ML19172A174

From kanterella
Jump to navigation Jump to search
LLC - Submittal of Changes to Final Safety Analysis Report, Section 2.5.4, Stability of Subsurface Materials and Foundations
ML19172A174
Person / Time
Site: NuScale
Issue date: 06/21/2019
From: Rad Z
NuScale
To:
Document Control Desk, Office of New Reactors
References
LO-0619-66019
Download: ML19172A174 (10)
v • d • e


Text

LO-0619-66019 June 21, 2019 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Submittal of Changes to Final Safety Analysis Report, Section 2.5.4, Stability of Subsurface Materials and Foundations

REFERENCE:

Letter from NuScale Power, LLC to Nuclear Regulatory Commission, NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 2, dated October 30, 2018 (ML18311A006)

During a May 30, 2019 email correspondence with Prosanta Chowdhury and Weijun Wang of the NRC Staff, NuScale Power, LLC (NuScale) discussed potential updates to Final Safety Analysis Report (FSAR), Section 2.5.4, Stability of Subsurface Materials and Foundations. As a result of this discussion, NuScale changed Section 2.5.4. The Enclosure to this letter provides a mark-up of the FSAR pages incorporating revisions in redline/strikeout format. NuScale will include this change as part of a future revision to the NuScale Design Certification Application.

This letter makes no regulatory commitments or revisions to any existing regulatory commitments.

If you have any questions, please feel free to contact Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Samuel Lee, NRC, OWFN-8H12 Gregory Cranston, NRC, OWFN-8H12 Prosanta Chowdhury, NRC, OWFN-8H12

Enclosure:

Changes to NuScale Final Safety Analysis Report, Section 2.5.4, Stability of Subsurface Materials and Foundations NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

LO-0619-66019

Enclosure:

Changes to NuScale Final Safety Analysis Report, Section 2.5.4, Stability of Subsurface Materials and Foundations NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

NuScale Tier 1 Site Parameters RAI 02.03.01-6, RAI 03.07.02-24S1, RAI 03.08.05-1, RAI 03.08.05-8 Table 5.0-1: Site Design Parameters Site Characteristic/Parameter NuScale Design Parameter Nearby Industrial, Transportation, and Military Facilities External hazards on plant structures, systems, and components (SSC) (e.g., explosions, fires, release of toxic chemicals and flammable clouds, pressure effects) on plant SSC No external hazards Aircraft hazards on plant SSC No design basis aircraft hazards Meteorology Maximum precipitation rate 19.4 inches per hour 6.3 inches for a 5 minute period Normal roof snow load 50 psf Extreme roof snow load 75 psf 100-year return period 3-second wind gust speed 145 mph (Exposure Category C) with an importance factor of 1.15 for Reactor Building, Control Building, and Radioactive Waste Building Design Basis Tornado maximum wind speed 230 mph translational speed 46 mph maximum rotational speed 184 mph radius of maximum rotational speed 150 ft pressure drop 1.2 psi rate of pressure drop 0.5 psi/sec Tornado missile spectra Table 2 of Regulatory Guide 1.76, Revision 1, Region 1.

Maximum wind speed design basis hurricane 290 mph Hurricane missile spectra Tables 1 and 2 of Regulatory Guide1.221, Revision 0.

Zero percent exceedance value (historical limit excluding peaks <2 hours)

Maximum outdoor design dry bulb temperature 115°F Minimum outdoor design dry bulb temperature -40°F Accident release /Q values at exclusion area boundary and outer boundary of low population zone 0-2 hr 6.22E-04 s/m3 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 support center door and heating ventilation and air Door Heating Ventilation and Air Conditioning conditioning intake Intake 0-2 hr 6.50E-03 s/m3 6.50E-03 s/m3 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 Hydrologic Engineering Maximum flood elevation Probable maximum flood and coincident wind wave and other effects on maximum flood level 1 foot below the baseline plant elevation Maximum elevation of groundwater 2 feet below the baseline plant elevation Tier 1 5.0-2 Draft Revision 3

NuScale Tier 1 Site Parameters Table 5.0-1: Site Design Parameters (Continued)

Site Characteristic/Parameter NuScale Design Parameter Geology, Seismology, and Geotechnical Engineering Ground motion response spectra/safe shutdown earthquake See Figure 5.0-1 and Figure 5.0-2 for horizontal and vertical certified seismic design response spectra (CSDRS) for all Seismic Category I SSC.

See Figure 5.0-3 and Figure 5.0-4 for horizontal and vertical high frequency certified seismic design response spectra (CSDRS-HF) for Reactor Building and Control Building.

Fault displacement potential No fault displacement potential Minimum soil bearing capacity (Qult) beneath safety-related structures 75 ksf Lateral soil variability Uniform site (< 20 degree dip)

Minimum soil angle of internal friction 30 degrees Minimum shear wave velocity 1000 fps at bottom of foundation Maximum settlement for the Reactor Building, Control Building, and Radioactive Waste Building:

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

Slope failure potential No slope failure potential Tier 1 5.0-3 Draft Revision 3

NuScale Final Safety Analysis Report Site Characteristics and Site Parameters CHAPTER 2 SITE CHARACTERISTICS AND SITE PARAMETERS 2.0 Site Characteristics and Site Parameters RAI 02.03.01-7 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 design 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 Draft Revision 3

Tier 2 NuScale Final Safety Analysis Report RAI 02.03.01-2, RAI 02.03.01-6, RAI 02.03.01-6S1, RAI 02.03.01-8, RAI 02.03.05-1S1, RAI 02.03.05-1S2, RAI 03.07.02-24S1, RAI 03.08.05-1, RAI 03.08.05-8 Table 2.0-1: Site Design Parameters Site Characteristic / Parameter NuScale Design 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, 2.0-2 3.8.4.4.1, 3.8.4.4.2, 3.8.4.8, and 3.8.5.5.5 100-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 Site Characteristics and Site Parameters pressure drop 1.2 psi 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 Draft Revision 3

Table 2.0-1: Site Design Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic / Parameter NuScale Design 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 Draft Revision 3 Maximum non-coincident wet bulb temperature 80°F Minimum outdoor design dry bulb temperature -10°F

Table 2.0-1: Site Design Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic / Parameter NuScale Design 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 Draft Revision 3

Table 2.0-1: Site Design Parameters (Continued)

Tier 2 NuScale Final Safety Analysis Report Site Characteristic / Parameter NuScale Design 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 Draft Revision 3

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 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.

RAI 03.08.05-1 Settlement is not a concern for the NuScale Power Plant design. 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 Draft Revision 3

Retrieved from "https://kanterella.com/w/index.php?title=ML19172A174&oldid=2523547"