ML18192A140

Summary of the May 30, 2018, Category 1, Public Teleconference to Discuss Nuscale Power, Llc'S Request for Additional Information Responses 9273 and 9188

ML18192A140
Person / Time
Site:	NuScale
Issue date:	07/16/2018
From:	Bavol B NRC/NRO/DLSE/LB1
To:	Samson Lee NRC/NRO/DLSE/LB1
Bavol B / 415-6725
References
Download: ML18192A140 (5)

Text

July 16, 2018 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 MAY 30, 2018, CATEGORY 1, PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS REQUEST FOR ADDITIONAL INFORMATION RESPONSES 9273 AND 9188 The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on May 30, 2018, to discuss the NuScale Power, LLC (NuScale) request for additional information responses pertaining to reactor vessel materials and steam generator tube plugging criteria.

Participants included personnel from NuScale. No members of the general public participated via bridgeline during the meeting.

The public meeting notice dated May 30, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18117A344. 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

ML18192A140 *By email NRO-002 OFFICE DLSE/LB1:PM DLSE/LB1:LA DEIA/MCB DLSE/LB1:PM NAME BBavol MBrown MMitchell* BBavol (signed)

DATE 7/11/2018 7/10/2018 7/12/2018 7/16/2018

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS REQUEST FOR ADDITIONAL INFORMATION RESPONSES 9273 AND 9188 MEETING AGENDA May 30, 2018 The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to seek clarification from NuScale Power, LLC (NuScale) on request for additional information (RAI) 9188 response on 05.03.01, Reactor Vessel Materials, and RAI 9273 response on 05.04.02.01, Steam Generator Materials.

Time Topic Speaker Introductions and 1:00-1:15 NRC identification of topics 1:15-2:30 RAI discussions NuScale 2:30-2:45 Questions from the public Public 2:45-2:50 Break All 2:30-3:00 Closed Portion NuScale Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES May 30, 2018 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)

Greg Makar NRC Nicholas McMurray NRC Leslie Terry NRC Carrie Fosaaen NuScale Power, LLC (NuScale)

John Fields NuScale Matt Mallet NuScale HQ Xu NuScale JJ Arthur NuScale Heqin Xu NuScale Gery Wilkowski Engineering Mechanics Corporation of Columbus (Emc2)

Elizabeth Kurth-Twombly Emc2 Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS REQUEST FOR ADDITIONAL INFORMATION RESPONSES The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to seek clarification on request for additional information (RAI) RAI 9273 response on 05.04.02.01, Steam Generator Materials, and RAI 9188 response on 05.03.01, Reactor Vessel Materials.

RAI 9273, question 05.04.02.01-1, the NRC staff requested clarification of several technical aspects of how NuScale Power, LLC (NuScale) determined the criterion for plugging steam generator tubes. To clarify how the tube plugging analyses were performed, the NuScale staff explained that they used finite element analysis to evaluate thinning from wear, and closed-form analytical equations to evaluate cracking. The NuScale staff also provided the source of the Alloy 690 stress-strain behavior they used for the analyses, and they identified the corresponding values of yield stress, ultimate tensile strength (engineering and true), and the strain at the ultimate tensile strength. With respect to the geometric details of the analyses, the NuScale staff confirmed that they included the helical geometry (segment with curvature representative of helical curvature), 2.4 percent ovalization of the tube diameter, and the nominal tube diameter. The NuScale staff also confirmed that they did not include thickness variations in the analyses. The NuScale staff explained the length of tubing included in the analyses and how the ends of the analyzed tube section were modeled. Finally, the NRC staff and NuScale staff discussed considerations in the length of postulated wear flaws as they relate to the plugging criterion determination. The NuScale staff explained that they did not analyze flaw lengths longer than the steam generator tube support tabs because longer flaws are not anticipated, and that they did not analyze flaws from foreign objects because they consider it unnecessary since they are managed through operational programs (i.e., Steam Generator Program and Foreign Object Exclusion Program).

The information provided in the call enables the NRC staff to complete its evaluation of the response to Question 05.04.02.01-1 in RAI 9273.

Regarding RAI 9188, question 05.03.01-4, at the request of NuScale, this discussion has been rescheduled for July 10, 2018.

Enclosure 3