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| {{#Wiki_filter:Code of Federal Regulations | | {{#Wiki_filter:September 13, 2018 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330 |
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| /RA/}}
| | ==SUBJECT:== |
| | NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH OPEN ITEMS FOR CHAPTER 17, QUALITY ASSURANCE AND RELIABILITY ASSURANCE |
| | |
| | ==Dear Mr. Bergman:== |
| | |
| | The U.S. Nuclear Regulatory Commission (NRC) staff is preparing a safety evaluation (SE) with open items (OIs) for each chapter of the NuScale Power, LLC (NuScale) Design Certification Application submitted by NuScale via letter dated December 31, 2016. |
| | The NRC staffs SE with OIs for Chapter 17, Quality Assurance and Reliability Assurance, is being provided to the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee to support an upcoming meeting of the ACRS Subcommittee, scheduled to be held on December 19, 2018. |
| | The enclosed SE with OIs is being provided to NuScale for review of proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390, Public Inspections, Exemptions, Requests for Withholding. The NRC will withhold the enclosed SE from public disclosure for ten business days from the date of this letter to allow you the opportunity to identify any proprietary information or factual errors. If within that ten day period, you do not request that all or portions of the SE be withheld from public disclosure, the enclosure will be made available for public viewing through the Publicly Available Records component of NRCs Agencywide Documents Access and Management System and placed on the NRCs public webpage for this application. |
| | Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED. |
| | |
| | T. Bergman 2 If you have any questions or comments concerning this matter, I can be reached at (301) 415-6616 or via e-mail address at Omid.Tabatabai@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Omid Tabatabai, Senior Project Manager Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors Docket No. 52-048 |
| | |
| | ==Enclosure:== |
| | : 1. Safety Evaluation with OIs for Chapter 17, Quality Assurance and Reliability Assurance |
| | |
| | Pkg: ML18201A182 Letter: ML18201A186 SER: ML18171A205 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA* NRO/DLSE/LB1: BC NRO/DLSE/LB1: PM NAME OTabatabai MMoore SLee* OTabatabai DATE 9/13/2018 9/13/2018 9/13/2018 9/13/2018}} |
Latest revision as of 19:56, 20 October 2019
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Category:Letter
MONTHYEARML23234A1232024-03-28028 March 2024 US600 DC and SDA 50.46 Exemption - Letter ML23180A1512023-06-29029 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 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 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 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 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 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 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
[Table view] |
Text
September 13, 2018 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
NUSCALE POWER, LLC, DESIGN CERTIFICATION APPLICATION - SAFETY EVALUATION WITH OPEN ITEMS FOR CHAPTER 17, QUALITY ASSURANCE AND RELIABILITY ASSURANCE
Dear Mr. Bergman:
The U.S. Nuclear Regulatory Commission (NRC) staff is preparing a safety evaluation (SE) with open items (OIs) for each chapter of the NuScale Power, LLC (NuScale) Design Certification Application submitted by NuScale via letter dated December 31, 2016.
The NRC staffs SE with OIs for Chapter 17, Quality Assurance and Reliability Assurance, is being provided to the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee to support an upcoming meeting of the ACRS Subcommittee, scheduled to be held on December 19, 2018.
The enclosed SE with OIs is being provided to NuScale for review of proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390, Public Inspections, Exemptions, Requests for Withholding. The NRC will withhold the enclosed SE from public disclosure for ten business days from the date of this letter to allow you the opportunity to identify any proprietary information or factual errors. If within that ten day period, you do not request that all or portions of the SE be withheld from public disclosure, the enclosure will be made available for public viewing through the Publicly Available Records component of NRCs Agencywide Documents Access and Management System and placed on the NRCs public webpage for this application.
Document transmitted herewith contains sensitive unclassified information. When separated from the enclosure, this document is DECONTROLLED.
T. Bergman 2 If you have any questions or comments concerning this matter, I can be reached at (301) 415-6616 or via e-mail address at Omid.Tabatabai@nrc.gov.
Sincerely,
/RA/
Omid Tabatabai, Senior Project Manager Licensing Branch 1 Division of Licensing, Siting and Environmental Analysis Office of New Reactors Docket No.52-048
Enclosure:
- 1. Safety Evaluation with OIs for Chapter 17, Quality Assurance and Reliability Assurance
Pkg: ML18201A182 Letter: ML18201A186 SER: ML18171A205 *via email NRO-002 OFFICE NRO/DLSE/LB1: PM NRO/DLSE/LB1: LA* NRO/DLSE/LB1: BC NRO/DLSE/LB1: PM NAME OTabatabai MMoore SLee* OTabatabai DATE 9/13/2018 9/13/2018 9/13/2018 9/13/2018