ML23243A010
| ML23243A010 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/2023 |
| From: | James Shea NRC/NRR/DNRL/NLIB |
| To: | Hayes M NRC/NRR/DNRL/NLIB |
| References | |
| Download: ML23243A010 (7) | |
Text
August 31 2023 MEMORANDUM TO: Michelle W. Hayes, Chief Licensing and Regulatory Infrastructure Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM: James J. Shea, Project Manager /RA/
Licensing and Regulatory Infrastructure Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF SECOND PUBLIC MEETING TO DISCUSS RISK INSIGHTS AND SEVERE ACCIDENT VULNERABILITY INFORMATION FOR LIGHT-WATER REACTOR CONSTRUCTION PERMIT APPLICATIONS On July 27, 2023, an observation public meeting was held by the staff of the U.S. Nuclear Regulatory Commission (NRC). The meeting addressed the scope of an application for a light-water reactor (LWR) construction permit (CP) under Title 10 of the Code of Federal Regulations (10 CFR) 50.34(a) and for approval of design features under § 50.35. The meeting was a follow-up to a previous public meeting held on March 30, 2023. The staff is seeking stakeholder input and feedback as it develops guidance on the level of detail on probabilistic risk assessment (PRA) and severe accident evaluation information to be provided in the preliminary safety analysis report.
The following topics were discussed during this meeting:
- The NRC staff update on the efforts to develop guidance on the content of PRA related information in a LWR construction permit application.
- Review of industry and public interest topics and proposed staff guidance from the first public meeting held on March 30, 2023 (Agencywide Documents Access Management System (ADAMS) Accession No. ML23104A314).
- Obtain additional industry or public feedback.
CONTACT: James Shea, NRR/DNRL 301-415-1366
M. Hayes 2 The NRC issued the public meeting notice on July 18, 2023, and posted it on the NRC public website (ML23199A236). Prior to the meeting, the NRC staff submitted presentation slides for the meeting (ML23206A006).
Enclosed are the meeting agenda (Enclosure 1), list of attendees of the meeting (Enclosure 2),
and the meeting summary (Enclosure 3).
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Meeting Summary
Pkg: ML23243A008 Memo: ML23243A010 Slides: ML23206A006 *via email NRR-106 OFFICE NRR/DNRL/NLIB: NRR/DRA/PRA-C: NRR/DNRL/NLIB: NRR/DNRL/NLIB:
PM BC LA PM NAME JShea* SVasavada* SGreen* JShea DATE 08/16/2023 08/23/2023 08/31/2023 08/31/2023 U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE JULY 27, 2023 SECOND OBSERVATION PUBLIC MEETING TO DISCUSS RISK INSIGHTS AND SEVERE ACCIDENT VULNERABILITY INFORMATION FOR LIGHT-WATER REACTOR CONSTRUCTION PERMIT APPLICATIONS Meeting Agenda Time Topic Speaker 01:00 pm - 02:00 pm NRC Introduction and NRC NRC Presentation 02:00 pm - 02:30 pm Public Questions Public/NRC Enclosure 1
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE JULY 27, 2023 SECOND OBSERVATION PUBLIC MEETING TO DISCUSS RISK INSIGHTS AND SEVERE ACCIDENT VULNERABILITY INFORMATION FOR LIGHT-WATER REACTOR CONSTRUCTION PERMIT APPLICATIONS List of Attendees Name Organization Name Organization Jim Shea NRC Alex Huning Holtec Anders Gilbertson NRC Jodine Vehec Holtec Martin Stutzke NRC Raymond Schiele TVA Malcolm Patterson NRC Scott Owen TVA Stacey Rosenberg NRC James Thornton TVA Hanh Phan NRC Dennis Petrarca TVA Keith Tetter NRC Stephen Kimura TVA Jan Mazza NRC Greg Cranston NRC Shilp Vasavada NRC Jana Bergman External Cristopher Tyree NRC Stephen P. OHearn External Candace de Messieres NRC Andrew Brennon External Steven Alferink NRC Leigh Lloveras Breakthrough Institute Alissa Neuhausen NRC Joelle Starefos External De Wu NRC Vodine Vehec External Sunwoo Park NRC Edwin Lyman External Ian Jung NRC Clark Shurtlef External Steven Lynch NRC Greg Oberson NRC Bernie Thomson NRC Carolyn Lauron NRC Enclosure 2
U.S. NUCLEAR REGULATORY COMMISSION
SUMMARY
OF THE SECOND OBSERVATION PUBLIC MEETING TO DISCUSS RISK INSIGHTS AND SEVERE ACCIDENT VULNERABILITY INFORMATION FOR LIGHT-WATER REACTOR CONSTRUCTION PERMIT APPLICATIONS Meeting Summary Over the next few years, the U.S Nuclear Regulatory Commission (NRC) anticipates the submission of construction permit applications for light-water reactors (LWR) under Title 10 of the Code of Federal Regulations part 50, Domestic Licensing of Production and Utilization Facilities. The staff summarized the two-step licensing process under this part. Based on preliminary design information for a power reactor, documented in an applicants preliminary safety analysis report (PSAR), the staff issues a construction permit (CP). When construction is essentially finished, more complete design information is documented in a final safety analysis report (FSAR). On the basis of the FSAR, the staff issues an operating license (OL). The FSAR submitted with the OL application should describe the final design of the facility as constructed and must identify any changes from the criteria, design, and bases provided in the PSAR.
Before issuing an OL, the NRC staff will review the applicants final design to determine whether all the Commissions safety requirements have been met. The most recent guidance on how to conduct the review of such applications is found in interim staff guidance: DNRL-ISG-2022-01, Safety Review of Light-Water Power Reactor Construction Permit Applications, issued in October 2022 (Agencywide Documents Access Management System Accession No. ML22189A099 (ADAMS)).
The staffs initiative and subsequent public engagement stemmed from the need for guidance identified by external stakeholders who are considering the two-step licensing process under 10 CFR Part 50 to determine the level of detail on risk insights and severe accident information needed for the developed of an acceptable CP application. The staff is currently developing guidance and engaging public stakeholders starting with the March 30, 2023, initial public meeting (ML23104A314) and then with the second public meeting held July 27, 2023.
Subsequent public meetings will be held, as needed, to identify an acceptable minimum level of detail and scope of a PRA needed to support a LWR CP application.
The staffs guidance would focus on LWRs, including small modular reactors. The staff emphasized that the guidance development includes collaboration with similar efforts for non-LWRs. The staff also emphasized that risk insights at the CP stage of 10 CFR Part 50 does not imply achieving a probabilistic risk assessment (PRA) that is technically acceptable when measured against endorsed PRA standards that would be required at the OL stage.
During the meeting, the staff provided an update on the progress of the guidance development including providing information as to the minimum level of detail and scope of PRA and severe accident information in the CP application and addressed the comments and questions raised from the March 30, 2023, meeting. Throughout the meeting, NRC staff and attendees engaged in dialogue where the staff provided clarifications on the anticipated scope and level of detail for risk insights and severe accident vulnerability information that would be expected in a CP application.
Enclosure 3
Some of the main topics of discussion included the following:
- 3. Systematic evaluation of all hazards on a site-specific basis.
- 4. The configuration control programs at the CP stage.
- 5. Topics currently being discussed by the staff to determine the corresponding minimum information needs in a CP application:
- Regulatory Treatment of Non-Safety Systems
- Internal Fire and Flood Non-PRA Risk Assessment
- Low Power and Shutdown Non-PRA Risk Assessment and PRA
- Severe Accident Analysis The meeting concluded with a discussion of the staffs next steps including holding any additional future public meetings if requested by external stakeholders. The staff also encouraged design-specific pre-application engagements on this topic.
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