IR 05000341/2025002
| 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
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 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
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.
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
- (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) 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:
- (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,
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
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) 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) 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) 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,
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 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 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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6M7215357
Emergency Equipment Cooling Water System Division II
Drawings
6M7215734
Emergency Diesel Generator System Functional Operating
Sketch
23.127
Reactor Building Closed Cooling Water/Emergency
Equipment Cooling Water System
153
23.205 Att. 1A
Division I RHR Initial Valve Lineup
23.205 Att. 8A
Division I RHR LPCI Standby Lineup Verification
Procedures
23.307
Emergency Diesel Generator System
139
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"
FPAB2M11
Auxiliary Building, Cable Spreading Room, Zone 11,
Elevation 630'
FPRHR114EDG
RHR Complex, EDG 14 Room, El. 590'0"
FPRHR151
RHR Complex, Division II Pump Room Zone 51, El. 590'0"
LPFP9402321
Fire Drill/Evaluation
Procedures
MOP10001
Fire Brigade Drill Record Form
EF2PRA011
Internal Flood Walkdown Summary Notebook
Engineering
Evaluations
EF2PRA012
Internal Flood Analysis Notebook
Miscellaneous
SSOP2022464
License Operator Requalification Simulation Lesson Plan
Procedures
2.000.03
Power Operation 25% to 100% to 25%
109
CR202436104
CTG 111 Failed to Achieve Base Load and Failed PMT
2/05/2024
Corrective Action
Documents
CR202441956
Standby Diesel Generator (Aggreko) Output Voltmeter
Reading Extremely Low
09/02/2024
Miscellaneous
27331
R1100 Get Well Plan
MMR APP D
Guidelines For Determining Fictional Failures (FFs) and
Maintenance Preventable Functional Failures (MPFFs)
MMR APP E
Maintenance Rule SSC Specific Functions
Procedures
MMR APP F
Maintenance Rule Performance Criteria
Engineering
Evaluations
TEE1108078
Removal of RHR Complex Pump Room Roof Plugs Under
F
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
MMR12
Maintenance Rue Conduct Manual Equipment Out of
Service Risk Management
20A
ODE20
Protected Equipment
Procedures
ODE20, ATT. 17
Protected Equipment Form EDG 12 Safety System Outage
Calculations
DC6336 Vol 1
EDG Starting Air System Sizing Basis
B
24680
Self-Assessment Finding: Non-Conservative EDG Starting
Air Operability Criterion
05/24/2012
23976
Control Rod 1031 Failed to Withdrawal
09/09/2023
23185
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
2/092024
CR202535153
Diesel Fire Pump Needs Coolant Topped Off
03/12/2025
CR202545556
Tie Pin for HPCI Control Valve Rod Linkage Broke While
Disassembling
2/10/2025
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
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
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
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
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
2/28/2019
Miscellaneous
VMB1160.1
[CONFIDENTIAL] Installation, Operation, and Maintenance
Driver Manual
35.202.009
HPCI Steam Turbine - General Maintenance
35.206.001
RCIC Steam Turbine Maintenance
35.206.005
RCIC Turbine Trip Throttle Valve General Maintenance
46.202.001
HPCI Turbine Governor Control System Calibration
54.000.03
Control Rod Scram Insert Time Test
74.000.19
Chemistry Routine Surveillances
74.00018
Chemistry Shiftly, 72Hour, and Situational Surveillances
76.000.34
Reactor Coolant Analysis
Procedures
CHS-PRI06
Fermi 2 - Chemistry Specifications
Work Orders
68147634
Neil Req'd - Clean and Lube External Portions of Control
and Stop Valves and Lid
2/06/2025
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
24860
EDG12 2 and 10 Piston/Liners Have Indications of Wear
09/16/2023
2547350
FME Cover Became Entangled in EDG12 Upper Torsional
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
23.307
Emergency Diesel Generator System
139
24.139.02
SLC Pump and Check Valve Operability Test
24.307.14
Emergency Diesel Generator 11 - Start and Load Test
Procedures
24.307.17
Emergency diesel generator 14 - Start and Load Test
24.307.45
Emergency Diesel Generator 11 - Fast Start Followed by
Load Reject
34.307.001
Emergency Diesel Generators - Inspection and Preventive
Maintenance
2.139.01
Standby Liquid Control System Associated Isolation Device
Test
IST Program
Description
Inservice Testing Program Fourth Ten-Year Interval
IST Program Pump
Basis
Inservice Testing Program for Pumps and Valves Part 12:
IST Program Basis
Procedures
IST Program Relief
Requests
Inservice Testing Program for Pumps and Valves Part 7:
IST Program Relief Requests
IST Pump Scope
Table
Inservice Testing Program for Pumps and Valves Part 3:
IST Pump Scope Table
IST Pump Testing
Program
Inservice Testing Program for Pumps and Valves Part 2:
IST Pump Testing Program
MMA11
Post-Maintenance Testing Guidelines
MWC10
Work Package Preparation
VME81.1
Operations and Maintenance Technical Manual-
67464736
Inspect Air Start Distributors, Pilot Valves and Springs
04/08/2025
293649
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
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
2/13/2024
CR202545627
Evaluate the Required Pounds per Square Inch (PSI) of
Training SCBA Cylinders
2/14/2025
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
Miscellaneous
65.000.769 Att 1
MSA AirHawk SCBA Inspection Record
Various
Miscellaneous
u019411
Fermi 2 - Radiation Protection Respirator Qualification
Report
04/15/2025
65.000.738
Filling of Breathing Air Cylinders
65.000.757
Filling Control Room Emergency Breathing Air System
65.000.768
Inspection of MSA FireHawk M7 Self-Contained Breathing
Apparatus
65.000.769
Inspection of MSA AirHawk Self-Contained Breathing
Apparatus
65.000.770
Inspection of MSA Ultra Elite AP Respirator
Procedures
65.000.771
Inspection of PremAire Cadet Escape Respiratory
Equipment
Self-Assessments NPRP240079
Quick Hit Self-Assessment: NRC Inspection 71124.03-
InPlant Airborne
2/13/2024
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
2/29/2023
CR202436344
Dose Alarm Received While Performing Main Steam Line
Plug Maintenance
2/16/2024
CR202437062
Safety Concern Due to RP Procedure Change
03/21/2024
CR202438147
Dosimetry Records Not Vaulted According to MGA07
04/10/2024
CR202438195
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
Miscellaneous
NPRP240033
Prospective Evaluation of Fermi 2 Internal Dose
05/07/2024
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
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
Self-Assessments NPRP240080
Quick Hit Self-Assessment: NRC Inspection 71124.04-
Occupational Dose Assessment
2/13/2024
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
24 Annual Radioactive Effluent Release Report
Procedures
24.000.02
Eight-Hour - Mode 1, 2, 3 - Control Room RCS Operation
Leakage
Various
23626
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
2/13/2021
26453
Cycle Isolation Monitoring: Elevated Temperature Noted on
North Reactor Feed Pump Min Flow Valve Following
Startup
05/19/2022
27151
Cycle Isolation Monitoring: Elevated Temperature Noted on
N3039F620 MTG MSR Reheater Steam Supply Drain
09/03/2023
27373
High Soluble Iron in RWCU Effluent Sample
06/23/2022
CR202310162
23 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
Corrective Action
Documents
CR202548091
NSRG 2501XX: NSRG Engineering Subcommittee Action
- Passive Component Degradation Trend
06/09/2025
Engineering
Evaluations
PEP19 Appendix A
FAC Program Susceptibility Review
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
Procedures
MES26
Flow Accelerated Corrosion Prediction, Detection, and
Correction
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
Miscellaneous
DBD-G3300
Reactor Water Cleanup System
D