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.

Sincere ly, ~

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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

NuScale Nonproprietary ACRS Presentation:

NuScale Chapters 4 and 5 Full Committee May 02, 2019 PM-0519-65402 Revision : O Copyrig ht 2018 by NuScale Power, LLC .

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Presentation Team Ben Bristol Supervisor, System Thermal Hydraulics Colin Sexton Chemical Engineer Rebecca Norris Supervisor, Licensing Matthew Presson Project Manager, Licensing 2

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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

LTOP 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 SG TUBES

Inspection Rl:N 01/EAfl !:

A.CC SS COVER 8

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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:

Develop and implement a SG Program) 9 PM-0519-65402 Revisio n: O Copyright 201 9 by NuScale Power, LLC.

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5.4.1 - Steam Generators UPPEIR SG SlJ PO.

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Tube supports

FIV (3.9.2) l0W8R SG SUPP ORT 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

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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

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

§ High Pressurizer Pressure Always Enabled

§ High RCS Hot Temperature Always Enabled

§ Low AC Voltage Always Enabled

§ High Main Steam Pressure Always Enabled Secondary Isolation Signals

§ Low-Low Pressurizer Level Enabled with CNV Level < 45'

§ Low-Low Pressurizer Pressure Enabled at RCS > 420 °F

§ High Containment Pressure Enable with RCS> 350°F

§ High UTB Temperature Always Enabled

§ Low Main Steam Pressure Enabled at Power > 15%

§ Low-Low Main Steam Pressure Enabled with CNV Level < 45'

§ High Main Steam Superheat 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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5.4.5 - Pressurizer

Integral to the reactor PZR Spray Nozzle (2)----"4-----~

Baffle plate separates PZR from PZR Region .___ -it-------~

RCS

Pressure controlled by heaters/spray PZR Heater

Level controlled by Bundles (2) eves

Highpoint degas line can be used during normal operation PZR Baffle Plate 15 PM-0519-65402 a!

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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-05 19-65402

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NSSS Sensor Performance Requirements (RAI 9005 Response)

Safety/Risk Sensor Response Safety-Related NSSS Sensor Location ' Sensor Type Sensor Accuracy I Classification Time Temperature Measurements Narrow range (NR) reactor top of downcomer Resistance Temperature coolant system (RCS) Hot A1 Category I +/- o.s°F s 6 seconds EQ Zone C Detector (RTD)

Temperature Wide Range (WR) RCS Hot top of downcomer RTD A1 Category I +/- 0.7°F s 6 seconds Temperature EQ Zone C downcomer below SG WR RCS Cold Temperature RTD A2 Category I +/- 0.7°F s 6 seconds EQ Zone B Upstream of main steam isolation valve (MSIV) on main steam (MS)

Main Steam Temperature RTD A1 Category I +/- 0.7°F s 6 seconds pipe EQ Zone G Under-the-bioshield Under the bioshield RTD A1 Category I +/- 0.7°F s 6 seconds Temperature EQ Zone G Pressure Measurements near top of PZR in CNV Transducer with remote +/- 2.6% Calibrated Pressurizer (PZR) Pressure A1 Category I s 0.4 seconds EQ Zone D electronics Span near top of PZR in CNV Transdu ce r with remote +/- 5.2% Calibrated WR RCS Pressure A2 Category I s 0.4 seconds EQ Zone D electronics Span upper part of CNV Transdu ce r with remote +/- 2.6% Calibrated NR CNT Pressure A1 Category I s 0.4 seconds EQ Zone F electronics Span Upstream of MSIVs on DHRS Tee Conventional pressure +/- 1.0% Calibrated Main Steam Pressure A1 Category I s 0.5 seconds EQ Zone G transmitter Span Level Measurements PZR Level/ Reactor Pressure above core to top of PZR +/- 2.0% Calibrated Radar A1 Category I s 2.0 seconds Vessel (RPV) Riser Level EQ Zone C/D Span above RRVs to top of CNV +/- 2.0% Calibrated CNT Water Level Radar A1 Category I s 2.0 seconds EQ Zone A-F Span downcomer below SGs +/- 5.0% Calibrated RCS Flow Ultrasonic transducer A1 Category I s 1.0 seconds EQ Zone B Span 17 PM-0519-65402

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NuScale Nonproprietary NuScale Chapter 4, Reactor Summary May 02, 2019 PM-0519-65402 *~! NUSCALE .

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Summary Description

160 MW Thermal Integral Natural Circulation PWR

37 NuFuelHTP2' Fuel Assemblies

16 Hybrid AIC/B 4 C 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

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Control Rod Design

CRA design based on proven US 17x17 PWR Technology C-njltoCADM

- Hybrid design - B4 C and AIC absorbers SPfine Retelnier Bott

- 24 control rods with Stainless Steel cladding

- One-piece cast stainless steel spider

- Standard 17x17 rod configuration .... Joint Sprin& Retainer

- Flex joint formed by the combination of the pin ,

nut, upper end plug and spider boss 20 PM-05 19-65402

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Nuclear Design

Fuel Cycle Design 2-yea r, 3-batch cycle Out-to-in fuel shuffle Gadolinia burnable absorber

Equilibrium Core A-02 A-01 A-02 Reference design and analysis in DCA Equi li brium core design is A-01 C-03 A-01 representative ; used for demonstration of methods A-02 A-01 A-02 Limits placed on this core design are applied to the design of all cycles Initial , transition, and equilibrium cycles must meet analyzed limits A-01 : Batch A Type 1, 4.05 wt% 235 U 235 A-02 : Batch A Type 2, 4 .55 wt% U, with Gadolinia 235 B-01: Batch B Type 1, 4 .05 wt% U B-02: Batch B Type 2, 4 .55 wt% 235 U, with Gadolinia 235 C-01: Batch C Type 1. 4.05 wt% U 235 C-02: Batch C Type 2, 4.55 wt% U, with Gadolinia 235 C-03: Batch C Type 3, 2.60 wt% U A - Twice burned, B - Once burned, C - Fresh 21 PM-0519-65402

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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 225 I I I Axial Offset Window Power Dependent Insertion Limits

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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/B 4 C Control Rods NuScale Reactor Design Parameters Key Reactor Parameter Value Core thermal output (MWt) 160 System pressure (psia) 1850 Inlet temperature (°F) 497 Core average temperature (°F) 543 Average temperature rise in core (°F) 100 Best estimate flow (lb/hr) 4.66E+06 Core bypass flow (%)(best estimate) 7.3 Average linear power density (kw/ft) 2.5 Peak linear power for normal operating conditions (kw/ft) 5 Normal operation peak heat flux (Btu/hr-ft2) 170,088 Total heat flux hot channel factor, FQ 2 Heat transfer area on fuel surface (ft2) 6275.6 Normal operation core average heat flux (Btu/hr-ft2) 85,044 Core flow area (ft2) 9.79 Core average coolant velocity (ft/sec) 2.7 24 PM-0519-65402 Revisio n: O Copyright 201 9 by NuScale Power, LLC .

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Design Basis TR-0116-20825-P-A, Rev. 1, Applicability of AREVA Fuel Methodology for the NuScale Design SRP Criteria Review Summary SRP 4 .2 Acceptance Analysis 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 EMF-92-116(P)(A)

Axial Growth (Rod and Assembly) 1.A.v 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 BAW-10231P-A Fuel Centerline Melt Analysis 1.B.iv Transient Clad Strain Analysis 1.B.vi BAW-10084P-A Clad Creep Collapse Analysis 1.B.ii BAW-10227P-A Rod Bow Evaluation 1.A.v XN-75-32(P)(A) 25 PM-0519-65402 Revision : O Copyright 20 19 by NuScale Power, LLC .

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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]

NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces 26 PM-0519-65402

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Acronyms

AOO -Anticipated Operational

EPRI - Electric Power Research Institute Occurrences

°F - degrees Fahrenheit

ASME -American Society of Mechanical Engineers

FIV - Flow Induced Vibration

ASTM -American Society for Testing and

FSAR - Final Safety Analysis Report Materials

ft - feet

BPVC - Boiler Pressure Vessel Code

FW - Feedwater

CES - Containment Evacuation System

FWIV - Feedwater Isolation Valve

CIV - Containment Isolation Valve

HZP - Hot Zero Power

CNV - Containment Vessel

ISi - lnservice Inspection

COL - Combined License

LOCA - Loss of Coolant Accident

CROM - Control Rod Drive Mechanism

LTOP - Low Temperature Overpressure Protection

eves - Chemical and Volume Control System

MPS - Module Protection System

DHRS - Decay Heat Removal System

MSIV - Main Steam Isolation Valve

ECCS - Emergency Core Cooling System

MSS - Main Steam System

EFPY - Effective Full Power Years

MWt - Megawatts thermal 27 PM-0519-65402

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Acronyms

NDE - Non-destructive Examination

RCPB - Reactor Coolant Pressure Boundary

NEI - Nuclear Energy Institute

RCS - Reactor Coolant System

NPM - NuScale Power Module

RG - Regulatory Guide

NPS - Nominal Pipe Size

RPV - Reactor Pressure Vessel

OD - Outside Diameter

RSV - Reactor Safety Valve

OE - Operations Experience

RT NOT - Reference Temperature for Nil-

ps ia - pounds per square inch absolute ductility Transition

P-T - Pressure and Temperature

RVV - Reactor Vent Valve

PTS - Pressurized Thermal Shock

SG - Steam Generator

PWR - Pressurized Water Reactor

TRV - Thermal Relief Valve

PWSCC - Primary Water Stress-Corrosion

TS - Technical Specifications Cracking

TT - Thermally Treated

PZR - Pressurizer

UHS - Ultimate Heat Sink

RCCWS - Reactor Component Cooling Water System

USE - Upper Shelf Energy 28 PM-0519-65402

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Portland Office Richland Office 6650 SW Redwood Lane, 1933 Jadwin Ave., Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541 .360.0500 971 .371 .1592 Arlington Office Corvallis Office 2300 Clarendon Blvd. , Suite 1110 1100 NE Circle Blvd., Suite 200 Arlington, VA 22201 Corvallis, OR 97330 541 . 360.0500 London Office 1st Floor Portland House Rockville Office Bressenden Place 11333 Woodglen Ave., Suite 205 London SW1 E 5BH Rockville, MD 20852 United Kingdom 301. 770.0472 +44 (0) 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980.349.4804 http://www. nuscalepower. com "JI Twitter: @NuScale_Power NUSCALE '

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ML19123A096

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