ML23172A015
| ML23172A015 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/20/2023 |
| From: | Dennis Galvin NRC/NRR/DORL/LPL4 |
| To: | Hicks J Vistra Operations Company |
| References | |
| L-2023-LLA-0058 | |
| Download: ML23172A015 (3) | |
Text
From:
Dennis Galvin Sent:
Tuesday, June 20, 2023 4:27 PM To:
Jack Hicks (Jack.Hicks@luminant.com)
Cc:
ryan.sexton@vistracorp.com
Subject:
RE: Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix A to 10 CFR Part 50 and Regulatory Guide 1.81 (EPID L-2023-LLA-0058)
Dear Mr. Hicks,
By letter dated April 20, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23110A156), as supplemented by letter dated June 15, 2023 (ML23166B144), Vistra Operations Company LLC (Vistra OpCo, the licensee) submitted a license amendment request for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (Comanche Peak), regarding changes to the Final Safety Analysis Report (FSAR). Specifically, the proposed amendments would allow a deviation in compliance to Regulatory Guide 1.81, Revision 1, Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants (ML003740343) to meet the regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix A, General Design Criteria for Nuclear Power Plants, General Design Criterion 5, Sharing of structures, systems, and components, and address the violation issued in the Comanche Peak Integrated Inspection Report dated November 1, 2022 (ML22299A056). To support the proposed amendment, the licensee proposed FSAR changes to provide additional description of the power feeds to some common 125 volts direct current and 118 volts alternating current safety-related electrical buses, which can be fed from both units and also feeds some Unit 1 specific loads. The licensee also submitted Technical Specifications (TSs)
Bases changes (mark-up) necessary to account for changes in the FSAR.
The purpose of this correspondence 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 10 CFR 50.90, 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, as supplemented, 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 and supplement, the NRC staff has estimated that this licensing request will take approximately 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br /> to complete. The NRC staff expects to complete this review by June 20, 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, and unanticipated addition of scope to the review. 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) 415-6256.
Respectfully, Dennis Galvin, Project Manager Plant Licensing Branch 4 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445, 50-446
Hearing Identifier:
NRR_DRMA Email Number:
2137 Mail Envelope Properties (SA1PR09MB811171BA8D1B14752D289C78FB5CA)
Subject:
RE Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix A to 10 CFR Part 50 and Regulatory Guide 1.81 (EPID L-2023-LLA-0058)
Sent Date:
6/20/2023 4:26:50 PM Received Date:
6/20/2023 4:26:00 PM From:
Dennis Galvin Created By:
Dennis.Galvin@nrc.gov Recipients:
"ryan.sexton@vistracorp.com" <ryan.sexton@vistracorp.com>
Tracking Status: None "Jack Hicks (Jack.Hicks@luminant.com)" <Jack.Hicks@luminant.com>
Tracking Status: None Post Office:
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