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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 NuScales 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
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January 22, 2018 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 NE Circle Boulevard, Suite 200 Corvallis, OR 97330
SUBJECT:
REQUEST FOR SEISMIC DESIGN ISSUES CLOSURE PLAN FOR THE NUSCALE POWER, LLC During a public meeting on August 17, 2017, NuScale Power, LLC (NuScale) informed the U.S.
Nuclear Regulatory Commission (NRC) that it would need over 60 days to respond to several request for additional information (RAI) questions related to seismic design issues. Some of the RAIs responses are anticipated in late 2018 (Enclosure 1). In order to successfully complete Phase 2 for Sections 3.7.2 Seismic System Analysis, 3.8.4 Other Seismic Category I Structures, and 3.8.5 Foundations, the NRC staff requests that NuScale provide a closure plan for resolving the technical issues raised in these RAI questions. The plan should include the approach NuScale will take to respond to the RAI questions, as well as the actions to be performed for closing and completing each response. Also, the plan should include a schedule for submitting the final responses and identifying where markups of the FSAR will be provided.
The NRC staff will review NuScales closure plan to determine whether its strategy for planned RAI-responses would meet NRC requirements and support the proposed schedule.
If you have any questions, please contact Gregory Cranston at (301) 415-0546 or via e-mail at Gregory.Cranston@nrc.gov.
Respectfully,
/RA/
Frank Akstulewicz, Director Division of New Reactor Licensing Office of New Reactors U.S. Nuclear Regulatory Commission
ML17318A701 *via email NRO-002 OFFICE NRO/DNRL/LB1: PM NRO/DNRL/LB1: LA NRO/DEI/SEB: BC NRO/DNRL/LB1: BC NAME GCranston MMoore SSamaddar SLee:
DATE 12/18/2017 12/19/2017 12/19/2017 1/16/2018 OFFICE NRO/DEI: DD NRO/DNRL: D NAME RCaldwell FAkstulewicz DATE 1/17/2018 1/22/2018 U.S. NUCLEAR REGULATORY COMMISSION REQUEST FOR SEISMIC DESIGN ISSUES CLOSURE PLAN FOR THE NUSCALE POWER, LLC LIST OF REQUESTS FOR ADDITIONAL INFORMATION SCHEDULED TO BE RESPONDED TO IN 2018 current RAI RAI ID Question # Review Document Section response Accession #
schedule 1 8936 03.07.02-7 ML17217A004 03.07.02 - Seismic System Analysis 01/31/2018 2 8966 03.08.04-3 ML17216A847 03.08.04 - Other Seismic Category I Structures 01/31/2018 3 8967 03.08.04-4 ML17216A848 03.08.04 - Other Seismic Category I Structures 01/31/2018 4 8967 03.08.04-5 ML17216A848 03.08.04 - Other Seismic Category I Structures 01/31/2018 5 8967 03.08.04-6 ML17216A848 03.08.04 - Other Seismic Category I Structures 01/31/2018 6 8967 03.08.04-7 ML17216A848 03.08.04 - Other Seismic Category I Structures 01/31/2018 7 8970 03.08.04-10 ML17217A002 03.08.04 - Other Seismic Category I Structures 01/31/2018 8 8973 03.08.04-15 ML17217A008 03.08.04 - Other Seismic Category I Structures 02/23/2018 9 8973 03.08.04-16 ML17217A008 03.08.04 - Other Seismic Category I Structures 02/23/2018 10 8973 03.08.04-17 ML17217A008 03.08.04 - Other Seismic Category I Structures 02/23/2018 11 8932 03.07.02-4 ML17211A001 03.07.02 - Seismic System Analysis 04/30/2018 12 8971 03.08.04-14 ML17217A003 03.08.04 - Other Seismic Category I Structures 04/30/2018 13 8932 03.07.02-6 ML17211A001 03.07.02 - Seismic System Analysis 05/31/2018 14 8838 03.08.04-1 ML17146B358 03.08.04 - Other Seismic Category I Structures 06/29/2018 15 8935 03.07.02-23 ML17223A124 03.07.02 - Seismic System Analysis 08/30/2018 16 8964 03.08.05-2 ML17224A004 03.08.05 - Foundations 08/30/2018 17 8971 03.08.04-13 ML17217A003 03.08.04 - Other Seismic Category I Structures 08/30/2018 18 8933 03.07.02-16 ML17217A006 03.07.02 - Seismic System Analysis 10/31/2018 19 8932 03.07.02-5 ML17211A001 03.07.02 - Seismic System Analysis 11/29/2018 20 8935 03.07.02-26 ML17223A124 03.07.02 - Seismic System Analysis 11/29/2018 21 8933 03.07.02-17 ML17217A006 03.07.02 - Seismic System Analysis 12/20/2018 22 8935 03.07.02-25 ML17223A124 03.07.02 - Seismic System Analysis 12/20/2018 23 8963 03.08.05-6 ML17230A108 03.08.05 - Foundations 12/20/2018 24 8971 03.08.04-11 ML17217A003 03.08.04 - Other Seismic Category I Structures 12/20/2018 25 8974 03.08.04-20 ML17217A022 03.08.04 - Other Seismic Category I Structures 12/20/2018 Enclosure