ML23192A097
| ML23192A097 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/11/2023 |
| From: | Marshall T Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML23192A097 (1) | |
Text
Sequoyah Nuclear Plant, Post Office Box 2000, Soddy Daisy, Tennessee 37384 July 11, 2023 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 25 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 2, Inservice Inspection (ISI)
Summary Report within 90 days from completion of the Unit 2 Cycle 25 Refueling Outage (U2C25). The U2C25 refueling outage ended on April 15, 2023. Accordingly, this report is required to be submitted by July 14, 2023.
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 Licensing Manager at (423) 843-8129.
Respectfully, Thomas B. Marshall Site Vice President Sequoyah Nuclear Plant 1\\14 TENNESSEE VALLEY AUTHORITY Marshall, Thomas B.
Digitally signed by Marshall, Thomas B.
Date: 2023.07.11 10:12:05 -04'00'
U.S. Nuclear Regulatory Commission Page 2 July 11, 2023
Enclosure:
ASME Section XI Inservice Inspection Summary Report, Unit 2 Cycle 25 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 25 REFUELING OUTAGE
Report Number Plant Unit No.
Current Inspection Interval Current Inspection Period 2
(if applicable)
FORM OAR-1 OWNER'S ACTIVITY REPORT U2R25 SEQUOYAH NUCLEAR PLANT, P.O. Box 2000, Soddy-Daisy, TN 37384-2000 Commercial Service Date June 1, 1982 4th (1'1, 2nd, 3rd, 4'", other) 2nd and 3rd (1~. 2nd, 3rd )
Refueling Outage No.
25 2007 Edition, 2008 Addenda - lnservice lnspection(ISI)
Edition and Addenda of Section XI applicable to the Inspection Plans 2013 Edition - Containment lnservice lnspection(CISI)
May 20, 2021 : 0-PI-DXl-000-114.4 Rev. 5 (ISi)
October 29, 2021 : O-PI-DXl-000-114.4 Rev. 6 (ISi)
March 14, 2022: 0-PI-DXl-000-114.4 Rev. 7 (ISi)
October 23, 2022: 0-TPP-DXl-000-114.4 Rev. 0 (ISi)
February 6, 2023: 0-TPP-DXl-000-114.4 Rev. 1 (ISi)
Date I Revision of Inspection Plans February 17, 2022: O-PI-DXl-000-116.3 R0001 (CISI)
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the 2007 Edition, 2008 Addenda inspection plans Code Cases used:
N-508-4, N-532-5, N-586-1, N-716-1, N-722-1, N-729-6 N-770-5 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this 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 U2R25 conform to the requirements of Section XI.
(refueling outage number)
Signed
~£ _ _&-..k3/4
/
Owner or Owner's Dealgnee, TIUe Date --"-b..._/---'z_,;,I.....__I_~..;....;~=-----
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boller and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut 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, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage, or a loss of any kind arising from or connected with this inspection.
---:;--"';;;;--- ~~
Commissions Na,.., 77J 0 I /\\.I R.
~
(National Board Number and Endorsement)
Date E-1 of 3
TABLE 1 Items With Flaws or Relevant on tons at C
di I Th R eau red Evaluation for C ont nue dS erv ce Examination Category and Item Number Item Description Evaluation Descrlotlon Support 2-FDH-322 CR 1846314 F-A/F1.20C Evaluation found support remains functional. WO123576377 Loose nut on pipe clamp corrected loose boltina and re-exam.
Support 2-MSH-423 CR 1846311 F-A/ F1.20D Evaluation found support remains functional. WO 123576376 Loose bolting on pipe clamp corrected loose boltina and re-exam.
CR 1738092 D-B I D2.10 2B-B 714' Pen Room Cooler This condition was evaluated using TVA's Prompt Determination of approximate 1 gpm leak.
Operability process and found to be acceptable for continued service.
TABLE 2 Abstract of Reoalrs/reolacement Activities Reauired for Continued Service Item Description Date Repair/Replacement Code Class Descriotion of Work Comoleted Plan Number Class 3 28-B CROM Cooling Coil Replaced entire cooling coil due to 4/11/23 120523599 through wall defect in tube.
Class 3 669 Pipe Chase Cooling Coil Replaced entire cooling coil due to 4/6/23 122132141 through wall defect in tube.
Replaced entire flex hose assembly Class 3 CCS Flex Hose due to leakage through the steel 4/10/23 123591197 braided oortion of the hose.
E-2 of 3
REPORTING REQUIRED BY 10 CFR 50.65a(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:
(1) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (it) An evaluation of each area, and the result of the evaluation; and (iit) A description of necessary corrective actions.
Portions of the SCV moisture barrier were found to have rejectable indications (lack of adhesion or damage), which can permit moisture to reach the inaccessible areas of the SCV. The areas of rejectable indications on the moisture barrier were excavated and these inaccessible areas of the SCV were evaluated for degradation in accordance with 10CFR50.55a(b)(2)(ix)(A)(2), using an exam method consistent with Category E-A, Item E1.11.
The conditions identified during the Unit 2 Cycle 25 refueling outage, on the SCV in an accessible area were determined to be acceptable per the sites Containment ISi procedure (0-PI-DXl-000-116.3) and do not affect the degradation assessment for inaccessible areas.
E-3 of 3