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| ==Dear Mr. Rad:== | | ==Dear Mr. Rad:== |
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| By letter dated January 10, 2017, NuScale Power, LLC (NuScale), submitted Topical Report (TR) TR-0516-49416, Non-Loss-of-Coolant-Accident Analysis Methodology, Revision 0, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17222A827) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. | | By {{letter dated|date=January 10, 2017|text=letter dated January 10, 2017}}, NuScale Power, LLC (NuScale), submitted Topical Report (TR) TR-0516-49416, Non-Loss-of-Coolant-Accident Analysis Methodology, Revision 0, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17222A827) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. |
| NuScale supplemented its submittal by letter dated March 7, 2017 (ADAMS Accession No. ML17066A463). By letters dated November 26, 2019, and May 27, 2020, NuScale submitted, TR-0516-49416, Revisions 2 and 3, (ADAMS Accession Nos. ML19331A516 and ML20148M391 respectively). The NRC staff has evaluated TR-0516-49416, Revision 3, 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). | | NuScale supplemented its submittal by {{letter dated|date=March 7, 2017|text=letter dated March 7, 2017}} (ADAMS Accession No. ML17066A463). By letters dated November 26, 2019, and May 27, 2020, NuScale submitted, TR-0516-49416, Revisions 2 and 3, (ADAMS Accession Nos. ML19331A516 and ML20148M391 respectively). The NRC staff has evaluated TR-0516-49416, Revision 3, 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. | | 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 | | CONTACT: Bruce M. Bavol, NRR/DNRL 301-415-6715 |
Latest revision as of 16:13, 9 December 2021
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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024 US600 DC and SDA 50.46 Exemption - Letter ML23180A1512023-06-29029 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 ML21084A1232021-04-0202 April 2021 Review Schedule for the NuScale Power, LLC, Topical Report Methodology for Establishing the Technical Basis for Plume Exposure Emergency Planning Zones, TR-0915-17772, Revision 2 (PROJ0769) ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 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 ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20171A7312020-06-19019 June 2020 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 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 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 ML20149M1192020-05-28028 May 2020 LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, 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 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3 ML20141L7872020-05-20020 May 2020 LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4 ML20128J3162020-05-18018 May 2020 OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20104A0792020-04-27027 April 2020 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 2024-03-28
[Table view] |
Text
June 22, 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-0516-49416, REVISION 3, NON-LOSS-OF-COOLANT ANALYSIS METHODOLOGY
Dear Mr. Rad:
By letter dated January 10, 2017, NuScale Power, LLC (NuScale), submitted Topical Report (TR) TR-0516-49416, Non-Loss-of-Coolant-Accident Analysis Methodology, Revision 0, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17222A827) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval.
NuScale supplemented its submittal by letter dated March 7, 2017 (ADAMS Accession No. ML17066A463). By letters dated November 26, 2019, and May 27, 2020, NuScale submitted, TR-0516-49416, Revisions 2 and 3, (ADAMS Accession Nos. ML19331A516 and ML20148M391 respectively). The NRC staff has evaluated TR-0516-49416, Revision 3, 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 Docket No.52-048
Enclosures:
- 1. TR-0516-49416 SER (Public)
- 2. TR-0516-49416 SER (Proprietary) cc: DC NuScale Power, LLC Listserv (w/o Enclosure 2)
Pkg: ML20181A429 Letter: ML20181A432 Enclosure No. 1: ML20181A431 PUBLIC Enclosure No. 2: ML20181A430 PROP *via email NRR-106 OFFICE DNRL/NRLB: PM DNRL/NRLB: LA DNRL/NRLB: BC DNRL: D NAME BBavol CSmith* MDudek* ABradford*
DATE 06/22/2020 06/22/2020 06/23/2020 06/22/2020