ML25223A266
| ML25223A266 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/11/2025 |
| From: | Sanchez-Santiago E NRC/RGN-III/DORS/RPB2 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2025002 | |
| Download: ML25223A266 (1) | |
Text
Peter Dietrich Senior VP and Chief Nuclear Officer DTE Electric Company Fermi 2 - 260 TAC 6400 North Dixie Highway Newport, MI 48166
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2025002
Dear Peter Dietrich:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On July 10, 2025, the NRC inspectors discussed the results of this inspection with C. Domingos, Site Vice President, 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 Fermi Power Plant, Unit 2.
August 11, 2025
P. Dietrich 2
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, Elba M. Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket No. 05000341 License No. NPF-43
Enclosure:
As stated cc: Distribution via LISTSERV Signed by Sanchez Santiago, Elba on 08/11/25
P. Dietrich 3
Letter to P. Dietrich from E. Sanchez Santiago dated August 11, 2025.
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2025002 DISTRIBUTION:
Tim Steadham RidsNrrDorlLpl3 RidsNrrPMFermi2 Resource RidsNrrDroIrib Resource Jack Giessner Mohammed Shuaibi Diana Betancourt-Roldan John Pelchat Jared Heck Jennifer Dalzell R3-DORS ADAMS Accession Number: ML25223A266
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII RIII NAME RNg:gmp ESanchezSantiago DATE 08/11/2025 08/11/2025 OFFICIAL RECORD COPY
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000341 License Number:
NPF-43 Report Number:
05000341/2025002 Enterprise Identifier:
I-2025-002-0051 Licensee:
DTE Electric Company Facility:
Fermi Power Plant, Unit 2 Location:
Newport, MI Inspection Dates:
April 01, 2025 to June 30, 2025 Inspectors:
J. Gewargis, Resident Inspector T. Hooker, Health Physicist E. Kokkinis, Resident Inspector R. Ng, Senior Project Engineer T. Taylor, Senior Resident Inspector Approved By:
Elba M. Sanchez Santiago, Chief Reactor Projects Branch 2 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Fermi Power Plant, Unit 2, 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 Reactor Water Cleanup System Piping Rupture Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000341/202500201 Open/Closed None (NPP) 71152S A self-revealed Green finding was identified when the licensee failed to follow procedure MES26, Flow Accelerated Corrosion Prediction, Detection, and Correction. Specifically, a component was modeled incorrectly and operating experience/noted off-normal conditions were not utilized when selecting components for examination.
Additional Tracking Items None.
3 PLANT STATUS Unit 2 began the inspection period at rated thermal power. On May 4, 2025, a planned power reduction to approximately 86 percent power was made for a routine rod pattern adjustment.
Power was restored to 100 percent later on May 4, 2025. On June 13, 2025, a planned power reduction to approximately 70 percent was made for a routine rod pattern adjustment and surveillances. Power was restored to 100 percent on June 15, 2025. The plant remained at 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 onsite 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)
Division 2 emergency equipment cooling water (EECW) during emergency diesel generator (EDG) 11 maintenance window, completed the week ending April 12, 2025 (2)
EDG 14 during EDG 11 maintenance window, completed the week ending April 19, 2025 (3)
Division 1 residual heat removal (RHR) system, completed the week ending June 14, 2025 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)
EDG 14 engine room, completed the week ending April 19, 2025 (2)
Division 2 residual heat removal service water (RHRSW) pump room, completed the week ending April 19, 2025 (3)
Auxiliary building cable spreading room, completed the week ending May 31, 2025
4 (4)
Auxiliary building relay room, completed the week ending May 31, 2025 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on the week ending April 26, 2025 71111.06 - Flood Protection Measures Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections in the: division 1 and division 2 switchgear rooms, direct current (DC) switchgear area, auxiliary building ventilation equipment areas, and division 1 and division 2 control room air conditioning rooms during the week ending April 26, 2025 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 down power on June 13, 2025 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated training in the control room simulator associated with loss of phase for an offsite AC source, and loss of all AC power during the week ending June 15, 2025 71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
Scheduling and execution of combustion turbine generator (CTG) 111 maintenance activities in accordance with technical requirements, completed the week ending May 31, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
5 (1)
Planned EDG 12 safety system maintenance outage, completed the week ending May 10, 2025 (2)
Unplanned inoperability of division 1 control center heating, ventilation, and cooling system during planned division 2 RHR/RHRSW maintenance outage, completed the week ending May 17, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
Reactor coolant system (RCS) and fuel cladding following reactor water cleanup system rupture and chemistry transient, completed the week ending May 3, 2025 (2)
Diesel fire pump (DFP) with coolant leak, completed the week ending May 17, 2025 (3)
EDG 13 starting air pressure drop, completed the week ending May 24, 2025 (4)
Failure of division 2 RHR system minimum flow valve to function during a surveillance, completed the week ending May 24, 2025 (5)
High pressure cooling injection (HPCI) turbine control valve pin shear, completed the week ending June 14, 2025 (6)
Review of site response to industry issue documented in condition report (CR)-202546350, regarding control rod drive (CRD) collet retainer tube cracking, completed the week ending June 14, 2025 71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
(1)
EDG 11 maintenance outage, completed the week ending April 12, 2025 (2)
Standby liquid control (SLC) pump operability test after SLC pump B seal maintenance, completed the week ending April 19, 2025 (3)
EECW division 1 pump and valve operability test after maintenance outage, completed the week ending May 10, 2025 (4)
Piping repair following leak from reactor water cleanup system, completed the week ending May 17, 2025 (5)
EDG 12 maintenance outage, to include review of foreign materials exclusion (FME) intrusion into engine, completed the week ending May 17, 2025 Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
EDG 14 slow start and load surveillance, completed week ending June 14, 2025 (2)
SLC pump overload testing, completed the week ending June 27, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Reactor core isolation cooling (RCIC) system pump operability and valve test, completed the week ending May 10, 2025
6 RADIATION SAFETY 71124.03 - InPlant Airborne Radioactivity Control and Mitigation Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1)
Standby gas treatment filtration system Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
(1)
The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.04 - Occupational Dose Assessment Source Term Characterization (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the following internal dose assessments:
(1)
Dose assessments for four workers exposed to contamination during a job in the torus on April 10, 2024 Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
(1) declared pregnant worker dose assessment performed from 2024 through 2025 (2)
Effective dose equivalent for external radiation exposure assessments performed in 2024 OTHER ACTIVITIES-BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
7 MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
(1)
April 1, 2024 through March 31, 2025 MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
(1)
April 1, 2024 through March 31, 2025 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
(1)
October 1, 2024, through March 31, 2025 BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
(1)
April 1, 2024 through March 31, 2025 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
October 1, 2024, through March 31, 2025 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, 2024, through March 31, 2025 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program to identify potential trends in the licensee's flow accelerated corrosion program that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow Up (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated systems and operator response to an unplanned isolation of the reactor water cleanup system following a pipe rupture, completed the week ending April 26, 2025
8 INSPECTION RESULTS Reactor Water Cleanup System Piping Rupture Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000341/202500201 Open/Closed None (NPP) 71152S A self-revealed Green finding was identified when the licensee failed to follow procedure MES26, Flow Accelerated Corrosion Prediction, Detection, and Correction. Specifically, a component was modeled incorrectly and operating experience/noted off-normal conditions were not utilized when selecting components for examination.
==
Description:==
On April 20, 2025, while attempting to place the 'A' reactor water cleanup (RWCU) filter/demineralizer in service, multiple alarms and indications were received indicating a rupture in the RWCU system. Safety-related systems responded appropriately to the rupture, isolating the RWCU system from the reactor via the associated containment isolation valves.
Temperature within the RWCU heat exchanger room became elevated, but remained below thresholds necessitating entry into the emergency operating procedures. The RWCU pumps tripped off by design. Between the initial rupture and a controlled pressurization of the system to help identify the leak location, areas immediately adjacent to the RWCU heat exchanger room on the second floor of the reactor building became highly contaminated with water flowing out of the room, along with the north side of the first floor of the reactor building due to leakage from above. Investigation revealed an approximate 1" thru-wall hole in the 4" return piping on the outlet of the regenerative heat exchanger. A four-foot section of pipe containing the hole was replaced, based, in part, on visual and ultrasonic examination of the upstream and downstream piping. During and after restoration of the reactor water cleanup (RCWU) system, some additional consequences of the pipe rupture were identified. For example, demineralizer resin was released into the RWCU system and that upon restoration, was transported into the reactor recirculation system, causing main steam line alarms (which subsequently cleared). The alarm required the operators to take actions to assess whether there was fuel cladding damage, which based on the indications they were able to rule out.
Additionally, a technical requirements manual (TRM) action statement was entered based on pH, conductivity, and chloride concentrations due to the resultant chemistry excursion. While not a chemistry parameter in the TRM, an increase in sulfate levels also led to discussions with industry peers and the fuel vendor regarding impacts to fuel and reactor vessel components. If the chemistry parameters had not returned to normal within the 72-hour TRM completion time a plant shutdown would have been required. Discussions with peers and the fuel vendor concluded there were no threats to continued operation.
A subsequent review by the licensee revealed flow accelerated corrosion (FAC) was the most likely cause of the rupture, pending a formal failure analysis of the pipe. On May 30, 2025, as part of an ongoing inspection sample to review the FAC program for potentially more significant issues, inspectors identified that in 2019, a corrective action document was written documenting abnormally high iron levels in water samples from the return piping of the RWCU system. Reference was made to a history of high conductivity alarms associated with high iron going back to 2011. A technical evaluation was performed, concluding FAC was likely occurring and that certain sections of piping should be inspected in the upcoming refueling outage (RF20-spring 2020). The section of piping from the outlet of the regenerative
9 heat exchanger to sample point 51 (SP51), where the high iron was being detected, was recommended for inspection, among other piping segments. The inspectors determined this segment was particularly notable, in that iron concentrations measured elsewhere were lower, and tended to narrow down the likely location where FAC was occurring. However, the inspection was removed from RF20, with the intention to perform the inspection in a RWCU maintenance outage in September of 2020. This work was never started, as the work order was still in the planning phase as of inspector review. In RF21 (spring 2022), a decision was made based, in part, on dose considerations, to not inspect that segment. Instead, piping was replaced in another segment (also recommended by the technical evaluation for inspection) downstream of SP51 instead of between the regenerative heat exchanger outlet and SP51.
Between RF21 and the rupture, no inspections were performed between the heat exchanger and SP51, nor an updated assessment of the susceptibility of that segment to FAC. Analysis for iron concentrations from SP51 (which had been periodically monitored following the 2019 technical evaluation) ceased in December 2022. Of note, following the downstream piping replacement in RF21, two more samples were taken from SP51 in June of 2022 and December of 2022, both indicating relatively high iron concentrations. A condition report (CR) was written for the June 2022 sample, but it was closed with no action, nor forwarded to engineering for review.
The licensees flow accelerated corrosion program is governed by Procedure MES26, Flow Accelerated Corrosion Prediction, Detection, and Correction. The procedure incorporates industry recommendations for an effective FAC program, and implements one of the aging management programs required by final safety analysis report section B, Aging Management Programs and Activities. In section 3.2. the procedure outlines requirements for identifying program scope and maintaining susceptibly reviews for computer-modeled, and non-modeled, piping. In section 6.3.2, the procedure requires information such as internal and external operating experience, plant operating history, and off-normal operating conditions to be used when selecting which piping to inspect. An equipment cause evaluation performed by the licensee for the rupture concluded system/component monitoring was ineffective at detecting the degradation that led to the rupture. Further, the licensee discovered the 'T' connection just upstream of the rupture was not correctly modeled in the system (socket welds versus the assumed butt welds). Additionally, the 'T' connection contained a thermowell. Both conditions likely raised velocity and turbulence of the RWCU flow, making the immediate downstream area more susceptible to FAC, and rendered the existing modeling non-conservative for predicting wear in that location.
Corrective Actions: The licensee entered the issue into the corrective action program, replaced the affected pipe, and reviewed the program in light of the pipe failure to check for any adjustments needed for upcoming component inspection scope.
Corrective Action References: CR 202547014 Performance Assessment:
Performance Deficiency: Procedure MES26, Flow Accelerated Corrosion Prediction, Detection, and Correction, implements the FAC program at the plant. Contrary to MES26 section 3.2, a susceptibility review, identifying susceptible modeled and non-modeled piping, was not maintained. Specifically, the model assumed the piping joint just upstream of the rupture location was a butt-welded connection versus a socket-welded connection with a thermowell, resulting in a non-conservative corrosion model for the piping. Additionally, as required by MES26 section 6.3.2, the plant's operating history and noted off-normal operating conditions were not utilized in the component examination selection
10 process. Specifically, a 2019 engineering technical evaluation, driven by unusually high iron concentrations in chemistry samples, recommended the piping between the regenerative heat exchanger outlet and SP51 be examined because of FAC concerns. The piping was not examined prior to rupture in 2025. Failing to meet the requirements of MES26 constituted a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance 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 performance deficiency resulted in a high-energy line break in the secondary containment (reactor building), resulting in a containment/reactor isolation of the RWCU system. Further, the rupture caused a pressure wave in the RWCU system, dislodging filter/demineralizer resin into the system and severely clogging a filter used during system warmup and flushing. Ultimately, upon restoration, the resin entered the reactor causing high radiation conditions in the main steam system and alarm response by the operations staff to assess for fuel cladding damage. The resultant chemistry excursion caused entry into a TRM 72-hour shutdown action statement as well, and consultation with the fuel vendor regarding potential impacts of high sulfates on the fuel and reactor components.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, utilizing Exhibit 1, section B, the high-energy line break did not result in a plant scram nor loss of mitigation equipment needed to achieve a stable shutdown condition.
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 July 10, 2025, the inspectors presented the integrated inspection results to C. Domingos, Site Vice President, and other members of the licensee staff.
On May 8, 2025, the inspectors presented the radiation protection inspection results to C. Domingos, Site Vice President, and other members of the licensee staff.
THIRD PARTY REVIEWS The inspectors reviewed a World Association of Nuclear Operators report that was issued to the site during the inspection period.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 6M7215357 Emergency Equipment Cooling Water System Division II 77 Drawings 6M7215734 Emergency Diesel Generator System Functional Operating Sketch 68 23.127 Reactor Building Closed Cooling Water/Emergency Equipment Cooling Water System 153 23.205 Att. 1A Division I RHR Initial Valve Lineup 0
23.205 Att. 8A Division I RHR LPCI Standby Lineup Verification 0
Procedures 23.307 Emergency Diesel Generator System 139 71111.04 Work Orders 69156730 Perform 24.307.17 Sec-5.1 EDG 14 Start and Load Test -
Slow Start 06/09/2025 FPAB28 Relay Room, Zone 8, Elevation 613'6" 7
FPAB2M11 Auxiliary Building, Cable Spreading Room, Zone 11, Elevation 630' 5
FPRHR114EDG RHR Complex, EDG 14 Room, El. 590'0" 6
FPRHR151 RHR Complex, Division II Pump Room Zone 51, El. 590'0" 5
LPFP9402321 Fire Drill/Evaluation 2
71111.05 Procedures MOP10001 Fire Brigade Drill Record Form 5
EF2PRA011 Internal Flood Walkdown Summary Notebook 0
71111.06 Engineering Evaluations EF2PRA012 Internal Flood Analysis Notebook 4
Miscellaneous SSOP2022464 License Operator Requalification Simulation Lesson Plan 0
71111.11Q Procedures 22.000.03 Power Operation 25% to 100% to 25%
109 CR202436104 CTG 111 Failed to Achieve Base Load and Failed PMT 02/05/2024 Corrective Action Documents CR202441956 Standby Diesel Generator (Aggreko) Output Voltmeter Reading Extremely Low 09/02/2024 Miscellaneous 1527331 R1100 Get Well Plan 17 MMR APP D Guidelines For Determining Fictional Failures (FFs) and Maintenance Preventable Functional Failures (MPFFs) 22 MMR APP E Maintenance Rule SSC Specific Functions 27 71111.12 Procedures MMR APP F Maintenance Rule Performance Criteria 27 71111.13 Engineering Evaluations TEE1108078 Removal of RHR Complex Pump Room Roof Plugs Under LCO 3.0.9 F
12 Inspection Procedure Type Designation Description or Title Revision or Date Miscellaneous Shift Manager Daily Alignment Meeting Package 05/13/2025 MMR APP H Maintenance Rule Conduct Manual OnLine Core Damage Risk Management Guidelines 18 MMR12 Maintenance Rue Conduct Manual Equipment Out of Service Risk Management 20A ODE20 Protected Equipment 31 Procedures ODE20, ATT. 17 Protected Equipment Form EDG 12 Safety System Outage 31 Calculations DC6336 Vol 1 EDG Starting Air System Sizing Basis B
1224680 Self-Assessment Finding: Non-Conservative EDG Starting Air Operability Criterion 05/24/2012 2023976 Control Rod 1031 Failed to Withdrawal 09/09/2023 2323185 Pert 21 60Day Interim Report Notification: Failure of the CRD Collet Retainer Tube/Outer Tube Weld (SC2301) 04/28/2023 CR202440147 Control Rod 2227 Difficult to Move 06/12/2024 CR202443587 Control Rod 2227 Difficult to Move 11/09/2024 CR202444216 Coolant Leak from Diesel Fire Pump 12/092024 CR202535153 Diesel Fire Pump Needs Coolant Topped Off 03/12/2025 CR202545556 Tie Pin for HPCI Control Valve Rod Linkage Broke While Disassembling 02/10/2025 CR202546070 Failure Analysis Findings for HPCI Pilot Valve Pin 03/06/2025 CR202546350 SIL 139 Revision 1, Control Rod Drive Collet Retainer Tube Cracking 03/19/2025 CR202546731 Coolant Leak From Diesel Fire Pump (DFP) 04/07/2025 CR202547132 Numerous MCR Alarms Received After Placing RWCU Pump in Service 04/26/2025 CR202547149 Fuel Warranty Limit Exceeded for Reactor Water Sulfates 04/26/2025 CR202547692 EDG 13 Air Receiver Check Valves Leak By 05/19/2025 CR202547693 EDG 13 Starting Air Pressure Drop > 30 psig During Slow Start Surveillance 24.307.16 05/19/2025 71111.15 Corrective Action Documents CR202547714 Division 2 RHR Min Flow Valve E1150F007B (RHR DIV2 PUMPS 'B' and 'D' MIN FLO MOV) did Not Automatically Open When Securing Torus Cooling 05/20/2025
13 Corrective Action Documents Resulting from Inspection CR202547061 NRC Identified - Coolant Residue on DFP Coolant System Piping 04/23/2025 66336C Gov Control System 10/03/1969 66375 D HPCI DIL Relay Assem-Remove Servo 10/07/1969 6M7212043 Diagram High Press Coolant Injection SYS Barometric CNDR (HPCI) Reactor Building AJ 6M7212083 Diagram Residual Heat Removal (RHR) Division 2 85 Drawings 6M72157082 HPCI Turbine Lube Oil/Control Oil Functional Operating Sketch L
Engineering Changes T13213 Residual Heat Removal System 04/18/2024 9609887 E4101C002 - Servo for Woodward Governor 07/08/1987 Engineering Evaluations FPEE240003 Evaluation of Surveillance Frequencies Extensions for Fire Protection Equipment 1
DBD-E1100 Residual Heat Removal System (RHR)
G EDP37362 RHR and Core Spray Strong Pump/Weak Pump Interaction B
Nuclear Generation Memorandum To: M. Kirschenheiter From: I. Finney; Latent Issue Review:
Control Rod Drive System 02/28/2019 Miscellaneous VMB1160.1
[CONFIDENTIAL] Installation, Operation, and Maintenance Driver Manual 0
35.202.009 HPCI Steam Turbine - General Maintenance 36 35.206.001 RCIC Steam Turbine Maintenance 8
35.206.005 RCIC Turbine Trip Throttle Valve General Maintenance 30 46.202.001 HPCI Turbine Governor Control System Calibration 44 54.000.03 Control Rod Scram Insert Time Test 62 74.000.19 Chemistry Routine Surveillances 27 74.00018 Chemistry Shiftly, 72Hour, and Situational Surveillances 64 76.000.34 Reactor Coolant Analysis 13 Procedures CHS-PRI06 Fermi 2 - Chemistry Specifications 36 71111.15 Work Orders 68147634 Neil Req'd - Clean and Lube External Portions of Control and Stop Valves and Lid 02/06/2025
14 71111.15 Work Orders 950023227 Div 2 RHR Min Flow Valve E1150F007B did Not Auto Open as Expected 05/21/2025 Calculations DC6309 VOL 1 Design-Basis of EDG Fuel Oil and Day Tank Level-Requirements and Setpoints B
1524860 EDG12 2 and 10 Piston/Liners Have Indications of Wear 09/16/2023 202547350 FME Cover Became Entangled in EDG12 Upper Torsional Damper 05/06/2025 CR202546696 Work Will Not Complete As Scheduled 04/04/2025 CR202546737 NQA - Documentation of Inspection Result Per MES83101 of the Coatings for R3000A005 (EDG11 Expansion Tank) 04/07/2025 CR202546745 TDX Time Delay Relay Failed AsFound Testing 04/07/2025 CR2025469793 Significant Wear on EDG 11 and 10 Upper Piston 04/09/2025 CR202547029 Leak in RWCU Heat Exchangers Room 04/20/2025 CR202547053 RWCU HX Room Transient Temperature Excursion of 168F EX Impact Assessment 04/22/2025 CR202547056 RWCU Inspection Results 04/23/2025 Corrective Action Documents CR202547089 G3300F033 RWCU Blowdown FCV Not Operating as Expected 04/24/2025 Drawings 6M7212046 Diagram Reactor Water Clean-Up Reactor Building 65 23.307 Emergency Diesel Generator System 139 24.139.02 SLC Pump and Check Valve Operability Test 52 24.307.14 Emergency Diesel Generator 11 - Start and Load Test 65 71111.24 Procedures 24.307.17 Emergency diesel generator 14 - Start and Load Test 63 24.307.45 Emergency Diesel Generator 11 - Fast Start Followed by Load Reject 21 34.307.001 Emergency Diesel Generators - Inspection and Preventive Maintenance 87 42.139.01 Standby Liquid Control System Associated Isolation Device Test 34 IST Program Description Inservice Testing Program Fourth Ten-Year Interval 4
IST Program Pump Basis Inservice Testing Program for Pumps and Valves Part 12:
IST Program Basis 1
71111.24 Procedures IST Program Relief Requests Inservice Testing Program for Pumps and Valves Part 7:
IST Program Relief Requests 3
15 IST Pump Scope Table Inservice Testing Program for Pumps and Valves Part 3:
IST Pump Scope Table 4
IST Pump Testing Program Inservice Testing Program for Pumps and Valves Part 2:
IST Pump Testing Program 3
MMA11 Post-Maintenance Testing Guidelines 27 MWC10 Work Package Preparation 51 VME81.1 Operations and Maintenance Technical Manual-Emergency Diesel Generators 30 67464736 Inspect Air Start Distributors, Pilot Valves and Springs 04/08/2025 68293649 Perform 24.139.02 SLC Pump and Check Valve Operability Test 04/15/2025 68558615 Perform 24.206.01 RCIC System Pump Operability and Valve Test at 1000 PSIG 05/12/2025 69029447 Perform 42.139.01 SLC Pump "A" Associated Isolation Test Device 06/24/2025 950019607 Perform 24.207.08 SEC5.1 DIV 1 EECW PUMP & VALVE OPERABILITY TEST 05/01/2025 Work Orders 950019686 Leak at RWCU Regenerate HX 04/21/2025 CR202435708 Reactor Services & Radiation Protection Need to Implement Airborne Contamination Mitigation Actions Prior to DW Head and Rx Head Disassembly Activities 01/18/2024 CR202438114 PAPR Failure in HRA/HCA 04/09/2024 CR202444310 RP RET SCBA Qualifications Below Threshold in XX33 12/13/2024 CR202545627 Evaluate the Required Pounds per Square Inch (PSI) of Training SCBA Cylinders 02/14/2025 Corrective Action Documents CR202546076 NQA Audit 250101 Recommendation-Improvement of HEPA Vacuum Issue/Return Log 03/06/2025 MSA Training Certificate of Accomplishments Various Annual SCBA Flow Tests Various 24032703601 Laboratory Report - Compressed Air/Gas Quality Testing 03/27/2024 24102216501 Laboratory Report - Compressed Air/Gas Quality Testing 10/22/2024 25011706504 Laboratory Report - Compressed Air/Gas Quality Testing 01/17/2025 65.000.768 Att 1 MSA FireHawk M7 SCBA Inspection Record Various 71124.03 Miscellaneous 65.000.769 Att 1 MSA AirHawk SCBA Inspection Record Various
16 Miscellaneous u019411 Fermi 2 - Radiation Protection Respirator Qualification Report 04/15/2025 65.000.738 Filling of Breathing Air Cylinders 13 65.000.757 Filling Control Room Emergency Breathing Air System 5
65.000.768 Inspection of MSA FireHawk M7 Self-Contained Breathing Apparatus 8
65.000.769 Inspection of MSA AirHawk Self-Contained Breathing Apparatus 5
65.000.770 Inspection of MSA Ultra Elite AP Respirator 2
Procedures 65.000.771 Inspection of PremAire Cadet Escape Respiratory Equipment 4
71124.03 Self-Assessments NPRP240079 Quick Hit Self-Assessment: NRC Inspection 71124.03-InPlant Airborne 12/13/2024 Calculations 24006 CDRM WB Multi Calculations EDEX Calculations of EDEX for Workers in 2024 Various CR202335303 Scheduled Work in RP Rad Health Not Performed due to Inadequate Staffing 12/29/2023 CR202436344 Dose Alarm Received While Performing Main Steam Line Plug Maintenance 02/16/2024 CR202437062 Safety Concern Due to RP Procedure Change 03/21/2024 CR202438147 Dosimetry Records Not Vaulted According to MGA07 04/10/2024 CR202438195 4 Individuals With Potential Uptakes 04/11/2024 CR202439872 Individual Reported to Davis-Besse Nuclear Power Station With Contamination on Boots 05/28/2024 Corrective Action Documents CR202545289 An Abundance of Individuals Undergoing Inprocessing Never Pick Up their DLR from Dosimetry and/or Do Not Require a DLR 01/28/2025 DLR/Secondary Dosimetry Comparison Resolution Form Various NPRP180203 Adjustment of Self Reading Dosimeter Doses to More Consistently Compare to Individual DLR Results 11/09/2018 NPRP240002 Scaling Factor Report & Waste Stream Sample results from GEL Laboratories, LLC, Dated November 21, 2023 01/18/2024 71124.04 Miscellaneous NPRP240033 Prospective Evaluation of Fermi 2 Internal Dose 05/07/2024
17 NPRP240076 Scaling Factor Report & Waste Stream Sample Results from GEL Laboratories, LLC, Dated August 16, 2024 11/15/2024 NPRP250012 Evaluation of Impact of Current Radionuclide Mix on RP Instruments 03/25/2025 Miscellaneous NVLAP LAB CODE 1005180 Certificate of Accreditation to ISO/IEC 17025:2017 Various 65.000.267 Whole Body Count Protocol and Evaluation of Bioassay Results 11.1 Procedures 66.000.248 Calibration of Self Reading Dosimeters 5
PM2024041115 Post Decon Survey of Bay 12 - 15:00 04/11/2024 PM202404111 Operator Uptake Investigation - 02:45 04/11/2024 PM2024041110 Updated Bottom of Torus Survey - 11:00 04/11/2024 Radiation Surveys PM202504304 Characterization of RWCU Piping Removed From RWCU HX Room. to Be Sent Out for Analysis 04/30/2025 71124.04 Self-Assessments NPRP240080 Quick Hit Self-Assessment: NRC Inspection 71124.04-Occupational Dose Assessment 12/13/2024 CR202437903 NRC identified: Locked High Radiation Area Controls Not in Accordance With Technical Specifications 04/05/2024 CR202441609 NRC Violation-2Q2024: Locked High Radiation Area Controls Not in Accordance with Technical Specifications 08/15/2024 Corrective Action Documents Resulting from Inspection CR202548223 NRC Identified - November 2024 and December 2024 EDG Performance Indicator (Unavailability) Report Discrepancies 06/13/2025 Fermi 2 - HPCI Performance Indicators Various Fermi 2 - EDG MSPI and WANO Performance Indicators Various MSPI Derivation Report - High Pressure Injection System Unreliability Index 03/2025 MSPI Derivation Report - High Pressure Injection System Unavailability Index 03/2025 MSPI Derivation Report - AC Power System Unreliability Index 03/2025 MSPI Derivation Report - AC Power System Unavailability Index 03/2025 Fermi II Reactor DEI Chemistry Data Report Various Activity Released by Release Point and Isotopes Various 71151 Miscellaneous 2024 Annual Radioactive Effluent Release Report
18 Procedures 24.000.02 Eight-Hour - Mode 1, 2, 3 - Control Room RCS Operation Leakage Various 2023626 AsFound Accelerated Corrosion Inside Valve Body of N22F413 09/09/2023 2130533 Increased Inleakage to Sump D017 11/29/2021 2130971 FAC and Erosion Control Program Investigation Related to 2130533, Increased Inleakage to Sump D017 12/13/2021 2226453 Cycle Isolation Monitoring: Elevated Temperature Noted on North Reactor Feed Pump Min Flow Valve Following Startup 05/19/2022 2227151 Cycle Isolation Monitoring: Elevated Temperature Noted on N3039F620 MTG MSR Reheater Steam Supply Drain 09/03/2023 2227373 High Soluble Iron in RWCU Effluent Sample 06/23/2022 CR202310162 2023 INPO Materials Review Visit: Recommendation for Flow Accelerated Corrosion Program 09/14/2023 CR202331926 Self-Assessment Recommendation: TMIS -230035 -
Update Information in PEP19 Appendix I 07/27/2023 CR202334588 Evaluate EPRI ASME Code Reconciliation for FAC Programs 11/20/2023 CR202435639 LRI OE Review: Flow Accelerated Corrosion Program:
Refueling Outage Path Delay Due to Valve Repairs 01/17/2024 CR202547014 Isolation of RWCU When Returning RWCU F/DA to Service 04/20/2025 CR202547035 Programmatic Weakness Involving the Conduct of FME Steering Committee Meetings 04/21/2025 CR202547054 Trend of Poor Initial FME High Risk Plan Quality -
Requesting Performance Gap Analysis 04/22/2025 CR202547100 FME Program Gap: Completion of Loss of Integrity Actions 04/24/2025 CR202547176 Passive Component Degradation Trend: Flow Accelerated Corrosion and Erosion Control and Service Water Piping Corrosion/Erosion Control 04/28/2025 CR202547914 WO for Proposed RWCU Piping Replacement Needed 05/30/2025 CR202548038 NQA - Ready to Work Challenges Identified Reviewing Sample of P1 and -100 Work Orders 06/05/2025 71152S Corrective Action Documents CR202548091 NSRG 2501XX: NSRG Engineering Subcommittee Action
- Passive Component Degradation Trend 06/09/2025
19 Engineering Evaluations PEP19 Appendix A FAC Program Susceptibility Review 6
FAC-RF22SCOPE Technical Basis for RF22 FAC Program Inspection and Replacements Scopes IAW MES26 Requirements 09/26/2022 Nuclear Generation Memorandum To: Sean T. Howell From: J.D. Wines - 2023 Quick Hit Self-Assessment Report for Materials Review Visit Readiness 07/28/2023 Miscellaneous PEP19 Flow Accelerated Corrosion Program Notebook 9
Procedures MES26 Flow Accelerated Corrosion Prediction, Detection, and Correction 22 65374361 Cycle Isolation Monitoring: Elevated Temperature Noted on North RFP Min Flow Valve 04/21/2024 Work Orders 66444817 FAC 40, 41, 42, and 43 - RF22 - Perform Erosion/Corrosion Inspection of Main Steam Piping 03/25/2024 Corrective Action Documents CR202547014 Isolation of RWCU When Returning RWCU F/DA to Service 04/20/2025 71153 Miscellaneous DBD-G3300 Reactor Water Cleanup System D