IR 05000315/2024003
| ML24298A098 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/31/2024 |
| From: | Matthew Learn NRC/RGN-III/DORS/ERPB |
| To: | Lies Q Indiana Michigan Power Co |
| References | |
| EA-24-078 IR 2024003, IR 2024001 | |
| Download: ML24298A098 (1) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2024003; 05000316/2024003; 07200072/2024001 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Q. Shane Lies:
On September 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On October 8, 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 did not involve a violation of NRC requirements.
If you disagree with a finding not associated with a regulatory requirement 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.
October 31, 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, Matthew C. Learn, Acting Branch Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket Nos. 05000315; 05000316 and 07200072 License Nos. DPR58 and DPR74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315; 05000316 and 07200072
License Numbers:
Report Numbers:
05000315/2024003; 05000316/2024003 and 07200072/2024001
Enterprise Identifiers: I2024-003-0057 and I2024-001-0130
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
July 01, 2024 to September 30, 2024
Inspectors:
N. Audia, Reactor Inspector
J. Cassidy, Senior Health Physicist
A. Guieb, Project Engineer
T. Hooker, Health Physicist
E. Kokkinis, Project Engineer
J. Kutlesa, Senior Emergency Preparedness Inspector
J. Mancuso, Senior Resident Inspector
T. Okamoto, Project Engineer
D. Sargis, Health Physicist
Approved By:
Matthew C. Learn, Acting Branch 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
Failure to Implement Design Control Process Causes Main Turbine Trip Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000315,05000316/2024003-01 Open/Closed None (NPP)71153 A self-revealed finding of very low safety significance (Green) was identified with the licensee's failure to implement a modification to a turbine supervisory instrumentation (TSI)card. Specifically, the licensee failed to correctly implement a modification to the turbine protection system, leading to incorrect inputs included into the turbine trip circuit which led to a main turbine trip and subsequent reactor trip.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000316,05000315/20 23011-01 Safety-Related Motor Control Center Bus Bar Commercial Grade Dedication 71111.21N.03 Discussed EDG EA24-078 Failure to Comply with 10 CFR Part 37 71124.08 Closed LER 05000316/2024-001-00 LER 2024-001-00 for Donald C. Cook Nuclear Plant, Unit 2, Reactor Trip due to Main Turbine Trip from a High-High Thrust Bearing Position Trip 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On September 27, 2024, Unit 1 reduced power to approximately 90 percent of rated thermal power for main turbine valve testing. The unit returned to full rated thermal power on September 28, 2024, and remained at or near full rated thermal power for the inspection period.
Unit 2 began the inspection period shutdown to address a reactor coolant system leak in excess of the 10 gallons per minute allowed by technical specifications. The unit started up on July 1, 2024, reached full rated thermal power on July 4, 2024, and remained at or near full 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)1E motor driven auxiliary feedwater pump (MDAFP) following a surveillance run on July 12, 2024 (2)2CD emergency diesel generator (EDG) during 2AB EDG work on July 25, 2024 (3)1CD EDG following planned surveillance on September 4, 2024 (4)1AB EDG following surveillance run on September 11, 2024
- (5) Unit 2 turbine driven auxiliary feedwater pump (TDAFP) during 12AB loop feed enclosure maintenance window on September 19, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 emergency core cooling (SIS) on August 5, 2024.
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) Fire Zone 17A/D Unit 1: auxiliary feed pump rooms and corridor to auxiliary feed pump rooms, both units, elevation 591' on September 3, 2024
- (2) Fire Zone 107/50: auxiliary feedwater battery room and HVAC on September 18, 2024
- (3) Fire Zone 18: CD diesel generator room, Unit 2, elevation 587' - 0" on September 18, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on August 15, 2024.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the Unit 1 safety injection pump room on September 16, 2024.
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 a Unit 1 downpower for main turbine valve functional testing on September 13, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated RQ-E4903 As-found Simulator Training on August 6, 2024.
- (2) The inspectors observed and evaluated an As-found Simulator Evaluation Scenario on August 27, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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 main steam on July 15, 2024
- (2) Unit 2 component cooling water (CCW) a(1) action plan on July 8, 2024
- (3) EDG frequency issues on July 29, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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 loop feed enclosure replacement on September 16, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples 1 Partial)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 2024-5435; 1-DCR205 Failed Inservice Test (IST) Stroke Time on July 15, 2024
- (3) AR 2023-4337; Indications of Partial Discharge on 12AB Loop Feed Enclosure on July 17, 2024
- (4) AR 2024-5322; 2-HV-AFP-T2AC is not working properly on July 17, 2024
- (5) AR 2024-6357; Work Order Generation for 2-IMO52 Repack on August 20, 2024
(Partial)
AR 2024-6650; Ice Bed Temperature Following Glycol Restoration on September 19, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)12 AB loop feed enclosure temp modifications on July 17, 2024
- (2) Unit 1 TDAFP temporary modifications on July 17, 2024 (3)1-DCR205 temporary modifications on July 18, 2024
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) (9 Samples)
(1)2-QRV251 following packing leak on July 11, 2024 (2)2W component cooling water PMT following planned work on July 18, 2024 (3)east diesel driven fire pump PMT following planned work window on July 30, 2024 (4)2N safety injection (SI) pump PMT following planned work on July 30, 2024 (5)supplemental diesel generator on August 14, 2024 (6)1-BATT-AB Cell 114 replacement on August 26, 2024
- (7) CEQ fan tripping on September 18, 2024
- (8) AB loop feed enclosure PMT on September 24, 2024 (9)2-WMO716, west containment spray heat exchanger essential service water inlet valve on September 27, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)2W residual heat removal (RHR) operability test on August 19, 2024 (2)2AB EDG monthly surveillance run on August 20, 2024 (3)2W MDAFP surveillance run on September 12, 2024
- (4) Unit 1 main turbine valve functional testing on September 13, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2 west charging pump operability test on July 29, 2024
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) FLEX diesel testing on September 13, 2024
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the following maintenance and testing of the alert and notification system:
- The inspectors reviewed the FEMA-approved Design Report and assessed the adequacy of Berrien County, Michigans performance of the test and maintenance activities associated with the approved Integrated Public Alert and Warning System (IPAWS) alert and notification system.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the Emergency Preparedness Program.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) hostile action-based drill on September 24,
RADIATION SAFETY
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
Groundwater Protection Initiative (GPI) Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the GPI program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Dry Active Waste Building
- (2) Radioactive Material Building
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Cask Dewatering Area in 587' Drumming Room
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste: (1)2022 Dry Active Waste (2)2023 Primary Filters (3)2022 Primary Resins
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment DCC24-048, Surveillance Coupon, UN2915 Type A package
- (2) Shipment DCC24-030, Dry Active Waste, UN3321
- (3) Shipment DCC23-015, Primary Resin, UN3321 LSA-II, RQ
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (April 1, 2023, through March 31, 2024)
- (2) Unit 2 (April 1, 2023, through March 31, 2024)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2023, through June 30, 2024)
- (2) Unit 2 (July 1, 2023, through June 30, 2024)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2023, through June 30, 2024)
- (2) Unit 2 (July 1, 2023, through June 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (April 1, 2023, through March 31, 2024)
- (2) Unit 2 (April 1, 2023, through March 31, 2024)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (September 1, 2023, through June 30, 2024)
- (2) Unit 2 (September 1, 2023, through June 30, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 1, 2023, through June 30, 2024 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) September 1, 2023, through June 30, 2024
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1, 2022, through June 30, 2024.
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2022, through June 30, 2024.
EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) Sirens are not part of the sites primary ANS. ANS will be inspected via IP 71114.02.
===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Samples 1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)turbine trip for steam leak on July 15, 2024 (2)indication of partial discharge on 12AB loop feed enclosure on August 1, 2024 (3)
(Partial) damage to the rod cluster control assembly in Unit 2 outage on August 12, 2024 71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)===
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) LER 2024-001-00 for Donald C. Cook Nuclear Plant, Unit 2, Reactor Trip due to Main Turbine Trip from a High-High Thrust Bearing Position Trip, 05000316/2024-001-00 (ADAMS Accession No. ML24141A120). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an ISFSI Operation of an ISFSI
- (1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loading activities from August 19 through August 23, 2024. Specifically, the inspectors observed the following activities during the loading of cask No. 65:
- fuel loading
- heavy load movement of loaded multi-purpose canister (MPC) out of the spent fuel pool
- closure welding and non-destructive evaluations
- forced helium dehydration
- stack-up and download of the MPC from the transfer cask into the storage cask
- radiological field surveys The inspectors performed walkdowns of the ISFSI pad and haul path, which also included performing independent radiation surveys.
The inspectors evaluated the following:
- spent fuel selected for loading into dry cask storage during this loading campaign
- selected corrective action program documents
- selected 72.48 screenings
- changes to the sites 10 CFR 72.212 report since the previous inspection
INSPECTION RESULTS
URI (Discussed)
Safety-Related Motor Control Center Bus Bar Commercial Grade Dedication URI 05000316,05000315/2023011-01 71111.21N.03
Description:
The NRC continued to evaluate the unresolved item documented in inspection report 2023011-01 (ADAMS Accession Number ML23233A187) related to the commercial grade dedication activities for a motor control center bus bar. The inspectors requested additional information related to the issues of concern and plan to review it to determine whether any performance deficiencies or violations exist.
Enforcement Discretion Enforcement Action EA24-078: Failure to Comply with 10 CFR Part 37 71124.08
Description:
On November 15, 2016, the licensee was issued NRC Inspection Report Nos.
05000315/2016404 and 05000316/2016404, which documented a licensee-identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program. The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52.
Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for Enforcement Discretion established within Section 9.3 of the NRC Enforcement Policy.
Corrective Actions: As specified in NRC Enforcement Policy, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action. Additional corrective actions are not required.
Corrective Action References: Not Applicable
Enforcement:
Violation: On November 15, 2016, a violation of 10 CFR Part 37 was documented in Donald C. Cook Inspection Report Nos. 05000315/2016404 and 05000316/2016404. The inspectors determined that the previously identified violation remains.
Basis for Discretion: This violation met the criteria for Enforcement Discretion as described in Section 9.3 of the NRC Enforcement Policy Enforcement Discretion for Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material.
Failure to Implement Design Control Process Causes Main Turbine Trip Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000315,05000316/2024003-01 Open/Closed None (NPP)71153 A self-revealed finding of very low safety significance (Green) was identified with the licensees failure to implement a modification to a turbine supervisory instrumentation (TSI)card. Specifically, the licensee failed to correctly implement a modification to the turbine protection system, leading to incorrect inputs included into the turbine trip circuit which, led to a main turbine trip and subsequent reactor trip.
Description:
On March 22, 2024, the Unit 2 main turbine tripped due to a main turbine thrust bearing trip condition, which led to an automatic trip of the Unit 2 reactor. The thrust bearing trip signal is designed to trip the main turbine if a thrust bearing wear condition is sensed on the turbine and is fed by a 2-out-of-2 logic trip input from thrust bearing probes A and B. Directly prior to the trip, probe B had spiked above the high alarm setpoint while probe A remained normal.
The licensee investigated the alarm and determined the momentary indication was most likely an indication of probe failure or a bad driver and recommended bypassing the alarm.
Approximately a minute later, probe B spiked high again (with probe A still reading normal),this time above the trip setpoint, inputting one of two trip inputs required for the trip signal.
Despite only having one of the two designed inputs for a trip, the Unit 2 main turbine still tripped.
Licensee investigation revealed the cause to be during implementation of engineering change EC00000047291, which modified a TSI card. This card is connected to the thrust bearing probes, with additional probes used to monitor various other trip conditions. In 2007, the main turbine thrust bearing trip was incorrectly set to monitor all probes on the TSI card instead of only the thrust bearing probes, allowing a 2-out-of-all logic trip input for the trip signal. At the time of the trip, vibration probe 1X on the TSI card showed bad quality (interpreted by the logic as failed or above setpoint), which input one of two trip inputs required for the trip signal. When thrust bearing probe B exceeded the trip setpoint, the second required trip input was met, signaled a trip, and caused the main turbine to trip and subsequent reactor trip.
Corrective Actions: The licensee took immediate corrective actions to remove the incorrect inputs for the thrust bearing trip, replaced the TSI card associated with the main turbine thrust bearing probes, and replaced probe B. Planned corrective actions going forward will be replacement of the remaining probes.
Corrective Action References: AR 2024-2321 Unplanned reactor/turb trip due to thrust bearing high vibe AR 2024-2318 MT TSI TP2 High vibes
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensees failure to implement a modification to a TSI card was contrary to EC0000047291 and was a performance deficiency.
Specifically, the licensee included additional probes into the thrust bearing trip function of the TSI card, which altered the trip logic.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the failure to use adequate design control resulted in an automatic reactor trip.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that this finding is of very low safety significance (Green) because they answered No to Exhibit 1, Section B, Transient Initiators screening question.
Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 8, 2024, the inspectors presented the integrated inspection results to Q. S. Lies, Executive Vice President and Chief Nuclear Officer, and other members of the licensee staff.
- On July 11, 2024, the inspectors presented the radiation protection inspection results to Q. S. Lies, Executive Vice President and Chief Nuclear Officer, and other members of the licensee staff.
- On July 26, 2024, the inspectors presented the emergency preparedness inspection results to L. Ellis, Plant Manager, and other members of the licensee staff.
- On August 23, 2024, the inspectors presented the ISFSI cask loading inspection results to M. Scarpello, Director of Regulatory Compliance and Licensing, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
SD220712-001
Evaluation of ISFSI Pad Settlement Survey
AR 2021-6205
Dry Cask Personnel Did Not Follow Written Instructions
07/15/2021
AR 2021-7151
Dry Cask - Welding Interpass Temperature Not Monitored
08/17/2021
AR 2022-4965
Possible Degradation of Sheave Bearing on 12-QM3E
06/06/2022
AR 2024-0560
Elevated ISFSI Cask Delta T
01/20/2024
AR 2024-2987
Deficiencies Found during Monthly Dry Cask Inspection
04/07/2024
Corrective Action
Documents
AR 2024-3469
2-QM80 Cable Deterioration Observed
04/19/2024
Corrective Action
Documents
Resulting from
Inspection
AR 2024-6459
WOs for East Aux Building Crane (12-QM3E) Need
Updating
08/22/2024
DC Cook Dry Cask Loading Campaign #5
Engineering
Evaluations
NFG-DCO23-01
Decay Heat Calculations to Support Dry Cask Storage
Campaign #5 (Summer 2024)
2.48 Tracking
No.: 2021-0188-
Incorporation of Holtec Engineering Change Order (ECO)
5014-132
10/18/2021
2.48 Tracking
No.: 2021-0203-
Addition of 69kV-12kV Transformer #10
01/18/2022
2.48 Tracking
No.: 2022-0037-
The 72.212 Evaluations Report and Regulatory Compliance
Report are Being Updated
03/28/2022
2.48 Tracking
No.: 2024-0004-
Update of the 10 CFR 72.212 Evaluations Report to Address
the NRC Approved Changes for the Renewed Certificate(s)
of Compliance and Associated HOLTEC FSAR(s)
01/23/2024
2.48 Tracking
No.: 2024-0043-
Transport Operations
04/21/2024
60855
Miscellaneous
2.48 Tracking
No.: 2024-0048-
MPC Preparation for Loading Transfer Operations
04/26/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2.48 Tracking
No.: 2024-0052-
MPC Loading Operations
05/22/2024
2.48 Tracking
No.: 2024-0062-
05/30/2024
2.48 Tracking
No.: 7248-2022-
0116-00
DC Cook Dry Cask Loading Campaign #5
10/19/2022
NDE Reports
20422-967-04
GQP-9.2 Liquid Penetrant Examination Report
08/21/2024
EHP SP.045
Ultrasonic Testing of Unit 1 Fuel for Cycle 14 Reload
EHP SP.048
Unit 1 In-Mast Fuel Sipping
2-EHP-4051-
DCO-300
Fuel Selection and Sequence Development for Dry Cask
Storage
2-OHL-4030-
SOM-009
Unit 12 Tours - ISFSI
2-OHP-4051-
DCO-300
MPC Loading Operations
2-OHP-4051-
DCO-400
MPC Welding, Blowdown, Drying and Backfill
2-OHP-4051-
DCO-500
Transfer Operations
MHI-5025
Control and Inspection of Rigging and Lifting Equipment,
Data Sheet 20, Annual Rigging and Lifting Inspection
Record
PMP-2350-SES-
2
CFR 72.48 Reviews
Procedures
PMP-5020-MHP-
001
Lifting and Rigging Program
CNP-2405-00110
Semi-Annual ISFSI Pad Survey
05/29/2024
Radiation
Surveys
SW_VSDS-M-
210807-2
Neutron Dose Rate Survey for Comparison of Meters
08/07/2021
GT 2023-8773
NRC ISFSI Inspection
05/09/2024
Self-Assessments
NOS-21-03
Nuclear Oversight Audit: Spent Fuel Storage
10/11/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
55565828-48
Perform DCO-805 Special Lifting Device Inspections
05/01/2024
C10044660001
MTE (12-QM-3E) Perform Inspection/Maintenance
2/12/2023
C10044660003
MTM: 12-QM-3E Perform Inspections and Maintenance
2/14/2023
Work Orders
C10070699001
MTM: 12-QM-3E, Perform Monthly Mechanical Crane
Inspection
06/06/2024
OP-1-5151A-51
Flow Diagram Emergency Diesel Generator AB Unit No. 1
07/15/2021
OP-1-5151B-65
Flow Diagram Emergency Diesel Generator AB Unit #1
04/15/2024
OP-2-5135-40
Flow Diagram CCW Pumps and CCW Heat Exchangers
11/14/2022
OP-2-5142
Flow Diagram Emergency Core Cooling (SIS)
10/19/2022
Drawings
OP-2-5151D-71
Flow Diagram Emergency Diesel Generator CD Unit No. 2
07/13/2021
1-OHP-4021-032-
008AB
Operating DG1AB Subsystems - DB1AB Fuel Oil System
Valves
1-OHP-4021-032-
008CD
Operating DG1CD Subsystems
1-OHP-4030-156-
017E
East MDAFP Valve Lineup
1-OHP-4030-156-
017E
East MDAFP Valve Lineup
2-OHP-4021-008-
2
Placing Emergency Core Cooling System in Standby
Readiness
036
2-OHP-4021-032-
008CD
Operating DG2CD Subsystems
2-OHP-4030-208-
053V
E.C.C.S. Valve Position Verification
009
2-OHP-4030-216-
20E
Unit Two East CCW Loop Flow Path Verification
2-OHP-4030-216-
20W
Unit Two West CCW Loop Flow Path Verification
Procedures
2-OHP-4030-256-
017T
Turbine Driven Auxiliary Feedwater System Test
Fire Plans
Fire Pre-Plans Volume 1
D.C. Cook Nuclear Plant Fire Safety Analysis (FSA)
Revision 5
08/11/2021
Miscellaneous
24-009-A
Fire Drill
08/15/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PRA-FLOOD-004
Internal Flooding - Qualitative Screening Analysis
PRA-FLOOD-007
Floor Drains Capacity
PRA-FLOOD-008
Flood Sources and the Associated Flood Mechanisms
Calculations
PRA-FLOOD-014
Internal Flood Detailed Analysis
Procedures
RQ-E-4903-U2
Licensed Operator Requalification Training Scenario
08/06/2024
2019-9540
As-Found LLRT Failure of Both 2-CCW-244-25 and
2-CCW-243-25
10/07/2019
21-10369
CCW-05 Maintenance Rule (a)(1) Consideration
2/22/2021
21-3313
As-Found LLRT of 2-CCW-244-25 Was Unable to be
Pressurized
04/20/2021
21-8634
SML-78 Drop 75 (C-9 Status Light) Not Lit
10/19/2021
21-9413
MRule Reliability Criteria for Function MS-09 Exceeded
11/17/2021
22-3634
Open & Inspect CCW Contain Isolation Valves on Unit 2
04/26/2022
22-5260
Sparge/Flush the Component Cooling Water Hx in U2C28
06/20/2022
23-7589
1-CCW-243-25 LLRT Failed
10/18/2023
24-2445
2-CCW-244-72 Gross LLRT Failure
03/26/2024
24-2448
2-CCW-243-25 Gross LLRT Failure
03/26/2024
Corrective Action
Documents
24-2450
2-CCW-244-25 Gross LLRT Failure
03/26/2024
Cook Nuclear Plant Excellence Plan Indicator CNP.142
Number of (a)(1) Systems, Unit 1, Unit 2 and Common
07/2024
Maintenance Rule Scoping Document; Component Cooling
Water
Miscellaneous
Maintenance Rule Scoping Document; Main Steam System
Procedures
2-OHP-SP-475
Risk Management for LCO 3.8.1 Entry during AB Loop Feed
Modification
09/09/2024
23-4337
Indications of Partial Discharge on 12AB Loop Feed
06/08/2023
23-9079
1-IMO-255 10 dpm Packing Leak
11/30/2023
24-4592
2-HV-AFP-T1AC Will Not Run
05/26/2024
24-5371
FLEX Blended RCS Pump Out of Service
07/01/2024
24-5435
1-DCR-205 Failed IST Stroke Time
07/04/2024
24-6357
Work Order Generation for 2-IMO-52 Repack
08/19/2024
Corrective Action
Documents
24-6650
Ice Bed Temperature Following Glycol Restoration
08/30/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2024-5322
2-HV-AFP-T2AC is Not Working Properly
06/28/2024
AR 2024-6986
Use of Local Tachometer for EDG Surveillance
09/17/2024
Miscellaneous
OHI-4032
Leakage Monitoring Program Cumulative Leak Rate Data
Log
2/07/2023
1-OHP-4030-114-
011
RCDT and Containment Sumps Valve Test
EHI-5072
ECCS Recirculation Leakage Reduction Program
OHI-4032
Leakage Monitoring Program
21
PMP-4030-001-
001
Impact of Safety Related Ventilation on the Operability of
Technical Specification Equipment
Procedures
PMP-7030-OPR-
001
22-5345
Evaluate TDAFP Room Cooler Performance
06/23/2022
22-5373
U1 TDAFP Room Cooler 1-HV-T1AC Not Working Correctly
06/24/2022
22-5375
U1 Unexpected CR Alarm for TDAFP Room Coolers
06/25/2022
22-6759
MRE Needed on U1 TDAFP Room Cooler Conditions
23-8396
Create WO to Replace 1-HV-AFP-T1AC
11/06/2023
Corrective Action
Documents
24-2805
2-DCR-205 Blown Diaphragm
04/02/2024
DWWO 2022-
8603
1-HV-AFP-T1AC Replace Cooler Unit
07/28/2022
Miscellaneous
GT 2022-10244
Risk Tracking for 1/2-DCR-205-206 and 1-VCR-11/21
2/20/2022
Corrective Action
Documents
24-6974
Light Not Lit on 2-HV-CEQ-1 Control Switch
09/17/2024
1-OHP-4030-114-
031
Breaker Alignment
09/23/2024
1-OHP-5030-050-
001
Main Turbine and Feed Pump Turbine Valve Functional
Checks
09/14/2024
2-MHP-5021-
033-001
Supplemental Diesel Generator Maintenance
005
2-OHP-4030-
033-01
Supplemental Diesel Generator Testing - SDG Quarterly
Surveillance
Procedures
2-OHP-5030-
FSG-421
FLEX 500 kW DG Functional Test
09/11/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-OHP-5030-
FSG-422
FLEX 250/350 kW DG Functional Test
09/11/2024
2-OHP-5030-
FSG-423
09/11/2024
2-OHP-4030-203-
2W
West Centrifugal Charging Pump Operability Test
2-OHP-4030-214-
031
Breaker Alignment
09/24/2024
2-OHP-4030-217-
050W
West Residual Heat Removal Train Operability
Test Modes 1-4
08/15/2024
2-OHP-4030-256-
017W
West Motor Driven Auxiliary Feedwater System Test
09/13/2024
2-OHP-4030-
STP-017W
West Motor Driven Auxiliary Feedwater System Test
OHI-4016
Conduct of Operations: Guidelines IST Valve Operability
After Maintenance
C10054830 001
MTM, 12-OME-250-SDG1, Annual Maintenance
(Vendor/MT)
08/06/2024
C10055989002
2-WMO-716 Full PM
07/22/2024
C10062773 001
MTM, 12-OME-250-SDG2, Annual Maintenance (Vendor)
08/06/2024
C10062959024
1-BATT-AB Replace Cell 114
08/21/2024
C10071943004
MTI, 2-QRV-251, Reinstall Instr, A/L Diagnostics
06/28/2024
C10076413-001
MTE: 2-HV-CEQ-1 (2-152-CEQ1) Replace Back Up Breaker
09/17/2024
Work Orders
C10076413-003
2-HV-CEQ-1: 2-IHP-4030-228-005B - Post Maintenance
Test
09/17/2024
AR 2022-6301
Loss of Federal IPAWS System
08/05/2022
Corrective Action
Documents
AR 2024-1557
Nationwide Cell Phone Outage
2/22/2024
Miscellaneous
FEMA Design
Report
Alert and Notification System Evaluation Report
01/01/2021
Self-Assessments NOS-24-02
Nuclear Oversight Audit NOS-24-02, Emergency
Preparedness
04/11/2024
AR 2024-1487
Evidence of EP-I-ERO Training Not Documented
(NOS-24-02)
2/20/2024
Corrective Action
Documents
AR 2024-2141
ARM-24-03-01, EP Training and Qualification
03/19/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
N/A
ERO Staff Training Records: 25 Records
Various
Procedures
ERO On-Shift Staffing Analysis Report
2/09/2019
Calculations
KLD TR - 1409
Donald C. Cook Nuclear Plant 2024 Population Update
Analysis
06/12/2024
Corrective Action
Documents
AR 2022-9770
PARs Not in Accordance With Drill Manual
11/30/2022
Procedures
N/A
DC Cook Emergency Plan
Rev. 49
Cook Work
Practices
Evaluation SRA
Work Practice Evaluation for GPI Implementation at Cook
Calculations
Risk Evaluations
Systems, Structures, and Components Site Risk
Assessment
AR 2022-10270
REMP Air Station Loss of Power Documentation for the
Annual
2/21/2022
AR 2023-0575
2-THP-6010-RPP-601 and Tech Spec 5.5.1c.3 Compliance
Issue
01/19/2023
AR 2023-2224
REMP TLD at Location OFT11 Lost
03/16/2024
Corrective Action
Documents
AR 2024-3218
NBF REMP Air Sample Unavailable
04/10/2024
ENVI-8916-GPI-
001
Groundwater Protection Program
Land Use Census
22
Radiological Environmental Monitoring Program Land Use
Census Summary
09/30/2022
Miscellaneous
Land Use Census
23
Radiological Environmental Monitoring Program Land Use
Census Summary
09/30/2023
2-THP-6010-
RPP-630
Collection of REMP Surface Water Sample
2-THP-6010-
RPP-634
Collection of REMP Groundwater Samples
Procedures
PMP-6010-OSD-
001
Off-Site Dose Calculation Manual
GT 2021-10170-1
Self-Assessment Report for the Radiological Environmental
Monitoring Program (REMP)
21
Self-Assessments
GT 2023-8764 - 1
Self-Assessment Report for the Radiological Environmental
23
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Monitoring Program (REMP)
Calculations
RPC/TB RP-16-
CPR Part 37 Category 1 and Category 2 Quantity
Determination
09/06/2016
AR 2024-1644
CFR 61 Scaling Factor Data - 2022, Data Entry Error
2/27/2024
Corrective Action
Documents
AR 2024-3186
Vehicle Inspection Check off Sheet Tire Inspections
06/30/2024
Corrective Action
Documents
Resulting from
Inspection
AR 2024-5469
Part 37 Annual Review
07/08/2024
CFR 61
Scaling Factor
Data - 2022
CFR 61 Scaling Factor Data - 2022
Not Provided
CFR 61
Scaling Factor
Data - 2023
CFR 61 Scaling Factor Data - 2023
Not Provided
2-THP-6010-
RPP-011 Data
Sheet 2
Radioactive Source Leak Test Record
05/20/2024
Lesson Plan GP-
I-AIND
10CFR37 Approved Individual
Cook Nuclear Plant Indiana and Michigan Power Part 37
Security Plan for the Protection of Category 1 and
Category 2 Quantities of Radioactive Material
Miscellaneous
SPP-2060-SFI-
217
Protection of Category 1 and Category 2 Quantities of
Radioactive Material
2-THP-6010-
RPP-011
Radioactive Source Control
2-THP-6010-
RPP-913
Scaling Factor Determination
2-THP-6010-
RPP-917
CFR Part 37 Material Accountability Program
Procedures
PMP-6010-PCP-
900
Radioactive Waste Process Control Program
Procedures
PMP-6010-PCP-
901
Shipment of Radioactive Materials and Waste
GT 2023-0671
Perform the Annual Part 37 Security review for 2023
11/15/2023
Self-Assessments
GT 2023-8765-1
Radiation Protection Radwaste Program
06/06/2024
DCC23-015
Primary Resin
05/23/2023
DCC24-030
Dry Active Waste
04/10/2024
Shipping Records
DCC24-048
Surveillance Capsule S
06/11/2024
C10027792002
Received Leak Check Counting Data
11/22/2022
C10043544001
RP Perform Source Leak Checks
06/05/2023
Work Orders
C10054043002
Received Leak Check Counting Data
11/20/2023
EPP-2080-ERO-
300
Emergency Preparedness Performance Indicators
Performance Indicator Verification
04/01/2022
through
06/30/2024
PMP-7110-PIP-
001
Reactor Oversight Program Performance Indicators and
Monthly Operating Report Data Sheets and MSPI Derivation
Sheets (High Pressure Injection Systems and Cooling Water
Systems; April 2023 through March 2024)
PMP-7110-PIP-
001
Reactor Oversight Program Performance Indicators and
Monthly Operating Report Data Sheets and MSPI Derivation
Sheets (Heat Removal System (AFW) and Residual Heat
Removal System; July 2023 through June 2024)
PMP-7110-PIP-
001 Data Sheet
Reactor Coolant System Specific Activity
Multiple
PMP-7110-PIP-
001 Data Sheet
Occupational Exposure Control Effectiveness
Multiple
71151
Miscellaneous
PMP-7110-PIP-
001 Data Sheet
RETS/ODCM Radiological Effluent Occurrences
Multiple