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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
L0-1218-63755 :
"ACRS Presentation Chapter 2 - Site Characteristics and Site Parameters," PM-1218-63753, 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 Presentation Chapter 2 -
Site Characteristics and Site Parameters J. J. Arthur, P.E.
Manager, Structures and Design Analysis
! Paul lnfanger I
I I Licensing Project Manager
.I December 18, 2018 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Purpose
- Provide FSAR Chapter 2 overview
- Site characteristics and parameters
- RAls
- SER open and confirmatory items 2
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Chapter 2 Overview
/
- Site parameters are generally consistent with past applicant precedents and 2014 EPRI Advanced LWR Utility Requirements Document 3
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Conceptual Site Layout EAB, LPZ urbine Build in 0 ad ~ste Control Building Building on -limiting
_____ d Re ctor Build in _, on -Limiting Analytical X/Q Analytical X/Q Distance urbme Building lim1tm Analytical X/Q Distance
( 00 feet) EAB, LPZ 4
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Site Design Parameters
- Design assumes site parameters representative of a reasonable number of potential plant site locations in the U.S. A summary of the parameters is in FSAR Table 2.0-1 and provided in following slides.
- COL Item 2.0-1: demonstrate site-specific characteristics are bounded by design parameters specified in Table 2.0-1. If not bounded, demonstrate acceptability of site-specific values.
5 PM-1218-63753 Revision: O Copyright 2018 by NuScale Power, LLC.
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2.1 Geography, Demography
- Minimum distance from EAB to nearest release point -
400 ft
- Minimum distance from LPZ outer boundary to nearest release point - 400 ft
- COL Item 2.1-1: describe site geographic and demographic characteristics 6
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2.2 Nearby Facilities
- No hazards from nearby industrial, transportation, or military facilities postulated
- No aircraft hazards postulated
- COL Item 2.2-1: describe nearby industrial, transportation, and military facilities; demonstrate design acceptability for each potential accident or provide site-specific design alternatives 7
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2.3 Meteorology
- Max precipitation rate [HMR (NOAA), EPRI URD]
- 19.4 inches/hr (6.3 inches for 5 min period)
- normal I extreme 50 psf / 75 psf
- 145 mph with importance factor of 1.15 for RXB, CRB, RWB
- Design basis tornado (RG 1. 76)
- max wind speed 230 mph
- translational speed 46 mph
- max rotational speed 184 mph (radius 150 ft)
- pressure drop / rate 1 .2 psi / 0 .5 psi/sec 8
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2.3 Meteorology (cont'd)
- missile spectra (RG 1.221 RO, Tables 1 & 2)
- max wind speed 290 mph
- Zero % exceeda nce values (historical limit excluding peaks < 2 hr) used for CRVS design
- max outdoor design dry bulb temp 115°F
- min outdoor design dry bulb temp -40°F
- max coincident wet bulb temp 80°F
- max non-coinc ident wet bulb temp 81°F 9
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2.3 Meteorology (cont'd) 0
- One /o exceedance values used for RBX and RWB HVAC design, and SCWS and CWS design
- max outdoor design dry bulb temp 100°F
- min outdoor design dry bulb temp -10°F
- max coincident wet bulb temp 77°F
- max non-coincident wet bulb temp 80°F
- Five% exceedance values used for TGB HVAC design
- max outdoor design dry bulb temp 95°F
- min outdoor design dry bulb temp -5°F
- max coincident wet bulb temp 77°F 10 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.3 Meteorology {cont'd)
- Atmospheric dispersion X/Q methodology based on ARCON96
- NuScale site boundary (400 ft) vs traditional LWR
(- 2,600 ft - 19,700 ft)
- NuScale applies ARCON96 methodology based on RG 1.194 for improved accuracy in predicting atmospheric dispersion for a short EAB/LPZ distance, as opposed to a PAVAN methodology based on RG 1.145, which was developed for longer distances
- Methodology described in Accident Source Term topical report Rev. 2 11 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.3 Meteorology {cont'd)
- Accident release X/Q at EAB/LPZ boundary 2 hr 6.22E-04 s/m3 8 hr 5.27E-04 s/m3 24 hr 2.41 E-04 s/m3
- 96 hr 2.51 E-04 s/m 3 720 hr 2.46E-04 s/m 3
- Accident release X/Q at MCR/TSC door and HVAC intake 2 hr 6.SOE-03 s/m 3 8 hr 5.34E-03 s/m 3 24 hr 2.32E-03 s/m 3 4 days 2.37E-03 s/m 3 30 days 2.14E-03 s/m3 12 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.3 Meteorology (cont'd)
- Routine release X/Q and D/Q (bounding offsite dose)
- undepleted/no decay 1.44E-05 s/m 3
- undepleted/2.26-day decay 1.44E-05 s/m 3
- depleted/8.00-day decay 1.44E-05 s/m 3
- D/Q 1.44E-07 l/m2
- COL Item 2.3-1: describe site-specific meteorological characteristics for Section 2.3.1 through Section 2.3.5 13 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.4 Hydrology
- Max flood elevation (EPRI URD)
- 1 ft below baseline plant elevation
- Max groundwater elevation (EPRI URD)
- 2 ft below baseline plant elevation
- COL Item 2.4-1: investigate and describe site-specific hydrologic characteristics for Section 2.4.1 through Section 2.4.14 14 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.5 Geology, Seismology
- Design uses geologic, seismologic, and geotechnical engineering parameters representative of a reasonable number of potential plant site locations in the U. S ..
- Two DBEs: CSDRS and CSDRS-HF
- Spectra bound most of central and eastern U.S., and sites in less seismically active portions of western U.S.
- Fault displacement potential none
- Min soil bearing capacity 75 ksf
- Lateral soil variability uniform ( < 20° dip)
- Min internal friction soil angle 30°
- Min shear wave velocity > 1000 fps .
15 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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2.5 Geology, Seismology (cont'd)
- Liquefaction potential none
- Max settlement for RXB, CRB, RWB
- Total 4inches
- Tilt . 0.5 inch per 50 ft of building length or 1 inch total in any direction
- Differential 0.5 inch (RXB-CRB, RXB-RWB)
- Slope failure potential none
- COL Item 2.5-1: describe the site-specific geology, seismology, and geotechnical characteristics for Section 2.5.1 through Section 2.5.5 16 PM-1218-63753 Revision: 0 ' Copyright 2018 by NuScale Power, LLC.
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RAIS
- ----~~-- ----:-~~ ~*----i FSAR Resolv~ esolved Suppl Resp
- RAIS Confirmatory Section Closed ~losed In Eval 2.3 5 2.4 1
~~ 5 1
- Unresolved Closed issue involves analysis of accidental release of radioactive liquid effluents in groundwater and sutiace water using BTP 11-6 methodology and guidance (RAI 8750 Question 02.04.13-1) 17 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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SER Open Item 02.03.04-1
- Acceptability of method for calculating accident offsite X/Q values for EAB and LPZ, which is the outer boundary from the AST topical report TR-0915-17565 18 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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SER Confirmatory Item 02.03.04-1
- Use "EAB and Outer Boundary of the LPZ" instead of "Security Owner Controlled Area Fence" and "Site Owner Controlled Area Fence"
- Changes incorporated in DCD Rev. 2.
19 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Abbreviations ASCE/SEI -American Society of Civil Engineers/Structural Engineering Institute AST - accident source term COL - combined license CRB - Control Building CRVS - normal control room HVAC system CSDRS - certified seismic design response spectra CSDRS-HF - CSDRS - high frequency CWS - circulating water system DCD - Design Control Document EAB - exclusion area boundary 20 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Abbreviations {cont'd)
EPRI - Electric Power Research Institute FSAR - Final Safety Analysis Report HMR - Hydrometeorological Report HVAC - heating ventilation and air conditioning LPZ - low population zone LWR - light water reactor MCR - main control room NOAA - National Oceanic and Atmospheric Administration RAI - request for additional information RG - Regulatory Guide 21 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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Abbreviations (cont'd)
RWB - Radioactive Waste Building RXB - Reactor Building SER - Safety Evaluation Report sews - site cooling water system TGB - Turbine Generator Building TSC - technical support center URD - Utility Requirements Document 22 PM-1218-63753 Revision: 0 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
~ Twitter: @NuScale_Power NUSCALE' Power for all humankind 23 PM-1218-63753 Revision: 0 Copyright 2018 by NuScale Power, LLC.
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