ML23037A003
| ML23037A003 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/06/2023 |
| From: | Bill Gleaves NRC/NRR/VPOB |
| To: | |
| References | |
| Download: ML23037A003 (1) | |
Text
LICENSEE: Southern Nuclear Operating Company FACILITY: Vogtle Electric Generating Plant, Units 3 and 4
SUBJECT:
SUMMARY
OF FEBRUARY 2, 2023, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY On February 2, 2023, at 9:00 a.m. Eastern Standard Time (EST), the U.S. Nuclear Regulatory Commission (NRC) held a virtual public meeting with representatives of Southern Nuclear Operating Company (SNC or the licensee). The purpose of the meeting was to have a post-submittal discussion of the exigent license amendment request (LAR) for Vogtle Electric Generating Plant (Vogtle), Unit 3, that is known as LAR 23004. The exigent LAR, found in the NRCs Agencywide Documents Access and Management System (ADAMS) at Accession No. ML23031A359, proposes modifications to the Unit 3, Combined License Appendix A, Technical Specifications (TS) sections 3.5.7 and 3.5.8, and related changes to TS sections 3.3.8, 3.3.9, 3.3.10, 3.3.16, 3.3.19, and 3.3.20. The changes, if approved, would be permanent to the Unit 3 TS, however their applicability would be temporary, until initial criticality is achieved. The meeting notice and agenda are available in ADAMS (ML2306A072). A list of attendees is enclosed.
SNC representatives presented their proposed LAR and described their technical and regulatory evaluations justifying the submitted exigent LAR 23004 for Vogtle Unit 3.
Below is a summary of the meeting:
There were approximately 48 participants on the call, including NRC staff, SNC staff and contractors, and the public.
SNC began its presentation by stating that the current TS were not written for startup of the reactor, but for power operation. The proposed changes pose no risk to the public. The LAR reflects the required operability considerations during Modes 5 and 6, prior to initial criticality, and related signals and controls.
SNC stated that the TS changes in the proposed LAR involve notes or footnotes in the proposed TS. While these are permanent TS changes, their applicability expires upon initial criticality of Vogtle Unit 3.
The staff asked about the methods SNC would use to ensure adequate reactor coolant inventory during any evolution where the coolant level was lowered below the level of the direct vessel injection (DVI) nozzle. SNC stated that Chemical and Volume Control System (CVS) letdown would be monitored, and excess inventory would go to the Liquid Radwaste System (WLS) with that inventory also being monitored. In addition, SNC has the ability to sample water and chemistry and do an analysis to see changes in the volume of water.February 6, 2023 The staff asked about the temperature that SNC would expect the reactor coolant to be during the lowered inventory period. SNC responded that it would be approximately 105 °F.
SNC confirmed that the CVS letdown line was at a higher elevation than the DVI line.
In response to a staff request, SNC described the planned repairs to the valve and stated that the repair activity would be performed in accordance with the currently applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code) requirements. SNC stated affirmatively that the repair activity would be performed in accordance with the requirements of ASME BPV Code,Section XI. Further, SNC stated that post-maintenance activities for the valve would satisfy the preservice testing requirements in the 2012 Edition of the ASME Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code), which is required by the NRC regulations to be implemented at Vogtle Unit 3 for the initial 10-year Inservice Testing Program interval.
These are licensee-controlled programs. The LAR does not include any requests for alternatives to the ASME BPV Code or OM Code requirements, and the staff did not identify any deviations from the Code requirements.
The staff asked about controls that would be in place to prevent a boron dilution event and how unborated water would be prevented from entering the primary system during a state of lower reactor water inventory. SNC stated that the depth of reactor coolant, from the bottom of the DVI nozzle to the top of fuel, is approximately 4 feet. In addition, SNC stated that they have source range nuclear instruments and a flux doubling actuation will be active to detect any changes in the reactor.
Members of the public were in attendance. There were no questions or comments from the public. The staff did not receive any Public Meeting Feedback forms. The meeting ended at 9:48 a.m. EST.
Please direct any inquiries to me at 301415-5848 or Bill.Gleaves@nrc.gov.
Sincerely, William (Billy) Gleaves, Senior Project Manager Vogtle Project Office Office of Nuclear Reactor Regulation Docket Nos. 52025 and 52026
Enclosure:
List of Attendees cc: Listserv Signed by Gleaves, William on 02/06/23
LIST OF ATTENDEES
February 2, 2023, NRC Meeting with Southern Nuclear Operating Company
Name Organization
Billy Gleaves Brian Wittick Christopher Welch Victor Hall Garry Armstrong Hanry Wagage Phil OBryan Rob Elliott Stew Bailey Rebecca Patton NRC Pravin Sawant Tanny Santos Jim Gaslevic Joe Ashcraft Michael Spencer Scott Burnell Shakur Walker Tom Fredette Thomas Scarbrough Bill Roggenbrodt
Bradley Davis Chris Even Dave Gasperson Jason Eargle NRC/Region II JP Parent Omar Lopez-Santiago Andrea Johnson
Jamie Coleman Amy Chamberlain Steve Leighty Ken Lowery Keith Dorsey William Garrett Denise Blackburn Southern Nuclear Operating Company Jacob Hawkins Thomas Kindred Matthew Leonard Daniel Williamson Ken Baity Cheryl Gayheart Ashley Black - Southern Company Services Enclosure Name Organization Derrick Trafford Eddie Grant Nathan Chapman
Tom Gurdziel Jana Bergman Members of the Public Jay Leininger
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ML23037A003 OFFICE NRR/VPO/VPOB NRR/VPO/VPOB NRR/VPO/VPOB NAME WGleaves WG VHall VH WGleaves WG DATE Feb 6, 2023 Feb 6, 2023 Feb 6, 2023