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ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview, PM-0419-65159, Revision 0
	ML19105A135
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Issue date:	04/11/2019
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"ACRS Presentation: NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview,"

PM-0419-65159 , 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

NuScale Nonproprietary ACRS Presentation:

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Presentation Team Derek Noel Supervisor, NSSS Component Design Colin Sexton Chemical Engineer Hongqing Xu Materials Engineer Carrie Fosaaen Supervisor, Licensing Zackary Rad Director, Regulatory Affairs 2

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Chapter 5: Reactor Coolant System and Connecting Systems Section Title 5.1 Summary Description 5.2 Integrity of Reactor Coolant Boundary 5.3 Reactor Vessel 5.4 Reactor Coolant System Component and Subsystem Design 3

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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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5.1 - Summary Description RPV Parameters Parameter Value Design thermal Power, MWt 160 Design Pressure, psia 2100 Design Temperature, °F 650 Overall Height (ft) 64.83 Inside diameter (excluding clad) (ft) 8.04 - 8.88 RCS Volumes RCS Region Nominal Volume (ft3 )

Hot Leg 635 Cold Leg 578 Core Region 89 SG Region 621 PZR Region 578 5

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5.1 - Summary Description RCS temperature and flow data 620 580 Ci:'

e...... 540 (1)

l ro (1) 500 a.

E (1) f-460

- - T_Hot - T_Cold - - T_Ave

T_Cold for Maximum Flow

T_Cold for Minimum Flow 420 0 20 40 60 80 100 700 600 en 500

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Cll E 200 Q.

100 Primary Flow

Minimum Flow

Maximum Flow 0

0 20 40 60 80 100 Reactor Power(%)

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5.2 - Integrity of Reactor Coolant Boundary Section Title 5.2.1 Compliance with Codes and Code Cases 5.2.2 Overpressure Protection 5.2.3 Reactor Coolant Pressure Boundary Materials (5.3 - Reactor Vessel also discussed here) 5.2.4 Reactor Coolant Pressure Boundary lnservice Inspection and Testing 5.2.5 Reactor Coolant Pressure Boundary Leakage Detection 7

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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 9

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5.3.1 - Reactor Vessel Materials CROM seismic support structure- fabricated per ASME BPVC Section Ill, NF SUPPORT ASSEMBLY RPV shell is fabricated per requirements of ASME BPVC Section Ill , NB --~ *

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RPV supports - fabricated per ASME BPVC Section Ill, NF SG tube supports -

LO'NER SG SUPPORT fabricated per ASME BPVC /

Section Ill, NG 10 PM-041 9-65 159

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5.3.1 & 5.3.2- RPV Materials & P/T Limits, Pressurized Thermal Shock, and Charpy Upper-Shelf Energy Data and Analyses

Fracture Toughness requirements, Material Surveillance requirements, Pressurized Thermal Shock screening, and Upper-Shelf Energy comply with regulatory requirements

Limit Curves Methodology in TR-1015-18177, "Pressure and Temperature Limits Methodology"

COL Items:

- 5.3-1: Establish measures to control the onsite cleaning of the RPV during construction in accordance with RG 1.28

- 5.3-2: Develop operating procedures to ensure that transients will not be more severe than those for which the reactor design adequacy had been demonstrated. These procedures will be based on material properties of the as-built reactor vessels.

- 5.3-3: Describe the reactor vessel material surveillance program consistent with NUREG 0800, Section 5.3.1 11 PM-0419-65159 a! NUSCALE .

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5.2.3 - Reactor Coolant Pressure Boundary Materials

Reactor Coolant Chemistry parameters and impurity limitations conform to EPRI PWR Primary Water Chemistry Guidelines and RG 1.44, Revision 1

COL Items:

- 5.2-4: Develop and implement a Strategic Water Chemistry Plan consistent with the latest version of the EPRI Pressurized Water Reactor Primary Water Chemistry Guidelines.

- 5.2-5: Develop and implement a Boric Acid Control Program that includes: inspection elements to ensure the integrity of the RCPB components for subsequent service, monitoring of the containment atmosphere for evidence of RCS leakage, the type of visual or other NOE inspections to be performed, and the required inspection frequency.

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5.2.4 - Reactor Coolant Pressure Boundary lnservice Inspection and Testing Inspections per ASME BPVC,Section XI

Applicable to ASME BPVC Class I components except for SG tubes

- ISi of SG tubes covered by SG Program COL Item:

5.2-6: Develop a site-specific preservice examination, inservice inspection, and inservice testing program plans in accordance with Section XI of the ASME BPVC and will establish implementation milestones. Identify the implementation milestone for the augmented inservice inspection program.

Identify the applicable edition of the ASME Code utilized in the program plans consistent with the requirements of 10 CFR 50.55a.

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5.2.5 - Reactor Coolant Pressure Boundary Leakage Detection Leakage Detection Methods

- CES 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 14 are reached.

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5.4 - Reactor Coolant System Component and Subsystem Design Section Title 5.4.1 Steam Generators 5.4.2 Reactor Coolant System Piping 5.4.3 Decay Heat Removal System 5.4.4 Reactor Coolant System High-Point Vents (not discussed) 5.4.5 Pressurizer 15 PM-0419-65159 Revision : O Copyright 2019 by NuScale Power, LLC .

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5.4.1 - Steam Generators REMOVABLE ACCESS, cov~s

Pressure drop

Heat transfer SGTUBES

Inspection ET 16 PM-0419-65159 Revisio n: 0 Copyright 2019 by NuScale Power, LLC .

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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) 17 PM-0419-65159 Revision : O Copyright 20 19 by NuScale Power, LLC .

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5.4.1 - Steam Generators UPPERSGSUFro

Tube supports

FIV (3.9.2) 8RSGSU PO 18 PM-0419-65159 Revision : O Copyright 2019 by NuScale Power, LLC .

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5.4.1 - Steam Generators

- -ruinuntln Pi te cer riot Flow Restrictor Bolt Flow Restrictor

Limit flow oscillations 19 PM-041 9-65159 Revision : O Copyright 2019 by NuSca le Power, LLC.

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5.4.2 - Reactor Coolant System Piping RCS Piping Design

NPS 2 - Schedule 160

Austenitic stainless steel - SA-312 , Type 304/304L (dual certified)

RCS Piping Includes:

Pressurizer spray supply

RCS injection

RCS discharge

RPV high-point degasification piping 20 PM-0419-65159 Revision : 0 Copyright 2019 by Nu Scale 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 21 PM-0419-65159 a!

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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 22 PM-0419-65159 Revision : O Copyright 2019 by NuScale Power, LLC .

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5.4.3 - Decay Heat Removal System Nominal two train cool down (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duration) 550 G:'"

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a.. 350 300 250 '---~~---'-~~~__,,_~~-----~~-'-~~~_.__~~-----'~~~-'--'

0 2000 4000 6000 8000 10000 12000 14000 Time (sec)

Hot Leg Average JI(

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5.4.5 - Pressurizer

Integral to the Reactor PZR Spray Nozzle (2)---H+----~

Baffle plate separates PZR from PZR Region ----.--,}-----...~

RCS

Pressure controlled by heaters/sprays PZR Heater

Level controlled by Bundles (2) eves

Highpoint degas line can be used during normal operation PZR Baffle Plate 24 PM-0419-65159 a!

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Acronyms

AOO -Anticipated Operational

EPRI - Electric Power Research Institute Occurrences

°F - degrees Fahrenheit

ASME - American Society of Mechanical

FIV - Flow Induced Vibration Engineers

FSAR - Final Safety Analysis Report

ASTM - American Society for Testing and 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

151 - 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 25 PM-0419-65159 a!

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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 NDT - Reference Temperature for nil-

psia - 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 26 PM-0419-65159 Revision: 0 Copyright 2019 by NuScale Power, LLC.

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