ML20197A388

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Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 02 - Site Characteristics and Site Parameters - Sections 02.00 - 02.05 (Rev. 4.1)
ML20197A388
Person / Time
Site: NuScale
Issue date: 06/19/2020
From: Bergman T
NuScale
To:
Office of Nuclear Reactor Regulation
Cranston G
References
NUSCALESMRDC, NUSCALESMRDC.SUBMISSION.12, NUSCALEPART02.NP, NUSCALEPART02.NP.5
Download: ML20197A388 (25)
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NuScale Standard Plant Design Certification Application Chapter Two Site Characteristics and Site Parameters PART 2 - TIER 2 Revision 4.1 June 2020

©2020, NuScale Power LLC. All Rights Reserved

COPYRIGHT NOTICE This document bears a NuScale Power, LLC, copyright notice. No right to disclose, use, or copy any of the information in this document, other than by the U.S. Nuclear Regulatory Commission (NRC), is authorized without the express, written permission of NuScale Power, LLC.

The NRC is permitted to make the number of copies of the information contained in these reports needed for its internal use in connection with generic and plant-specific reviews and approvals, as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by NuScale Power, LLC, copyright protection notwithstanding. Regarding nonproprietary versions of these reports, the NRC is permitted to make the number of additional copies necessary to provide copies for public viewing in appropriate docket files in public document rooms in Washington, DC, and elsewhere as may be required by NRC regulations. Copies made by the NRC must include this copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

NuScale Final Safety Analysis Report Table of Contents TABLE OF CONTENTS CHAPTER 2 SITE CHARACTERISTICS AND SITE PARAMETERS . . . . . . . . . . . . . . . . . . . . . . .2.0-1 2.0 Site Characteristics and Site Parameters. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-1 2.1 Geography and Demography. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.2 Nearby Industrial, Transportation, and Military Facilities . . . . . . . . . . . . . . . . . . . . . . 2.2-1 2.3 Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.3.1 Regional Climatology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.3.2 Local Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.3.3 Onsite Meteorological Measurements Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.3.4 Short-Term Atmospheric Dispersion Estimates for Accident Releases . . . . . . . . . 2.3-2 2.3.5 Long-Term Atmospheric Dispersion Estimates for Routine Releases . . . . . . . . . . 2.3-2 2.3.6 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-3 2.4 Hydrologic Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.1 Hydrologic Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.2 Floods. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.4 Potential Dam Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.5 Probable Maximum Surge and Seiche Flooding. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.6 Probable Maximum Tsunami Hazards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.7 Ice Effects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.4.8 Cooling Water Canals and Reservoirs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.9 Channel Diversions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.10 Flood Protection Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.11 Low Water Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.12 Groundwater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.13 Accidental Releases of Radioactive Liquid Effluents in Groundwater and Surface Waters. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-2 2.4.14 Technical Specifications and Emergency Operation Requirements. . . . . . . . . . . . 2.4-3 2.5 Geology, Seismology, and Geotechnical Engineering . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 2.5.1 Basic Geologic and Seismic Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 2.5.2 Vibratory Ground Motion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 2.5.3 Surface Faulting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 2.5.4 Stability of Subsurface Materials and Foundations . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 Tier 2 i Revision 4.1

NuScale Final Safety Analysis Report Table of Contents TABLE OF CONTENTS 2.5.5 Stability of Slopes. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-2 2.5.6 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-3 Tier 2 ii Revision 4.1

NuScale Final Safety Analysis Report List of Tables LIST OF TABLES Table 2.0-1: Site Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-2 Tier 2 iii Revision 4.1

NuScale Final Safety Analysis Report List of Figures LIST OF FIGURES Figure 2.3-1: Limiting Analytical Distance to EAB and LPZ Outer Boundary . . . . . . . . . . . . . . . . . . . 2.3-4 Figure 2.3-2: Source to Control Building Door Distances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-5 Figure 2.3-3: Source to Control Building HVAC Intake Distance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-6 Tier 2 iv Revision 4.1

NuScale Final Safety Analysis Report Site Characteristics and Site Parameters CHAPTER 2 SITE CHARACTERISTICS AND SITE PARAMETERS 2.0 Site Characteristics and Site Parameters The NuScale Power Plant design assumes site parameters that are representative of a reasonable number of potential plant site locations in the United States. A summary of these parameters is provided in Table 2.0-1.

COL Item 2.0-1: A COL applicant that references the NuScale Power Plant design certification will demonstrate that site-specific characteristics are bounded by the site parameters specified in Table 2.0-1. If site-specific values are not bounded by the values in Table 2.0-1, the COL applicant will demonstrate the acceptability of the site-specific values in the appropriate sections of its combined license application.

Tier 2 2.0-1 Revision 4.1

Tier 2 NuScale Final Safety Analysis Report Table 2.0-1: Site Parameters Site Characteristic Site Parameter References to Parameter Geography and Demography (Section 2.1)

Minimum exclusion area boundary 400 feet from the closest release point Sections 2.1 and 2.3.4 Minimum outer boundary of low population zone 400 feet from the closest release point Sections 2.1 and 2.3.4 Nearby Industrial, Transportation, and Military Facilities (Section 2.2)

External hazards on plant systems, structures, and No external hazards Section 2.2 components (SSC) (e.g., explosions, fires, release of toxic chemicals and flammable clouds, pressure effects) on plant SSC Aircraft hazards on plant SSC No design basis aircraft hazards Sections 2.2 and 3.5.1.6 Meteorology (Section 2.3)

Maximum precipitation rate 19.4 inches per hour Sections 3.4.2.2 and 3.8.4.3.10 6.3 inches for a 5 minute period Normal roof snow load 50 psf Sections 3.4.2.2, 3.8.4.3.10, 3.8.4.3.11, 3.8.4.3.16, 3.8.4.4.1, 3.8.4.4.2, 3.8.4.8, and 3.8.5.5.5 Extreme roof snow load 75 psf Sections 3.4.2.2, 3.8.4.3.10, 3.8.4.3.12, 3.8.4.3.16, 3.8.4.4.1, 3.8.4.4.2, 3.8.4.8, and 3.8.5.5.5 2.0-2 100-year return period 3-second wind gust speed 145 mph (Exposure Category C) with an importance factor of Sections 3.3.1.1, 3.8.4.3.13, and 3.8.4.8 1.15 for Reactor Building, Control Building, and Radioactive Waste Building Design basis tornado Sections 3.1.1.2, 3.3.2.1, 3.3.2.2, 3.3.2.3, maximum wind speed 230 mph 3.8.4.3.14, and 3.8.4.8 translational speed 46 mph maximum rotational speed 184 mph radius of maximum rotational speed 150 ft pressure drop 1.2 psi Site Characteristics and Site Parameters rate of pressure drop 0.5 psi/sec Tornado missile spectra Table 2 of Regulatory Guide 1.76, Revision 1, Region 1 Sections 3.3.2.3, 3.5.1.4, 3.5.2, 3.5.3.1, and 3.5.3.2 Maximum wind speed design basis hurricane Sections 3.1.1.2, 3.3.2.1, 3.3.2.2, 3.3.2.3, 290 mph 3.8.4.3.14, and 3.8.4.8 Hurricane missile spectra Tables 1 and 2 of Regulatory Guide 1.221, Revision 0 Section 3.5.1.4, 3.3.2.3, 3.5.2, 3.5.3.1, and 3.5.3.2 Revision 4.1

Table 2.0-1: Site Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic Site Parameter References to Parameter Accident release /Q values at exclusion area boundary and outer boundary of low population zone 0-2 hr 6.22E-04 s/m3 Sections 15.0.3.2 and 15.0.3.3.11; Table 15.0-13 2-8 hr 5.27E-04 s/m3 8-24 hr 2.41E-04 s/m3 24-96 hr 2.51E-04 s/m3 96-720 hr 2.46E-04 s/m3 Accident release /Q values at main control room/technical Door HVAC Intake support center door and HVAC intake 0-2 hr 6.50E-03 s/m3 6.50E-03 s/m3 Section 15.0.3.3.11; Table 15.0-13 2-8 hr 5.34E-03 s/m3 5.34E-03 s/m3 8-24 hr 2.32E-03 s/m3 2.32E-03 s/m3 1-4 day 2.37E-03 s/m3 2.37E-03 s/m3 4-30 day 2.14E-03 s/m3 2.14E-03 s/m3 Routine release /Q and D/Q values at restricted area 2.0-3 boundary undepleted/no decay 1.44E-05 s/m3 Tables 11.3-5 and 11.3-6 undepleted/2.26-day decay 1.44E-05 s/m3 depleted/8.00-day decay 1.44E-05 s/m3 D/Q 1.44E-07 1/m2 Zero percent exceedance values (historical limit excluding Sections 3.8.4.3.8, 3.8.4.8, 9.4.1.1, 20.1.1.4, and peaks <2 hours) 20.1.1.5; Table 9.4.1-1 Site Characteristics and Site Parameters Maximum outdoor design dry bulb temperature 115°F Maximum coincident wet bulb temperature 80°F Maximum non-coincident wet bulb temperature 81°F Minimum outdoor design dry bulb temperature -40°F One percent annual exceedance values Section 9.2.7.2.1; Tables 9.2.7-1, 9.4.2-1, 9.4.3-1, Maximum outdoor design dry bulb temperature 100°F and 10.4-9 Maximum coincident wet bulb temperature 77°F Maximum non-coincident wet bulb temperature 80°F Revision 4.1 Minimum outdoor design dry bulb temperature -10°F

Table 2.0-1: Site Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic Site Parameter References to Parameter Five percent annual exceedance values Table 9.4.4-1 Maximum outdoor design dry bulb temperature 95°F Maximum coincident wet bulb temperature 77°F Minimum outdoor design dry bulb temperature -5°F Hydrologic Engineering (Section 2.4)

Maximum flood elevation 1 foot below the baseline plant elevation Sections 2.4.2 and 3.4.2.1; Table 3.8.5-8 Probable maximum flood and coincident wind wave and other effects on max flood level Maximum elevation of groundwater 2 feet below the baseline plant elevation Sections 2.4.12, 3.4.2.1, 3.8.4.3.22.1, and 3.8.4.8; Table 3.8.5-8 Geology, Seismology, and Geotechnical Engineering (Section 2.5)

Ground motion response spectra /safe shutdown earthquake See Figures 3.7.1-1 and 3.7.1-2 for horizontal and vertical Sections 3.7.1.1, 3.8.4.3.16, and 3.8.4.8 certified seismic design response spectra (CSDRS) for all Seismic Category I SSC.

See Figures 3.7.1-3 and 3.7.1-4 for horizontal and vertical high frequency certified seismic design response spectra (CSDRS-HF) for Reactor Building and Control Building.

2.0-4 Fault displacement potential No fault displacement potential Section 2.5.3 Minimum soil bearing capacity (Qult) beneath safety-related 75 ksf Sections 2.5.4, 3.8.5.6.3, and 3.8.5.6.7 structures Lateral soil variability Uniform site (< 20 degree dip) Section 2.5.4 Minimum soil angle of internal friction 30 degrees Sections 2.5.4 and 3.8.5.3.1; Table 3.8.5-1 Minimum shear wave velocity 1000 fps at bottom of foundation Section 2.5.4 Liquefaction potential No liquefaction potential Section 2.5.4 Coefficient of friction (CoF) between concrete foundation and 0.58 Section 2.5.4, 3.8.5.3.1, 3.8.5.4.1.2, 3.8.5.5.2, Site Characteristics and Site Parameters soil where CoF = tan () Table 3.8.5-1, Table 3.8.5-8 Coefficient of friction (CoF) between concrete 0.55 Section 2.5.4, 3.8.5.4.1.4, Table 3.8.5-8 foundation and soil (CRB nonlinear analysis)

Coefficient of friction (CoF) 0.50 Section 2.5.4, 3.8.5.4.1.2, 3.8.5.4.1.4, between walls and soil Table 3.8.5-1, Table 3.8.5-8 Revision 4.1

Table 2.0-1: Site Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic Site Parameter References to Parameter Maximum settlement for the Reactor Building, Control Building, and Radioactive Waste Building:

  • total settlement 4 inches Sections 2.5.4, 3.8.5.6.1, and 3.8.5.6.2
  • tilt settlement Maximum of 0.5 inch per 50 feet of building length or 1 inch Sections 2.5.4, 3.8.5.6.1, 3.8.5.6.2, and 3.8.5.6.4 total in any direction at any point in these structures
  • differential settlement (between Reactor Building and 0.5 inch Section 3.8.5.6.4 Control Building, and between Reactor Building and Radioactive Waste Building)

Slope failure potential No slope failure potential Section 2.5.5 2.0-5 Site Characteristics and Site Parameters Revision 4.1

NuScale Final Safety Analysis Report Geography and Demography 2.1 Geography and Demography The certified design assumes that the Exclusion Area Boundary and Low Population Zone outer boundary are as close as 400 feet from the nearest release point. This is a key site parameter and included in Table 2.0-1.

COL Item 2.1-1: A COL applicant that references the NuScale Power Plant design certification will describe the site geographic and demographic characteristics.

Tier 2 2.1-1 Revision 4.1

NuScale Final Safety Analysis Report Nearby Industrial, Transportation, and Military Facilities 2.2 Nearby Industrial, Transportation, and Military Facilities The NuScale Power Plant certified design does not postulate any hazards from nearby industrial, transportation or military facilities.

COL Item 2.2-1: A COL applicant that references the NuScale Power Plant design certification will describe nearby industrial, transportation, and military facilities. The COL applicant will demonstrate that the design is acceptable for each of these potential hazards, or provide site-specific design alternatives.

Tier 2 2.2-1 Revision 4.1

NuScale Final Safety Analysis Report Meteorology 2.3 Meteorology The NuScale Power Plant is designed using meteorological parameters that are representative of a reasonable number of potential plant site locations in the United States. These parameters are discussed below and presented in Table 2.0-1.

COL Item 2.3-1: A COL applicant that references the NuScale Power Plant design certification will describe the site-specific meteorological characteristics for Section 2.3.1 through Section 2.3.5, as applicable.

2.3.1 Regional Climatology The design maximum precipitation rate is 19.4 inches per hour and 6.3 inches for a 5 minute period. These values come from NWS HMR #52 (Reference 2.3-1) and address the majority of locations in the contiguous United States.

The design normal roof snow load is 50 psf. For the extreme roof snow load, a value of 150 percent of the normal roof snow load, or 75 psf was selected.

The design basis severe wind is a 3-second gust at 33 ft above ground for exposure category C. The wind speed (W) is 145 mph. The wind speed is increased by an importance factor of 1.15 for the design of the site independent structures. These design parameters are based upon ASCE/SEI 7-05 (Reference 2.3-4).

The parameters provided in Table 2.0-1 for the design basis tornado and tornado missiles are the most severe tornado parameters postulated for the contiguous United States as identified in RG 1.76, Rev. 1. Similarly, the parameters for the design basis hurricane and hurricane missiles are the most severe parameters postulated in RG 1.221, Rev 0.

The design basis dry-bulb and wet bulb temperatures are based on the EPRI Utility Requirements Document (Reference 2.3-2). Pertinent zero percent, and one and five percent annual exceedance values assumed in the design are provided in Table 2.0-1. The coincident wet-bulb temperature value represents the overall maximum wet bulb temperature that is coincident with the indicated dry-bulb temperature.

Regional climatology is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.3-1.

2.3.2 Local Meteorology Local meteorology is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.3-1.

2.3.3 Onsite Meteorological Measurements Programs Onsite meteorological measurement programs are site-specific and are addressed by the COL applicant as part of the response to COL Item 2.3-1.

Tier 2 2.3-1 Revision 4.1

NuScale Final Safety Analysis Report Meteorology 2.3.4 Short-Term Atmospheric Dispersion Estimates for Accident Releases Accidental Radioactive Releases Topical Report TR-0915-17565-P-A, Revision 4, (Reference 2.3-3) describes the methodology used for establishing source terms and calculating the atmospheric dispersion factors used to determine accident radiological consequences at the technical support center (TSC), main control room (MCR) and offsite locations for the NuScale Power Plant certified design.

Atmospheric dispersion factors (/Q values) are determined at the exclusion area boundary (EAB) and the low population zone (LPZ) outer boundary, which may be as close as 400 feet from the closest release point. These /Q values as well as the /Q values for the MCR were determined for various sites in the United States using a meteorological database that included multiple years of data across all regions of the United States. This approach determined that the meteorological dataset for Sacramento, California, between 1984-1986, is representative of the bounding 80th to 90th percentile of potential NuScale Power Plant construction sites in the United States. This meteorological data set was used to calculate the /Q values for the certified design.

The /Q values at the EAB and the LPZ outer boundary are listed in Table 2.0-1. These /Q values are based on the source location and path shown in Figure 2.3-1.

The /Q values used for evaluation of doses in the MCR and TSC are determined at the Control Building doors and HVAC inlet and are listed in Table 2.0-1. Figure 2.3-2 and Figure 2.3-3 show the path and distances from the Reactor Building release point to MCR door and HVAC inlet. The two source locations shown in Figure 2.3-2 and Figure 2.3-3 are the limiting source locations because they are the closest source locations to the main control room personnel doors and main control room HVAC intake. Assumptions for release point characteristics used for the /Q calculations are listed in Table 15.0-20.

The /Q values for the TSC are the same as the MCR because the TSC is located directly above the MCR and shares the same HVAC inlet and outside doors.

The COL applicant will determine site specific /Q values for the EAB, LPZ outer boundary, MCR and present that information as part of the response to COL item 2.3-1.

Hazardous Material Releases As stated in Section 2.2, the NuScale Power Plant certified design does not postulate any hazards from on-site sources or nearby industrial, transportation, or military facilities.

The COL applicant will provide discussion of site specific hazardous material releases as part of the response to COL item 2.3-1.

2.3.5 Long-Term Atmospheric Dispersion Estimates for Routine Releases Routine release atmospheric dispersion factors (/Q values) and relative deposition factor (D/Q) values at the restricted area boundary provided in Table 2.0-1 are conservatively Tier 2 2.3-2 Revision 4.1

NuScale Final Safety Analysis Report Meteorology estimated and used to calculate release concentrations for comparison to the activity release limits in 10 CFR 20, as discussed in Section 11.3.

Routine release atmospheric dispersion factors (/Q values) and deposition factor (D/Q) values in unrestricted areas and at locations of interest are site-specific and are developed by the COL applicant as part of the response to COL Item 2.3-1.

2.3.6 References 2.3-1 National Oceanic and Atmospheric Administration, "Application of Probable Maximum Precipitation Estimates- United States East of the 105th Meridian,"

Hydrometeorological Report Number 52, Washington DC, August 1982.

2.3-2 Electrical Power Research Institute, "Advanced Nuclear Technology: Advanced Light Water Reactor Utility Requirements Document," Rev. 13, 2014, Palo Alto, CA.

2.3-3 NuScale Power, LLC, "Accident Source Term Methodology," TR-0915-17565-P-A Revision 4.

2.3-4 American Society of Civil Engineers/Structural Engineering Institute, "Minimum Design Loads for Buildings and Other Structures," ASCE/SEI 7-05, Reston, VA, 2005.

Tier 2 2.3-3 Revision 4.1

NuScale Final Safety Analysis Report Meteorology Figure 2.3-1: Limiting Analytical Distance to EAB and LPZ Outer Boundary EAB, LPZ Turbine Building Radwaste Control Building Building Reactor Building Non-Limiting Non-Limiting Analytical /Q Analytical /Q Distance Distance Turbine Building Limiting Analytical /Q Distance (400 feet) EAB, LPZ Tier 2 2.3-4 Revision 4.1

NuScale Final Safety Analysis Report Meteorology Figure 2.3-2: Source to Control Building Door Distances

(( Withheld - See Part 9 Tier 2 2.3-5 Revision 4.1

NuScale Final Safety Analysis Report Meteorology Figure 2.3-3: Source to Control Building HVAC Intake Distance (( Withheld - See Part 9 }} Tier 2 2.3-6 Revision 4.1

NuScale Final Safety Analysis Report Hydrologic Engineering 2.4 Hydrologic Engineering The NuScale Power Plant design does not rely upon an external water supply for the ultimate heat sink or safety-related makeup water. This design reduces the influence local hydrologic features have on plant safety. Site parameters selected to represent site conditions are presented in Table 2.0-1. COL Item 2.4-1: A COL applicant that references the NuScale Power Plant design certification will investigate and describe the site-specific hydrologic characteristics for Section 2.4.1 through Section 2.4.14, except Section 2.4.8 and Section 2.4.10. 2.4.1 Hydrologic Description The local hydrology is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.2 Floods The design assumes that the maximum flood elevation (including wind-induced wave run-up) is one foot below baseline plant elevation. The baseline plant elevation is the top of concrete of the ground floor of the Reactor Building. This maximum flood elevation is a key design parameter. The potential for flooding is site-specific and is addressed by the COL applicant as part of part of the response to COL Item 2.4-1. 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers The probable maximum flood (PMF) is site-specific and is addressed by the COL as part of the response to COL Item 2.4-1. 2.4.4 Potential Dam Failures The presence of onsite, upstream, and downstream water control structures is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.5 Probable Maximum Surge and Seiche Flooding The potential for surge or seiche flooding is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.6 Probable Maximum Tsunami Hazards The potential for tsunamis is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.7 Ice Effects The design does not rely upon a safety-related intake structure as a makeup source for the reactor pool, which acts as the ultimate heat sink. Therefore, ice effects do not affect safety Tier 2 2.4-1 Revision 4.1

NuScale Final Safety Analysis Report Hydrologic Engineering related cooling. The potential for ice effects to contribute to flooding is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.8 Cooling Water Canals and Reservoirs The design does not rely upon safety-related cooling water canals or reservoirs as a makeup source for the reactor pool, which acts as the ultimate heat sink. 2.4.9 Channel Diversions The design does not rely upon a safety-related makeup water source. Therefore, upstream channel diversions would not adversely affect safety-related cooling. The potential for channel diversions to contribute to flooding is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.10 Flood Protection Requirements The design assumes that the baseline plant elevation is one foot above the maximum flood level. Therefore there are no flood protection requirements. 2.4.11 Low Water Considerations The design does not rely upon a safety-related source of makeup water. Low flow from surges, seiches, tsunamis, downstream dam failures, future water controls, ice effects, upstream channel diversions, or other sources of low water would not adversely affect safety-related cooling. The potential effects of low water levels on nonsafety-related water supplies is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.12 Groundwater The design does not employ a permanent dewatering system. Groundwater is assumed to be a minimum of two feet below site grade. High groundwater has an adverse effect on stability. This is a key design parameter. Groundwater is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. 2.4.13 Accidental Releases of Radioactive Liquid Effluents in Groundwater and Surface Waters Dilution factors, dispersion coefficients, flow velocities, travel times, adsorption, and pathways of liquid contaminants for radioactive liquid effluents from accidental releases into groundwater or surface water is site-specific and is addressed by the COL applicant as part of the response to COL Item 2.4-1. The source term provided in Table 12.2-10 associated with the pool surge control system storage tank is assumed to be contained by the passive and durable mitigative design feature (a metal-lined concrete catch basin) in an analysis to evaluate the effects of an accidental release of radioactive liquid as part of the Tier 2 2.4-2 Revision 4.1

NuScale Final Safety Analysis Report Hydrologic Engineering response to COL Item 2.4-1 demonstrating the adequacy of the sites hydrogeologic properties. 2.4.14 Technical Specifications and Emergency Operation Requirements The design does not require emergency protective measures to minimize the impact of adverse hydrology-related events on safety-related facilities. Site-specific emergency protective measures are addressed by the COL applicant as part of the response to COL Item 2.4-1. Tier 2 2.4-3 Revision 4.1

NuScale Final Safety Analysis Report Geology, Seismology, and Geotechnical Engineering 2.5 Geology, Seismology, and Geotechnical Engineering The NuScale Power Plant is designed using geologic, seismologic, and geotechnical engineering parameters that are representative of a reasonable number of potential plant site locations in the United States. These parameters are presented in Table 2.0-1. COL Item 2.5-1: A COL applicant that references the NuScale Power Plant design certification will describe the site-specific geology, seismology, and geotechnical characteristics for Section 2.5.1 through Section 2.5.5, below. 2.5.1 Basic Geologic and Seismic Information Basic regional and site geologic and seismic information is site-specific and addressed by the COL applicant as part of the response to COL Item 2.5-1. 2.5.2 Vibratory Ground Motion There are two design basis earthquakes for the evaluation of structures that are included in the certified design: the certified seismic design response spectra (CSDRS) and the certified seismic design response spectra - high frequency (CSDRS-HF). These spectra were developed by reviewing earthquake design data from the U.S. nuclear industry and are intended to bound most of the central and eastern U.S. as well as sites in less seismically active portions of the western U.S. The CSDRS and CSDRS-HF are discussed in Section 3.7.1. The CSDRS is shown in Figure 3.7.1-1 and Figure 3.7.1-2. The CSDRS-HF is shown in Figure 3.7.1-3 and Figure 3.7.1-4. The CSDRS and CSDRS-HF are key design parameters. Local vibratory ground motion, including development of a safe shutdown earthquake is site-specific and addressed by the COL applicant as part of the response to COL Item 2.5-1. 2.5.3 Surface Faulting The design analysis assumes that there is no fault displacement potential under the plant structures. This assumption is a key design parameter. Detailed surface and subsurface geological, seismological, and geophysical information, including surface faulting, is site-specific and addressed by the COL applicant as part of the response to COL Item 2.5-1. 2.5.4 Stability of Subsurface Materials and Foundations The design analysis assumes the following parameters:

  • The minimum shear wave velocity is 1000 fps. Competent material is generally considered to be in situ material having a minimum shear wave velocity of 1,000 fps.
  • The minimum ultimate bearing capacity (Qult) is 75 ksf. This bearing capacity is sufficient to provide a factor of safety greater than 3.0 for the static bearing pressure Tier 2 2.5-1 Revision 4.1

NuScale Final Safety Analysis Report Geology, Seismology, and Geotechnical Engineering and greater than 2.0 for dynamic bearing pressure. Bearing pressures for the Reactor Building and Control Building are provided in Section 3.8.5.

  • The soil column is uniform (i.e., the site layers dip less than 20 degrees). As described in NUREG/CR-0693, the use of horizontal layers for soil-structure interaction analysis is acceptable if the layers dip less than 20 degrees.
  • There is no potential for soil liquefaction. This analysis may be performed with the site-specific safe shutdown earthquake.
  • The minimum coefficient of static friction at the interfaces between the basemat and the soil is 0.58. The minimum coefficient of friction at the interface between the basemat and the soil for Control Building nonlinear analyses is 0.55. In addition, the minimum coefficient of friction between the walls and soil is 0.50. The friction is defined between concrete and clean gravel, gravel-sand mixture, or coarse sand with a friction angle of 30 degrees (Reference 2.5-1).
  • The minimum soil angle of internal friction is 30 degrees.

There are no rigid safety-related connections between the structures and no safety-related connections to other site structures. The maximum allowable total settlement at any foundation node is 4 inches and a maximum allowable differential settlement between the Reactor Building and Control Building, and between the Reactor Building and Radioactive Waste Building is 0.5 inch. A settlement tilt limit of 1 inch total or half an inch per 50 feet has been established. This tilt (< 0.1 degree) is small enough that it does not affect the structural analysis. The following are key design parameters:

  • minimum shear wave velocity
  • minimum ultimate bearing capacity
  • uniformity of soil layers
  • potential for soil liquefaction
  • minimum coefficient of static friction
  • minimum soil angle of internal friction
  • settlement tilt Characteristics of the subsurface materials are site-specific and are discussed by the COL applicant as part of the response to COL Item 2.5-1.

2.5.5 Stability of Slopes The standard plant layout assumes a uniform, graded site as shown in Figure 1.2-4. Therefore, no slope failure potential is a key design parameter. Stability of slopes on or near the site are confirmed by the COL applicant as part of the response to COL Item 2.5-1. This analysis may be performed with the site-specific safe shutdown earthquake. Tier 2 2.5-2 Revision 4.1

NuScale Final Safety Analysis Report Geology, Seismology, and Geotechnical Engineering 2.5.6 References 2.5-1 Department of the Navy, "Design Manual 7.2 - Foundation and Earth Structures," NAVFAC DM-7.2, Alexandria, VA, May 1982. Tier 2 2.5-3 Revision 4.1}}

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