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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)
	v • d • e

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.

Enclosure 1 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 Enclosure 1: "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

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Presenters Chris Maxwell Senior Reactor Operator 4 Sarah Bristol Supervisor, Probabilistic Risk Assessment Nadja Joergensen Licensing Specialist 3 2

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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

10 CFR 52.47(c)(3) requires evaluation of module operating configurations, considering:

- 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.

With the exception of the ultimate heat sink (UHS),

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

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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 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

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ML19135A064

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