ML23144A086

Acceptance of Requested Licensing Action Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853

ML23144A086
Person / Time
Site:	Oconee
Issue date:	05/24/2023
From:	Shawn Williams Plant Licensing Branch II
To:	Treadway R Duke Energy Carolinas
Williams S
References
EPID L-2023-LLR-0024
Download: ML23144A086 (2)

Text

From: Shawn Williams To: Treadway, Ryan I Cc: Vaughan, Jordan L

Subject:

Oconee Nuclear Station, Units 1, 2, and 3 - Acceptance of Requested Licensing Action RE: Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853 (EPID L-2023-LLR-0024)

Date: Wednesday, May 24, 2023 8:37:06 AM

Mr. Treadway,

By letter dated May 4, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23124A384), Duke Energy Carolinas, LLC, (the licensee, Duke Energy) submitted Relief Request (RA-23-0018) for Oconee Nuclear Station, Units 1, 2, and 3. Specifically, Duke Energy is requesting to utilize Code Case N-853, "PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1" with deviations, for the 6th inservice inspection interval currently scheduled to start in July 15, 2024, and end July 14, 2034. Duke Energy submitted the request pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations, which requires the applicant to demonstrate that the proposed alternative would provide an acceptable level of quality and safety.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to begin its detailed technical review. The acceptance review is also intended to identify whether the request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to begin its detailed technical review and make an independent assessment regarding the acceptability of the proposed request 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 in despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> to complete. The NRC staff expects to complete this review by January 24, 2024. 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. These estimates are based on the NRC staffs initial review of the application and they can change due to several factors including requests for additional information, and unanticipated addition of scope to the review. 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 Shawn Williams at (301) 415-1009 or Shawn.Williams@nrc.gov.

Shawn Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-269, 50-270, 50-287

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