ML25112A223
| ML25112A223 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/22/2025 |
| From: | Wetzel B Plant Licensing Branch III |
| To: | Kivi J, Mark Miller Northern States Power Co |
| Ballard, Brent | |
| References | |
| EPID L-2025-LLA-0047 | |
| Download: ML25112A223 (1) | |
Text
From:
Beth Wetzel To:
Miller, Michael A; Kivi, Jeffrey L Cc:
Subject:
Prairie Island Nuclear Generating Plant - Acceptance of Requested Licensing Action re: Request to Revise Technical Specifications to Adopt TSTF-541 (EPID-L-2025-LLA-0047)
Date:
Tuesday, April 22, 2025 9:33:00 AM Good morning,
By letter L-PI-25-006 dated March 12, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25071A416), as supplemented on April 15, 2025 (ADAMS Accession No. ML20105A222), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy submitted a request for an amendment to the Technical Specifications (TS) for the Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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 proposed LAR would revise the Technical Specifications to adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, which is an approved change to the Standard Technical Specifications (STS), into the PINGP Units 1 and 2 Technical Specifications (TS). The proposed amendment modifies certain TS Surveillance Requirements (SRs) by adding exceptions to consider the SR met when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position, in order to consider the SR met.
Securing the automatic damper in the actuated position may affect the operability of the system or any supported systems. The associated Limiting Condition for Operation (LCO) is met if the subject structure, system or component (SSC remains operable (i.e.,
capable of performing its specified safety function).
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an application for an amendment to a license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your submittal 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 amendment 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 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 request will take approximately 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> to complete. The NRC staff expects to complete this review by October 15, 2025. 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 could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by the NRC advisory committees or hearing-related activities. 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 at 301-415-5223 or by e-mail.
Thank you, Beth
Beth Wetzel Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-5223