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Category:ACRS Background Information
MONTHYEARML19254A6502019-09-13013 September 2019
OEDO-19-00423 - Response to the Acrs'S August 2 2019 Letter on NuScale Ch 3, 6, 15 and 20 Rev 1
ML19204A0942019-08-0505 August 2019
OEDO-19-00326 - Response to the Acrs'S June 27 2019 Letter on NuScale Odi
2019-09-13
[Table view]
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
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
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
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
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
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
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
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 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
August 5, 2019 Dr. Peter Riccardella, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
CHAPTER 2, SITE CHARACTERISTICS AND SITE PARAMETERS, AND CHAPTER 17, QUALITY ASSURANCE AND RELIABILITY ASSURANCE, 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:
Thank you for your letter, dated June 27, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19171A350), providing the Advisory Committee on Reactor Safeguards (ACRS or Committee) views on the U.S. Nuclear Regulatory Commission (NRC) staffs process for reviewing the NuScale Power, LLC (NuScale), Open Design Items, which are also called unverified design assumptions. I appreciate the time and effort the ACRS has devoted to this important subject, as reflected in meetings held with the ACRS Subcommittee for NuScale on December 18, 2018, the ACRS Full Committee on February 6, 2019, and a follow-up informational meeting with the NRC staff on June 6, 2019.
In your letter of June 27, 2019, the ACRS recommended the following:
[T]he staffs review process prior to design certification should identify those unverified design assumptions that are important to the reasonable assurance finding. This will help ensure that required closure prior to operability of the affected structure, system or component is identified and included as part of the design certification licensing basis. It is important that this process is not limited to items covered by the quality assurance program.
The Staff agrees with this conclusion and appreciates the opportunity to have explored the matter of Open Design Items more fully with the Committee. While performing a design certification review, including the NuScale review, the staff identifies the key input parameters and specified performance capabilities associated with the applicants demonstration of compliance with the applicable regulatory requirements. The key parameters and performance capabilities that the staff relied upon to make its findings must be appropriately captured or tracked within the final design certification document or supporting controlled
P. Riccardella 2 documents and calculations. This applies equally to those regulatory requirements that are subject to a quality assurance program and those that are not. With respect to the NuScale review, the staff is confident that the key parameters and performance capabilities to be relied upon in the staffs findings are either already captured in the current revision of the design control application or are being tracked using an appropriate regulatory mechanism.
Sincerely,
/RA/ (Kevin Coyne for)
Frederick D. Brown, Director Office of New Reactors Docket No.52-048 cc: Chairman Svinicki Commissioner Baran Commissioner Caputo Commissioner Wright SECY EDO
Pkg: ML19191A018 Ltr: ML19204A094 *via e-mail NRO-002 OFFICE NRO/DLSE/LB1 QTE NRO/DLSE/LB1 NRO/DCIP/QVI NRO/DLSE/LB1
- PM : LA B: BC : BC NAME OTabatabai JDougherty* MMoore* KKavanagh* SLee (GCranston for)
DATE 07/24/2019 07/24/2019 07/24/2019 07/24/2019 07/24/2019 OFFICE NRO/DSRA: D NRR/DIRS: D NRO/DLSE: D OGC (NLO) NRO: D NAME KCoyne* CMiller RTaylor SVrahoretis* FBrown (Kevin Coyne for)
DATE 07/24/2019 07/26/2019 07/31/2019 07/24/2019 08/05/2019