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| Issue date: | 10/31/2023 |
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NuScale US460 Plant Standard Design Approval Application Chapter Two Site Characteristics and Site Parameters Final Safety Analysis Report Revision 1
©2023, NuScale Power LLC. All Rights Reserved
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TABLE OF CONTENTS NuScale Final Safety Analysis Report Table of Contents NuScale US460 SDAA i
Revision 1 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................................................ 2.3-2 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 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..... 2.4-2 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 Deformation........................................ 2.5-1 2.5.4 Stability of Subsurface Materials and Foundations................. 2.5-1
TABLE OF CONTENTS NuScale Final Safety Analysis Report Table of Contents NuScale US460 SDAA ii Revision 1 2.5.5 Stability of Slopes........................................... 2.5-2 2.5.6 References................................................ 2.5-2
LIST OF TABLES NuScale Final Safety Analysis Report List of Tables NuScale US460 SDAA iii Revision 1 Table 2.0-1:
Site Parameters.............................................. 2.0-2
NuScale Final Safety Analysis Report Site Characteristics and Site Parameters NuScale US460 SDAA 2.0-1 Revision 1 CHAPTER 2 SITE CHARACTERISTICS AND SITE PARAMETERS 2.0 Site Characteristics and Site Parameters The NuScale Power Plant US460 standard design uses site parameters that are representative of a reasonable number of potential plant site locations in the United States. Table 2.0-1 summarizes these parameters.
COL Item 2.0-1:
An applicant that references the NuScale Power Plant US460 standard design 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 applicant will demonstrate the acceptability of the site-specific values in the appropriate sections of its license application.
NuScale Final Safety Analysis Report Site Characteristics and Site Parameters NuScale US460 SDAA 2.0-2 Revision 1 Table 2.0-1: Site Parameters Parameter Description Site Parameter References to Parameter Geography and Demography (Section 2.1)
Minimum exclusion area boundary 369 feet from the closest release point Section 2.1 and Section 2.3.4 Minimum outer boundary of low population zone 369 feet from the closest release point Section 2.1 and Section 2.3.4 Nearby Industrial, Transportation, and Military Facilities (Section 2.2)
External hazards (e.g., explosions, fires, release of toxic chemicals and flammable clouds, pressure effects) on plant structures, systems, and components (SSC)
No external hazards Section 2.2 Aircraft hazards on plant SSC No design basis aircraft hazards Section 2.2 and Section 3.5.1 Meteorology (Section 2.3)
Maximum precipitation rate 19.4 inches per hour 6.3 inches for a 5 minute period Section 3.4.2 Normal roof snow load 50 psf Section 3.4.2 and Section 3.8.4 Extreme roof snow load 75 psf Section 3.4.2 and Section 3.8.4 100-year return period 3-second wind gust speed 190 mph (Exposure Category C) with an importance factor of 1.15 for Reactor Building (RXB), Control Building (CRB), and Radioactive Waste Building (RWB)
Section 3.3.1 and Section 3.8.4 Design basis tornado maximum wind speed translational speed maximum rotational speed radius of maximum rotational speed pressure drop rate of pressure drop 270 mph 55 mph 215 mph 150 ft 1.6 psi 0.9 psi/sec Section 3.3 and Section 3.8.4 Tornado missile spectra Table 2 of Regulatory Guide 1.76, Revision 1, Region I Section 3.3, Section 3.5.1, Section 3.5.2, and Section 3.5.3 Maximum wind speed design basis hurricane 290 mph Section 3.3 and Section 3.8.4 Hurricane missile spectra Tables 1 and 2 of Regulatory Guide 1.221, Revision 0 Section 3.5.1, Section 3.3, Section 3.5.2, and Section 3.5.3 Accident release /Q values at exclusion area boundary and outer boundary of low population zone(1) 0-2 hr 8.96E-04 s/m3 Section 15.0.3 and Section 11.3.3 2-8 hr 7.41E-04 s/m3 8-24 hr 3.32E-04 s/m3 24-96 hr 3.63E-04 s/m3 96-720 hr 3.51E-04 s/m3
NuScale Final Safety Analysis Report Site Characteristics and Site Parameters NuScale US460 SDAA 2.0-3 Revision 1 Accident release /Q values at main control room personnel access doors and HVAC intake Door HVAC Intake 0-2 hr 3.50E-03 s/m3 3.50E-03 s/m3 Section 15.0.3 2-8 hr 2.83E-03 s/m3 2.83E-03 s/m3 8-24 hr 1.26E-03 s/m3 1.26E-03 s/m3 1-4 day 1.26E-03 s/m3 1.26E-03 s/m3 4-30 day 1.14E-03 s/m3 1.14E-03 s/m3 Routine release /Q and D/Q values at restricted area boundary
/Q 9.98E-06 s/m3 Section 11.3.3 D/Q 9.98E-08 1/m2 Zero percent exceedance values (historical limit excluding peaks <2 hours)
Maximum outdoor design dry bulb temperature Maximum coincident wet bulb temperature Maximum non-coincident wet bulb temperature Minimum outdoor design dry bulb temperature 115°F 80°F 81°F
-40°F Section 3.8.4 One percent annual exceedance values Maximum outdoor design dry bulb temperature Maximum coincident wet bulb temperature Maximum non-coincident wet bulb temperature Minimum outdoor design dry bulb temperature 100°F 77°F 80°F
-10°F Hydrologic Engineering (Section 2.4)
Maximum flood elevation Probable maximum flood and coincident wind wave and other effects on max flood level 1 foot below the baseline plant elevation Section 2.4.2, Section 3.4.2, and Section 3.8.5 Maximum elevation of groundwater 2 feet below the baseline plant elevation Section 2.4.12, Section 3.4.2, Section 3.8.4, and Section 3.8.5 Geology, Seismology, and Geotechnical Engineering (Section 2.5)
Ground motion response spectra/safe shutdown earthquake Figure 3.7.1-1 and Figure 3.7.1-2 show horizontal and vertical certified seismic design response spectra for Seismic Category I SSC.
Figure 3.7.1-3 and Figure 3.7.1-4 show horizontal and vertical high frequency certified seismic design response spectra - high frequency, for RXB and CRB.
Section 3.7.1.1 and Section 3.8.4 Fault displacement potential No fault displacement potential Section 2.5.3 Table 2.0-1: Site Parameters (Continued)
Parameter Description Site Parameter References to Parameter
NuScale Final Safety Analysis Report Site Characteristics and Site Parameters NuScale US460 SDAA 2.0-4 Revision 1 Minimum allowable soil bearing capacities(2)(3)
- RXB static bearing capacity
- RXB dynamic bearing capacity
- CRB static bearing capacity
- CRB dynamic bearing capacity 16 ksf 34 ksf 6 ksf 25 ksf Section 2.5.4 and Section 3.8.5 Minimum soil angle of internal friction 30 degrees Section 2.5.4 and Section 3.8.5 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) 0.58 where CoF = tan ()
Section 2.5.4 and Section 3.8.5 Maximum settlement for the RXB, CRB, and RWB
- Maximum tilt
- Maximum total settlement
- Maximum differential settlement RXB CRB RWB 0.1 inches 0.2 inches 0.3 inches per 50 feet per 50 feet(4) per 50 feet 1.5 inches 1.0 inches 1.3 inches(5) 0.2 inches 0.3 inches 0.7 inches Section 2.5.4 and Section 3.8.5 Slope failure potential No slope failure potential Section 2.5.5 Note 1: The /Q values provided are conservatively calculated based on approximately 90 percent of the exclusion area boundary distance.
Note 2: Minimum allowable soil bearing capacity is equivalent to the maximum soil bearing demand.
Note 3: Maximum static and dynamic bearing demands are obtained at the building base edges.
Note 4: For the Seismic Category I portion of the building.
Note 5: At the edge of the tunnels that extend towards the RXB.
Table 2.0-1: Site Parameters (Continued)
Parameter Description Site Parameter References to Parameter
NuScale Final Safety Analysis Report Geography and Demography NuScale US460 SDAA 2.1-1 Revision 1 2.1 Geography and Demography The NuScale Power Plant US460 standard design considers that the exclusion area boundary and low population zone outer boundary are as close as 369 feet from the nearest release point. The minimum distance to the exclusion area boundary and low population zone boundary is a key site parameter and included in Table 2.0-1.
COL Item 2.1-1:
An applicant that references the NuScale Power Plant US460 standard design will describe the site geographic and demographic characteristics.
NuScale Final Safety Analysis Report Nearby Industrial, Transportation, and Military Facilities NuScale US460 SDAA 2.2-1 Revision 1 2.2 Nearby Industrial, Transportation, and Military Facilities The NuScale Power Plant US460 standard design does not postulate hazards from nearby industrial, transportation, or military facilities.
COL Item 2.2-1:
An applicant that references the NuScale Power Plant US460 standard design will describe nearby industrial, transportation, and military facilities. The applicant will demonstrate that the design is acceptable for each of these potential hazards, or provide site-specific design alternatives.
NuScale Final Safety Analysis Report Meteorology NuScale US460 SDAA 2.3-1 Revision 1 2.3 Meteorology The NuScale Power Plant US460 standard design uses 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:
An applicant that references the NuScale Power Plant US460 standard design 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, NuScale selected a value of 150 percent of the normal roof snow load, or 75 psf.
The design basis severe wind is a 3-second gust at 33 ft above ground for exposure category C. The wind speed is 190 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 on ASCE/SEI 7-05 (Reference 2.3-2).
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 Regulatory Guide (RG) 1.76, Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants, Revision 1. The parameters for the design-basis hurricane and hurricane missiles are the most severe parameters postulated in RG 1.221, Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants, Revision 0.
The design-basis dry-bulb and wet-bulb temperatures are based on the EPRI Utility Requirements Document (Reference 2.3-3). Pertinent zero percent and one 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.
2.3.2 Local Meteorology Local meteorology is site-specific.
2.3.3 Onsite Meteorological Measurements Programs Onsite meteorological measurement programs are site-specific.
NuScale Final Safety Analysis Report Meteorology NuScale US460 SDAA 2.3-2 Revision 1 2.3.4 Short-Term Atmospheric Dispersion Estimates for Accident Releases Accidental Radioactive Releases Topical Report TR-0915-17565-P-A, Revision 4 (Reference 2.3-4) describes the methodology for establishing source terms and calculating the atmospheric dispersion factors to determine accident radiological consequences at the Technical Support Center (TSC), main control room (MCR), and off-site locations for the design.
Atmospheric dispersion factors (/Q values) are determined at the exclusion area boundary and the low population zone outer boundary, which can be as close as 369 feet from the closest release point. These /Q values as well as the /Q values for the MCR are determined for various sites in the United States using a meteorological database with multiple years of data across regions of the United States. This approach determines that the meteorological dataset for Sacramento, California, between 1984-1986, is representative of the bounding 80th to 90th percentile of potential construction sites in the United States. NuScale uses this meteorological data set to calculate the /Q values for the design.
The /Q values at the exclusion area boundary and the low population zone outer boundary are listed in Table 2.0-1.
The /Q values for evaluation of doses in the MCR and TSC are determined at the Control Building (CRB) doors and heating, ventilation, and air conditioning inlet and are listed in Table 2.0-1. The limiting distance between Reactor Building (RXB) release points and CRB openings is that from the door in the RXB west wall to the door in the CRB south wall. Assumptions for release point characteristics for /Q calculations and MCR /Q calculations are listed in tables in Section 15.0.
The /Q values for the TSC are the same as the MCR because both are located on the same floor of the CRB and share the same heating, ventilation, and air conditioning inlet and outside doors.
2.3.5 Long-Term Atmospheric Dispersion Estimates for Routine Releases NuScale uses the routine release /Q values and relative deposition factor (D/Q) values at the restricted area boundary provided in Table 2.0-1 to calculate release concentrations for comparison to the activity release limits in 10 CFR 20, as discussed in Section 11.3.
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 American Society of Civil Engineers/Structural Engineering Institute, "Minimum Design Loads for Buildings and Other Structures,"
ASCE/SEI 7-05, Reston, VA.
NuScale Final Safety Analysis Report Meteorology NuScale US460 SDAA 2.3-3 Revision 1 2.3-3 Electrical Power Research Institute, "Advanced Nuclear Technology:
Advanced Light Water Reactor Utility Requirements Document,"
Revision 13, EPRI, Palo Alto, CA, 2014.
2.3-4 NuScale Power, LLC, "Accident Source Term Methodology,"
TR-0915-17565-P-A Revision 4.
NuScale Final Safety Analysis Report Hydrologic Engineering NuScale US460 SDAA 2.4-1 Revision 1 2.4 Hydrologic Engineering The NuScale Power Plant US460 standard design does not rely on 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. Table 2.0-1 presents parameters selected to represent site conditions.
COL Item 2.4-1:
An applicant that references the NuScale Power Plant US460 standard design will investigate and describe the site-specific hydrologic characteristics for Section 2.4.1 through Section 2.4.14, except Section 2.4.8, Section 2.4.10, and Section 2.4.11.
2.4.1 Hydrologic Description The local hydrology is site-specific.
2.4.2 Floods The design assumes 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 RXB. This maximum flood elevation is a key design parameter.
2.4.3 Probable Maximum Flood on Streams and Rivers The probable maximum flood is site-specific.
2.4.4 Potential Dam Failures The presence of on-site, upstream, and downstream water control structures is site-specific.
2.4.5 Probable Maximum Surge and Seiche Flooding The potential for surge or seiche flooding is site-specific.
2.4.6 Probable Maximum Tsunami Hazards The potential for tsunamis is site-specific.
2.4.7 Ice Effects The design does not rely on 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-related cooling.
NuScale Final Safety Analysis Report Hydrologic Engineering NuScale US460 SDAA 2.4-2 Revision 1 2.4.8 Cooling Water Canals and Reservoirs The design does not rely on safety-related cooling water canals or reservoirs as a makeup source for the reactor pool, which acts as the ultimate heat sink. Therefore, cooling water canals or reservoirs do not affect safety-related cooling.
2.4.9 Channel Diversions The design does not rely on a safety-related makeup water source. Therefore, upstream channel diversions would not adversely affect safety-related cooling.
2.4.10 Flood Protection Requirements The design assumes 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.
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. Maximum elevation of groundwater is a key design parameter.
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 are site-specific. The source term provided in Table 12.2-9 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 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 nor technical specifications to minimize the impact of adverse hydrology-related events on safety-related facilities.
NuScale Final Safety Analysis Report Geology, Seismology, and Geotechnical Engineering NuScale US460 SDAA 2.5-1 Revision 1 2.5 Geology, Seismology, and Geotechnical Engineering The NuScale Power Plant US460 standard design uses 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:
An applicant that references the NuScale Power Plant US460 standard design will describe the site-specific geology, seismology, and geotechnical characteristics for Section 2.5.1 through Section 2.5.5.
2.5.1 Basic Geologic and Seismic Information Basic regional and site geologic and seismic information is site-specific.
2.5.2 Vibratory Ground Motion Two design-basis earthquakes for the evaluation of structures are included in the design: the certified seismic design response spectra (CSDRS) and the certified seismic design response spectra - high frequency (CSDRS-HF). These spectra are developed by reviewing earthquake design data from the United States nuclear industry and are intended to bound most of the central and eastern United States as well as sites in less seismically-active portions of the western United States.
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.
2.5.3 Surface Deformation The design analysis assumes there is no fault displacement potential under the plant structures. This assumption is a key design parameter.
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 considered to be in situ material having a minimum shear wave velocity of 1000 fps.
Allowable soil bearing capacities for the Reactor Building and Control Building are provided in Table 2.0-1 and Section 3.8.5.
There is no potential for soil liquefaction. This analysis can 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 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.
NuScale Final Safety Analysis Report Geology, Seismology, and Geotechnical Engineering NuScale US460 SDAA 2.5-2 Revision 1 There are no rigid safety-related connections between the structures and no safety-related connections to other site structures. The maximum allowable total settlement, maximum total settlement, maximum tilt, and maximum differential settlement values are provided in Table 2.0-1. For sites not meeting these parameters, site-specific analyses demonstrate the adequacy of the standard plant design.
The following are key design parameters:
minimum shear wave velocity minimum allowable soil bearing capacity uniformity of soil layers potential for soil liquefaction minimum coefficient of static friction minimum soil angle of internal friction tilt 2.5.5 Stability of Slopes The standard plant layout assumes a uniform, graded site. Therefore, no slope failure potential is a key design parameter.
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.