ML25233A021
| ML25233A021 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/21/2025 |
| From: | Michael K Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML25233A021 (1) | |
Text
Sequoyah Nuclear Plant, Post Office Box 2000, Soddy Daisy, Tennessee 37384 August 21, 2025 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 2 Renewed Facility Operating License No. DPR-79 NRC Docket No. 50-328
Subject:
Unit 2 Cycle 26 Refueling Outage Day Inservice Inspection Summary Report In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition and the 2008 Addenda, Article IWA-6240 and Code Case N-532-5, the Tennessee Valley Authority is providing the Sequoyah Nuclear Plant (SQN),
Unit 2, Inservice Inspection (ISI) Summary Report within 90 days from completion of the Unit 2 Cycle 26 Refueling Outage (U2C26). The U2C26 refueling outage ended on May 26, 2025.
Accordingly, this report is required to be submitted by August 24, 2025.
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. Rick Medina, Site Regulatory Compliance Manager at (423) 843-8129 or rmedina4@tva.gov.
Respectfully, Kevin M. Michael Site Vice President Sequoyah Nuclear Plant
U.S. Nuclear Regulatory Commission Page 2 August 21, 2025
Enclosure:
ASME Section XI Inservice Inspection Summary Report, Unit 2 Cycle 26 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 2 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
REPORT UNIT 2 CYCLE 26 REFUELING OUTAGE
Pl,111I U111t No Current Inspection Interval Current Inspection Penod 2
FOl~M OAR-1 OWNER'S ACTIVITY REPORT U2R26 SEQUOYAH NUCI.EAI~ Pl AN I, PO Box 2000, Soddy-Daisy, TN 37384 -2000 Cornmcrc1al Serv1co Date
___ J1111u _I._ 1_982 _
Refuelmg Outage No 26 4Ih (ISi) wId 3rd (CISI)
(I , ).' ' 1 4" olhcr) 3rd (ISi) and 2nd (CISI)
(I 2 T' )
Ed1t1on and Addenda ol Section XI applicnble to the lnspoclion Pl;111~
2007 Edition, 200/l Addenda - lnscrvicc lnspection(ISI) 201 :l Edition*- Containment lnservice lnspection(CISI)
Date I Revision of Inspection Plans November 20, 2023. 0-TPP-DXl-114.4 Rev 2 (ISIJ April 17, 2024: 0-TPP-DXl-114.4 Rev. 3 (ISi)
July 22, 2024: 0-TPP-DXl-000-114.4 Rev. 4 (ISi)
February 17, 2022 0-PI-DXl-000-116.3 Rev. 1 (CISIJ Edition and Addenda of Section XI applicable to repair/replacement act1v1t1cs, if d1ffercnI than the inspection plans
______ 2007 Edition, 2008 Addenda Code Cases used.
N-508-4, N-532-5, N-586-1, N-613-2, N-648-1, N-716-1, N-722-1. N-729-6, N-731, N-747, N-751, N-770-5, N-798,
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CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in lh1s report are correct, (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code,Section XI, and (c) the repair/replacement activities and evaluations supporting the completion of U2R26 conform to the requirements of Sectio XI (relueln<J Oulago """'"" "
Signed
~
Date ---------
wner's Oes,gnee. 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. Connecticut have inspected the items described 1n this Owner's Aclivity Report, and state that, to lhe 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. neither the Inspector nor his employer shall be liablo in any manner for any personal injury or pr perty damage loss of any kind arising from or connected w1lh this inspection N 1~1130 IN R (National Board Number and E:ndorscment)
Date E-1 of 4
E-2 of 4 TABLE 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description F-A, F1.20C Variable Spring Support 2-AFDH-316 setting found to be out of tolerance and found to contain a bent rod.
CR 1953133 Evaluation found support would continue to perform its design function. Based on the Civil Design Evaluation, the variable spring support, BE-401 Type B Size 4 catalog, was well within the working load range, and the minor bend in the rod support would not prevent the support from performing its intended function. All the support components had significant margin, and the increased load identified during inspection was insignificant per calculation 2-AFDH-0316 and Catalog 193 Basic-PSA, INC. Accepted as is, and WO 124757011 was electively generated to restore the support to the original design compliant condition.
E-3 of 4 TABLE 2 Abstract of Repair/replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 3
SQN-2-CLR-030-0195 Replace the 2B-B 714 Pen Room Cooler due to through wall tube leak 5/24/2023 122564426 3
SQN-0-STN-067-1065 Replace 1 strainer blowdown flange due to through wall leak 6/28/2023 123802272 3
SQN-2-AHU-313-0367 Replace piping/fittings with new on 2B Shutdown Board Room cooler due to through wall leak 5/19/2025 125302018
E-4 of 4 REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)(2)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection Program 10 CFR 50.55a(b)(2)(ix)(A)(2) requires licensee to provide the following in the ISI Summary Report as required by IWA-6000:
(i) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (ii) An evaluation of each area, and the result of the evaluation; and (iii) A description of necessary corrective actions.
There were no conditions identified during the Unit 2 Cycle 26 refueling outage on the items examined that prompted an evaluation of the inaccessible area of the SCV, as required.