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Category:License-Application for Design Certification
MONTHYEARML20224A5212020-07-29029 July 2020 Part 07 - Exemptions - Chapters 01 - 17 (Rev. 5) - Part 07 - Exemptions - Chapters 01 - 17 ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20197A4142020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 20 - Mitigation of Beyond-Design-Basis Events - Sections 20.01 - 20.04 (Rev. 4.1) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20197A4322020-06-19019 June 2020 Part 10 - Quality Assurance Program Description (Rev. 4.1) - Part 10 - Quality Assurance Program Description (Rev. 4.1) ML20197A4302020-06-19019 June 2020 Part 09 - Withheld Information (Rev. 4.1) - Part 09 - Withheld Information (Rev. 4.1) ML20197A4282020-06-19019 June 2020 Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) - Part 08 - License Conditions, Inspections, Tests, Analyses and Acceptance Criteria (Rev. 4.1) ML20197A4262020-06-19019 June 2020 Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) - Part 07 - Exemptions - Chapters 01 - 17 (Rev. 4.1) ML20197A4242020-06-19019 June 2020 Part 06 - Security Plans (Rev. 4.1) - Part 06 - Security Plans (Rev. 4.1) ML20197A4222020-06-19019 June 2020 Part 05 - Emergency Plans (Rev. 4.1) - Part 05 - Emergency Plans (Rev. 4.1) ML20197A4202020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 2 - Bases - Chapters 02 - 03 (Rev. 4.1) ML20197A4192020-06-19019 June 2020 Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants (Rev. 4.1) - Part 04 - Generic Technical Specifications - NuScale Nuclear Power Plants - Volume 1 - Specifications - Chapters 01 - 05 (Rev. 4.1) ML20197A4172020-06-19019 June 2020 Part 03 - Applicants Environmental Report - Standard Design Certification (Rev. 4.1) - Part 03 - Applicants Environmental Report - Standard Design Certification - Section 1.0 - Appendix B (Rev. 4.1) ML20197A4152020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 21 - Multi-Module Design Considerations - Sections 21.01 - 21.04 (Rev. 4.1) ML20197A4132020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Sections 19.00 - 19.05 (Rev. 4.1) ML20197A4122020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 18 - Human Factors Engineering - Sections 18.00 - 18.12 (Rev. 4.1) ML20197A4112020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 17 - Quality Assurance and Reliability Assurance - Sections 17.01 - 17.06 (Rev. 4.1) ML20197A4102020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 16 - Technical Specifications - Section 16.01 - Technical Specifications (Rev. 4.1) ML20197A4092020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 15 - Transient and Accident Analyses - Sections 15.00 - 15.10 (Rev. 4.1) ML20197A4082020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 14 - Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria - Sections 14.00 - 14.03 (Rev. 4.1) ML20197A4072020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 13 - Conduct of Operations - Sections 13.01 - 13.07 (Rev. 4.1) ML20197A4062020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 12 - Radiation Protection - Sections 12.01 - 12.05 (Rev. 4.1) ML20197A4042020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 10 - Steam and Power Conversion System - Sections 10.01 - 10.04 (Rev. 4.1) ML20197A3842020-06-19019 June 2020 Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) - Part 01 - General and Financial Information - Sections 01.01 - 01.04 (Rev. 4.1) ML20197A3862020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 01 - Certified Design Descriptions and Inspections, Tests, Analyses, and Acceptance Criteria - Chapters 01 - 05 (Rev. 4.1) ML20197A3872020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 01 - Introduction and General Description of the Plant - Sections 01.01 - 01.10 (Rev. 4.1) ML20197A3882020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 02 - Site Characteristics and Site Parameters - Sections 02.00 - 02.05 (Rev. 4.1) ML20197A3892020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.01 - 03.06 (Rev. 4.1) ML20197A3902020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 1 - 265 (Rev. 4.1) ML20197A3912020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 266 - 307 (Rev. 4.1) ML20197A3922020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 308 - 345 (Rev. 4.1) ML20197A3932020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.07 - Seismic Design - Pages 346 - 482 (Rev. 4.1) ML20197A3942020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 1 - 140 (Rev. 4.1) ML20197A3962020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 (Rev. 4.1) ML20197A3952020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Section 03.08 - Des. Cat I Str. - Pgs 141 - 271 (Rev. 4.1) ML20197A3972020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C (Rev. 4.1) ML20197A3982020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 (Rev. 4.1) ML20197A3992020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 (Rev. 4.1) ML20197A4002020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 (Rev. 4.1) ML20197A4012020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 (Rev. 4.1) ML20197A4022020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 (Rev. 4.1) ML20197A4032020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 09 - Auxiliary Systems - Section 09.01 - Appendix 9A (Rev. 4.1) ML20197A4052020-06-19019 June 2020 Part 02 - Final Safety Analysis Report (Rev. 4.1) - Part 02 - Tier 02 - Chapter 11 - Radioactive Waste Management - Sections 11.01 - 11.06 (Rev. 4.1) ML20036D4442020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 08 - Electric Power - Sections 08.01 - 08.04 ML20036D4422020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 07 - Instrumentation and Controls - Sections 07.00 - 07.02 ML20036D4402020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 06 - Engineered Safety Features - Sections 06.01 - 06.07 ML20036D4392020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 05 - Reactor Coolant System and Connecting Systems - Sections 05.01 - 05.04 ML20036D4382020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 04 - Reactor - Sections 04.01 - 04.06 ML20036D4372020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Appendices 3A - 3C ML20036D4332020-01-16016 January 2020 Part 02 - Final Safety Analysis Report (Rev. 4) - Part 02 - Tier 02 - Chapter 03 - Design of Structures, Systems, Components and Equipment - Sections 03.09 - 03.13 2020-07-29
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NuScale Standard Plant Design Certification Application Withheld Information PART 9 Revision 4 January 2020
©2020, NuScale Power LLC. All Rights Reserved
COPYRIGHT NOTICE This document bears a NuScale Power, LLC, copyright notice. No right to disclose, use, or copy any of the information in this document, other than by the U.S. Nuclear Regulatory Commission (NRC), is authorized without the express, written permission of NuScale Power, LLC.
The NRC is permitted to make the number of copies of the information contained in these reports needed for its internal use in connection with generic and plant-specific reviews and approvals, as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by NuScale Power, LLC, copyright protection notwithstanding. Regarding nonproprietary versions of these reports, the NRC is permitted to make the number of additional copies necessary to provide copies for public viewing in appropriate docket files in public document rooms in Washington, DC, and elsewhere as may be required by NRC regulations. Copies made by the NRC must include this copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
Withheld Information Part 9 - Withheld Information Part 9 of the NuScale Power, LLC Design Certification Application (DCA) identifies the location of security-related information within the Final Safety Analysis Report (FSAR).
NuScale requests the security-related information be withheld from public disclosure in accordance with 10 CFR 2.390(d)(1).
The following figures and tables contain security-related information and have been withheld:
Figure or Table Number Figure or Table Title Fig. 1.2-4 Layout of a Multi-Module NuScale Power Plant Fig. 1.2-5 Cutaway Illustration of 12 Module Configuration Fig. 1.2-10 Reactor Building 24-0 Elevation Fig. 1.2-11 Reactor Building 35-8 Elevation Fig. 1.2-12 Reactor Building 50-0 Elevation Fig. 1.2-13 Reactor Building 62-0 Elevation Fig. 1.2-14 Reactor Building 75-0 Elevation Fig. 1.2-15 Reactor Building 86-0 Elevation Fig. 1.2-16 Reactor Building 100-0 Elevation Fig. 1.2-17 Reactor Building 126-0 Elevation Fig. 1.2-18 Reactor Building 145-6 Elevation Fig. 1.2-19 Reactor Building East and West Section View Fig. 1.2-20 Reactor Building South Section View Fig. 1.2-21 Control Building 50-0 Elevation Fig. 1.2-22 Control Building 63-3 Elevation Fig. 1.2-23 Control Building 76-6 Elevation Fig. 1.2-24 Control Building 100-0 Elevation Fig. 1.2-25 Control Building 120-0 Elevation Fig. 1.2-26 Control Building North Section View Fig. 1.2-27 Control Building West Section View Fig. 1.2-28 Radioactive Waste Building 71-0 Elevation Fig. 1.2-29 Radioactive Waste Building 82-0 Elevation Fig. 1.2-30 Radioactive Waste Building 100-0 Elevation Fig. 1.2-31 Radioactive Waste Building 120-0 Elevation Fig. 1.2-32 Radioactive Waste Building North and South Section Views Fig. 1.2-33 Radioactive Waste Building West Section View Fig. 2.3-2 Source to Control Building Door Distances Fig. 2.3-3 Source to Control Building HVAC Intake Distance Table 3.4-2 Flood Levels for Rooms Containing Systems, Structures, and Components Subject to Flood Protection (Without Mitigation)
Figure 3.5-1 Plan View of Partial NuScale Plant Showing Turbine Missile Trajectory Figure 3.5-2 Section View of RXB and TGB Showing Turbine Missile Barriers Figure 3.5-3 Section View of CRB and TGB Showing Turbine Missile Barriers Fig. 3B-26 RXB Reinforcement Plan at EL 100-0 Fig. 9.1.3-5 Reactor Building Pool Water Level and Plant Feature Elevations Fig. 9.1.4-4a New Fuel Elevator Table 9.2.5-1 Relevant Ultimate Heat Sink Parameters Table 9.4.2-3 Reactor Building Ventilation System Major Components Table 9.4.2-5 Reactor Building Areas with Air Change Rates Greater than 0.5 per Hour Fig. 12.3-1a Reactor Building Radiation Zone Map - 24 Elevation Fig. 12.3-1b Reactor Building Radiation Zone Map 8 Elevation Part 9 1 Revision 4
Withheld Information Figure or Table Number Figure or Table Title Fig. 12.3-1c Reactor Building Radiation Zone Map - 50 Elevation Fig. 12.3-1d Reactor Building Radiation Zone Map - 62 Elevation Fig. 12.3-1e Reactor Building Radiation Zone Map - 75 Elevation Fig. 12.3-1f Reactor Building Radiation Zone Map - 86 Elevation Fig. 12.3-1g Reactor Building Radiation Zone Map - 100 Elevation Fig. 12.3-1h Reactor Building Radiation Zone Map - 126 Elevation Fig. 12.3-1i Reactor Building Radiation Zone Map - 146 Elevation Fig. 12.3-2a Radioactive Waste Building Radiation Zone Map - 71 Elevation Fig. 12.3-2b Radioactive Waste Building Radiation Zone Map - 100 Elevation Part 9 2 Revision 4