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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
[Table view] Category:Slides and Viewgraphs
MONTHYEARML20184A2872020-07-0101 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 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 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 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 ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to NuScales EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 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 ML20072H3272020-03-0909 March 2020 LLC - Public Meeting Presentation: Topic - Emergency Core Cooling System Boron (ECCS) Distribution, PM-0320-69218, Revision 0 ML20069A1632020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A9692020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision O ML20069A1542020-03-0404 March 2020 ACRS Full Committee Presentation: NuScale Topical Report- Non-Loss-of-Coolant Accident, PM-0320-69141, 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 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 ML20066G2772020-02-28028 February 2020 ACRS Full Committee Presentation: NuScale - Steam Generator Design, PM-0220-69051, Revision 0 ML20054A9622020-02-19019 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report - Non-Loss-of-Coolant Accident, PM-0220-68852, Revision 0 ML20054A4062020-02-17017 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report- Loss-of-Coolant Accident Evaluation Model, PM-0220-68917, Revision 0 ML20054B6342020-02-17017 February 2020 Nuscale - ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology, PM-1019-67365, Revision 0 ML20035C7892020-02-0404 February 2020 Nuscale - ACRS Subcommittee Presentation, FSAR, Steam Generator Design ML19340B5912019-12-0606 December 2019 Public Meeting - NuScale Incorporated by Reference (Ibr) Slides ML19324C8362019-11-13013 November 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Source Term Methodology Application, PM-1119-67928, Revision 0 ML19192A1662019-07-10010 July 2019 Presentation Entitled, Evaluation Methodology for Stability Analysis of the NuScale Power Module. ML19169A1662019-06-14014 June 2019 Mitigation of Beyond-Design-Basis-Events, NuScale FSAR Chapter 20, PM-0619-65964, Revision 0 ML19135A0642019-05-0909 May 2019 LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations, PM-0519-65533, Revision 0 ML19105A1352019-04-11011 April 2019 ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, Revision 0 ML19105A1312019-04-10010 April 2019 Enclosuacrs Presentation: Chapter 4, Reactor Overview, PM-0419-65096, Revision 0 ML19098A7802019-04-0202 April 2019 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Chapter 9, Auxiliary Systems, PM-0319-64807, Revision 0 ML19073A0482019-03-11011 March 2019 LLC - ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 1 ML19073A0512019-03-11011 March 2019 ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 1 ML19073A0532019-03-11011 March 2019 Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 1 ML19050A1632019-02-20020 February 2019 Enclosure 1: ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 0 ML19053A5182019-02-19019 February 2019 Nuscale - Dhrs and ECCS Logic Changes, PM-0219-64563, Revision 0 ML19050A3982019-02-13013 February 2019 Enclosure 1: ACRS Presentation Chapter 10 - Steam and Power Conversion System, PM-0219-64501, Revision 0 ML19045A3062019-02-12012 February 2019 PM-0219-64475-NP, Revision 0, Reactor Vessel Flange Tool (Rft) Design Plan and Schedule. ML19042A0732019-02-0505 February 2019 Nuscale - Chapters 2 and 17 ACRS Full Committee, PM-0219-64333, Revision 0 ML19024A2042019-01-23023 January 2019 ECCS Valve DCA Demonstration Testing, PM-0119-64160-NP, Revision 0 ML18360A1782018-12-19019 December 2018 Enclosure 2: Presentation Titled, Addressing Component Fatigue for NuScale Dca. ML18362A1422018-12-19019 December 2018 Enclosure 2: Absorption Coefficient for Pool Water and Reactor Building Floor Interaction, PM-1218-63882, Revision 0 ML18347A2032018-12-18018 December 2018 Enclosure 1: ACRS Presentation Chapter 17 - Quality Assurance and Reliability Assurance, PM-1218-63732, Revision 0 ML18347A2072018-12-18018 December 2018 ACRS Presentation Chapter 2 - Site Characteristics and Site Parameters, PM-1218-63753, Revision 0 ML19025A2212018-12-18018 December 2018 Enclosure 2: Slides Titled, Basis for an Rft Stand COL Item, PM-1218-63892-NP, Revision 0, Non-Proprietary Version ML18331A1602018-11-20020 November 2018 Enclosure 2: Addressing Component Fatigue for NuScale DCA, November 20, 2018 ML18338A1032018-11-14014 November 2018 Nuscale - LTC RAI Closure Plan, PM-1118-63594-NP, Revision 0, Nonproprietary Version ML18235A3152018-08-23023 August 2018 LLC - Presentation Materials Entitled ACRS Presentation: NuScale Instrumentation and Controls Design Overview, PM-0618-60212, Revision 0 ML18222A1932018-08-0808 August 2018 Enclosure 1: NuScale Accident Source Terms Methodology Options PM-0818-61166, Revision 0 ML18213A1572018-08-0101 August 2018 Risk-Informed Review of NuScale Initial Test Program, PM-0718-61123, Revision 0 ML18220A8742018-07-25025 July 2018 Enclosunuscale CIRLT-RAI 9474 ML18156A1262018-06-0101 June 2018 LLC Submittal of Presentation Materials Entitled, ACRS Presentation Chapter 8 Overview, for Use During a Public Meeting on June 6, 2018 ML18156A1272018-05-31031 May 2018 LLC Submittal of Presentation Materials Entitled NuScale Power Containment Leak Rate Test Program, PM-0518-59978, Revision 1 ML18116A4422018-04-24024 April 2018 Enclosure 2: NuScale Power Comprehensive Vibration Assessment Program - Audit Report Summary Discussion, Revision 0, PM-0218-58803-NP (Non-Proprietary Version) ML18037A6732018-02-0808 February 2018 PM-0218-58480, Revision 0, Shutdown Capability of the NuScale Power Module. 2020-07-01
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L0-0219-64492 :
"ACRS Presentation Chapter 10 - Steam and Power Conversion System," PM-0219-64501, Revision 0 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
NuScale Nonproprietary NuScale FSAR Tier 2, Ch.
10 ACRS Presentation Zack Houghton, P.E.
Mechanical Design Engineering Manager February 20th, 2019 PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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Acronyms ABS: Auxiliary Boiler System MC: Main Condenser CARS: Condenser Air Removal System MS: Main Steam CFWS: Condensate and feedwater System MSIBV: Main Steam Isolation Bypass Valve CNTS: Containment System MSIV: Main Steam Isolation Valve COL: Combined Operating License MSS: Main Steam System CPS : Condensate Polishing System MSSV: Main Steam Safety Valve CWS: Circulating Water System NEI: Nuclear Energy Institute DCA: Design Certification Application NS: Non safety-related DHR HX: Decay Heat Removal Heat Exchanger NSAC: Nuclear Safety Analysis Center EPRI: Electric Power Research Institute PDC: Principal Design Criteria FAC: Flow-accelerated Corrosion RG: Regulatory Guide FW: Feedwater RIT: Radiation Indicating Transmitter FWRV: Feedwater Regulation Valve RT: Radiation Transmitter FWT : Feedwater Treatment System RXB: Reactor Building GDC: General Design Criteria SR: Safety-related HP: High Pressure SG: Steam generator IP: Intermediate Pressure TEWAC: Totally Enclosed Water to Air Cooled ITAAC: Inspections, Tests, Analyses, and Acceptance TG: Turbine generator Criteria TGS: Turbine Generator System LP: Low Pressure VFD: Variable Frequency Drive 2
PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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Ch. 10 - Topics
- 10.4 Other Features of Steam and Power Conversion System 3
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Template#: 0000-21727-F01 R5
Ch. 10.1 Summary Description
- The NuScale steam and power conversion system is comprised of the following systems:
- Turbine generator system
- Main steam system
- Main condenser
- Condenser air removal system
- Turbine gland sealing system
- Turbine bypass system
- Circulating water system
- Condensate polishing system
- Condensate and feedwater system
- Auxiliary boiler system
- Feedwater treatment system 4
PM-0219-64501 Revision: 0 Copyright 2019 by NuScale Power, LLC.
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Ch. 10.1 Summary Description Figure 10.1- 1: Power Conversion System Block Flow Diagram Removable Turbine Spool Pieces Bypass lt l Valve Seismic Feedwater Seismic Anchor
- Located at Exit FranRXB D*superheNt TGS Turbine Stop Valve TGS t cFWS -+/-
o Cooling Tower MSS ._j_..TGS
-~
CNTS SG Valves ABS Aux Steam Header ,..._ _..,
CARS CFWS i
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Entrance to ElChauster MS$
~ Removable Spool Pieces Packages
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SG ,st:)'",,, Condenser Air Removal Packages MS$
c~
--+ CFWS ToP Huter TG LEGEND t Condensate Steam Generator & Aux Boiler c:::::::J Feedwater Pumps Gland
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Turbine Generator System -
Condensate & Feeo.vater System - Nu Scale Power Cycle Block Flow Diagram Condenser Air Removal System c:::::::,
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Ch. 10.1 Summary Description II tl .-,-----------------,
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Power Island Layout Condenser 7
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Ch 10.2 Turbine generator system
- Converts thermal energy from SG into rotational energy
- Turbine control valves regulate steam flow from SG
- Generator directly coupled with turbine
- Vendor to be selected by COL applicant Component Parameter Value Rotor Single Turbine, 10 stage condensing Turbine RPM 3600 rpm Power Output 50MWe Generator Cooling Type TEWAC 8
PM-0219-64501 Revision : 0 Copyrig ht 2019 by NuScale Power, LLC.
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Missile Protection
- Missile protection addressed in Section 3.5
- All essential equipment located inside the reactor or control buildings
- Barrier approach taken per RG 1.11 5 to credit reactor and control building walls as a missile barrier.
- No missile generation probability analysis or rotor integrity program credited
- Overspeed protection system similar in design to industry standard 9
PM-0219-64501 Revision : 0 Copyright 20 19 by NuScale Power, LLC .
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Turbine Bypass
- Capable of supplying 100°/o rated power steam flow to main condenser
- Minimized potential for main steam release or reactor trip on load rejection 10 PM-0219-64501
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10.3 Main Steam System
- Delivers steam from steam generators to:
- Directly to condenser through bypass valve
- Provides means of dissipating residual and sensible heat generated by module during hot standby and cooldown operations by bypassing turbine to main condenser
- Transports extraction steam from turbine to feedwater heaters 11 PM-0219-64501
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10.3 Main Steam System
- Main Steam System Boundary Removable Spool Pieces MSSVs Safety Seismic 111 SR NS Seismic Anchor
/- Located at Exit From RXB Main Steam v-ABS MSS+TGS Secondary Main Steam Isolation Valves Aux Steam Header 4 ,_ _ _. ,
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10.3 Main Steam System
- Secondary steam isolations provided as backup to MSIVs
- Nonsafety-related
- Credited as backup protection for the safety-related isolations
- Periodically tested per the lnservice Testing Program
- Included within Technical Specifications
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10.4 Other Features
- Supplies FW at necessary temperature, pressure, and chemistry to steam generator
- Consists of:
- Three feedwater pumps (2x 50°10 capacity, 1 on standby)
- Three condensate pumps (2x 50°10 capacity, 1 on standby)
- Condensate polishing subsystem
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10.4 Other Features
- Condensate and Feedwater System Boundary Removable Spool Pieces 1 FromHP Her**
't CFWS MSS
--+
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10.4 Other Features
- Nonsafety-related
- Credited as backup protection for the safety-related isolations
- Periodically tested per the lnservice Testing Program
- Included within Technical Specifications 16 PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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10.4 Other Features
- Full flow condensate polishing
- All volatile chemistry (amine to control pH, oxygen scavenger to control dissolved oxygen)
- Controls erosion and corrosion of CFWS components by monitoring and maintaining pH and dissolved oxygen levels
- Chemistry program based on current revision of the EPRI PWR Secondary Water Chemistry Guidelines and NEI 97-06 (Steam Generator Program) 17 PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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10.4 Other Features*
- Provides cooling water to main condenser
- Two identical circulating water systems, each providing cooling water to six main condensers 18 PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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10.4 Other Features
- Auxiliary boiler system (ABS)
- Supplies steam to systems when main steam is not available or not preferred
- High-pressure feeds module heatup system during startup
- Low-pressure feeds turbine gland seals, main condenser for deaeration, and condensate polishing regeneration system 19 PM-0219-64501
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Ch. 10 COL Items 10.3-1 A COL applicant that references the NuScale Power Plant design certification will provide a site-specific chemistry control program based on the latest revision of the Electric Power Research Institute Pressurized Water Reactor Secondary Water Chemistry Guidelines and Nuclear Energy Institute (NEI) 97-06 at the time of the COL application.
10.3-2 A COL Applicant that references the NuScale Power Plant design certification will provide a description of the flow-accelerated corrosion monitoring program for the steam and power conversion systems based on Generic Letter 89-08 and the latest revision of the Electric Power Research Institute NSAC-202L at the time of the COL application.
- 10.4-1 . A COL applicant that references the NuScale Power Plant design certification will determine the size and number of new and spent resin tanks in the condensate polishing system.
10.4-2 A COL applicant that references the NuScale Power Plant design certification will describe the type of fuel supply for the auxiliary boilers.
10.4-3 A COL applicant that references the NuScale Power Plant design certification will provide a secondary water chemistry analysis. This analysis will show that the size, materials, and capacity of the feedwater treatment system equipment and components satisfies the water quality requirements of the secondary water chemistry program described in Section 10.3.5, and that it is compatible with the chemicals used.
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Open Items Item# Summary Description
--- .------ ---- -, -*--* ------- ---- ... --- -- . -- .. -- -- -** -------------- - -- ----- - -- - -- -- --*--- --- . ------ -* -- -- *-* . - - . -- --- --- - - ----*-- -------------------------1 8.3-1 !l Related to requested exemption from GDC/PDC 34, "Residual Heat Removal," with I
!; respect to the system function of transferring residual and sensible heat from the :_
ij reactor coolant system. '
I,_ . * . * .
- _ ***** __ ... _ -*** __ __ *. .
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Confirmatory Items (Cl)
~ ,,, ' ~ .~ 4 .. * ..
RAI NRC Cl Summary Description . .
Question# " .
- Ii 10.3.6-1 r: Request to re-indude text related to the FAC program into COL Item 10.3- !
1 3 55 0.0 .o - ::_ 10.3.6-3 !i 2 and Section 10.3.6.3. The DCA was revised as requested. !
Request to revise FSAR Tier 2, Section 10.3.6 to only discuss the non-10.03.06-6 None safety related portions of the steam and power conversion systems. The DCAwas revised as requested.
' ]j \: Request to revi~~-th~ DCD t~-i~~l-ud~-i~~tifi~ati~~--de~c~-ib-i~g-h~w-th~ ------ 1 10.03.06-7 10.3.6-2 i' NuScale SG program meets NEI 97-6 and EPRI SG management
- ! program guidan~~'._T_~~-'?CA was revised a~ ~~9_ue~~e~._ l
-- ---____ I Request to explicitly include EPRI Action Levels for secondary water 10.04.06-7 None chemistry into COL Item 10.3-1. NuScale considered the COL item adequate as written .
. Request to include additional discussion on the role of maintenance and Conference :!
Call ,; 10.4.7-1 :* operating procedures on minimizing the occurrence of water hammer. The i
'.* DCA was revised as requested.
Request to remove Table 10.4-22 and specify that tanks are constructed Conference 10.4.11-1 of corrosion resistant materials compatible with chemicals used. The DCA Call was revised as requested.
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RAls
- Unresolved Closed Question# Summary Desc~iption .* . .* ,
" . ~ " ,_ ~ . ~ . . .- - .- ~ " '
r - - * ----- ----- --- - ---.,---- ------------ ----- ------- ----- - - -- -*-- -----* - --------------------- ------- ---- -* **---*- - .... -- -** --- . -------- --------- --------- -------- .. ---- - - - - - - - - - ---- - ----------i
- 10.02-1 !: TGS - turbine overspeed trip setpoint, single failure criteria and protection against J
- (: common cause failures
_J,_ - - - - - -- * - -- --------- - *-- - ---
i, 10.02-2 TGS - overspeed trip system diversity, defense-in-depth, trip logic, common components and impact of component failures
'. 10.02.03-1 !f I!
Request for ITAAC related to turbine rotor integrity/turbine missiles - - * * - - 1 10.02.03-2 Request for COL item related to a turbine inspection and testing program
- Waiting for Response/Supplemental Qtlestion # S~mmary Descriptio~ . * -: * *. *:_. . . . .
- 10.04.07-3 !; Request for COL item to pr~vide operating and maintenance procedures*t~---;dd~e-~;---*:
1
_ __ __ !/ __ water ham~er issu_esJor th_e CF'JYS _ ____ _ _____ _________ __]
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Portland Office Richland Office 6650 SW Redwood Lane, 1933 Jadwin Ave., Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541. 360. 0500 971.371.1592 Arlington Office Corvallis Office 2300 Clarendon Blvd., Suite 1110 1100 NE Circle Blvd., Suite 200 Arlington, VA 22201 Corvallis, OR 97330 541. 360. 0500 London Office 1st Floor Portland House Rockville Office Bressenden Place 11333 Woodglen Ave., Suite 205 London SW1 E 5BH Rockville, MD 20852 United Kingdom 301. 770.0472 +44 (0) 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980.349.4804 http://www.nuscalepower.com
'!I Twitter: @NuScale_Power NUSCALE' Power for all humankind 24 PM-0219-64501 Revision: O Copyright 2019 by NuScale Power, LLC.
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Backup Slides 25 PM-0219-64501 Revision: 0 Copyright 2019 by NuScale Power, LLC.
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Heat Balance Figure 10.1-2: Flow Diagram and Heat Balance Diagram at Rated Power for Steam and Power Conversion System Cycle
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