IR 05000341/2024001
| ML24121A196 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/30/2024 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Peter Dietrich DTE Electric Company |
| References | |
| IR 2024001 | |
| Download: ML24121A196 (1) | |
Text
SUBJECT:
FERMI POWER PLANT, UNIT 2 - INTEGRATED INSPECTION REPORT 05000341/2024001
Dear Peter Dietrich:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2. On April 19, 2024, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding 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.
April 30, 2024 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Billy C. Dickson, Jr., 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:
I-2024-001-0073
Licensee:
DTE Electric Company
Facility:
Fermi Power Plant, Unit 2
Location:
Newport, MI
Inspection Dates:
January 01, 2024 to March 31, 2024
Inspectors:
J. Gewargis, Resident Inspector
R. Ng, Senior Project Engineer
T. Taylor, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., 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
Attempted Temporary Power Connection from Class 1E to Non-Class 1E Circuit Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2024001-01 Open/Closed
[H.4] -
Teamwork 71111.18 The inspectors identified a Green finding with an associated non-cited violation (NCV) of TS 5.4, Procedures, upon discovery of an electrical connection being made between 1E and non-1E electrical circuits in the plant. The licensee created a plant procedure to perform the connection, however, the requirement that the procedure would only be performed in modes 4 or 5 was not incorporated into the procedure.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000341/2022-002-00 LER 2022-002-00 for Fermi 2 Power Plant, Unexpected High Pressure Coolant Injection Turbine Trip 71153 Closed LER 05000341/2022-004-00 LER 2022-004-00 for Fermi 2 Power Plant, Containment Isolation Valve Actuator Found Disconnected from its Bonnet Resulting in Condition Prohibited by Technical Specifications 71153 Closed
PLANT STATUS
Fermi Unit 2 began the inspection period at or near 100 percent power. On January 16, 2024, the plant commenced a down power to approximately 60 percent to address indications of a main condenser tube leak. On January 17, the down power continued, and the plant was shut down on January 18 due to worsening chemistry from the main condenser tube leakage. On January 20, the plant was restarted based on isolating the leakage to one-half of the main condenser. The plant synchronized with the electric grid on January 22, and raised power to approximately 60 percent on January 23. The plant was returned to 100 percent power on January 29 following repairs to the main condenser. On January 29, power was reduced to approximately 70 percent for a routine rod pattern adjustment. Power was returned to 100 percent on January 30.
On February 13, the plant completed a down power to approximately 60 percent due to indications of main condenser tube leakage. Power was returned to 100 percent after repairs on February 22. On February 23, power was reduced to approximately 75 percent for a routine rod pattern adjustment, and power was returned to 100 percent on February 24. The plant remained at or near 100 percent power until March 22, when a power reduction to start the planned refueling outage commenced. During final preparations to trip the main turbine and reactor following the down power, a high pressure scram of the reactor occurred. No safety limits were violated, and no relief valves were lifted. After verifying the plant was stable, operators continued taking the plant to cold shutdown per the refueling outage schedule. The plant remained in the refueling outage for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) With severe winds and snow forecasted the week of January 8, 2024, the inspectors evaluated the conditions of the circulating water, general service water, and division I 120kV distribution systems for issues that could lead to initiating events.
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 II standby gas treatment system (SGTS) during division I SGTS cooler maintenance on January 5, 2024
- (2) Emergency diesel generator (EDG) 11 after the EDG 11 slow start on January 12, 2024
- (3) High pressure coolant injection (HPCI) post HPCI run on February 20, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Auxiliary building division I switchgear room on January 5, 2024
- (2) Standby gas treatment system (SGTS) division I and II rooms on January 10, 2024
- (3) Direct current motor control center area auxiliary building third floor on February 1, 2024
- (4) EDG 13 engine room on February 2, 2024
- (5) Auxiliary building 4th floor on February 12, 2024
- (6) T-room auxiliary building basement during the week ending February 23, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill: fire in the dress out area on auxiliary building 2nd level with search and rescue on February 6, 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 startup and power ascension following an outage to address condenser leakage during the week ending January 27, 2024
- (2) The inspectors observed and evaluated licensed operator performance in the control room during the down power and shutdown for an outage to address main condenser tube leakage on January 17 - 18, 2024
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated training on refueling outage RF22 permanent modifications on February 7, 2024
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Reactor core isolation cooling (RCIC) on February 20, 2024
- (2) Spurious alarms and contact issues on reactor protection system (RPS) and high pressure coolant injection (HPCI) circuits, completed the week ending March 23, 2024
- (3) Division I of the standby gas treatment system, completed the week ending March 23, 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 of station blackout battery charger R2103S007, completed the week ending February 3, 2024.
- (2) Troubleshooting of the south separator seal tank emergency drain valve on January 24, 2024
- (3) Division I non-interruptible air supply (NIAS) maintenance and resultant impacts to reactor building to torus vacuum breakers, with combustion turbine generator (CTG)11-1 OOS, on February 10, 2024
- (4) Fuel pool cooling and cleanup (FPCCU) safety system outage and high risk plan review on February 12, 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) Reactor pressure regulator issues during the week ending January 27, 2024
- (2) Usage of Technical Specification 3.0.4. during mode changes, and adherence to Technical Requirements Manual chemistry specifications the week ending January 27, 2024
- (3) Engine coolant levels on the diesel fire pump, completed the week ending February 3, 2024
- (4) Seismic monitor computer rendered nonfunctional and requiring restart on February 9, 2024
- (5) RHRSW pump 'D' alert range differential pressure on February 23, 2024
- (6) Storage of equipment by southwest quad, potentially impacting safety-related below during the week ending March 2, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Review of temporary power supply to the reactor building elevator HVAC system from a safety-related bus, completed the week ending March 31, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated activities associated with refueling outage 22, which commenced on March 23, 2024. The plant remained in the refueling outage the remainder of the inspection period. Activities performed included review of the outage risk plan, observation of shutdown and cooldown activities, drywell walkdowns, review of electrical and system lineups, and portions of reactor disassembly.
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 SGTS room cooler maintenance during the week ending January 6, 2024
- (2) EDG 12 jacket coolant pump replacement during the week ending January 27, 2024
- (3) RPS channel A2 main condenser agastat relay C7100M222C replacement, completed the week ending February 10, 2024
- (4) Division II control center radiation monitoring system calibration after power supply replacement on February 27, 2024
- (5) Division I NIAS planned maintenance on February 6, 2024, completed the week ending March 2, 2024
- (6) RCIC leakage test after declared inoperability due to check valve leak by on March 1, 2024
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) EDG 11 slow start surveillance on January 12, 2024
- (2) Division I mechanical draft cooling tower (MDCT) fan operability surveillance on February 8, 2024
- (3) Emergency equipment service water/cooling water (EESW/EECW) pump and valve surveillance on February 28, 2024
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) Low pressure coolant injection (LPCI) system and torus spray pump and valve surveillance on January 24, 2024
- (2) HPCI pump and valve surveillance on February 20, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Local leak rate test of valve P3400F409, division II post accident sampling system liquid inboard isolation valve, completed the week ending March 30,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 2 (January 1, 2023 through December 31, 2023)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) Unit 2 (January 1, 2023 through December 31, 2023)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) Unit 2 (January 1, 2023 through December 31, 2023)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) Unit 2 (January 1, 2023 through December 31, 2023)
===71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample 1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Change management and associated training related to the fire protection program surveillances and preventative maintenance items. Recently the site integrated the fire protection program preventative maintenance items and fire protection surveillances to the maintenance and operations department, respectively.
(2)
(Partial)
The inspectors commenced a review of information associated with the high pressure RPS scram that occurred during the shutdown of the plant for the refueling outage.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)===
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2022-002-00, Unexpected High Pressure Coolant Injection Turbine Trip, (ADAMS Accession No. ML22187A109). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is Closed.
- (2) LER 2022-004-00, Containment Isolation Valve Actuator Found Disconnected from its Bonnet Resulting in Condition Prohibited by Technical Specifications (ADAMS Accession No. ML22304A009). The circumstances surrounding this LER are documented in Inspection Report 05000341/2022003 under Inspection Results Section 71111.12. This LER is Closed.
INSPECTION RESULTS
Attempted Temporary Power Connection from Class 1E to Non-Class 1E Circuit Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000341/2024001-01 Open/Closed
[H.4] -
Teamwork 71111.18 The inspectors identified a Green finding with an associated non-cited violation (NCV) of TS 5.4, Procedures, upon discovery of an electrical connection being made between 1E and non-1E electrical circuits in the plant. The licensee created a plant procedure to perform the connection, however, the requirement that the procedure would only be performed in modes 4 or 5 was not incorporated into the procedure.
Description:
On March 15, 2024, the inspectors conducted a plant tour and noted workers dressed in electrical safety gear near the 480-volt motor control centers (MCCs) 72F-4A and 72E-4B in the reactor building. The inspectors questioned the workers and discovered a temporary power connection was being made per plant procedure 35.TMP.044, Temporary Power for Reactor Building Elevator A/C Unit, Revision 1. The connection was from a spare breaker position on 72F-4A (safety-related, or class 1E) to the load side of the breaker supplying the reactor building elevator's air conditioning (A/C) system on 72E-4B (non-safety-related/non-class 1E). The connection was needed because of an electrical bus outage planned during the upcoming refueling outage. The workers were preparing to splice an electrical cable between the two points. The inspectors questioned the operating shift, maintenance, and engineering personnel on how the licensee justified the connection while the plant operated in mode 1. Pending a response to the inspectors' questions, the licensee stopped work before energizing the temporary power supply.
The creation of plant procedure 35.TMP.044, Revision 1, was intended to enable the connection of temporary power to the reactor building elevator A/C system. However, the procedure, issued on February 28, 2024, did not contain restrictions regarding plant operating mode nor descriptions of how component operability could be impacted. This oversight had serious implications for safety-related loads. The procedure was being performed in mode 1, which requires both divisions of emergency AC power to be operable along with the respective distribution systems. In contrast, in modes 4 and 5, only one division of emergency AC power and one division of AC distribution are required to be operable. The procedure involved cubicle doors being left ajar on the busses, but during its creation, the effects of medium energy line breaks (MELBs) had not been considered. Additionally, potential faults on the non-safety-related loads had not been analyzed for their impacts on safety-related loads. The effects of the added load on the associated EDG during a loss of offsite power event had also not been analyzed, posing potential safety risks.
Upon being questioned by the inspectors, the licensee promptly took corrective actions. They refrained from completing the electrical connection until the plant was in modes 4 and 5, when HELBs/MELBs were no longer a concern, and the bus was not required to be operable.
Furthermore, the procedure was revised to clearly state its applicability only in modes 4 and 5, ensuring compliance with safety regulations.
Corrective Actions: The licensee stopped work and prevented the electrical connections between the class 1E and non-class 1E circuits from being made. The procedure was also revised to state it was only applicable in modes 4 and 5.
Corrective Action References: CR 2024-36954
Performance Assessment:
Performance Deficiency: Licensee procedure MGA02, Procedures, Manuals, and Orders, Revision 55, outlines requirements for creating plant procedures. Section 5.2 requires that procedure to be reviewed for technical adequacy and Section 8.1 requires completion of checklist MGA02001, which requires precautions and limitations to be included. However, procedure 35.TMP.044 did not receive an adequate technical review as the effects of MELBs, additional EDG loading, and impacts of non-safety-related component faults were not analyzed when approving the procedure. Further, appropriate precautions or limitations were not included.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, absent NRC intervention, an electrical configuration would have existed outside existing analyses, calling into question the ability of various safety-related components to perform their functions. The inspectors utilized IMC0612, Appendix E, example 5a to inform their determination.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, since the electrical connection was never made, all questions in Exhibit 2, Section A, of IMC 0609 Appendix A were answered 'no.'
Cross-Cutting Aspect: H.4 - Teamwork: Individuals and work groups communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety is maintained. Specifically, during creation of 35.TMP.044, some individual(s) believed the intent was for it to be performed only in modes 4 and 5. However, the approved procedure did not reflect those restrictions. Further, the work activity was scheduled to occur in mode 1.
Enforcement:
Violation: Technical Specification 5.4, Procedures, requires, in part, that written procedures shall be established, implemented. and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2. Appendix A. February 1978. Section 9 of Regulatory Guide 1.33 addresses procedures for performing maintenance and states, in part, that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures appropriate to the circumstances.
Contrary to the above, maintenance to connect temporary power from safety-related bus 72F-4A to non-safety-related bus 72E-4B was not preplanned and performed in accordance with written procedures appropriate to the circumstances. On March 15, 2024, execution of 35.TMP.044 was in progress; however, the procedure did not consider the potential adverse effects of MELBs, electrical faults, and additional EDG loading the non-safety-related components would have on safety-related components while 72F-4A was required to be operable.
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 April 19, 2024, the inspectors presented the integrated inspection results to Peter Dietrich and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
23.101
107
Procedures
23.131
General Service Water System
114
CARD-18-26135
Div. I SGTS Exhaust Fan Supply Vortex Damper Failed to
Operate
08/14/2018
Corrective Action
Documents
CARD-21-23701
Tubing Ordered for WO Does Not Match Tubing in Plant
04/27/2021
Standby Gas Treatment System Diagram Instrumentation
and Controls
R
Diagram Standby Gas Treatment and Primary Containment
Purge System Reactor Building
Emergency Diesel Generator System Functional Operating
Sketch
BL
Standby Gas Treatment System Functional Operating
Sketch
Drawings
P and ID Diesel Generator System Div. I RHR Complex
T46-00
Design Basis Document: Standby Gas Treatment System
Miscellaneous
Calibration Specification Sheet: Standby Gas Treatment
(SGT) Exhaust Fan T4600C004 Div. 2
05/20/2019
23.202
High Pressure Coolant Injection System
119
23.307
Emergency Diesel Generator System
135
23.404
Procedures
High Pressure Coolant Injection System Functional
Operating Sketch
FP-AB-2-9b
Auxiliary Building, Division I Switchgear Room, Zone 9, EL.
613'6"
FP-AB-3-14F
Auxiliary Building, DC Motor Control Center (MCC) Room
Zone 14, EL. 643'-6"
FP-AB-4-16C
Auxiliary Building Ventilation Equipment Room, Zone 16, EL.
659'6"
FP-AB-5-16A
Auxiliary Building, North Standby Gas Treatment System
(SGTS) Room, Zone 16, EL.677'6"
Fire Plans
FP-AB-5-16B
Auxiliary Building, South Standby Gas Treatment System
(SGTS) Room, Zone 16, EL.677'6"
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-RB-B-5C
Reactor Building Basement Corridors Zone 5, E
- L. 562, and
EL. 564
FP-RHR-1-13-
RHR Complex, EDG-13 Room, EL. 590'
LP-FP-940-2412
Fire Drill Evaluation: 2nd Floor Auxiliary Building Personal
Changing Room, Class A Fire
Miscellaneous
Training Material:
LP-OP-202-2414
RF22 Modifications Training
2.000.02
Plant Startup to 25% Power
110
2.000.03
Power Operation 25% to 100% to 25%
108
2.000.04
Plant Shutdown from 25% Power
23.205
Residual Heat Removal System
149
Procedures
24.603.02
SRM/TRM/APRM Overlap Verification
23-30437
HPCI Inboard Torus Suction Isolation Valve Abnormal
Stroke
05/23/2023
23-30997
3D93 Neutron Monitoring System Channel Trip Received
06/18/2023
23-32868
E4150F006 Will Not Stay Closed While Performing
24.202.05 Section 5.1
09/06/2023
23-33899
3D93 Neutron Monitoring System Channel Trip Spurious
Alarms
10/22/2023
24-36108
3D93 Neutron Monitoring System Channel Trip Spurious
Alarms
2/06/2024
24-36518
E4150F042 HPCI Booster Pump Suct from Supr Pool Iso
MOV Failed to Close
2/25/2024
24-36597
Failure of Div 1 SGTS Upstream HEPA Filter In-Place Test
2/28/2024
24-36605
Degraded Gasket on Div 1 SBGT Filter Unit Air Inlet Heater
Termination Cover
2/29/2024
2-26436
3D93 Neutron Monitoring System Channel Trip Received
with No Apparent Cause
05/18/2022
2-28826
Differential Pressure for Div 1 Standby Gas Treatment
System Moisture Separator is at the Spec of 0.5" H2O per
23.404 P&L 3.1
08/18/2022
CARD-13-24415
Packing Leak on E5100F053
06/20/2013
Corrective Action
Documents
CARD-14-20569
01/28/2014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD-14-22669
Leakage Identified during RPV Pressure Test E5150F008
03/21/2014
CARD-14-26438
Packing Leak on E5150F046
08/12/2014
CARD-20-31076
Revise Tolerances on E51N006
10/08/2020
CARD-23-20919
2PA1 Pos 1B Feed to RCIC Barometric Condensate Pump
260VDC Switch Is Not Making Contact
2/02/2023
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-2023-345850
E5150-F026 Packing Leak Has Increased
2/04/2023
CR-2023-35172
Inaccurate Information from Vendor on MCC Eaton
Disconnects Leads to Updates of Equipment Cause
Evaluation and Outage PMs
2/19/2023
Reactor Core Isolation Cooling System Sketch Functional
Operating Sketch
I-2080-23
Visual Annunciator and Sequence Recorder Alarm
Schematic
S
I-2145-18
Power Range Neutron Monitoring Reactor Protection
System Outputs
H
I-2155-06
RPS Trip System A Trip Relays
W
I-2155-08A
RPS Trip System A2 Scram Trip Logic
C
I-2221-05
HPCI SYS-Pump Discharge Isolation Valves E4150F006
and F007
I-2221-08
HPCI SYS Suppression Pool Isolation Valves E4150F041
and F042
Z
Drawings
I-2225-04
HPCI Logic Circuit Part 2
V
Engineering
Evaluations
TE-E41-12-027
Evaluate Effect of AOV E4100F054 Remaining Open until
RF15
43.404.001
Standby Gas Treatment Filter Performance Test Division 1
ARP 3D93
Neutron Monitoring System Channel Trip
MWC06
Work Screening and Processing
Procedures
MWC07
Online Scheduling Process
35445274
Steam Leak on E5150F054
2/16/2014
37976580
03/18/2014
Work Orders
37976612
RCIC AOV Packing Leaks/Bad Stem Replace Valve
11/04/2015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
38182487
Leakage Identified During RPV Pressure Test E5150F008
03/22/2014
60850744
Vent Header Recoat Project Requires SGTS D2 Charcoal
Replacement
04/06/2021
226505
Replace Division 1 SGTS Upstream HEPA Filters
05/06/2022
70435403
Work Orders Needed to Test SGTS Charcoal Following
Drywell Moisture Barrier Replacement in RF22
2/20/2023
70880193
Standby Gas Treatment System Div 1 Moisture Separator
D/P at High Mark
2/06/2024
24-35948
Smoke Coming from SBO House 125VDC Battery Charger
01/31/2024
Corrective Action
Documents
24-36104
CTG 11-1 Failed to Achieve Base Load and Failed PMT
2/05/2024
One Line Diagram AC and DC Systems
B
Wiring Diagram for DCS Term Cab 1A (S14P001) Front
View (Zones A and B) Rear View (Zones C and D)
A
Diagram Feedwater Heater Drains, Emergency Drains, and
Heat Air Vents System
Fuel Pool Cooling and Cleanup System Functional
Operating Sketch
T
Fuel Pool Cooling and Cleanup System Functional
Operating Sketch
T
Fuel Pool Filter Demin System Functional Operating Sketch
K
Fuel Pool Filter Demineralizer System Functional Operating
Sketch
K
Feedwater Heater Drains, Vents, and Emergency Drains
Functional Operating Sketch
Nitrogen Interting System Functional Operating Sketch
One Line diagram 13.8Kv
BH
Drawings
DSD721F-164
25VDC Diagram [CONFIDENTIAL]
J
SCR 24-0008
50.59 Screen: TM 24-0003
Engineering
Evaluations
TM 24-0003
N22F414B Temporary Support Plate Installation
Operations logs, February 5, 2024 thru February 7, 2024
Plan of the Day
2/09/2024
P50-02.03
Control Air System
C
Miscellaneous
Risk
Risk Management Plan: 66384440 Rework G4100F002B
2/12/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Management
Plan
FPCCU Isolation Valve and G4100F012B
TSC 89-011
Non-Interruptible Control Air System Operability and
Compliance of Limiting Condition for Operations
23.205
149
Procedures
23.708
Fuel Pool Cooling and Cleanup System
23-32706
Diesel Fire Pump Coolant Water Reservoir Needs to Be
Replenished
08/31/2023
23-33313
DFP Right Angle Drive Particle Count Above Expected
Value
09/27/2023
23-35159
Diesel Fire Pump Right Angle Drive Oil Particle Count High
Out of Specification
2/20/2023
24-35422
Diesel Fire Pump Coolant Level Issue
01/09/2024
24-35449
DFP Coolant Level Low
01/09/2024
21-20069
T5000F404B Seat Leakage
01/04/2021
CARD 20-22467
IST to investigate implementing 2 Pump Testing of the
RHRSW Pumps
03/06/2020
CARD-15-21042
Inadequate Procedural Guidance for Past Operability
Reviews
2/09/2015
CARD-17-21711
Process for Flagging Past Operability Reviews in CARDs
Inadequate
09/15/2023
CARD-20-22410
RHRSW Pump D DP Approaching IST Alert Limit
03/04/2020
CR-2024-35747
Pressure Regulator #1 Not Tracking with Pressure Regulator
- 2 and Unable to Be Selected as Controlling Regulator
01/20/2024
CR-2024-35761
Pressure Regulator Issues during Startup
01/21/2024
Corrective Action
Documents
CR-2024-36427
RHRSW Pump D in the Alert Range Low for Calculated D/P
2/20/2024
24-36644
Wrong Revision of MOP23002 Used
03/01/2024
24-36644
NRC Identified: Wrong Revision of MOP23002 Used
03/01/2024
Corrective Action
Documents
Resulting from
Inspection
24-36759
NRC Identified-Variety of Plant Storage Issues in the
Reactor Building
03/06/2024
Diagram Residual Heat Removal Division II
Functional Operating Sketch Traversing Incore Probe
System
H
Drawings
Primary Containment Monitoring System Functional
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operating Sketch
P and ID RHR Service Water System Division II RHR
Complex
AH
16-022
ISI/NDE-IST Program Evaluation Sheet: Evaluation of SOE
15-07 Data and Establishing New Acceptance Criteria for
E1151C001D
2-019
IST Program Acceptance Criteria for RHRSW B Pump
24.205.06
Division II RHRSW Pump and Valve Operability Test
66340315
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
2/20/2024
Engineering
Evaluations
TE-ANE-24-001
TRLCO 3.0.4(b) Mode Change Restraint Assessment for FO
24-01
CHS-PRI-06
Chemistry Specifications: Reactor Water
N3012A
Fermi 2 Nuclear Training - Operations Systems Student
Test, Governor/Pressure Control
Miscellaneous
VMB11-60.1
Installation, Operation and Maintenance Driver Manual
[CONFIDENTIAL]
2.000.03
Power Operation 25% to 100% to 25%
108
23.109
Turbine Operating Procedure
100
23.110
Unitized Actuator System
23.612
Seismic Monitoring
44.090.003
Seismic Monitoring-Active Seismic Monitoring System
Channel Check
44.180.005
Main Turbine Bypass System Response Time Test and
Functional Test
44.180.005
Main Turbine Bypass System Response Time Test and
Functional Test
CR-2023-33665
Active Seismic Central Recorder has Abnormal Indications
Following 44.090.001
10/11/2023
CR-2024-36158
Active Seismic Monitor System Found in Abnormal State
2/07/2024
MCE03
Chemistry and Environmental Monitoring Conduct Manual
MES27
Verification of System Operability
2A
MES58
Technical Evaluations
5B
Procedures
MES82
Technical Specification Surveillance Frequency Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Program
MLS05
Notifications/General Regulatory Reporting Requirements
MOP23
Plant Storage
64808082
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
09/11/2023
65564354
Perform 24.205.06 Division 2 RHRSW Pump and Valve
Operability
2/11/2023
Work Orders
70844865
License Renewal Perform RHR Pump B&D First Floor Hoist
and Trolley Inspections
2/02/2024
Corrective Action
Documents
Resulting from
Inspection
24-36954
NRC Discovered Potential Issue with TMP 24-005
03/15/2024
DC-5512 Volume
Evaluation of 1E/Non-1E Separation Criteria
C
Engineering
Evaluations
TSR-100511
Post DC-5512 Vol 1 for Implementing Temp Power
Procedure 35.TMP.044
Procedures
35.TMP.044
Temporary Power for Reactor Building Elevator A/C Unit
and 1
Work Orders
68341691
Pre RF22 Install Temp Power for RB ELEV Cooling
(72E-4B)
05/04/2023
2-21434
Valve E1100F060A is Very Difficult to Close
2/09/2022
Corrective Action
Documents
2-24619
Actuator Broken during Reassembly
04/03/2022
24-37146
NRC Concerns-Large Box within 2 Feet of Potential
Important to Safety Equipment and Box Close to NIAS
Piping
03/23/2024
24-37278
NRC Identified-Motor/Actuator Missing Cover in Drywell
Basement
03/26/2024
24-37279
NRC Identified-Potentially Missing Insulation in Drywell
Basement
03/26/2024
24-37280
NRC Identified-Leak from P4400-F274 in Drywell Basement
03/26/2024
Corrective Action
Documents
Resulting from
Inspection
24-37282
NRC Identified-Potentially Loosened Support in Drywell
Basement
03/26/2024
M-2084
Residual Heat Removal Div 1
BS
Drawings
M-2090
System Diagram Nuclear Boiler System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M-5007
Primary Containment Pneumatic Supply System
Z
M-5707
Core Spray System Functional Operating Sketch
AJ
M-5730-5
Interruptible Control Air Reactor Building Functional
Operating Sketch
AG
SD-2500-01
One Line Diagram Plant 4160V and 480V System Service
Engineering
Changes
2-0009
Remove Testable Function from Check Valve E2100F006A
Miscellaneous
G4100-000150
Clearance for Reactor Vessel Flood-Up
03/24/2024
2.000.03
Power Operation 25% to 100% to 25%
108
2.000.04
Plant Shutdown from 25% Power
23.205
149
23.708
Procedures
24.203.04
Core Spray Valve Operability and Position Verification Test
CR-2024-35869
EDG-12 Standby Jacket Coolant Pump Above Shutdown
Limit Recommended by Engineering
01/24/2024
Corrective Action
Documents
CR-2024-35888
Higher than Expected Resistance to Rotation on New
Standby Jacket Coolant Pump assembly MM#100312369
01/25/2024
Schematic Diagram Nuclear Steam Supply Shut Off System
Trip System A
O
Schematic Diagram Reactor Protection System Testability
Modification
M
Residual Heat Removal Division II Functional Operating
Sketch
Residual Heat Removal Division II Functional Operating
Sketch
Reactor Water Cleanup Reactor Building Functional
Operating Sketch
Reactor Feedwater System Functional Operating Sketch
Non-Interruptible Control Air System Division 1 and 2
Functional Operating Sketch
Emergency Diesel Generator System Functional Operating
Sketch
BL
P and ID Diesel Generator System Division I RHR Complex
Drawings
I-2400-10
Sample Line Tie-In and Return Diagram Post Accident
J
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sampling System
I-2400-11
Post Accident Sampling System Piping Interconnection
Diagram
N
23.205
Residual Heat Removal System
149
24.202.01
HPCI Pump and Valve Operability Test at 1025 PSIG
25
24.204.01
Division I LPCI and Suppression Pool Cooling and Spray
Pump and Valve Operability Test
24.205.08
Division I RHR Cooling Tower Fan Operability and Valve
Lineup Verification Test
24.206.01
RCIC System Pump and Valve Operability
24.208.02
Division I EESW and EECW Makeup Pump and Valve
Operability Test
24.307.14
EDG 11 Start and Load Test-Slow Start
35.318.017
Maintenance Procedure
54A
43.401.300
Local Leakage Rate Test Type C-General
43.401.405
Local Leakage Rate Testing for Penetration X-210B
43.401.515
RCIC Pressure Isolation Valve Leak Test
44.020.059
Surveillance Procedure
47.000.02
Mechanical Vibration Measurements for Trending
46A
64.120.041
Containment Area High Range Radiation Monitor Division 2
Calibration
Reactor Core Isolation Cooling Sketch Functional Operating
Sketch
MES27
Verification of System Operability
2A
MES58
Technical Evaluations
5B
MMA06
Interim Alterations
8B
Procedures
MQA11-100
Operability Determination Process
60495674
Perform 64.120.041 Containment Area High Range
Radiation Monitor Division II Calibration
01/17/2024
63543821
License Renewal-T4100B016 Inspect, Lube, and Check
Belts
01/03/2024
65398830
Calibrate Division 1 Control Air Instruments
05/30/2022
Work Orders
65475211
Replace RPS Channel 'A2' Main Condenser Agastat Relay
2/05/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C7100M222C
65638746
Perform 24.802.02 D1 EESW Pump and Valve Operability
11/29/2023
65788678
Perform 24.307.14 Section 5.1 EDG 11 Start and Load
Test-Slow Start
01/08/2024
65984824
Perform 24.204.01 DIV. I LPCI and Torus Cooling Spray
Pump and Valve Operability Test
01/11/2024
66186578
Perform 24.205.08 Division I RHR Cooling Tower Fan
Operability and Valve Lineup Verification Test
2/08/2024
287377
Perform 24.202.01 HPCI Pump/Flow Test and Valve Stroke
at 1025 PSIG
2/20/2024
66447792
Final 43.401.405 LLRT for X-210B (Test-4 P34F409)
03/27/2024
66456204
Perform 24.802.02 D1 EESW Pump and Valve Operability
2/28/2024
70612648
Replace the Pump and Motor Assembly for R3001C027
EDG12 JC STBY PMP
01/25/2024
Corrective Action
Documents
23-31768
Elevated Temperatures C Condenser Pump >265 Degrees
Fahrenheit
07/23/2023
Licensing Performance Indicator - Safety System Function
Failure IRIS Data Entry, Verification and Approval
01/2023 -
2/2023
Operating Data Report
01/2023 -
2/2023
71151
Miscellaneous
23 Operators Narrative Log
Various
Dates
CR-2023-31533
NQA Notice of Elevation - Change Actions Associated with
the Ownership Transition of the Fire Protection Program
Off-Track
07/12/2023
CR-2023-323116
Investigate Classifications of Fire Protection Performance
Tests PT vs PTT
08/04/2023
CR-2023-35199
Job Analysis for Fire Protection Activities Assigned to
Operations Department
2/20/2023
CR-2024-35445
License Renewal-AMP B.1.16 External Surfaces Monitoring
PTT WO's Cancelled
01/08/2024
CR-2024-36389
Potential Challenges to Industrial and Nuclear Safety due to
Improper Fire Protection Training
2/19/2024
Corrective Action
Documents
CR-2024-36490
Safety Concern: NQA Fire Protection Escalation Ineffective
2/23/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
at Correcting Deficiencies in Fire Protection Program
2.000.04
Plant Shutdown from 25% Power
Procedures
MES55
Transient Analysis Program
58748762
Perform 28.501.04 Fire Suppression and Sprinkler System
Valve Operability Test
06/15/2022
281876
Perform 28.501.04 Valve Operability for T8000F037
04/06/2022
2468187
Perform 28.501.04 Fire Suppression and Sprinkler System
Valve Operability Test-License Renewal
04/07/2023
65034551
Perform 28.501.04 Valve Operability for T8000F037
07/23/2023
Work Orders
65973610
Perform 28.501.02 Fire Suppression Water System Valve
Lineup Verification
01/24/2024
Corrective Action
Documents
CARD-22-26226
Unexpected HPCI Turbine Trip
05/11/2022
Miscellaneous
LER 2022-004-00
Containment Isolation Valve Actuator Found Disconnected
from its Bonnet Resulting in Condition Prohibited by
Technical Specifications.
10/31/2022
Procedures
35.202.009
HPCI Steam Turbine-General Maintenance
53455389
Calibrate HPCI Turbine Governor Speed Loop
2/16/2021
58642933
Replace and Calibrate HPCI Ramp Generator and Signal
Converter
2/15/2021
267358
Unexpected HPCI Turbine Trip. Troubleshoot and Repair
05/11/2022
Work Orders
269101
Replace Failed HPCI Speed Sensor
05/12/2022