ML18353A831

LLC Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application

ML18353A831
Person / Time
Site:	NuScale
Issue date:	12/18/2018
From:	Rad Z NuScale
To:	Document Control Desk, Office of New Reactors
References
RAIO-1218-63908
Download: ML18353A831 (3)

Text

RAIO-1218-63908 December 18, 2018 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.

386 (eRAI No. 9316) on the NuScale Design Certification Application

REFERENCE:

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

386 (eRAI No. 9316)," dated March 13, 2018 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. 9316:

03.09.02-55 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 Marty Bryan at 541-452-7172 or at mbryan@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Marieliz Vera, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 9316 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com

RAIO-1218-63908 :

NuScale Response to NRC Request for Additional Information eRAI No. 9316 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.: 9316 Date of RAI Issue: 03/13/2018 NRC Question No.: 03.09.02-55 In RAI 8884, Question 03.09.02-8, the staff requested NuScale to provide the separate effects test results of the steam generator inlet flow restrictor (SGIFR). The response indicates that the SGIFR testing is to be re-performed. Provide a description of the final SGIFR design and a summary of the test plan. Without the information, the staff cannot reach a reasonable assurance finding on the structural integrity of the reactor internals components to withstand the adverse effects of vibration because the SGIFR is susceptible to leakage flow instability and there is no analysis performed.

NuScale Response:

Chapter 5, Section 5.4.1.2 of the NuScale Final Safety Analysis Report provides a description of the final design of the steam generator inlet flow restrictor (SG IFR). The NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-0918-60894, submitted by NuScale letter LO-1218-63700, dated December 7, 2018, summarizes the plan for validation testing of the SG IFR final design in its Section 5.3.

Impact on DCA:

There are no impacts to the DCA as a result of this response.

NuScale Nonproprietary