ML24185A091

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Acceptance of LAR to Revise TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses
ML24185A091
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 07/01/2024
From: Ballard B
Plant Licensing Branch III
To: Kivi J, Mark Miller
Northern States Power Co
References
EPID L-2024-LLA-0067
Download: ML24185A091 (1)


Text

From: Brent Ballard To: Miller, Michael A; Kivi, Jeffrey L Cc: Jeff Whited

Subject:

Prairie Island, Units 1 and 2 - Acceptance of LAR to Revise TS Definition of REACTOR TRIP SYSTEM (RTS)

RESPONSE TIME and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses Date: Monday, July 1, 2024 12:00:00 PM

Good morning Mike and Jeff,

By letter dated June 3, 2024 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML24155A220), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The proposed amendment would revise the Technical Specification (TS) definition of REACTOR TRIP SYSTEM (RTS) RESPONSE TIME used in TS Surveillance Requirement 3.3.1.16 to allow allocation of response times in lieu of testing using methodologies proposed in the LAR, and revise applicability of SR 3.3.1.16 to RTS trip functions in TS Table 3.3.1-1.

The purpose of this letter 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.

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 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 amendment 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 licensing request will take approximately 430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> to complete. The NRC staff expects to complete this review in approximately 10.5 months, about May 16, 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 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 301-415-0680 or by e-mail.

Thank you, Brent

Brent Ballard Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-0680