ML21081A034
| ML21081A034 | |
| Person / Time | |
|---|---|
| Site: | 99902049 |
| Issue date: | 03/25/2021 |
| From: | Michael Dudek NRC/NRR/DNRL/NRLB |
| To: | Morin T Holtec International SMR |
| Greg Cranston-NRR/DNRL 301-415-0546 | |
| References | |
| HI2201064R2, ML20356A018, ML21056A022, ML21064A037 | |
| Download: ML21081A034 (3) | |
Text
March 25, 2021 Ms. Tammy Morin Senior Engineering and Licensing Manager SMR, LLC. A Holtec International Company Holtec Center, 1001 U.S. Highway 1 North Jupiter, Florida 33477
SUBJECT:
ACCEPTANCE LETTER FOR THE REVIEW OF HOLTEC SMR LICENSING TOPICAL REPORT HI-2201064R2, ELIMINATION OF LARGE BREAK LOSS OF COOLANT ACCIDENT (LOCA) AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA, (DOCKET No. 99902049)
Dear Ms. Morin:
By letter dated December 21, 2020, SMR, LLC, submitted Licensing Topical Report (LTR)
HI2201064R1, Elimination of Large Break Loss of Coolant Accident (LOCA) and Establishment of LOCA Acceptance Criteria, (Agencywide Documents Access and Management System Accession No. ML20356A018), to the U.S. Nuclear Regulatory Commission (NRC) staff for review. SMR, LLC, submitted a revision to the LTR, HI-2201064R2 (ADAMS Accession No. ML21064A037) on March 5, 2021, to provide additional information and criteria needed to describe the methodology regarding the regulatory basis to eliminate the need to analyze a large break LOCA for the SMR-160 reactor coolant system.
The purpose of this letter is to inform you that the NRC staff has evaluated the submitted LTR on Elimination of Large Break Loss of Coolant Accident (LOCA) and Establishment of LOCA Acceptance Criteria, Revision 2, and determined that it provides sufficient technical information for the NRC staff to conduct a detailed technical review. Though NRC is accepting the topical report, it should be noted that additional information will be required from Holtec to present a sufficient basis regarding the structural integrity of: (1) the welded connection between the reactor pressure vessel (RPV) and the steam generator (SG); and (2) the SG riser weld points to the tubesheets to justify that a break in either location is noncredible and can be excluded from the design basis of the reactor. The first topic was discussed with you and your staff in a public meeting on February 17, 2021 (ML21056A022), and the second is a topic for future communications.
On March 11, 2021, SMR, LLC, was notified by telephone that the subject LTR was accepted for the NRC staffs review. Subsequently, on March 25, 2021 SMR, LLC, was notified by telephone of the preliminary review schedule and associated resources. The NRC staff expects to issue requests for additional information (RAIs) before May 22, 2021. If SMR, LLC, satisfactorily responds to all RAIs within 30 days of receipt and resolves all issues identified during the review process, the NRC staff expects to provide the advanced safety evaluation report with no open items to SMR, LLC, for proprietary material and fact check review on or before January 23, 2022. The staff will then coordinate with the Advisory Committee on Reactor Safeguards (ACRS) on available dates regarding their review of the LTR.
T. Morin Section 170.21, Schedule of fees for production and utilization facilities, review of standard referenced design approvals, special projects, inspections, and import and export licenses, of Title 10 of the Code of Federal Regulations requires that LTRs are subject to fees based on the full cost of the review. You did not request a fee waiver; therefore, the NRC staffs hours will be billed accordingly.
The NRC staff estimates that conducting a detailed safety review of this LTR will require approximately 2,600 staff-hours, including project management time. This estimate is based on RAIs with a 30-day SMR, LLC, response time, with the initiation of a RAI review timeline that starts upon draft RAI receipt by SMR, LLC. The estimate also assumes three meetings between the NRC staff and the SMR, LLC staff to discuss the LTR review, possible audit activities, and presentations to the ACRS. This estimate is based on the NRC staffs review for sufficiency and completeness. The level of effort could change once the NRC staff delves into matters of technical and/or policy merit during the detailed safety review of the LTR.
Similarly, the schedule could change if additional rounds of RAIs are needed, or if the ACRS declines or delays the review of the LTR.
If you have any questions please contact the Senior Project Manager, Gregory Cranston, at Gregory.Cranston@nrc.gov.
Sincerely, Michael I. Dudek, Branch Chief New Reactor Licensing Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No. 99902049 Michael I.
Dudek Digitally signed by Michael I. Dudek Date: 2021.03.25 12:24:42 -04'00'
SUBJECT:
ACCEPTANCE LETTER FOR THE REVIEW OF HOLTEC SMR LICENSING TOPICAL REPORT HI-2201064R2, ELIMINATION OF LARGE BREAK LOSS OF COOLANT ACCIDENT (LOCA) AND ESTABLISHMENT OF LOCA ACCEPTANCE CRITERIA, (DOCKET No. 99902049)
DATED: MARCH 25, 2021 DISTRIBUTION:
PUBLIC NRLB R/F MDudek, NRR ABradford, NRR ABuford, NRR RPatton, NRR MMitchell, NRR SRosenberg, NRR DWidrevitz, NRR BWittick, NRR SKrepel, NRR GCranston, NRR PChowdhury, NRR SGreen, NRR RidsNrrDnrl Resource RidsNrrDnrlNrlb Resource RidsOgcMailCenterResource RidsACRS_MailCTR Resource RidsOpaMailResource RidsNrrLACSmithResource ADAMS Accession No.: ML21081A034 NRR-106 OFFICE NRR/DNRL/NRLB: PM NRR/DNRL/NRLB: LA NRR/DNRL/NRLB: PM NAME GCranston SGreen GCranston DATE 03/22/2021 03/22/2021 03/24/2021 OFFICE NRR/DNRL/NRLB: BC NRR/DNRL: D NAME MDudek ABradford DATE 03/24/2021 03/25/2021 OFFICIAL RECORD ONLY