ML19105B294

LLC Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application

ML19105B294
Person / Time
Site:	NuScale
Issue date:	04/15/2019
From:	Rad Z NuScale
To:	Document Control Desk, Office of New Reactors
References
RAIO-0419-65232
Download: ML19105B294 (5)

Text

RAIO-0419-65232 April 15, 2019 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

SUBJECT:

NuScale Power, LLC Response to NRC Request for Additional Information No.

520 (eRAI No. 9642) on the NuScale Design Certification Application

REFERENCE:

U.S. Nuclear Regulatory Commission, "Request for Additional Information No.

520 (eRAI No. 9642)," dated March 20, 2019 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 9642:

16-66 The response for the remaining questions of RAI No. 520, eRAI No. 9462 will be provided by May 20, 2019.

This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.

If you have any questions on this response, please contact Carrie Fosaaen at 541-452-7126 or at cfosaaen@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8H12 Samuel Lee, NRC, OWFN-8H12 Getachew Tesfaye, NRC, OWFN-8H12 : NuScale Response to NRC Request for Additional Information eRAI No. 9642 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-0419-65232 :

NuScale Response to NRC Request for Additional Information eRAI No. 9642 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

Response to Request for Additional Information Docket No.52-048 eRAI No.: 9642 Date of RAI Issue: 03/20/2019 NRC Question No.: 16-66 Paragraph (a)(11) of 10 CFR 52.47 and paragraph (a)(30) of 10 CFR 52.79 state that a design certification (DC) applicant and a combined license (COL) applicant, respectively, are to propose technical specifications (TS) prepared in accordance with 10 CFR 50.36 and 50.36a.

10 CFR 50.36 sets forth requirements for TS to be included as part of the operating license for a nuclear power facility.

This question is a followup of RAI 472-9445 (ML18130A984), Question 16-43, to which the applicant has responded ((ML18163A417).

NuScales methodology to set the AXIAL OFFSET (AO) (LCO 3.2.2) and Power Dependent Insertion Limits (PDILs) (LCO 3.1.6) is dependent upon TR-0516-49422, Loss-of-Coolant Accident Evaluation Model and TR-0716-50350, Rod Ejection Accident Methodology, in additional to the other methodologies listed. Also, CHF is used as acceptance criteria in LOCA and rod-ejection analyses. Accordingly, the staff believes the following changes need to be made to paragraph b of GTS 5.6.3:

The applicant is requested to update References 1, 3, and 4 to include TR-0516-49422, Loss-of-Coolant Accident Evaluation, and TR-0716-50350, Rod Ejection Accident Methodology.

NuScale Response:

References 1, 3, and 4 of specification 5.6.3, Core Operating Limits Report (COLR) were modified to include TR-0516-49422, Loss-of-Coolant Accident Evaluation, and TR-0716-50350, Rod Ejection Accident Methodology.

NuScale Nonproprietary

Impact on DCA:

The Technical Specifications have been been revised as described in the response above and as shown in the markup provided in this response.

NuScale Nonproprietary

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) (continued)

1. [NuScale Standard Design Certification Analysis (DCA), Part 2, Tier 2, NuScale Final Safety Analysis Report (FSAR), Section 4.3, Nuclear Design, Revision 1, March 2018;, and TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 0, May 2016 (NuScale Proprietary); TR-0516-49422, "Loss-of-Coolant Accident Methodology," Revision 0, May 2016 (NuScale Proprietary); and TR-0716-50250, "Rod Ejection Accident Methodology," Revision 0, July 2016 (NuScale Proprietary).

(Methodology for Specifications 3.1.1 - SHUTDOWN MARGIN (SDM), 3.1.3 - Moderator Temperature Coefficient, 3.1.4 - Rod Group Alignment Limits, 3.1.5 - Shutdown BankGroup Insertion Limits, 3.1.6 - Regulating BankGroup Insertion Limits, and 3.1.8 -

PHYSICS TESTS Exceptions.)]

2. [NuScale DCA, Part 2, Tier 2, NuScale FSAR, Section 9.3.4, Chemical and Volume Control System, Revision 1, March 2018;,

and TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 0, May 2016 (NuScale Proprietary).

(Methodology for Specification 3.1.9 - Boron Dilution Control.)]

3. [NuScale DCA, Part 2, Tier 2, NuScale FSAR, Sections 4.3, Nuclear Design, and 4.4, Thermal and Hydraulic Design, Revision 1, March 2018; TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 0, May 2016 (NuScale Proprietary); and TR-0915-17564-A, Subchannel Analysis Methodology, Revision 21, SeptemberFebruary 20195 (NuScale Proprietary); TR-0516-49422, "Loss-of-Coolant Accident Methodology," Revision 0, May 2016 (NuScale Proprietary); and TR-0716-50250, "Rod Ejection Accident Methodology," Revision 0, July 2016 (NuScale Proprietary).

(Methodology for Specifications 3.2.1 - Enthalpy Rise Hot Channel Factor (FH), and 3.2.2 - AXIAL OFFSET (AO).)]

4. [NuScale DCA, Part 2, Tier 2, NuScale FSAR, Section 4.4, Thermal and Hydraulic Design, Revision 1, March 2018; and TR-0516-49416, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 0, May 2016 (NuScale Proprietary);

TR-0516-49422, "Loss-of-Coolant Accident Methodology,"

Revision 0, May 2016 (NuScale Proprietary); and TR-0716-50250, "Rod Ejection Accident Methodology," Revision 0, July 2016 (NuScale Proprietary).

NuScale 5.6-3 Draft Revision 3.0