for Internal Events Reference TSTF-505 LAR and SE Reference TSTF-425 LAR and SE PRA Technical Adequacy for Other PRAs Reference TSTF-505 LAR and SE Reference TSTF-425 LAR and SE Reference LAR and SE from other applications, if applicable Status of Open Findings N/A Articulate any open peer review findings from relevant PRA models above

©2021 Nuclear Energy Institute 10 Complete revisions to RIPE to allow use of TS-425 under a streamlined review process Identify lead plant to use RIPE process Continued use of VLSSIR process, as appropriate Begin a dialogue on expansion of RIPE to issues not quantitatively evaluated in a PRA Next Steps

©2021 Nuclear Energy Institute 11 We appreciate the NRCs risk-informed approach to address issue of low safety significance which helps focus NRC and licensee resources on the most safety significant issues.

Conclusion