ML19057A409

Summary of Public Teleconference to Discuss NuScale Power Llc'S Fuel Seismic Aspect of the Reactor Vessel Flange Tool

ML19057A409
Person / Time
Site:	NuScale
Issue date:	03/04/2019
From:	Bavol B NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Bavol B M/nro/5715
References
Download: ML19057A409 (5)

Text

March 4, 2019 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Bruce M. Bavol, Project Manager /RA/

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

SUMMARY

OF THE FEBRUARY 12, 2019, CATEGORY 1, PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS FUEL SEISMIC ASPECT OF THE REACTOR VESSEL FLANGE TOOL The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on February 12, 2018, to discuss the NuScale Power, LLC (NuScale) to discuss the fuel seismic aspect of the reactor vessel flange tool (RFT). One member of the general public participated via bridgeline during the meeting.

The public meeting notice dated February 12, 2019, can be found in the NRCs Agencywide Documents Access and Management Systems (ADAMS) under Accession No. ML19029A113.

The NuScale presentation material dated February 11, 2019, can be found under ADAMS Accession No. ML19045A334. This meeting notice was also posted on the NRC public website.

Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosures 2), and overview (Enclosure 3).

Docket No.52-048

Enclosures:

1. Meeting Agenda

2. List of Attendees

3. Meeting Overview cc w/encl.: DC NuScale Power, LLC Listserv CONTACT: Bruce M. Bavol, NRO/DLSE 301-415-6715

ML19057A409 *By email NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DSRA/SRSB:BC DLSE/LB1:PM NAME BBavol MMoore* RKaras* BBavol (signed)

DATE 2/26/2019 2/26/2019 03/01/2019 03/04/2019 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC REQUEST FOR ADDITIONAL INFORMATION NO. 9225 REACTOR VESSEL FLANGE TOOL ISSUE MEETING AGENDA February 12, 2019 The purpose of the meeting was discuss the reactor vessel flange tool (RFT) - fuel seismic aspect regarding Request for Additional Information No. 9225.

Time Topic Speaker 1:30-1:35 Introductions and identification of topics NRC 1:35-2:10 RFT discussions (Public) NRC/NuScale 2:10-2:15 Questions from the public Public 2:15-3:30 RFT discussions (Closed) NRC/NuScale 3:30 Adjourn ----

Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES February 12, 2019 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)

Rebecca Karas NRC Pravin Patel NRC Manas Chakravorty NRC Marieliz Vera NRC Chris Van Wert NRC Sunwoo Park NRC Robert Roche-Rivera NRC Greg Cranston NRC Martin Bryan NuScale Power, LLC (NuScale)

Matthew Presson NuScale Dylan Addison NuScale Larry Linik NuScale John Conly NuScale Corrie Nichol NuScale Evren Ulku NuScale Josh Parker NuScale Wayne Massie NuScale Kyra Perkins NuScale Marvin Lewis Public Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC REQUEST FOR ADDITIONAL INFORMATION NO. 9225 REACTOR VESSEL FLANGE TOOL ISSUE On February 12, 2019, a public teleconference meeting was held to discuss the NuScale Power, LLC (NuScale) fuel seismic aspect of the reactor vessel flange tool (RFT). The purpose of the meeting was to support the Phase 2 open Request for Additional Information (RAI) No. 9225.

One member of the general public participated via bridgeline during the meeting and did not have any questions for NRC staff following the discussion.

During the meeting, NuScale staff outlined the preliminary analyses performed by Framatome that assessed the difference in conditions between fuel in the NuScale Power Module (NPM) location and fuel in the RFT location, considering the impact of those differences when used as input for the ANP-10337P-A, "PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations," methodology. The conclusion provided with these analyses indicates that the impacts of a seismic event on fuel in the RFT location would be less severe than that which was already analyzed for the NPM location and submitted as part of the NuScale design certification application.

While the impact of an event occurring with fuel in the RFT location was indicated to be bounded by the analysis submitted for the NPM location, the preliminary analyses also concluded that additional analysis of the RFT location would be required in order to adequately support NuScales response to RAI No. 9225. This additional analysis is required to provide precise margins for fuel in the RFT location during a seismic event.

Enclosure 3