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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 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com Docket No.52-050 February 14, 2023 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)

LO-135022 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360.0500 Fax 541.207.3928 www.nuscalepower.com

Enclosure:

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

NuScale Nonproprietary ACRS Presentation (Open Session)

February 15th, 2023 US460 Design and SDAA Overview Update Tom Griffith Licensing Manager, Acting - SDAA Kristopher Cummings Licensing Engineer V Brian Meadors Chief Engineer, Regulatory Affairs

NuScale Nonproprietary 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

NuScale Nonproprietary 4

High Level Design Changes 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.

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 Standard Design Approval (SDA) Application Content

NuScale Nonproprietary SDA Application Content APPLICATION PART DESIGN CERTIFICATION (10 CFR 52 subpart B)

SDAA - Required by Regulation (10 CFR 52 subpart E)

SDAA - Needed to Support COL Include as Part of SDAA 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 and ITAAC Yes No ITAAC Only ITAAC Only (see Part 08)

Ch. 3 - Shared SSCs and Non-SSCs Design Descriptions and ITAAC Yes No ITAAC Only ITAAC Only (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 DCA No No No Part 6: Security Plans Optional (Limited Scope) Not in NuScale DCA No No No Part 7: Exemptions, Departures, and Variances Yes, if Applicable Yes, if Applicable N/A Yes - Exemptions Part 8: License Conditions; Inspections, Tests, Analyses and Acceptance Criteria Yes, (ITAAC only) NuScale DCA references Part 2 Tier 1 No Yes (only ITAAC)

Yes (only ITAAC)

Part 9: Withheld Information Yes, NuScale DCA provides list of tables and figures Yes N/A Yes Part 10: Quality Assurance Program Description Yes, NuScale DCA references separate topical report Yes Yes Yes Part 11: Supplemental Information (e.g., Limited Work Authorization)

Yes, if applicable None for NuScale DCA No No No Gold - differences from DCA Green - Included for COLA

NuScale Nonproprietary US460 Design Changes

NuScale Nonproprietary Site Design Changes

Reduced footprint

Dry cooling via air-cooled condensers

Single (1x6) turbine building o Rather than two (2x3)

Conforming site layout changes Balance of Site Equipment Central Utilities Building Annex Building Radwaste Building Turbine Building Onsite Warehouse Air-cooled Condensers Substation Control Building Transmission Towers Reactor Building

NuScale Nonproprietary RXB Design Changes

Six modules o 2x3 configuration

Reclassify seismic class of RXB 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

Conforming changes - i.e., RBC, Bioshield

COL Items for spent fuel storage racks, reactor flange tool.

Reactor Building Crane Refueling Machine Biological Shield Reactor Pool Reactor Vessel Flange Tool NuScale Power Module Spent Fuel Pool Ground Surface Containment Vessel Flange Tool

NuScale Nonproprietary Reactor Building Overhead View

NuScale Nonproprietary NPM Design Changes

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

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

Upper CNV Material change from SA-508 low alloy SS to F6NM martensitic SS o Stronger material allows for higher design pressure with reduced wall thickness and no need for cladding steam line feedwater line containment vessel reactor vessel pressurizer support lug steam generator feedwater header reactor core module support skirt

NuScale Nonproprietary Module Protection System Setpoints for Design Basis Events Setpoints with Changes DCA SDAA High Power (% RTP) [for 15% RTP]

120 115 High RCS Hot Temperature (°F) 610 620 High RCS Average Temperature (°F)

N/A 555 High Pressurizer Pressure (psia) 2000 2100 Low Pressurizer Pressure (psia) 1720 1850 Low Low Pressurizer Pressure (psia) 1600 1200 Low Low Pressurizer Level (%)

20 15 High Main Steam Pressure (psia) 800 1200 Low RCS Flow (ft3/sec) 1.7 1.0 High CNV Water Level (inches) 240 - 264 N/A Low RCS Pressure (psia) 800 N/A Low RPV Riser Level (inches)

N/A 540 - 552 Low Low RPV Riser Level (inches)

N/A 460 - 472 Setpoints without Changes High Power (% RTP) [for <15% RTP]

25 Source and Intermediate Range Log Power Rate (decades per min) 3 High Power Rate (+/-% RTP per min) 15 High Source Range Count Rate (counts per sec) 5.0E+05 High Subcritical Multiplication 3.2 High Containment Pressure (psia) 9.5 High Pressurizer Level (%)

80 Low Pressurizer Level (%)

35 Low Low Main Steam Pressure (psia)*

20 Low Main Steam Pressure (psia)*

300 High Main Steam Superheat (°F) 150 Low Main Steam Superheat (°F) 0 Low Low RCS Flow (ft3/sec) 0 Low AC Voltage (seconds) 60 High Under-the-Bioshield Temperature (°F) 250

In SDAA, the setpoint bypass is changed from RTP=15% to Thot=500 °F

NuScale Nonproprietary Topical Reports

NuScale Nonproprietary SDAA Topical Reports Approved Topical Reports o Nuclear Analysis Codes and Methods (NACM) o Highly Integrated Protection System (HIPS)

Platform o Accident Source Term (AST) o Risk Significance Determination o Control Room Staffing o Soil-Structure-Fluid Interaction 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)

Acceptance Review ongoing o Quality Assurance Program Description (QAPD) o LOCA Analysis Methodology o Non-LOCA Analyses Methodology o Density Wave Oscillation (DWO) o Extended Passive Cooling and Reactivity Control

NuScale Nonproprietary Technical Reports

NuScale Nonproprietary SDAA Technical Reports (by Chapter)

Pipe Rupture Hazards (3)

Containment Vessel Ultimate Pressure Integrity (3)

US460 NPM Seismic Analysis (3)

NuScale CVAP Analysis (3)

NuScale CVAP Measurement and Inspection Plan (3)

NPM Short-Term Transient Analysis (3)

NuFuel-HTP2TM Fuel and CRA Designs (4)

Use of Austenitic Stainless Steel for NPM Lower Reactor Pressure Vessel (5)

Pressure and Temperature Limits Methodology (5)

Fluence Calculation Methodology and Results (5)

Containment Leakage Integrity Assurance (6)

Instrument Setpoint Methodology (7)

Effluent Release (GALE Replacement)

Methodology and results (11)

NuScale Design of Physical Security System (13)

Treatment of DC Power in Safety Analyses (15)

US460 SDAA Technical Specification Development (16)

Human Factor Engineering and Concept of Operations (18) - 10 Technical Reports

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