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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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Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application
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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
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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
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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
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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
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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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ML20141L7872020-05-20020 May 2020
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
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
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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 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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Text
July 24, 2019 Dr. Peter Riccardella, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
INTERIM LETTER - CHAPTER 3, SECTION 3.9.2, AND CHAPTERS 14, 19, AND 21 OF THE U.S. NUCLEAR REGULATORY COMMISSION STAFFS SAFETY EVALUATION REPORT WITH OPEN ITEMS RELATED TO THE DESIGN CERTIFICATION APPLICATION REVIEW OF THE NUSCALE POWER, LLC, SMALL MODULAR REACTOR
Dear Dr. Riccardella:
In your letter dated June 19, 2019, the Advisory Committee on Reactor Safeguards (ACRS or the Committee) reported on the Committees interim safety review of Chapter 3, Section 3.9.2, Dynamic Testing and Analysis of Systems, Structures and Components; Chapter 14, Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria; Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors; and Chapter 21, Multi-Module Design Considerations, of the U.S. Nuclear Regulatory Commission (NRC) staffs safety evaluation report (SER) with open items for the NuScale Power, LLC (NuScale), small modular reactor (Agencywide Documents Access and Management System Accession No. ML19170A381). I appreciate the time and effort the ACRS has devoted to these important subjects, as reflected in meetings held with the ACRS Subcommittee for NuScale on May 14-16, 2019, and the ACRS Full Committee on June 5, 2019.
Your letter contained three conclusions and recommendations, as shown below with staff responses:
Conclusion and Recommendation 1:
SIET Test Facility-3 (TF-3) comprehensive vibration tests are required to ensure that the steam generator design is not susceptible to flow-induced vibration. The completion of these tests should be identified as an item for Inspections, Tests, Analyses and Acceptance Criteria (ITAAC).
Staff Response: The NRC staff agrees that completion of the TF-3 tests provides additional demonstration that the steam generator design is not susceptible to flow induced vibration. As these tests will not be finished before the planned completion of the staffs review of the design certification application, the NRC staff will apply appropriate licensing tools (e.g., ITAAC and/or combined license action item).
Conclusion and Recommendation 2:
We have not identified any major issues at this time for Chapter 3, Section 3.9.2, and Chapters 14, 19, and 21.
P. Riccardella 2 Staff Response: The NRC staff agrees with Conclusion and Recommendation 2. The staff plans to close the remaining open items and submit an advanced SER for Committee review by the end of the staffs Phase 4 review.
Conclusion and Recommendation 3:
To help identify risk insights in this unique design, there are technical issues in the probabilistic risk assessment (PRA) that merit further consideration.
Staff Response: The NRC staff acknowledges the technical issues raised by the ACRS in its letter and notes that the scope of the staffs review of a design certification PRA is to ensure the applicant has adequately addressed the Commissions objectives regarding consideration of severe accidents and the use of PRA in the design of the facilities. These objectives are focused on identification and reduction of potential vulnerabilities, identification of risk-informed safety insights, comparison to the Commissions safety goals, and support for other programmatic objectives (e.g.,
regulatory treatment of non-safety systems and the reliability assurance program). The staff performed an extensive review of the NuScale DCA and audits of the supporting notebooks, including an assessment of sensitivity studies and uncertainty quantification, to verify that the PRA will support the intended uses of a design certification PRA once all open items are resolved. The staff utilized the agency commissioned enhanced safety focused review approach (ESFRA) and took into consideration the unique design features to limit its review to the information needed to make reasonable assurance findings that the Commissions objectives were met. The staff notes that a COL holder will be required by 10 CFR 50.71(h) to develop a Level 1 and a Level 2 PRA covering those initiating events and modes for which NRC-endorsed consensus standards on PRA exist one year prior to the scheduled date for initial loading of fuel. The staff will consider revisiting the technical issues raised by ACRS as it prepares its Phase 4 advanced SER with no open items.
The NRC staff appreciates your review of these parts of the SER and looks forward to future interactions with the Committee as part of its NuScale review activities.
Sincerely,
/RA/
Frederick D. Brown, Director Office of New Reactors Docket No.52-048 cc: Chairman Svinicki Commissioner Baran Commissioner Caputo Commissioner Wright SECY
Pkg: ML19179A225; Ltr: ML19183A409 *via e-mail NRO-002 OFFICE NRO/DLSE/LB1: NRO/DLSE/LB1: NRO/DLSE/LB1: NRO/DLSE/LB1: NRO/DLSE/LB1:
PM PM PM PM LA NAME CSantos PChowdhury* MVera RFranovich MMoore*
DATE 7 /15 /2019 7 / 2 /2019 7 / 15 /2019 7 / 15 /2019 7/03/2019 OFFICE QTE NRO/DESR/SPRA NRO/DESR/MEB NRO/DLSE/SRS NRR/DIRS/QVI
- BC : BC B: BC B: BC NAME QTE* MHayes* TLuphold* RKaras* KKavanagh*
DATE 7/ 8 /2019 7/ 1/2019 7 / 2 /2019 7/ 2/2019 7/ 2 /2019 OFFICE NRO/DLSE/RG NRO/DLSE/LB1: NRR/DIRS: D NRO/DESR: D NRO/DLSE: D RB: BC BC NAME MDudek* GCranston for SLee GBowman* for KCoyne* RTaylor CMiller DATE 7 /2 /2019 7 /15/2019 7 / 10 /2019 7 /12 /2019 7 /16 /2019 OFFICE NRO: D NAME FBrown DATE 7 /24 /2019