IR 05000315/2023004
| ML24030A965 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/31/2024 |
| From: | Dariusz Szwarc NRC/RGN-III/DORS/ERPB |
| To: | Lies Q Indiana Michigan Power Co |
| References | |
| IR 2023004 | |
| Download: ML24030A965 (1) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2023004 AND 05000316/2023004
Dear Q. Shane Lies:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On January 10, 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.
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, Dariusz Szwarc, Acting 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:
05000315/2023004 and 05000316/2023004
Enterprise Identifier:
I-2023-004-0048
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
October 01, 2023 to December 31, 2023
Inspectors:
J. Cassidy, Senior Health Physicist
T. Hooker, Health Physicist
J. Mancuso, Resident Inspector
J. Park, Reactor Inspector
J. Winslow, Reactor Systems Engineer
P. Zurawski, Senior Resident Inspector
Approved By:
Dariusz Szwarc, Acting 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
None.
PLANT STATUS
Unit 1 and Unit 2 began the inspection period at rated thermal power and remained at or near rated thermal power with the following exceptions: Unit 1 was shut down for refueling outage from October 11, 2023, to November 18, 2023, and reduced power to approximately 22 percent on December 10, 2023, for repair of a main steam leak. Unit 1 was returned to 100 percent power on December 12, 2023. Unit 2 reduced power to approximately 75 percent on December 8, 2023, for main turbine valve testing and returned to100 percent power on December 9,
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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 Outage U1C32 High Risk: Low Reactor Coolant System (RCS) Inventory/High RCS Heat Load on October 17, 2023
- (2) Unit 1 Dual Essential Service Water (ESW) Pump Outage with Unit 2 ESW/Component Cooling Water Pumps, 4kV Rooms, Emergency Diesel Generators (EDGs) and SDGs guarded on October 23, 2023
- (3) Unit 1 & 2 Spent Fuel Pool Heat Exchangers/Cooling on October 30, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 N-Train Battery system on October 3, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) Unit 1 Outage U1C32 Key Safety Function Fire Preservation Actions During the weeks of October 9 and October 16, 2023:
- Fire Zone 42D, E.P.S. Battery Room, Unit 1 Elevation 609'-6"
- Fire Zone 44N, Auxiliary Building North, Both Units Elevation 609'-0"
- Fire Zone 44S, Auxiliary Building South, Both Units Elevation 609'-0"
- Fire Zone 53, Unit 1 Control Room
- (2) Fire Zones 8, 9, 10, 11, 23, 24, 25, & 26: U-1 Quadrants 3N, M, S, 4 RCT and U-2 Quadrants 3N, M, S, & 4 Cable Tunnel - Elev. 596'-3.5"
- (3) Fire Zone 55: Switch Gear Room Cable Vault, Unit 1 Elevation 625' 10" on November 27, 2023
===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 from October 16, 2023, to October 31, 2023.
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
- Residual Heat Removal System Welds, 1-RH-28-12S and -13S, Cat. R-A, Item R1.20 Magnetic Particle Examination
- Pressurizer Support Weld, 1-PZR-26, Cat. B-K, Item B10.10 Visual Examination
- Reactor Bottom Mounted Instrumentation (BMI) Penetration Welds, Code Case N-722 Exam, Item B15.80
- Reactor BMI Penetration Nozzle Dissimilar Metal Welds, Code Case N-722 Exam, Item B15.100 Welding Activities
- Repair/Replacement of Weld No. 1 and 2, Replacement of Check Valve 1-SI-158-L2 on Safety Injection (SI) to Loop #2 Hot Leg under WO 55512999-02 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) Boric Acid Evaluations
- Action Request (AR) 2022-4046-1, Boric Acid on Bottom of U1 Lower Vessel, June 7, 2022
- AR 2023-3461-1, Unit 1 North SI Pump Mechanical Seal Boric Acid Leak, May 30, 2023 Corrective Actions
- AR 2022-2701, Boric Acid Deposit on U1 SWI Piping Suspect Through Wall, April 5, 2022
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from February 14, 2023, to March 20, 2023.
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 control room during Unit 1 U1C32 Shutdown on October 13, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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 1 and 2 Ice Condenser a(1) Plan on November 6, 2023
- (2) Unit 1 Non-Essential Service Water System on December 11, 2023
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 1 refueling outage U1C32 risk management on October 23, 2023
- (4) Maintenance Risk Cycle 128, Week 12, with Unit 1 risk significant component cooling water work and condenser waterbox isolations the week of December 18, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 and Unit 2 Open Operational Decision Making Issues on October 5, 2023
- (2) AR 2023-7398; Unit 1 Motor Driven Aux Feed Pump did not Restart During LOP/LOCA Test on October 23, 2023
- (3) AR 2023-8319; Char Testing Identified Sort on Outer Shield to Ground (Source Range Instrumentation) on November 8, 2023
- (4) AR 2023-9006; High Reactor Coolant Activity/Potential Failed Fuel on November 28, 2023
- (5) AR 2023-9354; Cracks on Walls of Battery 1-BATT-AB Cells 55 and 113 on December 13, 2023
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)10CFR 50.59 Technical Specification change 2019-0189-03 for dose equivalent I-131 specific activity due to leaking fuel assembly on December 10, 2023
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Refueling Outage U1C32 activities from October 14 through November 15, 2023.
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) (8 Samples)
- (1) Unit 1 East Residual Heat Removal (RHR) Heat Exchanger Outlet Control Valve 2-IRV-310 on October 5, 2023
- (3) Unit 1 Containment Chiller A on October 10, 2023
- (4) Ice Condenser Testing during Refueling Outage U1C32 on November 9, 2023
- (5) Unit 1 Motor Driven Auxiliary Feedwater Pump following failure on November 18, 2023
- (6) Unit 1 East Component Cooling Water Loop Surveillance Test on December 4, 2023
- (7) Unit 1 West Component Cooling Water MOV Diagnostic Testing on December 19, 2023
- (8) Unit 1 East Centrifugal Charging Pump Operability Test on December 26, 2023
Surveillance Testing (IP Section 03.01) (3 Samples)
(1)12-IHP-4030-046-001; Unit 1 and 2 Personnel Airlock Leak Rate Surveillance on November 8, 2023 (2)12-IHP-4030-0082-005; AB, CD, and N-Train Battery Monthly Surveillance and Maintenance on November 28, 2023 (3)2-OHP-4030-232-027AB; AB Diesel Generator Operability Test (Train B) on December 20, 2023
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1 Trevi-Testing on October 12, 2023
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)1-OHP-4030-108-053A & 053B; Emergency Core Cooling System Vale Operability Test - Train A & B on October 30, 2023
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1 Ice Condenser Ice Basket Weighing, October 12 through November 15, 2023
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.
- RMA-2080-EPA-008: Screening # 22-33, June 22, 2022
- RMA-2080-EPA-008: Screening # 22-47, November 17, 2022
- RMA-2080-EPA-008: Screening # 23-17, May 11, 2023 This evaluation does not constitute NRC approval.
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, 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 and supplies leaving the radiologically controlled area (RCA)
- (2) Workers exiting Unit 1 upper containment during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensees control of radiological hazards for the following radiological work:
- (1) Unit 1 containment spray valve internals inspection
- (2) Unit 1 quick release valve testing
- (3) High radiation area and contamination briefing for Unit 1 quick release valve internals replacement High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
- (1) Unit 1 reactor pit hatch
- (2) Unit 1 lower containment reactor coolant drain tank gate
- (3) Unit 1 upper containment reactor coolant drain tank hatch 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.
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)===
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2022 through September 30, 2023)
- (2) Unit 2 (October 1, 2022 through September 30, 2023)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2022 through September 30, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 1, 2022 through September 30, 2023
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) AR 2023-7857; Mistras Part 21 Notification Regarding Falsification of Calibration Certificate for Acoustic Emission Test Equipment Used for Reactor Head and Internals Lift Rigs
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in minimum staffing that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Observation: Updated Information Related to Acoustic Emission (AE) Test Instrument Issue for Reactor Head and Internals Lifting Rigs was Not Reviewed 71152A As a result of an issue identified during the June 2021, Nuclear Procurement Issues Corporation (NUPIC) audit of the licensees vendor, Mistras Services, regarding falsification of calibration for an acoustic emission (AE) data acquisition system instrument, the licensee documented the condition under Action Requests (AR) 2021-5416 and 2021-7084. Under these ARs, the licensee evaluated the AE tests performed during the reactor head and internals lift activities in March 2019, for Unit 1, and October 2019, for Unit 2. It concluded there was no adverse licensee impact on the use of the AE test instrument, and that the calibration of the AE test instrument used at the licensee facility was valid.
However, during an inquiry into the licensee actions following the vendor issuance of a Title 10 Code of Federal Regulations (CFR) Part 21 Interim Report, dated October 20, 2023, noting a deviation in the calibration certificates for the AE instruments used at the licensee facility, the inspectors identified that the vendor previously sent the licensee a letter dated April 4, 2023. This letter notified the licensee that the AE tests performed in March and October 2019, for Units 1 and 2, respectively, both used the instruments that did not have a then-current valid certificate of calibration. This was updated information that was not reviewed against the result of the licensee corrective action review for ARs 2021-5416 and 2021-7084. The importance of reviewing the updated information is to ensure whether theres any significant effect to the results of a prior corrective action review that had been performed. The promptness of such review ensures potential issues are fully identified and appropriate corrective actions assigned as necessary in a timely manner. It becomes especially important for major activities such as the reactor head and internals lifting devices during refuel outages.
As a result, the licensee initiated AR 2023-7857 on October 24, 2023. Immediate corrective actions included a detailed evaluation of instrumentation used during the 2019, Unit 1 AE test, prior to the scheduled reactor head and internals lifts during the 2023, Unit 1 refuel outage. The licensee also completed similar evaluation for the Unit 2 AE test. These reviews concluded that the 2019 AE tests were acceptable as-is. Inspectors did not identify any safety concern or performance deficiency.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 10, 2024, the inspectors presented the integrated inspection results to Q. Lies, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.
- On October 27, 2023, the inspectors presented the radiation protection inspection results to K. Ferneau, Site Vice President, and other members of the licensee staff.
- On October 31, 2023, the inspectors presented the Inservice inspection results to M. Scarpello, Regulatory Affairs Director, and other members of the licensee staff.
- On November 30, 2023, the inspectors presented the Emergency Action Level and Emergency Plan change review inspection results to M. Scarpello, Regulatory Affairs Director, and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed the World Association of Nuclear Operators (WANO) September 2023 Peer Review Report. The inspectors evaluated this report to ensure that NRC perspectives of licensee performance were consistent with any issues identified during the assessment. The inspectors also reviewed this report to determine whether INPO identified any significant safety issues that required further NRC follow-up.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2015-14835
2-QC-3 Area (SFP) Requires Painting
11/15/2015
AR 2021-9726
No Vibration Pads on N SFP Pump/Motor
11/30/2021
AR 2022-8028
SFP Temp Alarm Coming in 6 degrees early
10/09/2022
Corrective Action
Documents
AR 2022-8635
Incorrect Date Entered on Procedure Attachment
10/24/2022
1-OHP-4021-032-
008AB
Operating DG1AB Subsystems
036
1-OHP-4021-032-
008CD
Operating DG1CD Subsystems
043
1-OHP-4021-082-
015
Operation of the N Train Battery System
21
2-OHP-4021-
018-002
Placing in Service and Operating the Spent Fuel Pit Cooling
and Cleanup System
2-OHP-4021-
019-001
Operation of the Essential Service Water System
076
2-OHP-4021-
2-008CD
Operating DG2CD Subsystems
037
2-OHP-4021-032-
008AB
Operating DG2AB Subsystems
040
Procedures
PMP-4100-SDR-
001
Plant Shutdown Safety and Risk Management
055
Fire Pre-Plans -
Volume 1
Fire Zone 8: Unit 1 Quadrant 4 RCT elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 9: Unit 1 Quadrant 3N RCT elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 10: Unit 1 Quadrant 3M RCT elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 23: Quadrant 3N Cable Tunnel Unit 2
elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 24: Quadrant 3M Cable Tunnel Unit 2
elev. 596' -3.5"
Fire Plans
Fire Pre-Plans -
Volume 1
Fire Zone 25: Quadrant 3S Cable Tunnel Unit 2
elev. 596' -3.5"
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Fire Pre-Plans -
Volume 1
Fire Zone 26: Quadrant 4 Cable Tunnel Unit 2
elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 11: Unit 1 Quadrant 3S RCT elev. 596' -3.5"
Fire Pre-Plans -
Volume 1
Fire Zone 44N: Auxiliary Building North Both Units,
elev. 609'-0"
Fire Pre-Plans -
Volume 1
Fire Zone 44S: Auxiliary Building South Both Units,
elev. 609'-0"
Fire Pre-Plans -
Volume 1
Fire Zone 53: Unit 1 Control Room, elev. 633'-0"
Fire-Pre-Plans -
Volume 1
Fire Zone 55: Switchgear Room Cable Vault Unit 1 - 625'-10"
2-FP-4030-066-
205
Fire Detection Instrumentation Channel Operational Test
(U-1 Zones 6, 8, 9, 12, 13[4kV], 14[RCT], 15[4kV], 17, 19,
21, 23 and 24)
2-FPP-4030-
066-204
Fire Detection Instrumentation Channel Operational Test
(U-2 Zones 1, 3, 4, 5, 7, 8, 10, 17, 18, 19, 21, 23, 25, 27, and
28)
Procedures
2-FPP-4030-
066-205
Fire Detection Instrumentation Channel Operational Test
(U-1 Zones 6, 8, 9, 12, 13[kV], 14[RCT], 15[4kV], 17, 19, 21,
23, and 24)
Work Orders
55548577-01
U1 Switchgear Cable Vault CO2 Fire Suppression Test
07/29/2021
22-2543
Variable Spring Support Setting Out of Tolerance
04/01/2022
22-2701
Boric Acid Deposit on U1 SWI Piping Suspect Through Wall
04/05/2022
22-2941
RCP #12 Shaft Seal Lower Housing Cap Screws are
Corroded
04/13/2022
22-6922
VT-2 Task Not Performed for Completed Work During
U1C31
08/30/2022
22-7339
Missed Construction Code Exam on E RHR Min-Flow Line
U1C31
09/20/2022
22-8007
Potential Trend of Missing Components from ISI Program
10/08/2022
Corrective Action
Documents
23-5741
Exam Item No. and Associated Welds Missing from ISI
Program
08/10/2023
Corrective Action
23-7287
Issues with Records for WO 55512999-02
10/13/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
AR 2022-2646-1
RCP Shaft Seal is Overflowing Down the Side of the
Pump
04/26/2022
AR 2022-4046-1
Boric Acid on Bottom of U1 Lower Vessel
06/07/2022
Engineering
Evaluations
AR 2023-3461-1
Unit 1 North SI Pump Mechanical Seal Boric Acid Leak
05/30/2023
U1-MT-23-001
Surface Exam (MT) of Pressurizer Support Weld 1-PZR-26
10/28/2023
U1-UT-23-001
Volumetric Exam of RH Pipe Weld 1-RH-28-12S
10/31/2023
U1-UT-23-002
Volumetric Exam of RH Pipe Weld 1-RH-28-13S
10/31/2023
U1-UT-23-016
Volumetric Exam of FW Pipe Weld 1-FW-12-02S
10/31/2023
U1-UT-23-017
Volumetric Exam of FW Pipe Welds 1-FW-12-03S
10/31/2023
U1-VT-23-017
Visual Examination of BMI Penetration Welds
10/25/2023
NDE Reports
U1-VT-23-018
Visual Examination of BMI Penetration Nozzle DM Welds
10/25/2023
2-QHP-5050-
NDE-002
Magnetic Particle Examination
2-QHP-5050-
NDE-027
Visual Examination for Boric Acid and Condition of
Component Surface
PMP-5030-001-
001
Boric Acid Corrosion Control
WDI-STD-1185
Generic Ultrasonic Examination Procedure for Ferritic Welds
in Accordance with PDI-UT-1
Procedures
WDI-STD-1186
Generic Ultrasonic Examination Procedure for Austenitic
Welds in Accordance with PDI-UT-2
Work Orders
55512999-02
1-SI-158-L2 Replace Valve
05/25/2022
Miscellaneous
Requalification
Program Annual
Testing Summary
Results
Licensed Operator Annual Examination Performance
Records for 2023
10/30/2023
AR 2023-1949
1-PP-85 Outboard Bearing is Hot
03/08/2023
AR 2023-1997
1-PP-*N Outboard Bearing is Hot to the Touch
03/09/2023
AR 2023-8958
U1 S NESW Pump Trip/Motor Fire
11/26/2023
AR 2023-9030
1-PP-8s Motor Grounding Bolt Broke Off
11/28/2023
Corrective Action
Documents
GT 2022-9972
Complete a Risk Assessment for Ice Basket Restoration
2/08/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Maintenance Rule Scoping Document - Ice Condenser
Engineering
Evaluations
Ice Condenser - Unit 1 (a)(1) Action Plan Revision
10/03/2023
Procedures
2-EHP-4030-
010-262
Ice Condenser Surveillance and Operability Evaluation
Corrective Action
Documents
AR 2023-7908
U1 AB EDG Auto Voltage Regulator Did Not Respond as
Expected
10/25/2023
Unit 1 Online Risk, Cycle 128 Week 12
0, 1, 2
Miscellaneous
Unit 1 Online Risk, Cycle 128 Week 12
0, 1, 2
2-IHP-6030-032-
001
Emergency Diesel Generator Automatic Voltage Regulator
Timing and Adjustment
009
2-IHP-6030-032-
004
Emergency Diesel Generator Woodward 2301A Analog
Governor Tuning and Adjustment
017
Procedures
PMP-4100-SDR-
2
Outage Risk Assessment Management
2
AR 2010-3656-21
Revise 12-IHP-5021-EMP-033
08/09/2010
AR 2010-3732
1-AB Diesel Fuel Oil Pump Cable Failures
AR 2018-7809
Error in AEP-15-46
08/06/2018
AR 2022-1764
RCP #2 Seal is Sticking Open
2/28/2023
AR 2022-7453
Unit 1 Generator Hydrogen Consumption Elevated
09/22/2022
AR 2022-9452
U2 Steam Seal Degraded
11/17/2022
AR 2022-9698
Unit 1 RCS In-Leakage Trend
11/29/2022
AR 2023-5879
Elevated Noise at 12AB Loop Feed Enclosure
08/16/2023
AR 2023-7398
West Motor Driven Aux Feed Pump Did Not Restart
10/15/2023
AR 2023-8319
Char Testing Identified Short on Outer Shield to Ground
(Source Range Instrumentation)
11/04/2023
AR 2023-9006
Elevated Radionuclide Activity Detected in Unit 1
11/28/2023
AR 2023-9354
Cracks on Walls of Battery 1-BATT-AB Cells 55 and 113
2/13/2023
Corrective Action
Documents
AR 2023-9475
Gas Void Near 1-RH-125W
2/21/2023
Miscellaneous
PMP-7030-OPR-
001 Data Sheet
- 3
Adverse Condition Monitoring Plan; AR 2023-9354, Cracks
on Walls of Battery 1-BATT-AB Cells 55 and 113
2/13/2023
Operability
Evaluations
1-2022-001
Operational Decision Making Issue (ODMI); Unit 1 Main
Generator Hydrogen Usage
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1-2022-003
Operational Decision Making Issue (ODMI); 1-SV-45A
Pressurizer OME-4 Safety Valve A Leaking to the
Pressurizer Relief Tank
1-2022-003
1-SV-45A OME-4 Pressurizer OME-4 Safety Valve A is
Leaking to the Pressurizer Relief Tank
1-2022-003
1-SV-45A OME-4 Pressurizer OME-4 Safety Valve A is
Leaking to the Pressurizer Relief Tank
1-2022-003
1-SV-45A OME-4 Pressurizer OME-4 Safety Valve A is
Leaking to the Pressurizer Relief Tank
1-2023-001
RCP #2 Seal is Sticking Open
1-2023-001
RCP #2 Seal is Sticking Open
2-2022-004
Unit 2 Steam Seal System is Degraded
22-7453-2
Operational Decision Making Issue (ODMI); Unit 1 Main
Generator Hydrogen Usage
10/27/2022
AR 2023-9006
Implement 12-EHP-PER-100, Fuel Performance Monitoring
and Failed Fuel Action Plan
11/27/2023
AR 2023-9354
Cracks on Walls of Battery 1-BATT-AB Cells 55 and 113
PMP-4010-ACM-
001; Data Sheet 1
Adverse Condition Monitoring Plan; Indications of Partial
Discharge on 12AB Loop Feed Enclosure
1-EHP-4030-108-
001B
Train B Monitoring and Trending of Gas Accumulation in
004
2-IHP-5021-
EMP-033
Cable Removal and Installation
2-IHP-5021-
EMP-033
Cable Removal and Installation
2-OHP-4022-
2-019
High Reactor Coolant Activity or Failed Fuel
Procedures
2-OHP-4022-
2-019
High Reactor Coolant Activity or Failed Fuel
005
Work Orders
5555715322
TPG, DIS, U1, Install Cable 35994-1, 35995-1, 36005-1,
36006-1
01/18/2022
Miscellaneous
DIT-B-03776-01
Supporting Radiological Analysis Information for
Compensatory Measures on Dose Equivalent I-131 for
Postulated Natural Circulation with an Idle Faulted Steam
2/10/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Generator
PWROG-19030-P
Asymmetric Natural Circulation Cooldown - Revised
Strategies
Inactive Loop Flow Stagnation During Natural Circulation
Cooldown, PA-ASC-0145
AR 2023-7312
1-RH-144; East RHR Upper Compartment Spray Ring
Header Draw Valve
10/14/2023
AR 2023-7321
1-NLP-151-IE; Instrument Equalization Valve
10/14/2023
AR 2023-7323
1-QDA-21; RCP 2 Thermal Barrier DP Alarm Switch
10/14/2023
AR 2023-7330
1-RC-142; RC Loop 1 XTMA 1-NPS-122 Pressure Indicator,
1-NPI-110, and Hot Leg Sample 1-NSX-101 Drain Valve
10/14/2023
AR 2023-7343
1-NFP-222-V2; RC Loop 2 Channel 3 Differential Flow
Instrument, 1-NFP-222 Low Side Root Valve 10/14/2023
AR 2023-7348
1-SI-167-2; Accumulator 2 Outlet and SI Pumps to RC Loop
Cold Leg Test Line Drain Valve
10/14/2023
AR 2023-7353
1-SI-156E; RHR East HX and North SI Pump RC Loop 1
Loop Hot Leg Drain Valve
10/14/2023
AR 2023-7392
1-RC-140; RX Vessel Level Indicators Hi-Pressure Root
Valve
10/15/2023
AR 2023-7421
RHR 1-ICM-129 Between Seat Equalization Line Connection
Valve
10/16/2023
AR 2023-7434
1-QRV-114; Excess Letdown to Excess Letdown
HX 1-HE-13 Train A Shutoff Valve
10/16/2023
Corrective Action
Documents
AR 2023-7447
1-OME-3-2/3; No. 2 Steam Generator (Manway Cover)
10/16/2023
DIT-10037-00
Unit 1 Cycle 31 End-of-Cycle (EOC) Time-to-Boil Information
08/29/2023
DIT-10038-00
Unit 1 Cycle 32 Beginning-of-Cycle (BOC) Time-to-Boil
Information
08/29/2023
Miscellaneous
PMP-4015-RMP-
001: Data Sheet 1
Reactivity Management Guidance Form: Unit 1 Cycle 31
TREVI Testing Downpower and Shutdown
10/05/2023
Operability
Evaluations
1-OHP-4030-103-
2E
East Centrifugal Charging Pump Operability Test
24
Procedures
PMP-4100-SDR-
2
Outage Risk Assessment and Management
Corrective Action
AR 2023-9010
Cell 88 Fill Cap Found Off 1-BATT-CD
11/28/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
Engineering
Evaluations
Projected Net Weights Report (4/15/2028) U1C35
10/24/2023
1-OHP-4030-108-
053A
E.C.C.S. Valve Operability Test
031
1-OHP-4030-108-
053B
E.C.C.S. Valve Operability Test
033
1-OHP-4030-116-
20E
East Component Cooling Water Loop Surveillance Test,
2-EHP-4030-
010-262
Ice Condenser Surveillance and Operability Evaluation
28
2-IHP-4030-046-
001
Unit 1 and 2 Personnel Airlock Leak Rate Surveillance
2
2-IHP-4030-082-
005
AB, CD, and N-Train Battery Monthly Surveillance and
Maintenance
2-IHP-5030-
EMP-001
Limitorque Valve Operator Preventive Maintenance
048
2-IHP-5030-
EMP-014
MOV Diagnostic Testing
2-MHP-4030-
010-007
Ice Condenser BSKET Surveillance
2-OHP-4030-208-
053A
East Residual Heat Removal Heat Exchanger HE-17E Outlet
Flow Control Valve 2-IRV-310 Stroke Test - RHR Shutdown
Procedures
2-OHP-4030-232-
27AB
DG2AB Slow Speed Start
C10008429-001
1-SV-1A-2, Assist with Setpoint Test
10/12/2023
C10008431001
1-SV-1A-3, Perform Setpoint Test/Adjust (RIP)
10/12/2023
C10008437001
1-SV-1B-2, Perform Setpoint Test/Adjustment (RIP)
10/12/2023
C10008522-001
1-SV-2A-3, Perform Setpoint Test/Adjust (RIP)
10/12/2023
C10008769-001
1-SV-2B-3, Perform Setpoint Test/Adjustment (RIP)
10/12/2023
C10008775-001
1-SV-3-3, Perform Setpoint Test/Adjustment (RIP)
10/12/2023
Work Orders
C10009919-001
1-SV-2B-2, Perform Setpoint Test/Adjustment (RIP)
10/12/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(Trevitest)
C1002647001
Unit 1 Lower Ice Perform Door Surveillance 1-DR-CNT642-1
and Install Blast Shield
RMA-2080-EPA-008 Screening Form # 22-33
06/22/2022
RMA-2080-EPA-008 Screening Form # 23-17
05/11/2023
CFR 50.54 (Q) Reviewer Qualification Records
(Spreadsheet)
07/05/2023
Miscellaneous
RMA-2080-EPA-008 Screening Form # 22-47
11/17/2022
CEP
Donald C. Cook Emergency Plan
CEP
Donald C. Cook Emergency Plan
PMP-2080-EPP-
101
Emergency Classification
PMP-2080-EPP-
101
Emergency Classification
Procedures
PMP-2080-EPP-
101
Emergency Classification
PMP-6010-ALA-
001
This ALARA Plan is to Provide Assistance to Personnel
Assigned to Perform Preventative and Corrective
Maintenance Activities for Primary and Secondary Valves in
the Containment & Auxiliary Buildings During U1C32.
ALARA Plans
RWP 231151
Remove Lower Motor Oil Spill Pans, Instrumentation,
Inspect/Replace Seal Package: Support Work on the RCP
22-9808
Individual Observed Exiting RCA after Turning in DLR.
2/01/2022
Corrective Action
Documents
23-5650
Unlocked Gate
09/27/2023
Corrective Action
Documents
Resulting from
Inspection
23-7980
Whole Body Counter was Using the Previous Calibration
Data
10/26/2023
Historical Alpha Data Characterization.xlsx
10/15/2023
Miscellaneous
Lapel air sampler
data
Lapel Air Sampler Usage by Employees During the
Refueling Outage
10/25/2023
2-THP-6010-
RPP-418
Radiological Posting
Procedures
2-THP-6010-
Monitor Alarm Response and Personnel Decontamination
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RPP-703
PMP-6010-RPP-
003
High, Locked High, and Very High Radiation Area Access
CNP-2310-00060
Flux Map Investigational Survey
10/19/2023
Radiation
Surveys
CNP-2310-00386
1-CTS-131W Valve Breach
10/24/2023
231128
U1C32 - Valve Activities in the Auxiliary Building,
Containment, and Plant Radiologically Controlled Areas
(RCA)
Radiation Work
Permits (RWPs)
231151
Remove Lower Motor Oil Spill Pans, Instrumentation,
Inspect/Replace Seal Package: Support Work on the RCP
Self-Assessments GT 2022-8073-2
Quick Hit Self-Assessment - 71124.01 Radiological Hazard
Assessment and Exposure Controls
Work Orders
5555685602
1-CTS-131W, Inspect Valve Internals for IST Inspection
10/24/2023
MSPI Derivation Report - MSPI Emergency AC Power
System (October 2022 - September 2023) - Unit 1
MSPI Derivation Report - MSPI Emergency AC Power
System (October 2022 - September 2023) - Unit 2
Operations Narrative Logs
Reactor Coolant System Leakage Performance Indicator
Data (October 2022 - September 2023) - Unit 1
Reactor Coolant System Leakage Performance Indicator
Data (October 2022 - September 2023) - Unit 2
Data Sheet 10
Reactor Coolant System Specific Activity
Various
Data Sheet 15
Occupational Exposure Control Effectiveness
Various
Miscellaneous
Data Sheet 16
RETS/ODCM Radiological Effluent Occurrences
Various
71151
Procedures
PMP-5078-STD-
2
Surveillance Test Interval Control
21-5416
Mistras Services on Hold
06/16/2021
Corrective Action
Documents
21-7084
Conditions Imposed on Mistras Services
08/17/2021
Corrective Action
Documents
Resulting from
Inspection
23-7857
Mistras Vendor
10/24/2023
Engineering
AR 2023-7857
Falsification Inspection Records for 1-OME-25 Reactor
10/31/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Evaluations
Vessel OME-1 Head Lifting Rig and 1-OME-26 Reactor
Vessel OME-1 Internals Lifting Rig
C1006949
Contract Release C1006949 to Contract 1588238
04/18/2023
Miscellaneous
Letter from
MISTRAS to DC
Cook
Acoustic Emission Equipment Nonconformance Update
04/04/2023
Work Orders
55520965-01
1-OME-25, MISTRAS, Perform Acoustic Test of Head Lift
Rig
03/10/2019