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| {{#Wiki_filter:April 15, 2021 Mr. Thomas A. Bergman Vice President, Regulatory Affairs NuScale Power, LLC 11333 Woodglen Dr., Suite 205 Rockville, MD 20852 | | {{#Wiki_filter:Mr. Thomas A. Bergman Vice President, Regulatory Affairs NuScale Power, LLC 11333 Woodglen Dr., Suite 205 Rockville, MD 20852 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==Dear Mr. Bergman:== | | ==Dear Mr. Bergman:== |
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| This letter is to acknowledge receipt of your letter, Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor, dated February 19, 2021, LO-0221-74035 (Agencywide Documents Access and Management System (ADAMS) | | This letter is to acknowledge receipt of your letter, Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor, dated February 19, 2021, LO-0221-74035 (Agencywide Documents Access and Management System (ADAMS) |
| Accession No. ML21050A431) to present your lessons-learned from the U.S. Nuclear Regulatory Commissions (NRCs) review of the NuScale Power, LLC (NuScale) design certification application of the NuScale small modular reactor. | | Accession No. ML21050A431) to present your lessons-learned from the U.S. Nuclear Regulatory Commissions (NRCs) review of the NuScale Power, LLC (NuScale) design certification application of the NuScale small modular reactor. |
| The NRC staff is currently conducting its own lessons-learned activity regarding the NuScale design certification review. During that activity, we will review and consider the five recommendations you summarized in the letter, as well as the bases provided for your recommendations. It is noted that several of your recommendations, such as establishing an appeals process and defining the term credible, may be applicable beyond the nuclear reactor safety program, and therefore require additional coordination and consideration. The staff may request to have a public meeting with NuScale in the future to discuss your recommendations. | | The NRC staff is currently conducting its own lessons-learned activity regarding the NuScale design certification review. During that activity, we will review and consider the five recommendations you summarized in the letter, as well as the bases provided for your recommendations. It is noted that several of your recommendations, such as establishing an appeals process and defining the term credible, may be applicable beyond the nuclear reactor safety program, and therefore require additional coordination and consideration. The staff may request to have a public meeting with NuScale in the future to discuss your recommendations. |
| If you have questions, please contact Gregory Cranston at (301) 415-0546, or by e-mail to Gregory.Cranston@nrc.gov. | | If you have questions, please contact Gregory Cranston at (301) 415-0546, or by e-mail to Gregory.Cranston@nrc.gov. |
| Sincerely, Signed by Taylor, Robert on 04/15/21 Robert Taylor, Deputy Office Director for New Reactors Office of Nuclear Reactor Regulation Docket No. 52-048 cc: DC NuScale Listserv | | Sincerely, Robert Taylor, Deputy Office Director for New Reactors Office of Nuclear Reactor Regulation Docket No. 52-048 cc: DC NuScale Listserv April 15, 2021 Signed by Taylor, Robert on 04/15/21 |
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| ML21075A346 (pkg) *via e-mail NRR-106 OFFICE PM:DNRL:NRLB: LA:DNRL:NRLB BC:DNRL:NRLB D:DNRL:NRR NAME GCranston* SGreen* MDudek* ABradford* | | ML21075A346 (pkg) |
| DATE 04/12/2021 04/12/2021 04/13/2021 04/15/2021 OFFICE DD:NRR NAME RTaylor DATE 04/15/2021}} | | *via e-mail NRR-106 OFFICE PM:DNRL:NRLB: |
| | LA:DNRL:NRLB BC:DNRL:NRLB D:DNRL:NRR NAME GCranston* |
| | SGreen* |
| | MDudek* |
| | ABradford* |
| | DATE 04/12/2021 04/12/2021 04/13/2021 04/15/2021 OFFICE DD:NRR NAME RTaylor DATE 04/15/2021}} |
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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
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
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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
ML20231A5982020-08-25025 August 2020
OEDO-20-00285_NuScale Area of Focus - Boron Redistribution
ML20210M8902020-07-29029 July 2020
Area of Focus - Boron Redistribution
ML20195A5872020-07-13013 July 2020
LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors
ML20195C7662020-07-13013 July 2020
LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application
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
ML20181A2702020-06-22022 June 2020
Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
ML20181A4322020-06-22022 June 2020
Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (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
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
ML20141L8162020-05-20020 May 2020
LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3
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
ML20141M1142020-05-20020 May 2020
LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3
ML20141L8042020-05-20020 May 2020
LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, 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
ML20112F4552020-05-0101 May 2020
LLC, Design Certification Application Phases 5 and 6 Review Status
ML20107F8492020-05-0101 May 2020
OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design
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 NuScales 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
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
[Table view] |
Text
Mr. Thomas A. Bergman Vice President, Regulatory Affairs NuScale Power, LLC 11333 Woodglen Dr., Suite 205 Rockville, MD 20852
SUBJECT:
LESSONS-LEARNED FROM THE DESIGN CERTIFICATION REVIEW OF THE NUSCALE POWER, LLC SMALL MODULAR REACTOR
Dear Mr. Bergman:
This letter is to acknowledge receipt of your letter, Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor, dated February 19, 2021, LO-0221-74035 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML21050A431) to present your lessons-learned from the U.S. Nuclear Regulatory Commissions (NRCs) review of the NuScale Power, LLC (NuScale) design certification application of the NuScale small modular reactor.
The NRC staff is currently conducting its own lessons-learned activity regarding the NuScale design certification review. During that activity, we will review and consider the five recommendations you summarized in the letter, as well as the bases provided for your recommendations. It is noted that several of your recommendations, such as establishing an appeals process and defining the term credible, may be applicable beyond the nuclear reactor safety program, and therefore require additional coordination and consideration. The staff may request to have a public meeting with NuScale in the future to discuss your recommendations.
If you have questions, please contact Gregory Cranston at (301) 415-0546, or by e-mail to Gregory.Cranston@nrc.gov.
Sincerely, Robert Taylor, Deputy Office Director for New Reactors Office of Nuclear Reactor Regulation Docket No.52-048 cc: DC NuScale Listserv April 15, 2021 Signed by Taylor, Robert on 04/15/21
ML21075A346 (pkg)
- via e-mail NRR-106 OFFICE PM:DNRL:NRLB:
LA:DNRL:NRLB BC:DNRL:NRLB D:DNRL:NRR NAME GCranston*
SGreen*
MDudek*
ABradford*
DATE 04/12/2021 04/12/2021 04/13/2021 04/15/2021 OFFICE DD:NRR NAME RTaylor DATE 04/15/2021