Text

LLC - Submittal of Presentation Materials Entitled ACRS Presentation: NuScale Chapters 4 and 5 Full Committee, PM-0519-65402, Revision 0
	ML19123A096
Person / Time
Site:	NuScale
Issue date:	05/01/2019
From:	Rad Z; NuScale
To:	; Document Control Desk, Office of New Reactors
References
	LO-0519-65403
	Download: ML19123A096 (31)
	v • d • e

L0-0519-65403 May 1, 2019 Docket No.52-048 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 "ACRS Presentation: NuScale Chapters 4 and 5 Full Committee," PM-0519-65402, Revision 0 The purpose of this submittal is to provide presentation materials for use during the upcoming Advisory Committee on Reactor Safeguards (ACRS) Full Committee meeting on May 2, 2019. The materials support NuScale's presentation of Chapter 4, "Reactor Summary," and Chapter 5, "Reactor Coolant System and Connecting Systems Overview," of the NuScale Design Certification Application. is the presentation entitled "ACRS Presentation: NuScale Chapters 4 and 5 Full Committee," PM-0519-65402, Revision 0.

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

If you have any questions, please contact Rebecca Norris at 541 -452-7539 or at rnorris@nuscalepower.com.

Sincerely,

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Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Robert Taylor, NRC, OWFN-8G9A Michael Snodderly, NRC, TWFN-2E26 Christopher Brown, NRC, TWFN-2E26 Samuel Lee, NRC, OWFN-8G9A Gregory Cranston, NRC, OWFN-8G9A Bruce Bavol, NRC, OWFN-8G9A : "ACRS Presentation: NuScale Chapters 4 and 5 Full Committee," PM-0519-65402, Revision 0 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

L0-0519-65403 :

"ACRS Presentation: NuScale Chapters 4 and 5 Full Committee," PM-0519-65402, Revision O NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

PM-0519-65402 Revision: O NuScale Nonproprietary ACRS Presentation:

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2 PM-0519-65402 Revision: O Presentation Team Ben Bristol Supervisor, System Thermal Hydraulics Colin Sexton Chemical Engineer Rebecca Norris Supervisor, Licensing Matthew Presson Project Manager, Licensing Copyright 2018 by NuScale Power, LLC.

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5.1 - Summary Description Overview of RCS Components

Reactor pressure vessel

Integral pressurizer

Reactor vessel internals

Reactor safety valves

RCS piping inside the containment vessel 4

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5.2 - Integrity of Reactor Coolant Boundary 5.2.1

Code of Record -ASME BPVC, 2013 Edition with No Addenda 5.2.2

RCPB Overpressure protection provided by RSVs -

primary and secondary sides

L TOP is provided by RVVs COL Item:

5.2-2: Provide a certified Overpressure Protection Report in compliance with ASME BPVC Section Ill, Subarticles NB-7200 and NC-7200 to demonstrate the RCPB and secondary system are designed with adequate overpressure protection features, including LTOP features.

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5.2.3 - Reactor Coolant Pressure Boundary Materials Materials selected, including weld materials, conform to fabrication, construction, and testing requirements of ASME BPVC, Section Ill, Subsection NB requirements

RCPB Materials include:

- SA-508 - base metal for RPV shell components

-Alloy 690 TT - SG tubes & Safe ends

- Dual certified 304/304L-RCS piping

-Austenitic SS and Nickel based (Ni-Cr-Fe) - Cladding

-Alloy 718 - Threaded Fastener material

Fabrication follows applicable ASME Code and regulatory requirements 6

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5.2.5 - Reactor Coolant Pressure Boundary Leakage Detection Leakage Detection Methods

- C ES collected condensate

- CNV pressure

- Radioactivity Monitoring & Chemistry Analysis

- RCS Inventory Mass Balance

LBB application to secondary side piping covered in 3.6.3 COL Item:

5.2-7: Establish plant-specific procedures that specify operator actions for identifying, monitoring, and trending RCS leakage in response to prolonged low leakage conditions that exist above normal leakage rates and below the TS limits. The objective of the methods of detecting and trending the RCPB leak will be to provide the operator sufficient time to take actions before the plant TS limits are reached.

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5.4.1 - Steam Generators Re.MOVABLE

\\CCESS COVERS

Pressure drop

Heat transfer

Inspection 8

PM-0519-65402 Revision: O Rl:N 01/EAfl !:

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5.4.1 - Steam Generators

Integral Helical Coil SG Design features

- Shell side is primary side - Tube side is secondary side

- Alloy 690 TT (1380 tubes, 77 - 87ft long, 5/8" OD)

- Low flow in primary (-1ft/sec)

- Tube wall degradation allowance (0.01 O" > ASME min wall)

- Support 100°/o volumetric inspection

- Normal access to shell side of tubes from below during refueling

Incorporation of OE

- Follow guidance of NEI 97-06 & EPRI (COL Item 5.4-1:

9 PM-0519-65402 Revision: O Develop and implement a SG Program)

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5.4.1 - Steam Generators EBN

B SU RPOR -....__ -.......,_

Tube supports FIV (3.9.2) 10 PM-0519-65402 Revision: O Copyright 2019 by NuScale Power, LLC.

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5.4.3 - Decay Heat Removal System

Two phase natural circulation system connected to SG

Condensers submerged in UHS

Closed loop is established on signal or loss of power by CIV

Two independent single failure proof trains

Design pressure matches RCS design pressure 11 PM-0519-65402 Revision: 0 Copyright 2019 by NuScale Power, LLC.

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5.4.3 - Decay Heat Removal System Thermal-Hydraulic Performance dependent on:

RCS temperature

Reactor pool water temperature

Water inventory

Noncondensable gas accumulation

Pressure losses

Driving head 12 PM-0519-65402 Revision: 0 Copyright 2019 by NuScale Power, LLC.

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DHRS Protections ESFAS Signals Enable Logic Secondary Isolation Signals w/ DHRS Actuation

§ High Pressurizer Pressure

§ High RCS Hot Temperature

§ Low AC Voltage

§ High Main Steam Pressure Secondary Isolation Signals

§ Low-Low Pressurizer Level

§ Low-Low Pressurizer Pressure

§ High Containment Pressure

§ High UTB Temperature

§ Low Main Steam Pressure

§ Low-Low Main Steam Pressure

§ High Main Steam Superheat Always Enabled Always Enabled Always Enabled Always Enabled Enabled with CNV Level < 45' Enabled at RCS > 420°F Enable with RCS> 350°F Always Enabled Enabled at Power > 15%

Enabled with CNV Level < 45' Enabled with CNV Level < 45'

§ Low Main Steam Superheat Enabled with CNV Level < 45' and both FWIVs open.

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Feedwater Control Variable speed feedwater pumps control flow from 25°/o to 100°/o reactor power Feedwater regulating valve (5°/o turndown ratio) controls from 0°/o to 25°/o reactor power, and during shutdowns and startups Turbine bypass valves provide additional control Trips are followed by high temperature holds at 520°F Normal shutdowns progress at a rate of <100°F/hr to 350°F, when containment flooding begins 14 PM-0519-65402 Revision: O Copyright 2019 by NuScale Power, LLC.

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Integral to the reactor 5.4.5 - Pressurizer PZR Spray

Baffle plate separates PZR from RCS Nozzle (2)----"4-----~

Pressure controlled by heaters/spray

Level controlled by eves

Highpoint degas line can be used during normal operation PZR Region._ __ -it-------~

PZR Heater Bundles (2)

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NSSS Sensor Development Program

NuScale NSSS sensors described in NuScale Advanced Sensor Technical Report, TR-0316-22048

Sensor Development Program

- First-of-a-kind sensor applications for RCS flow, Pressurizer, RPV and CNT level, and RCS and CNT pressure applications

- Establish performance requirements as basis of safety evaluation

- Phased development program confirms performance requirements are satisfied

>> technology selection, prototype and testing, qualification, testing and manufacture

Radar selected for level sensors for continuous level measurement 16 PM-0519-65402 Revision: O Copyright 2019 by NuScale Power, LLC.

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NSSS Sensor Performance Requirements (RAI 9005 Response)

Safety-Related NSSS Sensor Narrow range (NR) reactor coolant system (RCS) Hot Temperature Wide Range (WR) RCS Hot Temperature WR RCS Cold Temperature Main Steam Temperature Under-the-bioshield Temperature Pressurizer (PZR) Pressure WR RCS Pressure NR CNT Pressure Main Steam Pressure PZR Level/ Reactor Pressure Vessel (RPV) Riser Level CNT Water Level 17 PM-0519-65402 Revision: O RCS Flow Location top of downcomer EQ Zone C top of downcomer EQ Zone C downcomer below SG EQ Zone B Upstream of main steam isolation valve (MSIV) on main steam (MS) pipe EQ Zone G Under the bioshield EQ Zone G near top of PZR in CNV EQ Zone D near top of PZR in CNV EQ Zone D upper part of CNV EQ Zone F Upstream of MSIVs on DHRS Tee EQ Zone G above core to top of PZR EQ Zone C/D above RRVs to top of CNV EQ Zone A-F downcomer below SGs EQ Zone B Sensor Type I

Safety/Risk Classification Temperature Measurements Resistance Temperature Detector (RTD)

A1 RTD A1 RTD A2 RTD A1 RTD A1 Pressure Measurements Transducer with remote electronics A1 Transducer with remote A2 electronics Transducer with remote electronics A1 Conventional pressure transmitter A1 Level Measurements Radar A1 Radar A1 Ultrasonic transducer A1 Copyright 2019 by NuScale Power, LLC.

Category I Category I Category I Category I Category I Category I Category I Category I Category I Category I Category I Category I Sensor Accuracy

+/- o.s°F

+/- 0.7°F

+/- 2.6% Calibrated Span

+/- 5.2% Calibrated Span

+/- 2.6% Calibrated Span

+/- 1.0% Calibrated Span

+/- 2.0% Calibrated Span

+/- 5.0% Calibrated Span Sensor Response Time s 6 seconds s 6 seconds s 6 seconds s 6 seconds s 6 seconds s 0.4 seconds s 0.4 seconds s 0.4 seconds s 0.5 seconds s 2.0 seconds s 2.0 seconds s 1.0 seconds

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Summary Description 160 MW Thermal Integral Natural Circulation PWR 37 NuFuelHTP2' Fuel Assemblies 16 Hybrid AIC/B4C Control Rods NuScale design based on proven US 17x17 PWR Technology Over 1500 17x17 HTP fuel assemblies with maximum burnup of 54 GWd/mTU NuScale design features:

Zircaloy-4 HTP' upper and intermediate spacer grids lnconel 718 HMP' lower spacer grid Coarse-mesh filter plate on bottom nozzle Zircaloy-4 MONOBLOC' guide tubes Quick-disconnect top nozzle Alloy MS fuel rod cladding 19 PM-051 9-65402 Revision: O Copyright 2019 by NuScale Power, LLC.

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Control Rod Design CRA design based on proven US 17x17 PWR Technology 20 PM-0519-65402 Revision: O Hybrid design - B4C and AIC absorbers 24 control rods with Stainless Steel cladding One-piece cast stainless steel spider Standard 17x17 rod configuration Flex joint formed by the combination of the pin, nut, upper end plug and spider boss Copyright 2019 by NuScale Power, LLC.

.... Joint Sprin& Retainer C-njltoCADM SPfine Retelnier Bott

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Nuclear Design Fuel Cycle Design 2-year, 3-batch cycle Out-to-in fuel shuffle Gadolinia burnable absorber Equilibrium Core Reference design and analysis in DCA Equilibrium core design is representative; used for demonstration of methods Limits placed on this core design are applied to the design of all cycles Initial, transition, and equilibrium cycles must meet analyzed limits A-02 A-01 A-02 A-01 C-03 A-01 A-02 A-01 A-02 A-01 : Batch A Type 1, 4.05 wt% 235U A-02: Batch A Type 2, 4.55 wt% 235U, with Gadolinia B-01: Batch B Type 1, 4.05 wt% 235U B-02: Batch B Type 2, 4.55 wt% 235U, with Gadolinia C-01: Batch C Type 1. 4.05 wt% 235U C-02: Batch C Type 2, 4.55 wt% 235U, with Gadolinia C-03: Batch C Type 3, 2.60 wt% 235U A - Twice burned, B - Once burned, C - Fresh 21 PM-0519-65402 Revision: O Copyright 2019 by NuScale Power, LLC.

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Core Power Distributions

Power distributions are protected by monitoring to ensure that limits are not exceeded during normal operation

Control rod assemblies (CRAs) are arranged into regulating and shutdown banks

The power dependent insertion limits (POils) and axial offset (AO) window ensure axial and radial peaking are within design limits

The NuScale power module is stable with respect to axial and radial xenon imbalances due to small core size, H/0 ratio 22 PM-0519-65402 Revision: O 225 1200

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-0.1 0.0 0.1 0.2 0.3 0.4 0.5 Axial Offset Fraction

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Pressure vs. Temperature Operation M~--

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Module protection system (Ch. 7, red )

Technical specification LCOs (Ch. 16, blue)

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Summary Description

160 MW Thermal Integral Natural Circulation PWR

37 NuFuelHTP2' Fuel Assemblies 16 Hybrid AIC/B4C Control Rods 24 PM-0519-65402 Revision: O NuScale Reactor Design Parameters Key Reactor Parameter Core thermal output (MWt)

System pressure (psia)

Inlet temperature (°F)

Core average temperature (°F)

Average temperature rise in core (°F)

Best estimate flow (lb/hr)

Core bypass flow (%)(best estimate)

Average linear power density (kw/ft)

Peak linear power for normal operating conditions (kw/ft)

Normal operation peak heat flux (Btu/hr-ft2)

Total heat flux hot channel factor, FQ Heat transfer area on fuel surface (ft2)

Normal operation core average heat flux (Btu/hr-ft2)

Core flow area (ft2)

Core average coolant velocity (ft/sec)

Copyright 201 9 by NuScale Power, LLC.

Value 160 1850 497 543 100 4.66E+06 7.3 2.5 5

170,088 2

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25 PM-0519-65402 Revision: O Design Basis TR-0116-20825-P-A, Rev. 1, Applicability of AREVA Fuel Methodology for the NuScale Design SRP Criteria Review Summary Analysis SRP 4.2 Acceptance Framatome Topical Report Criteria Shipping And Handling Stress Analysis 1.A.i Fuel Assembly/Component Stress Analysis 1.A.i FIV Assessment 1.A.iii Axial Growth (Rod and Assembly) 1.A.v EMF-92-116(P)(A)

Fuel Lift Analysis 1.A.vii Internal Hydriding 1.B.i Clad Stress Analysis 1.A.i Fuel Rod Buckling Analysis 1.A.i BAW-10227P-A Clad Fatigue Analysis 1.A.ii Clad Corrosion Analysis 1.A.iv Fuel Rod Internal Pressure 1.A.vi Fuel Centerline Melt Analysis BAW-10231P-A 1.B.iv Transient Clad Strain Analysis 1.B.vi Clad Creep Collapse Analysis 1.B.ii BAW-10084P-A BAW-10227P-A Rod Bow Evaluation 1.A.v XN-75-32(P)(A)

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26 PM-0519-65402 Revision: O Design Basis TR-0915-17564-P-A Subchannel Analysis Methodology TR-0116-21012-P-A NuScale Power Critical Heat Flux Correlations TR-0616-48793-P-A Nuclear Analysis Codes and Methods Qualification TR-0716-50350 [in review]

Rod Ejection Accident Methodology TR-0516-49417 [in review]

Evaluation Methodology for Stability Analysis of the NuScale Power Module TR-0716-50351 [in review]

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Acronyms

AOO -Anticipated Operational Occurrences

ASME -American Society of Mechanical Engineers

ASTM -American Society for Testing and Materials

BPVC - Boiler Pressure Vessel Code

CES - Containment Evacuation System

CIV - Containment Isolation Valve

CNV - Containment Vessel

COL - Combined License

CROM - Control Rod Drive Mechanism

eves - Chemical and Volume Control System

DHRS - Decay Heat Removal System

ECCS - Emergency Core Cooling System

EFPY - Effective Full Power Years

EPRI - Electric Power Research Institute

°F - degrees Fahrenheit

FIV - Flow Induced Vibration

FSAR - Final Safety Analysis Report

ft - feet

FW - Feedwater

FWIV - Feedwater Isolation Valve

HZP - Hot Zero Power

ISi - lnservice Inspection

LOCA - Loss of Coolant Accident

LTOP - Low Temperature Overpressure Protection

MPS - Module Protection System

MSIV - Main Steam Isolation Valve

MSS - Main Steam System

MWt - Megawatts thermal

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Acronyms

NDE - Non-destructive Examination

NEI - Nuclear Energy Institute

NPM - NuScale Power Module

NPS - Nominal Pipe Size

OD - Outside Diameter

OE - Operations Experience

psia - pounds per square inch absolute

P-T - Pressure and Temperature

PTS - Pressurized Thermal Shock

PWR - Pressurized Water Reactor

PWSCC - Primary Water Stress-Corrosion Cracking

PZR - Pressurizer

RCCWS - Reactor Component Cooling Water System

RCPB - Reactor Coolant Pressure Boundary

RCS - Reactor Coolant System

RG - Regulatory Guide

RPV - Reactor Pressure Vessel

RSV - Reactor Safety Valve

RT NOT - Reference Temperature for Nil-ductility Transition

RVV - Reactor Vent Valve

SG - Steam Generator

TRV - Thermal Relief Valve

TS - Technical Specifications

TT - Thermally Treated

UHS - Ultimate Heat Sink

USE - Upper Shelf Energy

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Portland Office 6650 SW Redwood Lane, Suite 210 Portland, OR 97224 971.371.1592 Corvallis Office 1100 NE Circle Blvd., Suite 200 Corvallis, OR 97330 541. 360. 0500 Rockville Office 11333 Woodglen Ave., Suite 205 Rockville, MD 20852 301. 770.0472 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980. 349. 4804 Richland Office 1933 Jadwin Ave., Suite 130 Richland, WA 99354 541.360.0500 Arlington Office 2300 Clarendon Blvd., Suite 1110 Arlington, VA 22201 London Office 1st Floor Portland House Bressenden Place London SW1 E 5BH United Kingdom

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ML19123A096

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