IR 05000315/2024002
| ML24206A041 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/24/2024 |
| From: | Nestor Feliz-Adorno NRC/RGN-III/DORS/ERPB |
| To: | Lies Q Indiana Michigan Power Co |
| References | |
| IR 2024002 | |
| Download: ML24206A041 (1) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2024002 AND 05000316/2024002
Dear Q. Shane Lies:
On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On July 18, 2024, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Donald C. Cook Nuclear Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Donald C. Cook Nuclear Plant.July 24, 2024 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: DPR-58 and DPR-74
Report Numbers: 05000315/2024002 and 05000316/2024002
Enterprise Identifier: I-2024-002-0057
Licensee: Indiana Michigan Power Company
Facility: Donald C. Cook Nuclear Plant
Location: Bridgman, MI
Inspection Dates: March 24, 2024 to June 30, 2024
Inspectors: N. Audia, Reactor Inspector J. Cassidy, Senior Health Physicist T. Hooker, Health Physicist E. Kokkinis, Project Engineer E. Magnuson, Reactor Inspector J. Mancuso, Senior Resident Inspector E. Sanchez Santiago, Senior Project Engineer P. Smagacz, Resident Inspector J. Winslow, Senior Project Engineer P. Zurawski, Branch Chief
Approved By: Néstor J. Féliz Adorno, Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety
Enclosure
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
Control and Use of Respiratory Protection Devices Procedure Noncompliance Cornerstone Significance Cross-Cutting Report Aspect Section Occupational Green [H.4] - 71124.03 Radiation Safety NCV 05000315,05000316/2024002-01 Teamwork Open/Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703 (c)(4)(vii) when the licensee failed to comply with their procedure for control and use of respiratory protection devices.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On June 5, 2024, Unit 1 reduced power to 50 percent of rated thermal power for Main Feed Pump Condenser Cleaning. The unit returned to full rated thermal power on June 9 and remained at or near full rated thermal power for the inspection period.
Unit 2 began the inspection period in a planned refueling outage. The unit was returned to service on May 3, 2024, and reached full rated thermal power on May 7. On May 14, 2024, Unit 2 was reduced to approximately 20 percent of rated thermal power to address a steam leak, however, oscillations of water level in the steam generators ultimately lead operators to manually take the unit off-line again. The unit returned to full rated thermal power on May 18 following repair of the steam leak. On June 27, 2024, Unit 2 began a controlled reduction of power to take the unit off-line to address a reactor coolant system leak in excess of the 10 gallons per minute allowed by technical specifications. Unit 2 remained shut down 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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending hot weather on June 17, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) 2W Charging following planned surveillance on June 12, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Dog House, upper containment on April 23, 2024
- (3) Fire Zone 40A: 4kV CD Switchgear Room, Unit 1, elevation 609'-0" on June 12, 2024
- (4) Fire Zone 15: 1 CD Diesel Generator Room, Unit 1, elevation 587'-0" on June 28, 2024
===71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities during Unit 2 refueling outage U2C28.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- Steam Generator #24 Tubesheet to Head Weld, Cat. B-B/B2.40
Dye Penetrant Examination
- RCP #22, Welded Support Lug #1, Cat. B-K/B10.30
Visual Examination
- Bare Metal Visual (BMV) of 58 Bottom Mounted Instrumentation Penetrations, Cat. N-722/B15.80
- BMV of 58 Bottom Mounted Instrumentation DM Welds, Cat. N-722/B15.100
- VT-1 of 2-RH-133 Closure Studs, Nuts, and Washers, Cat. B-G-2/B7.70
- VT-1 of 2-RH-133 Valve Body Internal Surfaces, Cat. B-M-2/B12.50
Welding Activities
- Weld Repair/Replacement of SI Check Valve 2-SI-161-L4 Work Order (WO) C10006111001
- Weld Repair/Replacement of SI Check Valve 2-SI-152N and Installation of High Point Vent Valve WO C10004063003
- Installation of High Point Vent Valve 2-SI-109 WO 55488557-01 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- BMV Examination of Reactor Vessel Upper Head Surface and Penetrations
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
- AR 2022-7595, Possible Boric Acid on Cooling Coils for 4 CLVs
- AR 2022-8016, 2-NMO-151 Inactive Packing Leak
- AR 2023-4580, Leak Found on 2-QC-107S
PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
- Eddy Current Testing (ECT) of all operational steam generator (SG) tubes for Unit 2 SG 21, 22, 23, and 24
- Secondary side visual examinations for Unit 2 SG 21, 22, 23, and 24
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 start up from Refueling Outage U2C28 on May 2, 2024.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 sync to grid from Refueling Outage U2C28 on May 3, 2024.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Unit 2 Dual Essential Service Water Outage on April 1, 2024
- (2) Emergent work to repair U2 Fuel Transfer Canal on April 17, 2024
- (3) Risk Management during Train B Reserve Feed work on May 14, 2024
- (4) Risk management during 1-BATT-AB replacement work on May 21, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 2024-3442, Fuel Assembly Unable to be Grappled Due to Rod Cluster Control Assembly (RCCA) Interference on April 18, 2024
- (2) AR 2024-3694, 4160V Run Bus Comp Measures and Meter Replacements on April 25, 2024
- (3) Public Address System speakers not working on April 25, 2024
- (4) Unit 2 Main Feedwater System on May 14, 2024
- (5) Void in Residual Heat Removal on May 20, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (3 Samples)
- (1) The inspectors evaluated refueling outage U2C28 activities from March 23 through May 5, 2024.
- (2) The inspectors evaluated forced outage activities to address a steam leak from May 14 to May 17, 2024.
- (3) The inspectors evaluated forced outage activities to address a reactor coolant system (RCS) unidentified leak rate in excess of 10 gallons per minute from June 27, 2024, through the end of the inspection period.
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) 2AB Emergency Diesel Generator PMT following emergent work on April 8, 2024
- (2) 2-IMO-128 PMT following planned work on April 15, 2024
- (3) 2E Component Cooling Water PMT following planned work on April 16, 2023
- (4) 1-BATT-AB Cell 55 replacement on May 21, 2024
- (5) 1-BATT-AB Cell 113 replacement on May 23, 2024
Surveillance Testing (IP Section 03.01) (1 Sample)
- (1) Emergency Core Cooling System valve operability test on April 16, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2 EDG Load Sequencing testing on March 23, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) 2-CCR-460 and 2-CCR-462 Local Leak Rate Testing on April 10, 2024
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) Ice Basket Weighing on June 24, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) Emergency Response Organization Training Drill on June 25,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) licensee surveys and decontamination of equipment leaving the Unit 2 lower containment step-off pad
- (2) workers exiting the radiologically controlled area during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Steam generator 2/3 diaphragm swap
- (2) Radiography of welds
- (3) 2-SI-161-L4 valve replacement High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 1 RC/Seal Water Filters Gate 1-GT-AUX1024
- (2) Unit 2 Steam Generator Hot and Cold Leg External Diaphragms
- (3) Unit 2 Reactor Pit
- (4) Unit 2 Reactor Coolant Drain Tank Back Door
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Temporary Ventilation Unit 702 used for 2-SV-51
- (2) Temporary Ventilation Unit 507 used for 2-SI-161-L4
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Shipment Preparation (IP Section 03.04)
- (1) The inspectors observed the preparation of radioactive shipment DCC24-030 of Dry Active Waste on April 10,
INSPECTION RESULTS
Control and Use of Respiratory Protection Devices Procedure Noncompliance Cornerstone Significance Cross-Cutting Report Aspect Section Occupational Green [H.4] - 71124.03 Radiation Safety NCV 05000315,05000316/2024002-01 Teamwork Open/Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 20.1703 (c)(4)(vii) when the licensee failed to comply with their procedure for control and use of respiratory protection devices.
Description:
The licensee was performing Unit 2 steam generator work as part of the refueling outage activities. A total effective dose equivalent (TEDE) evaluation was performed for Unit 2 steam generator platform work activities. This TEDE evaluation required the use of powered air purifying respirators (PAPRs) for platform work while the steam generators were open.
The licensees respiratory protection program is implemented through their fire protection department. The radiation protection department assists in the program's implementation.
The licensee controls the use of respiratory protection devices through procedure PMP-2281-RES-001 to ensure compliance with Title 10 CFR 20.1703 (c)(4)(vii) which requires licensees to implement and maintain procedures regarding their respiratory protection program. There are multiple steps in this procedure ensuring that the users of the respiratory equipment are qualified to wear and use the respiratory equipment. Of note are the following steps: Step 3.3.4 "departmental supervisors are responsible for ensuring personnel requiring respiratory protection are qualified to wear the specific respiratory protection devices. "Step 3.8.1 "all respirator qualifications shall be verified through the use of the plant qualification matrix (PQM), prior to issuing any respiratory device." Step 3.10.1 "personnel who issue respiratory equipment shall ensure the worker is qualified to wear the type of respiratory equipment requested via the PQM" and "document the issuance on Data Sheet 1, Respiratory Device Form, Data Base, or equivalent" (data sheet).
On April 9, 2024, and April 10, 2024, the inspectors observed the radiation protection department covering the Unit 2 steam generator platform work activities. Per the TEDE evaluation, PAPRs were issued to workers. The inspectors observed various, non-standardized methods of ensuring the workers were qualified such as workers giving verbal confirmation or nods to a supervisor that they had already verified their respirator qualifications. These observations did not align with PMP-2281-RES-001 step 3.10.1.
Specifically, the qualifications for the person requesting respiratory equipment was not verified via the PQM by the personnel who issued the respiratory equipment (the radiation protection technician that removed the respirator from the locked cabinet and gave it to the user).
Following these observations, the inspectors requested the data sheet to verify the qualifications for personnel that had previously been issued respiratory protection devices while performing Unit 2 steam generator platform work. The provided data sheet did not document the issuance of the PAPRs. Consequently, the inspectors could not use the data sheet to verify that the workers who were issued the PAPRs were qualified to use the PAPRs.
Additionally, this did not align with PMP-2281-RES-001 step 3.10.1. Specifically, the issuance of respiratory equipment was not documented on the data sheet.
Due to these failures, the licensee could not demonstrate that respiratory equipment was controlled to ensure respiratory equipment was only issued to qualified personnel. This means the individual had been medically certified capable of wearing the device without causing personal injury, were trained on how to wear the device properly to reduce the intake of radioactive materials, and in some cases, were fit tested to ensure the respiratory device fit the user to ensure the protection factors authorized by the NRC are appropriate.
Corrective Actions: The licensee evaluated this finding, and they entered the issue into their corrective action program. Their actions clarified the expectation for ensuring qualifications was for the radiation protection department to call the fire protection department to verify the qualifications before respiratory equipment was issued to workers. The licensee's procedure PMP-2281-RES-001 was revised and implemented by the exit meeting. The revision added a column in the data sheet to document the medical and respirator qualification verification via the PQM. Additionally, the radiation protection department had already submitted a request for training to be qualified to issue respiratory equipment independent of the fire protection department.
Corrective Action References: AR 2024-3173
Performance Assessment:
Performance Deficiency: The licensee failed to comply with their procedure for control and use of respiratory protection devices. This was reasonably within the licensees ability to foresee and correct and failing to comply with the procedure could have been prevented.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Without documenting who was issued respiratory equipment, it is possible that workers could be issued respiratory equipment who were not qualified to use the respiratory equipment, therefore leading to a more significant safety concern.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix C, Occupational Radiation Safety SDP. The inspectors determined the significance was very low safety significance (Green) because the finding was not associated with ALARA Planning or Work Controls, was not an over-exposure, was not a substantial potential for an over-exposure, and the ability to assess dose was not compromised.
Cross-Cutting Aspect: H.4 - Teamwork: Individuals and work groups communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained. The licensee held differing expectations between the fire protection and radiation protection departments. These expectations turned into misunderstandings and ultimately resulted in the failure to comply with their procedure.
Enforcement:
Violation: Title 10 CFR 20.1703(c)(4)(vii) requires, in part, that the licensee shall implement and maintain a respiratory protection program that includes written procedures regarding issuance of respiratory protection equipment. The licensees procedure intended to meet this regulation PMP-2281-RES-001 required the licensee to control and document the issuance of respiratory equipment with step 3.10.1, "personnel who issue respiratory equipment shall ensure the worker is qualified to wear the type of respiratory equipment requested via the PQM" and "document the issuance on Data Sheet 1, Respiratory Device Form, Data Base, or equivalent" (data sheet)..
Contrary to the above, on April 9, 2024, and April 10, 2024, the licensee failed to implement their procedure regarding the issuance of respiratory equipment. Specifically, step 3.10.1 of the PMP-2281-RES-011 required that personnel who issue respiratory equipment shall ensure the worker is qualified to wear the type of respiratory equipment requested via the PQM and document the issuance on a data sheet and these actions were not performed.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 18, 2024, the inspectors presented the integrated inspection results to Q. S. Lies, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.
- On April 12, 2024, the inspectors presented the radiation protection inspection results to K. Ferneau, Site Vice President, and other members of the licensee staff.
- On April 25, 2024, the inspectors presented the inservice inspection results to J. McClelland, Engineering Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.01 Procedures 12-OHP-4022-Severe Weather 24
001-010
PMPO-5055-Severe Weather Guidelines 14
SWM-001
71111.04 Miscellaneous 2-OHL-5030- Unit 2 Tours - U2 Auxiliary Tour 47
SOM-077
Procedures 2-OHP-4021-003-Letdown, Charging and Seal Water Operation 74
001
71111.05 Fire Plans Fire Pre-Plans, Volume 1 47
Miscellaneous D.C. Cook Fire Safety Analysis (FSA) 5
71111.08P Corrective Action AR 2016-9197 Primary-to-Secondary Leakage in Unit 2 Identified 08/12/2016
Documents AR 2022-7595 Possible Boric Acid on Cooling Coils for 4 CLVs 09/28/2022
AR 2022-7713 RVLIS Piping and Indicator Housing 10/01/2022
AR 2022-7884 2-PP-6N CBP Impeller Degraded 10/05/2022
AR 2022-7952 FME Identified and Removed 10/07/2022
AR 2022-8016 2-NMO-151 Inactive Packing Leak 10/08/2022
AR 2022-8018 Evaluate Relevant Conditions Identified during RVCH Exam 10/08/2022
AR 2022-8087 22 RCP Motor Air Inlet Screen Gaskets Were Loose 10/10/2022
AR 2022-8560 FM Found during Initial Core Plate Inspection 10/21/2022
AR 2022-8576 2-HE-6B, ECT Probe Stuck in Tube 10/22/2022
AR 2022-8708 Limited Volume Coverage Obtained during ISI Examination 10/26/2022
AR 2022-9001 Metal Punch Found on Unit 2 Reactor Head 11/02/2022
AR 2023-1061 FM Found during Condenser Waterbox inspection 02/03/2023
AR 2023-3492 Components Not in the ISI Program 05/04/2023
AR 2023-3515 Components Not in the ISI Program 05/04/2023
AR 2023-3711 Missing Components from the ISI Program 05/15/2023
AR 2023-3919 Dedicated Section XI valve 05/22/2023
AR 2023-4580 Leak Found on 2-QC-107S 06/20/2023
AR 2023-5520 No Stamping Guidance in ISI Program Procedures 07/31/2023
AR 2023-5741 Exam Item No. and Associated Welds Missing from ISI 08/10/2023
Program
Inspection Type Designation Description or Title Revision or
Procedure Date
AR 2024-0205 Actions to Address Condition Under CR 2022-3869 01/08/2024
AR 2024-0891 Foreign Material Identified and Removed in New Fuel 01/31/2024
Assembly
AR 2024-0895 Active Leakage for U2 CTS Spray Ring Header 01/31/2024
AR 2024-2313 Flaw Found during Prefabrication Weld Radiography 03/22/2024
Inspection
AR 2024-2550 Cavity Leakage Identified during U2 Cavity Flood up 03/28/2024
AR 2024-2737 U2C28 Steam Generator Foreign Material - Aggregate 04/01/2024
AR 2024-2892 AR 2024-2892; 2-RH-133, (3) Studs and (3) Nuts Failed 04/23/2024
VT-1 Inspection
GT 2016-0437-4 Primary-to-Secondary Leak Program Assessment 12/01/2016
GT 2023-0340 ISI and Alloy 600 Program Full SA 01/12/2023
Corrective Action AR 2024-2474 NRC Observation of Cook Welding Procedures 03/26/2024
Documents AR 2024-2513 Flaking Paint on the RX Pit Walls 03/27/2024
Resulting from
Inspection
Drawings DC-00032 Instrumentation Penetration Assy. and Details - Bottom 0
Head
DC-03135 Instrumentation Tube Final Machining Details 9
DC-03136 Instrumentation Tube Installation Details 10
Engineering EC 1000222 Replace Check Valve 2-Sl-161-L4 0
Changes EC 1001760 2-SI-152N, Check Valve Replacement 0
EC 1001818 2-SI-247N, Install New High Point Vent on Unit 2 ECCS 0
Train `A' Piping Upstream of Valve 2-SI-152N
EC 55940 2-SI-109, Install New Vent Valve on ECCS Piping Between 0
Valves 2-IMO-255 & 2-IMO-256
Miscellaneous Unit 2 Steam Generator Primary Side Integrity Plan 7
Primary-to-Secondary Leak Strategic Plan 0
51-9198861-001 DC Cook Unit 2 Steam Generator Degradation Assessment 1
U2C23
51-9263363-000 DC Cook U2C23 Steam Generator Condition Monitoring and 0
Operational Assessment
51-9318053-000 DC Cook Unit-2 SG Operational Assessment to Support 0
Deferral of Planned Inspections at U2C26 (Spring 2021) and
Inspection Type Designation Description or Title Revision or
Procedure Date
U2C27 (Fall 2022)
AEP-NRC-2017-2016 Steam Generator Tube Inspection Report 05/24/2017
AEP-NRC-2022-Unit 2 Updated Steam Generator Tube Inspection Report to 07/18/2022
Reflect TSTF-577 Reporting Requirements
AEP-NRC-2022-Request for Relief Related to American Society of 10/24/2022
Mechanical Engineers (ASME) Code Case N-729-6
Supplemental Examination Requirements, ISIR-5-06
AEP-NRC-2024-Request for Relief Related to American Society of 04/03/2024
Mechanical Engineers (ASME) Code Case N-729-6
Supplemental Examination Requirements, ISIR-5-07
SG-CDMP-24-3 D.C. Cook U2C28 Steam Generator Degradation 0
Assessment
NDE Reports 41290301-Radiographic Examination of SI-152N Field Welds 04/12/2024
AD9618
RAL46202 Radiographic Examination of 2-SI-161-L4 Field Welds 2 and 04/13/2024
RAL600212 Radiographic Examination of 2-SI-161-L4 Shop Weld 1 03/26/2024
U2-PT-24-002 Liquid Penetrant Examination of RCP #22 Support Lug #1 04/04/2024
U2-UT-24-013 Ultrasonic Examination of STM-24-01 Tubesheet to Head 04/04/2024
U2-VE-24-002 VT-1 of 2-RH-133 Studs, Bolts, and Nuts 04/15/2024
U2-VE-24-003 VT-1 of 2-RH-133 Valve Body Internal Surface 04/15/2024
U2-VE-24-004 VT-1 of 2-RH-133 Studs, Bolts, and Nuts 04/15/2024
U2-VT-22-047 Bare Metal Visual of 58 BMI Penetrations 10/25/2022
U2-VT-22-051 Bare Metal Visual Examination of Upper Closure Head and 10/24/2022
U2-VT-22-056 Bare Metal Visual Examination of Upper Closure Head and 10/24/2022
U2-VT-24-027 Bare Metal Visual of 58 Bottom Mounted Instrumentation 04/02/2024
U2-VT-24-036 Bare Metal Visual Examination of Upper Closure Head and 04/04/2024
U2-VT-24-037 Bare Metal Visual Examination of Upper Closure Head and 04/04/2024
Inspection Type Designation Description or Title Revision or
Procedure Date
U2-VT-24-038 Visual Examination of 58 Bottom Mounted Instrumentation 04/05/2024
Procedures 12-QHP-5050- Liquid Penetrant Examination 12
NDE-001
2-QHP-5050- Visual Examination: VT-1 and VT-3 9
NDE-006
2-QHP-5050- Radiographic Examination of Welds 7
NDE-010
2-QHP-5050- Visual Examination for Boric Acid and Condition of 7
NDE-027 Component Surface
8-MC-GTAW WPS for Qualification of Automatic GTAW Welds 16
8-MN-GTAW WPS for Qualification of Manual GTAW Welds 7
MRS 2.4.2 GEN-Eddy Current Inspection of Pre-Service and In-Service Heat 20
Exchanger Tubing
MRS-GEN-1127 Guideline for Steam Generator Eddy Current Data Quality 16
Requirements
MRS-GEN-1240 Position Verification Procedure 7
MRS-GEN-1503 ANSER Automated Analysis Recommended System 1
Configuration
PMP-5030-001-Boric Acid Corrosion Control 31
001
SGMS 2.2.1 DC Cook U2C28 Steam Generator Inspection Plan 0
GEN-01
SGMS 2.2.1 Steam Generator Data Management 21
GEN-01
SGP-PLG-RIB-Mechanical Ribbed Plugging of Steam Generator Tubes 5
SGS-VIP-0001-DC Cook U2C28 Secondary Side Inspection Plan 0
SSI-A-005 Qualification And Certification of Nondestructive Examination 34
and Testing Personnel
WDI-STD-1138 Manual Ultrasonic Examination of Vessel Welds >2 Inches in 6
Thickness in Accordance with ASME Section XI, Appendix I
Inspection Type Designation Description or Title Revision or
Procedure Date
(Non-Appendix VIII)
WDI-STD-1188 Generic Procedure for Ultrasonic Straight Beam Examination 1
of Studs and Bolts in Accordance with PDI-UT-5
WPS 8.1TS Welding Procedure Specification for Manual GTAW and 7
Work Orders WO 5548855701 Install a High Point Vent Downstream of 2-IMO-255/266 10/29/2022
71111.11Q Procedures 2-OHP-4021-001-Reactor Start-Up 71
2
71111.13 Corrective Action 2024-3397 Spent Fuel Pool Transfer System Overload 04/17/2024
Documents 2024-3562 Transfer Canal Cover Plate Bent Hinge 04/20/2024
Miscellaneous Detailed Risk Assessment, Unit 1 Week of 05/12/2024 to 0
05/18/2024
Detailed Risk Assessment, Unit 1 Week of 3/31/2024 - 0
4/6/2024
Detailed Risk Assessment, Unit 2 Week of 04/14/2024 to 0
04/20/2024
Detailed Risk Assessment, Unit 1 Week of 05/19/2024 to 0
05/25/2024
71111.15 Corrective Action 2024-4331 Unit 2 Manual Reactor Trip (Oscillating S/G Water Levels)05/15/2024
Documents AR 2024-3442 Fuel Assembly Unable to be Grappled due to RCCA 04/18/2024
Interference
AR 2024-3455 Damaged RCCA 04/19/2024
AR 2024-3694 4160V Run Bus Comp Measures and Meter Replacements 04/24/2024
Miscellaneous CEP Donald C. Cook Nuclear Plant Emergency Plan 48
DIT-B-01099-12 Minimum Acceptable Voltages at the 4160V and 600V 12/17/2004
Safety Buses for Modes 1 through 6 and Defueled Condition
Procedures 1-OHL-4030- UNIT 1 TOURS - U1 CR M5,6&D SHIFT CHKS 43
SOM-038
1-OHP-4030-114-Operations Weekly Surveillance Checks 36
031
2-OHL-4030- UNIT 2 MODE CHANGE - 2 MC CR M5,6&D SHIFT CHKS 36
SOM-064
2-OHP-4030-214-Operations Weekly Surveillance Checks 38
031
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.24 Corrective Action AR 2024-2974 2ABEDG Tripped during PMT due to Uncontrolled Voltage 04/07/2024
Documents Rise
AR 2024-3007 U2 AB EDG Tripped during PMT due to no Voltage Indicated04/08/2024
AR 2024-3014 2-CCR-462 is Greater than the Admin Limit for the A/L LLRT04/08/2024
AR 2024-3121 Leakage Past 2-CCR-460 During LLRT 04/10/2024
AR 2024-3291 Cracked Outer Covering on Bottom Right Conduit Labeled 04/15/2024
8094R
Miscellaneous Containment Integrated Leak Rate Program Post-Outage 06/18/2024
Report U2C28
Procedures 2-EHP-4030-234-Unit 2 LLRT Test Sketch Leak Rate Data Sheet 36
2-3
2-IHP-4030-217-Seat Leakage Test of 2-IMO-128 & 2-ICM-129 Rev. 4
001
2-OHP-4030-208-E.C.C.S. Valve Operability Test - Defueled 43
053A
2-OHP-4030-208-East Residual Heat Removal Heat Exchanger HE-17A Outlet 43
053A Flow Control Valve 2-IRV-310 Stroke Test - RHR in Service
2-OHP-4030-208-West Residual Heat Removal Heat Exchanger HE-17W 39
053B Outlet Flow Control Vale 2-IRV-320 Stroke Test - RHR in
Service
2-OHP-4030-208-E.C.C.S. Valve Operability Test - Defueled 39
053B
2-OHP-4030-232-AB Diesel Generator Operability Test (Train B) Rev. 73
27AB
2-OHP-4030-232-DG2AB Load Sequencing & ESF 63
217B
Work Orders C10025688013 2-IMO-128-ACT, PERFORM AS FOUND/AS LEFT 04/15/2024
DIAGNOSTICS
C10025688034 2-IMO-128, Perform as Left Seal Leakage Test (2-IHP-4030-04/15/2024
217-001)
C10050769-029 (PH005) 2-WMO-734-ACT: Install New ETT Sensor 04/10/2024
C10054628001 2-OME-ICE-COND, Normal Refueling Ice Condenser 03/23/2024
Maintenance
C10062959001 Replace 1-BATT-AB Cell 55 05/21/2024
Inspection Type Designation Description or Title Revision or
Procedure Date
C10063016001 1-BATT-AB Replace Cell 113 05/23/2024
71124.01 Procedures 12-THP-6010- Radiation Work Permit (RWP) Processing 45
RPP-006
2-THP-6010- Radiological Posting 44
RPP-418
2-THP-6010- Radiological Controls for Radiography 14
RPP-420
2-THP-6010- Locked High Radiation Area and Very High Radiation Area 7
RPP-019 Verification
Radiation CNP-2403-00265 2-SI-161-L4 03/25/2024
Surveys CNP-2404-00087 2-SI-161-L4 Breach and Cut Out 04/03/2024
CNP-2404-00118 2-SI-161-L4 Initial Internals/ Pipe Prep 04/04/2024
CNP-2404-00135 Downpost HCA 04/05/2024
Radiation Work 242130 U2C28 - Perform Radiography in Auxiliary, Containment, 00
Permits (RWPs) & Turbine Buildings & Plant Radiologically Controlled Areas
(RCAs)
2148 U2C28 - Steam Generator Primary Activities 00
71124.03 Corrective Action AR 2024-3173 Respirators Issued without Proper 04/11/2024
Documents Documentation/Verification
Resulting from
Inspection
Miscellaneous PMP-2281-RES-Data Sheet 1, Respiratory Device Issue Form 04/10/2024
001
Procedures PMP-2281-RES-Control and Use of Respiratory Protection Devices 25
001
PMP-2281-RES-Control and Use of Respiratory Protection Devices 26
001
71124.08 Corrective Action AR 2024-3186 Vehicle Inspection Check off Sheet Tire Inspection Marked 04/11/2024
Documents N/A
Resulting from
Inspection
Shipping Records DCC24-030 UN3321, Radioactive Material, Low Specific Activity (LSA-II), 04/10/2024
Class 7
18