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LLC Submittal of Presentation Materials Entitled, US460 Design and Sdaa Overview Update, PM-135236, Rev. 0 (Open Session)
	ML23045A080
Person / Time
Site:	99902078, 05200050
Issue date:	02/14/2023
From:	Shaver M; NuScale
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	LO-135022
	Download: ML23045A080 (1)
	v • d • e

LO-135022 February 14, 2023 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 Presentation Materials Entitled US460 Design and SDAA Overview Update, PM-135236, Revision 0 (Open Session)

The purpose of this submittal is to provide presentation materials to the NRC for use during the upcoming Advisory Committee on Reactor Safeguards (ACRS) NuScale Subcommittee Meeting on February 15, 2023. The materials support NuScales presentation of the US460 design and overview of the NuScale Standard Design Approval Application.

The enclosure to this letter is the nonproprietary version of the presentation entitled US460 Design and SDAA Overview Update (Open Session).

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

If you have any questions, please contact Thomas Griffith at 541-452-7813 or tgriffith@nuscalepower.com.

Sincerely, Mark W. Shaver Acting Director, Regulatory Affairs NuScale Power, LLC Distribution: Michael Dudek, NRC Getachew Tesfaye, NRC Bruce Bavol, NRC Mike Snodderly, NRC

Enclosure:

US460 Design and SDAA Overview Update, PM-135236, Revision 0 (Open Session)

NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com

LO-135022

Enclosure:

US460 Design and SDAA Overview Update , PM-135236, Revision 0 (Open Session)

NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com

NuScale Nonproprietary 1

US460 Design and SDAA Overview Update ACRS Presentation (Open Session)

February 15th, 2023 Kristopher Cummings Licensing Engineer V Brian Meadors Chief Engineer, Regulatory Affairs Tom Griffith Licensing Manager, Acting - SDAA PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 2

Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0008928.

This presentation was prepared as an account of work sponsored by an agency of the United States (U.S.)

Government. Neither the U.S. 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 U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

NuScale Nonproprietary 3

Agenda - Open Portion

SDAA Content

US460 Design Overview

Topical and Technical reports PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 4

Why we are here and how did we get here?

The SDA submittal is an engineering optimization of the NuScale DCA to allow for better customer use and deployment. The SDA maintains the approved technical and licensing basis from the DCA while maintaining the overall safety and risk profile.

High Level Design Changes

Redesigned site layout to accommodate a 6 NPM configuration

NPM optimized for increased power output; ease of maintenance, manufacturing and operation while maintaining safety margins:

o Steam generator was over designed for 160MWth application (DCA) and allows for increased power output while maintaining design limits o Additional testing has been performed to validate performance of NPM engineered safety features at an increased power level o Additional engineered safety features added to eliminate certain events and simplify Chapter 15 analysis

Current evaluation of SDA design changes does not significantly alter the DCA PRA risk insights.

NuScale Nonproprietary 5

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SDA Application Content DESIGN CERTIFICATION SDAA - Required by Regulation SDAA - Needed to Include as Part of SDAA APPLICATION PART (10 CFR 52 subpart B) (10 CFR 52 subpart E) Support COL Submittal Transmittal Letter Yes Yes N/A Yes Part 1: General and Financial Information (financial info. Not required) (financial info. Not required) N/A Yes Part 2: Safety Analysis Report - Tier 1 Yes No No No Ch. 1 - Introduction Yes No No No Ch. 2 - Unit Specific SSCs Design Descriptions Yes No ITAAC Only ITAAC Only and ITAAC (see Part 08)

Ch. 3 - Shared SSCs and Non-SSCs Design Yes No ITAAC Only ITAAC Only Descriptions and ITAAC (see Part 08)

Ch. 4 - Interface Requirements Yes No No No Ch. 5 - Site Parameters Yes No No No (in FSAR Ch. 2)

Part 2: Safety Analysis Report - Tier 2 Yes Yes Yes Yes Part 3: Environmental Report Yes No No No Part 4: Technical Specifications Yes No Yes Yes Part 5: Emergency Plans Optional (Limited Scope) Not in NuScale No No No DCA Part 6: Security Plans Optional (Limited Scope) Not in NuScale No No No DCA Part 7: Exemptions, Departures, and Variances Yes, if Applicable Yes, if Applicable N/A Yes - Exemptions Part 8: License Conditions; Inspections, Tests, Yes, (ITAAC only) NuScale DCA No Yes (only ITAAC) Yes (only ITAAC)

Analyses and Acceptance Criteria references Part 2 Tier 1 Part 9: Withheld Information Yes, NuScale DCA provides list of tables Yes N/A Yes and figures Part 10: Quality Assurance Program Description Yes, NuScale DCA references separate Yes Yes Yes topical report Part 11: Supplemental Information Yes, if applicable No No No (e.g., Limited Work Authorization) None for NuScale DCA Gold - differences from DCA Green - Included for COLA PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

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Site Design Changes

Reduced footprint Balance of Site Equipment

Dry cooling via air-cooled condensers Reactor Building

Single (1x6) turbine building Central Utilities Building o Rather than two (2x3) Control Building

Conforming site layout changes Annex Building Radwaste Building Turbine Building Onsite Warehouse Substation Transmission Air-cooled Condensers Towers PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 9

Biological Reactor RXB Design Changes Refueling Building Shield Machine Crane

Six modules o 2x3 configuration Ground

Reclassify seismic class of RXB Surface o Some floor and roof slabs are SC-II

Steel plate composite walls (from reinforced concrete) o Supported by the BDAM LTR

Lower Pool Level o Improves long term cooling, while still maintaining SFP and ECCS coverage. Allows room to re-arrange CNV penetrations.

Reduction in sizes and quantities of SSC in RXB Reactor Reactor Pool

Conforming changes - i.e., RBC, Bioshield Spent Fuel Vessel NuScale Containment Power Module Pool Flange Tool

COL Items for spent fuel storage racks, reactor flange Vessel tool. Flange Tool PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 11 NPM Design Changes

Increased Power Level (250MWth from 160MWth) steam line o Includes conforming changes (e.g., pressures, temperatures) feedwater line o Safety-related and risk significant containment vessel o Re-performing safety analyses in SDAA reactor vessel

Lower RPV material change from SA-508 low alloy SS to FXM-19 austenitic SS pressurizer o No expected radiation embrittlement, allows removal of the RPV support lug surveillance program steam generator

Upper CNV Material change from SA-508 low alloy SS to F6NM martensitic SS feedwater header o Stronger material allows for higher design pressure with reduced wall thickness and no need for cladding reactor core module support skirt PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 12 Module Protection System Setpoints for Design Basis Events Setpoints with Changes DCA SDAA Setpoints without Changes High Power (% RTP) [for <15% RTP] 25 High Power (% RTP) [for 15% RTP] 120 115 Source and Intermediate Range Log Power Rate 3 High RCS Hot Temperature (°F) 610 620 (decades per min)

High RCS Average Temperature (°F) N/A 555 High Power Rate (+/-% RTP per min) 15 High Source Range Count Rate (counts per sec) 5.0E+05 High Pressurizer Pressure (psia) 2000 2100 High Subcritical Multiplication 3.2 Low Pressurizer Pressure (psia) 1720 1850 High Containment Pressure (psia) 9.5 Low Low Pressurizer Pressure (psia) 1600 1200 High Pressurizer Level (%) 80 Low Low Pressurizer Level (%) 20 15 Low Pressurizer Level (%) 35 Low Low Main Steam Pressure (psia)* 20 High Main Steam Pressure (psia) 800 1200 Low Main Steam Pressure (psia)* 300 Low RCS Flow (ft3/sec) 1.7 1.0 High Main Steam Superheat (°F) 150 High CNV Water Level (inches) 240 - 264 N/A Low Main Steam Superheat (°F) 0 Low RCS Pressure (psia) 800 N/A Low Low RCS Flow (ft3/sec) 0 Low RPV Riser Level (inches) N/A 540 - 552 Low AC Voltage (seconds) 60 High Under-the-Bioshield Temperature (°F) 250 Low Low RPV Riser Level (inches) N/A 460 - 472

In SDAA, the setpoint bypass is changed from RTP=15% to Thot=500 °F PM-135236 Rev. 0 Copyright © 2023 NuScale Power, LLC.

NuScale Nonproprietary 14 SDAA Topical Reports

Approved Topical Reports

Acceptance Review ongoing o Nuclear Analysis Codes and Methods (NACM) o Quality Assurance Program Description (QAPD) o Highly Integrated Protection System (HIPS)

Platform o LOCA Analysis Methodology o Accident Source Term (AST) o Non-LOCA Analyses Methodology o Risk Significance Determination o Density Wave Oscillation (DWO) o Control Room Staffing o Extended Passive Cooling and Reactivity o Soil-Structure-Fluid Interaction Control o Building Design and Analysis Methodology (BDAM) o Framatome Fuel Methodologies Applicability o Evaluation Model for Stability Analyses

Under NRC review o Critical Heat Flux (CHF) o Statistical Subchannel Analysis Methodology o Rod-Ejection Analysis (REA)

NuScale Nonproprietary 16 SDAA Technical Reports (by Chapter)

Pipe Rupture Hazards (3)

Fluence Calculation Methodology and Results (5)

Containment Vessel Ultimate Pressure Integrity (3)

Containment Leakage Integrity Assurance (6)

US460 NPM Seismic Analysis (3)

Instrument Setpoint Methodology (7)

NuScale CVAP Analysis (3)

Effluent Release (GALE Replacement)

Methodology and results (11)

NuScale CVAP Measurement and Inspection Plan (3)

NuScale Design of Physical Security System (13)

NPM Short-Term Transient Analysis (3)

Treatment of DC Power in Safety Analyses (15)

NuFuel-HTP2TM Fuel and CRA Designs (4)

US460 SDAA Technical Specification

Use of Austenitic Stainless Steel for NPM Lower Development (16)

Reactor Pressure Vessel (5)

Human Factor Engineering and Concept of

Pressure and Temperature Limits Methodology (5)

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