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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
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ML20072M6682020-03-30030 March 2020
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ML20069A9632020-03-0404 March 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0
ML20069A1772020-03-0404 March 2020
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ML20069A1572020-03-0404 March 2020
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ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
2024-03-28
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OFFICIAL USE ONLY PROPRIETARY INFORMATION September 13, 2018 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
FINAL SAFETY EVALUATION FOR NUSCALE POWER, LLC TOPICAL REPORT-0616-48793, REVISION 1, NUCLEAR ANALYSIS CODES AND METHODS QUALIFICATION
Dear Mr. Bergman:
By letter dated August 30, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16243A517), as supplemented by letter dated July 6, 2017 (ADAMS Accession No. ML17187B240), NuScale Power, LLC (NuScale), requested that the U.S. Nuclear Regulatory Commission (NRC) review and approve Topical Report (TR) TR-0616-48793, Nuclear Analysis Codes and Methods Qualification. This TR describes the NuScale methodology for the design and steady-state analysis of the NuScale reactor core. This methodology includes the use of the Studsvik Scandpower, Inc., Core Management Software, Version 5 Suite.
By letter dated March 7, 2017, NuScale provided supplemental information in support of the NuScale TR (ADAMS Accession No. ML17066A463). The NRC staff considered the information provided by Studsvik to support the review of TR-0616-48793.
By letter dated July 30, 2018 (ADAMS Accession No. ML18211A429) NuScale submitted Revision 1, TR-0616-48793, Nuclear Analysis Codes and Methods Qualification, which incorporates all changes made to the TR during NRC staffs review.
The NRC staff has found that the TR-0616-48793, Nuclear Analysis Codes and Methods Qualification, is acceptable for referencing in licensing applications for the NuScale small modular reactor design to the extent specified and under the conditions and limitations delineated in the enclosed safety evaluation report (SER). The SER defines the basis for acceptance of the TR.
Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.
CONTACT: Bruce M. Bavol, NRO/DLSE 301-415-6715 OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION 2
The NRC staff requests that NuScale publish the applicable version(s) of the SER listed above within three months of receipt of this letter. The accepted version of the TR shall incorporate this letter and the enclosed SER and add -A (designated accepted) following the report identification number.
If the NRC staffs criteria or regulations change, so that its conclusion that the SER is acceptable is invalidated, NuScale and/or the applicant referencing the SER will be expected to revise and resubmit its respective documentation, or submit justification for continued applicability of the SER without revision of the respective documentation.
Prior to placing the public version of this document in the publicly available records component of NRCs ADAMS, the NRC staff requests that NuScale perform a final review of the SER for proprietary or security related information not previously identified. If you believe that any additional information meets the criteria, please identify such information line by line and define the basis pursuant to the criteria established in Title 10 of the Code of Federal Regulations, Part 2, Section 390, Public inspections, exemptions, requests for withholding.
If after a 10day period, you do not request that all or portions of the SER be withheld from public disclosure, the SER will be made available for public inspection through the publicly available records component of NRCs ADAMS.
If you have any questions or comments concerning this matter, please contact Bruce Bavol at 301-415-6715 or via e-mail address at Bruce.Bavol@nrc.gov.
Sincerely,
/RA/
Robert Taylor, Director Division of Licensing, Siting, and Environmental Analysis Office of New Reactors Docket No.52-048
Enclosures:
- 1. TR-0616-48793 SER (Non-Proprietary)
- 2. TR-0616-48793 SER (Proprietary) cc: DC NuScale Power, LLC Listserv (w/o Enclosure 2)
OFFICIAL USE ONLY PROPRIETARY INFORMATION
Pkg: ML18234A292 Letter: ML18234A294 Enclosure No. 1: ML18234A295 Enclosure No. 2: ML18234A293 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA NRO/DSRA/SRSB: BC NRO/DLSE/LB1: BC NAME BBavol MMoore BKaras SLee DATE 8/22/2018 8/20/2018 9/12/2018 9/13/2018