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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 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
[Table view] Category:Report
MONTHYEARML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20141M7642020-05-20020 May 2020 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, 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 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20066F4672020-02-28028 February 2020 Enclosure 1: ACRS Subcommittee Presentation: NuScale FSAR Topic- Resolution of Chapter 15 Phase 2 Open Items, PM-0220-69062, Revision 0 ML19353A7192019-12-19019 December 2019 LLC, Submittal of NuFuel-HTP2 Fuel and Control Rod Assembly Designs, TR-0816-51127, Revision 3 ML19338E9482019-12-0404 December 2019 LLC Submittal of Human-System Interface Style Guide, ES-0304-1381, Revision 4 ML19331A9102019-11-27027 November 2019 LLC Submittal of Human Factors Engineering Design Implementation Implementation Plan, RP-0914-8544, Revision 4 ML19330F3872019-11-26026 November 2019 LLC Submittal of Containment Response Analysis Methodology, Technical Report, TR-0516-49084, Revision 2 ML19302H5982019-10-29029 October 2019 LLC - Submittal of Mitigation Strategies for Loss of All AC Power Event, TR-0816-50797, Revision 3 ML19252A1642019-09-0909 September 2019 LLC Submittal of Human Factors Engineering Design Implementation Implementation Plan, RP-0914-8544, Revision 3 ML19218A1472019-08-0505 August 2019 LLC - Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 1 ML19214A2482019-08-0202 August 2019 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-0918-60894, Revision 1 ML19212A7732019-07-31031 July 2019 LLC Submittal of Human Factors Engineering Verification and Validation Results Summary Report, RP-1018-61289, Revision 1 ML19212A6822019-07-31031 July 2019 LLC Submittal of Pipe Rupture Hazards Analysis Technical Report, TR-0818-61384, Revision 2 ML19212A7762019-07-31031 July 2019 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-0716-50439, Revision 2 ML19212A0842019-07-30030 July 2019 LLC Submittal of Mitigation Strategies for Extended Loss of AC Power Event, TR-0816-50797, Revision 2 ML19211D4112019-07-30030 July 2019 LLC Submittal of NuScale Power Module Short-Term Transient Analysis, TR-1016-51669, Revision 1 ML19210E5942019-07-29029 July 2019 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 2 ML19183A4882019-07-0202 July 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 4.3, Nuclear Design ML19183A4852019-07-0202 July 2019 LLC - Submittal of Fluence Calculation Methodology and Results, TR-0116-20781, Revision 1 ML19165A2942019-06-14014 June 2019 LLC Submittal of Loss of Large Areas Due to Explosions and Fires Assessment, TR-0816-50796, Revision 1 ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19158A3822019-06-0707 June 2019 LLC - Submittal of Containment Vessel Ultimate Pressure Integrity, TR-0917-56119, Revision 1 ML19151A8532019-05-31031 May 2019 LLC Submittal of Mitigation Strategies for Extended Loss of AC Power Event, TR-0816-50797, Revision 1 ML19151A8102019-05-31031 May 2019 LLC Submittal of Technical Report NuScale Generic Technical Guidelines, TR-1117-57216, Revision 1 ML19149A2982019-05-28028 May 2019 LLC Submittal of NuScale Containment Leakage Integrity Assurance, TR-1116-51962, Revision 1 ML19137A3612019-05-17017 May 2019 LLC - Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 2 ML19136A4112019-05-16016 May 2019 LLC - Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 2 ML19123A0962019-05-0101 May 2019 LLC - Submittal of Presentation Materials Entitled ACRS Presentation: NuScale Chapters 4 and 5 Full Committee, PM-0519-65402, Revision 0 ML19196A3062019-04-30030 April 2019 Non-Proprietary - Independent Melcor Confirmatory Analysis for NuScale Small Modular Reactor ML19119A3782019-04-29029 April 2019 LLC Submittal of Human Factors Engineering Design Implementation Plan, RP-0914-8544, Revision 2 ML19119A3982019-04-29029 April 2019 LLC - Submittal of Human-System Interface Design Results Summary Report, RP-0316-17619, Revision 2 ML19119A3422019-04-29029 April 2019 LLC Submittal of Human Factors Engineering Program Management Plan, RP-0914-8534, Revision 5 ML19119A3932019-04-29029 April 2019 LLC - Submittal of Human Factors Engineering Task Analysis Results Summary Report, RP-0316-17616 Revision 2. (Non-Proprietary Version) ML19112A1722019-04-21021 April 2019 LLC Submittal of Accident Source Term Methodology, TR-0915-17565, Revision 3 ML19093B8502019-04-0303 April 2019 LLC - Submittal of Technical Report TR-0916-51502, NuScale Power Module Seismic Analysis, Revision 2 ML19091A2322019-03-28028 March 2019 LLC - Submittal of Combustible Gas Control, TR-0716-50424, Revision 1 ML19088A2102019-03-28028 March 2019 Review of Nuscale'S Design Certification Application with Respect to Mitigation of Beyond-Design-Basis Events Final Rule ML19077A3312019-03-18018 March 2019 LLC - Submittal of Human Factors Engineering Verification and Validation Results Summary Report, RP-1018-61289, Revision 0. (Non-Proprietary) ML19052A0492019-02-15015 February 2019 LLC - Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 0 ML19045A4932019-02-14014 February 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 3.7.1, Seismic Design Parameters ML19050A3982019-02-13013 February 2019 Enclosure 1: ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 0 ML19036A9692019-02-0505 February 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program and Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria ML19030B8622019-01-30030 January 2019 LLC Submittal of Changes to Final Safety Analysis Report,Sections 2.0, Site Characteristics and Site Parameters, Section 2.5.4, Geology, Seismology, and Geotechnical Engineering, and Section 3.8.5, Design of Category I Structures 2021-02-19
[Table view] Category:Technical
MONTHYEARML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 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 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 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20066F4672020-02-28028 February 2020 Enclosure 1: ACRS Subcommittee Presentation: NuScale FSAR Topic- Resolution of Chapter 15 Phase 2 Open Items, PM-0220-69062, Revision 0 ML19353A7192019-12-19019 December 2019 LLC, Submittal of NuFuel-HTP2 Fuel and Control Rod Assembly Designs, TR-0816-51127, Revision 3 ML19338E9482019-12-0404 December 2019 LLC Submittal of Human-System Interface Style Guide, ES-0304-1381, Revision 4 ML19331A9102019-11-27027 November 2019 LLC Submittal of Human Factors Engineering Design Implementation Implementation Plan, RP-0914-8544, Revision 4 ML19330F3872019-11-26026 November 2019 LLC Submittal of Containment Response Analysis Methodology, Technical Report, TR-0516-49084, Revision 2 ML19252A1642019-09-0909 September 2019 LLC Submittal of Human Factors Engineering Design Implementation Implementation Plan, RP-0914-8544, Revision 3 ML19218A1472019-08-0505 August 2019 LLC - Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 1 ML19214A2482019-08-0202 August 2019 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-0918-60894, Revision 1 ML19212A7732019-07-31031 July 2019 LLC Submittal of Human Factors Engineering Verification and Validation Results Summary Report, RP-1018-61289, Revision 1 ML19212A7762019-07-31031 July 2019 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Analysis Technical Report, TR-0716-50439, Revision 2 ML19212A6822019-07-31031 July 2019 LLC Submittal of Pipe Rupture Hazards Analysis Technical Report, TR-0818-61384, Revision 2 ML19212A0842019-07-30030 July 2019 LLC Submittal of Mitigation Strategies for Extended Loss of AC Power Event, TR-0816-50797, Revision 2 ML19211D4112019-07-30030 July 2019 LLC Submittal of NuScale Power Module Short-Term Transient Analysis, TR-1016-51669, Revision 1 ML19210E5942019-07-29029 July 2019 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 2 ML19183A4852019-07-0202 July 2019 LLC - Submittal of Fluence Calculation Methodology and Results, TR-0116-20781, Revision 1 ML19183A4882019-07-0202 July 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 4.3, Nuclear Design ML19165A2942019-06-14014 June 2019 LLC Submittal of Loss of Large Areas Due to Explosions and Fires Assessment, TR-0816-50796, Revision 1 ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19158A3822019-06-0707 June 2019 LLC - Submittal of Containment Vessel Ultimate Pressure Integrity, TR-0917-56119, Revision 1 ML19151A8532019-05-31031 May 2019 LLC Submittal of Mitigation Strategies for Extended Loss of AC Power Event, TR-0816-50797, Revision 1 ML19151A8102019-05-31031 May 2019 LLC Submittal of Technical Report NuScale Generic Technical Guidelines, TR-1117-57216, Revision 1 ML19149A2982019-05-28028 May 2019 LLC Submittal of NuScale Containment Leakage Integrity Assurance, TR-1116-51962, Revision 1 ML19137A3612019-05-17017 May 2019 LLC - Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 2 ML19136A4112019-05-16016 May 2019 LLC - Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 2 ML19123A0962019-05-0101 May 2019 LLC - Submittal of Presentation Materials Entitled ACRS Presentation: NuScale Chapters 4 and 5 Full Committee, PM-0519-65402, Revision 0 ML19196A3062019-04-30030 April 2019 Non-Proprietary - Independent Melcor Confirmatory Analysis for NuScale Small Modular Reactor ML19119A3932019-04-29029 April 2019 LLC - Submittal of Human Factors Engineering Task Analysis Results Summary Report, RP-0316-17616 Revision 2. (Non-Proprietary Version) ML19119A3422019-04-29029 April 2019 LLC Submittal of Human Factors Engineering Program Management Plan, RP-0914-8534, Revision 5 ML19119A3782019-04-29029 April 2019 LLC Submittal of Human Factors Engineering Design Implementation Plan, RP-0914-8544, Revision 2 ML19119A3982019-04-29029 April 2019 LLC - Submittal of Human-System Interface Design Results Summary Report, RP-0316-17619, Revision 2 ML19112A1722019-04-21021 April 2019 LLC Submittal of Accident Source Term Methodology, TR-0915-17565, Revision 3 ML19093B8502019-04-0303 April 2019 LLC - Submittal of Technical Report TR-0916-51502, NuScale Power Module Seismic Analysis, Revision 2 ML19091A2322019-03-28028 March 2019 LLC - Submittal of Combustible Gas Control, TR-0716-50424, Revision 1 ML19077A3312019-03-18018 March 2019 LLC - Submittal of Human Factors Engineering Verification and Validation Results Summary Report, RP-1018-61289, Revision 0. (Non-Proprietary) ML19052A0492019-02-15015 February 2019 LLC - Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 0 ML19045A4932019-02-14014 February 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 3.7.1, Seismic Design Parameters ML19050A3982019-02-13013 February 2019 Enclosure 1: ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 0 ML19036A9692019-02-0505 February 2019 LLC Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program and Section 14.3, Certified Design Material and Inspections, Test, Analyses, and Acceptance Criteria ML19030B8622019-01-30030 January 2019 LLC Submittal of Changes to Final Safety Analysis Report,Sections 2.0, Site Characteristics and Site Parameters, Section 2.5.4, Geology, Seismology, and Geotechnical Engineering, and Section 3.8.5, Design of Category I Structures ML18320A1892018-11-16016 November 2018 Nuscale Power, LLC Submittal of Changes to Final Safety Analysis Report, Tier 1 Section 2.5, Module Protection System and Safety Display and Indication System, Tier 2 Sections 14.2, Initial Plant Test Program, and 14.3, Certified Design ... ML18317A3642018-11-13013 November 2018 Nuscale Power, LLC - Submittal of Effluent Release (Gale Replacement) Methodology and Results, TR-1116-52065, Revision 1 ML18305A9642018-10-31031 October 2018 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 1 2020-07-13
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LO-1018-62155 October 17, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Submittal of Supplemental Response to Design Specification Audit Issue No. 92-99
REFERENCE:
NuScale Power, LLC Submittal of Response to Design Specification Audit Issue No. 92-99, LO-0818-61395, dated September 06, 2018 This supplemental response to Design Specification Audit Issue No. 92-99 supersedes the referenced response in its entirety. It reflects follow-on comments provided in a public telecon with NRC reviewers on September 25, 2018.
During an August 8, 2018 public Design Specification Audit Phase 2 teleconference with NRC Project Manager Marieliz Vera and NRC audit reviewer Jim Strnisha, NuScale Power, LLC (NuScale) discussed a proposed response to Audit Issue No. 92-99. Audit Issue No. 92-99 addresses compliance with Appendix QR-B in ASME QME-1-2007 with exceptions to ASME QME-1 2007, Appendix QR-B for the valve design specifications. As a result of this discussion, NuScale agreed to formally submit its detailed response to Issue 92-99 for further NRC review, identifying the alternatives to ASME QME-1 2007, Appendix QR-B and the basis for their suitability.
The Enclosures to this letter provide the response to the Design Specification Audit Issue No. 92-99, addressing alternatives and basis for each of the following.
- 1. Identification of activation energy
- 2. Determination and recording of shelf life for nonmetallics
- 3. Qualification Report that documents the tests performed on the nonmetallic parts, and
- 4. Shelf life preservation requirements This response includes FSAR pages incorporating revisions to Table 1.9-2, Section 3.11, and Appendix 3C in redline/strikeout format. NuScale will include these changes as part of a future revision to the NuScale Design Certification Application.
This letter makes no regulatory commitments or revisions to any existing regulatory commitments.
If you have any questions, please feel free to contact Marty Bryan at 541.452.7172 or at mbryan@nuscalepower.com.
Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-1018-62155 Page 2 of 2 10/16/18 Distribution: Samuel Lee, NRC, OWFN-8G9A Prosanta Chowdhury, NRC, OWFN-8G9A Marieliz Vera, NRC, OWFN-8G9A Enclosure 1: Alternatives to ASME QME-1 2007 Appendix QR-B Exceptions and Basis for Suitability Enclosure 2: Changes to NuScale Final Safety Analysis Report Table 1.9-2, Conformance with Regulatory Guides Enclosure 3: Changes to NuScale Final Safety Analysis Report Section 3.11.6, Qualification of Mechanical Equipment Enclosure 4: Changes to NuScale Final Safety Analysis Report Section 3.11.8, References Enclosure 5: Changes to NuScale Final Safety Analysis Report Appendix 3C, Section 3C.4, Aging NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-1018-62155 :
Alternatives to ASME QME-1 2007 Appendix QR-B Exceptions and Basis for Suitability NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-1018-62155 Alternatives to ASME QME-1 2007, Appendix QR-B Exceptions and Basis for Suitability NuScale complies with ASME QME-1 2007, Appendix QR-B for the environmental qualification of nonmetallic in active mechanical components with the following exceptions noted below.
- 1. QR-B5200, Identification and Specification of Qualification Requirements, (g) material's activation energy (in conjunction with one of the above identification methods only and that is based on the material's critical failure mechanism in the intended service).
Alternative:
In accordance with Appendix QR-B5200, nonmetallic material will be qualified to perform its intended functions. Although activation energy might not be used for material identification purposes per QR-B5200, the activation energy is applied to the thermal energy equation for determining material degradation and qualification.
Basis:
ASME QME-1, 2007, Appendix QR-B5200, item (g) requires identification of a material activation energy (in conjunction with one of the above identification methods only and that is based on the material's critical failure mechanism in the intended service). To be clear, NuScale is not taking exception to using the material activation energy as part of the qualification and testing. As stated in FSAR, Tier 2, Appendix 3C, Section 3C.4.2, Aging, NuScale recognizes the Arrhenius Methodology is considered an acceptable method of addressing accelerated aging. The development of the accelerated thermal aging parameters and activation energies are considered based upon the IEEE standards referenced in Section 3C.4.2.
This response addresses NRC question 1 (Identification of activation energy).
- 2. QR-B5300, Selection of Qualification Methods, last paragraph which states, The shelf life of all nonmetallics, and any applicable storage limitations, should be determined and recorded in the qualification documentation.
Alternative:
Shelf life and storage limitations are documented in accordance with the NQA-1 2008, Requirement 13 and Subpart 2.2, in lieu of ASME QME-1 2007, Appendix QR-B5300. These requirements will not be included in the environmental qualification record file, but will be documented separately.
Basis:
ASME QME-1, 2007, Appendix QR-B5300 states that shelf life needs to be part of the qualification documentation. Shelf life and qualified life are not necessarily linked and the basis for shelf life should be allowed to exist outside of the EQ documentation. This would be a unique requirement that is not imposed on the qualification of electrical equipment.
Linking shelf life to Qualified Life (QL) also is contrary to current industry practice. It can also significantly complicate the establishment and management of EQ replacement activities since the QL (or replacement due dates) become item specific (e.g. each item issued from the warehouse for the same application would likely have a unique due date if shelf life is considered as part of QL.
This response addresses NRC question 2 (Determination and recording of shelf life for nonmetallic).
NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-1018-62155
- 3. QR-B5500, Documentation, (d) the Qualification Report NuScale has reconsidered this requirement and will comply with providing a qualification report for nonmetallic items that were tested as part of their qualification process.
This response addresses NRC question 3 (Qualification Report that documents the tests performed on the nonmetallic parts).
- 4. QR-B5500, Documentation, (h) shelf life preservation requirements.
Alternative:
Shelf life preservation requirements are documented in accordance with the NQA-1 2008, Requirement 13 and Subpart 2.2 in lieu of ASME QME-1 2007, Appendix QR-B5500, item h). These requirements will not be included in the environmental qualification record file, but will be documented separately.
Basis:
ASME QME-1, 2007, Appendix QR-B5500 states that shelf life preservation requirements need to be part of the qualification documentation. Shelf life and qualified life are not necessarily linked and the basis for shelf life preservation should be allowed to exist outside of the EQ documentation. This would be a unique requirement that is not imposed on the qualification of electrical equipment.
This response addresses NRC question 4 (Shelf life preservation requirements).
NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-1018-62155 :
Changes to NuScale Final Safety Analysis Report Table 1.9-2, Conformance with Regulatory Guides NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
Table 1.9-2: Conformance with Regulatory Guides (Continued)
Tier 2 NuScale Final Safety Analysis Report RG Division Title Rev. Conformance Sta- Comments Section tus 1.100 Seismic Qualification of Elec- 3 Partially Conforms This RG is applicable except for aspects related 3.9 trical and Active Mechanical to: (1) when site-specific spectra exceed the 3.10 Equipment and Functional certified design spectra (e.g., Position 3.11 Qualification of Active C1.2.1.g); and (2) qualification of new and Mechanical Equipment for replacement equipment in older unresolved 5.2 Nuclear Power Plants safety issue A46 plants (e.g., Position C.1.2.2.j). 14.3 Not applicable to electrical equipment. Site- 3C specific guidance is the responsibility of the COL applicant. RG 1.100 endorses ASME QME-1 2007. NuScale complies with the non-mandatory Appendix QR-B with the following exceptions:
QR-B5200, Identification and Specification of Qualification Requirements, (g) material acti-vation energy.
QR-B5300 Selection of Qualification Methods 1.9-23 for determination and recording of shelf life of nonmetallics.
QR-B5500 Documentation, (h) shelf life preservation requirements.
Appendix 3C describes the exceptions cited.
1.101 Emergency Response Plan- 5 Not Applicable This RG is limited to providing emergency Not Applicable ning and Preparedness for response guidance for co-located licensees. As Nuclear Power Reactors such, this RG is the responsibility of the COL applicant proposing to site a power plant such Conformance with Regulatory Criteria that the definition of co-located is met. Since RG 1.101, Revision 4, is the most current revi-sion that endorses NUREG-0654/FEMA-REP-1, Revision 1, Revision 4 of RG 1.101 is applicable to the extent that it endorses (through NUREG-06554/FEMA-REP-1) the design-specific aspects of NUREG-0696.
Draft Revision 2 1.102 Flood Protection for Nuclear 1 Applicable The design assumes the NPP is located above 2.4 Power Plants the maximum flood height (including wind 3.4 induced wave run-up).
LO-1018-62155 :
Changes to NuScale Final Safety Analysis Report Sections 3.11.6, Qualification of Mechanical Equipment NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
NuScale Final Safety Analysis Report Environmental Qualification of Mechanical and Electrical Equipment accident, and post-accident conditions as required by GDC 4 and 10 CFR 50 Appendix B.
Mechanical equipment qualification verifies the design is capable of functioning during normal, abnormal and accident conditions and includes the effects of the fluid medium (e.g., borated water) on the environmental conditions.
RAI 03.11-13 For mechanical equipment located in a mild environment, acceptable environmental design is demonstrated by the design and purchase specifications for the equipment. The specifications contain a description of the functional requirements for a specific environmental zone during normal environmental conditions and anticipated operational occurrences. The programs identified in Section 3.11.2.1 for verifying that electrical equipment located in a mild environment are capable of performing their intended function will also be applied to mechanical equipment located in a mild environment. For mechanical equipment that must function during or following exposure to a harsh environment, compliance with the environmental design provisions of GDC 4 are generally achieved by demonstrating that the non-metallic parts/components of the equipment suitable for the postulated design basis environmental conditions. Safety-related mechanical equipment that performs an active function during or following exposure to harsh environmental conditions will beis qualified in accordance with ASME QME-1, Appendix QR-B (Reference 3.11-13) as endorsed by RG 1.100, Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants, Revision 3 with the following exceptions noted below.
- 1) Exception to QR-B5200, Identification and Specification of Qualification Requirements, (g) material activation energy.
- 2) Exception to QR-B5300, Selection of Qualification Methods for determination and recording of shelf life of nonmetallics.
- 3) Exception to QR-B5500 Documentation, (h) shelf life preservation requirements.
Documentation and the status of the testing and analysis are performed in accordance with the processes presented in Appendix 3.C.
Mechanical equipment located in harsh environmental zones is designed to perform under all appropriate environmental conditions. The primary focus with mechanical equipment is on materials that are sensitive to environmental effects (e.g., seals, gaskets, lubricants, fluids for hydraulic systems, and diaphragms). A list of the mechanical components that contain non-metallic or consumable parts located in harsh environment areas that require EQ is provided in Table 3.11-1.
RAI 12.03-7S1 There can be no environmentally induced debris inside the CNV that could interfere with the proper functioning of the ECCS. This requirement is addressed as a generic requirement to ensure that all SSCs inside the CNV that have the potential to generate debris during the course of an accident have been qualified to demonstrate that no debris is generated or released that could impair the performance of the ECCS.
RAI 03.11-14 Tier 2 3.11-11 Draft Revision 2
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Changes to NuScale Final Safety Analysis Report Section 3.11.8, References NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
NuScale Final Safety Analysis Report Environmental Qualification of Mechanical and Electrical Equipment 3.11-6 IEEE Std. 7-4.3.2-2003, Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.
3.11-7 IEEE Std. 603-1991, Criteria for Safety Systems for Nuclear Power Generating Stations.
3.11-8 IEEE Std. 572-2006, IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations.
3.11-9 IEEE Std. 535-1986, IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations.
3.11-10 Topical Report TR-0915-17565-P, Accident Source Term Methodology.
3.11-11 IEEE Std. 383-2003, IEEE Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations.
3.11-12 IEEE Std. 323-2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.
3.11-13 American Society of Mechanical Engineers, ASME QME-1-200712, Qualification of Active Mechanical Equipment Used In Nuclear Facilities.
CP2-1289 Tier 2 3.11-13 Draft Revision 2
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Changes to NuScale Final Safety Analysis Report Appendix 3C, Section 3C.4, Aging NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
Methodology for Environmental Qualification of Electrical and NuScale Final Safety Analysis Report Mechanical Equipment QR-B5200, Identification and Specification of Qualification Requirements, (g) material activation energy.
QR-B5300 Selection of Qualification Methods for determination and recording of shelf life of nonmetallics.
QR-B5500 Documentation, (h) shelf life preservation requirements.
These exceptions are addressed with the following alternatives:
QR-B5200, Identification and Specification of Qualification Requirements, (g) material's activation energy (in conjunction with one of the above identification methods only and that is based on the material's critical failure mechanism in the intended service).
Alternative:
In accordance with Appendix QR-B5200, nonmetallic material will be qualified to perform its intended functions. Although activation energy might not be used for material identification purposes per QR-B5200, the activation energy will be applied to the thermal energy equation for determining material degradation and qualification.Listing the activation energy as a required identification method for commercial grade item dedication purposes has been shown to conflict with existing industry guidance regarding dedication activities (see ADAMS ML18208A208). Identification methods identified per QR-B5200 items (a) through (g) are acceptable for identification purposes for qualification, and no alternative is therefore provided.
QR-B5300, Selection of Qualification Methods, last paragraph which states, The shelf life of all nonmetallics, and any applicable storage limitations, should be determined and recorded in the qualification documentation.
Alternative:
Shelf life and preservation requirements are documented in accordance with the NQA-1 2008, Requirement 13 and Subpart 2.2, in lieu of ASME QME-1 2007, Appendix QR-B5300. These requirements are not included in the environmental qualification record file, but are documented separately.
QR-B5500, Documentation, (h) shelf life preservation requirements.
Alternative:
Shelf life preservation requirements are documented in accordance with the NQA-1 2008, Requirement 13 and Subpart 2.2 in lieu of ASME QME-1 2007, Appendix QR-B5500, item (h).
These requirements are not included in the environmental qualification record file, but are documented separately.
Mechanical and electrical equipment required to perform a design function related to safety located in mild environments is qualified in accordance with the provisions of GDC 4.
For each piece of equipment selected for environmental qualification, the environmental Tier 2 3C-3 Draft Revision 3