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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024
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Area of Focus - Boron Redistribution
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Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter)
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Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter)
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LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1
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Letter to NuScale Requesting -A for TR-0716-50350
ML20150C5172020-05-29029 May 2020
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ML20150C8812020-05-29029 May 2020
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ML20141L8082020-05-20020 May 2020
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ML20141N0122020-05-20020 May 2020
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ML20141L7872020-05-20020 May 2020
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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
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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
April 17, 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 February 21, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19052A046), about the Advisory Committee on Reactor Safeguards (ACRS or Committee) review of Chapter 2, Site Characteristics and Site Parameters, and Chapter 17, Quality Assurance and Reliability Assurance, of the safety evaluation report (SER) with open items (OIs) associated with the NuScale Power, LLC (NuScale), design certification application (DCA). 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 December 18, 2018, and the ACRS Full Committee on February 6, 2019.
Your letter contained four conclusions and recommendations, as shown below with staff responses:
Conclusion and Recommendation 1:
We have not identified any major issues in Chapters 2 and 17 at this time. However, there are some items, as noted below, that need to be resolved.
Staff Response: The staff agrees with Conclusion and Recommendation 1.
Conclusion and Recommendation 2:
The NuScale methodology for calculating accident offsite /Q values for the exclusion area boundary and low population zone coupled with the accident source term methodology for the NuScale design needs to be completed and reviewed by the staff.
Staff Response: The staff agrees with Conclusion and Recommendation 2. The staff plans to complete its review of NuScales methodologies, as stated in ACRS conclusion and Recommendation 2, by the end of the Phase 4 review.
P. Riccardella Conclusion and Recommendation 3:
The staff has requested an exemption from the Commission from requiring an inspection, test, analysis, and acceptance criterion, or ITAAC for the NuScale design reliability assurance program and this remains an open item.
Staff Response: The staff agrees with Conclusion and Recommendation 3. The staff will complete its evaluation of the OI in Phase 4 of the DCA review in accordance with the Commissions direction on SECY-18-0093, Recommended Change to Verification of the Design Reliability Assurance Program, dated September 20, 2018 (ADAMS Accession No. ML181928471), as stated in your letter.
In addition to the above recommendation, on page 3 of your letter, related to the discussion on DCA Chapter 17, the ACRS discussed the exclusion of the chemical and volume control system (CVCS) from design reliability assurance program (D-RAP) and stated that the final list of structures, systems, and components (SSCs) included in the D-RAP will be confirmed after Chapter 19 is completed. The staff notes that the applicant followed an adequate process for determining the D-RAP SSCs. Specifically, the applicant adequately used probabilistic risk criteria to develop a candidate list of risk significant SSCs, the expert panel adequately considered the CVCS for inclusion in the D-RAP list, and the rationale for not including the CVCS in the D-RAP SSCs was appropriately documented. The process (DCA Chapter 17, Figure 17.4.1) identifies those changes that would cause the applicant to consider any updates to the D-RAP list.
Conclusion and Recommendation 4:
The applicants Open Design Items for structures, systems, and components covered by Chapter 17 requirements need to be identified for eventual closure.
Staff Response: NuScales quality assurance program is committed to NQA-1-2008, Quality Assurance Requirements for Nuclear Facility Applications, and NQA-1a-2009 (hereafter referred to as NQA-1). NQA-1 addresses the issue referred to in Conclusion and Recommendation 4. Specifically, NQA-1, Requirement 3, Design Control, Subsection 403(d), states that documentation of design analyses shall include assumptions and also indicate assumptions that must be verified as the design proceeds.
Therefore, the applicants commitment to NQA-1 further requires of Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to Title 10 of the Code of Federal Regulations Part 50, Domestic Licensing of Production and Utilization Facilities, already calls for applicants and certificate holders to identify open design items (assumptions that need verification as the design proceeds) in their design calculation packages.
The NRC performed two quality assurance implementation inspections at NuScale.
During these inspections, the NRC also verified the applicants implementation of its quality assurance program. The NRC staff reviewed NuScales design control process and the open design item process. The NRC staff did not identify any findings of significance during these inspections.
P. Riccardella After DCA certification, combined license applicants and holders are required to ensure that engineering assumptions are verified as part of the combined license applicants and holders quality assurance programs.
The staff appreciates your review of this 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 Burns Commissioner Caputo Commissioner Wright SECY
Pkg: ML19064A734 Ltr: ML19072A215 *via e-mail NRO-002 OFFICE NRO/DLSE/LB1: NRO/DLSE/LB1: QTE NRO/DLSE/LB1: NRO/DLSE/RG PM PM LA RB:BC NAME OTabatabai PChowdhury QTE* SGreen* MDudek*
DATE 03/13/2019 03/13/2019 03/18/2019 03/19/2019 03/13/2019 OFFICE NRO/DLSE/EXHB: NRO/DSRA/SPRA: NRO/DCIP/QVI NRO/DLSE/LB1: NRO/DSRA: D BC BC B: BC BC NAME JGiacinto (Acting) MHayes* KKavanagh* SLee JMonninger (OTabatabai for)
DATE 03/13/2019 03/14/2019 03/14/2019 03/22/2019 03/20/2019 OFFICE NRO/DCIP: D NRO/DLSE: D OGC (NLO) NRO: D NAME TMcGinty* RTaylor MSpencer* FBrown DATE 03/20/2019 03/21/2019 03/21/2019 04/17/2019