ML22115A002

Correction to Amendment No. 350 Regarding One-Time Change to Technical Specification3.4.12, Low Temperature Overpressure Protection System,

ML22115A002
Person / Time
Site:	Sequoyah
Issue date:	05/17/2022
From:	Perry Buckberg Plant Licensing Branch II
To:	Jim Barstow Tennessee Valley Authority
Wentzel M
References
EPID L 2021-LLA-0194
Download: ML22115A002 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 17, 2022

Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNIT 2 - CORRECTION TO AMENDME NT NO.

350 REGARDING ONE-TIME CHANGE TO TECHNICAL SPECIFICATION 3.4.12,

LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM, (EPID L-2021-LLA-0194)

Dear Mr. Barstow:

By letter dated October 27, 2021 (Agencywide Documents Access a nd Management System (ADAMS) Accession No. ML21298A031), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 350 to Renewed Facility Operating License (RFOL) No. DPR-79 for the Sequoyah Nuclear Plant, Unit 2. The amendment revised Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to add a on e-time note to allow operation of one safety injection pump and one charging pump capable of injecting into the reactor coolant system during MODE 5 or MODE 6 with the pressur izer manway cover removed.

An error was identified in this license amendment in that RFOL No. DPR-79 page 3 was inadvertently not included as part of Enclosure 1 to the licens e amendment.

Enclosed with this letter is RFOL No. DPR-79 page 3 for License Amendment No. 350.

The error does not change any of the conclusions in the safety evaluation associated with the October 27, 2021, Amendment No. 350, nor does it affect the no significant hazard consideration, as published in the Chattanooga Times Free Press on October 26, 2021.

J. Barstow

If you have any questions, please contact me at (301) 415-1383 or via e-mail at Perry.Buckberg@nrc.gov.

Sincerely,

/RA/

Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket No. 50-328

Enclosure:

Current Technical Specification Page 3

cc: Listserv ENCLOSURE

CORRECT PAGE 3 OF RENEWED FACILITY OPERATING LICENSE NO. DPR-79

FOR LICENSE AMENDMENT NO. 350

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT, UNIT 2

DOCKET NO. 50-328

- 3 -

(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to rece ive, possess, and use at any time any byproduct, source and special nuclear m aterial as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to rece ive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive appara tus or components; and

(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to poss ess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 350 are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

Amendment No. 350 Renewed License No. DPR-79

ML22115A002 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA OGC NAME PBuckberg RButler JAzeizat DATE 04/26/2022 04/26/2022 05/10/2022 OFFICE NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME DWrona PBuckberg DATE 05/17/2022 05/17/2022