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Category:Legal-Affidavit
MONTHYEARML20150E1772020-05-29029 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 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 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 RAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML20066H1812020-02-28028 February 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 19 - Probabilistic Risk Assessment Area of Focus, PM-0220-69046, Revision 0 ML20066H1842020-02-28028 February 2020 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Topic-Resolution of Chapter 15 Phase 2 Open Items (Closed Session), PM-0220-69063, Revision 0 ML20054A4112020-02-17017 February 2020 LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topical Report - Loss-of-Coolant Accident Evaluation Model (Closed Session), PM-0220-68914, Revision 0 ML20054A9652020-02-17017 February 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology (Closed Session), PM-1019-67366, Revision 0 ML20054A9692020-02-17017 February 2020 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topical Report- Non-Loss-of-Coolant Accident (Closed Session), PM-0220-68851, Revision 0 ML19353A7192019-12-19019 December 2019 LLC, Submittal of NuFuel-HTP2 Fuel and Control Rod Assembly Designs, TR-0816-51127, Revision 3 ML19352G6972019-12-18018 December 2019 LLC Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 2 ML19338E9482019-12-0404 December 2019 LLC Submittal of Human-System Interface Style Guide, ES-0304-1381, Revision 4 ML19337B4472019-12-0202 December 2019 LLC - Submittal of Changes to Long-Term Cooling Methodology, TR-0916-51299, Revision 1 ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19238A3092019-08-26026 August 2019 LLC - Submittal Nuscale'S Proposed Closure Plan to Address Impacts of the Adjusted Iab Operations Range ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19218A1472019-08-0505 August 2019 LLC - Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 1 ML19215A0062019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 441 (Erai No. 9485) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19212A3752019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 483 (Erai No. 9516) on the NuScale Design Certification Application ML19212A7992019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19211D4112019-07-30030 July 2019 LLC Submittal of NuScale Power Module Short-Term Transient Analysis, TR-1016-51669, Revision 1 ML19207B3812019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19192A1602019-07-0909 July 2019 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Evaluation Methodology for Stability Analysis of the NuScale Power Module, PM-0719-66244, Revision 0 ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19183A4852019-07-0202 July 2019 LLC - Submittal of Fluence Calculation Methodology and Results, TR-0116-20781, Revision 1 ML19182A0462019-06-27027 June 2019 LLC - Submittal of Presentation Materials Titled TF-3 Modal Demonstration Testing and Siet Tour, PM-0619-66058-P, Revision 0 ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19172A1012019-06-17017 June 2019 LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation, NuScale FSAR Chapter 15, Transient and Accident Analyses, and Chapter 6.2.1, Containment Functional Design, PM-0619-65992-P, Revision 0 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 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8102019-05-31031 May 2019 LLC Submittal of Technical Report NuScale Generic Technical Guidelines, TR-1117-57216, Revision 1 ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19151A8342019-05-31031 May 2019 LLC - Submittal of Turbine Missile Barrier Design Closure Plan Actions (Final Safety Analysis Report, Tier 2, Section 3.5.1.3) 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 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) ML19105B0772019-04-15015 April 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 478 (Erai No. 9470) on the NuScale Design Certification Application ML19101A4412019-04-11011 April 2019 LLC Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19099A4732019-04-0909 April 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19098B6202019-04-0808 April 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 465 (Erai No. 9494) on the NuScale Design Certification Application ML19093B8502019-04-0303 April 2019 LLC - Submittal of Technical Report TR-0916-51502, NuScale Power Module Seismic Analysis, Revision 2 ML19087A2882019-03-28028 March 2019 LLC Updates to Final Safety Analysis Report, Section 1.6,Materials Referenced, Section 3.6, Protection Against Dynamic Effects Associated with Postulated Rupture of Piping, and the Pipe Rupture Hazards Analysis, TR-0818-61384 2020-05-29
[Table view] 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] Category:License-Application for Design Certification
MONTHYEARML20224A5212020-07-29029 July 2020 Part 07 - Exemptions - Chapters 01 - 17 (Rev. 5) - Part 07 - Exemptions - Chapters 01 - 17 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 ML20197A4142020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 20 - Mitigation of Beyond-Design-Basis Events - Sections 20.01 - 20.04 (Rev. 4.1) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20197A4322020-06-19019 June 2020 Part 10 - Quality Assurance Program Description (Rev. 4.1) - Part 10 - Quality Assurance Program Description (Rev. 4.1) ML20197A4302020-06-19019 June 2020 Part 09 - Withheld Information (Rev. 4.1) - Part 09 - Withheld Information (Rev. 4.1) ML20197A4282020-06-19019 June 2020 Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) - Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) ML20197A4262020-06-19019 June 2020 Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) - Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) ML20197A4242020-06-19019 June 2020 Part 06 - Security Plans (Rev. 4.1) - Part 06 - Security Plans (Rev. 4.1) ML20197A4222020-06-19019 June 2020 Part 05 - Emergency Plans (Rev. 4.1) - Part 05 - Emergency Plans (Rev. 4.1) ML20197A4202020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 2 - Bases - Chapters 02 - 03 (Rev. 4.1) ML20197A4192020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 1 - Specifications - Chapters 01 - 05 (Rev. 4.1) ML20197A4172020-06-19019 June 2020 Part 03 - Applicants Environmental Report - Standard Design Certification (Rev. 4.1) - Part 03 - Applicants Environmental Report - Standard Design Certification - Section 1.0 - Appendix B (Rev. 4.1) ML20197A4152020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 21 - Multi-Module Design Considerations - Sections 21.01 - 21.04 (Rev. 4.1) ML20197A4132020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Sections 19.00 - 19.05 (Rev. 4.1) ML20197A4122020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 18 - Human Factors Engineering - Sections 18.00 - 18.12 (Rev. 4.1) ML20197A4112020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 17 - Quality Assurance and Reliability Assurance - Sections 17.01 - 17.06 (Rev. 4.1) ML20197A4102020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 16 - Technical Specifications - Section 16.01 - Technical Specifications (Rev. 4.1) ML20197A4092020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 15 - Transient and Accident Analyses - Sections 15.00 - 15.10 (Rev. 4.1) ML20197A4082020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 14 - Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria - Sections 14.00 - 14.03 (Rev. 4.1) ML20197A4072020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 13 - Conduct of Operations - Sections 13.01 - 13.07 (Rev. 4.1) ML20197A4062020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 12 - Radiation Protection - Sections 12.01 - 12.05 (Rev. 4.1) ML20197A4042020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 10 - Steam and Power Conversion System - Sections 10.01 - 10.04 (Rev. 4.1) ML20197A3842020-06-19019 June 2020 Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) - Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) ML20197A3862020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 01 - Certified Design Descriptions and Inspections, Tests, Analyses, and Acceptance Criteria - Chapters 01 - 05 (Rev. 4.1) ML20197A3872020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 01 - Introduction and General Description of the Plant - Sections 01.01 - 01.10 (Rev. 4.1) ML20197A3882020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 02 - Site Characteristics and Site Parameters - Sections 02.00 - 02.05 (Rev. 4.1) ML20197A3892020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.01 - 03.06 (Rev. 4.1) ML20197A3902020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 1 - 265 (Rev. 4.1) ML20197A3912020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 266 - 307 (Rev. 4.1) ML20197A3922020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 308 - 345 (Rev. 4.1) ML20197A3932020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 346 - 482 (Rev. 4.1) ML20197A3942020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 1 - 140 (Rev. 4.1) ML20197A3962020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 (Rev. 4.1) ML20197A3952020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 141 - 271 (Rev. 4.1) ML20197A3972020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C (Rev. 4.1) ML20197A3982020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 (Rev. 4.1) ML20197A3992020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 (Rev. 4.1) ML20197A4002020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 (Rev. 4.1) ML20197A4012020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 (Rev. 4.1) ML20197A4022020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 (Rev. 4.1) ML20197A4032020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 09 - Auxiliary Systems - Section 09.01 - Appendix 9A (Rev. 4.1) ML20197A4052020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 11 - Radioactive Waste Management - Sections 11.01 - 11.06 (Rev. 4.1) ML20036D4442020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 ML20036D4422020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 ML20036D4402020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 ML20036D4392020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 ML20036D4382020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 ML20036D4372020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C ML20036D4332020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 2020-07-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 441 (Erai No. 9485) on the NuScale Design Certification Application ML19212A7622019-07-31031 July 2019 LLC Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19212A3752019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 483 (Erai No. 9516) on the NuScale Design Certification Application ML19212A7992019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19212A6892019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19210D1592019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19210D7342019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application ML19210E1462019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19207B3812019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19207A5342019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19207B8522019-07-25025 July 2019 LLC Response to NRC Request for Additional Information No. 194 (Erai No. 8884) on the NuScale Design Certification Application ML19203A3152019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19203A3212019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 333 (Erai No. 9282) on the NuScale Design Certification Application ML19203A3092019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 54 (Erai No. 8837) on the NuScale Design Certification Application ML19203A3422019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 154 (Erai No. 8938) on the NuScale Design Certification Application ML19200A2482019-07-19019 July 2019 LLC Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19200A2082019-07-19019 July 2019 LLC - Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19198A3252019-07-17017 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 249 (Erai No. 9135) on the NuScale Design Certification Application ML19196A3682019-07-15015 July 2019 LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application ML19191A2202019-07-10010 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19170A3702019-06-19019 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19168A2442019-06-17017 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
[Table view] |
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RAIO-0718-61073 July 25, 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 Response to NRC Request for Additional Information No.
427 (eRAI No. 9408) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
427 (eRAI No. 9408)," dated April 17, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosures to this letter contain NuScale's response to the following RAI Question from NRC eRAI No. 9408:
03.09.02-75 is the proprietary version of the NuScale Response to NRC RAI No. 427 (eRAI No.
9408). NuScale requests that the proprietary version be withheld from public disclosure in accordance with the requirements of 10 CFR § 2.390. The enclosed affidavit (Enclosure 3) supports this request. Enclosure 2 is the nonproprietary version of the NuScale response.
This letter and the enclosed responses make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.
Sincerely, Z ckary W. Rad Za Zackary Di t Regulatory Director, R l t Aff Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Marieliz Vera, NRC, OWFN-8G9A Enclosure 1: NuScale Response to NRC Request for Additional Information eRAI No. 9408, proprietary NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0718-61073 : NuScale Response to NRC Request for Additional Information eRAI No. 9408, nonproprietary : Affidavit of Zackary W. Rad, AF-0718-61074 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0718-61073 :
NuScale Response to NRC Request for Additional Information eRAI No. 9408, proprietary NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0718-61073 :
NuScale Response to NRC Request for Additional Information eRAI No. 9408, nonproprietary NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 9408 Date of RAI Issue: 04/17/2018 NRC Question No.: 03.09.02-75 10 CFR 50, Appendix A, GDC 4 requires structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents. During the audit from May 16, 2017, through November 2, 2017, the staff finds that NuScale has not measured or simulated reasonable flow-induced forcing functions for the CRAGT structures. Although several internal NuScale documents state that the CRAGT flow- induced forces are not known and that the flow fields do not resemble those of simple flows cited in the literature, no measurements of these flows or forces have been conducted.
Assuming the simplified flow forces led to an estimated ((2(a),(c) wall thickness degradation. The staff is unable to determine if this significant wall degradation impacts safety, or if more severe wall degradation may occur due to more complex flows through and around the CRAGTs.
NuScale is requested to provide the following information. Alternatively, NuScale may propose other options to resolve the staff's concerns identified above.
- 1. summarize the operating history of similar CRAGT designs in other currently operating plants,
- 2. define the maximum acceptable wall thickness degradation for the CRAGTs before replacement is needed,
- 3. explain the safety implications associated with complete wall thickness degradation of the CRAGTs, and
- 4. explain how more prototypic flow fields and forces will be estimated and applied to updated structural response analyses, or how tests might be used to show that CRAGT vibration and/or strain is negligible.
Update the comprehensive vibration assessment program report TR-0716-50439 or other appropriate documentation in the design certification package to include a summary of the requested information.
NuScale Nonproprietary
NuScale Response:
Item 1
- 1) The EPRI Materials Reliability Program (MRP) considers the potential for wear for components found in operating reactors. MRP-227 provides guidelines for inspection and evaluation of the reactor vessel internals based on a detailed assessment of the aging degradation mechanisms for reactor vessel internals found in MRP-175. Figures 4-1 and 4-5 of MRP-227 show that structures similar to NuScales control rod assembly guide tube (CRAGT),
the B&W control rod guide tubes (CRGTs), have been evaluated using this program for aging degradation mechanisms. Wear is one of the eight aging degradation mechanisms considered (See Section 2.1 of MRP-227). Table 3-1 of MRP-227 lists the assessment results regarding the B&W CRGTs. The subparts were found to be not susceptible to wear and no additional measures were recommended. The NuScale design has a similar mechanical design to the B&W CRGTs, but has no bulk external cross flow (the fluid exits through the upper CRAGT support for NuScale, while for B&W the fluid exits the side of the region), and has flow velocities around 1/5th of those found in the B&W design (due to natural circulation vs. forced flow). These differences are advantages for the NuScale CRAGT relative to the B&W CRGT with respect to turbulent buffeting.
Appendix C of MRP-175 establishes the screening criteria for wear. The first criterion for inclusion is locations where relative motion may occur. The CRGTs are given as an example, but only the Westinghouse CRGT cards are placed in the primary group for wear. These components have relative motion (between the card and the rodlets), and thus are susceptible to wear. B&W CRGT components, which are similar to the NuScale CRAGT, are categorized as requiring no additional measures (i.e., they are not susceptible to wear).
In summary, MRP review of similar structures in operating plants concluded that they are not a location for wear due to 1) lack of motion of the part relative to the supports and 2) no history of wear being observed in service at the interface between the industry CRGT and their supports.
Items 2-4 The wear estimates presented for the CRAGTs have been revised to more accurately represent the maximum relative motion between the CRAGT and the support. Wear estimates generally vary linearly with the cumulative sliding distance over the life of the component. The sliding distance due to turbulent buffeting has been revised to take out unnecessary conservatism. The previous estimate was based on the CRAGT traveling one complete circular path around the support hole at the root mean square (RMS) crossing frequency. Turbulent buffeting of the CRAGT cannot generate this large motion. The new estimate is based on traveling four times the zero-to-peak amplitude of the RMS vibration at the crossing frequency. The new estimate for the cumulative sliding distance is more than three orders of magnitude lower than the previous estimate.
NuScale Nonproprietary
The revised calculation shows that the maximum wear over the life of the plant of the CRAGT due to turbulent buffeting vibrations is low: equivalent to wear through (( }}2(a),(c) of the wall thickness at a single concentrated wear location. This analysis conservatively applies the maximum RMS response (found at the mid-span of the CRAGT) to the support location.
- 2) The CRAGTs do not have specified limits for the extent of allowable wear. The Comprehensive Vibration Assessment Program (CVAP) inspection during startup testing and the inservice inspection program ensure that the plant is not operated with unsafe levels of wear on reactor vessel internal components on a case-by-case basis.
- 3) The CRAGTs are not expected to experience significant wear that would warrant the evaluation of the consequences of complete degradation. This is supported by operating experience of similar components. Regular inspection ensures that, even if the wear estimates are lower than real wear rates, the CRAGTs will not progress to an unsafe condition over the life of the plant.
- 4) Because the estimated extent of turbulent vibration induced degradation is low for fatigue, impact, and wear, no additional analysis or tests to validate the flow force estimates are necessary. The annular flow PSD selected exceeds similar PSD evaluations for cross flow. The CRAGT flow is a mix of cross flow and annular flow, so the larger of the two PSDs is used.
In summary, CRAGT wear has been estimated with a more accurate, yet still conservative, methodology demonstrating that the CRAGT is not at risk for significant flow induced degradation of any kind. While the CRAGT flow patterns do not neatly fit into an available literature source for a PSD, the most bounding PSD estimate available is used to estimate turbulent buffeting vibrations. The CRAGT is included in the inservice inspection program to ensure that unforeseen degradation does not progress to the point of component failure over the plant life. The CRAGT screens out of further testing according to the methodology defined in the CVAP technical report TR-0716-50439. Additionally, the CVAP technical report does not contain wear assessments. NuScale does not plan to have additional tests or analyses to develop further specific flow forcing functions for the CRAGT due to the large margins estimated in turbulent buffeting calculations with standard flow forcing functions.
Impact on DCA:
There are no impacts to the DCA as a result of this response.
NuScale Nonproprietary
RAIO-0718-61073 :
Affidavit of Zackary W. Rad, AF-0718-61074 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
NuScale Power, LLC AFFIDAVIT of Zackary W. Rad I, Zackary W. Rad, state as follows:
- 1. I am the Director, Regulatory Affairs of NuScale Power, LLC (NuScale), and as such, I have been specifically delegated the function of reviewing the information described in this Affidavit that NuScale seeks to have withheld from public disclosure, and am authorized to apply for its withholding on behalf of NuScale.
- 2. I am knowledgeable of the criteria and procedures used by NuScale in designating information as a trade secret, privileged, or as confidential commercial or financial information. This request to withhold information from public disclosure is driven by one or more of the following:
- a. The information requested to be withheld reveals distinguishing aspects of a process (or component, structure, tool, method, etc.) whose use by NuScale competitors, without a license from NuScale, would constitute a competitive economic disadvantage to NuScale.
- b. The information requested to be withheld consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), and the application of the data secures a competitive economic advantage, as described more fully in paragraph 3 of this Affidavit.
- c. Use by a competitor of the information requested to be withheld would reduce the competitor's expenditure of resources, or improve its competitive position, in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
- d. The information requested to be withheld reveals cost or price information, production capabilities, budget levels, or commercial strategies of NuScale.
- e. The information requested to be withheld consists of patentable ideas.
- 3. Public disclosure of the information sought to be withheld is likely to cause substantial harm to NuScale's competitive position and foreclose or reduce the availability of profit-making opportunities. The accompanying Request for Additional Information response reveals distinguishing aspects about the method by which NuScale develops its power module seismic analysis.
NuScale has performed significant research and evaluation to develop a basis for this method and has invested significant resources, including the expenditure of a considerable sum of money.
The precise financial value of the information is difficult to quantify, but it is a key element of the design basis for a NuScale plant and, therefore, has substantial value to NuScale.
If the information were disclosed to the public, NuScale's competitors would have access to the information without purchasing the right to use it or having been required to undertake a similar expenditure of resources. Such disclosure would constitute a misappropriation of NuScale's intellectual property, and would deprive NuScale of the opportunity to exercise its competitive advantage to seek an adequate return on its investment.
AF-0718-61074
- 4. The information sought to be withheld is in the enclosed response to NRC Request for Additional Information No. 427, eRAI 9408. The enclosure contains the designation "Proprietary" at the top of each page containing proprietary information. The information considered by NuScale to be proprietary is identified within double braces, "(( }}" in the document.
- 5. The basis for proposing that the information be withheld is that NuScale treats the information as a trade secret, privileged, or as confidential commercial or financial information. NuScale relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC § 552(b)(4), as well as exemptions applicable to the NRC under 10 CFR §§ 2.390(a)(4) and 9.17(a)(4).
- 6. Pursuant to the provisions set forth in 10 CFR § 2.390(b)(4), the following is provided for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld:
- a. The information sought to be withheld is owned and has been held in confidence by NuScale.
- b. The information is of a sort customarily held in confidence by NuScale and, to the best of my knowledge and belief, consistently has been held in confidence by NuScale.
The procedure for approval of external release of such information typically requires review by the staff manager, project manager, chief technology officer or other equivalent authority, or the manager of the cognizant marketing function (or his delegate), for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside NuScale are limited to regulatory bodies, customers and potential customers and their agents, suppliers, licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or contractual agreements to maintain confidentiality.
- c. The information is being transmitted to and received by the NRC in confidence.
- d. No public disclosure of the information has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or contractual agreements that provide for maintenance of the information in confidence.
- e. Public disclosure of the information is likely to cause substantial harm to the competitive position of NuScale, taking into account the value of the information to NuScale, the amount of effort and money expended by NuScale in developing the information, and the difficulty others would have in acquiring or duplicating the information. The information sought to be withheld is part of NuScale's technology that provides NuScale with a competitive advantage over other firms in the industry.
NuScale has invested significant human and financial capital in developing this technology and NuScale believes it would be difficult for others to duplicate the technology without access to the information sought to be withheld.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July 25, 2018.
Zackary Z k W W. RRadd AF-0718-61074}}