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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
US600 DC and SDA 50.46 Exemption - Letter
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Area of Focus - Boron Redistribution
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Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
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Letter to NuScale Requesting -A for TR-0716-50350
ML20150C5172020-05-29029 May 2020
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ML20150E1772020-05-29029 May 2020
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ML20150C8812020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0
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ML20141L8082020-05-20020 May 2020
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ML20141N0122020-05-20020 May 2020
LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report
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ML20141L7872020-05-20020 May 2020
LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4
ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
ML20141L8042020-05-20020 May 2020
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ML20099H0802020-04-0808 April 2020
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ML20072M6682020-03-30030 March 2020
Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content
ML20072H3332020-03-0909 March 2020
LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0
ML20057D9002020-03-0606 March 2020
Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant
ML20062F7262020-03-0505 March 2020
Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public
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
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0
ML20069A1572020-03-0404 March 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0
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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Text
June 3, 2020 Mr. Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC.
1100 Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
FINAL SAFETY EVALUATION FOR NUSCALE POWER, LLC TOPICAL REPORT TR-0716-50350, REVISION 1, ROD EJECTION ACCIDENT METHODOLOGY
Dear Mr. Rad:
By letter dated December 30, 2016, NuScale Power, LLC (NuScale), submitted Topical Report (TR) TR-0716-50350, Rod Ejection Accident Methodology, Revision 0, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16365A242) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval.
By letter dated November 15, 2019, NuScale submitted, TR-0716-50350-P, Revision 1, (ADAMS Accession No. ML19319C685). The NRC staff has evaluated TR-0716-50350, Revision 1, and found that it is acceptable for referencing 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 NRC staff requests that NuScale publish the applicable version(s) of the SER listed above within 30 days 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.
CONTACT: Bruce M. Bavol, NRR/DNRL 301-415-6715
Z. Rad If the NRC staffs criteria or regulations change, and its acceptability conclusion in the SER 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.
After receiving the package with the -A version, 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/
Anna H. Bradford, Director Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Bob Caldwell for Docket No.52-048
Enclosures:
- 1.
TR-0716-50350 SER (Public)
- 2.
TR-0716-50350 SER (Proprietary) cc: DC NuScale Power, LLC Listserv (w/o Enclosure 2)
Pkg: ML20157A220 Letter: ML20157A223 Enclosure No. 1: ML20157A221 PUBLIC Enclosure No. 2: ML20157A222 PROP
- via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NRLB: LA DNRL/NRLB: BC DNRL: D NAME BBavol CSmith*
MDudek*
RCaldwell for ABradford*
DATE 06/02/2020 06/02/2020 06/02/2020 06/03/2020