ML18299A242

Summary of Teleconference to Discuss NuScale Power, Llc., Responses to Requests for Additional Information Associated with NuScale Design Certification Application

ML18299A242
Person / Time
Site:	NuScale
Issue date:	10/31/2018
From:	Getachew Tesfaye NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Tesfaye G/NRO/415-8013
References
Download: ML18299A242 (5)

Text

October 31, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Getachew Tesfaye, Senior Project Manager /RA/

Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors

SUMMARY

OF THE OCTOBER 3, 2018, CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC., RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on October 3, 2018, to discuss responses to the NRC staffs requests for additional information associated with the NuScale Power, LLC. (NuScale) design certification application.

Participants included personnel from NuScale and members the general public.

The public meeting notice dated October 3, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under accession number ML18275A424. This meeting notice was also posted on the NRC public website.

Enclosed is the Meeting Agenda (Enclosure 1), List of Attendees (Enclosure 2), and an overview of the teleconference (Enclosure 3).

Docket No.52-048

Enclosures:

As stated cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Getachew Tesfaye NRO/DLSE 301-415-8013

ML18299A242 NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DSRA/SPRA DNRL/LB1:PM NAME GTesfaye CSmith JSchaperow* GTesfaye (signed)

DATE 10/26/2018 10/30/2018 10/29/2018 10/31/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC.

RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA October 3, 2018 1:00 - 1:15 PM Introductions and Identification of topics 1:15 - 1:30 PM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Response to Request for Additional Information (RAI) No. 9224, Question 01.05-32 01:30 - 01:35 PM Public Comments/Questions 01:35 - 3:00 PM Closed portion Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES October 3, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC)

Anne-Marie Grady NRC Hossein Esmaili NRC Michael Salay NRC Michelle Hart NRC Jason Schaperow NRC Michelle Hayes NRC Paul Infanger NuScale Power, LLC (NuScale)

Etienne Mullin NuScale Scott Weber NuScale Jennie Wike NuScale Dan Lassiter NuScale Mark Shaver NuScale Paul Guinn NuScale Russell Goff NuScale Sarah Fields Member of the public Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE OCTOBER 3, 2018, TELECONFERENCE TO DISCUSS THE NUSCALE POWER, LLC., RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was to discuss the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of NuScale Power LLCs., (NuScale) Response to Request for Additional Information (RAI) 9224, Question 01.05-32.

The following is the summary of the NRC staffs feedback and agreed upon next steps for the resolution of the remaining issues.

1. Response to RAI 9224, Question 01.05-32 (ADAMS Accession Number ML18212A192):

a. NRC Feedback: The NRC staff requested clarifications on two of the issues in the RAI response. One issue was the method used to select severe accident scenarios together with the statistical metric used to determine the magnitude of source term from the core to the containment. The other issue was the amount of non-radioactive aerosol assumed to be released from the core to the containment which could affect the fission product aerosol deposition rate in containment. In addition, the staff requested clarification of the basis for the containment leak rates assumed in the topical report. The staff sought clarifications in areas where novel approaches or assumptions were being used as well as unique features of the NuScale design (e.g., evacuated containment) that might affect the approaches and assumptions taken in the accident source term methodology.

b. Next Step: the applicant provided the clarifications requested by the staff. The staff concluded the meeting by stating that it would consider the additional information provided by the applicant and decide whether to request changes to the NuScale accident source term topical report or to the Final Safety Analysis Report.

2. The proprietary information discussion topics for the closed portion of the meeting, prepared by the NRC staff, can be found in ADAMS (ML18299A099).

Enclosure 3