ML20197A430

Part 09 - Withheld Information (Rev. 4.1) - Part 09 - Withheld Information (Rev. 4.1)

ML20197A430
Person / Time
Site:	NuScale
Issue date:	06/19/2020
From:	Bergman T NuScale
To:	Office of Nuclear Reactor Regulation
Cranston G
References
NUSCALESMRDC, NUSCALESMRDC.SUBMISSION.12, NUSCALEPART09.NP, NUSCALEPART09.NP.5
Download: ML20197A430 (4)

Text

NuScale Standard Plant Design Certification Application Withheld Information PART 9 Revision 4.1 June 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 1

Revision 4.1 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

Withheld Information Part 9 2

Revision 4.1 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 Figure or Table Number Figure or Table Title