ML19135A064

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LLC - Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations, PM-0519-65533, Revision 0
ML19135A064
Person / Time
Site: NuScale
Issue date: 05/09/2019
From: Rad Z
NuScale
To:
Document Control Desk, Office of New Reactors
References
LO-0519-65534 PM-0519-65533, Rev 0
Download: ML19135A064 (16)


Text

L0-0519-65534 May 9, 2019 Docket No.52-048 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Submittal of Presentation Materials Entitled "ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations," PM-0519-65533, Revision 0 The purpose of this submittal is to provide presentation materials for use during the upcoming Advisory Committee on Reactor Safeguards (ACRS) NuScale Subcommittee meeting on May 15, 2019. The materials support NuScale's presentation of Chapter 21, "Multi-Module Design Considerations," of the NuScale Design Certification Application. is the nonproprietary presentation entitled "ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations," PM-0519-65533, Revision 0.

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

If you have any questions, please contact Nadja Joergensen at 541-452-7338 or at

  • njoergensen@nuscalepower.com.

Sincerely,~*~

Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Robert Taylor, NRC, OWFN-7H4 Michael Snodderly, NRC, TWFN-2E26 Gregory Cranston, NRC, OWFN-8H12 Samuel Lee, NRC, OWFN-8H12 Prosanta Chowdhury, NRC, OWFN-8H12 : "ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations," PM-0519-65533, 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

L0-0519-65534 :

"ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Considerations,"

PM-0519-65533, 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-0519-65533 Revision: O NuScale Nonproprietary ACRS Subcommittee Presentation NuScale FSAR Chapter 21 Multi-Module Design Considerations May15,2019 i-1 ~!:'.;;.f~!g Template#: 0000-21727-F01 R5 Copyright 2019 by NuScale Power, LLC.

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  • Presenters Chris Maxwell Senior Reactor Operator 4 Sarah Bristol Supervisor, Probabilistic Risk Assessment Nadja Joergensen Licensing Specialist 3 Copyright 2019 by NuScale Power, LLC.

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Modular Designs

  • Per 10 CFR 52.1, modular design means A nuclear power station that consists of two or more essentially identical nuclear reactors (modules) and each module is a separate nuclear reactor capable of being operated independent of the state of completion or operating condition of any other module co-located on the same site, even though the nuclear power station may have some shared or common systems.
  • The NuScale Power Plant design is consistent with this definition.

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Modular Designs

- Common (shared) systems

- Interface requirements

- System interactions

- Restrictions during construction and startup 4

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Shared Systems

  • The NuScale Power Plant is des.igned such that each NPM can be safely operated independent of other NPMs.

safety-related systems are module-specific and functionally independent of shared systems and other NPMs.

- Emergency core cooling system

- Containment system

- Decay heat removal system

- Module protection system

- Demineralized water isolation valves 5

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Shared Systems

  • The UHS has sufficient capacity to remove heat from one NPM experiencing a OBA, while simultaneously removing heat from 11 NPMs in shutdown and cooldown.
  • Long-term heat removal is provided by the UHS and the module-specific safety-related systems without reliance on other shared systems or operator action.

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Shared Systems Module heatup system Fire protection system Boron addition system Fire detection system Containment flooding and drain Fuel handling equipment system Module assembly equipment Reactor component cooling Instrument air system water system Gaseous radioactive waste Process sampling system system Circulating water system Liquid radioactive waste system Auxiliary boiler system Normal control room HVAC Site cooling. water system system Nitrogen distribution system Reactor building HVAC system Demineralized water system Control room habitability system 7

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Shared Systems Chilled water system Highly reliable DC power Ultimate heat sink system Reactor pool cooling system Normal DC power system Pool surge control system Safety display and indication system Pool cleanup system Plant protection system Pool leak detection system Plant control system Spent fuel pool cooling system 13.8 kV and switchyard system Medium voltage AC electrical distribution system Low voltage AC electrical distribution system 8

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System Interactions

  • The shared systems that have potential for an adverse system interaction or an undesirable multi-module interaction were evaluated.
  • The evaluations demonstrate that shared system operation does not result in adverse system interactions, such as

- a loss of a safety-related function,

- a DBE and a simultaneous degradation of a safety-related

function,

- a DBE and simultaneous degradation of critical operator information, or

- a DBE and a requirement for operator actions outside the control room.

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Interface Requirements

  • Shared systems that serve one NPM at a time are equipped with isolation features that prevent a direct module-to-module interface during normal operation.
  • For an adverse multi-module interaction to occur as a result of a failure associated with a shared system that serves one NPM at a time:

- Abnormal lineups

- Multiple concurrent failures 10 PM-0519-65533 Revision: O Copyright 2019 by NuScale Power, LLC.

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Interface Requirements

  • The reactor component cooling water system (RCCWS) is the only shared system that directly interfaces with multiple NPMs and is also designed to simultaneously support more than one NPM at a time.
  • The RCCWS is designed such that no single failure can cause the loss of RCCWS heat removal from more than one NPM.

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Construction and Startup

  • During the construction phase that occurs prior to the initial NPM fuel load, the shared and module-specific systems within the Reactor Building (RXB), Control Building (CRB), and Radioactive Waste Building (RWB) are substantially completed with the exception of the installation of additional NPMs.
  • The construction method and the phased expansion of NPMs provide assurance that

- the operating configuration is not materially different than that assumed in the safety analysis and

- that the independence of NPM safety~related systems is maintained.

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Construction and Startup.

  • In addition, the analysis of shared system interactions continues to apply to the operating NPMs during installation of subsequent NPMs.
  • Consequently, restrictions in operating configurations or interface requirements are not necessary to ensure the safe operation of operating NPMs during installation, testing, or startup of subsequent NPMs.

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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

+44 (0) 2079 321700 http://www. nuscalepower. com

~ Twitter: @NuScale_Power 14 PM-0519-65533 Revision: O Copyright 2019 by NuScale Power, LLC.

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