ML21217A288

Cycle 24 Refueling Outage - 90-Day Inservice Inspection Summary Report

ML21217A288
Person / Time
Site:	Sequoyah
Issue date:	08/04/2021
From:	Marshall T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
U1R24
Download: ML21217A288 (5)

Text

1\14 TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant, Post Office Box 2000, Soddy Daisy, Tennessee 37384 August 4, 2021 10 CFR 50.4 10 CFR 50.55a ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-77 NRC Docket No. 50-327

Subject:

Unit 1 Cycle 24 Refueling Outage Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Article IWA-6240 and Code Case N-532-5, the Tennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN), Unit 1, Inservice Inspection (ISI)

Summary Report within 90 days from completion of the Unit 1 Cycle 24 Refueling Outage (U1C24). The U1C24 refueling outage ended on May 10, 2021. Accordingly, this report is required to be submitted by August 8, 2021.

The Enclosure to this letter contains the Owners Activity Report, a list of items with flaws or relevant conditions that required evaluation for continued service (Table 1), an abstract of repair and replacement activities required for continued service due to a flaw or relevant condition (Table 2), and the evaluation of acceptability of inaccessible areas of the steel containment vessel in accordance with 10 CFR 50.55a(b)(2)(ix)(A).

There are no new regulatory commitments associated with this submittal. Should you have any questions, please contact Mr. Jeff Sowa, Site Licensing Manager at (423) 843-8129.

Respectfully, Marshall, Digitally signed by Marshall, Thomas B.

Thomas B. Date: 2021.08.04 14:29:02

-04'00' Thomas B. Marshall Site Vice President Sequoyah Nuclear Plant

U.S. Nuclear Regulatory Commission Page 2 August 4, 2021

Enclosure:

ASME Section XI Inservice Inspection Summary Report, Unit 1 Cycle 24 Refueling Outage cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant

ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNIT 1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT UNIT 1 CYCLE 24 REFUELING OUTAGE E-1

FORM OAR-1 OWNER'S ACTIVITY REPORT U1R24 Report Number Plant SEQUOYAH NUCLEAR PLANT, P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Unit No. Commercial service date July 1, 1981 Refueling outage no. 24 rit applicable)

Current inspection interval Fourth Inspection interval (1", 2"', 3"'. 4~, other)

Current inspection period Second Inspection Period of the Fourth Interval for ISi First Inspection Period of the rourth Interval for IWE:

(1", 2"'. 3"'}

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition, 2008 Addenda Date and revision of inspection November 8, 2019 PI-DXl-000-114.4 Revision 2 plans March 10, 2020 PI-DXl-000-114.4 Revision 3 August 25, 2020- 0-PI-DXl-000-114.4 Revision 4 Septem ber 12, 2018 PI-DXl-000-116.3 Revision o Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases N-508-4, N-513-3 , N-532-5, N-586-1 , N-716-1, N-722-1 , N-729-4, N-729-6, N-770-2, N-770-5 used :

VI applicable, including cases modified by Case N-532 and later revisions)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan required by the ASME Code XI and (c) the repair/replacement activities and evaluations supporting the completion of U1 R24 conform to the requirements of Section XI.

Signed o;,,..., .. _,..,,_,,.,,.. R/R Program Owner Date Merrill, James Dylan :;:::,*,,,21 ,,,n, """' .,,.w Brevard, Darien Wayne ~:!~;~;;i,br:~;;~~~W ayne Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neitr.er the Inspector nor his employer shall be liable in manner for personal injury or property damage or a loss of any kind arising from or connected with this inspection.

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ASME SECTION XI INSERVICE INSPECTION

SUMMARY

REPORT SEQUOYAH NUCLEAR PLANT UNIT 1 CYCLE 24 REFUELING OUTAGE TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number None None None TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/Replacement Class Description of Work Completed Plan Number 3 SQN-1-VLV-067-0520A Replace pipinQ 5n12021 121604966 2 SQN-1-VLV-001-0621 Replace bolting 5/11/2021 121975429 2 SQN-1-VLV-003-0511 Replace bonnet boltinQ 5/8/2021 122073065 REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)

ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10 CFR 50.55a(b )(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the performance of the ASME Section XI , Subsection IWE Steel Containment Vessel (SCV)

Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.

There were no conditions identified during the Unit 1 Cycle 24 refueling outage on the items examined that prompted an evaluation of the inaccessible area of the SCV, as required.