ML18169A031

Summary of the May 22, 2018, Category 1 Public Teleconference to Discuss Nuscale Power, LLC Responses to Requests for Additional Information Associated with the Nuscale Design Certification Application

ML18169A031
Person / Time
Site:	NuScale
Issue date:	06/20/2018
From:	Getachew Tesfaye NRC/NRO/DNRL/LB1
To:	Samson Lee NRC/NRO/DNRL/LB1
Tesfaye G / 415 8013
References
Download: ML18169A031 (6)

Text

June 20, 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 MAY 22, 2018, CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS 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 May 22, 2018, to discuss responses to the NRC staff requests for additional information (RAI) associated with the NuScale Power, LLC (NuScale) design certification application. Participants included personnel from NuScale. No members of the general public participated via bridgeline during the meeting.

The public meeting notice dated May 22, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems under Accession No. ML18117A330. This meeting notice was also posted on the NRC public website.

Enclosed is the meeting agenda (Enclosure 1), list of participants (Enclosure 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: Getachew Tesfaye NRO/DLSE 301-415-8013

ML18169A031 NRO-002 OFFICE DLSE/LB1:PM DLSE /LB1:LA DLSE/RPAC DNRL/LB1:PM NAME GTesfaye MBrown MDudek GTesfaye (signed)

DATE 6/17 /2018 6/18/2018 6/20/2018 6/20/2018 U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION MEETING AGENDA MAY 22, 2018 11:00 - 11:05 AM Meeting Introductions 11:05 - 12:45 PM Discussion of U.S. Nuclear Regulatory Commission Staffs Questions regarding NuScale Power LLCs Responses to Requests Additional Information 9245, 9285, 9292, 9284, and 9278.

12:45 - 12:55 PM Public Comments/Questions 12:50 - 01:00 PM Public interaction 01:00 PM Meeting Closure Enclosure 1

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLC RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION ASSOCIATED WITH THE NUSCALE DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES May 22, 2018 Name Organization Getachew Tesfaye U.S. Nuclear Regulatory Commission (NRC)

Yeshnik, Andrew NRC Hernandez, Raul NRC Lavera, Ronald NRC Meighan, Sean NRC Dudek, Michael NRC Williams, Stephen NRC Lee, Samuel NRC Markley, Anthony NRC Istar, Ata NRC Gran, Zachary NRC Roche-Rivera, Robert NRC Gary Becker NuScale Power, LLC (NuScale)

Rick Biasca NuScale Christian Lobscheid NuScale Scott Harris NuScale Derek Noel NuScale Greg Myers NuScale Jim Osborn NuScale Pat Conley NuScale Lee Dougherty NuScale Steve Mirsky NuScale Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION OVERVIEW OF THE MAY 22, 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) Responses to Requests for Additional Information (RAI) 9245, 9285, 9292, 9284, and 9278.

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

1. RAI 9245, Question 12.03-7

a. NRC Staff Feedback: One of the original questions posed by NRC staff was to ask how non-safety related components located inside of the containment vessel (CNV) but outside of the reactor vessel are evaluated as it relates to the requirements of the EQ program. NuScales response did provide an answer to the specific examples provided in the background to the RAI. The response also addressed how DCD Sections 6.2.2 and 6.3 describe that the qualification program should address potential debris generating non-safety related SSCs inside of containment. However, the NRC staff is seeking information that verifies that the NuScale design performs EQ analysis for all non-safety related components located inside of the CNV but outside of the reactor vessel to ensure that these components would not suffer degradation under accident conditions that could impact safety related functions, such as but not limited to debris generation.

The NRC staff has been unable to determine if there are discussions of other non-safety related components similar to the examples provided. The NRC staff is looking for information in DCD Section 3.11 that discusses if the EQ program would require testing or analysis for other non-safety related components that are not discussed in this response.

b. Next Step: NuScale understood the NRC staffs question and agreed to provide supplemantal response.

2. RAI 9245, Question 12.03-8

a. NRC Staff Feedback: The response does not appear to address the question asked regarding high cobalt wear products resulting from flexure of the control rod drive shaft. NuScales response does detail how the control rods have their flexure limited using the control rod assembly (CRA) cards. However, it is not Enclosue 3

clear to the NRC staff how the flexure of the control rod drive shaft itself is controlled. The NRC staff seeks to gain clarity as to whether it is NuScales intent that the flexure of the control rod drive shaft is limited by the control rods CRA card? The NRC staff continues to have concerns given the length of the control rod drive shaft is now longer than what has been seen in past designs.

b. Next Step: NuScale understood the NRC staffs question and agreed to provide supplemantal response.

3. RAI 9285, Question 12.03-41

a. NRC Staff Feedback: The response provided by NuScale seems reasonable; however, the staff needs additional clarification related to air sparging operations for the phase separator tank (PST). It would appear that there would be only the 1 valve of separation when these operations would occur since the valves leading to the sides of the PST would be opened during this operation.

b. Next Step: NuScale understood the NRC staffs question and agreed to provide supplemantal response.

4. RAI 9292 This RAI was not discussed during the teleconfrence. The NRC staff informed NuScale that it was considering a regulatory audit to clarify and address the remaing unresolved issues.

5. RAI-9284 - Smooth Surfaces:

a. Staff Feedback: In response to NuScales comment regarding the American Society of Mechanical Engineers (ASME) specification for a smooth surface, and their belief that the proposed specification represented a mirror finish, the NRC staff reviewed the ASME code and the determined that: 1) the section of the ASME code referenced by NuScale only ensured the surface was smooth enough to be able to perform ultrasonic inspections and 2) the NRC staff notes that a No. 4 surface finish [identified in the reference Electric Power Research Institute (EPRI) document] is much coarser than an No. 8 (ASME Mirror) finish.

Guidance regarding acceptable smoothness is provided through operating experience identified in the referenced EPRI document submitted by industry to the NRC staff.

b. Next Step: The NRC project manager will provide NuScale docketed example of specification for the surface finish that were provided by other applicant for design certification.

6. RAI 9278, Regarding deletion of Question 12.3-38 The NRC staff found NuScales response acceptable. After verification, the NRC staff will change the status of this RAI to resolved closed.

Enclosue 3