ML22028A023
| ML22028A023 | |
| Person / Time | |
|---|---|
| Site: | 99902049 |
| Issue date: | 02/10/2022 |
| From: | Gregory Cranston NRC/NRR/DNRL/NRLB |
| To: | Michael Dudek NRC/NRR/DNRL/NRLB |
| Cranston G | |
| Shared Package | |
| ML22028A027 | List: |
| References | |
| Download: ML22028A023 (6) | |
Text
February 10, 2022 MEMORANDUM TO:
Michael I. Dudek, Chief New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM:
Gregory V. Cranston, Project Manager /RA/
New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE NOVEMBER 23, 2021, PUBLIC MEETING TO DISCUSS THE HOLTEC SMALL MODULAR REACTOR, SMR-160, TOPICAL REPORT: ELIMINATION OF LARGE BREAK LOCA AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA On November 23, 2021, an Observation Public Meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and SMR, LLC, a Holtec International Company (Holtec),
regarding the NRC staffs request for additional information regarding licensing topical report (LTR), Elimination of Large Break Loss-of-Coolant Accident (LOCA) and Establishment of LOCA Acceptance Criteria, Revision 2 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML21068A255). The meeting summary is provided in. The public meeting notice can be found in ADAMS under Accession No.
ML21314A137 and was also posted on the NRCs public Web site.
This meeting discussed items related to the audit of the LTR and is a follow-up to previous public meetings on June 16, 2021 (ADAMS Accession No. ML21180A465) and July 13, 2021 (ADAMS Accession No. ML21180A466), to continue discussions on a path forward for the LTR review. Enclosed are the meeting agenda (Enclosure 1), list of attendees (Enclosure 2), and the meeting summary (Enclosure 3).
Docket No. 99902049
Enclosures:
- 1. Meeting Agenda
- 2. List of Attendees
- 3. Meeting Summary CONTACT: Gregory Cranston, NRR/DNRL 301-415-0546
PKG: ML22028A027 LTR: ML22028A024 MEETING NOTICE: ML22028A023
- via e-concurrence NRR-106 OFFICE NRR/DNLR/NRLB: PM NRR/DNRL/NRLB: LA NRR/DNRL/NRLB: BC NAME GCranston*
SGreen MDudek*
DATE 01/27/22 02/02/22 02/03/22 OFFICE NRR/DNLR/NVIB: BC NRR/DNRL/NPHP:(a) BC NRR/DSS/SNRB: BC NAME ABuford*
SCumblidge*
RPatton* w/edits from ABarrett DATE 02/04/22 02/07/22 02/09/22 OFFICE NRR/DEX/EMIB:(a) BC NRR/DNRL/NRLB: BC NRR/DNLR/NRLB: PM NAME ITseng* w/edits MDudek*
GCranston*
DATE 02/07/22 02/10/22 02/10/22
SUMMARY
OF THE NOVEMBER 23, 2021, PUBLIC MEETING TO DISCUSS THE HOLTEC SMALL MODULAR REACTOR, SMR-160, TOPICAL REPORT:
ELIMINATION OF LARGE BREAK LOCA AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA November 23, 2021 Meeting Agenda Time Topic Organization 1:00 p.m. - 1:10 p.m.
Introductions and Opening Remarks NRC and Holtec 1:10 p.m. - 2:30 p.m. SMR-160 Licensing Topical Report Discussion - Open Session NRC and Holtec 2:30 p.m.
Adjourn
SUMMARY
OF THE NOVEMBER 23, 2021, PUBLIC MEETING TO DISCUSS THE HOLTEC SMALL MODULAR REACTOR, SMR-160, TOPICAL REPORT:
ELIMINATION OF LARGE BREAK LOCA AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA November 23, 2021 List of Participants Name Affiliation David Lewis Holtec Hickey, Kevin Holtec Lietwiler, Clay Holtec Marcille, Thomas Holtec McCloskey, Sean Holtec Morin, Tammy Holtec Rajkumar, Joseph Holtec Trotta, Rick Holtec Vehec, Jodine Holtec Daigle, David Public Ring, Mark Numark Assoc Seewald, Tom Public Brown, Christopher NRC Buford, Angie NRC Cranston, Greg NRC Dudek, Michael NRC Halnon, Gregory NRC Honcharik, John NRC Li, Yueh-Li NRC Manoly, Kamal NRC Mitchell, Matthew NRC Moyer, Carol NRC Nolan, Ryan NRC Patton, Rebecca NRC Scarbrough, Thomas NRC Tsao, John NRC Tseng, Ian NRC Barrett, Antonio NRC
2
SUMMARY
OF THE NOVEMBER 23, 2021, PUBLIC MEETING TO DISCUSS THE HOLTEC SMALL MODULAR REACTOR, SMR-160, TOPICAL REPORT: ELIMINATION OF LARGE BREAK LOCA AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA November 23, 2021 Meeting Summary On November 23, 2021, an Observation Public Meeting was held between the U.S.
Nuclear Regulatory Commission (NRC) staff and SMR, LLC, a Holtec International Company (Holtec), regarding the NRC staffs request for additional information regarding licensing topical report (LTR) Elimination of Large Break Loss-of-Coolant Accident (LOCA) and Establishment of LOCA Acceptance Criteria, Revision 2 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML21068A255).
The public meeting notice can be found in ADAMS under Accession No. ML21314A137 and was also posted on the NRCs public Web site.
The public meeting commenced with opening remarks and an introduction of participants. There were members of the public attending but there were no public comments.
The meeting discussed items related to the audit of the LTR and is a follow-up to previous public meetings conducted on June 16, 2021 (ADAMS Accession No. ML21180A465) and July 13, 2021 (ADAMS Accession No. ML21202A235), to continue discussing a path forward for the LTR review.
The NRC staff continued to emphasize that the LTR should provide criteria that, if met after the design is finalized, would allow the NRC staff to make a determination that there is reasonable assurance of adequate protection, and identify that an exemption from 10 CFR 50.46 is needed.
Holtec expressed concern that putting additional criteria in the LTR could bind a future applicant to meeting criteria that the applicant may not want. Holtec stated that criteria and how the criteria will be met would be determined later by Holtec or by a future applicant.
The NRC staff stated that the reactor system staffs analytical questions have focused on obtaining an understanding of the capability of the preliminary design to mitigate consequences for various break sizes, as well as defense-in-depth considerations.
The staff stated that information is needed regarding the secondary side of the steam generator in conjunction with a potential primary to secondary reactor coolant leak.
The staff also stated that it would be difficult at this time to agree that the Holtec design is just like a typical reactor pressure vessel. The Holtec design is unique in shape and configuration and there is no operating experience associated with such a configuration. The staff continued to seek clarity during the meeting as to what is different with that Holtec SMR-160 design that could potentially affect what the potential likelihood of failures may be and what would be the extent of that failure (break size).
2 As such, the staff stated that there may need to be a set of limitations and conditions to cover the key aspects of the Holtec design and associated welds, such as limitations and conditions on inspectability, welding, fatigue, and water chemistry. The NRC staff stated that Holtec should decide what would be the appropriate set of potential criteria that, if met once the design is finalized, would provide sufficient information for the NRC to make its safety finding. If the Holtec specified design criteria are not sufficient to allow NRC to make its safety finding, then the staff stated that they would consider the viability of providing limitations and conditions to be incorporated into the LTR to supplement existing criteria. The criteria to be met must be sufficiently comprehensive, such that if the criteria are later determined to be met, there is reasonable assurance that the plant will operate safely with no undue risk to the public health and safety.
Although the audit and discussions during this meeting repeated and confirmed that additional information is necessary in the LTR, Holtec reiterated they would be reluctant to provide any additional information and requested that the NRC staff proceed with developing limitations and conditions instead.
Regarding next steps, the NRC staff stated that it would be continuing with the audit.
Additionally, the NRC staff would consider the viability of working on developing a set of potential limitations and conditions that could be discussed with Holtec to provide better insight on what should be added to the LTR to facilitate completing the review of the LTR and preparing an SER. The possible development of the limitations and conditions will be coordinated between the NRC reactor systems, mechanical engineering, and materials groups; and will be discussed with NRC management before being presented to Holtec.
Discussions between the NRC staff and Holtec regarding the next steps are ongoing.
The meeting was adjourned.