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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 NuScales 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 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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Text
L0-1218-63884 :
"Absorption Coefficient for Pool Water and Reactor Building Floor Interaction," PM-1218-63882, Revision 0, nonproprietary version 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 Absorption Coefficient for Pool Water and Reactor Building Floor Interaction Tamas Liszkai, Heqin Xu Dylan Addison, J.J. Arthur Structures and Design Analysis 12119/2018 PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Outline
_* Review overall DCA seismic methodology
- Types of models
- Workflow
- Model interfaces
- High level physics
- Unique fluid-structure-interaction (FSI) considerations
- Discuss limitation and conservatisms of DCA methodology regarding FSI
- Discuss the basis of a reasonable approach to account for FSI in sub-structure analysis
- Present results of absorption coefficient develop,ment 2
PM-1218-63882-N P Revision: 0 Copyright 2018 by NuScale Power, LLC.
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DCA Seismic Analysis
- Current methodolo gy in NuScale DCA
- provides a reasonable and conservative evaluation of seismic loads/demand
- Conforms to NRC regulatory guidelines
- Many complex interfaces between building and NPM models
- Unique design of u,timate heat sink provides challenge s for codes like SASSI
- Fluid structure interaction (FSI) plays significant role
- Large model size
- Deeply embedded structure
- Inherent conservatism of multi-step process results in high design loads 3
PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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DCA Seismic Analysis Process
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Multiple Sub-modeling
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Consequence of DCA Methodology
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Soil-Library Methodology
- NuScale submitted for review a fully-coupled FSSI methodology for frequency domain analysis (TR-0118-58005)
- Soil impedance from SASSI + ANSY S structural model +
ANSYS equation solver and post-processing
- Functionally identical to SASSI except that it overcomes the limitations associated with lack of FSI capabilities
- Uses one-step dynam ic analysis for SSI of buildings, NPMs, and pool water 7
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Observations using full FSSI Model
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Option to Include Acoustic Fluid Damping"
- Complex impedance boundary condition (BC) at the pool cut-boundary can be applied in which is the ratio between the pressure and normal particle velocity
- Development of exact BC of this kind is cumbersome and poses many challenges due to its frequency dependent nature and location dependency
- Alternatively an absorption coefficient can be used which can reasonably represent the wave dissipation at the boundary
- Absorption coefficient represents how much of the waves at the boundary are being reflected vs. absorbed
- NuScale developed a conservative approach to determine a reasonable absorption coefficient for seismic analysis of the NPM 9
PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Key Takeaways
- The use of absorption coefficient is to remedy limitations associated with sub-modeling using multiple software
- Seismic analysis other than.the NPM has no use for absorption coefficient, soil structure integratron and fluid pressure impact on building design is considered separately
- The NPM seismic 30 FSI model uses acoustic elements to correctly account for hydrodynamic mass of pool
- Acoustic pressure in absence of fluid damping has high harmonic peak which is unrealistic at resonance conditions
- Employing absorption coefficient to model dissipative phenomena is a reasonable approximation when computing structural response of NPM -
10 PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Absorption Coefficient Development 11 PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Background
- Acoustic Elements used for FSI in the transient seismic model
- RXB present in the SASSI model but not in the transient seismic model
- Acoustic surface without FSI considered "rigid wall"
- Neumann BC
- Absorption coefficient needed to account for energy absorption at acoustic element surface
- No existing data available for FSI
- Limited literature in-air data shows AC depends on material, surface, thickness, frequency, etc
- Range from 0.01 to 0.99 12 PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Methodology
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Methodology
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Methodology
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Calculation
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Calculation
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Calculation
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Calculation-
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Calculation
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Conclusion
- Iterative process to determine absorption coefficient that matches the response of the NPM at key locations with and without the surrounding building
- Absorption coefficient of 0.7 generates similar peak responses independent of NPM location
- For added conservatism a value of 0.4 is used for NPM analysis 25 PM-1218-63882-NP Revision: O Copyright 2018 by NuScale Power, LLC.
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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 26 PM-1218-63882-NP Revision: 0 Copyright 2018 by NuScale Power, LLC.
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