IR 05000315/2025004
| ML26036A248 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/05/2026 |
| From: | Nestor Feliz-Adorno NRC/RGN-III/DORS/ERPB |
| To: | Ferneau K Indiana Michigan Power Co |
| References | |
| IR 2025004 | |
| Download: ML26036A248 (0) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2025004 AND 05000316/2025004
Dear Kelly Ferneau:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On January 22, 2026, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Néstor J. Féliz Adorno, Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2025004 and 05000316/2025004
Enterprise Identifier:
I-2025-004-0064
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
October 01, 2025, to December 31, 2025
Inspectors:
R. Cassara, Senior Resident Inspector
Z. Helgert, Resident Inspector
A. Hobbs, Reactor Inspector
J. Mancuso, Senior Resident Inspector
T. McGowan, Emergency Preparedness Inspector
A. Shaikh, Senior Reactor Inspector
Approved By:
Néstor J. Féliz Adorno, Chief
Engineering and Reactor Projects Branch
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Donald C. Cook Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000315/2025-002-00 LER 2025-002-00 for Donald C. Cook Nuclear Plant, Unit 1,
Supplemental Diesel Generators (DG) Unavailable Resulting in Emergency DGs Inoperable Greater Than Allowed by TS 71153 Closed
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection period.
Unit 2 began the inspection period shut down for a refueling outage. On October 24, 2025, the unit commenced start up and returned to rated thermal power on October 28, 2025.
The unit remained at or near rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated winter readiness for seasonal extreme cold weather conditions prior to the onset of seasonal cold temperatures for the following systems:
Supplemental diesel generators, Unit 2 N-train batteries, heat trace on multiple systems, main steam safety valves, and supplemental heating in multiple buildings during the week ending December 13, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 east motor driven auxiliary feedwater pump following a surveillance run during the week ending November 15, 2025
- (2) Unit 2 west residual heat removal (RHR) train following a surveillance run during the week ending November 22, 2025
- (3) Unit 2 north safety injection train prior to south safety injection surveillance run during the week ending December 13, 2025
- (4) Unit 1 east containment spray train prior to west train surveillance during the week ending December 20, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 essential service water (ESW) system during the week ending October 25, 2025.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zones 2/112/113/139: Units 1/2 sub-basement & ESW pipe tunnel during the week ending November 8, 2025
- (2) Fire Zone 58: Unit 2 containment during hot work during the week ending October 11, 2025
- (3) Fire Zone 54: Unit 2 control room during the week ending December 13, 2025
- (4) Fire Zones 29A/B/C/D/E/F/G: Units 1/2 ESW pump areas and basement motor control cabinet room during the week ending December 20, 2025
- (5) Fire Zones 1A/1B/44A/44B/61: Unit 1 auxiliary building east and west containment spray pumps, heat exchanger room, and spray additive tank room during the week ending December 20, 2025
- (6) Fire Zones 70/71/72/73: Units 1/2 control room HVAC equipment and computer rooms during the week ending December 27, 2025
- (7) Fire Zones 17C/D/E/F/G: Units 1/2 east motor driven auxiliary feed pump and turbine driven auxiliary feed pump rooms during the week ending December 27, 2025 71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor vessel upper head (RVUH) visual and volumetric examinations are examined for degradation and dispositioned in accordance with the applicable codes and standards for any fabrication, repair, and analysis, by reviewing the following activities in Unit 2 during refueling outage U2C29 from September 22 to December 8, 2025.
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02) (1 Partial)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
(Partial)
- RVUH Penetrations Bare Metal Visual Examination
- RVUH Penetrations Ultrasonic Examination
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Unit 2 control room during reactor startup and plant heat up after refueling outage U2C29 on October 24, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator licensed operator requalification training during the week ending December 6, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (5 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 2 turbine driven auxiliary feedwater pump maintenance during the U2C29 refueling outage
- (2) Offsite power and its 10 CFR 50.65 a(1) action plan (3)2AB Emergency Diesel Generator (EDG) thermal overload failure. This completes the partial sample from the 2nd quarter of 2025
- (4) Units 1 and 2 250-volt safety-related batteries. This completes the partial sample from the 4th quarter of 2024
- (5) Unit 2 component cooling water check valve gross leakage discovered while conducting a local leak rate test during the U2C29 refueling outage
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Unit 2 reactor coolant pump 2 during seal package replacement during the week ending November 22, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Risk management during geomagnetic disturbance monitoring over 3-day period during the week ending November 8, 2025.
- (2) Risk management during Unit 1 east component cooling water train outage, and supplemental diesel generators unavailable during the week ending December 6, 2025.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability determination for Unit 1 ESW after Unit 2 west ESW taken into pull to lock without notifying Unit 1, as documented in Action Request (AR) 2025-7903
- (2) Operability determination following control room indication (CRID) 3 elevated voltage, as documented in AR 2025-8022
- (3) Unanticipated Loss of Power to Unit 2 critical control room power (CCRP) during loss of offsite power/loss of coolant accident (LOP/LOCA) testing, as documented in AR 2025-7351
- (4) Operability determination following reactor coolant pump back and side seismic restraint bumper shims out of tolerance during plant heat up from refuel outage, as documented in AR 2025-8688
- (5) Operability determination following void found in Unit 1 east RHR piping above acceptance criteria, as documented in AR 2025-6836
- (6) Operability determination following bearing issue found in Unit 2 south control room ventilation, as documented in AR 2025-9195
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Removal of hydrogen recombiners in Unit 2 containment during the week ending December 20, 2025.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage U2C29 activities from October 1 to October 24, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
- (1) Unit 2 CD EDG following voltage regulator replacement during the week ending October 4, 2025
- (2) Unit 2 distributed ignition system PMT following ignitor replacements during the week ending November 22, 2025
- (3) Unit 2 turbine driven auxiliary feedwater pump PMT run following maintenance during the week ending November 22, 2025
- (4) Unit 1 north safety injection pump following maintenance during the week ending November 29, 2025
- (5) Unit 1 reactor vessel level indication system PMT after card replacement during the week ending December 6, 2025
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) Unit 2 control rod drop time testing during the week ending November 22, 2025
- (2) Unit 2 Train A containment recirculation fan timing surveillance during the week ending November 29, 2025
- (3) Unit 1 delta temperature, average temperature set 1 calibration during the week ending December 13, 2025 (4)2AB EDG fast speed start operability run after thermal overload issues, during the week ending December 20, 2025
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) Unit 2 east component cooling water pre-service Test on the week ending October 11, 2025
- (2) Emergency core cooling system valve operability test - Train A & B during the week ending October 18, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2 containment airlock isolation valves leak rate tests during the week ending November 1, 2025
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- No changes were made during this inspection period.
This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
- (1) The inspectors evaluated: licensed operator requalification drill and exercise performance (DEP) simulator evaluation during the week ending November 22, 2025.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (October 2024, through September 2025)
- (2) Unit 2 (October 2024, through September 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 2024, through September 2025)
- (2) Unit 2 (October 2024, through September 2025) 71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Unit 1 fuel assembly BH24 identified as leaking during cycle 32.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in fire barrier deficiencies that might be indicative of a more significant safety issue.
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000315/2025-002-00, Supplemental Diesel Generators (DG) Unavailable Resulting in Emergency DGs Inoperable Greater Than Allowed by TS (ADAMS Accession No. ML25302A454). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153.
This LER is closed.
INSPECTION RESULTS
Observation: Fire Protection Trend Review 71152S The licensee missed opportunities to identify problems, as evidenced by the following examples identified by NRC inspectors during a review of fire protection issues entered into the corrective action program for the period of January 1, 2025, through October 31, 2025:
- When following up on fire watch gaps documented by the licensee in the corrective action program as Action Request (AR) 2025-8364, 2025-1016, 2025-2016, 2025-2763, 2025-2687, and 2025-8159, which involved missed tours, log-keeping issues, and reflash watch deficiencies, the inspectors observed fire watches in the plant and interviewed fire watch personnel. During these interviews, the inspectors identified a fire watch who demonstrated a lack of knowledge of required fire watch duties. AR 2025-8166 was written to address the issues observed by the inspectors.
Corrective actions included training.
- When following up on a fire protection issue documented by the licensee in the corrective action program, the inspectors reviewed AR 2025-6827, which addressed a degraded fire seal and referenced several related ARs generated as part of an investigation into similar degradation across the site. During this follow-up, the inspectors identified a gap in a fire seal, which prompted further investigation by fire protection personnel. As a result, several fire seals were found to be degraded due to age-related shrinkage, previous conduit installations without adequate repair, and original pour issues. Some seals connected common fire areas to redundant trains of safety-related equipment, including auxiliary feedwater and emergency power buses.
As corrective action for the seal issues identified because of the inspectors, the licensee enhanced inspection procedures to better identify age-related shrinkage.
Specifically, the licensee revised inspection criteria to proactively identify shrinkage that could reasonably be expected to exceed acceptance criteria before the next 10-year inspection interval. In addition, the licensee determined that the affected seals remained functional and that the rate of shrinkage would support functionality until the next 10-year inspection interval.
The inspectors did not identify any findings or violations.
Minor Violation 71153 Minor
Violation:
On September 3, 2025, the licensee identified that Supplemental Diesel Generator (SDG) fuel oil usage calculations did not incorporate vortexing phenomena within the fuel oil storage tank. When revised to include vortexing, the licensee determined the procedurally allowed minimum fuel oil inventory did not ensure the SDGs would meet their 24-hour mission time, with a shortfall of approximately 32 minutes. Technical Specification (TS) 3.8.1, AC Sources - Operating, requires two diesel generators capable of supplying the onsite Class 1E power distribution subsystems to be OPERABLE in Modes 1, 2, 3, and 4.
When one Emergency Diesel Generator (EDG) is inoperable, TS 3.8.1 Condition B requires verification that both SDGs are available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
If this verification is not met, TS 3.8.1 Condition C requires restoration of both SDGs to available status or restoration of the required EDG to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the Required Action and associated Completion Time of Condition C are not met, TS 3.8.1 Condition G requires the unit to be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Contrary to this, during the periods from March 1, 2023, at 07:00 to March 2, 2023, at 20:18, and from June 11, 2025, at 06:01 to June 12, 2025, at 23:57, Unit 1 EDGs at Donald C. Cook Nuclear Plant, Unit 1 were in maintenance outages and declared inoperable while the SDGs were unavailable to support the required mission time, and the unit did not complete required actions and exceeded the associated completion times required by TS 3.8.1 Condition G.
Screening:
The inspectors determined the performance deficiency was minor. The inspectors screened this per IMC 0612, Appendix B, Issue Screening Directions, dated May 28, 2025, and determined it could not be seen as a precursor to a significant event, did not have the potential to lead to a more significant safety concern, and did not adversely impact the mitigating systems cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). Specifically, the SDGs remained capable of performing their credited mitigating function for about 98 percent of the 24-hour mission time. The SDG mission time is intended to provide margin to restore power or obtain additional resources, such as supplemental fuel, and the limited reduction in margin did not meaningfully degrade the ability of the onsite AC power system to perform its safety function.
Enforcement:
At the conclusion of the periods described above, the licensee returned the Unit 1 EDGs to operable status. The licensee also revised SDG fuel oil usage calculations to incorporate vortexing and updated procedures to address standby fuel requirements as well as online refueling of the SDGs. This failure to comply with TS 3.8.1 Condition G constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 22, 2026, the inspectors presented the integrated inspection results to K. Ferneau, Executive VP and Chief Nuclear Officer, and other members of the licensee staff.
- On December 11, 2025, the inspectors presented the emergency preparedness inspection results to D. Burgoyne, Emergency Preparedness Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
PMP-5055-001-
001
Winterization/Summerization
Work Orders
C10079601
Perform Plant Winterization
09/17/2025
25-10093
NRC Identified Housekeeping Issue
2/16/2025
25-9358
NRC Questioned Unit 2 RHR Instrument Valve Position
11/14/2025
25-9359
Trash in the Unit 2 West RHR Heat Exchanger room
11/14/2025
Corrective Action
Documents
Resulting from
Inspection
25-9968
2-IMO-362 MOV Seeping Oil Leak
2/10/2025
1-OHP-4021-009-
001
Placing the Containment Spray System in Standby Readiness
2-OHP-4021-019-
001
Operation of the Essential Service Water System
2-OHP-4021-008-
2
Placing Emergency Core Cooling System in Standby
Readiness
2-OHP-4021-056-
001
Filling And Venting Auxiliary Feedwater System
2-OHP-4030-219-
2E
Unit 2 East ESW Header Flow Path Verification
Procedures
2-OHP-4030-256-
017E
East Motor Driven Auxiliary Feedwater System Test
25-8166
Firewatch Did Not Understand Roles and Responsibilities
10/08/2025
25-8905
Fire Seal W7177 Gap
10/28/2025
25-8915
Unit 1 569' Turbine Wall Penetration Seal Gap Not Sealed
10/29/2025
Corrective Action
Documents
Resulting from
Inspection
25-8919
inch by 4 " Gap in Wall Plate Unit 2 ESW Pipe Tunnel
10/29/2025
Fire Plans
Fire pre-plans
volume 1
Fire pre-plans volume 1
25-7601
RVCH - Relevant Indication Identified on Penetration #76
09/26/2025
Corrective Action
Documents
25-7648
RVCH - Relevant Indication Identified on Penetration #77
09/26/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
25-7649
RVCH - Relevant Indication Identified on Penetration #60
09/26/2025
25-7681
RVCH - Relevant Indication Identified on Penetration #67
09/28/2025
25-7682
RVCH - Relevant Indication Identified on Penetration #55
09/28/2025
Engineering
Evaluations
IR-2025-0865
EPRI Independent Review of Ultrasonic Examination Data
from Pre-Service and First In-Service Inspections of the
D.C. Cook Unit 2 Alloy 690 Replacement Reactor Vessel
Head
10/01/2025
U2-VE-25-005
As Found BMV - RVCH
10/13/2025
NDE Reports
U2-VE-25-006
As Left BMV - RVCH
10/14/2025
2-QHP-5050-
NDE-027
Visual Examination for Boric Acid and Condition of
Component Surface
WDI-STD-1005
Manuel or Multi-channel Automated Ultrasonic Instrument
Linearity Procedure
WDI-STD-1040
RVCH - Ultrasonic Examination Acquisition Procedure
Procedures
WDI-STD-1041
RVCH - Ultrasonic Examination Analysis Procedure
C10072280002
Perform as Found Bare Metal Visual Exam - RVCH
09/30/2025
Work Orders
C10072280019
Perform as Left Bare Metal Visual Exam - RVCH
10/03/2025
71111.11Q Miscellaneous
RQ-E-5006-U2-A
Period 5006 As Found Simulator Evaluation Unit 2 Primary
11/03/2025
21-8026
Station Lost Train B Reserve Feed for Both Units
09/24/2021
23-9354
Cracks On Walls of Battery 1-BATT-AB Cells 55 And 113
2/13/2023
24-5485
Battery Acid Cleaner for Station Batteries
07/09/2024
25-3437
2AB Diesel Trip After Failed Voltage Indication
04/22/2025
25-5378
DG1CD Failed Its Scheduled Surveillance
07/02/2025
25-7497
Suspect 2-CCW-243-25 Gross Leakage
09/24/2025
Corrective Action
Documents
25-7503
Suspect 2-CCW-244-25 Gross Leakage
09/24/2025
Unit 1 & 2 Offsite Power to 4KV source breakers - (a)(1)
Action Plan
03/29/2022
Engineering
Evaluations
CMP-CCW-03
CCW to Containment Penetrations Inner Cooling Coils
01/16/2015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNTMT Iso Check Valve CMP Plan
Performance Monitoring Plan: Suspended Solids
Concentration in CCW System
03/18/2024
Miscellaneous
Preventative
Maintenance
2850074
2AB & 12CD, Vendor Partial Discharge Monitoring
04/18/2022
Procedures
2-OHP-4030-256-
017T
Turbine Driven Auxiliary Feedwater System Test
C10003943
2-12AB-BUS-DUCT Install Heaters/PD monitors
11/22/2021
C10047219
2-12CD-BUS-DUCT INSPECT LOOP FEED ENCLOSURE
10/04/2025
C10070188006
Inspect/Replace Seal Package
10/15/2025
C10095412015
2-QT-506, Inspect/Adjust Balance Chamber Pressure
10/22/2025
Work Orders
C10095412020
2-QT-506, Replace Bonnet
10/22/2025
Plan of the Day Meeting - Guarded Equipment
11/07/2025
Miscellaneous
Plan of the Day Meeting - Guarded Equipment
2/01/2025
2016-1902
Bad Fan Shaft Found on 2-HV-ACRA-2
2/17/2016
25-6836
Void at 1-SI-287
09/03/2025
25-7903
Ineffective Notification to U1 Of U2 ESW Pump Removal
10/02/2025
25-8022
CRID 3 Elevated Voltage Upon Inverter Energization
10/05/2025
25-8688
U2 RCP 1-4 Seismic Restraint Bumper Gaps Out of Tolerance 10/20/2025
Corrective Action
Documents
25-9195
Pillow Block Bearing Shuttling On 2-HV-ACR-2
11/10/2025
Procedures
2-THP-6020-
CHM-322
Vent Stack Gaseous Sampling
C10071284009
(MM) MTH: 2-HV-ACRA-2; Investigate/Repair Bearings
(2025-9195)
11/18/2025
Work Orders
C10088979001
U1 Train A Evaluate Gas Voids Per 1-EHP-4030-108-001A
09/03/2025
Engineering
Changes
Unit 2 Hydrogen Recombiner Removal and Storage Rack
Installation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
25-8576
Loop Cold Leg Drain Spring Can
10/18/2025
25-8579
Missing Nut on U-bolt Support for Conduit in U2 Containment
10/18/2025
25-8583
U2 Containment Conduit Cord and Boot Separated
10/18/2025
Corrective Action
Documents
Resulting from
Inspection
25-8584
U2 Light Shade Is Loose
10/18/2025
U2C29 Refueling Outage Shutdown Safety Plan Report
08/16/2025
Miscellaneous
Clearance: Administrative Control of PW Dilution Sources
10/03/2025
25-10095
2-OME-150-AB Tripped Due To No Voltage or Frequency Ind
2/16/2025
25-8256
Failed DIS Igniter
10/10/2025
25-8718
Higher 2-QT-506 Balance Chamber Pressure than Procedure
10/21/2025
Corrective Action
Documents
25-9616
WOT, RVLIS New Card 4NCT8, Add A Jumper And Replace
1-TS-413
11/26/2025
25-10142
2AB EDG Test Wiring Configuration Not Preserved During FIP 12/18/2025
Corrective Action
Documents
Resulting from
Inspection
25-8972
Potential Enhancements To 2-IHP-4030-234-001
10/30/2025
Engineering
Evaluations
DCC2509R0
AMS Onsite Final Report: Measurement of Drop Times of
Control and Shutdown Rods at D.C. Cook Unit 2
10/22/2025
1-OHP-4030-108-
051N
North Safety Injection Pump System Test
2-OHP-4030-232-
27AB
AB Diesel Generator Operability Test (Train B)
Procedures
2-OHP-4030-232-
27CD
CD Diesel Generator Operability Test (Train A)
C10008503015
OPS, 2-PP-10E, Place In-Service, Operational Check/PMT
10/02/2025
C10042671007
MTI, 2 DGCD VRCKT, tune and PMT Voltage Regulator
10/01/2025
C10050626007
MTE: 2-UDISA; PMT TRAIN A IGNITERS
10/21/2025
C10050626011
MTE: 2-UDISB; PMT TRAIN B IGNITERS
10/20/2025
C10050923004
2-LDISA: PMT TRAIN A IGNITERS
10/14/2025
Work Orders
C10050923005
2-LDISB: PMT TRAIN B IGNITERS
10/14/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C10066464001
MTI 1-IHP-4030-102-003B Train B RVLIS Calibrations
2/02/2025
C10069215001
OPS: 2-OHP-4030-208-053A ECCS Valve Operability
Test/Defueled
10/08/2025
C10069216001
OPS: 2-OHP-4030-208-053B ECCS Valve Test-Defueled
10/08/2025
C10070071003
MTP, 2-AIRLOCK-C612, 4030-046-001 (AL)Leak Rate,
Egress Block
10/18/2025
C10070071004
MTP, 2-AIRLOCK-C650, 4030-046-001 (AL)Leak Rate,
Egress Block
10/18/2025
C10070437
Multiple Rod Drop Measurements
10/23/2025
c10072432001
MTI, 1-IHP-430-102-025, delta T/Tavg Set 1 Calibration
2/11/2025
C10091166
TDAFP Group B Pump Test
10/28/2025
C10091661001
MTI: 2-IHP-4030-228-005A; 2-HV-CEQ-2 Train A Quarterly
Test
11/10/2025
C10098491
AR 2025-10098, 2-OME-150-AB Capital Tasks for Repairs
2/22/2025
Miscellaneous
N/A
Letter Titled Changes to the ECP or EAL
11/24/2025
CEP
Donald C. Cook Emergency Plan
Procedures
PMP-2080-EPP-
101
Donald C. Cook Emergency Classification
Miscellaneous
RQ-E-5006-U2-A
Period 5006 As Found Simulator Evaluation Unit 2
11/03/2025
Miscellaneous
Operations Narrative Logs
10/01/2024 -
09/30/2025
71151
Procedures
PMP-7110-PIP-
001
Reactor Oversight Program Performance Indicator and
Monthly Operating Report Datasheets (October 2024 Through
September 2025)
Corrective Action
Documents
25-2625
Fuel Assy BH24 Identified As Leaking Via In-Mast Sipping
03/31/2025
Miscellaneous
PE-PPE-25-002
Post Irradiation Examination (PIE) report D.C. Cook Unit 1
EOC-32 leaking fuel inspections
Corrective Action
2018-1208
Control Room Fire Penetration Seals
2/06/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
25-6827
Degraded Fire Seal W9214
09/03/2025
Documents
25-8166
Firewatch Did Not Understand Roles And Responsibilities
10/08/2025
Procedures
2-FPP-4030-066-
017
Inspection of Fire Barrier Penetration Seals
55406247
Inspection of Fire Barrier Penetrations
01/20/2014
Work Orders
55498904
OPFP, U-1 & 1-2 Inspect TRM Fire Seals
03/24/2018
Calculations
MD-12-DG-010-S
Determination of Minimum Fuel Oil Level to Allow for 24 Hours
of SDG Operation at 55% Load and Maximum Run Time of
SDG Operation at 100% Load
Corrective Action
Documents
AR 2025-6830
MD-12-DG-010-S Rev Impacts Previous Operations Impact &
09/03/2025