AEP-NRC-2024-47, Form OAR-1, Owners Activity Report

Form OAR-1, Owners Activity Report

ML24212A071
Person / Time
Site:	Cook
Issue date:	07/30/2024
From:	Scarpello M Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
AEP-NRC-2024-47
Download: ML24212A071 (1)

Text

s INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant One Cook Place POWIR Bridgman, Ml 49106 A unit of American Electric Power lndianaMichiganPower.com

July 30, 2024 AEP-NRC-2024-4 7 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, Form OAR-1, Owner's Activity Report, for lnservice Inspection activities performed at CNP Unit 2 through the completion of the Unit 2 Cycle 28 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 20, for the current inspection interval.

The Authorized Code Inspection Company is Bureau Veritas Inspection and Insurance Company, 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.

di~~,!! ~ m;ohul ~ta-rpdlo 1

<./ ~~:a~I K. Scarpello / f Jil Director of Regulatory Affairs

KMH/sjh

Enclosures:

1. Form OAR-1, Owner's Activity Report for Donald C. Cook Nuclear Plant Unit 2 > Cycle 28 Refueling Outage 1 U.S. Nuclear Regulatory Commission AEP-NRC-2024-47 Page 2

c: EGLE - RMD/RPS J. 8. Giessner - NRC Region Ill NRC Resident Inspector N. Quilico - MPSC R. M. Sistevaris-AEP Ft. Wayne S. P. Wall - NRC Washington D.C.

A. J. Williamson - AEP Ft. Wayne Enclosure 1 to AEP-NRC-2024-47

Form OAR-1, Owner's Activity Report for Donald C. Cook Nuclear Plant Unit 2 Cycle 28 Refueling Outage D. C. Cook Nuclear Unit 2 FORM OAR-1 OWNER'S ACTIVITY REPORT

Report Nlffllber 2-2024-5-2-01

Plant Donald C Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106

Unit No. 2 Commercial service date 7/1/1978 Refueling outage no U2C28 (I applicable)

Ci.man! inspedion interval 5th f0t Components and Supports (C&S) and 3rd for Containment ISi (CISt) Progtam (Isl 2nd 3nl. 4th. other)

Current inspection period 2nd for C&S and 2nd for CISI (1st. 2nd. 3nlJ

Edition and Addenda of Section XI applicable to the inspection plans 2013 Edillon/No Addenda

Date and revision of inspection plans 5110/2023 Revision 6 lor C&S, 3/10/2022 Revision 1 for CISI

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-722-1, N-729-6 and N-770-5 for C&S (If lll'l)licable, including cases mod.., by Case N-532 111d 1a1or...-,isio,ls)

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 requlred by the ASME Code,Section XI ; and (c) the repair/replacement activities and evaluations aupPOfling the e0tnpletion of U2C28 conform to the requirements of Section XI. (reluelng oo iaoe nutnber)

Signed...;;.l,.J__...;;~=;;;.._.;=-ll~--ci\\. __ ~ _ __...;;;;..;::;a,--...:..*=ISI __ PrOQt__.._a=m;....;;Owne='-r _ Cate _7...... l.... -i.:_~..... (..... -i._o_l!::'f__, ______ _

OMMn o, Ownln Desq,ee, TIiie

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 Bureau Verilas Inspection and Insurance C0tnpany 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 an activities represented by this report in accordance with the requirements of SecUon XI.

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

Commission 90a&3 A;I~ ~,J I NaW do;; Number and~

Page1 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 boric acid deposits, discoloration and entrained residues were identified at one penetration of the Reactor Vessel Closure Head (RVCH) during Visual Examination (VE). After cleaning, no releyant conditions and no degradation of the RVCH were identified during the as-left VE. The relevant Nozzles and partial-penetration welds of conditions were attributed to leakage from in-core N-729-6 B4.40 Primary Water Stress Corrosion Cracking (TECSA) and were not indicative instrumentation (IC!) thermocouple sealing assembly (PWSCC)- resistant materials in head leakage. Relief of possible nozzle was granted from performing the supplemental Ultrasonic Testing and surface examinations required under ASME Code Case N-729-6 (ADAMS Accession Number Ml241078120). A subsequent VE will be performed in the next refueling outage per the Code case.

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D. C. Cook Nuclear Unit 2 I T Table 2 I !

Abstract of Repair/Replacement Activities Required for Continued Service I I

Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 2-GRH-V819 (RESIDUAL HEAT I I I

REMOVAL SYSTEM '

2 ISOMETRIC DRAWING 2-RH-Replace Damaged Support Items, Action Request (AR) 2019-1349 1/12/2023 WO-C10010107003 26 3 INCH VARIABLE RATE SPRING TYPE PIPE SUPPORT) 2-RH-133 (RESIDUAL HEAT, I 1 REMOVAL TO REACTOR Replace Studs and Nuts not Meeting Acceptance Standards, 4/19/2024 WO-C10049494001 ' I COOLANT LOOP #2 COLD AR 2024-2892 l LEG CHECK VALVE)

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