NRC-24-0048, Submittal of Inservice Inspection Summary Report
| ML24219A253 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/06/2024 |
| From: | Banker S DTE Electric Company |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC-24-0048 | |
| Download: ML24219A253 (1) | |
Text
USNRC NRC-24-0048 Page 2 cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III M. Wilson - Authorized Nuclear Inservice Inspector (ANII)
D. Stenrose - Chief Inspector Michigan Department of Licensing and Regulatory Affairs (LARA)
Bureau of Construction Codes and Fire Safety - Boiler Division
to NRC-24-0048 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Form OAR-1 Owners Activity Report
Report Number Plant Fermi 2 Nuclear Power Plant Form OAR-1 Owner's Activity Report RF-22 OAR-1 Fermi Nuclear Power Plant 6400 North Dixie Hwy, Newport, Ml 48166 Unit No.
2 Commercial SeNice Date 1_/2_3_/_19_8_8 ____ Refueling Outage No. ___
2_2 __ _
(if applicable)
Current Inspection lnteNal Current Inspection Period Edition and Addenda of Section XI applicable to the inspection plans Date and Revision of inspection plans ISi 4th lnteNal, IWE 3rd lnteNal (1st, 2nd, 3rd, 4th, other) 2nd (1st, 2nd, 3rd) 2013 Edition 2/28/2024, Revision 14 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Case used for inspection and evaluation:
N-532-5, N-613-2, N-716-1, N-845 (If 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 as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of RF-22 conform to the requirements of Section XI.
(Refueling Outage Number)
Signed Joshua A. Meisel/
Owners d} 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 One State St, Hartford, CT have inspected the items described in this Owner's ActivityReport, 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 loss of any kind arising from or connected with this inspection.
Mark D. Wilson/~~
...::)
0 9
Commissions _______
N_B_9_4_8_6_B_I_N_N_S_R __,_M_I_30_0_6_1_0 _____ _
Inspector's Signature National Board Number and Endorsement Date 07-z.3-20 23/ to NRC-24-0048 Page 1 of 3
RF22 Owners Activity Report Attachment Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description B-N-2, B13.40 Core Shroud ISI-NDE Evaluation 24-004 evaluated a relevant H3 weld indication and concluded it did not challenge structural integrity of the core shroud, even considering ten years of flaw growth at each end.
F-A, F1.20C High Pressure Coolant Injection Pipe Support (E41-3169-G13)
CR-2024-37682 evaluated out of tolerance spring settings and determined the as-found spring settings were acceptable.
F-A, F1.30R Emergency Equipment Service Water Pipe Support (P45-3353-G05)
TE-P45-24-017 evaluated a loose pipe clamp nut and determined the support was functional in the as-found condition. The nut was tightened and reinspected satisfactorily.
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
Division 2 Residual Heat Removal Heat Exchanger Repair of shell-to-partition plate fillet weld 4/11/2024 23-019 1
Reactor Recirculation B Discharge Line Pipe Support Replace missing nut on welded beam attachment bolt 4/23/2024 24-020 1
Reactor Pressure Vessel Head Vent (N7) Flange Bolts Replaced bolts due to damage during removal 9/2/2023 23-036 2
Division 2 Emergency Equipment Cooling Water Drywell Sump Heat Exchanger Return Check Valve Replaced bonnet to body studs and nuts due to corrosion 4/20/2024 24-013 2
Division 2 Emergency Equipment Cooling Water Supply Header Relief Valve Replaced flange bolting due to corrosion 4/20/2024 23-042 to NRC-24-0048 Page 2 of 3
Reporting Required by 10 CFR 50.55a(b)(2)(ix)(A)(2)
ASME Section XI, Subsection IWE Metal Containment Examinations 10 CFR 50.55a(b)(2)(ix)(A)(2) requires for each inaccessible area identified for evaluation, the licensee 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.
Portions of the drywell moisture barrier were found to have rejectable indications (lack of adhesion). In all areas tightly adhered seal remained below the areas of lack of adhesion. In addition, a complete removal of the moisture barrier was performed, and VT-1 examination of the drywell shell behind the moisture barrier was satisfactory. Therefore, the degraded moisture barrier does not indicate the presence of degradation of the inaccessible drywell shell below the concrete floor, and no evaluation is required.
The moisture barrier and coatings in the drywell dado region were completely replaced.
No other conditions were identified that could indicate the presence of degradation in inaccessible areas. to NRC-24-0048 Page 3 of 3