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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
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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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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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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
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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
ML20141L8162020-05-20020 May 2020
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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
ML20141M1142020-05-20020 May 2020
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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
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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
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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
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Text
June 19, 2019 Dr. Peter Riccardella, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
INTERIM LETTER: CHAPTER 4, REACTOR; CHAPTER 5, REACTOR COOLANT SYSTEM AND CONNECTING SYSTEMS; AND TECHNICAL REPORT, TEMPERATURE LIMITS METHODOLOGY, OF THE U.S. NUCLEAR REGULATORY COMMISSION STAFFS SAFETY EVALUATION REPORT WITH OPEN ITEMS RELATED TO THE CERTIFICATION OF THE NUSCALE POWER, LLC, SMALL MODULAR REACTOR
Dear Dr. Riccardella:
In your letter dated May 30, 2019, the Advisory Committee on Reactor Safeguards (ACRS or the Committee) reported on the Committees interim safety review of Chapter 4, Reactor; Chapter 5, Reactor Coolant System and Connecting Systems; and Technical Report, Temperature Limits Methodology, of the U.S. 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. ML19155A203). 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 April 17, 2019, and the ACRS Full Committee on May 2, 2019.
Your letter contained two conclusions and recommendations, as shown below with NRC staff responses:
Conclusion and Recommendation 1:
There are a number of Chapter 4 and Chapter 5 open items related to Chapter 15 accident analysis issues that must be reviewed and resolved in order to demonstrate acceptability of the NuScale reactor design in satisfying GDC 27, GDC 34, and GDC 35.
Staff Response: The NRC staff agrees with Conclusion and Recommendation 1. As the NRC staff continues to engage the applicant to resolve the remaining open items related to the subject chapters and Chapter 15 accident analysis issues with regard to satisfying General Design Criterion (GDC) 34, Residual Heat Removal, and GDC 35, Emergency Core Cooling, in Appendix A, General Design Criteria for Nuclear Power Plants, to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, the staff has a path forward to address all regulatory requirements and risk-significant items for the NuScale design.
The NRC staff continues to engage the applicant to resolve the remaining open items associated with the exemption to GDC 27, Combined Reactivity Control Systems
P. Riccardella 2 Capability, which involves the scenario in which all control rods fail to successfully insert. The staff will apply the criteria discussed in SECY-18-0099, NuScale Power Exemption Request from 10 CFR Part 50, Appendix A, General Design Criterion 27, Combined Reactivity Control Systems Capability, dated October 9, 2018, to bring this issue to closure.
Conclusion and Recommendation 2:
We have not identified any additional major issues at this time for Chapter 4 and Chapter 5.
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.
The NRC staff appreciates your review of these SERs 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
Package: ML19155A199 Letter: ML19161A020 via e-mail* EDO-002 OFFICE NRO:DLSE:LB1:PM NRO:DLSE:LB1:LA QTE NAME BBavol MMoore* JDougherty*
DATE 06/08/2019 06/05/2019 06/07/2019 OFFICE NRO:DLSE:LB1:BC NRO:DLSE:D NRO:D NAME SLee RTaylor FBrown DATE 06/10/2019 06/13/2019 06/19/2019