ML18093A180

March 27, 2018 Summary of Public Meeting NuScale ASME Code Requirements

ML18093A180
Person / Time
Site:	NuScale
Issue date:	04/03/2018
From:	Bavol B NRC/NRO/DNRL/LB1
To:	Samson Lee NRC/NRO/DNRL/LB1
Bavol B
References
Download: ML18093A180 (5)

Text

April 3, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors FROM: Bruce M. Bavol, Project Manager /RA/

Licensing Branch 1 Division of New Reactor Licensing Office of New Reactors

SUMMARY

OF THE MARCH 27, 2018, CATEGORY 1, PUBLIC TELECONFERENCE TO DISCUSS AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE REQUIREMENTS ASSOCIATED WITH THE NUSCALE POWER, LLC DESIGN CERTIFICATION APPLICATION The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on March 27, 2018, to discuss the NuScale Power, LLC (NuScale) design certification applications American Society of Mechanical Engineers Code requirements along with select request for additional information responses. Participants included personnel from NuScale. No members of the general public participated via bridgeline during the meeting.

The public meeting notice dated March 27, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18085A639. 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 CONTACT: Bruce M. Bavol, NRO/DNRL 301-415-6715 cc w/encl.: DC NuScale Power, LLC Listserv

ML18093A180 NRO-002 OFFICE DNRL/LB1:PM DNRL/LB1:LA DEIA/MCB DNRL/LB1:PM NAME BBavol MBrown MMitchell BBavol (signed)

DATE 4/03/2018 4/03/2018 4/03/2018 4/03/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE REQUIREMENTS ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA March 27, 2018 The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss application of American Society of Mechanical Engineers Code Requirements to the NuScale Power, LLC Design associated with the NuScale Design Certification Application currently under review. Also, to promote a common understanding of the technical issues associated with request for additional (RAI) responses:

Chapter 3, RAI 9183, Question No. 2 Chapter 5, RAI 9193, Question No. 1, 2, and 10 Chapter 6, RAI 9109, Questions No. 1 and 2 Time Topic Speaker 1:00 - 1:10 pm Introductions and Identification of Topics NRC 1:10 - 2:45 pm Design Review Discussions NRC / NuScale 2:45 - 3:00 pm Questions from the Public Public 3:00 pm End of Meeting Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES March 27, 2018 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)

Matthew Mitchell NRC Yueh-Li (Renee) Li NRC Nick Hansing NRC John Honcharik NRC Nicholas McMurray NRC Stephen Cumblidge NRC Andrew Yeshnik NRC Cynthia Carpenter NRC Eric Reichelt NRC Samuel Lee NRC Carrie Fosaaen NuScale Power, LLC (NuScale)

John Fields NuScale Jennie Wike NuScale Ben Heald NuScale Ed Heald NuScale Cindy Williams NuScale Gary Becker NuScale Matt Mallet NuScale Zack Houghton NuScale Marty Bryan NuScale Greg Myers NuScale Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE MARCH 27, 2018, PUBLIC MEETING TO DISCUSS AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE REQUIREMENTS ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to discuss application of American Society of Mechanical Engineers (ASME) Code Requirements to the NuScale Power, LLC (NuScale) Design associated with the NuScale Design Certification Application currently under review. Also, to promote a common understanding of the technical issues associated with request for additional information (RAI) 9183 (Chapter 3), RAI 9193/9103 (Chapter 5), and RAI 9109 (Chapter 6).

The NRC staff explained that this topic relates to the staffs ability to reach a conclusion regarding the NuScale design meeting General Design Criteria related to system and component integrity (e.g., GDC 14), as referenced in the aforementioned RAIs, and other essential aspects of the design (e.g., NuScales requested exemption from performing Type A containment leak rate testing; assumptions regarding failure of the containment vessel and reactor vent and recirculation valve connections to the reactor vessel as being not credible within the NuScale design basis; etc.). The NRC staff indicated that it was principally seeking to understand how NuScale evaluated the material qualification, preservice inspection, in-service inspection, etc. requirements specified in the ASME Code and determined where they were adequate to achieve levels of system and component integrity and reliability appropriate to support the overall safety of the NuScale design, or where augmented treatment requirements (e.g., as discussed in Section 6.6.8 of the DCD) were warranted. The NRC staff, in developing the RAIs identified above, identified specific examples (e.g., piping ISI requirements, bolting ISI requirements, etc.) where augmentation of ASME Code requirements might be considered in light of the overall NuScale design.

At the end of the teleconference and in order to reach a better understanding of the general background for the NRC staffs questions associated with this issue, the NRC and NuScale staff resolved to follow up with additional public teleconferences to discuss specific technical issues associated with this topic.

Enclosure 3