ML22207A012

Acceptance Review Determination Revision to Alternative Source Term Analysis for Containment Leakage

ML22207A012
Person / Time
Site:	Nine Mile Point
Issue date:	07/26/2022
From:	Richard Guzman NRC/NRR/DORL/LPL1
To:	Reynolds R Constellation Energy Generation
Guzman R
References
EPID L-2022-LLR-0094
Download: ML22207A012 (2)

Text

From: Guzman, Richard To: Reynolds, Ronnie J.:(Exelon Nuclear)

Cc: RidsNRRLIC109 Resource; Gonzalez, Hipo

Subject:

Nine Mile Point Nuclear Station, Unit No. 1 - Acceptance Review Determination: Revision to Alternative Source Term analysis for Containment Leakage [EPID: L-2022-LLA-0094]

Date: Tuesday, July 26, 2022 7:05:28 AM Mr. Reynolds, By letter dated June 29, 2022 (ADAMS Accession No. ML22180A020), Constellation Energy Generation, LLC (CEG, the licensee) submitted a license amendment request (LAR) for Nine Mile Point Nuclear Station, Unit 1 (Nine Mile Point 1). The LAR proposes to revise the post-loss-of-coolant accident alternative source term (AST) analysis for containment leakage at NMP1. The proposed changes are in response to a Nuclear Regulatory Commission (NRC) inspection finding where it was discovered that changes were made to the original 2007 AST analysis that when taken consecutively, would not have been allowed via Section 50.59 of Title 10 of the Code of Federal Regulations (10 CFR). The first change was performed where corrections to the chemical group assignment for various radionuclides modeled in the RadTrad 3.03 code were needed. The second change involved updates and recategorizations to the modeling of both main steam isolation valve (MSIV) leakage and non-MSIV leakage.

The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this 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 submittal 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 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 the licensees submittal and concludes 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 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 the review of the LAR will take approximately 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> to complete. The NRC staff expects to complete this review by March 31, 2023. 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 and unanticipated addition of scope to the review.

Please contact me if you have any questions. A copy of this e-mail will be made publicly available in ADAMS.

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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