AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report

Form OAR-1, Owner'S Activity Report

ML21230A306
Person / Time
Site:	Cook
Issue date:	08/12/2021
From:	Scarpello M American Electric Power Co, Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2021-44
Download: ML21230A306 (6)

Text

m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com .

August 12, 2021 AEP-NRC-2021-44 10 CFR 50.55a Docket No.: 50-316

. U. S; Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Form OAR-1, Owner's Activity Report Indiana Michigan Power Company the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 2, is providing as Enclosure 1 to this letter a copy of Form OAR-1, Owner's Activity Report, for lnservice Inspection activities performed at CNP Unit 2 through the completion of the Unit 2 Cycle 26 Refueling Outage.

• This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1." This code case is used as.an alternative to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000, as specified in Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 19, for the current inspection interval.

The Authorized Code Inspection Company is OneCIS Insurance Co., of Lynn, Massachusetts. The Authorized Nuclear lnservice Inspector is Howard M. Burkhart, Jr.

There are no new or revised commitments in this letter. Should you have any questions, please contact me, at (269) 466-2649.

~~fl Michael K. Scarpello Regulatory Affairs Director SJM/mll

U.S. Nuclear Regulatory Commission

• AEP-NRC-2021-44 Page 2

Enclosure:

1. Form OAR-1, Owner's Activity Report for Donald C. Cook Nuclear Plant Unit 2 Cycle 26 Refueling Outage c: R. J. Ancona - MPSC EGLE - RMD/RPS J. B. Giessner- NRC Region Ill NRC Resident Inspector R. M. Sistevaris -AEP Ft. Wayne J.E. Walcutt-AEP Ft. Wayne S. P. Wall - NRC, Washington D.C.

A. J. Williamson - AEP Ft. Wayne

Enclosure 1 to AEP-NRC-2021-44 Form OAR-1, Owner's Activity Report for Donald C. Cook Nuclear Plant Unit 2 Cycle 26 Refueling Outage

D. C. Cook Nuclear Unit 2 FORM OAR-1 OWNER'S ACTIVITY REPORT Rei:>ort Number 2-2021-5-1-01 Plant Donald C Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 Unit No. 2 Commercial service date 7/1/1978 Refueling outage no. U2C26 (if applicable)

Current inspection interval 5th for Components and Supports {C&S) and 3rd for Containment ISi (GISI) Program (1sL 2nd, 3rd, 4th, other)

. Cur~Elrit inSl)Elction period . 1st for C&S and 1st for GISI (1sL 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2013 Edition/No Addenda Date and revision of inspection plans 3/30/2021 Rev 2 for C&S, 3/1/2020 Revision Ofor GISI Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Edition and Addenda are the same as the Inspection Plans Code Cases used for inspection and evaluation: N-513-4, N-722-1 and N-729-6 for C&S (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 U2C26 conform to the requirements of Section XI. (refueling outage number)

Signed ~~~~~ , ISi Program Owner Date gl5L2.o2.,

Owners or Owne(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 OneCIS Insurance Co. of Lynn, MA 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 loss of any kind arising from or connected with this inspection.

19JJ'h\"'n ~t\~ h_ Commission 903~  ::c. ar :i;s Al~

lnspecto(s Sigl1ture National Board Number and Endorsement Date S A~ .!lo;ai.

Page 1 of3

D. C. Cook Nuclear Unit 2 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description Relevant conditions including discoloration and accumulated residues were identified at 15 penetrations of the Reactor Vessel Closure Head (RVCH) during Visual Examination (VE). After cleaning, no relevant conditions and no degradation of the RVCH was identified during the as-left VE. The relevant conditions were attributed to cleaning of previous spills from refueling operations and Nozzles and partial-penetration welds of PWSCC-materials deposited by the RVCH ventilation system and N-729-6 B4.40 resistant materials in head were not indicative of possible nozzle leakage. Relief was

[Reactor Vessel Upper Head]

granted from performing the supplemental UT and surface examinations required under ASME Code Case N-729-6 (ADAMS Accession Number ML21130A008). A subsequent VE will be performed in the next refueling outage per the Code Case.

A through wall leak was identified on a Class 3 Essential Service Water (ESW) pipe. The leak was evaluated as acceptable per ASME Code N-513-4. The augmented D-B D2.10 Pressure Retaining Components examinations were performed as required until the associated portion of the piping was down-graded to non-Code per the design change process.

Page 2 of 3

D. C. Cook Nuclear Unit 2 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 1/2 Valve 2-NRV-163 Replace bellows leak off pipe with plug 5/8/2020 55546796-22 1/2 Valve 2-NRV-164 Replace bellows leak off pipe with plug 5/7/2020 55546796-61 Page 3 of 3