ML18109A537
| ML18109A537 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 05/01/2018 |
| From: | Bavol B NRC/NRO/DNRL/LB1 |
| To: | Samson Lee NRC/NRO/DNRL/LB1 |
| Bavol B | |
| References | |
| Download: ML18109A537 (5) | |
Text
April 30, 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
SUBJECT:
SUMMARY
OF THE APRIL 4, 2018, CATEGORY 1, PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS STEAM GENERATOR REQUEST FOR ADDITIONAL INFORMATION RESPONSES The U.S. Nuclear Regulatory Commission (NRC) held a Category 1 public teleconference on April 4, 2018, to discuss the NuScale Power, LLC (NuScale) responses to steam generator request for additional information. Participants included personnel from NuScale. No members of the general public participated via bridgeline during the meeting.
The public meeting notice dated April 4, 2018, can be found in the NRCs Agencywide Documents Access and Management Systems (ADAMS) under Accession No. ML18082A051.
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/DNRL 301-415-6715
- By email NRO-002 OFFICE DNRL/LB1:PM DNRL/LB1:LA DEIA/MCB DNRL/LB1:PM NAME BBavol MBrown*
MMitchell*
BBavol (signed)
DATE 4/30/2018 4/19/2018 4/20/2018 4/30/2018
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS STEAM GENERATOR REQUEST FOR ADDITIONAL INFORMATION RESPONSES MEETING AGENDA April 4, 2018 The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to seek clarification on some of their responses to certain Steam Generator questions in requests for additional information (RAI) 9231 (Chapter 5) and RAI 9234 (Chapter 16). Also, to promote a common understanding of the technical issues associated with RAI responses:
RAI 9231 - Question 5.4.2.1-6 RAI 9234 - Question 16-38 RAI 9234 - Question 16-40 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
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS DESIGN CERTIFICATION APPLICATION LIST OF ATTENDEES April 4, 2018 Name Organization Bruce Bavol U.S. Nuclear Regulatory Commission (NRC)
Greg Makar NRC Paul Klein NRC Andrew Johnson NRC Leslie Terry NRC Yuken Wong NRC Anthony Markley NRC Craig Harbuck NRC Carrie Fosaaen NuScale Power, LLC (NuScale)
John Fields NuScale Karl Gross NuScale Mark Shaver NuScale Matt Mallet NuScale Renee Martin NuScale Gery Wilkowski Engineering Mechanics Corporation of Columbus (Emc2)
Elizabeth Kurth-Twombly Emc2 Ed Punch Emc2
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER LLCS STEAM GENERATOR REQUEST FOR ADDITIONAL INFORMATION RESPONSES The purpose of this teleconference was for the U.S. Nuclear Regulatory Commission (NRC) staff to promote a common understanding of the technical issues and seek clarification on some of NuScales Power, LLC (NuScales) responses to steam generator (SG) Request for Additional Information (RAI) 9231 (Chapter 5) and RAI 9234 (Chapter 16).
For RAI 9231, Question 05.04.02.01-6, the NRC staff requested clarification about the design and fabrication of SG tube support spacers described in proposed revisions to final safety analysis report (FSAR) Section 5.4.1.2 and Figure 5.4-6. The NRC staff was unclear on the number, location, fabrication, and inspection details, and whether the spacers were incorporated in all design evaluations. NuScale staff provided clarifying information about the spacers and confirmed that they are being incorporated in design evaluations, including the Comprehensive Vibration Assessment Program.
For RAI 9234, the NRC staff requested clarification on the responses to Questions 16-38 and 16-40 on, respectively, the accident induced leakage criterion in the generic technical specifications (GTS) and the inspection intervals proposed in the GTS. The NRC staff was unclear on the leakage values assumed in accident analyses. NuScale staff confirmed that the accident analysis assumed 300 gallons per day to include conservatism above the technical specification limit of 150 gallons per day primary-to-secondary leakage from both SGs. With respect to inspection interval, the NRC staff asked NuScale to clarify how the inspection intervals permitted by the proposed GTS could be supported if, for example, the initial units observe degradation in the first operating cycle that must be evaluated with no other operating experience. The NuScale staff explained their expectation that the programmatic requirements incorporated in the GTS would reduce the time to the next inspection, and that a shorter inspection interval in the GTS would not provide much benefit in managing early degradation.
The NRC staff also requested clarification on FSAR revisions proposed in the response to RAI 9231, Question 05.04.02.01-2.a, which appeared to be missing an entry for integral feed plenum in revised Table 5.2-4. The NuScale staff explained that the feed plenum access port serves as both the plenum and the port, and therefore the table information is accurate.
The call provided the clarification needed for the NRC staff to complete its evaluation of the responses to RAI 9231 and RAI 9234. No new actions were identified for the NuScale or NRC staff as a result of the call.