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Category:Meeting Briefing Package/Handouts
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 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 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 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 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 ML20069A9692020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision O ML20069A1632020-03-0505 March 2020 ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 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 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 ML20054B6342020-02-17017 February 2020 Nuscale - ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident Methodology, PM-1019-67365, Revision 0 ML20054A4062020-02-17017 February 2020 ACRS Subcommittee Presentation: NuScale Topical Report- Loss-of-Coolant Accident Evaluation Model, PM-0220-68917, 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 ML19204A2772019-07-22022 July 2019 Discussion Topic July 22, 2019 Public Meeting to Discuss Interface Requirement Associated with the NuScale Design Certification Application ML19190A0882019-07-0303 July 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation, NuScale FSAR Chapter 20, Mitigation of Beyond-Design-Basis Events, PM-0719-66189, Revision 0 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 ML19134A0742019-05-0909 May 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, PM-0519-65372, Revision 0 ML19105A1352019-04-11011 April 2019 ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, 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 ML19079A2382019-03-20020 March 2019 Enclosure 1: ACRS 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 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 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 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 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 ML18205A3182018-07-24024 July 2018 NRC Staff Questions for the August 1, 2018 Public Meeting with NuScale on ITP 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) ML18090A0032018-04-0202 April 2018 Handout for the April 2, 2018 Public Meeting to Discuss NuScale Plans to Respond to the NRC Staff RAIs Related to Sections 3.7 and 3.8 ML18085A0722018-03-26026 March 2018 NRC Staff Questions for April 9, 2018 Public Meeting with NuScale on DCA Chapter 20 ML18037A6732018-02-0808 February 2018 PM-0218-58480, Revision 0, Shutdown Capability of the NuScale Power Module. ML18019A1612018-01-23023 January 2018 LLC - Shutdown Capability of the NuScale Power Module ML18019A1632018-01-23023 January 2018 Source Term Revision, Revision 0, PM-0118-58201 2020-07-01
[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 Nuscale'S 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
[Table view] Category:Topical Report
MONTHYEARML20099H0802020-04-0808 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 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 ML19352G6972019-12-18018 December 2019 LLC Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 2 ML19319C7872019-11-15015 November 2019 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 3 ML19324C8392019-11-13013 November 2019 LLC Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation NuScale Topical Report -Accident Source Term Methodology, PM-1119-67927, Revision 0 ML19211C9012019-07-30030 July 2019 LLC Submittal of NuFuel-HTP2 Fuel and Control Rod Assembly Designs, TR-0816-51127, Revision 2 ML19192A1662019-07-10010 July 2019 Presentation Entitled, Evaluation Methodology for Stability Analysis of the NuScale Power Module. ML19175A2992019-06-24024 June 2019 LLC Submittal of NuScale Topical Report: Quality Assurance Program Description for the NuScale Power Plant, TR-1010-859-NP, Revision 4 ML19136A3322019-05-16016 May 2019 LLC Submittal of Changes to the Pipe Rupture Hazards Analysis Technical Report, TR-0818-61384, Revision 1 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 ML18354B4002018-12-20020 December 2018 LLC - Submittal of Pipe Rupture Hazards Analysis, TR-0818-61384, Revision 1 ML18360A6322018-12-19019 December 2018 LLC - Submittal of Approved Version of Topical Report TR-0116-21012, NuScale Power Critical Heat Flux Corrections, Revision 1 ML18341A3372018-12-0707 December 2018 LLC Submittal of NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-0918-60894, Revision 0 ML18338A0312018-12-0404 December 2018 Final Safety Evaluation for NuScale Power, TR-0915-17564-P, Subchannel Analyses Methodology, Revision 2 ML18310A1542018-11-0505 November 2018 LLC Submittal of Fuel Storage Rack Analysis, TR-0816-49833, Revision 1 ML18096B8852018-04-0606 April 2018 LLC Submittal of Technical Report TR-1015-18177, Pressure and Temperature Limits Methodology, Revision 1 2020-04-08
[Table view] |
Text
L0-0320-69139
Enclosure:
"ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model," PM-0320-69138, Revision O 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 ACRS Full Committee Presentation N uScale Topical Report Loss-of-Coolant Accident Evaluation Model March 5, 2020 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
Revision: 0 Template#: 0000-21727-F01 R5
Presenters Matthew Presson Licensing Project Manager Dr. Pravin Sawant Supervisor Code Validation and Methods Dr. Selim Kuran Thermal Hydraulic Analyst Ben Bristol Supervisor System Thermal Hydraulics 2
PM-0320-69138 Copyright 2020 by NuScale Power, LLC. ,
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Agenda
- Background
- Regulatory Requirements
- Methodology Roadmap
- NPM Safety Systems Overview
- Element 2: Assessment Base
- Element 3: NRELAPS Evaluation Model
- Element 4: Applicability Evaluation
PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
- '""I! NUSCALE" Powo, lo, ull ""'"o">lnd Revision: 0 Template#: 0000-21727-F01 R5
Background
- Unique NPM Design Features
- Integrated design eliminates piping and limits potential breaks
- Coolant captured completely in containment, cooled and returned to RPV using a large pool as ultimate heat sink
- Simple LOCA Progression with Well-Known Phenomena
- Choked/un-choked flow through break and ECCS valves
- Core decay heat and RCS stored energy release
- CNV heat transfer to pool (condensation, conduction, convection)
- Follows Regulatory Guide 1.203 EMDAP (Table 2-1)
- Compliance with 10 CFR 50.46 and Appendix K requirements (Table 2-2) 4 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
- ~! NUSCALE" eowo, ro, ull humuntlnd Revision: 0 Template#: 0000-21727-F01 R5
Regulatory Requirements
- Max. clad temperature< 2200 °F
- Cladding oxidation > 0.17 times thickness
- Hydrogen generation < 0.01 times total hydrogen from oxidation of all cladding
- Core remains amenable to cooling
- Long-term cooling maintained
- Maximum PCT at steady state, no clad heat up
- Conservative LOCA EM Acceptance Criteria (FOMs)
- Core remains covered: collapsed level > TAF
- MCHFR > CHFR Limit (1.29)
- Containment pressure and temperature below design limit 5
PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
- "'I! NUSCALE Revision: 0 Template#: 0000-21727-F01 R5
Methodology Roadmap
- RG 1.203 EMDAP (Section 2.1 of LTR) r Element 1 Establish Requirements for EM Capabilities LOCA PIRT (LTRCh. 4) r Element3 Element2 Develop Evaluation Model Develop Assessment Base SET and IET Assessment (L TR Ch. 7)
Evaluation model (LTR Ch. 5)
\... ~ "'" Break spectrum and sensitivity calcs. (LTR Ch. 9) ~
Element4 Assess EM Adequacy Top-down and Bottom-up evaluation (LTR Ch. 8) 6 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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NPM Safety Systems
- Opens a boiling/condensing circulation flow path to transfer decay and residual heat to reactor pool
- Reactor Recirculation Valves (RRV) : 2 valves
- Reactor Vent Valves (RVV) : 3 valves
- Actuation Signals: High C NV level, 24-hour loss of AC power
- Fail safe: ECCS trip valves open on loss of DC power
- Inadvertent Actuation Block (IAB)
Reactor Vent Valves
- Prevents inadvertent opening of ECCS valves at high RCS pressure
- Actuation based on differential pressure between RPV and CNV
- Module Protection System (MPS)
- Reactor scram
- Steam Generator (SG) and Containment (CNV) Isolation
- Passive safety system activation (ECCS and DHRS)
- ---+-+- Reactor Recirculation Valves
- Passive, boiling-condensation system
- Removes heat from RCS through SG via two trains
- Each trains capable of removing 100% decay heat
- Not credited in LOCA EM NOTTO SCALE 7
PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
e ow * , la , ull h c m a ,* h" d Revision: 0 Template#: OOOQ..21727-F01 R5
Element 1 PIRT 8
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PIRT Process
- Assessment of relative importance of phenomena
- Unique phases
- Key components
- PIRT panel included recognized experts and NuScale subject matter experts
- State-of-knowledge, design description, LOCA description, NRELAPS calculations
- CHF, Collapsed level above top of the active fuel , CNV P & T
- Importance: High, Low, Medium, Inactive
- Knowledge: Well known (small uncertainty), Known (moderate uncertainty, partially known (large uncertainty), very limited 9
PM--0320-69138 Copyright 2020 by NuScale Power, LLC.
Revision : O Template#: 0000-21727-F01 R5
Spatial and Temporal Decomposition
- Phenomena identified for Systems , Structure, Components (SSCs) and LOCAphases o Phase 1a: Slowdown o Phase 1b: ECCS activation (opening)
RCS-CNV -e-ti Phase 1a hase 1b Phase 2 0
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Slowdown ECCS Actuation Flow Reversal at RRVs
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Element 2 Assessment Base 11 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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NRELAP5 Code
- RELAP5-3D©v4.1.3 used as a baseline code o Two-fluid model (thermal and mechanical non-equilibrium)for hydrodynamics with
- Non-condensable gases with gas phase
- Semi-implicit scheme for time integration o Heat conduction across 1 D geometries (slab, cylinder, sphere) o Neutron Kinetics with thermal hydraulic feedback o Special Process Models o Comprehensive control/trip system modeling
- Code configuration control and development consistent with NuScale's NQA-1 2008 / 2009a QA program
- Modifications for NRELAPS:
- NuScale specific components (e.g., helical coil SG)
- Regulatory requirements (i.e., Appendix K)
- Error correction 12 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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IET and SET Data
- Extensive database with adequate coverage of all high-ranked phenomena
- Integral effects tests (IET)
- Six (6) NIST-1 tests
- Separate effects tests (SET)
- Two (2) NIST-1 SETs
- Four (4) other NuScale SETs
- Nine (9) Legacy SETs 13 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
Pow *
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NIST-1 Facility
- Primary source of NuScale-Specific IET and SET data
- Integral Reactor Vessel with electrically heated rod bundle core, helical coil steam generator, and pressurizer Containment with HTP and Cooling Pool
- DHRS, ECCS, eves lines represented
- 700 instruments
- Sca ling Basis Power/Volume Scaling Reduced height and reduced volume scale
- Full Pressure and Temperature Same Time Scale (isochronicity) 14 PM-0320-69 138 Copyright 2020 by NuScale Power, LLC.
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Element 3 NRELAP5 NPM LOCA 15 *~ !NUSCALE .
PM-0320-69138 eowo, ro, arr humm*,rnu Copyright 2020 by NuScale Power, LLC.
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NPM LOCA Model Overview
- Analysis and Justifications
- NRELAP5 model nodalization and input options
- Time-step control
- Initial and boundarycondition biases
- Treatment of setpoints and trips
- Break location and sizes
- Single failures
- Power availability
- Methodology sensitivity calculations
- Required by Appendix K
- Phenomena-specific
- To establish conservative biases 16 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Element 4 Applicability Evaluation 17 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Applicability Evaluation
- Evaluated models and correlations (bottom-up)
- Identified dominant models/correlations for 'H' phenomena (Table 8-1 of LTR)
- Identified key model/correlation parameters and phenomenological domain where models/correlations are used (Tables 8-2 and 8-4)
- Reviewed models/correlations (Table 8-18 of LTR)
- Pedigree, Applicability range, Fidelity to SET data, Scalability
- Evaluated integral performance of EM (top-down)
- Reviewed code governing equations and numerics
- Evaluated integral performance of code using IET data (Table 8-19 of LTR)
- Evaluated IET data applicability and NRELAPS scalability
- Scaling and distortion analysis
- Differences and distortions between NPM and NIST can be accounted using NRELAP5 18 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Conclusions
- Number of conservatisms built into the NuScale LOCA EM
- 10 CFR 50 Appendix K
- Other methodology conservatisms
- Cycle independent bounding LOCA analysis
- Supported by extensive experiment database, well qualified code, and several sensitivity calculations
- Applicability evaluation consistent with RG 1.203
- Collapsed level in RPV remains above TAF
- CNV P& Tremain below design limits 19 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Appendix B to LOCALTR Extension to IORV Event 20 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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IORV Background
- Liquid space (RRV) and steam space (RVV, RSV) discharge
- Similartransient phenomena and progression
- EM Developr11ent Approach
- Compliance with DSRS for NuScale SMR Design 15.6.6
- Follows RG 1.203 EMDAP
- Element 1 (PIRT), Element 2 (Assessment), and Element4 (Applicability) remains same as LOCA EM
- Initial LOCJ~ PIRT addressed IORV
- Element 3 (NRELAPS Model) unique due to event classification 21 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Differences from LOCA EM
- Minor methodology differences given AOO classification
- MCHFR ~ Lim it(~ 1.13 high flow range, ~ 1.37 low flow range)
- Conservatisrns same as LOCA with exceptions:
- Fuel properties still biased to maximize stored energy, but additional 15°/o bias removed
- Limiting axial power shapes and radial peaking based on subchannel analysis
- Moody choked flow model for 2-phase flow choking applied to initiating valve
- Initial conditions biased to minimize MCHFR 22 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Conclusions
_* IORV is an extension of LOCA EM given similar transient phenomena and progression
- PIRT, Assessment, and Applicability same as LOCA
- Minor methodology differences for AOO classification
- Focused on conservative CHFR evaluation
- MCHFR occurs early in transient, then rapidly rises given increasing flow to power ratio
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Acronyms 1-0 one-dimensional HP high pressure 30 three-dimensional HS heat sink AC alternating current HTP heat transfer plate ANS American Nuclear Society H2TS hierarchical two-tiered scaling CCFL counter current flow limitation IAB inadvertent actuation block CHF critical heat flux IET integrated effects test CNV containment vessel INL Idaho National Laboratory eves chemical and volume control system KATHY Karlstein thermal-hydraulic test facility DC direct current kW kilowatt DCA Design Certification Application LOCA loss-of-coolant accident DHRS decay heat removal system LTR Licensing Topical Report ECCS emergency core cooling system Max maximum EM evaluation model MCHFR minim um critical heat flux ratio EMDAP evaluation model development and Min minimum assessment process Mlb/ft2 *hr pounds mass per square foot per hour FW feedwater MPS module protection system FSAR Final Safety Analysis Report MSIV main steam isolation valve FOM figure of merit NIST-1 NuScale Integral System Test Facility HL hot leg NPM NuScale Power Module 24 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Acronyms P&T pressure and temperature PCT peak cladding temperature PIRT phenomena identification and ranking table psi pounds per square inch psia pounds per square inch absolute PZR pressurizer QA Quality Assurance RCS reactor coolant system RG Regulatory Guide RRV reactor recirculation valve RPV reactor pressure vessel RW reactor vent valve SG steam generator SET separate effects test SIET Societa lnformazioni Esperienze Termoidrauliche StDev standard deviation TAF top of active fuel 25 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Portland Office Richland Office 6650 SW Red'AOOCI Lane, 1933 Jadv,in Ave., Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541. 360. 0500 971.371.1592 Charlotte Office Corvallis Office 2815 Coliseum Centre Drive, 1100 NE Circle Blvd., Suite 200 Suite 230 Corvallis, OR 97330 Charlotte, NC 28217 541.360. 0500 980. 349. 4804 Rockville Office 11333 Woodglen Ave., Suite 205 Rockville, MD 20852 301. 770.0472 http:l!WvVW.nuscalepowercom W Twtter: @NuScale_Pov..er NUSCALE TM Powe r for al l hu m ankind 26 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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Backup IORV Slides 27 PM-0320-69138 Copyright 2020 by NuScale Power, LLC.
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RRV Opening Results Sequence of Events Time (s) 1800 RRVopens 0 1600 1400 Minimum CHFR occurs 0.5
- ? 1200 Containment pressure reaches analytical limit 0.7 <I) a.
- 1000
~
Control rods begin to fall 2.7 ::J
- l 800
~
Peak steam generator pressure is reached 64 Cl.. 600 400 Remaining ECCS valves open 161 200 Minimum collapsed liquid level above the core 170 50 100 150 200 250 300 Peak containment pressure is reached 171 Time (sec)
RPV Pressure - - CNV Pressure -
Natural circulation from containment to RPV is g 35 197 ~
established 0 30 0
Cl> 25
-~
u
<( 20
§! 15 0
.c
<(
10 ai Cl> 5
...I
'C
- .:J -5
'C Cl>
<I) -1 0 a.
~
0 -15 0 50 100 150 200 250 300 0
Time_{sec)
RPV, R1ser -+--
CNV -
TAF Ref. Elevation at O ft -
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RW Opening Results 1800 Sequence of Events Time (s) 1600 RWopens 0 1400 Containment pressure reaches analytical limit 0.3 1200
~
Minimum CHFR occurs 0.3 -~ 1000 Cl)
- 5 800 Control rods begin to fall 2.3
"'"'~ 600 Peak steam generator pressure is reached 25 a..
400 Peak containment pressure is reached 52 200 Remaining ECCS valves open 3925 Natural circulation from containment to RPV is 4072 RPV Pressure --+- Time (sec) CNV Pressure -
established
~
35 Minimum collapsed liquid level above the core 4192 ...
Cl) 0 30 0
Cl) 25
.2:
ti
<( 20 Cl)
> 15
.8
<(
10 ru>
5
~
-0
- .J -5
-0 (I) ti) -10 0.
l'll 0 -15 0 0 500 1000 1500 2000 2500 3000 3500 4000 nm~{sec)
RPV, Riser - -
CNV -
TAF Ref. Elevation at Oft -
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