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ACRS Full Committee Presentation: NuScale - Steam Generator Design, PM-0220-69051, Revision 0
	ML20066G277
Person / Time
Site:	NuScale
Issue date:	02/28/2020
From:	; NuScale
To:	; Office of Nuclear Reactor Regulation
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ML20066G660	List: ML20066G273; ML20066G277;
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	Download: ML20066G277 (14)
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L0-0220-69052

Enclosure:

"ACRS Full Committee Presentation: NuScale - Steam Generator Design," PM-0220-69051, 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 Full Committee Presentation NuScale Steam Generator Design March 5, 2020 PM-0220-69051

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Presenters Kevin Spencer Engineer, NSSS Engineering Bob Houser Manager, Testing and Code Development Brian Wolf Supervisor, Code Development Marty Bryan Licensing Project Manager 2

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Agenda

-* Steam Generator Design

DCA Revisions 3

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Steam Generator Design SG ORT 4

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Steam Generator Inlet Flow Restrictor Inlet Flow Restrictor (IFR)

IFR in Tubesheet 5

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Steam Generator Design

Integral Helical Coil SG Design features

- Shell side is primary side - Tube side is secondary side

- Alloy 690 TT (1380 tubes, 74 - 86 ft long , 5/8" OD)

- Low flow in primary (-1ft/sec)

- Tube wall degradation allowance (0.01 O" > ASME min wall)

- Support 100% volumetric inspection

- Normal access to shell side of tubes from below during refueling

Steam Generator Program and In-service Inspections

- Follow guidance of NEI 97-06 & EPRI (COL Item 5.4-1: Develop and implement a SG Program)

SG is designed with a flow restrictor at tube inlet to reduce the potential for density wave oscillations (DWO) 6 PM-0220-0220-69051 Revision : O Copyright 2020 by NuScale Power, LLC.

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DCA Revisions

An Action Item has been established for the Combined License applicant (COL Item 3.9-14)

A COL applicant that references the NuScale Power Plant design certification will develop an evaluation methodology for the analysis of secondary-side instabilities in the steam generator design . This methodology will address the identification of potential density wave oscillations in the steam generator tubes, and qualification of the applicable portions of the reactor coolant system integral reactor pressure vessel and steam generator given the occurrence of density wave oscillations, including the effects of reverse fluid flows within the tubes.

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DCA Revisions (cont'd)

FSAR Section 3.9 has been revised and establishes a COL Item for development of an evaluation methodology for analysis of secondary side instabilities.

FSAR Section 5.4 clarifies language related to secondary side instabilities.

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NuScale Conclusion

The successful completion of ITAAC and the COL Item constitutes the basis for the NRC determination to allow operation of a facility certified under 10 CFR 52 9

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Portland Office Richland Office 6650 SW Red1MJod Lane, 1933 Jadwn Ave. , Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541. 360. 0500 971.371.1592 Charlotte Office Corvallis Office 2815 Coliseum Centre Drive, 1100 NE Circle Blvd., Suite 200 Suite 230 Corvallis, OR 97330 Charlotte, NC 28217 541. 360. 0500 980. 349. 4804 Rockville Office 11333 Woodglen Ave., Suite 205 Rockville, MD 20852 301. 770.0472 http:IIWNW.nuscalepowe r com W Twtter: @NuScale_Po'M3r NUSCALE TM Po we r f o r a ll humankind 10 PM-0220-69051

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ITAAC Closure Path for DWO

Resolution of DWO is to be achieved through ITAAC activities related to the steam generator

Tier 1 Table 2.1-2 defines the NuScale Power Module (NPM) ASME Code Class 1, 2, 3, and CS components that comply with ASME Code Section Ill requirements including:

Equipment Name ASME Code Section Ill RCS Integral RPV/SG/Pressurizer 1

Number 02.01.01 specifies that "each ASME Code Class 1, 2, and 3 component (including piping systems) of a nuclear power plant requires a Design Report in accordance with NCA-3550" 12 PM--0220--0220~9051 Revision : 0 Copyright 2020 by NuScale Power, LLC.

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ITAAC Closure Path for DWO {continued)

An ITAAC inspection is performed of the NuScale Power Module "ASME Code Class 1, 2, 3, and CS as-built component Design Reports to verify that the requirements of ASME Code Section Ill are met"

From Subsection NCAof the 2013 Edition of the ASME Code -

- NCA-2142.2 requires that Design Specifications identify all loadings (e.g.

pressure , temperature , mechanical loads , cycles , and/or transients) and the service limits a component will experience

Loading combinations for the RPV (including SG tubes) defined in Table 3.9-3 of DCA

Transient (T H) loads are based on time history of design basis transients, described in DCA Section 3.9.1.

- NCA-3254 and 3255 provide additional information about design specifications

- NCA-3260 requires that the Design Report evaluate the loads as defined in the design specification 13 PM-0220-0220-69051 a!

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ML20066G277

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