ML20303A077: Difference between revisions

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==Dear Mr. Taylor,==
==Dear Mr. Taylor,==


By letter dated September 23, 2020 (Agencywide Documents Access and Management System Accession No. ML20267A617), the Tennessee Valley Authority (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, respectively. The proposed amendments would revise Technical Specifications (TSs) to allow the use of Westinghouse RFA-2 fuel with Optimized ZIRLOTM cladding. Further, the proposed amendments would revise TS 5.6.3, Core Operating Limits Report to replace the loss-of-coolant accident analysis evaluation model references with the FULL SPECTRUM' Loss-of-Coolant Accident (FSLOCA') Evaluation Model. Finally, the proposed amendments would revise the TSs to permit the use of 52 full length control rods with no full-length control rod assembly in core location H-08. The license amendment request included a related request for exemption from the requirements of Section 50.46 of Title 10 of the Code of Federal Regulations (10 CFR) and Appendix K to 10 CFR Part 50. That exemption request will be processed separately from this license amendment request. The U.S. Nuclear Regulatory Commission (NRC) staff performs acceptance reviews of applications to determine if the scope and depth of technical information is sufficient for the staff to complete its technical reviews. The acceptance reviews also intend 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.
By {{letter dated|date=September 23, 2020|text=letter dated September 23, 2020}} (Agencywide Documents Access and Management System Accession No. ML20267A617), the Tennessee Valley Authority (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, respectively. The proposed amendments would revise Technical Specifications (TSs) to allow the use of Westinghouse RFA-2 fuel with Optimized ZIRLOTM cladding. Further, the proposed amendments would revise TS 5.6.3, Core Operating Limits Report to replace the loss-of-coolant accident analysis evaluation model references with the FULL SPECTRUM' Loss-of-Coolant Accident (FSLOCA') Evaluation Model. Finally, the proposed amendments would revise the TSs to permit the use of 52 full length control rods with no full-length control rod assembly in core location H-08. The license amendment request included a related request for exemption from the requirements of Section 50.46 of Title 10 of the Code of Federal Regulations (10 CFR) and Appendix K to 10 CFR Part 50. That exemption request will be processed separately from this license amendment request. The U.S. Nuclear Regulatory Commission (NRC) staff performs acceptance reviews of applications to determine if the scope and depth of technical information is sufficient for the staff to complete its technical reviews. The acceptance reviews also intend 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 TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original application.
Consistent with 10 CFR 50.90, an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original application.
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.
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.

Latest revision as of 21:55, 7 March 2021

NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Request to Transition to Westinghouse RFA-2 Fuel
ML20303A077
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 10/29/2020
From: Michael Wentzel
NRC/NRR/DORL/LPL2-2
To: Taylor A
Tennessee Valley Authority
References
L-2020-LLA-0216
Download: ML20303A077 (3)
v • d • e


Text

From: Wentzel, Michael Sent: Thursday, October 29, 2020 7:12 AM To: Taylor, Andrew Charles Cc: Shoop, Undine; Williams, Gordon Robert

Subject:

Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Request to Transition to Westinghouse RFA-2 Fuel (EPID L-2020-LLA-0216)

Dear Mr. Taylor,

By letter dated September 23, 2020 (Agencywide Documents Access and Management System Accession No. ML20267A617), the Tennessee Valley Authority (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, respectively. The proposed amendments would revise Technical Specifications (TSs) to allow the use of Westinghouse RFA-2 fuel with Optimized ZIRLOTM cladding. Further, the proposed amendments would revise TS 5.6.3, Core Operating Limits Report to replace the loss-of-coolant accident analysis evaluation model references with the FULL SPECTRUM' Loss-of-Coolant Accident (FSLOCA') Evaluation Model. Finally, the proposed amendments would revise the TSs to permit the use of 52 full length control rods with no full-length control rod assembly in core location H-08. The license amendment request included a related request for exemption from the requirements of Section 50.46 of Title 10 of the Code of Federal Regulations (10 CFR) and Appendix K to 10 CFR Part 50. That exemption request will be processed separately from this license amendment request. The U.S. Nuclear Regulatory Commission (NRC) staff performs acceptance reviews of applications to determine if the scope and depth of technical information is sufficient for the staff to complete its technical reviews. The acceptance reviews also intend 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 TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original application.

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 concluded that the licensees submittal provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed 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 the NRC staff identifies issues that affect its ability to complete the detailed technical review despite completion of an adequate acceptance review. If the NRC staff needs additional information, it will notify the licensee by separate correspondence.

The staff has estimated that it will take approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> to complete this licensing request and that it will complete its review within one year of acceptance of the application (i.e., by October 2021).

These estimates are based on the NRC staffs initial review of the application and could change because of several factors, such as requests for additional information, unanticipated addition of application scope, review by NRC advisory committees, or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance of or in parallel with industry program initiatives or pilot

applications. If complexities or challenges during the review cause significant changes to the estimated hours or completion date, the assigned project manager will communicate the new estimates and reasons for the changes to the licensee during routine interactions.

If you have any questions, please contact me at (301) 415-6459 or michael.wentzel@nrc.gov.

Sincerely, Michael J. Wentzel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Hearing Identifier: NRR_DRMA Email Number: 869 Mail Envelope Properties (MN2PR09MB5867D54EC3ED54E79F1F3EFCE7140)

Subject:

Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Request to Transition to Westinghouse RFA-2 Fuel (EPID L-2020-LLA-0216)

Sent Date: 10/29/2020 7:12:05 AM Received Date: 10/29/2020 7:12:05 AM From: Wentzel, Michael Created By: Michael.Wentzel@nrc.gov Recipients:

"Shoop, Undine" <Undine.Shoop@nrc.gov>

Tracking Status: None "Williams, Gordon Robert" <grwilliams1@tva.gov>

Tracking Status: None "Taylor, Andrew Charles" <actaylor@tva.gov>

Tracking Status: None Post Office: MN2PR09MB5867.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 3999 10/29/2020 7:12:05 AM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

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