ML25042A111
| ML25042A111 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/11/2025 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Jeanne Johnston Southern Nuclear Operating Co |
| References | |
| L-2025-LLL-0002 | |
| Download: ML25042A111 (3) | |
Text
From:
John Lamb Sent:
Tuesday, February 11, 2025 9:53 AM To:
Johnston, Jeanne D.
Cc:
Joyce, Ryan M.
Subject:
Acceptance Review - Vogtle 1 and 2 - License Renewal Commitment Item 20 -
a Plant-specific Analysis of Certain Reactor Vessel Internal Components (L-2025-LLL-0002)
- Jeanne, By letter dated January 16, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25016A339), Southern Nuclear Operating Company (SNC, the licensee) submitted, in accordance with license renewal commitment Item 20, a plant-specific analysis of certain reactor vessel internal components at the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, for the U.S. Nuclear Regulatory Commission (NRC) staff review and approval.
The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this licensing action request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The Vogtle, Units 1 and 2, Updated Final Safety Analysis Report (UFSAR) (ML24297A651),
Section 19.2.24, Reactor Vessel Internals Program, states:
The Reactor Vessel Internals Program is a plant-specific program that addresses material degradation issues for the VEGP [Vogtle Electric Generating Plant] reactor vessel internals.
The program will be based on the following set of implementation commitments:
- a. SNC will participate in the industry program for investigating and managing aging effects on reactor vessel internals.
[Electric Power Research Institute] Material Reliability Program (MRP), as applicable to the VEGP reactor vessel internals.
- c. SNC will submit an inspection plan for the VEGP reactor vessel internals to the NRC for review and approval not less than 24 months before entering the period of extended operation for VEGP Units 1 and 2. This inspection plan will address the bases, inspection methods, and acceptance criteria associated with aging management of the reactor vessel thermal sleeves and the core support lugs (along with the associated support pads and attachment welds).
The Reactor Vessel Internals Program will be implemented prior to the period of extended operation.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review
and make an independent assessment regarding the acceptability of the proposed licensing action in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
Based on the information provided in your submittal and discussions during the pre-licensing meeting on December 16, 2024 (ML24352A079), the NRC staff has estimated that this licensing request will take approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> to complete. The NRC staff expects to complete this review by February 11, 2026. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager.
Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
If you have any questions, please contact me.
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier:
NRR_DRMA Email Number:
2723 Mail Envelope Properties (MN2PR09MB5084F1C74F841CBE3FE627E9FAFD2)
Subject:
Acceptance Review - Vogtle 1 and 2 - License Renewal Commitment Item 20 - a Plant-specific Analysis of Certain Reactor Vessel Internal Components (L-2025-LLL-0002)
Sent Date:
2/11/2025 9:52:52 AM Received Date:
2/11/2025 9:52:00 AM From:
John Lamb Created By:
John.Lamb@nrc.gov Recipients:
"Joyce, Ryan M." <RMJOYCE@southernco.com>
Tracking Status: None "Johnston, Jeanne D." <JEAJOHNS@SOUTHERNCO.COM>
Tracking Status: None Post Office:
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