ML19105A135

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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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L0-0419-65158 :

"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 Revision: O NuScale Nonproprietary ACRS Presentation:

NuScale Chapter 5, Reactor Coolant System and Connecting Systems Overview Copyright 2018 by NuScale Power, LLC.

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2 PM-041 9-65159 Revision: O 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 Copyright 2018 by NuScale Power, LLC.

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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

  • 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 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 5

PM-0419-65159 Revision: 0 Nominal Volume (ft3) 635 578 89 621 578 Copyright 2019 by NuScale Power, LLC.

Value 160 2100 650 64.83 8.04 - 8.88 M

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

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--T_Hot T_Cold -- T_Ave T _Cold for Maximum Flow 420 0

20 40 60 700 600 en 500 Cl

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100 Primary Flow Minimum Flow Maximum Flow 0

0 20 40 60 Reactor Power(%)

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

T_Cold for Minimum Flow 80 100 80 100 a! NUSCALE..

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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

  • 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 9

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10 PM-041 9-65159 Revision: O 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

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  • RPV supports - fabricated per ASME BPVC Section Ill, NF

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SG tube supports -

fabricated per ASME BPVC /

Section Ill, NG Copyright 2019 by NuScale Power, LLC.

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"

- 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 a! NUSCALE..

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5.2.3 - Reactor Coolant Pressure Boundary Materials

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

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5.4.1 REMOVABLE

ACCESS, cov~s
  • Pressure drop
  • Heat transfer

- Steam Generators SGTUBES ET 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:

17 PM-0419-65159 Revision: O Develop and implement a SG Program)

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5.4.1 - Steam Generators

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5.4.1 - Steam Generators riot

  • Limit flow oscillations 19 PM-041 9-65159 Revision: O Copyright 2019 by NuScale 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
  • 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 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
  • Pressure losses

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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) 23 PM-0419-65159 Revision: O G:'"

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0 2000 4000 6000 8000 Hot Leg Cold Leg Time (sec)

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

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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
  • eves - Chemical and Volume Control System
  • EFPY - Effective Full Power Years
  • EPRI - Electric Power Research Institute
  • °F - degrees Fahrenheit
  • FSAR - Final Safety Analysis Report
  • ft-feet
  • HZP - Hot Zero Power
  • 151 - lnservice Inspection
  • LOCA - Loss of Coolant Accident
  • LTOP - Low Temperature Overpressure Protection
  • MPS - Module Protection System
  • MWt - Megawatts thermal a! NUSCALE..

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Acronyms

  • 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
  • RG - Regulatory Guide
  • RSV - Reactor Safety Valve
  • RT NDT - Reference Temperature for nil-ductility transition
  • RVV - Reactor Vent Valve
  • TRV - Thermal Relief Valve
  • TS - Technical Specifications
  • TT - Thermally Treated
  • USE - Upper Shelf Energy 26 PM-0419-65159 Revision: 0 Copyright 2019 by NuScale Power, LLC.

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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 SW1E 5BH United Kingdom

+44 (OJ 2079 321700 http://www. nuscalepower. com "JI Twitter: @NuScale_Power 27 PM-041 9-65159 Revision: O Copyright 2018 by NuScale Power, LLC.

NUSCALE' Power for a ll humankind

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