IR 05000341/2025010
| ML25253A285 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/10/2025 |
| From: | Sanchez Santiago E NRC/RGN-III/DORS/RPB2 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2025010 | |
| Download: ML25253A285 (1) | |
Text
SUBJECT:
FERMI POWER PLANT, UNIT 2 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000341/2025010
Dear Peter Dietrich:
On August 7, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Fermi Power Plant, Unit 2 and 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.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight Process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
September 10, 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 w/ encl: Distribution via LISTSERV Signed by Sanchez Santiago, Elba on 09/10/25
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The inspectors performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety-conscious work environment.
- Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees Problem Identification and Resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of the 2-stage Target Rock Safety Relief Valves.
- Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
- Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
- Safety-Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Corrective Action Program Based on the samples reviewed, the team concluded that the licensees implementation of the Corrective Action Program was generally effective and supported nuclear safety.
Effectiveness of Problem Identification:
Based on the samples reviewed, the team determined that the licensee continued to identify issues at a low threshold and appropriately entered these issues into the Corrective Action Program. The team also determined that the licensee usually entered problems into the Corrective Action Program completely and accurately.
The team noted that issues were being identified by all levels of organization and with varying degrees of safety significance. The licensee also utilized a number of Corrective Action Program support processes to identify problems, including the self-assessment and audit process and the Operating Experience Program. Some deficiencies were identified by external organizations, including the NRC, that had not been previously identified by licensee staff and were subsequently entered into the Corrective Action Program for resolution. For example, the licensee performed departmental self-assessments and Nuclear Quality Assurance (NQA) audits to identify issues in station processes. The identified deficiencies and improvement opportunities were entered into the Corrective Action Program for resolution. Similarly, the licensee screened issues from both NRC and industry operating experience and entered them into the Corrective Action Program when they were applicable to the station.
As low level, as well as safety significant issues were entered into the CAP, the team determined that the licensee was generally effective at identifying trends and taking appropriate corrective actions to prevent more significant problems from developing. In addition, the licensee used the Corrective Action Program to document instances in which previous corrective actions were ineffective or were inappropriately closed. The team did identify a potential trend in condition report (CR) generation rate decreasing over the last few years; however, the inspectors did not identify any safety or programmatic concerns with the trend.
The team performed a 5-year review of the 2-stage Target Rock Safety Relief Valves. As part of this review, the team interviewed the system engineer, and reviewed plant health reports, and selected corrective action and condition evaluation documents. The team concluded that deficiencies and concerns were identified and entered into the Corrective Action Program at a low threshold and the corrective actions were adequate and timely, commensurate with their safety significance.
Effectiveness of Prioritization and Evaluation of Issues:
Based on the samples reviewed, the team determined that licensee performance was generally effective at prioritizing and evaluating issues commensurate with the safety significance of the identified problem. In general, once a degraded or non-conforming issue was identified, the CAP process was effective in directing equipment operability / functionality review. During the Ownership Screening Committee (OSC) and Management Review Committee (MRC) meetings the team attended, licensee staff were generally thorough and intrusive in reviewing and screening issues. The team also observed healthy dialogue and good interactions among the members of the screening groups. The members came prepared and challenged each other on disposition of the identified conditions. Actions were prioritized based on the safety significance of the issues.
Effectiveness of Corrective Actions:
Based on the samples reviewed, the team determined that the licensee was generally effective in implementing corrective actions. In general, corrective actions for deficiencies that were safety significant were implemented in a timely manner. Problems requiring the performance of a root cause evaluation or other causal evaluation methodologies were resolved in accordance with Corrective Action Program requirements. The team sampled assignments associated with violations that were identified by the NRC previously and with licensee event reports (LERs). The team determined that the corrective actions sampled were generally effective and timely.
Assessment 71152B Self-Assessments and Audits Based on the samples reviewed, the team determined that the licensees performance of self-assessments and audits was generally effective. The licensee performed department self-assessments and quality assurance audits throughout the organization on a periodic basis. These self-assessments and audits were generally effective at identifying issues and enhancement opportunities at an appropriate threshold. The self-assessments and audits reviewed by the team identified issues that were not previously known, including issues within the Corrective Action Program itself. NQA had identified deficiencies with the licensees processes and those issues were addressed by the station using the Corrective Action Program.
Assessment 71152B The Use of Operating Experience Based on the samples reviewed, the team determined that licensees performance in the use of operating experience was generally effective. The licensee screened industry and NRC operating experience information for applicability to station. Based on these initial screenings, the licensee initiated actions in the Corrective Action Program to fully evaluate the impact, if any, to the station. When applicable, actions were developed and implemented under the Corrective Action Program to prevent similar issues from occurring. Operating experience lessons learned were communicated and incorporated into plant operations. The team observed the information being used in daily activities, such as pre-job briefs, as well as Corrective Action Program issues reviews and investigations.
Assessment 71152B Safety-Conscious Work Environment During this assessment, the team conducted focus groups and interviews, reviewed Employee Concerns Program (ECP) and Safety Culture Monitoring Panel procedures and files, examined corrective actions associated with the last SCWE inspection, and reviewed the 2024 USAA Safety Culture assessment. The team interviewed over 93 employees from the Operations, Security, Maintenance, Radiation Protection, Chemistry, NQA, and Engineering Departments. This included 15 first-line supervisors, 7 contractors, and the ECP manager.
As described in Inspection Manual Chapter, Aspects within the Cross-Cutting Areas and NUREG-2165, Safety Culture Common Language, in the area of Environment for Raising Concerns (RC), the team did not identify any significant issues with the work environment site-wide, as most interviewees (90 percent) stated they would raise any type of concern without fear of retaliation. Only 4 percent indicated hesitancy in raising nuclear safety concerns, localized to one department: Security. Specifically, 15 percent of individuals interviewed in the Security department indicated hesitancy in raising nuclear safety concerns.
This was classified as a significant precursor in the trait of RC.1 - Safety-Conscious Work Environment Policy, which could lead to a chilled work environment.
Furthermore, the team received positive feedback about the ECP representative and their accessibility as an avenue for raising concerns. While individuals expressed a willingness to submit CRs, there is a general perception that they do not consistently receive adequate feedback on the resolution of those CRs. CRs are often closed without resolving the issue, or they are assigned back to the originator for resolution, even when it is not their area of expertiseparticularly when the concerns are not directly related to nuclear safety. This was categorized as precursor in the Problem Identification and Resolution (PI) trait, specifically PI.3.
The team also noted that the Nuclear Safety Culture Monitoring Panel identified a steady increase in anonymous CR submissions. This trend raises concerns that the current work environment may be impacting the normal processes intended to surface such issues. Our review found that information from the Corrective Action Program, ECP, and other sources (e.g., Gallup) has provided opportunities for management to detect shifts in certain aspects of safety culture and SCWE. However, this information was not broken down by departments and was not trended to identify department-specific challenges.
In the area of Leadership Safety Values and Actions, the team heard that significant site-wide staffing challenges are placing tremendous strain on the organization. These challenges appeared to be attributed to attrition and delays in filling vacant positions. Staff reported that these concerns have been communicated to management multiple times; however, responses have been slow and have not fully addressed the ongoing issues. Additional concerns were shared by the Security organization, specifically related to the amount of forced overtime. The NRC team determined that this impacted LA.1, which states that leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety.
The team also identified concerns related to Field Presence (LA.2). Staff expressed that senior leaders are frequently absent from the field and are perceived to be consistently tied up in meetings. While they acknowledged improvements in the open-door policy and leadership presence in strategic meetings, they felt that senior leaders are failing to connect with workers at their level. One example shared involved a senior leader introducing themselves multiple times to the same individuals within a single day, suggesting a lack of familiarity and engagement with staff.
In the area of Respectful Work Environment (WE), individuals expressed concerns about feeling disrespected, specifically in some coaching in the moment activities, and that leadership should talk to people, not down at them (WE1). Most of the interviewees expressed concern with trust, specifically trust in senior leadership. There were instances described when management described a change with one vision, and the implementation was completely different. Additionally, individuals viewed the increased number of anonymous condition reports as indicative of a lack of trust. (WE3). The change in senior leadership was viewed as positive, and the request to resubmit the long-standing issues via the Corrective Action Program was viewed as a hope that things will be different. While the areas of opportunity identified in this trait are not affecting individuals ability to raise nuclear safety concerns, it is considered a precursor to a decline in safety culture. All the interviewees expressed a high level of trust and confidence in their immediate supervisors.
In the area of Effective Safety Communication (CO), some interviews revealed issues with communication, specifically a lack of transparency. Comments indicated that individuals feel they need to consider how management will react to feedback before providing it, and that the rumor mill is filling the gaps in information (CO.3). Staff expressed concerns about the lack of response or feedback provided in CR closures, perceiving that management is making decisions in a vacuum and not sharing the reasoning behind some decisions, yet they ask for the rationale when staff propose ideas. Some also mentioned that responses are tailored based on the originator of the question or the manager responding, rather than being consistent and comprehensive (CO.2).
Overall, interviewees stated that morale is declining. While it may be better than last year, it is not trending upward. The NRC will continue to monitor the safety culture at Fermi and expects Fermi to implement swift corrective actions to address issues in the Security department.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 7, 2025, the inspectors presented the biennial problem identification and resolution inspection results to Peter Dietrich and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD 09-27876
2009 Configuration Design Basis Inspection (CDBI) Self
Assessment - Additional Unanalyzed HPCI/RCIC and Room
LOCA Heat Load
10/08/2009
CARD 09-28082
Key Calculation Review for DC-2849 Primary Containment
Pneumatic Supply System
10/15/2009
CARD 10-24554
HPCI and RCIC Gland Steam Leakage Higher than
Expected
06/03/2010
CARD 14-21236
Results from the BADGER Test Report Indicate 3 Fuel
Storage Rack Panels Have Boron Density Less than That
Assumed
2/17/2024
CARD 14-23790
NRC Audit - Specification 3071-226 DRILLCO Capacity
05/01/2014
CARD 15-23277
RHRSW Return From RHR HX High Temperature Alarm
Setpoints Above Piping Design Temperature
05/07/2015
CARD 16-22201
Error in Calculation of Strainer Debris Weights
03/10/2016
CARD 16-25611
2016 EQ Program Self-Assessment Deficiency: EQ Central
Files EQ1-EF2-020 and -058 Lack Formal Documentation for
the Use of Sound Reasons to the Contrary IAW with
10CFR50.49 Par. (l)
07/14/2016
CARD 16-29202
Sparging of SLC Tank and Effects on Operability Not Fully
Evaluated.
11/16/2016
CARD 17-20988
Incomplete Incorporation of TSR-36838 Rev A As-Built
Posting Against DC-0367 Vol I
2/02/2017
CARD 17-22354
AOV Thrust Calc Overly Conservative
03/22/2017
CARD 18-24672
Evaluate R1400 for (a)(1) Status
06/13/2018
CARD 19-21968
ARP 3D54 RBCCW Radn Monitor Upscale, Revised with
Insufficient Detail, Does Not Match Field Installation.
03/13/2019
CARD 19-22113
OAR Review - DC-5713 Rev F Fire Header Hydraulic Calc
Minor Error Found
03/19/2019
CARD 19-26744
Description of the RPS EPA Setpoints in the TS 3.3.8.2
Bases is Inconsistent with the UFSAR 7.2.1.1.2
09/09/2019
CARD 20-25381
SRV Insulation Found to Not Be Properly Installed
04/29/2020
Corrective Action
Documents
CARD 20-25413
Generate Work Orders to Repair SRV Insulation Identified in
04/29/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD 20-25381
CARD 20-25708
Air Leak on union for SRV 'R'
05/13/2020
CARD 20-28723
UNSAT SRV inspection
07/28/2020
CARD 20-28737
Missing Insulation on SRV P (B2104F013P)
07/28/2020
CARD 20-29013
SRV A Tailpipe Temperature Elevated Following RF-20
Startup
08/06/2020
CARD 20-29165
SRV 'M' Tailpipe Temperature Elevated Following RF-20
Startup
08/10/2020
CARD 20-29828
NRC Identified: Evaluate Alarm Set-Point Change for HI
Drywell Temps
09/01/2020
CARD 20-30554
Three SRVs Removed in RF-20 Found outside of As-Found
Set-Point Tolerance
09/24/2020
CARD 21-23072
Possible 50.9 Issue with SFPLI Modification
04/06/2021
CARD 21-24255
DC-6447 Voltage Issue for H21P557
05/14/2021
CARD 21-25514
21 NRC 50.59 Inspection - HPCI Strainer Evaluation in
EDP 70097 Does Not Factor Design Basis Loading
Conditions
06/22/2021
CARD 21-29019
The R3200 System Has Exceeded its Availability Criteria for
Maintenance Rule
10/11/2021
CARD 21-29328
20 MMR14 Structures Monitoring Inspection of Reactor
Building North Exterior Wall (Investigation)
10/21/2021
CARD 21-29364
Revise EP-304-01
10/21/2021
CARD 22-00260
Water alarm Manhole 16949, Pump Run Light Lit
2/23/2022
CARD 22-25711
Unable to Raise RPV Level with Div 1 Core Spray Keep-Fill
04/27/2022
CARD 22-26034
EP-101, Classification of Emergencies Needs Clarification
Based on 20-32952 and EPFAQ 2015-006
05/05/2022
CARD 22-26422
SRVs B2104F013 M, D, F, and J have elevated Tail Pipe
Temperatures
05/17/2022
CARD 22-26474
Four SRVs (M, D, F, J) indicative of weeping
05/20/2022
CARD 22-28201
Three SRVs removed in RF-21 Found outside of As-Found
Set-Point Tolerance
07/26/2022
Corrective Action
Documents
CARD 22-29803
FERMEX 2022 - Opportunities to Improve Dispatch
Timeliness of DCRTs
09/22/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD 22-30029
NRC Design Basis Assurance Inspection (DBAI) Re-Exit
Finding
09/30/2022
CARD 22-31399
EDG LO Sampling Not Aligned with Renewed License
11/28/2022
CARD 22-32154
PST Perform 28.508.04 Emergency Equipment Monthly
Inspection
2/28/2022
CARD 23-20646
Investigate Drywell Cooling Time for Dedicated Shutdown
Scenario
01/24/2023
CR-2023-30014
Lack of transparency from senior leadership team
05/05/2023
CR-2023-30106
TR.2 Area of Concern: Line and Training Managers Have
Not Fully Analyzed Some Gaps in the Oversight Of Training
Programs and Developed Actions to Address Underlying
Behaviors
05/10/2023
CR-2023-30342
License Renewal - Indication on CST Fourth Level Wall
Panel Below Minimum Design Thickness
05/19/2023
CR-2023-30437
HPCI Inboard Torus Suction Isolation Valve Abnormal Stroke
05/23/2023
CR-2023-31630
MDCT D Fan Tripped
07/18/2023
CR-2023-31935
NQA Audit 23-0107 Finding - Repeated Gaps with
Radioactive Material (RAM) Management and Survey Map
Documentation
07/27/2023
CR-2023-32105
ILT 2023 Throughput did not meet expectations, Root Cause
08/03/2023
CR-2023-32208
1D58 - STM LK DET RCIC LOGIC POWER FAILURE and
1D62 - STM LK DET HPCI LOGIC POWER FAILURE
Received Simultaneously
08/09/2023
CR-2023-32454
DW Leak identification - RCS leakage from B Reactor Recirc
Sample Line
08/20/2023
CR-2023-32488
NQA Audit 23-0108 Recommendation - Evaluate Emergency
Preparedness Drill Objectives Rated Unsat or Marginal
from 2021 through 2023 for Trends
08/22/2023
CR-2023-32802
Diesel Fire Pump Fail to Start
09/04/2023
CR-2023-33018
28.501.02 - FIRE SUPPRESSION WATER SYSTEM VALVE
LINEUP VERIFICATION past critical
09/12/2023
CR-2023-33390
Zone 14 - DC MCC - Fire Alarm light lit with no Fire Alarm
09/29/2023
CR-2023-33907
Components Prematurely Removed From 24.425.01
10/23/2023
Corrective Action
Documents
CR-2023-34053
Uncontrolled Material Discovered in the Safeguards
10/27/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Information (SGI) Room
CR-2023-34093
NRC Violation - 2023 CYBER SECURITY INSPECTION:
Failure to meet Defense-in-Depth Protective Strategies per
NEI 08-09 Section E.6 Controls
2/22/2023
CR-2023-34253
Procedure Non-Adherence SEP-AD4-02
11/06/2023
CR-2023-34258
Vendor Assigned to Access Authorization Notified Fermi 2 of
An Internal Investigation.
11/06/2023
CR-2023-34344
NRC Violation - Integrated Inspection: Inoperable MDCTs
Following Modification to the Brake Control Circuit.
2/08/2023
CR-2023-35161
Improper Oil Viscosity and Oil Type
2/19/2023
CR-2024-35333
Numerous Fire Protection Surveillances going Unperformed
Due Poor Change Management And Lack Of Training
01/02/2024
CR-2024-35386
Revised Security NRC Baseline Inspection Procedures
01/04/2024
CR-2024-35411
Fatigue Management - Work Hours Not Entered into FRMS
01/05/2024
CR-2024-35422
Diesel Fire Pump Coolant Level Issue
01/06/2024
CR-2024-35449
DFP Coolant level low
01/08/2024
CR-2024-35596
Security CLO - Failure to coordinate Protected Area barrier
manipulation with CAS
01/16/2024
CR-2024-35783
Condenser Tube Leaks and SF6 Testing, Root Cause
07/18/2024
CR-2024-35844
28.504.08 Cannot Be Performed as Written
01/23/2024
CR-2024-36020
NRC SCWE Inspection Observation-Perception of
Production over Safety (Radiation Safety)
CR-2024-36022
NRC SCWE Inspection Observation-Site over reliance on
CR-2024-36023
NRC SCWE Inspection Observation-Long Term Contractor
Support
CR-2024-36106
Issues with FRMS Software Calculations
2/06/2024
CR-2024-36149
NRC Violation - 4Q2023: Division 1 Emergency Equipment
Cooling Water/Service Water (EECW/EESW) Heat
Exchangers Found Above Operability Limit
03/07/2024
CR-2024-36156
NRC Violation - 4Q2023: Failure to Identify Conditions
Adverse to Quality Associated with Gear Reducer Foot
Supports for the Mechanical Draft Cooling Towers
04/09/2024
CR-2024-36261
NRC KPI for Security Equipment Unavailability Reaches
2/13/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Critical Margin Threshold
CR-2024-36293
NQA - Methods for Calibration Validation of Containment
High Range Radiation Monitors Appear to Not Meet Station
Design or Regulatory Requirements.
2/14/2024
CR-2024-36363
OSSF SPING Not Restored to Functional Status within 30
Days.
2/17/2024
CR-2024-36436
Procedure Enhancement 24.204.06 LPCI P&V
2/21/2024
CR-2024-36581
Entry into TRLCO 3.0.3 required for Appendix R Alternate
Shutdown Auxiliary Systems (2C1-2 Spare Battery Charger)
2/28/2024
CR-2024-36632
HHS Lab Rejected Specimen
2/29/2024
CR-2024-36700
NOS - Apparently Incorrect Conversion Factors for Off Gas
Radiation Monitor B Calibration.
03/04/2024
CR-2024-37085
NRC Identified Hose Hanging Over Handrail of HPCI Hatch.
03/21/2024
CR-2024-37127
Inadequate Corrective Actions to Sustain Excellence in the
03/22/2024
CR-2024-37148
Automatic RPS Scram on High RPV Pressure While
Attempting to Lower Generator MW to 55 MWe per
2.000.04
03/23/2024
CR-2024-37198
NQA RF22 Monitoring - Junior RP Technician Did Not Verify
Daily Source Check of Canberra Tennelec as Required by
65.000.146
03/24/2024
CR-2024-37245
Foreign Material Dropped in Suppression Pool.
03/25/2024
CR-2024-37411
MOP05-200 Identifies Core Spray as a WICA System
Inconsistently
03/28/2024
CR-2024-37844
Fatigue Management - 10 CFR 26 Subpart I Work Hour Rule
Violations
04/04/2024
CR-2024-38029
Div-1 CCHVAC Chiller Trip
04/08/2024
CR-2024-38133
FFD Procedure Revision
04/10/2024
CR-2024-38195
Individuals with Potential Uptakes.
04/11/2024
CR-2024-38264
Lower Retaining Nut Loosened on C11A-K4A Relay Prior to
Reinstallation.
04/12/2024
CR-2024-38698
24.321.04 DEDICATED SHUTDOWN PANELS H21-P627
AND H21-P628-OPERABILITY TEST Procedure
enhancement
04/23/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2024-38856
G343R609 RWCU Pump Disch Flow Indication Reading 100
GPM with Pumps Shutdown
04/26/2024
CR-2024-38999
E5150F007 tripped thermal overloads while stroking open
04/29/2024
CR-2024-39110
EDG Fuel Delivery Additives Not Properly Verified Prior to
On-Site Chem Testing and Fuel Offload
05/01/2024
CR-2024-39164
Purge Trouble and Chiller Surging Div-1 CCHVAC
05/02/2024
CR-2024-39230
AOP Entry due to Trip of the East CRD Pump
05/04/2024
CR-2024-39570
SRVs B2104F013A, B, H Have Elevated Tail Pipe
Temperatures
05/13/2024
CR-2024-39746
SRVs B2104F013P & R Have Elevated Tailpipe
Temperatures
05/21/2024
CR-2024-39872
Individual Reported to Davis Besse Nuclear Power Station
with Contamination on Boots.
05/28/2024
CR-2024-39996
EDG 13 Overvoltage Trip String Monitor Light Out
06/02/2024
CR-2024-40139
Security Loggable Event - Loss of Vital Area Keys
06/07/2024
CR-2024-40149
Div 2 Battery Room Higher than Max Design Temp Limit
06/08/2024
CR-2024-40664
Missed Hourly Firewatch rounds in the Aux Bldg.
07/01/2024
CR-2024-40826
FermEX Submittal Not Completed per the Requirements of
10CFR50, Appendix E, IV, F.2.b
07/10/2024
CR-2024-41183
Leak from T4100-F375 Instrument Line
07/26/2024
CR-2024-41313
Four SRV Pilots Removed in RF-22 Found outside of
As-Found Set-Point Tolerance.
08/01/2024
CR-2024-41471
DIV 1 Control Air Dryer Differential Pressure High
08/08/2024
CR-2024-41473
RHR Pump "A" Motor Upper Thrust Bearing Low out of
Standstill
08/09/2024
CR-2024-41569
Employee with Expired Fitness for Duty (FFD) Training and
Active Badge
08/14/2024
CR-2024-41615
Licensee-Identified Violation - NRC report 2Q2024:
Individual entered Locked High Radiation Area without
proper dosimetry
10/09/2024
CR-2024-41616
Licensee-Identified Violation - NRC report 2Q2024: Gaps in
M&TE Program Compliance Over Last 4 Years Resulting in
Presumed Lost Test Equipment and Other Issues.
05/14/2025
Corrective Action
Documents
CR-2024-41634
Licensee-Identified Violation - NRC report 2Q2024:
10/29/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
E5150F007 - Non-Conservative Gear Ratio Discrepancy
Resulting in Negative Analytical Torque Margin
CR-2024-41787
Installed Material does Not Meet Dedication Requirements
08/26/2024
CR-2024-41837
FERMEX 2024 Critique Item-Dosimeters for TSC and OSC
08/28/2024
CR-2024-41876
RERP Exercise 08/27/2024 - Dose Discrepancies
Encountered
08/28/2024
CR-2024-41900
28.502.10 Scheduled for WW 2435 and will Not Be Able to
Be Performed Prior to Going past Critical.
08/29/2024
CR-2024-42165
EDG13 Lube Oil Level High
09/12/2024
CR-2024-42192
Blown Fuse E41F2B in H21-P081
09/12/2024
CR-2024-42273
Preplanned Loss of Security UPS Availability for Removal
and Replacement
09/17/2024
CR-2024-42371
Trend of Lowering EDG 13 Jacket Coolant Expansion Tank
Level
09/21/2024
CR-2024-42530
NRC Identified Operability Quality for CR-2024-40402 did
Not Provide Enough Detail to Explain Bases for Operability.
09/27/2024
CR-2024-43107
Tailgating event/ Security Rules Violation
10/22/2024
CR-2024-43113
2F-5A Pos 2B-R M Contactor Stationary and Moveable
Contacts Found with Excessive Pitting
10/22/2024
CR-2024-43174
Identify Common Causes of Recent NRC Violations and
Findings
10/24/2024
CR-2024-43380
SCWE: Concerning Exponential Trend in Anonymous CRs
Under the Current Senior Leadership Team
CR-2024-43443
Trend Only - Compensatory Measures established at PAP
and RHR
11/04/2024
CR-2024-43993
24 RP Pre-NRC 71124.03 Self-Assessment
Recommendation - Evaluate Risk of Emergency Air
Breathing Compressor Being Located outside the PA
11/26/2024
CR-2024-44059
Div 1 EECW Heat Exchanger A has Loose Clamping Bolt
2/02/2024
CR-2024-44090
Procedure 64.120.040 CONTAINMENT AREA HIGH
RANGE RADIATION MONITOR-DIVISION 1 CALIBRATION
Not Usable for Calibration
2/03/2024
CR-2024-44182
Replacement of All Site SCBAs, Cylinders and Confined
Space Respirators.
2/06/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2024-44278
RP Department Gap in Radiological Risk Recognition.
2/12/2024
CR-2024-44703
Temporary Loss of CCTV call up cameras
2/23/2024
CR-2024-44750
10D67 Div 2 48/24V Battery 2IB Trouble in alarm with
Normal Charger Parameters
2/29/2024
CR-2025-31643
Rollup of aggregate RHR Hydramotor Problems
07/11/2023
CR-2025-44994
East Main Turbine Bypass Valve Spurious Opening
01/13/2025
CR-2025-45311
Revise EP-101 Enclosure A (EAL Classification Matrix)
01/29/2025
CR-2025-45347
NRC Violation - 4Q2024: Failure to Establish Required
Firewatch with RB SW Quad Fire Detectors Non-Functional.
03/19/2025
CR-2025-45386
E5150F025 RCIC Turb Steam Drain Pot Inboard Isolation
Valve Stroke Time Outside IST Limit
01/31/2025
CR-2025-45531
RB SPING Not Restored to Functionally Capable within 30
Days as Required by ODCM
2/07/2025
CR-2025-45537
EDM Truck Would Not Start during Weekly Testing
2/08/2025
CR-2025-45552
EITER -Owner Controlled Area Notification System (OCANS)
Speaker Tower #1 and #3 Not Functioning Properly
2/10/2025
CR-2025-45569
3D56 Testability Logic CH A/B RPS/PWR Failure due to
Gross Failure on C11-N601D (SDV Water Level)
2/11/2025
CR-2025-45604
RERP Emergency Management Performance Evaluation
(EMPE) Drill - Objective K5.3 UNSAT for TSC - TSC
Emergency HVAC
2/27/2025
CR-2025-45678
During February 11, 2025 Emergency Management
Performance Evaluation (EMPE), Objective I.3.6 was UNSAT
for the TSC
2/17/2025
CR-2025-45781
CAS and SAS Intercom not functioning as designed
2/21/2025
CR-2025-45863
Missing / unaccounted for equipment
2/25/2025
CR-2025-45914
During February 11, 2025 Emergency Management
Performance Evaluation (EMPE), Objective E1.6 was SAT
with Significant Comments for the EOF
2/27/2025
CR-2025-45949
Failed Calibration of M&TE, AG-058-M, Heise HQS-2 0-100
PSIA Pressure Module on Q Work Performed Between
2/20/2023 and 8/06/2023 by Work Group Mechanical
Maintenance
2/28/2025
Corrective Action
Documents
CR-2025-46173
Evaluate D.C. Cook Security Event
03/11/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2025-46327
Security Industry Operation Experience Applicability
Review - Vogtle and Callaway Protective Strategy NRC
Violations
03/18/2025
CR-2025-46429
Fermi Security OE Applicability Review - Palo Verde SIED
25-003: Negligent Discharge during Dry Fire Manipulations
03/24/2025
CR-2025-46529
Failed Calibration of M&TE, AG-045-M, Heise HQS-2 0-20
PSIA Pressure Module on Q Work Performed Between
2/19/2024 and 3/19/2025 by Work Group RADPROI
03/28/2025
CR-2025-46871
Cleanliness Within Both Divisions of RHR Complex
Unsatisfactory
04/12/2025
CR-2025-47014
Isolation of RWCU when Returning RWCU F/D-A to Service
04/20/2025
CR-2025-47114
Lead Shielding Installed on G3300F033 Without Completing
65.000.303 and WI-RE-10
04/25/2025
CR-2025-47490
When did the Fermi Motto Become More with less
CR-2025-47649
Failed Calibration of M&TE, PG-962-M and PG-725-M on "Q"
Work Performed between 03/29/2024 to 09/29/2024 and
03/30/2024 to 09/30/2024 Work by Group IANDC
05/16/2025
CR-2025-47749
Fatigue Management - SAP Files for FRMS Not Being
Processed
05/22/2025
CR-2025-47768
Division 2 Control Air Compressor (CAC) Loading Very
Slowly
05/23/2025
CR-2025-47853
Loss of Video Capture in CAS/SAS
05/28/2025
CR-2025-47984
Lead Curtains Fell off of X-Ray Machine #2
06/04/2025
CR-2025-48063
TSC Conditions Do Not Support RERP Drill Scheduled for
6/10/2025
06/08/2025
CR-2025-49070
25 NRC PI&R Inspection Observation
07/25/2025
CR-2025-49072
25 NRC PI&R Inspection Observation
07/25/2025
CR-2025-49134
25 NRC PI&R Inspection Feedback on SCWE Interviews
with Individual Contributors Across Site
07/29/2025
CR-2025-49161
25 NRC PI&R Inspection: Discrepancy with Web Based
Training Due Dates
07/30/2025
CR-2025-49164
25 NRC PI&R Inspection - Inspector Feedback
07/30/2025
Corrective Action
Documents
Resulting from
Inspection
CR-2025-49186
25 NRC PI&R Inspection: Enhancement Required to
Guidance for Issuance of M&TE Under MMA05, Tool and
07/31/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M&TE Issue, Control and Return.
CR-2025-49241
25 NRC PI&R Inspection - NRC Identified - Improper
Closure of CARC CR-2025-45678 Related to EMPE
Objective I.3.6 UNSAT for the TSC
08/04/2025
CR-2025-49346
25 NRC PI&R Inspection - NRC Feedback on CAP
CARDs 20-29828 and 22-30029
08/07/2025
Engineering
Evaluations
EFA-E41-24-002
Evaluation of E4100F067 Hydraulic Piston Seal
ECP Investigations
24
Safety Culture Monitoring Panel Presentation and Minutes
for 2025
Spring Gallup Survey
25
Station Trend Reports for Q1, Q2 and Q3
25
OSC Meeting Package
07/24/2025
MRC Meeting Package
07/29/2025
OSC Meeting Package
07/23/2025
341-2024-001
Automatic RPS SCRAM on High RPV Pressure While
Attempting to Lower Generator Output During RF-22
05/15/2024
341-2024-002
Primary Containment Isolation Valve Declared Inoperable
for a Period Prohibited by Plant Technical Specifications
05/16/2024
CSCCD-
G41K187A
Spent Fuel Pool (SFP) Level Primary Channel Signal
Processor
CSCCD-
G41R601A
Spent Fuel Pool (SFP) Level Primary Channel Remote
Indicator - Control Room
Calibration Specification Sheet - Spent Fuel Pool Water
Level Indicator
A
MGA16
Fatigue Management
Revision 15
NOS-24-0017
24 Nuclear Safety Culture Assessment (NSCA) Report
11/24/2024
Miscellaneous
Annual Radioactive Effluent Release Report and
Radiological Environmental Operating Report
04/28/2025
20.300.SBO
Loss of Offsite and Onsite Power
23.139
Standby Liquid Control System
Classification of Emergencies
Procedures
FBP-8
FERMI 2 Management Observation Program
Revision 12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FBP-82
Fostering a Healthy Nuclear Safety Culture
Revision 20
MCE03
Chemistry Sampling and Analysis
MGA12
FERMI Employee Concerns Program
Revision 7
MQA11
Corrective Action Program
MQA11-100
Operability Determination Process
MQA11-200
Quality Assurance Conduct Manual
Implementing Procedure
Revision 2
MQA11-300
Screening and Assignment
MQA11-400
Corrective Action Program Condition Disposition
MQA11-500
Non-Corrective Action Program Condition Disposition
MQA11-600
Root Cause Evaluations
23-0100
Operations, Emergency Operating Procedures, and Fire
Protection Program Reports
2/27/2023
23-0107
Nuclear Quality Assurance Audit of the Radiation Protection
Program
08/18/2023
23-0108
Nuclear Quality Assurance Audit of the Emergency
Preparedness Program
09/26/2023
23-07
Oversight Station Assessment Report
11/01/2023
23-1001
22 Mid-Cycle Recommendation Surveillance
03/24/2023
24-0101
Security Audit Report
03/11/2024
24-0105
Nuclear Quality Assurance audit of the Evaluation and
Corrective Action, and Operating Experience Programs
08/09/2024
24-0106
Nuclear Quality Assurance Audit of the Radiation Protection,
Radiological Effluents Monitoring, and Radioactive Material,
Transfer & Disposal Programs
08/16/2024
24-0107
Training and Qualifications of Unit Program Audit Report
09/09/2024
24-04
Oversight Station Assessment Report Final
11/01/2024
24-1002
Nuclear Quality Assurance Surveillance of Emergency
Preparedness Program
09/26/2024
NAPI-25-0003
Problem Identification and Resolution (PI&R) Formal
Self-Assessment
06/16/2025
Self-Assessments
NARP-24-0078
Pre-Inspection Readiness QHSA - EAL and Emergency Plan
Changes
08/01/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NARP-24-0100
NRC Inspection Readiness Assessment: Exercise Evaluation
71114.01 & Performance Indicator Verification 71151
07/30/2024
NPOP-23-0086
Quality of OJT/TPE Training
11/12/2023
NPOP-24-0017
Fire Protection Implementation
11/28/2023
NPRP-24-0003
QHSA: Radioactive Gaseous and Liquid Effluent Treatment
System
01/16/2024
NPRP-24-0079
Quick Hit Self-Assessment: NRC Inspection 71124.03 - In-
Plant Airborne
2/13/2024
NSSE 25-0020
Security Training (IP 71130.07) Security Plan Changes
05/02/2025
Self-Assessments
NSSE-24-0029
Force-On-Force (IP 71130.03)
09/20/2024
66491878
Perform 44.030.272 ECCS RX Stm Dome Pres RHR/CSS
Inject, Div 2, CHNL B, Xmtr Cal
04/05/2024
67598569
G33R609 - Replace Indicator
04/29/2024
68531328
Troubleshoot and Repair Close Seal In Ckt on E4150-F042
03/19/2024
Work Orders
68688424
Perform 24.202.01 HPCI Pump / Flow Test & Valve Stroke at
25 PSIG
05/15/2025