AEP-NRC-2025-39, Part 21 30-day Notification
| ML25239A088 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 08/27/2025 |
| From: | Dailey S Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| AEP-NRC-2025-39 | |
| Download: ML25239A088 (1) | |
Text
INDIANA MICHIGAN POW*R An MP Company BOUNDLESS ENERGr August27,2025 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Part 21 30-day Notification Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 indianamichiganpower.com AEP-NRC-2025-39 10 CFR 21.21(d)(3)(ii)
Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Units 1 and 2 is providing, as the enclosure to this letter, the required written notification of a defect of a basic component in accordance with 10 CFR 21.21 (d)(3)(ii). The enclosed notification pertains to a failed Thermal Overload within an Emergency Diesel Generator Voltage Regulator supplied by Paragon Energy Solutions, LLC.
There are no commitments included in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.
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Scott A. Dailey Site Vice President RAW/sjh
Enclosure:
Part 21 Notification of Paragon Energy Solutions Emergency Diesel Generator Voltage Regulator
U. S. Nuclear Regulatory Commission Page 2 c:
EGLE - RMD/RPS J. B. 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 AEP-NRC-2025-39
Enclosure to AEP-NRC-2025-39 Part 21 Notification of Paragon Energy Solutions Emergency Diesel Generator Voltage Regulator
- 1. Name and address of the individual or individuals informing the Commission.
Scott A. Dailey Site Vice President Cook Nuclear Plant Indiana Michigan Power Company 1 Cook Place Bridgman, MI 49106
- 2. Identification of the facility, the activity, or the basic component supplied for such a facility or such activity within the United States which fails to comply or contains a defect.
Cook Nuclear Plant Unit 1 Docket No. 50-315 License No. DPR-58 Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-7 4 Basic Component: Emergency Diesel Generator (EDG) Voltage Regulator (VR)
- 3. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
Paragon Energy Solutions, LLC 7 410 Pebble Drive Fort Worth, TX 76118 Tel: 817-284-0077
- 4. Nature of the defect or failure to comply and safety hazard which is created or could be created by such defect or failure to comply.
An Emergency Diesel Generator (EDG) Voltage Regulator (VR) was supplied containing two deficiencies associated with the Thermal Overload (TOL) that were determined to be Defects.
The subject Thermal Overload (TOL) is a sub-component of the EDG VR. The EDG VR is a basic component within the EDG system. The TOL serves to protect the rotating equipment field (the EDG exciter) from excessive heating due to prolonged over current conditions.
Should the TOL spuriously trip it will create a condition in which the EDG VR can no longer control the generator voltage, resulting in an inability of the EDG system to supply automatic onsite emergency AC power.
Deficiency 1: A heater dimensional tolerance deficiency was identified in that the heater coil is taller on the subject TOL such that it contacted the bimetallic strip when it was installed into the TOL. The heater contacting the bimetallic strip can exert a preload which lowers the activation threshold of the bimetallic strip resulting in spurious trips at a lower than intended operating current or when the device is subject to mechanical agitation. It can also result in localized overheating which could lead to uneven or excessive bending of the bimetal.
Deficiency 2: A braided control wire was confirmed to be incorrectly routed; it was found pinched between the phenolic boss of the cover and the pressure bar. This would restrict the movement of the pressure bar.
Enclosure to AEP-NRC-2025-39 Page2
- 5. The date on which the information of such defect or failure to comply was obtained.
The defect was identified on July 22, 2025.
- 6. In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.
The subject Thermal Overload was manufactured by General Electric (GE) and is a model CR124K028 with a K624A heater. The DC Cook station has 4 EDG VRs with this model of GE TOL:
Lot 1355235, SN NLl-3S7950GR751A1-1002 Lot 1310478, SN NLl-3S7950GR751A1-1005 Lot 1290298, SN NLl-3S7950GR751A1-1006 Lot 1310479, SN NLl-3S7950GR751A1-1001 Basic components supplied to other licensees is unknown to Cook Nuclear Plant. Contact the vendor for additional information.
- 7. The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
The TOL containing the identified deficiencies was immediately replaced.
The extent of condition review included performing X-ray examinations of other potentially impacted TOLs that were installed. This identified one additional TOL containing "deficiency 2" and was immediately removed from the plant upon discovery.
Cook Nuclear Plant is performing daily continuity checks on impacted TOLs. This action is intended to continue until the TOLs are replaced with new style TOLs.
Cook Nuclear Plant is planning for replacement of the TOLs for the impacted EDG VRs with new style TOLs and will be completed by October 31, 2026.
- 8. Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
None.
- 9. In the case of an early site permit, the entities to whom an early site permit was transferred.
Not Applicable.