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LLC Submittal of US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1
	ML24327A036
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Site:	05200050
Issue date:	11/22/2024
From:	Shaver M; NuScale
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
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	LO-175558 TR-121515, Rev 1
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LO-175558 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com November 22, 2024 Docket No.52-050 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 US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1

REFERENCE:

NuScale letter to NRC, NuScale Power, LLC Submittal of the NuScale Standard Design Approval Application, Revision 1, dated October 31, 2023 (ML23304A330)

NuScale Power, LLC (NuScale) hereby submits Revision 1 of the US460 NuScale Power Module Seismic Analysis, (TR-121515). This revision includes changes made during the Standard Design Approval Application audit. The next revision of the Standard Design Approval Application (Revision 2) will reference this revision of TR-121515. contains the proprietary version of the report entitled, US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1. NuScale requests that the proprietary version be withheld from public disclosure in accordance with the requirements of 10 CFR § 2.390. The enclosed affidavits (Enclosures 3 and 4) support this request. has also been determined to contain Export Controlled Information. This information must be protected from disclosure per the requirement of 10 CFR Part 810. pertains to the NuScale proprietary information, denoted by double braces (i.e., ((). Enclosure 4 pertains to the Framatome Inc. proprietary information, denoted by brackets (i.e., [ ]). Enclosure 2 contains the nonproprietary version of the report. This letter makes no regulatory commitments and no revisions to any existing regulatory commitments. If you have any questions, please contact Elisa Fairbanks at 541-452-7872 or at efairbanks@nuscalepower.com. I declare under penalty of perjury that the foregoing is true and correct. Executed on November 22, 2024. Sincerely, Mark W. Shaver Director, Regulatory Affairs NuScale Power, LLC

LO-175558 Page 2 of 2 11/22/2024 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com Distribution: Mahmoud Jardaneh, Chief, New Reactor Licensing Branch, NRC Getachew Tesfaye, Senior Project Manager, NRC Prosanta Chowdhury, Senior Project Manager, NRC

US460 NuScale Power Module Seismic Analysis, TR-121515-P, Revision 1, Proprietary Version : US460 NuScale Power Module Seismic Analysis, TR-121515-NP, Revision 1, Nonproprietary Version : Affidavit of Mark W. Shaver, AF-175559 : Affidavit of Morris Byram, Framatome Inc.

LO-175558 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com US460 NuScale Power Module Seismic Analysis, TR-121515-P, Revision 1, Proprietary Version

LO-175558 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com US460 NuScale Power Module Seismic Analysis, TR-121515-NP, Revision 1, Nonproprietary Version

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Licensing Technical Report © Copyright 2024 by NuScale Power, LLC i US460 NuScale Power Module Seismic Analysis November 2024 Revision 1 Docket: 52-050 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 www.nuscalepower.com © Copyright 2024 by NuScale Power, LLC

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Licensing Technical Report © Copyright 2024 by NuScale Power, LLC ii REVISION HISTORY Revision Date Notes 0 December 2022 Initial Issuance 1 Major revision in response to RAI 10111 Question 3.9.2-1. Change bars are not provided.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Licensing Technical Report © Copyright 2024 by NuScale Power, LLC iii COPYRIGHT NOTICE This report has been prepared by NuScale Power, LLC and bears a NuScale Power, LLC, copyright notice. No right to disclose, use, or copy any of the information in this report, 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 this report that is necessary 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 copies necessary 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 and contain the proprietary marking if the original was identified as proprietary.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Licensing Technical Report © Copyright 2024 by NuScale Power, LLC iv Department of Energy Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0008928. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Table of Contents © Copyright 2024 by NuScale Power, LLC v Abstract................................................................... 1 Executive Summary.......................................................... 2 1.0 Introduction.......................................................... 3 1.1 Purpose.............................................................. 3 1.2 Scope................................................................ 3 1.3 Abbreviations and Definitions.............................................. 4 2.0 Background.......................................................... 6 2.1 Layout of the NuScale Power Module and Reactor Building...................... 6 2.2 Load Path for Core Support............................................... 6 2.3 Regulatory Requirements................................................ 7 3.0 Analytical Methodology................................................. 8 3.1 Main Components of NuScale Power Module................................. 8 3.2 Analytical Representation of NuScale Power Module........................... 8 3.3 Simplified NuScale Power Module Model.................................... 9 3.4 Detailed NuScale Power Module Model..................................... 11 3.4.1 Containment Vessel and Wall...................................... 18 3.4.2 Piping Inside Containment......................................... 33 3.4.3 Piping Outside Containment........................................ 41 3.4.4 Top Support Structure............................................ 50 3.4.5 Reactor Pressure Vessel.......................................... 52 3.4.6 Reactor Vessel Internals.......................................... 60 3.4.7 Control Rod Drive Mechanism Assembly and Support Structures........... 75 3.4.8 Core Support Mounting Bracket..................................... 83 3.4.9 Fritz Elements for Hydrodynamic Masses............................. 83 3.4.10 Final Combined Model............................................ 85

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Table of Contents © Copyright 2024 by NuScale Power, LLC vi 3.5 Soil-Structure Interaction Harmonic Analysis of Double Building with Detailed NuScale Power Module Model............................................ 95 3.6 NuScale Power Module - Ultimate Heat Sink Model........................... 96 3.6.1 Preparation of NPM-UHS Model.................................... 96 3.6.2 Pool Sloshing................................................... 97 3.6.3 Detailed NuScale Power Module Model with the Liner Elastic Interior Components Represented with a Superelement........................ 97 3.7 Preparation and Processing of Input Acceleration Time Histories for NuScale Power Module - Ultimate Heat Sink Transient Analysis......................... 98 3.8 Nonlinear Transient Analysis............................................. 99 3.8.1 Rayleigh Damping.............................................. 100 3.8.2 Linear Transient Analysis versus Harmonic Analysis.................... 101 3.8.3 Contact - Target Settings......................................... 101 4.0 Calculation Body.................................................... 102 4.1 Verification of the Simplified NuScale Power Model with Superelements.......... 102 4.2 Verification of the Detailed NuScale Power Module Model..................... 103 4.2.1 Verification of Containment Vessel Simplified Finite Element Model........ 103 4.2.2 Verification of Piping Inside Containment Simplified Finite Element Model... 104 4.2.3 Verification of Piping Outside Containment Simplification Approach........ 105 4.2.4 Verification of Top Support Structure Simplified Finite Element Model...... 106 4.2.5 Verification of Reactor Pressure Vessel Simplified Finite Element Model.... 107 4.2.6 Verification of Support Structure Simplified Finite Element Model.......... 108 4.2.7 Verification of Reactor Vessel Internals Simplified Finite Element Model.... 109 4.2.8 Verification of Control Rod Drive Mechanism Support Frame Simplified Finite Element Model............................................ 119

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 Table of Contents © Copyright 2024 by NuScale Power, LLC vii 4.3 Modal Analysis Results................................................ 120 4.4 Verification of the Detailed NuScale Power Module Model with the Linear Elastic Interior Represented with a Superelement.................................. 124 4.5 Preparation and Processing of Input Acceleration Time Histories for NuScale Power Module - Ultimate Heat Sink Transient Analysis........................ 125 4.6 Linear Transient Analysis............................................... 128 5.0 Results............................................................ 131 5.1 Time-History Displacement Data......................................... 131 5.2 Time-History Force and Moment Data..................................... 137 5.3 In-Structure Response Spectra Data...................................... 143 5.4 Discussion of Non-linear Transient Analysis Results.......................... 146 5.5 Conclusions......................................................... 148 6.0 References......................................................... 149 Appendix A Comparative Assessment of In-Structure Response Spectra from the Simplified and Detailed Double Building Models Soil-Structure Interaction Harmonic Analysis....................................A-1 A.1 Selected Nodes.......................................................A-1 A.2 Acceleration Time History Calculations and Oversampling......................A-6 A.3 In-Structure Response Spectra Averaging, Enveloping and Broadening...........A-6 A.4 Results..............................................................A-6 A.5 Conclusions..........................................................A-9

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Tables © Copyright 2024 by NuScale Power, LLC viii Table 1-1 Abbreviations.................................................... 4 Table 1-2 Definitions....................................................... 5 Table 3-1 Containment Vessel Material Designation............................. 29 Table 3-2 Piping Support Joint Coupling in Local Coordinate System (0: Uncoupled, 1: Coupled)..................................................... 39 Table 3-3 Top Support Structure Material Designation........................... 51 Table 3-4 Reactor Pressure Vessel Material Designation......................... 58 Table 3-5 Fuel Assembly Beam Model Parameters.............................. 63 Table 3-6 Total Mass and Center of Mass of the Fuel Model....................... 64 Table 3-7 Fuel Assembly Effective Modal Mass Ratio............................ 64 Table 3-8 Lower Riser System Component Properties........................... 69 Table 3-9 Linear Elastic Material Properties.................................... 69 Table 3-10 Mass of Lower Reactor Vessel Internal Components from Reference Finite Element Model.................................................. 71 Table 3-11 Upper Reactor Vessel Internal Component Properties................... 72 Table 3-12 Upper Riser Bellow Spring Constants................................ 73 Table 3-13 Mass of Upper Reactor Vessel Internal Components from Reference Finite Element Model.................................................. 74 Table 3-14 Total Mass and Modal Analysis Results of the Control Rod Drive Mechanism Models.............................................. 76 Table 3-15 Mass from Reference and Simplified Target and Finite Element Models of the Control Rod Drive Mechanism Support Frame...................... 78 Table 3-16 Control Rod Drive Mechanism Support Structure Material Designation...... 82 Table 3-17 Fritz Elements for Contained Fluid................................... 85 Table 3-18 Connections in the Combined Model................................. 86 Table 4-1 Frequencies and Effective Modal Mass Ratio of the Major Modes of the Simplified and Detailed NuScale Power Module Models Without Pool...... 102 Table 4-2 Reference Reactor Vessel Internals Finite Element Model Modal Analysis Results....................................................... 110 Table 4-3 Core Plate Mass Information...................................... 113

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Tables © Copyright 2024 by NuScale Power, LLC ix Table 4-4 Control Rod Assembly Guide Tube and Lower Control Rod Drive Shaft Support Plate Mass Properties..................................... 114 Table 4-5 Core Plate Support Mass Information............................... 117 Table 4-6 Comparison of Mass Properties of the Reactor Vessel Internals from Reference and Simplified Models................................... 117 Table 4-7 Frequencies and Effective Modal Mass Ratio of the Major Modes......... 120 Table 5-1 Soil Column Frequencies for Embedment Depth of Reactor Building....... 147 Table A-1 Event Input Acceleration Time Histories..............................A-6

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC x Figure 3-1 Combined Containment Vessel and Superelement of the Simplified NuScale Power Module Model............................................. 10 Figure 3-2 Lug and Corbel Connections of the Simplified NuScale Power Module Model......................................................... 11 Figure 3-3 Finite Element Model of the Detailed NuScale Power Module.............. 12 Figure 3-4 NuScale Power Module Upper Portion................................ 13 Figure 3-5 NuScale Power Module Middle Portion............................... 14 Figure 3-6 NuScale Power Module Lower Portion................................ 15 Figure 3-7 Major Load Paths Through Components.............................. 16 Figure 3-8 ANSYS Workbench Project Scheme Showing the Development Layout of the Detailed NuScale Power Module Model............................ 17 Figure 3-9 Models of the CNV and Wall Systems................................ 19 Figure 3-10 Containment Vessel Geometry and Mesh............................. 20 Figure 3-11 Containment Vessel Lower Head and Skirt............................ 21 Figure 3-12 Geometry and Mesh of the Pool Water in the NuScale Power Module Bay... 22 Figure 3-13 Basemat in Separated Parts....................................... 23 Figure 3-14 Containment Vessel Bottom and Basemat Mesh........................ 24 Figure 3-15 Distributed Mass on Containment Vessel............................. 25 Figure 3-16 Containment Vessel Head Valve Locations (in Blue)..................... 26 Figure 3-17 Decay Heat Removal System...................................... 27 Figure 3-18 Skirt-to-Basemat Frictionless Contact................................ 28 Figure 3-19 Containment Vessel Materials...................................... 30 Figure 3-20 Fluid-Structure Interaction and Zero Hydrostatic Pressure................ 31 Figure 3-21 Meshes of the Simplified Model and Reference Model................... 32 Figure 3-22 Boundary Conditions for Modal Analysis.............................. 33 Figure 3-23 Piping Inside Containment Geometry and Mesh........................ 34 Figure 3-24 Lumped Mass on Feedwater Piping.................................. 35 Figure 3-25 Pipe End to Containment Vessel Connections.......................... 36 Figure 3-26 Pipe End to-Reactor Pressure Vessel Connections...................... 37

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC xi Figure 3-27 Piping Support Types............................................. 38 Figure 3-28 Piping Support Naming Convention and Local Coordinate Systems......... 39 Figure 3-29 Meshes of the Simplified Model and Reference Model................... 41 Figure 3-30 Top Support Structure, Piping, and Cables on the Containment Vessel Top Head.......................................................... 42 Figure 3-31 Piping Outside Containment Mesh................................... 43 Figure 3-32 Spherical Joints for Translational Degrees of Freedom of the Ball Joints..... 44 Figure 3-33 Torsional Springs for Rotational Degrees of Freedom of the Ball Joints...... 45 Figure 3-34 An Example of Inserted APDL to Change Spring Direction and Properties.... 45 Figure 3-35 Pipe-to-Top Support Structure Connections........................... 46 Figure 3-36 Pipe-to-Containment Vessel Connections............................. 47 Figure 3-37 Pipe Support-to-Bay East/West Wall Connections....................... 48 Figure 3-38 Pipe End-to-North Wall Connections................................. 49 Figure 3-39 Meshes of the Simplified Model and Reference Model................... 50 Figure 3-40 Top Support Structure Mesh....................................... 51 Figure 3-41 Meshes of the Simplified Model and Reference Model................... 52 Figure 3-42 Reactor Pressure Vessel Geometry.................................. 53 Figure 3-43 Reactor Pressure Vessel Mesh..................................... 54 Figure 3-44 Added Mass on Reactor Pressure Vessel............................. 55 Figure 3-45 Reactor Pressure Vessel Head Valve Locations........................ 56 Figure 3-46 Reactor Pressure Vessel-to-Containment Vessel Ledge Connection........ 57 Figure 3-47 Reactor Pressure Vessel-to-Containment Vessel Seismic Restraint Connection..................................................... 58 Figure 3-48 Meshes of the Simplified Model and Reference Model................... 59 Figure 3-49 Water Mass Inside of Reactor Vessel Internals......................... 61 Figure 3-50 Fuel Finite Element Model and Schematic............................. 62 Figure 3-51 Fuel Finite Element Model Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions................................................. 65 Figure 3-52 Lower Reactor Vessel Internal Geometry............................. 66

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC xii Figure 3-53 Core System Components......................................... 67 Figure 3-54 Lower Riser System Components................................... 68 Figure 3-55 Lower Reactor Vessel Internal Reference Finite Element Model and the Reflector Representation.......................................... 70 Figure 3-56 Upper Reactor Vessel Internal Geometry and Components............... 71 Figure 3-57 Upper Reactor Vessel Internal Reference Finite Element Model............ 73 Figure 3-58 Control Rod Drive Mechanism Finite Element Model with Point Masses...... 77 Figure 3-59 Control Rod Drive Mechanism Support Frame Geometry and Finite Element Model Mesh of the Reference and Simplified Models............. 78 Figure 3-60 Control Rod Drive Mechanism Support Structure Geometry............... 79 Figure 3-61 Control Rod Drive Mechanism Support Structure Mesh.................. 80 Figure 3-62 Support Structure-to-Reactor Pressure Vessel Connection................ 81 Figure 3-63 Mesh of the Simplified Model and Reference Model..................... 82 Figure 3-64 Core Support Mounting Bracket Mesh................................ 83 Figure 3-65 Fritz Element Segments........................................... 84 Figure 3-66 Upper Reactor Pressure Internal Shell to Reactor Pressure Vessel Shell Spring Connections.............................................. 87 Figure 3-67 Bonded Reactor Pressure Vessel Baffle Plate and Upper Reactor Pressure Internal Hanger Plate............................................. 88 Figure 3-68 Bonded Core Support Mounting Bracket and Reactor Pressure Vessel Lower Head.................................................... 89 Figure 3-69 Joint Connections for Lower Core Plate Tab to Core Support Mounting Bracket........................................................ 90 Figure 3-70 Bonded Control Rod Drive Mechanism Bottom and Reactor Pressure Vessel Top Head................................................ 91 Figure 3-71 Joint Connection for Control Rod Drive Mechanism to Support Frame....... 92 Figure 3-72 Joint Connection for Control Rod Drive Mechanism to Support Structure..... 93 Figure 3-73 Bonded Containment Vessel Head and Support Frame.................. 94 Figure 3-74 Plan View of the Detailed NuScale Module Models Included in the Ultimate Heat Sink Volume........................................ 95

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC xiii Figure 3-75 NuScale Power Module - Ultimate Heat Sink Local Seismic Model.......... 96 Figure 3-76 Superelement Model and Eight Master Nodes.......................... 98 Figure 3-77 Rayleigh Damping Used in the Analysis Models....................... 100 Figure 4-1 Cumulative Effective Modal Mass Ratio of the Containment Vessel from Reference and Simplified Finite Element Models....................... 103 Figure 4-2 Cumulative Effective Modal Mass Ratio of the Piping Inside Containment from Reference and Simplified Finite Element Models.................. 104 Figure 4-3 Cumulative Effective Modal Mass Ratio of the Piping Outside Containment from Reference and Simplified Finite Element Models.................. 105 Figure 4-4 Cumulative Effective Modal Mass Ratio of the Top Support Structure from Reference and Simplified Finite Element Models....................... 106 Figure 4-5 Cumulative Effective Modal Mass Ratio of the Reactor Pressure Vessel from Reference and Simplified Finite Element Models.................. 107 Figure 4-6 Cumulative Effective Modal Mass Ratio of the Control Rod Drive Mechanism Support Structure from Reference and Simplified Finite Element Models....................................................... 109 Figure 4-7 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Pressure Vessel Internals from the Reference Finite Element Model........................................................ 111 Figure 4-8 Three Major Modes of the Reactor Vessel Internals from the Reference Finite Element Model............................................ 112 Figure 4-9 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Pressure Vessel from the Reference and the Core Plate Simplified Models....................................................... 113 Figure 4-10 Cumulative Effective Modal Mass Ratio Distribution in X, Y, and Z Directions of the Reactor Vessel Internals Reference Model and the Core Plate, Bellows, Control Rod Assembly Guide Tube, and Lower Control Rod Drive Shaft Plate Simplified Model.................................. 115 Figure 4-11 Simplified Finite Element Model of Reactor Vessel Internals with Coarse Mesh......................................................... 116 Figure 4-12 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Vessel Internals from Reference and Simplified Models.......... 118

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC xiv Figure 4-13 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Control Rod Drive Mechanism Support Frame from Reference and Simplified Models............................................... 119 Figure 4-14 X Mode....................................................... 121 Figure 4-15 Y Modes...................................................... 122 Figure 4-16 Z Modes...................................................... 123 Figure 4-17 Cumulative Effective Mass Ratio of the NuScale Power Module........... 124 Figure 4-18 Displacement Time Histories Baseline Correction for Node 73,859........ 126 Figure 4-19 Kinetic and Strain Energy Time Histories............................. 127 Figure 4-20 Comparison of Acceleration Time Histories, Fourier Spectra, and In-Structure Response Spectra for the Upper Core Plate from Harmonic and Linear Transient Analyses..................................... 129 Figure 4-21 Comparison of Acceleration Time Histories, Fourier Spectra, and In-Structure Response Spectra for the Lower Core Plate from Harmonic and Linear Transient Analyses..................................... 130 Figure 5-1 Remote Points for Lower Core Plate and Upper Core Plate.............. 131 Figure 5-2 Lower Core Plate Displacements from Module 1 from Baseline Soil-7 with Sliding........................................................ 132 Figure 5-3 Input Displacement Time Histories for the Capitola Design-Basis Ground Motion at the Outcrop............................................ 132 Figure 5-4 Remote Points for CNV Skirt Flange, Basemat, and NuScale Power Module East Lug in Module 1...................................... 133 Figure 5-5 Skirt and Basemat Displacement for Module 1 from Baseline Soil-7 with Sliding........................................................ 134 Figure 5-6 Horizontal Relative Displacements Between Skirt and Basemat in Module 1 from Baseline Soil-7 Case with Sliding............................... 135 Figure 5-7 Vertical Relative Displacement Between Skirt and Basemat for Module 1 from Baseline Soil-7 Case with Sliding............................... 136 Figure 5-8 Cross Section of Lower Core Barrel................................. 137 Figure 5-9 Lower Core Barrel Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding............................................... 138

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 List of Figures © Copyright 2024 by NuScale Power, LLC xv Figure 5-10 Lower Core Barrel Reaction Moments for Module 1 from Baseline Soil-7 Case with Sliding............................................... 139 Figure 5-11 Skirt Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding........................................................ 140 Figure 5-12 Skirt Reaction Moments for Module 1 from Baseline Soil-7 Case with Sliding........................................................ 141 Figure 5-13 East Lug Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding........................................................ 142 Figure 5-14 Upper Core Plate and Lower Core Plate Accelerations for Module 1 from Baseline Soil-7 Case with Sliding................................... 143 Figure 5-15 Upper Core Plate and Lower Core Plate Four Percent Damping In-Structure Response Spectra for Module 1 from Baseline Soil-7 Case with Sliding.................................................... 144 Figure 5-16 Enveloped and Broadened In-Structure Response Spectra for Lower Core Plate from Analyses with Sliding................................... 145 Figure 5-17 Enveloped and Broadened In-Structure Response Spectra for Lower Core Plate from Analyses without Sliding................................. 146 Figure A-1 Selected Nodes on the Slab at 146-6 Elevation and the Roof of the Reactor Building.................................................A-2 Figure A-2 Selected Nodes on the Slabs at 85, 100, and 126 Elevations on the Reactor Building.................................................A-3 Figure A-3 Selected Nodes on the Basemat and Slabs at 55 and 70 Elevations on the Reactor Building..............................................A-4 Figure A-4 Selected Nodes on the Basemat and at 100 Elevation on the Radioactive Waste Building..................................................A-5 Figure A-5 Enveloped In-Structure Response Spectra on the Structural Members for the Hybrid Reactor Building Model...................................A-7 Figure A-6 Enveloped In-Structure Response Spectra on the Structural Members for the Hybrid Radioactive Waste Building Model..........................A-8

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 1 Abstract This report describes the methodologies and structural models used to calculate the dynamic structural response of the US460 NuScale Power Module (NPM) due to seismic loads. In addition, the report presents analysis results. The NPM detailed dynamic model couples with the dynamic model of the Reactor Building to represent the effects of fluid-structure interaction due to pool water found between the NPM and pool floor and walls. The performance of the dynamic analysis yields loads, in-structure response spectra, and in-structure time histories, which are the basis for the mechanical design of Seismic Category I structures, systems, and components that comprise or are supported by the NPM. This report supports Final Safety Analysis Report Section 3.7, Seismic Design, for the NuScale US460 Standard Design.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 2 Executive Summary Seismic analysis of the US460 NuScale Power Module (NPM) and its structures, systems, and components (SSC) requires a complete system model to represent the dynamic coupling of the reactor pressure vessel, containment vessel, reactor internals and core support, reactor core, surrounding pool water and structural members, and SSC supported by the NPM. NuScale performed a dynamic analysis of the NPM system using time history dynamic analysis methods and a three-dimensional ANSYS finite element model. The seismic input for the dynamic analysis of the NPM system is calculated by performing soil-structure interaction (SSI) harmonic analysis in the frequency domain for several design basis ground motions and soil conditions using the double-building model, which includes the Reactor Building, Radioactive Waste Building, and the engineered backfill. For these analyses, NuScale developed simplified and detailed NPM models. The SSI analyses performed with the simplified NPM model is used for the analysis and design of SSC within the Reactor Building and Radioactive Waste Building, excluding NPMs. The SSI harmonic analyses performed with the detailed NPMs are used to calculate the response of the walls and the basemat around the ultimate heat sink (UHS) as the seismic input for the nonlinear transient analysis of a local NPM model. The local NPM model consists of the UHS, NPMs, and the structural members around them (NPM-UHS model). Non-linear transient time-history dynamic analysis performed with the NPM-UHS seismic models is used to calculate in-structure time histories and response spectra for the qualification of NPM components, equipment supported by the NPM, and in-structure time histories for seismic qualification of fuel assemblies.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 3 1.0 Introduction 1.1 Purpose This report describes methodologies and finite element models (FEMs) of the NuScale Power Module (NPM) used for seismic analyses of systems, structures, and components (SSC) and presents NPM analysis results. In-structure responses determined by using the presented methodologies and models are inputs for the dynamic response analysis of subsystems and components supported by the NPM. Loads and displacement time histories from the dynamic analysis of detailed NPM models are used in conjunction with other loads to design the containment vessel (CNV), reactor pressure vessel (RPV), core support, and internal structures. 1.2 Scope The SSC in the scope of this report are those that comprise the NPM, which is the self-contained nuclear steam supply system in the NuScale Power Plant. The NPM is comprised of a reactor core, a pressurizer, and two steam generators (SGs) integrated within an RPV and housed in a compact steel CNV. Other components integral to the NPM are the fuel assemblies, reactor vessel internals (RVI), control rod drive mechanisms (CRDMs), piping, valves, and instrumentation and controls. The NPM seismic analysis provides time histories of core support motions used as seismic input for fuel qualification. The interface forces between the NPM and the Reactor Building (RXB) (lug and skirt reaction forces) are included in this report. The methodologies for seismic qualification of the fuel is provided in TR-117605, NuFuel-HTP2 Fuel and Control Rod Assembly Designs (Reference 6.0.1). The NPM model uses seismic input from the double-building soil-structure interaction (SSI) analyses that are performed with the detailed three-dimensional NPM finite element models incorporated into the RXB. The Final Safety Analysis Report, Section 3.7.2, addresses methodologies used for the RXB soil-structure interaction analysis; however, this report includes a brief discussion as background information. The seismic analysis methodology described in this report applies to the NPM and the SSC supported by the NPM, and includes the CNV, top support structure (TSS) and piping outside containment, piping inside containment, RPV, upper RVI (URVI), lower RVI (LRVI), CRDM, and CRDM support structure. This report includes the methodology for building the different versions of the NPM models, validation of the NPM models through modal analyses, and a nonlinear transient analysis of the integrated system.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 4 Because details of the geometry and mesh refinements are insufficient for representing local stress distributions and stress concentrations, this report does not consider stress analysis models. Software used for performing NPM seismic analyses conforms with the requirements for computer software as per the NuScale Quality Assurance Program Description (Reference 6.0.2). 1.3 Abbreviations and Definitions Table 1-1 Abbreviations Term Definition APDL ANSYS parametric design language CAD computer aided design CMS component mode synthesis CNV containment vessel CRAGT control rod assembly guide tube CRDM control rod drive mechanism CRDS control rod drive shaft CSDRS certified seismic design response spectra CSDRS-HF certified seismic design response spectra for high frequency CSMB core support mounting bracket DB double building DHRS decay heat removal system DOF degrees of freedom FSI fluid-structure interaction FW feedwater ISRS in-structure response spectra LCP lower core plate LRVI lower reactor vessel internals MS main steam NPM-DM NuScale Power Module detailed model NPM-DM-SE NuScale Power Module detailed model with the linear elastic interior represented with a superelement NPM-SE NuScale Power Module simplified model RCS reactor coolant system RP remote point RPV reactor pressure vessel RVI reactor vessel internals RXB reactor building SF support frame SG steam generator SS support structure SSC structures, systems, and components SSI soil-structure interaction TSS top support structure UCP upper core plate UHS ultimate heat sink

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 5 URVI upper reactor vessel internals WB ANSYS workbench Table 1-2 Definitions Term Definition Superelement ANSYS terminology that represents a single-matrix element determined by condensing a group of finite elements into one through substructuring methodology. Table 1-1 Abbreviations (Continued) Term Definition

Background

This seismic analysis technical report provides the information necessary to conclude that the US460 Standard Plant design complies with General Design Criterion 2 and 10 CFR 50, Appendix S. These regulatory requirements, in part, state that SSC are designed to withstand the effects of earthquakes without loss of capability to perform their safety functions. 2.1 Layout of the NuScale Power Module and Reactor Building The RXB is an embedded structure located above and below grade. The RXB houses the NPMs, systems, and components required for plant operation and shutdown. The RXB is a rectangular configuration approximately 230 ft long and 155 ft wide, with a height approximately 81 ft above nominal plant grade level. The bottom of the RXB foundation is approximately 83 ft below grade. Each NPM is located in the reactor pool within its own three-walled bay with the open side toward the center of the pool. The bays are two rows, with three bays per row, along the north and south walls of the reactor pool. A central channel between the bays allows for movement of the NPMs between the bays and the refueling pool. The reactor pool, the refueling pool, and the spent fuel pool are the three safety-related pools that comprise the ultimate heat sink (UHS) and contain borated water. The UHS is located below grade in the RXB. 2.2 Load Path for Core Support The upper and lower core plates provide vertical and horizontal support for the reactor core. The core barrel and lower RPV support the core plates. The load transfers from the lower core plate (LCP) and core barrel to the RPV through four core support mounting brackets, located on the interior of the RPV bottom head. The peripheral fuel assemblies become in contact with the reflector to resist the horizontal displacement of the core. The reflector load, supported by the core support, is transferred through the core support blocks. For horizontal seismic loads acting on the LCP, the primary load path from the RPV to the RXB is through the RPV/CNV seismic restraint connections located between the bottom of the RPV and the CNV. The horizontal load in this load path is transfered to the pool floor primarily through the CNV skirt. Horizontal loads from the UCP and the LCP are carried through the CNV skirt, with a secondary load path through the supports of the RPV and CNV support lugs. The CNV support lugs provide horizontal restraint. Vertical loads from the core are transferred from the core support and lower RPV upward to the connection of the upper RPV and CNV. The load is transferred downward from the

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 7 upper RPV and CNV to the CNV support skirt. To allow free vertical thermal expansion of the RPV and internals, no vertical load is transferred through the seismic restraints at the bottom of the RPV. 2.3 Regulatory Requirements NuScale developed seismic analysis methods in accordance with guidance below:

U.S. Nuclear Regulatory Commission, Standard Review Plan for review of Safety Analysis Reports for Nuclear Power Plants, NUREG-0800 DSRS 3.7.2, U.S. Nuclear Regulatory Commission, Design-Specific Review Standard for NuScale SMR Design, Section 3.7.2, Seismic System Analysis, Revision 0, June 2016 Section 3.7.1, Seismic Design Parameters, Revision 4, December 2014 Section 3.7.2, Seismic System Analysis, Revision 4, September 2013 Section 3.9.2, Dynamic Testing and Analysis of Systems, Structures, and Components, Revision 3, March 2007

DC/COL-ISG-017, Interim Staff Guidance on Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses

DC/COL-ISG-01, Interim Staff Guidance on Seismic Issues Associated with High Frequency Ground Motion in Design Certification and Combined License Applications

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 8 3.0 Analytical Methodology This section describes NPM finite element models and the methodology employed to perform nonlinear seismic transient analyses with the NPM-UHS model. 3.1 Main Components of NuScale Power Module The main components of the NPM include the CNV, TSS, piping outside containment, piping inside containment, RPV, RVI, CRDMs, CRDM support frame (SF), CRDM support structure (SS), and fuel assembly. The reactor pool water, bay walls, and basemat are also included in the model development for defining the boundary around the NPM during testing and verification of the NPM model. 3.2 Analytical Representation of NuScale Power Module The analytical representation of the NPM is varied from simplified to detailed, depending on the purpose of analyses and calculations. A total of three different analytical models of the NPM are developed. The first model is the simplified NPM model (NPM-SE). The simplifications are primarily accomplished by using superelements. The main purpose of the NPM-SE model is to represent the fundamental dynamic characteristics of the NPM assembly such that the dynamic coupling between the RXB structure and the NPM assembly can be captured during seismic analyses. The NPM-SE is incorporated into the double-building (DB) model, which consists of the RXB, the Radioactive Waste Building (RWB), and the engineered backfill. The DB model is then used to calculate the seismic response of structural components, such as the reinforced concrete diaphragms and steel-composite walls within the RXB. The second model is the detailed NPM model (NPM-DM) in which the complete set of major subcomponents are explicitly modeled. The NPM-DM model is used for calculating the seismic response at the boundary of the local NPM model. The NPM-DM model is incorporated into the DB model to perform seismic SSI analyses. The local NPM model (NPM-UHS) consists of the UHS, NPMs, and the structural members around them. The third model is the detailed NPM model in which the major linear elastic subcomponents are represented by using a superelement (NPM-DM-SE). The NPM-DM-SE model is used to perform nonlinear transient analyses with the NPM-UHS model and calculate the seismic response of the SSC within the NPM.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 9 In summary, three analytical NPM models are developed for the analyses presented in this report. Among these three models, NPM-SE is used only for calculating the seismic response of the SSC that are not within the NPM, whereas, NPM-DM and NPM-DM-SE are used for calculating the seismic response of the SSC within the NPM. 3.3 Simplified NuScale Power Module Model The NPM-SE is developed and incorporated into the DB model to perform static and harmonic SSI analyses of the RXB, calculate the static and seismic response for sensitivity calculations, and for design of structural members and components that are not within the NPM. The NPM-SE is generated by developing the CNV model and superelement representation of the TSS, RPV, URVI, LRVI, and CRDM and then assembling each superelement into a single superelement. The component mode synthesis (CMS) method in ANSYS is used for superelement generation. The CNV and the superelement are combined (Figure 3-1) and incorporated into the RXB model.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 10 In the RXB model, each of the three lugs of the NPM is tangentially restrained by the corbels on the bay walls (Figure 3-2). The connection between the corbels and lugs is defined by using spring elements with high stiffness. Each of the CNV skirts are connected to the top of the RXB basemat through stiff spring elements (COMBIN14) provided in X, Y, and Z directions. A fluid-structure interaction (FSI) is defined at the CNV surface that is in contact with the pool water. The pool top surface is set to be free of pressure. Figure 3-1 Combined Containment Vessel and Superelement of the Simplified NuScale Power Module Model

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 11 3.4 Detailed NuScale Power Module Model (( }}2(a),(c),ECI Figure 3-2 Lug and Corbel Connections of the Simplified NuScale Power Module Model (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 17 (( }}2(a),(c),ECI Figure 3-8 ANSYS Workbench Project Scheme Showing the Development Layout of the Detailed NuScale Power Module Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 19 3.4.1.1 Geometry (( }}2(a),(c),ECI Figure 3-9 Models of the CNV and Wall Systems (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 20 (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-10 Containment Vessel Geometry and Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 22 3.4.1.2 Mesh (( }}2(a),(c),ECI Figure 3-12 Geometry and Mesh of the Pool Water in the NuScale Power Module Bay (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 25 3.4.1.3 Mass Adjustment (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-15 Distributed Mass on Containment Vessel (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 26 (( }}2(a),(c),ECI Figure 3-16 Containment Vessel Head Valve Locations (in Blue) (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 28 3.4.1.4 Connections and Contacts (( }}2(a),(c),ECI Figure 3-18 Skirt-to-Basemat Frictionless Contact (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 29 (( }}2(a),(c),ECI 3.4.1.5 Materials and Fluid-Structure Interaction (( }}2(a),(c),ECI (( }}2(a),(c),ECI Table 3-1 Containment Vessel Material Designation (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 31 3.4.1.6 Justification for Simplification (( }}2(a),(c),ECI Figure 3-20 Fluid-Structure Interaction and Zero Hydrostatic Pressure (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 32 3.4.1.6.1 Models (( }}2(a),(c),ECI Figure 3-21 Meshes of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 33 3.4.1.6.2 Modal Analysis (( }}2(a),(c),ECI 3.4.2 Piping Inside Containment (( }}2(a),(c),ECI Figure 3-22 Boundary Conditions for Modal Analysis (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 34 3.4.2.1 Geometry (( }}2(a),(c),ECI Figure 3-23 Piping Inside Containment Geometry and Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 35 3.4.2.2 Mesh (( }}2(a),(c),ECI 3.4.2.3 Mass Adjustment (( }}2(a),(c),ECI Figure 3-24 Lumped Mass on Feedwater Piping (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 36 3.4.2.4 Connections and Supports (( }}2(a),(c),ECI 3.4.2.4.1 Pipe End to Containment Vessel (( }}2(a),(c),ECI 3.4.2.4.2 Pipe End to Reactor Pressure Vessel (( }}2(a),(c),ECI Figure 3-25 Pipe End to Containment Vessel Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 37 3.4.2.4.3 Piping Support (( }}2(a),(c),ECI Figure 3-26 Pipe End to-Reactor Pressure Vessel Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 39 Figure 3-28 Piping Support Naming Convention and Local Coordinate Systems (( }}2(a),(c),ECI Table 3-2 Piping Support Joint Coupling in Local Coordinate System (0: Uncoupled, 1: Coupled) (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 40 3.4.2.5 Materials (( }}2(a),(c),ECI 3.4.2.6 Justification for Simplification (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 41 3.4.3 Piping Outside Containment (( }}2(a),(c),ECI 3.4.3.1 Geometry (( }}2(a),(c),ECI Figure 3-29 Meshes of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 42 3.4.3.2 Mesh (( }}2(a),(c),ECI Figure 3-30 Top Support Structure, Piping, and Cables on the Containment Vessel Top Head (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 43 (( }}2(a),(c),ECI 3.4.3.3 Mass Adjustment (( }}2(a),(c),ECI Figure 3-31 Piping Outside Containment Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 44 3.4.3.4 Connections and Supports 3.4.3.4.1 Pipe-to-Pipe Connection by Ball Joint (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-32 Spherical Joints for Translational Degrees of Freedom of the Ball Joints (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 45 3.4.3.4.2 Pipe Support-to-Top Support Structure (( }}2(a),(c),ECI Figure 3-33 Torsional Springs for Rotational Degrees of Freedom of the Ball Joints (( }}2(a),(c),ECI Figure 3-34 An Example of Inserted APDL to Change Spring Direction and Properties (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 46 3.4.3.4.3 Pipe-to-Containment Vessel (( }}2(a),(c),ECI Figure 3-35 Pipe-to-Top Support Structure Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 47 3.4.3.4.4 Pipe-to-Wall (( }}2(a),(c),ECI Figure 3-36 Pipe-to-Containment Vessel Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 48 (( }}2(a),(c),ECI Figure 3-37 Pipe Support-to-Bay East/West Wall Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 49 3.4.3.5 Materials (( }}2(a),(c),ECI Figure 3-38 Pipe End-to-North Wall Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 50 3.4.3.6 Justification for Simplification (( }}2(a),(c),ECI 3.4.4 Top Support Structure 3.4.4.1 Geometry (( }}2(a),(c),ECI 3.4.4.2 Mesh (( }}2(a),(c),ECI Figure 3-39 Meshes of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 51 3.4.4.3 Connections (( }}2(a),(c),ECI 3.4.4.4 Materials (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-40 Top Support Structure Mesh (( }}2(a),(c),ECI Table 3-3 Top Support Structure Material Designation (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 52 3.4.4.5 Justification for Simplification (( }}2(a),(c),ECI 3.4.5 Reactor Pressure Vessel (( }}2(a),(c),ECI Figure 3-41 Meshes of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 53 3.4.5.1 Geometry (( }}2(a),(c),ECI Figure 3-42 Reactor Pressure Vessel Geometry (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 55 3.4.5.3 Mass Adjustment (( }}2(a),(c),ECI Figure 3-44 Added Mass on Reactor Pressure Vessel (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 56 (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-45 Reactor Pressure Vessel Head Valve Locations (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 57 (( }}2(a),(c),ECI 3.4.5.4 Connections (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-46 Reactor Pressure Vessel-to-Containment Vessel Ledge Connection (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 58 3.4.5.5 Materials (( }}2(a),(c),ECI (( }}2(a),(c),ECI Figure 3-47 Reactor Pressure Vessel-to-Containment Vessel Seismic Restraint Connection (( }}2(a),(c),ECI Table 3-4 Reactor Pressure Vessel Material Designation (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 59 3.4.5.6 Justification for Simplification (( }}2(a),(c),ECI Figure 3-48 Meshes of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 61 3.4.6.1 Fuel Assembly (( }}2(a),(c),ECI Figure 3-49 Water Mass Inside of Reactor Vessel Internals (( }}2(a),(c),ECI

[

}}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 64 (( }}2(a),(c),ECI Table 3-6 Total Mass and Center of Mass of the Fuel Model (( }}2(a),(c),ECI Table 3-7 Fuel Assembly Effective Modal Mass Ratio (( [ ] [ ] [ ] [ ] [ ] [ ] [ ] [ ] }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 65 [ ] [ ] [ ] Figure 3-51 Fuel Finite Element Model Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions (( }}2(a),(c),ECI Table 3-7 Fuel Assembly Effective Modal Mass Ratio (Continued) (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 66 3.4.6.2 Lower Reactor Vessel Internal 3.4.6.2.1 Geometry (( }}2(a),(c),ECI Figure 3-52 Lower Reactor Vessel Internal Geometry (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 69 3.4.6.2.2 Reference Finite Element Model (( }}2(a),(c),ECI Table 3-8 Lower Riser System Component Properties (( }}2(a),(c),ECI Table 3-9 Linear Elastic Material Properties (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 70 (( }}2(a),(c),ECI Figure 3-55 Lower Reactor Vessel Internal Reference Finite Element Model and the Reflector Representation (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 71 3.4.6.3 Upper Reactor Vessel Internal 3.4.6.3.1 Geometry (( }}2(a),(c),ECI Table 3-10 Mass of Lower Reactor Vessel Internal Components from Reference Finite Element Model (( }}2(a),(c),ECI Figure 3-56 Upper Reactor Vessel Internal Geometry and Components (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 72 (( }}2(a),(c),ECI 3.4.6.3.2 Reference Finite Element Model (( }}2(a),(c),ECI Table 3-11 Upper Reactor Vessel Internal Component Properties (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 73 (( }}2(a),(c),ECI Figure 3-57 Upper Reactor Vessel Internal Reference Finite Element Model (( }}2(a),(c),ECI Table 3-12 Upper Riser Bellow Spring Constants (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 74 3.4.6.4 Reactor Vessel Internals Simplified Finite Element Model (( }}2(a),(c),ECI Table 3-13 Mass of Upper Reactor Vessel Internal Components from Reference Finite Element Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 75 (( }}2(a),(c),ECI 3.4.7 Control Rod Drive Mechanism Assembly and Support Structures 3.4.7.1 Control Rod Drive Mechanism (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 76 (( }}2(a),(c),ECI Table 3-14 Total Mass and Modal Analysis Results of the Control Rod Drive Mechanism Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 77 3.4.7.2 Control Rod Drive Mechanism Support Frame (( }}2(a),(c),ECI Figure 3-58 Control Rod Drive Mechanism Finite Element Model with Point Masses (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 78 (( }}2(a),(c),ECI Figure 3-59 Control Rod Drive Mechanism Support Frame Geometry and Finite Element Model Mesh of the Reference and Simplified Models (( }}2(a),(c),ECI Table 3-15 Mass from Reference and Simplified Target and Finite Element Models of the Control Rod Drive Mechanism Support Frame (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 79 3.4.7.3 Control Rod Drive Mechanism Support Structure 3.4.7.3.1 Geometry (( }}2(a),(c),ECI Figure 3-60 Control Rod Drive Mechanism Support Structure Geometry (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 80 3.4.7.3.2 Mesh (( }}2(a),(c),ECI Figure 3-61 Control Rod Drive Mechanism Support Structure Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 81 3.4.7.3.3 Connections (( }}2(a),(c),ECI Figure 3-62 Support Structure-to-Reactor Pressure Vessel Connection (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 82 3.4.7.3.4 Materials (( }}2(a),(c),ECI 3.4.7.3.5 Justification for Simplification (( }}2(a),(c),ECI Table 3-16 Control Rod Drive Mechanism Support Structure Material Designation (( }}2(a),(c),ECI Figure 3-63 Mesh of the Simplified Model and Reference Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 83 3.4.8 Core Support Mounting Bracket (( }}2(a),(c),ECI (( }}2(a),(c),ECI 3.4.9 Fritz Elements for Hydrodynamic Masses (( }}2(a),(c),ECI Figure 3-64 Core Support Mounting Bracket Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 85 (( }}2(a),(c),ECI 3.4.10 Final Combined Model The components presented above are combined in the NPM system. The combined model has the capability to be switched between nonlinear and linear. 3.4.10.1 Connections Table 3-18 lists the connections assigned in the combined model. This table also provides the document sections discussing the details of these connections. Table 3-17 Fritz Elements for Contained Fluid (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 86 3.4.10.1.1 Upper Reactor Pressure Internal Outside Shell to Reactor Pressure Vessel Inside Shell (( }}2(a),(c),ECI Table 3-18 Connections in the Combined Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 87 Figure 3-66 Upper Reactor Pressure Internal Shell to Reactor Pressure Vessel Shell Spring Connections (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 88 3.4.10.1.2 Reactor Pressure Vessel Baffle Plate to Upper Reactor Pressure Internal Hanger Plate (( }}2(a),(c),ECI 3.4.10.1.3 Core Support Mounting Bracket Bottom Surface to Reactor Pressure Vessel Lower Head (( }}2(a),(c),ECI Figure 3-67 Bonded Reactor Pressure Vessel Baffle Plate and Upper Reactor Pressure Internal Hanger Plate (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 89 3.4.10.1.4 Lower Core Plate Tab to Core Support Mounting Bracket (( }}2(a),(c),ECI Figure 3-68 Bonded Core Support Mounting Bracket and Reactor Pressure Vessel Lower Head (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 90 3.4.10.1.5 Control Rod Drive Mechanisms to Reactor Pressure Vessel Top Head (( }}2(a),(c),ECI Figure 3-69 Joint Connections for Lower Core Plate Tab to Core Support Mounting Bracket (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 91 3.4.10.1.6 Control Rod Drive Mechanism Upper Support to Support Frame Bottom Beam (( }}2(a),(c),ECI Figure 3-70 Bonded Control Rod Drive Mechanism Bottom and Reactor Pressure Vessel Top Head (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 92 3.4.10.1.7 Control Rod Drive Mechanism Lower Support to Support Structure Top Beams (( }}2(a),(c),ECI Figure 3-71 Joint Connection for Control Rod Drive Mechanism to Support Frame (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 93 3.4.10.1.8 Containment Vessel Top Head to Support Frame (( }}2(a),(c),ECI Figure 3-72 Joint Connection for Control Rod Drive Mechanism to Support Structure (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 94 3.4.10.2 Modal Analysis of the Detailed NuScale Power Module Model (( }}2(a),(c),ECI Figure 3-73 Bonded Containment Vessel Head and Support Frame (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 95 3.5 Soil-Structure Interaction Harmonic Analysis of Double Building with Detailed NuScale Power Module Model Six NPM-DM models are incorporated into the RXB model to perform SSI harmonic analyses. (( }}2(a),(c),ECI Figure 3-74 presents the NPM models incorporated into the UHS and connected to the bay walls. Figure 3-74 Plan View of the Detailed NuScale Module Models Included in the Ultimate Heat Sink Volume (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 96 3.6 NuScale Power Module - Ultimate Heat Sink Model The NPM-UHS seismic model consists of six NPMs, the UHS, the basemat, and the structural members around and within UHS. The NPM-UHS model is extracted from the DB model that is developed by incorporating six NPMs into the RXB (Section 3.5). 3.6.1 Preparation of NPM-UHS Model The NPM-UHS model is extracted from the DB harmonic analysis model. (( }}2(a),(c),ECI Figure 3-75 presents the NPM-UHS model and the interface nodes at its boundary. Figure 3-75 NuScale Power Module - Ultimate Heat Sink Local Seismic Model

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 97 3.6.2 Pool Sloshing Sloshing does not have a significant effect upon wall motions. The maximum sloshing height is estimated to be less than 3.5 feet. This height corresponds to a pressure increase of (( }}2(a),(c) at the surface. This value is about 3.5 percent of the total pressure due to peak mean hydrodynamic pressure ((( }}2(a),(c)) and the peak hydrostatic pressure ((( }}2(a),(c)), and therefore it is insignificant in terms of response and design of the pool walls. Furthermore, the frequency of sloshing is much lower than the fundamental frequency of the NPM. Therefore, sloshing is assumed to have an insignificant effect on the seismic response of the NPM. 3.6.3 Detailed NuScale Power Module Model with the Liner Elastic Interior Components Represented with a Superelement The nonlinear transient analyses are computationally demanding and require significantly small time-steps for sufficiently accurate calculation of numerical integrations and many equilibrium iterations to satisfy the force convergence at the nonlinear interfaces between the NPMs and the basemat. To manage the analysis computation time and to achieve sufficiently accurate simulations, the linear elastic interior components of the NPM-DM are replaced with a superelement. The new NPM model is called NPM-DM-SE. (( }}2(a),(c),ECI Figure 3-76 presents the superelement model and the eight master nodes.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 98 3.7 Preparation and Processing of Input Acceleration Time Histories for NuScale Power Module - Ultimate Heat Sink Transient Analysis Acceleration time histories are calculated for each node at the interface between the NPM-UHS model and the DB model (Figure 3-75). Acceleration time histories at the interface nodes are calculated for two design-basis ground motions that are developed using the seismic motion records from the two earthquakes namely the Capitola (Loma Prieta, CA, USA, 1989) and Lucerne (Landers, CA, USA, 1992). Among the two events listed, Capitola seismic motion is compatible with the certified seismic design response spectra (CSDRS) and used for the simulations performed with Baseline Soil-7, Soil-11, and Soil-Separation Soil-7 design bases. The Lucerne seismic motion, which is compatible with the certified seismic design response spectra for high frequency (CSDRS-HF), is used for the simulation performed with Baseline Soil-9 design basis. Figure 3-76 Superelement Model and Eight Master Nodes (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 99 The acceleration time histories are calculated by extracting transfer functions from the SSI harmonic analysis and convolving them with the input design-basis ground motions as explained in TR-0118-58005, Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis (Reference 6.0.4). The interpolation of the transfer functions sometimes leads to drifts in the calculated displacement time histories. To address this drift, the calculated acceleration time histories are baseline corrected (( }}2(a),(c),ECI 3.8 Nonlinear Transient Analysis (( }}2(a),(c),ECI ANSYS guidelines suggests having 20 points per cycle at the highest frequency of interest. Within the limits of the available computational power, the selected time step is acceptable to achieve sufficient accuracy. Transient analyses are performed for four cases (Baseline Soil-7, Soil-11, Soil-9, Soil-Separation Soil-7). (( }}2(a),(c),ECI The run times are determined based on the minimum requirement from the Design-Specific Review Standard for NuScale SMR Design, 3.7.1 Seismic Design Parameters (Reference 6.0.5) and the strong motion duration of the input ground motions.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 100 3.8.1 Rayleigh Damping Two different sets of Rayleigh damping parameters are used in the analyses. (( }}2(a),(c),ECI Figure 3-77 Rayleigh Damping Used in the Analysis Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 101 3.8.2 Linear Transient Analysis versus Harmonic Analysis The NPM-UHS model and the scripts generated to perform the transient analysis are tested by performing a linear transient analysis for Baseline Soil-7 case. (( }}2(a),(c),ECI 3.8.3 Contact - Target Settings (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 102 4.0 Calculation Body 4.1 Verification of the Simplified NuScale Power Model with Superelements Modal analyses are performed using both the NPM-SE and NPM-DM. (( }}2(a),(c) Table 4-1 lists the major modes with significant effective modal mass ratio in X, Y, and Z directions. In general, the modal analysis results from the two models show agreement with each other. (( }}2(a),(c) It is verified in Appendix A that the differences between the two NPM models do not lead to major changes on the seismic demand on the SSC that are not associated with the NPMs. Table 4-1 Frequencies and Effective Modal Mass Ratio of the Major Modes of the Simplified and Detailed NuScale Power Module Models Without Pool (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 103 4.2 Verification of the Detailed NuScale Power Module Model 4.2.1 Verification of Containment Vessel Simplified Finite Element Model (( }}2(a),(c),ECI Figure 4-1 Cumulative Effective Modal Mass Ratio of the Containment Vessel from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 104 4.2.2 Verification of Piping Inside Containment Simplified Finite Element Model (( }}2(a),(c),ECI Figure 4-2 Cumulative Effective Modal Mass Ratio of the Piping Inside Containment from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 105 4.2.3 Verification of Piping Outside Containment Simplification Approach (( }}2(a),(c),ECI Figure 4-3 Cumulative Effective Modal Mass Ratio of the Piping Outside Containment from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 106 4.2.4 Verification of Top Support Structure Simplified Finite Element Model (( }}2(a),(c),ECI Figure 4-4 Cumulative Effective Modal Mass Ratio of the Top Support Structure from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 107 4.2.5 Verification of Reactor Pressure Vessel Simplified Finite Element Model (( }}2(a),(c),ECI Figure 4-5 Cumulative Effective Modal Mass Ratio of the Reactor Pressure Vessel from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 109 4.2.7 Verification of Reactor Vessel Internals Simplified Finite Element Model 4.2.7.1 Reference Finite Element Model Modal Analysis (( }}2(a),(c),ECI Figure 4-6 Cumulative Effective Modal Mass Ratio of the Control Rod Drive Mechanism Support Structure from Reference and Simplified Finite Element Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 110 (( }}2(a),(c),ECI Table 4-2 Reference Reactor Vessel Internals Finite Element Model Modal Analysis Results (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 111 Figure 4-7 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Pressure Vessel Internals from the Reference Finite Element Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 112 4.2.7.2 Simplification of Core Plates (( }}2(a),(c),ECI Figure 4-8 Three Major Modes of the Reactor Vessel Internals from the Reference Finite Element Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 113 Table 4-3 Core Plate Mass Information (( }}2(a),(c),ECI Figure 4-9 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Pressure Vessel from the Reference and the Core Plate Simplified Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 114 4.2.7.3 Simplification of Control Rod Assembly Guide Tube and Lower Control Rod Drive Shaft Support Plates (( }}2(a),(c),ECI Table 4-4 Control Rod Assembly Guide Tube and Lower Control Rod Drive Shaft Support Plate Mass Properties (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 115 Figure 4-10 Cumulative Effective Modal Mass Ratio Distribution in X, Y, and Z Directions of the Reactor Vessel Internals Reference Model and the Core Plate, Bellows, Control Rod Assembly Guide Tube, and Lower Control Rod Drive Shaft Plate Simplified Model (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 116 4.2.7.4 Simplification of Core Plate Supports and Mesh Coarsening (( }}2(a),(c),ECI Figure 4-11 Simplified Finite Element Model of Reactor Vessel Internals with Coarse Mesh (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 117 (( }}2(a),(c),ECI (( }}2(a),(c),ECI Table 4-5 Core Plate Support Mass Information (( }}2(a),(c),ECI Table 4-6 Comparison of Mass Properties of the Reactor Vessel Internals from Reference and Simplified Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 118 Figure 4-12 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Reactor Vessel Internals from Reference and Simplified Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 119 4.2.8 Verification of Control Rod Drive Mechanism Support Frame Simplified Finite Element Model (( }}2(a),(c),ECI Figure 4-13 Cumulative Effective Modal Mass Ratio in X, Y, and Z Directions of the Control Rod Drive Mechanism Support Frame from Reference and Simplified Models (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 120 4.3 Modal Analysis Results Table 4-7 provides the major modes of the NPM-DM model with significant effective modal mass in X, Y, and Z directions. Figure 4-14, Figure 4-15, and Figure 4-16 show the mode shapes of these fundamental modes for the X, Y, and Z directions, respectively. (( }}2(a),(c),ECI Table 4-7 Frequencies and Effective Modal Mass Ratio of the Major Modes (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 124 4.4 Verification of the Detailed NuScale Power Module Model with the Linear Elastic Interior Represented with a Superelement The accuracy of the superelement in capturing the dynamic characteristics of the NPM model is verified through a modal analysis. (( }}2(a),(c),ECI Figure 4-17 compares the distribution of the cumulative effective modal mass ratio to the modal results determined from the NPM-DM model, in which subcomponents are explicitly modeled. (( }}2(a),(c),ECI Figure 4-17 Cumulative Effective Mass Ratio of the NuScale Power Module (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 125 4.5 Preparation and Processing of Input Acceleration Time Histories for NuScale Power Module - Ultimate Heat Sink Transient Analysis The level of drift and the improvement achieved by baseline correction is evaluated by plotting time histories from random points that are selected among the nodes at the interface of NPM-UHS and DB (Figure 3-75). To present the improvement achieved more clearly, the relative time histories are calculated with respect to a node at the center of the basemat on the concrete-soil interface. Figure 4-18 presents the relative time histories before and after baseline correction. Even though the baseline correction does not fully remove the observed drift, it significantly improves the calculated response time-histories. The improvement is also visible in the strain energy plots from the non-linear simulations performed with and without baseline-corrected time histories (Figure 4-19). The baseline correction addresses unrealistic quadratic accumulation of strain energy.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 126 Figure 4-18 Displacement Time Histories Baseline Correction for Node 73,859 (( }}2(a),(c).ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 128 4.6 Linear Transient Analysis A sample linear transient analysis is performed to verify the APDL scripts and present the level of conservatism introduced by Rayleigh damping. The analyses are performed using the NPM-UHS model without nonlinearities, the model that is included in the harmonic analysis model of the Double Building, and the input time-histories from Baseline Soil-7 case. (( }}2(a),(c),ECI The acceleration time histories, Fourier spectra, and ISRS curves that are calculated from the linear transient analysis are compared to the corresponding results from the harmonic analysis at multiple locations. Figure 4-20 and Figure 4-21 present comparisons for the lower and upper core plates. (( }}2(a),(c),ECI The similarity of the acceleration time histories and the expected conservatism introduced due to Rayleigh damping verifies the NPM-UHS seismic model and the scripts used to perform transient analyses.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 129 Figure 4-20 Comparison of Acceleration Time Histories, Fourier Spectra, and In-Structure Response Spectra for the Upper Core Plate from Harmonic and Linear Transient Analyses (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 130 Figure 4-21 Comparison of Acceleration Time Histories, Fourier Spectra, and In-Structure Response Spectra for the Lower Core Plate from Harmonic and Linear Transient Analyses (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 131 5.0 Results (( }}2(a),(c),ECI 5.1 Time-History Displacement Data (( }}2(a),(c),ECI Figure 5-1 Remote Points for Lower Core Plate and Upper Core Plate (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 132 Figure 5-2 Lower Core Plate Displacements from Module 1 from Baseline Soil-7 with Sliding (( }}2(a),(c),ECI Figure 5-3 Input Displacement Time Histories for the Capitola Design-Basis Ground Motion at the Outcrop (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 133 (( }}2(a),(c),ECI Figure 5-4 Remote Points for CNV Skirt Flange, Basemat, and NuScale Power Module East Lug in Module 1 (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 134 (( }}2(a),(c),ECI Figure 5-5 Skirt and Basemat Displacement for Module 1 from Baseline Soil-7 with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 135 (( }}2(a),(c),ECI Figure 5-6 Horizontal Relative Displacements Between Skirt and Basemat in Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 136 Figure 5-7 Vertical Relative Displacement Between Skirt and Basemat for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 137 5.2 Time-History Force and Moment Data (( }}2(a),(c),ECI Figure 5-8 Cross Section of Lower Core Barrel (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 138 Figure 5-9 Lower Core Barrel Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 139 (( }}2(a),(c),ECI Figure 5-10 Lower Core Barrel Reaction Moments for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 140 Figure 5-11 Skirt Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 141 (( }}2(a),(c),ECI Figure 5-12 Skirt Reaction Moments for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 142 Figure 5-13 East Lug Reaction Forces for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 143 5.3 In-Structure Response Spectra Data (( }}2(a),(c),ECI Figure 5-14 Upper Core Plate and Lower Core Plate Accelerations for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 144 Figure 5-15 Upper Core Plate and Lower Core Plate Four Percent Damping In-Structure Response Spectra for Module 1 from Baseline Soil-7 Case with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 145 (( }}2(a),(c),ECI Figure 5-16 Enveloped and Broadened In-Structure Response Spectra for Lower Core Plate from Analyses with Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 146 5.4 Discussion of Non-linear Transient Analysis Results (( }}2(a),(c),ECI Figure 5-17 Enveloped and Broadened In-Structure Response Spectra for Lower Core Plate from Analyses without Sliding (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 147 (( }}2(a),(c),ECI Table 5-1 Soil Column Frequencies for Embedment Depth of Reactor Building (( }}2(a),(c),ECI

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC 149 6.0 References 6.0.1 TR-117605, NuFuel-HTP2 Fuel and Control Rod Assembly Designs, Revision 1, December 2022. 6.0.2 MN-122626, NuScale Power, LLC Quality Assurance Program Description, Revision 1-A, January 2024. 6.0.3 AREVA Fuels Doc. FS1-0025171, Rev. 3.0, NuScale Lateral Faulted Analysis - Grid Impact Loads from Externally Applied Lateral Dynamic Excitations. 6.0.4 TR-0118-58005, Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis, Revision 2-A, December 2020. 6.0.5 Design-Specific Review Standard for NuScale SMR Design, 3.7.1 Seismic Design Parameters, Revision 0, June 2016. 6.0.6 TR-0920-71621, Building Design and Analysis Methodology for Safety-Related Structures, Revision 1-A, March 2022.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-1 Appendix A Comparative Assessment of In-Structure Response Spectra from the Simplified and Detailed Double Building Models Soil-Structure Interaction Harmonic Analysis Appendix A presents a comparative assessment of the seismic demand on the SSC that are not associated with the NPMs for the two DB models that are built with NPM-SE and NPM-DM models. The evaluation is performed using the ISRS that are calculated for multiple points on major structural members, such as the basemat, roof, and floor systems. The ISRS calculations are performed using ANSYS with a damping ratio of 5 percent. A.1 Selected Nodes There are 446 nodes on the RXB and 50 nodes on the RWB that are selected for ISRS calculations. Figure A-1, Figure A-2, Figure A-3, and Figure A-4 present the selected nodes.

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-2 Figure A-1 Selected Nodes on the Slab at 146-6 Elevation and the Roof of the Reactor Building (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-3 Figure A-2 Selected Nodes on the Slabs at 85, 100, and 126 Elevations on the Reactor Building (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-4 Figure A-3 Selected Nodes on the Basemat and Slabs at 55 and 70 Elevations on the Reactor Building (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-5 Figure A-4 Selected Nodes on the Basemat and at 100 Elevation on the Radioactive Waste Building (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-6 A.2 Acceleration Time History Calculations and Oversampling Acceleration time histories at the selected nodes are calculated using the in-layer input time histories for the six design-basis ground motions (Table A-1). Among the six ground motions listed, five of them are CSDRS-compatible and used for the simulations performed with Baseline Soil-7, Soil-11, and Soil-Separation Soil-7 models. One event (LUC) is used for the simulation performed with Baseline Soil-9 model. The acceleration time history calculations are performed following the procedure in Reference 6.1.3. For accurate ISRS calculations, the acceleration time histories at the selected nodes are oversampled using the Fourier zero-padding approach to have the sampling time step as 0.5 milliseconds. A.3 In-Structure Response Spectra Averaging, Enveloping and Broadening The ISRS are calculated per node and per structural member. For the latter, initially the ISRS calculated for the nodes on a structural member are enveloped to represent the enveloping ISRS for the structural member of interest per event. The ISRS for the events are averaged to represent the mean ISRS per soil condition. The mean ISRS per soil condition are enveloped for the analyses performed (Baseline Soil-7, Soil-11, Soil-9, and Soil Separation Soil-7) to represent the enveloping ISRS for the structural member or node of interest. The ISRS are broadened 15 percent to account for variability. The procedure followed for the ISRS calculation is in accordance with TR-0920-71621, "Building Design and Analysis Methodology for Safety-Related Structures (Reference 6.1.5). A.4 Results (( }}2(a),(c) Table A-1 Event Input Acceleration Time Histories Earthquake Label Chi-Chi (Nantou, Taiwan), 1999 CHI Loma Prieta (California, USA), 1989 CAP Kocaeli (Izmit, Turkiye), 1999 IZM Imperial Valley (California, USA), 1940 ELC Landers (Californica, USA), 1992 YER Landers (Californica, USA), 1992 LUC

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-7 Figure A-5 Enveloped In-Structure Response Spectra on the Structural Members for the Hybrid Reactor Building Model (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-8 Figure A-6 Enveloped In-Structure Response Spectra on the Structural Members for the Hybrid Radioactive Waste Building Model (( }}2(a),(c)

US460 NuScale Power Module Seismic Analysis TR-121515-NP Revision 1 © Copyright 2024 by NuScale Power, LLC A-9 A.5 Conclusions The differences between the ISRS calculated for DB models with NPM-DM and NPM-SE models are negligible. Thus, the use of analysis results from the DB model with NPM-SE is acceptable for the seismic evaluation of SSC that are not associated with NPMs.

LO-175558 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com Affidavit of Mark W. Shaver, AF-175559

AF-175559 Page 1 of 2

NuScale Power, LLC AFFIDAVIT of Mark W. Shaver I, Mark W. Shaver, state as follows: (1) I am the Director of Regulatory Affairs of NuScale Power, LLC (NuScale), and as such, I have been specifically delegated the function of reviewing the information described in this Affidavit that NuScale seeks to have withheld from public disclosure, and am authorized to apply for its withholding on behalf of NuScale. (2) I am knowledgeable of the criteria and procedures used by NuScale in designating information as a trade secret, privileged, or as confidential commercial or financial information. This request to withhold information from public disclosure is driven by one or more of the following: (a) The information requested to be withheld reveals distinguishing aspects of a process (or component, structure, tool, method, etc.) whose use by NuScale competitors, without a license from NuScale, would constitute a competitive economic disadvantage to NuScale. (b) The information requested to be withheld consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), and the application of the data secures a competitive economic advantage, as described more fully in paragraph 3 of this Affidavit. (c) Use by a competitor of the information requested to be withheld would reduce the competitors expenditure of resources, or improve its competitive position, in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product. (d) The information requested to be withheld reveals cost or price information, production capabilities, budget levels, or commercial strategies of NuScale. (e) The information requested to be withheld consists of patentable ideas. (3) Public disclosure of the information sought to be withheld is likely to cause substantial harm to NuScales competitive position and foreclose or reduce the availability of profit-making opportunities. The accompanying report reveals distinguishing aspects about the process by which NuScale develops its Module Seismic Analysis. NuScale has performed significant research and evaluation to develop a basis for this process and has invested significant resources, including the expenditure of a considerable sum of money. The precise financial value of the information is difficult to quantify, but it is a key element of the design basis for a NuScale plant and, therefore, has substantial value to NuScale. If the information were disclosed to the public, NuScale's competitors would have access to the information without purchasing the right to use it or having been required to undertake a similar expenditure of resources. Such disclosure would constitute a misappropriation of NuScale's intellectual property, and would deprive NuScale of the opportunity to exercise its competitive advantage to seek an adequate return on its investment. (4) The information sought to be withheld is in the enclosed report entitled, US460 NuScale Power Module Seismic Analysis, TR-121515, Revision 1. The enclosure contains the designation Proprietary at the top of each page containing proprietary information. The information considered by NuScale to be proprietary is identified within double braces, (( }} in the document.

AF-175559 Page 2 of 2 (5) The basis for proposing that the information be withheld is that NuScale treats the information as a trade secret, privileged, or as confidential commercial or financial information. NuScale relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC § 552(b)(4), as well as exemptions applicable to the NRC under 10 CFR §§ 2.390(a)(4) and 9.17(a)(4). (6) Pursuant to the provisions set forth in 10 CFR § 2.390(b)(4), the following is provided for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld: (a) The information sought to be withheld is owned and has been held in confidence by NuScale. (b) The information is of a sort customarily held in confidence by NuScale and, to the best of my knowledge and belief, consistently has been held in confidence by NuScale. The procedure for approval of external release of such information typically requires review by the staff manager, project manager, chief technology officer or other equivalent authority, or the manager of the cognizant marketing function (or his delegate), for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside NuScale are limited to regulatory bodies, customers and potential customers and their agents, suppliers, licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or contractual agreements to maintain confidentiality. (c) The information is being transmitted to and received by the NRC in confidence. (d) No public disclosure of the information has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or contractual agreements that provide for maintenance of the information in confidence. (e) Public disclosure of the information is likely to cause substantial harm to the competitive position of NuScale, taking into account the value of the information to NuScale, the amount of effort and money expended by NuScale in developing the information, and the difficulty others would have in acquiring or duplicating the information. The information sought to be withheld is part of NuScale's technology that provides NuScale with a competitive advantage over other firms in the industry. NuScale has invested significant human and financial capital in developing this technology and NuScale believes it would be difficult for others to duplicate the technology without access to the information sought to be withheld. I declare under penalty of perjury that the foregoing is true and correct. Executed on November 22, 2024. Mark W. Shaver

LO-175558 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com : Affidavit of Morris Byram, Framatome Inc.

A F F I D A V I T 1. My name is Morris Byram. I am Product Manager, Licensing & Regulatory Affairs for Framatome Inc. (Framatome) and as such I am authorized to execute this Affidavit. 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria. 3. I am familiar with the Framatome information contained in Enclosure 1 entitled US460 NuScale Power Module Seismic Analysis, TR-121515-P, Revision 1, to the NuScale Power, LLC letter Number LO-175558, and referred to herein as Document. Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information. 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential. 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) Trade secrets and commercial or financial information.

6.

The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary: (a) The information reveals details of Framatomes research and development plans and programs or their results. (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service. (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome. (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability. (e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome. The information in this Document is considered proprietary for the reasons set forth in paragraph 6(c), 6(d) and 6(e) above.

7.

In accordance with Framatomes policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8.

Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9.

The foregoing statements are true and correct to the best of my knowledge, information, and belief.

I declare under penalty of perjury that the foregoing is true and correct. Executed on: (11/20/2024) (NAME) Email: morris.byram@framatome.com Phone: 434-221-1082 BYRAM Morris Digitally signed by BYRAM Morris Date: 2024.11.20 13:59:22 -08'00'}}

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