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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
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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
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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
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LLC, Submittal of Environmental Report: Revision Status
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LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020
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OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance
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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
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
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
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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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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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January 27, 2020 Mr. Matthew W. Sunseri, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
SAFETY EVALUATION OF THE NUSCALE POWER, LLC TOPICAL REPORT TR-0915-17565, REVISION 3, ACCIDENT SOURCE TERM METHODOLOGY, AND SOURCE TERM AREA OF FOCUS REVIEW FOR THE NUSCALE SMALL MODULAR REACTOR
Dear Mr. Sunseri:
Thank you for the letter, dated December 20, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19354A031), regarding the Advisory Committee on Reactor Safeguards (ACRS or the Committee) review of the U.S. Nuclear Regulatory Commission (NRC) staffs safety evaluation of the NuScale Power, LLC., (NuScale)
Topical Report (TR) TR-0915-17565, Revision 3, Accident Source Term Methodology, and source term area of focus review for the NuScale design certification application (DCA) as discussed in the letter dated September 25, 2019 (ML19269B682). I appreciate the time and effort that the ACRS has devoted to these important subjects, as reflected in the meetings held with the ACRS Subcommittee for NuScale on November 20, 2019, and the ACRS Full Committee between December 4 - 6, 2019.
The letter contained the following four conclusions and recommendations:
- 1. Given its unique design attributes, the NuScale DCA uses alternative source terms for both normal operation and accident conditions for siting, safety analysis, control room and technical support center habitability, and equipment qualification and survivability. This approach aligns with Commission guidance noting that design-specific source terms for light-water small modular reactors may not necessarily follow all guides that currently pertain to large light-water reactors (LWRs).
- 2. The exclusion area boundary (EAB) and low-population zone (LPZ) are anticipated to be close to a NuScale plant. The traditional dose model to calculate radiological consequences for LWRs is inaccurate at short distances from the reactor. Therefore, NuScale has modified an NRC computer code that is more accurate at these reduced distances to address dose evaluations at the EAB and LPZ. The staff has found this approach acceptable.
- 3. The overall approach to establish the source term for NuScale is acceptable with the conditions and limitations noted by the staff. The SER on the topical report methodology should be issued.
M. Sunseri 2
- 4. Important design differences in NuScale compared to a conventional pressurized-water reactor call into question the prescriptive application of the post-accident requirements for long-term hydrogen and oxygen monitoring. The risk tradeoff between unisolating the NuScale containment to enable long-term hydrogen and oxygen monitoring should be weighed against alternatives that may not require such monitoring.
We will continue to explore this issue in our NuScale review.
The NRC staff appreciates the ACRSs review and recommendation and will issue the safety evaluation report. Additionally, we understand your concerns related to the need and capability for long-term post-accident hydrogen and oxygen (combustible gas) monitoring. The NRC staff is scheduled to address these concerns at an ACRS meeting in March 2020.
Sincerely,
/RA/ Andrea Veil for Ho K. Nieh Office Director of New Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket No.: 52-048 cc: Chairman Svinicki Commissioner Baran Commissioner Caputo Commissioner Wright SECY
PKG: ML20006D944 LTR: ML20013G921 *via e-mail NRR-106 OFFICE DNRL/NRLB:PM DNRL/NRLB:LA DNRL/NRLB: BC NRR/DNRL: D NRR/DDNR NAME GTesfaye CSmith* MDudek ABradford HNieh (AVeil for)
DATE 01/14/2020 01/14/2020 01/15/2020 01/15/2020 01/27/2020