acrs presentation: nuscale chapter 5, reactor coolant ... · l0-0419-65158 enclosure 1: "acrs...

L0-0419-65158

Enclosure 1:

"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

PM-0419-65159

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NuScale Nonproprietary

ACRS Presentation:

NuScale Chapter 5,

Reactor Coolant System

and

Connecting

Systems Overview

Copyright 2018 by NuScale Power, LLC. M ~~.?.~A~§-

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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

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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

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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

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5.1 - Summary Description RPV Parameters

Parameter

Design thermal Power, MWt

Design Pressure, psia

Design Temperature, °F

Overall Height (ft)

Inside diameter (excluding clad) (ft)

RCS Volumes

RCS Region

Hot Leg

Cold Leg

Core Region

SG Region

PZR Region

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Nominal Volume (ft3)

635

578

89

621

578

Copyright 2019 by NuScale Power, LLC.

Value

160

2100

650

64.83

8.04 - 8.88

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5.1 - Summary Description RCS temperature and flow data

620

580

Ci:' e...... 540 (1) '-::l

ro '- 500 (1) a. E (1) f-

460

--T_Hot - T_Cold --T_Ave • T _Cold for Maximum Flow

420 0 20 40 60

700

600

en 500 Cl ~ 400 3: 0

u::: 300 C" Cll E 200 ·;::

Q.

100 Primary Flow • Minimum Flow • Maximum Flow

0 0 20 40 60

Reactor Power(%)

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• •

• T_Cold for Minimum Flow

80 100

•

•

80 100

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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

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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

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5.3.1 - Reactor Vessel Materials

CROM seismic support structure- fabricated per ASME BPVC Section Ill, NF

RPV shell is fabricated per requirements of ASME BPVC Section Ill , NB --~ ·

RPV supports - fabricated per ASME BPVC Section Ill, NF

- .=--,..,

SG tube supports -fabricated per ASME BPVC / Section Ill, NG


SUPPORT ASSEMBLY

LO'NER SG SUPPORT

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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

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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 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

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5.4.1

REMOVABLE ACCESS, cov~s

• Pressure drop

• Heat transfer

• Inspection

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- Steam Generators

SGTUBES

ET

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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:

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Develop and implement a SG Program)

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• Tube supports

• FIV (3.9.2)

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UPPERSGSUFro

8RSGSU PO

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riot

• Limit flow oscillations 19

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--ruinuntln Pi te cer

Flow Restrictor Bolt

Flow Restrictor

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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

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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

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Thermal-Hydraulic Performance dependent on:

• RCS temperature

• Reactor pool water temperature

• Water inventory

• Noncondensable gas accumulation

• Pressure losses

• Driving head

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Nominal two train cool down (4 hour duration)

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.~ .... a..

550

500

450

400

350

300

250 '---~~---'-~~~__,,_~~---''--~~-'-~~~_.__~~-----'~~~-'--' 0 2000 4000 6000 8000

Hot Leg Cold Leg

Time (sec)


10000 12000 14000

Average JI(

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• Integral to the Reactor

5.4.5 - Pressurizer

PZR Spray

• Baffle plate separates PZR from RCS

Nozzle (2)---H+----~

• Pressure controlled by heaters/sprays

• Level controlled by eves

• Highpoint degas line can be used during normal operation

PZR Region ----.--,}-----...~

PZR Heater Bundles (2)

PZR Baffle Plate

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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

• 151 - 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 NDT - 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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