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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023
LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3)
ML21102A3072021-04-15015 April 2021
OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor
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OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor
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OEDO-20-00285_NuScale Area of Focus - Boron Redistribution
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Area of Focus - Boron Redistribution
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LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
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LLC, Submittal of Environmental Report: Revision Status
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ML20181A4322020-06-22022 June 2020
Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
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Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20198M3922020-06-19019 June 2020
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LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use
ML20157A2232020-06-0303 June 2020
Letter to NuScale Requesting -A for TR-0716-50350
ML20150C5172020-05-29029 May 2020
LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0
ML20150E1772020-05-29029 May 2020
LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0
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
ML20149M1192020-05-28028 May 2020
LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33
ML20141L8082020-05-20020 May 2020
LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3
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
ML20141M7642020-05-20020 May 2020
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LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4
ML20141L8162020-05-20020 May 2020
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ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
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OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring
ML20133K0882020-05-12012 May 2020
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ML20133J9142020-05-11011 May 2020
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OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology
ML20099H0802020-04-0808 April 2020
LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0
ML20098G2372020-04-0707 April 2020
Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items
ML20097F1922020-04-0606 April 2020
Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0
ML20094H6742020-04-0303 April 2020
LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0
ML20092L8992020-04-0101 April 2020
LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4
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
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
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
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
ML20066G2802020-03-0303 March 2020
LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0
ML20066G2882020-02-28028 February 2020
LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0
2023-06-29
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February 27, 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-0716-50351, REVISION 1, NUSCALE APPLICABILITY OF AREVA METHOD FOR THE EVALUATION OF FUEL ASSEMBLY STRUCTURAL RESPONSE TO EXTERNALLY APPLIED FORCES
Dear Mr. Rad:
By letter dated September 30, 2016, NuScale Power, LLC (NuScale), submitted Topical Report (TR)-0716-50351, NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces, Revision 0, to the U.S. Nuclear Regulatory Commission (NRC). NuScale asked the NRC to review and approve the use of AREVAs methodology as described in ANP-10377P-A, PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations, Revision 0, dated April 30, 2018, for the NuScale design. By letter dated December 19, 2019, NuScale submitted Revision 1, TR-0716-50351, which incorporated changes from request for additional information responses.
The NRC staff has evaluated TR-0716-50351, 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 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.
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.
Prior to placing the public version of this document in the publicly available records component of NRCs Agencywide Documents and Access Management System (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 3.90, Public inspections, exemptions, requests for withholding.
If after a 10-day 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/
Anna H. Bradford, Director Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket No.52-048
Enclosures:
- 1. TR-0716-50351 SER (Public)
- 2. TR-0716-50351 SER (Proprietary) cc: DC NuScale Power, LLC Listserv (w/o Enclosure 2)
Pkg: ML20056C808 Letter: ML20056C907 Enclosure No. 1: ML20056C908 PUBLIC Enclosure No. 2: ML20056C867 PROP *via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NRLB: LA DNRL/NRLB: BC DNRL: D NAME BBavol CSmith* MDudek ABradford DATE 02/25/2020 12/23/2019 02/26/2020 02/27/2020