ML24198A077
| ML24198A077 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/18/2024 |
| From: | Turner Z NRC/NRR/DORL/LPL2-1 |
| To: | Southern Nuclear Operating Co |
| Shared Package | |
| ML14190A131 | List: |
| References | |
| EPID L-2024-LRM-0086 | |
| Download: ML24198A077 (1) | |
Text
July 18, 2024
LICENSEE: Southern Nuclear Operating Company, Inc.
FACILITIES: Joseph M. Farley Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF JULY 11, 2024, OB SERVATION PUBLIC MEETING HELD WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC., REGARDING ITS LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.6.5, CONTAINMENT AIR TEMPERAT URE, COMPLETION TIME INCREASE USING RISK-INFORMED PROCESS FOR EVALUATION FOR JOSEPH M.
FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (EPID L-2024-LRM-0086)
On July 11, 2024, an observation meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNC, the licensee). The purpose of the meeting was to discuss technical and regulatory information related to the non-acceptance of SNCs proposed license amendment request (LAR) to change Technical Specification (TS) 3.6.5, Containment Air Temperature, actions for the Joseph M.
Farley Nuclear Plant (Farley), Units 1 and 2, using Risk-Informed Process for Evaluation (RIPE) and to facilitate a mutual exchange on information needs for a possible resubmittal. The meeting notice and agenda, dated July 2, 2024, are available in the NRCs Agencywide Documents Access and Management System (ADA MS) under Accession No. ML24193A028. A list of attendees is provided in the enclosure.
The NRC staff opened the meeting with introductory remarks followed by a slide show presentation (ML24190A108). The licensee then presented slides providing additional technical information related to its original submittal (ML24192A226).
The following items were discussed during the meeting:
- 1. The NRC staff does not expect SNC to perform and submit a full loss-of-coolant-accident (LOCA) analysis for this review. Rather, the staff expects the licensee to provide sufficient information that describes the methodology of analysis that is being used to realistically model the Farley reactor system to estimate the effects of increased containment average air temperature on peak cladding temperature (PCT). This discussion should provide detailed discussion on why the model being used is similar to or bounding with regards to Farley and its consistency with the requirements of 10 CFR 50.46.
- 2. The current PCT rack-up in Farleys safety analysis report (SAR) should be updated to include the proposed TS action change in the licensees LAR resubmittal. This will ensure that future licensing action reviews properly account for PCT margin.
- 3. The inputs and the associated uncertainties for Farleys GOTHIC code used to evaluate how the proposed change in Containment Average Air Temperature impacts loss-of-coolant accident (LOCA) containment sump temperature response should be included in the licensees LAR resubmittal, along with Net Positive Suction Head (NPSH) margin for containment spray and residual heat removal pumps.
- 4. The licensees previously proposed LAR modified the TS Required Actions and completion times such that there were no licensee actions to actively bring the containment air temperature back within specif ication. Instead, the remedial restorative actions proposed were to monitor the containment average air temperature and refueling water storage tank temperature every eight hours while ensuring that containment average air temperature did not exceed the limiting conditions for operation (LCO) for 720 cumulative hours per calendar year. Any changes to LCOs must be derived from the analysis in the SAR. If a future proposal includes modifying the Required Actions and Completion Times to address elevated containment average air temperature, then an appropriate technical and safety justification for the action and associated completion time should be provided.
- 5. The licensee should discuss why the proposed change required actions and completion times would not result in a non-conservative TS as described in Regulatory Guide 1.239, Revision 0, and NEI, 15-03, Revision 3, Licensee Actions to Address Nonconservative Technical Specifications.
During the meeting, SNC stated their intent to resubmit the amendment request on July 19, 2024, outside of the RIPE process. SNC will be requesting an expedited review in consideration of anticipated increased and prolonged summer temperatures at Farley. Due to the expedited request, if the licensees resubmittal is accepted for review, a regulatory audit would likely be required to efficiently identify information needed on the docket for the NRC staff to evaluate that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
The meeting adjourned at 1:44 pm Eastern Time (ET). There were no public questions or comments provided during the meeting. The NRC staff did not consult with the SNC personnel, and the NRC staff did not make any regulatory decisions during the meeting. Once received, the NRC staff will perform a thorough review of the proposed license amendment. The NRC staff will make any regulatory decisions in writing in a timely manner. Public Meeting Feedback forms were available, but no comments were received.
Please direct any inquiries to me at 301-415-2258 or by e-mail to Zachary.Turner@nrc.gov.
/RA/
Zachary M. Turner, Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-348 and 50-364
Enclosure:
List of Attendees
cc: Listserv
LIST OF ATTENDEES JULY 11, 2024, PUBLIC MEETING WITH SOUTHERN NUCLEAR COMPANY TO DISCUSS NONACCEPTANCE OF PREVIOUS LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.6.5, CONTAINMENT AIR TEMPERATURE JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2
ATTENDEE REPRESENTING
Zach Turner U.S. Nuclear Regulatory Commission (NRC)
Ahsan Sallman NRC Andy Rosebrook NRC Antonious Zoulis NRC Bo Pham NRC Boyce Travis NRC Christian Scott NRC Daniel King NRC David Gennardo NRC David Nold NRC Demetrius Murray NRC Derek Scully NRC Ed Miller NRC Eric Bowman NRC Jack Bryant NRC Jamie Pelton NRC John Hughey NRC John Lamb NRC Logan Gaul NRC Matthew Leech NRC Meena Khanna NRC Michael Markley NRC Michelle Kichline NRC Milton Valentin NRC Nathan Denney NRC Nicholas Soliz NRC Phillip Sahd NRC Raul Hernandez NRC Robert Elliott NRC Santosh Bhatt NRC Sarah Temple NRC Steve Smith NRC Shivani Mehta NRC Shilp Vasavada NRC Tony Nakanishi NRC Travis Boyce NRC Vic Cusumano NRC
Enclosure
ATTENDEE REPRESENTING
Wesley Sparkman Southern Nuclear Operating Company (SNC)
Daniel McInnes SNC Daniel Williamson SNC Eddie Grant SNC Gene Surber SNC Jamie Coleman SNC Jared Cannon SNC Jill Hershman SNC Jonathan Register SNC Neil Barnett SNC Richard Langford SNC Ryan Joyce SNC Steven Newell SNC Thomas Kindred SNC Allison Fisher Westinghouse Amy Colussy Westinghouse Jeffrey Kobelak Westinghouse Kevin Barber Westinghouse Andrew Mauer Nuclear Energy Institute (NEI)
Brett Titus NEI Jeff Sharkey Balch & Bingham Deann Raleigh Curtiss-Wright
Pkg ML24190A131 Meeting Notice ML24184B871 Meeting Summary ML24198A077 NRC Slides ML24190A108 SNC Slides ML24192A226 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/B NRR/DSS/SNSB/BC C
NAME ZTurner KGoldstein SMehta PSahd DATE 7/16/2024 07/16/2024 7/17/2024 7/17/2024 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley ZTurner DATE 7/18/2024 7/18/2024