ML25224A162
| ML25224A162 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/26/2025 |
| From: | Klos L NRC/NRR/DORL/LPL2-1 |
| To: | Duke Energy Carolinas |
| References | |
| EPID L-2025-LRM-0097 | |
| Download: ML25224A162 (1) | |
Text
August 26, 2025 LICENSEE:
Duke Energy Carolinas, LLC FACILITIES: MCGUIRE, UNITS 1 AND 2
SUBJECT:
SUMMARY
OF AUGUST 11, 2025, PUBLIC MEETING WITH DUKE ENERGY CAROLINAS, LLC REGARDING A FUTURE LICENSE AMENDMENT FOR MCGUIRE, UNITS 1 AND 2; SPENT FUEL POOL CRITICALITY (EPID L-2025-LRM-0097)
On August 11, 2025, an observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy Carolinas, LLC (Duke Energy or the licensee). The purpose of the meeting was to discuss a future license amendment request (LAR) which proposes to modify the Technical Specifications (TSs) and update the criticality safety analysis for McGuire Nuclear Station, Units 1 and 2, for increased enrichment and fuel burnups to support a 24-month fuel cycle.
The meeting notice and agenda, dated July 17, 2025, is available at Agencywide Documents and Access Management System (ADAMS) Accession No. ML25198A154. The licensee presented slides that are available at ML25217A192. A list of attendees is provided in the Enclosure.
The licensee, in summary, presented the following information in the meeting slides:
- 1.
Purpose and Scope of the LAR
- 2.
Spent Fuel Pool Background and New Fuel Vault Configurations
- 3.
High-level outline of proposed TSs changes
- 4.
Proposed changes to the criticality safety analysis
- 5.
Potential inclusion of exemption request for enrichment limits
- 6.
Anticipated LAR timeline for submittal/review/implementation The NRC staff asked and discussed with the licensee:
Regarding the presentations new fuel vault sketch, does that represent concrete walls in the north-south and east-west orientation?
Please note that the topical report that will address CASMO5 computer codes application with enrichment greater than 5% is anticipated for completion in the spring of 2026.
How much Integral Fuel Burnable Absorber (IFBA) will be used in what combination of fuel? Will there be applications of Gadolinia and IFBA used?
What guidance reference would the licensee be applying if combinations of Gadolinia and IFBA were utilized?
The licensee intends to articulate in the LAR submittal the direction taken related to use of gadolinia, IFBA, and wet annular burnable absorbers.
The licensee should ensure to discuss consistencies with or deviations from any topical reports being referenced.
Please ensure that the LARs description for comprehensive fuel handling operator training includes a discussion of an approach for misload accidents.
Based on the presentation, please discuss the licensees approach for modeling the Spent Fuel Pool (SFP) based on a 6x6 over 3x3 assembly configurations.
The LAR should also ensure that the submittal discusses only the categories of combinations selected and present justification as to why they should be considered acceptable.
Discuss and describe what constitutes the 6 legacy fuels that will be considered for this LAR.
The NRC staff recommended that the future LAR discuss the difference in footprint for the 15x15 Oconee Nuclear Station fuel versus the standard McGuire fuel type, the differences between the different fuel types to be stored in the SFP. The NRC staff also recommended that due diligence be performed on the history of the fuel within the SFP, and disposition items not included within the modeling (e.g., hafnium rods not used).
What is the purpose and function of the spacing between region 1 and 2, shown in the presentation?
Ensure that the LAR submittal addresses and provides justification for any eccentric positioning.
Discuss and describe in detail the graph shown on page 11 of the slides.
Describe to the NRC staff the reason for the color differences shown on page 15 of the slides.
It is suggested to plot graph on Slide 23 from minimum to maximum, as well as including Method 1 and Method 2 data in a singular diagram.
How will the TSs be written and presented in the amendment for the existing and the future fuel and SFP configuration change?
The proposed TSs changes, once implemented, will bound current and future fuel designs. Only the new proposed TS will exist moving forward once implemented (i.e., only one set of TS moving forward after implementation).
It is anticipated that a second presubmittal meeting will be held in the future in the second quarter of 2026, approximately.
It is anticipated that an audit will be conducted for this LAR.
The NRC staff opened the meeting for public comments and questions. There were no public comments or questions.
The NRC staff did not make any regulatory decisions during the meeting.
Please direct any inquiries to John.Klos@nrc.gov.
/RA/
John Klos, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369, and 50-370.
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES AUGUST 11, 2025, PUBLIC MEETING WITH DUKE ENERGY FOR PLANNED SFP CRITICALITY LAR Name Organization John Klos U.S. Nuclear Regulatory Commission (NRC)
Matt Yoder NRC Brandon Wise NRC Kent Wood NRC Matt Hamm NRC Reena Boruk NRC Alex Collier NRC Jack Vande Polder NRC Kevin Heller NRC Dennis Earp Duke Energy Carolinas, LLC (Duke)
David Orr Duke Robert Hall Duke Damon Bryson Duke
ADAMS Package: ML25224A147 Meeting Notice: ML25198A154 Meeting Summary: ML25224A162
- via eConcurrence NRC-001 OFFICE NRR/DORL/LPL2-1/PM*
NRR/DORL/LPL2-1/LA*
NRR/DNRL/NCSG/BC*
NAME JKlos KZeleznock SBloom DATE 8/12/2025 8/18/2025 8/18/2025 OFFICE NRR/DSS/SFNB/BC*
NRR/DSS/STSB/BC*
NRR/DORL/LPL2-1/BC*
NAME SKrepel SMehta MMarkley DATE 8/22/2025 8/25/2025 8/25/2025 OFFICE NRR/DORL/LPL2-1/PM*
NAME JKlos DATE 8/26/2025