IR 05000341/2024004
| ML25029A079 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/29/2025 |
| From: | Sanchez-Santiago E NRC/RGN-III/DORS/RPB2 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2024004 | |
| Download: ML25029A079 (1) | |
Text
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2024004
Dear Peter Dietrich:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On January 13, 2025, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Fermi Power Plant, Unit 2.
If you disagree with a cross-cutting aspect assignment 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.
January 29, 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
Inspection Report
Docket Number:
05000341
License Number:
Report Number:
Enterprise Identifier:
I2024004-0059
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
October 01, 2024 to December 31, 2024
Inspectors:
J. Cassidy, Senior Health Physicist
J. Gewargis, Resident Inspector
J. Kutlesa, Senior Emergency Preparedness Inspector
T. Taylor, Senior Resident Inspector
Approved By:
Elba M. Sanchez Santiago, Chief
Reactor Projects Branch 2
Division of Operating Reactor Safety
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
Failure to Establish Required Firewatch with Reactor Building Southwest Quadrant Fire Detectors Nonfunctional Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/202400401 Open/Closed
[H.5] - Work Management 71111.05 A self-revealed Green Finding and associated Non-Cited Violation (NCV) of Fermi License Condition 2.C.(9) was identified during performance of surveillance 28.505.03, Fire Detection Zone 3 Operability Test RB BMT and SBMT SW Quad, for nonfunctional fire detectors in a reactor building fire zone. Specifically, two of four early warning, notification only, fire detectors in the reactor building southwest quadrant, fire zone 3, were deenergized and nonfunctional without the appropriate hourly fire watch established in accordance with the sites fire protection program.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000341/2023003-00 LER 2023003-00 for Fermi 2 Power Plant, Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure 71153 Closed LER 05000341/2024001-00 LER 2024001-00 for Fermi 2 Power Plant, Automatic RPS SCRAM on High RPV Pressure While Attempting to Lower Generator Output During RF22 71153 Closed LER 05000341/2023001-00 LER 2023001-00 for Fermi,
Unit 2, Loss of Mechanical Draft Cooling Tower Fan Brakes during High Speeds Leads to Loss of Safety Function and Inoperability,
Revision 0 71153 Closed
LER 05000341/2023001-01 LER 2023001-01 for Fermi 2 Power Plant, Loss of Mechanical Draft Cooling Tower Fan Brakes during High Speeds Leads to Loss of Safety Function and Inoperability, Revision 1 71153 Closed LER 05000341/2023002-00 LER 2023002-00 for Fermi 2 Power Plant, Technical Specification Completion Time Exceeded Due to Repairs on the Mechanical Draft Cooling Tower (MDCT)
Fan D 71153 Closed
PLANT STATUS
Unit 2 began the inspection period at or near rated thermal power. On October 4, 2024, power was reduced to approximately 75 percent for routine rod pattern adjustments and surveillances.
Power was restored to 100 percent on October 6, 2024. The plant remained at or near 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
General service water, emergency diesel generators (EDGs), and condensate system, completed the week ending December 14, 2024
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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) Zone 3, reactor building basement and subbasement southwest quad on December 11, 2024
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the torus room, reactor building quadrant subbasements, and the high pressure coolant injection (HPCI) room on December 11, 2024
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from October 21, 2024, to November 22, 2024
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during down power on October 4, 2024
- (2) The inspectors observed and evaluated licensed operator performance in the control room during reactor core isolation cooling (RCIC) system testing on November 8, 2024
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a portion of the annual licensed operator requalification exam simulator scenarios
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Standby feedwater system, completed the week ending November 2, 2024
- (2) Residual heat removal service water (RHRSW) system, completed the week ending November 16, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Failure, troubleshooting, and repair of battery charger 2A2, completed the week ending October 26, 2024
- (2) Repair of an oil leak from the 'B' reactor recirculation motor-generator set oil system, completed the week ending November 1, 2024
- (3) Coordination of work involving a reactor building steam tunnel entry, a HPCI maintenance outage, and emergent work on an electrical connection associated with division 2 of reactor pressure system (RPS), completed the week ending November 23, 2024
- (4) Failure of low pressure coolant injection loop select circuitry due to degraded relay contacts, completed the week ending December 14, 2024
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) Control complex heating ventilation and air conditioning (CCHVAC) leakage past operability/inoperability, completed the week ending October 12, 2024
- (2) Calculation error regarding density of emergency equipment service water (EESW)piping supports P454630-G01 and P453352-G22, completed the week ending November 16, 2024
- (3) Review of missed oil and coolant samples for station blackout generator CTG111, completed the week ending December 14, 2024
- (4) Past operability of battery charger 2A2 following discovery of phase imbalance during maintenance, completed the week ending December 14, 2024
- (5) RHRSW pump 'B' approaching required action high range on December 9, 2024
- (6) Review of circumstances regarding environmental qualification of 'A' and 'C' RHR pump motors described in CR202444589, completed the week ending December 28, 2024
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (6 Samples)
- (1) Division I CCHVAC high vibrations and dampener installation, completed the week ending November 1, 2024
- (2) EDG 14 following a planned maintenance outage, completed the week ending November 16, 2024
- (3) HPCI system following a maintenance outage completed the week ending November 16, 2024
- (4) Alternate electrical protection assembly (EPA) breaker repair and PMT, completed the week ending December 6, 2024
- (5) Division I ultimate heat sink inspection and bolt replacement for EESW and RHRSW pumps on December 11, 2024
- (6) Division I CCHVAC emergency inlet air radiation (CCEA) monitor RM1000 engineering change, completed the week ending December 31, 2024
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Testing criteria for E4150F067, high pressure coolant injection pump steam admission valve, completed the week ending November 1, 2024
- (2) EDG 11 fast start, completed the week ending November 8, 2024
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) Diesel full load test and Neptune/Dominator full load test surveillance review on December 11, 2024
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.0102.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- RERP Plan Fermi 2 Radiological Emergency Response Preparedness Plan, Rev 49
- RERP Plan Fermi 2 Radiological Emergency Response Preparedness Plan, Rev 50
- RERP Plan Fermi 2 Radiological Emergency Response Preparedness Plan, Rev 51 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Tabletop drill conducted in the emergency operations facility on October 8,
OTHER ACTIVITIES
BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) September 1, 2023 through September 30, 2024
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 1, 2023 through September 30, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) September 1, 2023 through September 30, 2024
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 that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) LER 2023001-00, and LER 2023001-01, Loss of Mechanical Draft Cooling Tower Fan Brakes during High Speeds Leads to Loss of Safety Function and Inoperability (ADAMS Accession Nos. ML23142A189; ML23177A043). The inspection conclusions associated with this LER are documented in Inspection Report 05000341/2023003 under Inspection Results Section 71152A, NCV 05000341/202300302. This LER is Closed.
- (2) LER 2023002-00, Technical Specification Completion Time Exceeded Due to Repairs on the MDCT Fan D (ADAMS Accession No. ML23258A067)
The inspection conclusions associated with this LER are documented in Inspection Report 05000341/2023004 under Inspection Results Section 71152A, NCV 05000341/202300403. This LER is Closed.
- (3) LER 2023003-00, Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure (ADAMS Accession No. ML24031A549).
The inspection conclusions associated with this LER are documented in Inspection Report 05000341/2023004 under Inspection Results Section 71152A, NCV 05000341/202300404. This LER is Closed.
- (4) LER 2024001-00, Automatic RPS SCRAM on High RPV Pressure While Attempting to Lower Generator Output During RF22 (ADAMS Accession No. ML24136A211).
The inspection conclusions associated with this LER are documented in Inspection Report 05000341/2024003 under Inspection Results Section 71152A, FIN 05000341/202400304. This LER is Closed.
INSPECTION RESULTS
Failure to Establish Required Firewatch with Reactor Building Southwest Quadrant Fire Detectors Nonfunctional Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/202400401 Open/Closed
[H.5] - Work Management 71111.05 A self-revealed Green Finding and associated Non-Cited Violation (NCV) of Fermi License Condition 2.C.(9) was identified during performance of surveillance 28.505.03, Fire Detection Zone 3 Operability Test RB BMT and SBMT SW Quad, for nonfunctional fire detectors in a reactor building fire zone. Specifically, two of four early warning, notification only, fire detectors in the reactor building southwest quadrant, fire zone 3, were deenergized and nonfunctional without the appropriate hourly fire watch established in accordance with the sites fire protection program.
Description:
The southwest reactor building quadrant basement and subbasement contains important to safety equipment that is relied upon to achieve safe shutdown during potential fire scenarios in the reactor building. This includes the Division II RHR pumps. The reactor building southwest quadrant, fire detection zone 3, is equipped with four early warning, notification only, ionization fire detectors, to warn the main control room of potential fire in that quadrant so that field operators can quickly be deployed, and the fire can be suppressed via manual firefighting means before significant damage can occur in the reactor building. There are two detectors in the basement, detectors C and D, and two detectors in the subbasement, detectors A and B. Detectors A and C are powered from one independent circuit and detectors B and D are powered from a different independent circuit.
During the Division II RHR pump motor replacement activities in RF22, the most recent refueling outage, interference removal work governed by three separate work orders (WO)was performed on equipment in the southwest quadrant that needed to be removed from service and relocated so that there would be enough physical clearance to facilitate the installation of the new pump motors. This interference removal work included removing from service all the ionization detectors in the southwest quadrant. During completion of these three WOs, the work groups deferred restoration of all four ionization detectors to the work order that was completed last. However, the WO that was completed last did not have the necessary steps to restore all four detectors. The last work order only had steps to restore the B and D ionization detectors. Upon completion of the last WO, detectors A and C were left deenergized and nonfunctional. This degraded condition was discovered on September 19, 2024, when the Instrumentation and Controls (I&C) department was performing surveillance 28.505.03, Fire Detection Zone 3 Operability Test RB BMT and SBMT SW Quad.
Technical Requirements Manual Limiting Condition for Operation (TRLCO) 3.12.1 Condition B requires that an hourly fire watch be established to inspect the affected zone(s) if one or more zones with less than or equal to one-half of the total number of instruments shown in Table 3.12.11 for Function A are functional. Technical Requirements Manual (TRM)
Table 3.12.11 shows 4 ionization instruments in that zone for Function A. The requirement to comply with the TRM action statements and implement a fire watch in response to the degraded condition was required to be in effect from when the site was relying on Division II RHR for shutdown cooling, beginning on May 3, 2024, until the degraded condition was discovered and corrected on September 19, 2024.
Corrective Actions: After discovering the degraded condition on September 19, 2024, the site implemented an hourly fire watch in accordance with the TRM, entered an associated fire impairment, and documented the condition in their corrective action program under CR202442326.
Corrective Action References: CR202442326
Performance Assessment:
Performance Deficiency: The licensee failed to follow TRM Section 3.12.1, from May 3, 2024, to September 19, 2024, which requires the site to establish an hourly fire watch when less than or equal to one-half of early warning, notification only, ionization detectors, in fire detection zone 3, the reactor building southwest quadrant basement and subbasement, are functional.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, with two of the four ionization detectors being left nonfunctional, and no required hourly fire watch being established, the capability of the southwest quadrant important to safety equipment to perform their fire safe shutdown function was adversely impacted.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. Specifically, the fire finding category for this performance deficiency was Fixed Fire Protection Systems, which led the inspectors to answer step 1.3 as "high" because more than 10 percent of detectors in the affected fire zone were nonfunctional. Next, the inspectors conservatively answered step 1.4 as no and moved on to step 1.5. In step 1.5, the inspectors determined the finding screened to Green based on the NRC regional Senior Risk Analysts review of the licensees fire PRA and their analysis for the nonfunctional fire detectors. Specifically, the associated change in core damage frequency was below the Green threshold of 1E6 per year.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, the work group implementing the three job activities deferred the fire detector restoration to a work order without the appropriate restoration steps and thus failed to adequately coordinate.
Enforcement:
Violation: Fermi Operating License Condition 2.C.(9) states, in part, the licensee, shall implement and maintain in effect all provisions of the approved fire protection program as described in its Final Safety Analysis Report.
Updated Final Safety Analysis Report (UFSAR) Section 9A describes, in part, the sites fire protection program. UFSAR Section 9A.6, Fire Protection Conditions for Operation states, The Fire Protection Conditions for Operation portion of Appendix 9A is in the TRM.
TRM Section 3.12 "Fire Protection" Subsection 3.12.1 Fire Detection Instrumentation limiting condition of operation (TRLCO) 3.12.1 states, in part, The fire detection instrumentation for each fire detection zone shown in Table TR3.12.11 shall be operable.
Table TR3.12.11 line item 1.c, SW corner rooms RHR pump, identifies the four early warning, notification only, fire detection ionization detectors of fire detection zone 3, the southwest quadrant basement and subbasement of the reactor building, to be governed under Section 3.12.1.
TRLCO 3.12.1 Condition B states, in part, that if the following condition exists, one or more zones with less than or equal to one-half of the total number of instruments shown in Table 3.12.11 for Function A, then perform the required action B.1, establish an hourly fire watch patrol to inspect the zone(s).
Contrary to the above, from May 3, 2024, to September 19, 2024, the licensee failed to implement and maintain in effect all provisions of the approved fire protection program as described in the UFSAR. Specifically, the licensee failed to implement an hourly fire watch for fire detection zone 3, the reactor building southwest quadrant, basement and subbasement, when two of the four early warning, notification only, ionization detectors were left deenergized and nonfunctional after the failure to restore the detectors following maintenance activities during RF22.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 13, 2025, the inspectors presented the integrated inspection results to Peter Dietrich and other members of the licensee staff.
- On December 20, 2024, the inspectors presented the emergency action level and emergency plan changes inspection results to A. Mann, Emergency Preparedness Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR202443880
[NRC Identified] 2023 MWC16100 Enclosure F,
Documentation Unavailable
11/21/2024
Corrective Action
Documents
Resulting from
Inspection
CR202444240
NRC Identified - Flooded Pit and Submerged Insulated
Piping at GSW Pump House
2/10/2024
Drawings
6M7212010
Diagram General Service Water System
23.131
General Service Water System
116
Procedures
MWC16100
Seasonal Readiness
Operator Outside Rounds Logs
10/13/2024 -
10/18/2024
Miscellaneous
DBD X4103
Residual Heat Removal Complex Heating and Ventilating
System
B
Procedures
MMA08
2.1
Corrective Action
Documents
CR202442326
When Attempting to Perform 28.505.03 Fire Detection Zone
Operability Test RB BMT and SBMT SW Quad Found End
of Line Resistor (91K ohm) on ZIU31A + and - Terminals.
Not Expected
09/19/2024
6I7212868-37
Wiring Diagram Fire Detection System Reactor Building
Basement and Sub-Basement
D
6I7212868-40
Wiring Diagram Fire Detection System Panel H11P916A1
and H11P916A2
L
6I7212868-41
Wiring Diagram Fire Detection System Panel H11916B1
and Panel H11P916B2
L
Drawings
6I7212868-8
Installation Fire Detection System Reactor Building
Basement and Subbasement
C
FPRB-B3b
Reactor Building Basement Southwest Corner Room, Zone
3, EL. 562'0"
Fire Plans
FPRB-SB3a
Reactor Building Sub-Basement Southwest Corner Room,
Zone 3, EL. 540'0"
Miscellaneous
VMB112.0
Fire and Smoke Detection Systems Vendor Manual
D
28.505.03
Fire Detection Zone 3 Operability Test RB BMT and SBMT
MES 35
Engineering Support Conduct Manual MES 35: Fire
Protection
MMA20
Maintenance Conduct Manual MMA20: Work Execution and
Closure
Procedures
MWC10
Work Control Conduct Manual MWC10: Work Package
Preparation
70025156
EDP80186C02 RHR Motors - Remove (Online) / Install
(Outage) RB1 SW Hatch
4/22/2024
70935801
RF22 EDP 80186C02 Relocate RHR E1102C002B Pump
Seal Heat Exchanger
04/30/2024
Work Orders
709360079
RF22 EDP 80186C02 RHR Motor C002B - Relocate
E113177-G18 Pipe Support
04/22/2024
DC4689 VOL I
Flood Depth in the Torus Room Assuming a Torus Rupture
A
DC5426
High and Moderate Energy Line Break Evaluation
Calculations
DECO04519
Pipe Break Outside Containment High and Moderate Energy
Line Break Evaluation
Drawings
6M7215706-2
Residual Heat Removal Division I Functional Operating
Sketch
EF2PRA012
Internal Flood Analysis Notebook
Engineering
Evaluations
XXX02
Design Basis Document: Design Basis Event Combinations
A
23.702.01
Plant System Leakage Check Procedure
29.100.01 SH 2
Emergency Operating Procedure: Primary Containment
Control Sheet 2
ARP 2D82
Reactor Building Torus Sump Level HiHi/LoLo
ARP 2D83
Reactor Building Leakage to Torus Sump High
Procedures
ARP 2D84
Reactor Building Northwest Leakage to Equipment Drain
Sump High
Procedures
ODE3
Operations Department Expectation ODE3:
Communications
2.000.03
Power Operation 25% to 100% to 25%
108
24.206.01
RCIC System Pump and Valve Operability Test
57.000.22
Load Profile Plan: 10/04/2024 Downpower
MOP01
Operations Conduct Manual MOP01: Conduct of Operations
SSOP9042485
LOR Scenario One: 10/23/2024
10/23/2024
Procedures
SSOP9042490
LOR Scenario Two: 10/23/2024
10/23/2024
CARD 1327286
Broken Fuse Clip Protector for MCC 2PC15A
10/10/2013
CARD 1327290
AFCC 4 "Open" Contactor for N2103F001 has Degraded
Pickup Voltage Above Acceptance Criteria
10/10/2013
CARD 1624781
2016 CDBI QHSA No. 2 Deficiency: Apparent Lack of
Demonstrated Alternate Boron Injection Pump Operation
07/20/2016
CARD 1627995
Low Meggar Readings on MOV Control Circuit
10/07/2016
CARD 2123001
CARD on PMs Not Meeting Critical Dates for RF23
04/05/2021
CARD 2125962
AIM for 24 Month Fuel Cycle PM Project PMO 07/02/2021
07/07/2021
Corrective Action
Documents
CARD 2130613
PMO 7 AIM Action Items
2/02/2024
CR202443340
NRC Identified - Component Criticality on N2000F800
(CNDS CPD Alternate RPV Boron Injection Pump Suction
Valve) is Incorrect
10/30/2024
Corrective Action
Documents
Resulting from
Inspection
CR202443532
NRC Identified-Evaluate Current SBFW Component
Classifications
11/07/2024
6M7215715-3
Standby Feedwater System Functional Operating Sketch
O
Drawings
6M7215715-4
Standby Feedwater Lube Oil System Turbine Building
Functional Operating Sketch
F
23.107.01
Standby Feedwater System
24.107.03
SBFW Pump and Valve Operability and Lineup Verification
Test
Procedures
24.321.05
Dedicate Shutdown Panel H21P623 Operability Test EF2
System Transfer
255091
Perform 24.107.03 Sec 5.3 SBFW Pump "B" Flow Test
2/09/2024
67179602
Perform 24.107.03 Sec 5.3 SBFW Pump "B" Flow Test
05/14/2024
Work Orders
67334311
Perform 24.107.03 Sec 5.3 SBFW Pump "B" Flow Test
08/09/2024
Calculations
DC2565
R111 Blast Door 1st Floor Reactor Building
B
Corrective Action
Documents
2444120
44.030.279 Fail Due to E11A-K32A Contacts Indicating
Open Instead of Closed (High Risk Surveillance)
2/05/2024
CR202442816
Divisional Battery Charger 2A2 Panel Mounted Ammeter
Failed to Calibrate
10/09/2024
CR202442844
Phasing Balance Acceptance Criteria Unsat for 2A2 Battery
Charger
10/10/2024
CR202442852
Nuclear Oversight - Potential Missed Opportunity to Align
the Station on Risk During Application of MOP05
10/11/2024
CR202442938
DPM Oil Leak on RR MG Set B Lube Oil Pumps
Discharge Header
10/14/2024
Corrective Action
Documents
CR202443083
B3103C001D is Approaching the Vibration Investigative
Limit
10/21/2024
240009.002
RVH 7206 DPN A2 (File B616)
24.0009.001
RVH 7206 DPN A2 (File B616)
6I7212045-20
Internal External Wiring Diagram RPS Trip System 'B' CAB
H11P611 PT. 2
T
6I7212151-02
Schematic Diagram RX Protection System Motor-Generator
Set 'B'
Z
6I7212154-01
Internal and External Wiring Diagram RPS PWR Dist Cable
'A' and 'B' C71P001A and C71P011B
Q
Drawings
6SD7212531-13
Internal Wiring Diagram 130V ESF Battery Chargers
O
240019
Commercial Change Package: Online Leak Repair Near
B3100F056
10/17/2024
Engineering
Changes
DC240009
Replace Reactor Building Steam Tunnel R11 Door Latch
Mechanism with Manual Sliding Pins
Fire Plans
FPRB417b
Reactor Building Recirculation System Motor-Generator
Area, Zone 17, EL 659'0"
ODE20
Protected Equipment
Miscellaneous
Risk Management
Plant
950008820 - Critical Hot Spots on RPS 'B' Trip Cabinet
H11P611
11/15/2024
20.138.01
Recirculation Pump Trip
35.000.242,
UFSAR Analyzed Event Barrier Form
44.030.279
ECCS-Reactor Steam Dome Pressure-RHR Loop Select
Permissive Division 1, Channel Functional Test
Procedures
6I7212095-30
Schematic Diagram Nuclear Boiler PRCS Instrumentation A
and B Circuits Testability Modification
L
ARP 3D154
Recirculation System B Circulating Lube Oil Pump Auto
ARP 3D155
Recirculation System B Emergency Lube Oil Pump Auto
Start
EF2PRA011
Internal Flood Walkdown Summary Notebook
MMR Appendix H
Online Core Damage Risk Management Guidelines
MMR12
Equipment out of Service Risk Management
20A
MOP05100
Protected Equipment
2C
ODE2
PRS B Hotspot Repair
950008210
Install Temp Mod 240019
10/17/2024
Work Orders
950008820
H11P611 Hot Spot Repair Bypass Terminal CC9
11/18/2024
CARD 1625611
EQ Central Files EQ1EF2020 and -058 Lack Formal
Documentation for the Use of "Sound Reasons to the
Contrary" IAW 10CFR50.49 Par. (I)
07/14/2016
CARD 2126201
Pump E1151C001C (Div. I RHRSW Pump C) Exceeded IST
Alert Criteria
07/14/2021
CARD 2228972
Safety Issue - Program/Process Breakdown Leading to
Procedure Violations
08/23/2022
CARD 2231593
Oil Samples Not Being Shipped after Being Turned in
2/06/2022
CARD 2322542
Chemistry Samples to Ship Out
04/03/2023
CR202334791
CTG Lube Oil Samples at Warehouse B
11/30/2023
CR202436427
RHRSW Pump D in the Alert Range Low for Calculated D/P
2/20/2024
CR202440585
RHRSW Pump A D/P Near the Alert Range
06/28/2024
CR202441183
Leak from T4100F0375
07/26/2024
CR202442816
Divisional Battery Charger 2A2 Panel Mounted Ammeter
Failed to Calibrate
10/09/2024
CR202442844
Phasing Balance Acceptance Criteria Unsat for 2A2 Battery
Charger
10/10/2024
CR202443237
Samples Should Be No Longer Taken from the CTGs
10/28/2024
CR202443341
PT Event WO 73592852 Does Not Identify Chemistry Tasks
or Resources Required
10/30/2024
CR202443428
DC6048 Vol 1: Legacy Errors Discovered for Pipe Supports
P454630-G01 and P453352-G22
11/01/2024
CR202443891
RHRSW Pump B D/P Approaching IST Alert Limit
11/21/2024
Corrective Action
Documents
CR202444589
TMTE240026 ERVR117: Replace RHR Pump Motors A
and C Per EDP80186 in RF23
2/17/2024
6SD7212531-13
Internal Wiring Diagram 130V ESF Battery Chargers
O
Drawings
M46301
Hanger Drawing for P454630-G01
2019
ISI/IST Program Evaluation Sheet
Engineering
Evaluations
DC5803 Vol I
RHRSW Design Basis Requirements
A
245100
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
05/04/2024
71880678
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
05/28/2024
71907133
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
06/23/2024
71907147
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
08/18/2024
Work Orders
950008047
Phasing Balance Acceptance Criteria Unsat for 2A2 Battery
Charger
10/11/2024
2443700
E4150F001 Packing Gland Follower Live Loaded Washers
Crushed and Stem Found Dry
11/13/2024
CARD 2124430
Trip of RPS B, B EPA Tripped Causing Loss of RPS B
05/19/2021
CARD 2124511
Failed PMT During EPA B Channel Functional - 61260479
06/17/2021
CARD2320285
No Response From Division I North CCEA Radiation
Monitor
01/11/2023
CR202332515
EPA Breaker C7100S003B
08/22/2023
CR202436205
Received 3D18 IPCS Inputs Abnormal For Division II
CHRRMS Downscale
2/11/2024
CR202439322
Division 2 CHRRMS Failed Downscale during Performance
of 24.000.05
05/07/2024
CR202440138
Technical Specification 3.3.3.1 Required Action A.1 Will Not
be Completed in Required Time for Division II CHRRMS
06/07/2024
CR202440250
TS LCO Expired without Priority WO to Repair Condition
06/12/2024
CR202442633
UNSAT PMT on T4100B007
10/01/2024
CR202442684
Review Spare Motor Inventory for T4100B007 Supply Fan
Motor
10/03/2024
Corrective Action
Documents
CR202442699
Missing Bolts Discovered on Div. I CCHVAC Supply Fan
Plenum
10/03/2024
CR202442784
NQA - T4100B007 Motor Vibration Dampener Does Not
Align With Design Equivalent Change Package 700050
10/09/2024
CR202442927
Timing Chain As Found Out of Spec
10/14/2024
CR202442937
Emergency Overspeed Switch Oil Intrusion and Oil-Soaked
Wires
10/14/2024
CR202443092
RM1000 Battery Replacement PMs Missed Significant
Detail
10/21/2024
CR202443272
1518 DPM Lube Oil Leak Coming from Discharge Piping of
EDG11 Engine Driven Lube Oil Pump While EDG11
Running
10/28/2024
CR202443272
Governor Oil Level Low out of Green Band during EDG11
Fast Start
10/28/2024
Corrective Action
Documents
CR202443963
C7100S003G Failed to Trip When S1 Switch Was Placed in
CAL/TEST
11/25/2024
6I721N271117
Schematic Diagram Emerg. Diesel Generator 11, 12, 13,
and 14 Exciter - Voltage Regulator
X
6I721N271134
Schematic Diagram Exciter and Voltage Regulator and
Governor Control Diesel Generator 13
I218103
Process Radiation Monitor Subsystems System Diagram
I218104
System Diagram-Process Radiation Monitoring System
I218302
Schematic Wiring Diagram PRMS D11N436 A, B and
D11N437 A, B CAHRM D11N443A, B
T
I3010007
Instrument Loop Diagram Accident Monitor Containment
Area High Range Division I RY-D11K816A
G
Drawings
M57363
Control Center A/C Air System Functional Operating Sketch
K
Engineering
Changes
EDP 70050
CCHVAC Div, I T4100B007 Motor Vibration Dampener
10/05/2024
DC4535
Calculation for CAHRM System Instrumentation
C
EFA-E4124-002
Evaluation of E4100F067 Hydraulic Piston Seal
Engineering
Evaluations
ISI/NDE-IST
13029
IST Classification Change for E4100F067
24149
Dive Report: Fermi RHR Online Inspection Division I
ACMP 22011
Division I CCHVAC Supply Motor Vibrations
10/05/2021
Miscellaneous
E4100
High Pressure Coolant Injection Design Basis Document
G
HX Inspection
Report
10/14/2024
HX Inspection
Report
10/14/2024
HX Inspection
Report
10/14/2024
Operations
Evolution Order
HPCI November 2024 SSO
VMES22
Instruction Manual for Generator Excitation System
[CONFIDENTIAL]
A
Miscellaneous
Risk Management
Plan
WO 66248962 Risk Management Plan: License Renewal
Inspection Perform Division I RHR Reservoir Zebra Mussel
Inspection
11/04/2024
24.202.01
HPCI Pump and Valve Operability Test at 1025 PSI
27
24.202.08
HPCI Time Response and Pump Operability Test at 1025
24.307.45
EDG 11 Fast Start Followed by Load Reject
Instrumentation Installation Tubing ISO
D
ARP 3D38
Control Center Emergency Air Division I Radiation Monitor
Trouble
ARP 3D43
Division I/II Containment Area Radiation Monitor Trouble
Procedures
ARP3D39
Control Center Emergency Air Division II Radiation Monitor
Trouble
46682634
Perform 3Year Performance Test of N+1 Train Dominator
and Neptune Equipment
11/15/2018
50966856
Perform 3Year Performance Test of N Train Dominator and
Neptune Equipment
11/13/2018
289097
Perform 3Year Performance Test of N+1 Train Dominator
and Neptune Equipment
08/16/2021
256368
Perform 3Year Performance Test of N Train Dominator and
Neptune Equipment
08/19/2021
2051058
EDG 14 Inspect L1 Connections on EDG 14 AVR Card
10/28/2024
65617405
Perform 42.610.01 Div. I Alternate Feed EPAs E and G
Functional
08/24/2023
Work Orders
248962
License Renewal - Perform Division I RHR Reservoir Zebra
Mussel Inspection Dive
11/04/2024
66764024
Plant Health T4100B007 Failed PMT
10/01/2024
67684841
EDG 14 Heat Exchanger Eddy Current Test
10/16/2024
69041446
Perform 24.307.45 EDG 11 Fast Start Followed by Load
Reject
10/28/2024
950007928
T4100B007 Trial Vibration Dampener / Troubleshooting
10/05/2024
EP101
Classification of Emergencies
RERP Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
RERP Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
RERP Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
Procedures
RERP Plan
Fermi 2 Radiological Emergency Response Preparedness
Plan
Miscellaneous
Tabletop / Dynamic Learning Activity Drill Scenario
10/08/2024
Procedures
EP101
Classification of Emergencies
CARD 0700189
SBO DCS Cabinet S14P004 4B Cooling Unit Malfunction
05/26/2007
CR202441095
Diesel Fire Pump Fuel Oil Level Low - 7D2 is Locked in
07/22/2024
CR202441183
Leak from T4100F375 Instrument Line
07/26/2024
CR202441568
E4150F042 not Closing Remotely when Pushbutton
Depressed
08/14/2025
CR202441598
24 NRC License Renewal Inspection - R300F983B Leak
08/15/2024
CR202442282
Leak Identified During Leak Check on P50F512B and
P50F514B
09/18/2024
CR202443100
2F5A Pos 2A "M" Contactor Both Stationary and
Moveable Contacts Have Excessive Pitting
10/22/2024
CR202443161
1RX62 As Found Did Not Meet Acceptance Criteria
10/24/2024
CR202443747
dpm Leak from NW Corner of HPCI Main Pump
11/14/2024
CR202443891
RHRSW pump B D/P Approaching IST Alert Limit
11/21/2024
CR202444270
RHR Keep Fill Valve Leak By
2/12/2024
Corrective Action
Documents
CR202445573
11D65 CTG 11 DCS Trouble in Alarm
2/17/2024
LER 2023001-00
Loss of Mechanical Draft Cooling Tower Fan Brakes during
High Speeds Le Ads to Loss of Safety Function and
Inoperability
LER 2023001-01
Loss of Mechanical Draft Cooling Tower Fan Brakes during
High Speeds Leads to Loss of Safety Function and
Inoperability
LER 2023002-00
Technical Specification Completion Time Exceeded due to
Repairs on the MDCT Fan D
09/15/2023
LER 2023003-00
Reactor Pressure Boundary Leakage at Socket Weld on
Reactor Recirculation Sample Line Caused by Fatigue
Failure
10/19/2023
Miscellaneous
LER 2024001-00
Automatic RPS SCRAM on High RPV Pressure While
Attempting to Lower Generator Output during RF22
05/15/2024