ML23145A004

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Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies
ML23145A004
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/25/2023
From: Richard Guzman
NRC/NRR/DORL/LPL1
To: Sinha S
Dominion Energy Nuclear Connecticut
References
EPID L-2023-LLA-0065
Download: ML23145A004 (1)


Text

From: Richard Guzman To: Shayan Sinha Cc: RidsNRRLIC109 Resource; Hipo Gonzalez

Subject:

Millstone Power Station, Unit 3 - Acceptance Review Determination Re: LAR to Revise to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Methodologies (EPID L-2023-LLA-0065)

Date: Thursday, May 25, 2023 6:44:00 AM Mr. Sinha, By letter dated May 2, 2023 (ADAMS Accession No. ML23123A279), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request (LAR) for Millstone Power Station, Unit No. 3 (MPS3). The amendment proposes to revise MPS3 Technical Specification (TS) 6.9.1.6.b to add Framatome (FRM) Topical Reports EMF-2328-P-A, "PWR Small Break LOCA [loss of coolant accident] Evaluation Model, S-RELAP5 Based," EMF-2103-P-A, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," and ANP-10349-P-A, "GALILEO Implementation in LOCA Methods" to the list of methodologies for establishing core operating limits. The proposed TS changes are needed to support the transition to FRM GAIA fuel with M5' cladding at MPS3, which requires the application of the FRM Small Break Loss of Coolant Accident (SBLOCA) and Realistic Large Break Loss of Coolant Accident (RLBLOCA) methodologies and the associated use of the GALILEO fuel performance code within the LOCA methods.

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 licensing action. 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),

whenever a holder of an operating license under this part desires to amend the license, application for an amendment must be filed with the Commission fully describing 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. If additional information is needed, you will be advised by separate correspondence.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> to complete. The NRC staff expects to complete this review by May 24, 2024. If there are emergent complexities or challenges in

our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), 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.

~~~~~~~~~~~~

Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov