ML19010A408

LLC Supplemental Response to NRC Request for Additional Information No. 164 (Erai No. 8935) on the NuScale Design Certification Application

ML19010A408
Person / Time
Site:	NuScale
Issue date:	01/10/2019
From:	Rad Z NuScale
To:	Document Control Desk, Office of New Reactors
References
RAIO-0119-64103
Download: ML19010A408 (39)

Text

RAIO-0119-64103 January 10, 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 Supplemental Response to NRC Request for Additional Information No. 164 (eRAI No. 8935) on the NuScale Design Certification Application

REFERENCES:

1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 164 (eRAI No. 8935)," dated August 11, 2017

2. NuScale Power, LLC Supplemental Response to NRC "Request for Additional Information No. 164 (eRAI No.8935)," dated August 29, 2018 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) supplemental response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's supplemental response to the following RAI Question from NRC eRAI No. 8935:

03.07.02-23 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.

If you have any questions on this response, please contact Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8H12 Samuel Lee, NRC, OWFN-8H12 Marieliz Vera, NRC, OWFN-8H12 : NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 8935 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0119-64103 :

NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 8935 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

Response to Request for Additional Information eRAI No.: 8935 Date of RAI Issue: 08/11/2017 NRC Question No.: 03.07.02-23 10 CFR 50 Appendix S requires that the safety functions of structures, systems, and components (SSCs) must be assured during and after the vibratory ground motion associated with the Safe Shutdown Earthquake (SSE) through design, testing, or qualification methods.

DSRS Section 3.7.2 provides guidance that, for soil-structure interaction (SSI) analysis for deeply embedded structures, proper consideration should be given to uncertainties associated with kinematic interaction, non-vertically propagating shear waves, sidewall impedance calculation, and other effects such as the development of gaps between the soil and structure specifically for strong-motion earthquakes. For non-vertically propagating shear waves, a sensitivity evaluation can be performed to determine whether this is an important effect to be included in the SSI analysis. Staff has not been able to identify how the applicant has considered these uncertainties associated with SSI of deeply embedded structures in the seismic analysis of NuScale Category I SSCs. Provide an explanation for what analyses the applicant has performed and how these uncertainties have been considered.

NuScale Response:

The NRC provided five feedback statements on the NuScale response to RAI 8935, Question 3.07.02-23, dated August 29, 2018. A supplement to NuScale's original response is provided herein to address the NRC statements.

NuScale Nonproprietary

1) In NUREG/CR-6896 ("Assessment of Seismic Analysis Methodologies for Deeply Embedded Nuclear Power Plant Structures"; ADAMS Accession Number, ML060820521), the staff notes that non-vertically propagating SH-waves increase torsional responses of embedded structures.

However, applicants RAI response did not include analysis involving non-vertically propagating SH-waves. Staff also notes that ASCE 4-16 provides a guideline that accidental torsion be considered to address the effects of non-vertically propagating waves. Therefore, the applicant is requested to provide an evaluation of potential impact of inclined SH-waves on torsional responses of the RXB and discuss if any additional torsional responses from inclined SH-waves can be covered by the provision of accidental torsion in NuScale FSAR Section 3.7.2.11.

1.1 Response to Question 1.

The Reactor Building (RXB) design forces and moments in the Final Safety Analysis Report (FSAR) have been increased by 5 percent to include the effect of torsional eccentricity due to horizontal seismic input loading. The RXB in-structure response spectra (ISRS) are enveloped and broadened per the American Society of Civil Engineers Standard 4, "Seismic Design of Safety-Related Nuclear Structures."

Because SH-waves cause ground motion in the Y-direction, the additional torsional response due to non-vertically propagating SH-waves can be demonstrated by comparing the X-direction ISRS plots at the edges of the building. The results of the comparison are provided below.

1.1.1 Study Results for Question 1.

Results for the inclined SH (Y) waves were not included in the original request for additional information (RAI) response because the differences in response due to vertically and non-vertically propagating SH-waves are small.

To explicitly determine if there is an increase in the ISRS due to SH (Y) shaking for three inclined angles considered for studying the effect of non-vertically propagating wave input, ISRS in the X-direction are obtained at the four exterior corners of the RXB: at the foundation, ground surface, and roof elevations, and at the RXM6 north support lug. The ISRS in the X-direction due to SH (Y) shaking provide the measure of torsional response.

Comparisons of ISRS are provided at the 13 locations listed in Table 1-1. The 13 locations are shown in Figure 1-1 through Figure 1-4.

NuScale Nonproprietary

Table 1-1 Locations of ISRS Comparison Count Node X (in) Y (in) Z (in) Figure Description 1 3974 0.0 -873.0 120.0 Figures 1-5a Top of Basemat, SW and 1-5b Corner 2 3996 0.0 873.0 120.0 Figures 1-6a Top of Basemat, NW and 1-6b Corner 3 5620 4092.0 -873.0 120.0 Figures 1-7a Top of Basemat, SE and 1-7b Corner 4 5642 4092.0 873.0 120.0 Figures 1-8a Top of Basemat, NE and 1-8b Corner 5 16635 3509.5 406.5 673.73 Figures 1-9a RXM6, North Lug Support and 1-9b 6 22810 0.0 -873.0 1020.0 Figures 1-10a El. 100', RXB SW Corner and 1-10b 7 22832 0.0 873.0 1020.0 Figures 1-11a El. 100', RXB NW Corner and 1-11b 8 24054 4092.0 -873.0 1020.0 Figures 1-12a El. 100', RXB SE Corner and 1-12b 9 24076 4092.0 873.0 1020.0 Figures 1-13a El. 100', RXB NE Corner and 1-13b 10 29076 0.0 -873.0 1824.0 Figures 1-14a El. 167', Roof, SW Corner and 1-14b 11 29098 0.0 873.0 1824.0 Figures 1-15a El. 167', Roof, NW Corner and -15b 12 29343 4092.0 -873.0 1824.0 Figures 1-16a El. 167', Roof, SE Corner and 1-16b 13 29365 4092.0 873.0 1824.0 Figures 1-17a El. 167', Roof, NE Corner and 1-17b NuScale Nonproprietary

Figure 1-1. Locations of Reactor Building ISRS Comparison at Top of Basemat.

Figure 1-2. Locations of Reactor Building ISRS Comparison at RXM6 North Lug.

NuScale Nonproprietary

Figure 1-3. Locations of Reactor Building ISRS Comparison at El. 100 (Ground Surface).

Figure 1-4. Locations of Reactor Building ISRS Comparison at El. 167 (Roof).

NuScale Nonproprietary

1.1.2 Comparison of X Response ISRS due to SH-Waves at Top of Basemat Figure 1-5a through Figure 1-8b show ISRS at the top of the basemat at the SW, NW, SE, and NE corners, respectively. For comparison purposes, the X response due to SH (Y) input is plotted first, followed by the X response due to SV (X) input.

Figure 1-5a. RXB - East-West (X) ISRS, Node 3974, Top of Basemat, SW Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-5b. RXB - East-West (X) ISRS, Node 3974, Top of Basemat, SW Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-6a. RXB - East-West (X) ISRS, Node 3996, Top of Basemat, NW Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-6b. RXB - East-West (X) ISRS, Node 3996, Top of Basemat, NW Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-7a. RXB - East-West (X) ISRS, Node 5620, Top of Basemat, SE Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-7b. RXB - East-West (X) ISRS, Node 5620, Top of Basemat, SE Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-8a. RXB - East-West (X) ISRS, Node 5642, Top of Basemat, NE Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-8b. RXB - East-West (X) ISRS, Node 5642, Top of Basemat, NE Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

1.1.3 Comparison of X Response ISRS due to SH-Waves at North Lug of RXM6 Figures 1-9a and 1-9b show ISRS at the north lug of RXM6. For comparison purposes, the X response due to SH (Y) input is plotted first, followed by the X response due to SV (X) input.

Figure 1-9a. RXB - East-West (X) ISRS, Node 16635, RXM6 North Lug, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-9b. RXB - East-West (X) ISRS, Node 16635, RXM6 North Lug, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

1.1.4 Comparison of X Response ISRS due to SH-Waves at El. 100 (Ground Surface)

Figure 1-10a through Figure 1-13b show ISRS at the corners of the RXB at El. 100 at the SW, NW, SE, and NE corners, respectively. The X response due to SH (Y) input is plotted first, followed by the X response due to SV (X) input.

Figure 1-10a. RXB - East-West (X) ISRS, Node 22810, El. 100', SW Corner, Capitola Input -

X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-10b. RXB - East-West (X) ISRS, Node 22810, El. 100', SW Corner, Capitola Input -

X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-11a. RXB - East-West (X) ISRS, Node 22832, El. 100', NW Corner, Capitola Input -

X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-11b. RXB - East-West (X) ISRS, Node 22832, El. 100', NW Corner, Capitola Input -

X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-12a. RXB - East-West (X) ISRS, Node 24054, El. 100', SE Corner, Capitola Input -

X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-12b. RXB - East-West (X) ISRS, Node 24054, El. 100', SE Corner, Capitola Input -

X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-13a. RXB - East-West (X) ISRS, Node 24076, El. 100', NE Corner, Capitola Input -

X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-13b. RXB - East-West (X) ISRS, Node 24076, El. 100', NE Corner, Capitola Input -

X Response due to SV (X) Input NuScale Nonproprietary

1.1.5 Comparison of X Response ISRS due to SH-Waves at Roof Figure 1-14a through Figure 1-17b show ISRS at the roof (El. 167) at the SW, NW, SE, and NE corners, respectively. For comparison purposes, the X response due to SH (Y) input is plotted first, followed by the X response due to SV (X) input .

Figure 1-14a. RXB - East-West (X) ISRS, Node 29076, El. 167', Roof, SW Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-14b. RXB - East-West (X) ISRS, Node 29076, El. 167', Roof, SW Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-15a. RXB - East-West (X) ISRS, Node 29098, El. 167', Roof, NW Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-15b. RXB - East-West (X) ISRS, Node 29098, El. 167', Roof, NW Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-16a. RXB - East-West (X) ISRS, Node 29343, El. 167', Roof, SE Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-16b. RXB - East-West (X) ISRS, Node 29343, El. 167', Roof, SE Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

Figure 1-17a. RXB - East-West (X) ISRS, Node 29365, El. 167', Roof, NE Corner, Capitola Input - X Response due to SH (Y) Input NuScale Nonproprietary

Figure 1-17b. RXB - East-West (X) ISRS, Node 29365, El. 167', Roof, NE Corner, Capitola Input - X Response due to SV (X) Input NuScale Nonproprietary

1.1.6 Conclusion of Study Results for Question 1.

Based on the ISRS results presented in Figure 1-5a through Figure 1-17b, the effect of torsional response due to non-vertically propagating SH-waves is estimated by comparing the X-response ISRS due to SH-waves to the X-response ISRS due to SV-waves. It is concluded that it has insignificant effect on the RXB torsional responses. Therefore, increasing all RXB design forces by 5 percent to account for accidental torsion is conservative.

2) According to the literature (e.g., "Dynamic Soil Structure Interaction" by Wolf, 1985), an incident P-wave will always lead to reflected P- and SV-waves. Likewise, an incident SV-wave will always lead to a reflected SV-wave but a reflected P-wave does not exist for a sufficiently shallow incident SV-wave. The limiting angle of incidence of the SV-wave, for which a reflected P-wave still arises, is called the critical angle of incidence and is dependent on the Poissons ratio of the soil. Please clarify if the critical angle of incidence was considered in NuScales study and, if not, provide an explanation for not doing so.

1.2 Response to Question 2.

The Wolf solution is for a uniform half-space and shows that the ratio of the vertical motion to the horizontal motion becomes unstable near the critical angle. Therefore, if the horizontal motion is equal to the certified seismic design response spectra, then the vertical motion becomes very large. Initial study runs with the incident angle near the critical angle were performed with Soil Type 7 free-field only. Figure 1-18 shows the response at the surface for various angles of incidence. The solution becomes unstable close to 45 degrees of inclined incident wave angle. Because of this instability, the critical angle was not considered in the NuScale study.

NuScale Nonproprietary

Figure 1-18. Soil Type 7, X and Z Response Spectra due to SV-Waves, Capitola Input

3) The staff believes that a COL Item should be added to NuScale DCD that requires a COL applicant that references NuScale DCD should perform a site-specific evaluation of the effects of non-vertically propagating seismic waves on the free-field ground motions and seismic responses of seismic Category I structures, systems, and components.

1.3 Response to Question 3 A COL Item has been added, as shown in the attached FSAR change package.

NuScale Nonproprietary

4) In proposed FSAR markup (for Page 3.7-118, Draft Revision 2) provided in the RAI response, the applicant states, "Note that in the legends of the figures, "X/SV" means the X-response due to SV-wave input; "X/P" means the X-response due to P-wave input; "Y/SH" means the Y-response due to SH-wave input; etc." However, staff finds that a legend including "Y/SH" is not present anywhere in the RAI response. Please clarify.

1.4 Response to Question 4 Y/SH results are not included in the RAI response. The phrase 'Y/SH' means the Y-response due to SH-wave input has been deleted in the attached FSAR change package.

5) In proposed markup for Figure 3.7.2-154, ISRS in the Y (North-South) direction is presented.

The staff understands that inclined SV or P-waves produce ground motions in the X-Z plane.

Please clarify if ground motions in the Y direction shown in Figure 3.7.2-154 are produced by inclined SH-waves.

1.5 Response to Question 5 The staffs interpretation is correct, i.e., the ground motions in the Y-direction shown in FSAR Figure 3.7.2-154 are produced by inclined SH-waves.

NuScale Nonproprietary

NuScale Final Safety Analysis Report Interfaces with Certified Design RAI 01-61, RAI 02.04.13-1, RAI 03.04.01-4, RAI 03.04.02-1, RAI 03.04.02-2, RAI 03.04.02-3, RAI 03.05.01.03-1, RAI 03.05.01.04-1, RAI 03.05.02-2, RAI 03.05.03-4, RAI 03.06.02-6, RAI 03.06.02-15, RAI 03.06.03-11, RAI 03.07.01-2, RAI 03.07.01-3, RAI 03.07.02-6S1, RAI 03.07.02-6S2, RAI 03.07.02-8, RAI 03.07.02-12, RAI 03.07.02-15S5, RAI 03.07.02-23S1, RAI 03.07.02-26, RAI 03.08.04-3S2, RAI 03.08.04-23S1, RAI 03.08.04-23S2, RAI 03.08.05-14S1, RAI 03.09.02-15, RAI 03.09.02-48, RAI 03.09.02-67, RAI 03.09.02-69, RAI 03.09.03-12, RAI 03.09.06-5, RAI 03.09.06-6, RAI 03.09.06-16, RAI 03.09.06-16S1, RAI 03.09.06-27, RAI 03.11-8, RAI 03.11-14, RAI 03.11-14S1, RAI 03.11-18, RAI 03.13-3, RAI 04.02-1S2, RAI 05.02.03-19, RAI 05.02.05-8, RAI 05.04.02.01-13, RAI 05.04.02.01-14, RAI 05.04.02.01-19, RAI 06.02.01.01.A-18, RAI 06.02.01.01.A-19, RAI 06.02.06-22, RAI 06.02.06-23, RAI 06.04-1, RAI 09.01.01-20, RAI 09.01.02-4, RAI 09.01.05-3, RAI 09.01.05-6, RAI 09.03.02-3, RAI 09.03.02-4, RAI 09.03.02-5, RAI 09.03.02-6, RAI 09.03.02-8, RAI 10.02-1, RAI 10.02-2, RAI 10.02-3, RAI 10.02.03-1, RAI 10.02.03-2, RAI 10.03.06-1, RAI 10.03.06-5, RAI 10.04.06-1, RAI 10.04.06-2, RAI 10.04.06-3, RAI 10.04.10-2, RAI 11.01-2, RAI 12.03-55S1, RAI 13.01.01-1, RAI 13.01.01-1S1, RAI 13.02.02-1, RAI 13.03-4, RAI 13.05.02.01-2, RAI 13.05.02.01-2S1, RAI 13.05.02.01-3, RAI 13.05.02.01-3S1, RAI 13.05.02.01-4, RAI 13.05.02.01-4S1, RAI 14.02-7, RAI 19-31, RAI 19-31S1, RAI 19-38, RAI 20.01-13 Table 1.8-2: Combined License Information Items Item No. Description of COL Information Item Section COL Item 1.1-1: A COL applicant that references the NuScale Power Plant design certification will identify the 1.1 site-specific plant location.

COL Item 1.1-2: A COL applicant that references the NuScale Power Plant design certification will provide the 1.1 schedules for completion of construction and commercial operation of each power module.

COL Item 1.4-1: A COL applicant that references the NuScale Power Plant design certification will identify the 1.4 prime agents or contractors for the construction and operation of the nuclear power plant.

COL Item 1.7-1: A COL applicant that references the NuScale Power Plant design certification will provide site- 1.7 specific diagrams and legends, as applicable.

COL Item 1.7-2: A COL applicant that references the NuScale Power Plant design certification will list additional 1.7 site-specific piping and instrumentation diagrams and legends as applicable.

COL Item 1.8-1: A COL applicant that references the NuScale Power Plant design certification will provide a list of 1.8 departures from the certified design.

COL Item 1.9-1: A COL applicant that references the NuScale Power Plant design certification will review and 1.9 address the conformance with regulatory criteria in effect six months before the docket date of the COL application for the site-specific portions and operational aspects of the facility design.

COL Item 1.10-1: A COL applicant that references the NuScale Power Plant design certification will evaluate the 1.10 potential hazards resulting from construction activities of the new NuScale facility to the safety-related and risk significant structures, systems, and components of existing operating unit(s) and newly constructed operating unit(s) at the co-located site per 10 CFR 52.79(a)(31).

The evaluation will include identification of management and administrative controls necessary to eliminate or mitigate the consequences of potential hazards and demonstration that the limiting conditions for operation of an operating unit would not be exceeded. This COL item is not applicable for construction activities (build-out of the facility) at an individual NuScale Power Plant with operating NuScale Power Modules.

COL Item 2.0-1: A COL applicant that references the NuScale Power Plant design certification will demonstrate 2.0 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.

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

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

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

COL Item 2.4-1: A COL applicant that references the NuScale Power Plant design certification will investigate 2.4 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.

Tier 2 1.8-3 Draft Revision 3

NuScale Final Safety Analysis Report Interfaces with Certified Design Table 1.8-2: Combined License Information Items (Continued)

Item No. Description of COL Information Item Section COL Item 3.7-11: A COL applicant that references the NuScale Power Plant design certification will perform a 3.7 site-specific analysis that, if applicable, assesses the effects of soil separation. The COL applicant will confirm that the in-structure response spectra in the soil separation cases are bounded by the in-structure response spectra shown in FSAR Figure 3.7.2-107 through Figure 3.7.2-122.

COL Item 3.7-12: A COL applicant that references the NuScale Power Plant design certification will perform an 3.7 analysis that uses site-specific soil and time histories to confirm the adequacy of the fluid-structure interaction correction factor.

COL Item 3.7-13: A COL applicant that references the NuScale Power Plant design certification will perform a site- 3.7 specific analysis that assesses the effects of non-vertically propagating seismic waves on the free-field ground motions and seismic responses of seismic Category I structures, systems, and components.

COL Item 3.8-1: A COL applicant that references the NuScale Power Plant design certification will describe the 3.8 site-specific program for monitoring and maintenance of the Seismic Category I structures in accordance with the requirements of 10 CFR 50.65 as discussed in Regulatory Guide 1.160.

Monitoring is to include below grade walls, groundwater chemistry if needed, base settlements and differential displacements.

COL Item 3.8-2: A COL applicant that references the NuScale Power Plant design certification will confirm that 3.8 the site -independent Reactor Building and Control Building are acceptable for use at the designated site.

COL Item 3.8-3: A COL applicant that references the NuScale Power Plant design certification will identify local 3.8 stiff and soft spots in the foundation soil and address these in the design, as necessary.

COL Item 3.8-4: A COL applicant that references the NuScale Power Plant design certification will evaluate and 3.8 document construction aid elements such as steel beams, Q-decking, formwork, lugs, and other items that are left in place after construction, but that were not part of the certified design, to verify the construction aid elements do not have an appreciable adverse effect on overall mass, stiffness, and seismic demands of the certified building structure. The COL applicant will confirm that these left -in -place construction aid elements will not have adverse effects on safety-related structures, systems, and components per Section 3.7.2.

COL Item 3.9-1: A COL applicant that references the NuScale Power Plant design certification will provide the 3.9 applicable test procedures before the start of testing and will submit the test and inspection results from the comprehensive vibration assessment program for the NuScale Power Module, in accordance with Regulatory Guide 1.20.

COL Item 3.9-2: A COL applicant that references the NuScale Power Plant design certification will develop 3.9 design specifications and design reports in accordance with the requirements outlined under American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III (Reference 3.9-1). A COL applicant will address any known issues through the reactor vessel internals reliability programs (i.e. Comprehensive Vibration Assessment Program, steam generator programs, etc.) in regards to known aging degradation mechanisms such as those addressed in Section 4.5.2.1.

COL Item 3.9-3: A COL applicant that references the NuScale Power Plant design certification will provide a 3.9 summary of reactor core support structure ASME service level stresses, deformation, and cumulative usage factor values for each component and each operating condition in conformance with ASME Boiler and Pressure Vessel Code Section III Subsection NG.

COL Item 3.9-4: A COL applicant that references the NuScale Power Plant design certification will submit a 3.9 Preservice Testing program for valves as required by 10 CFR 50.55a.

COL Item 3.9-5: A COL applicant that references the NuScale Power Plant design certification will establish an 3.9 Inservice Testing program in accordance with ASME OM Code and 10 CFR 50.55a.

Tier 2 1.8-8 Draft Revision 3

NuScale Final Safety Analysis Report Seismic Design X-response ARS at the surface due to SV-waves for = 0°, 17°, and 30°. Note that these curves are identical because the control point is at the ground surface. The CSDRS at the rock outcrop (dashed line) is shown for reference only. All three ARS at the surface due to SV-waves for = 0°, 17°, and 30° are identical. Once coupling terms from inclined waves are considered, the motion at the foundation depth far exceeds those of the CSDRS responses. For example, see Figure 3.7.2-152. Therefore, the coupling terms from inclined waves should not be included in the response calculation in order to properly maintain the as-defined design-basis seismic inputs, the CSDRS and CSDRS-HF.

RAI 03.07.02-23, RAI 03.07.02-23S1 Note that in the legends of the figures, X/SV means the X-response due to SV-wave input; and X/P means the X-response due to P-wave input; Y/SH means the Y-response due to SH-wave input; etc. Also, when a response is referred to as CSDRS, it means the response due to the CSDRS-compatible input time history.

RAI 03.07.02-23 ISRS Results RAI 03.07.02-23 The SSI effects due to the RXB being subjected to non-vertically propagating waves are also studied. Comparisons of ISRS results for all angles of incidence with the broadened design ISRS show that there are exceedances at a few locations at narrow frequency bandwidths. These exceedances are due to the fact that the free-field within (in-layer) motions for inclined waves at depth exceed the corresponding motions from the CSDRS with vertically propagating waves, resulting in an effective SSI input motion that is higher than the CSDRS input motion. For a sample of results, see Figure 3.7.2-153 through Figure 3.7.2-155. In addition, if the complete set of time histories were used, the ISRS would smooth out and flatten.

RAI 03.07.02-23 Finally, it is concluded that combining the coupling responses due to non-vertically propagating waves can lead to overly conservative results.

The combination of the free-field responses at the foundation level due to inclined waves results in a design response spectrum which is much higher than the CSDRS.

RAI 03.07.02-23S1 COL Item 3.7-13: A COL applicant that references the NuScale Power Plant design certification will perform a site-specific analysis that assesses the effects of non-vertically propagating seismic waves on the free-field ground motions and seismic responses of seismic Category I structures, systems, and components.

Tier 2 3.7-115 Draft Revision 3