ML23018A295

Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email)

ML23018A295
Person / Time
Site:	Prairie Island
Issue date:	01/18/2023
From:	Ballard B Plant Licensing Branch III
To:	Kivi J Xcel Energy
Kuntz R
References
EPID L-2022-LLA-0184
Download: ML23018A295 (1)

Text

Brent Ballard From: Brent Ballard Sent: Wednesday, January 18, 2023 12:28 PM To: Jeffrey.L.Kivi@xcelenergy.com Cc: michael.a.miller@xcelenergy.com; Nancy Salgado

Subject:

Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, "Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)" (EPID L-2022-LLA-0184)

Good afternoon, By letter L-PI-22-020 dated December 2, 2022 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML22343A257), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) for Prairie Island Nuclear Generating Plant, Unit 1 and Unit 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 Technical Specification (TS) 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), to replace the current PTLR method with more recent analytical methods for determining RCS pressure and temperature limits and cold overpressure mitigating system setpoints, and for calculating neutron fluence. The proposed amendment would also remove from TS 5.6.6 a reference to an American Society of Mechanical Engineers (ASME) Code Case that is no longer necessary.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an application for an amendment to the 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 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 licensing request will take approximately 275 hours0.00318 days <br />0.0764 hours <br />4.546958e-4 weeks <br />1.046375e-4 months <br /> to complete. The NRC staff expects to complete this review by January 18, 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 could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC 1

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 2