IR 05000266/2025004
| ML26040A343 | |
| Person / Time | |
|---|---|
| Site: |  |
| Issue date: | 02/10/2026 |
| From: | Sanchez E NRC/RGN-III/DORS/RPB2 |
| To: | Coffey B NextEra Energy |
| References | |
| IR 2025004 | |
| Download: ML26040A343 (0) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2025004 AND 05000301/2025004
Dear Bob Coffey:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On January 20, 2026, the NRC inspectors discussed the results of this inspection with Thad Edmonds, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding 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 Point Beach Nuclear Plant.
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 Point Beach Nuclear Plant.
February 10, 2026 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 Nos. 05000266 and 05000301 License Nos. DPR-24 and DPR-27 Enclosure:
As stated cc w/ encl: Distribution via GovDelivery Thad Edmonds, Site Vice President Signed by Sanchez Santiago, Elba on 02/10/26
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Point Beach Nuclear Plant, 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 Promptly Identify a Condition Adverse to Quality Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000266,05000301/2025004-01 Open/Closed
[H.11] -
Challenge the Unknown 71111.15 On September 15, 2025, a Green finding and an associated NCV of 10 CFR Part 50,
Appendix B, Criterion XVI, Corrective Action, was self-revealed for the licensees failure to promptly identify increased moisture in the safety-related south bank air receivers that rendered the G-02 emergency diesel generator inoperable due to a stuck open air start valve.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power and remained at or near full power throughout the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power and remained at or near full power throughout 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
71111.04 - 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) Unit 1 safety injection system on October 22, 2025
- (2) Unit 2 residual heat removal system on October 23, 2025
- (3) Unit 1 component cooling water system on October 29, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) Fire Zones 162, 163, 164, 165, 166, 167:
Unit 2 charging pump rooms and hallway, gas treatment area, and pipeway 4 valve gallery on October 24, 2025
- (2) Fire Zones 237, 238:
Component cooling water heat exchanger, boric acid room and plant auxiliary building 46' general area on October 24, 2025
- (3) Fire Zones 152, 153, 154, 155, 156, 158, 159:
Unit 1 charging pump rooms and hallway, laundry tank room, pipeway 1 valve gallery, and heating, ventilation and air conditioning equipment room on October 30, 2025
- (4) Fire Zones 319, 320, 321, 323, 324:
Non-vital switchgear room, swing battery room, and condensate storage tank area on November 4, 2025
- (5) Fire Zones 101, 104, 105, 108, 109:
Unit 1 and Unit 2 residual heat removal pump rooms and primary auxiliary building -19' general area on November 5, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) An inspector reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between September 2, 2025, and October 23, 2025.
Seventy operators were examined. This population is one short of the number in RPS OL Report 9. The one individual not examined is currently licensed as a Reactor Operator undergoing training for upgrade to Senior Reactor Operator in the current class. Excusal from completing the requalification examination cycle is permissible per NUREG-1021.
One operator failed the JPM portion. This individual was remediated the following week. No concerns for the method of remediation. Additional action is not warranted per IP 711111.11A.
TABLE 03.03-1 EXAMINATION RESULTS
1. Total number of licensed operators. 71
2. Number of licensed operators administered a requalification examination
required by 10 CFR 55.59(a). 70
3. Number of individual licensed operators who failed any portion of a
requalification examination (written, JPM, or individual simulator scenario failures). 1
4. Divide line 3 by line 2 to obtain the individual requalification examination
failure rate. Line 3/Line 2. 1.4%
5. Number of crews administered simulator scenarios as part of a requalification
examination required by 10 CFR 55.59(a). 12
6. Number of crews who performed unsatisfactorily on the simulator scenarios. 0
7. Divide line 6 by line 5 to obtain the crew simulator scenario failure rate.
Line 6/Line 5. 0%
The failure rate (1.4%) is below threshold for additional actions of IP 71111.11A (20%).
The licensee and NRC staff discussed future dates for Licensed Operator Requalification examinations in 2026.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during high-risk maintenance activities performed on Unit 1 and Unit 2 on October 7, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated an annual operator requalification scenario on October 22, 2025.
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 (SSCs) remain capable of performing their intended function:
- (1) Post-accident containment temperature, pressure, and hydrogen concentration instrumentation
- (2) Safety-related cable vault structure and alarms
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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) Elevated risk during Unit 2 crossover steam dump testing on October 7, 2025
- (2) Elevated risk during Unit 1 reactor protection and safeguards logic tests on October 9, 2025
- (3) Elevated risk during new fuel receipt and heavy lifts over the spent fuel pool on December 2, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Functionality of 13.8 kilovolt bus H-01 with high resistance readings
- (2) Operability of residual heat removal pump found with high vibrations
- (3) Operability of emergency diesel generator G-02 transformer 2X-06 with temperature monitor breaker found off
- (4) Operability of the emergency diesel generators when new diesel fuel chemistry specifications were found below acceptable limits
- (5) Operability of emergency diesel generator G-02 after the south bank of starting air depressurized
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) (4 Samples)
- (1) Unit 1 charging pump, 1P-2C, restoration following controller replacement on October 17, 2025
- (2) Station battery PMT following replacement of a faulty cell on October 22, 2025
- (3) Unit 1 residual heat removal PMT following pressure transmitter replacement on December 1, 2025
- (4) Condensate storage tank A and B return to service following internal coating inspections on December 1, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) TS 82, G-02 emergency diesel generator operability test on November 9, 2025
- (2) IT 08B, turbine driven auxiliary feedwater pump suction from service water motor operated valve exercise test on November 12, 2025
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
1. License Amendment Request of October 4, 2022, as supplemented by other
requests (ML22278A031)
2. Safety Evaluation Report dated December 13, 2024 (ML24285A103)
This evaluation does not constitute NRC approval.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2024, through September 30, 2025)
- (2) Unit 2 (October 1, 2024, through September 30, 2025)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2024, through September 30, 2025)
- (2) Unit 2 (October 1, 2024, through September 30, 2025)71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Corrective actions taken for Part 21 notification associated with ASCO NP8321 series solenoid used in applications with extended periods of de-energization
- (2) Repeat Rod Control Failures
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) FLEX Equipment Performance Issue Trends
INSPECTION RESULTS
Failure to Promptly Identify a Condition Adverse to Quality Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000266,05000301/2025004-01 Open/Closed
[H.11] -
Challenge the Unknown 71111.15 On September 15, 2025, a Green finding and an associated NCV of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, was self-revealed for the licensees failure to promptly identify increased moisture in the safety-related south bank air receivers that rendered the G-02 emergency diesel generator inoperable due to a stuck open air start valve.
Description:
On September 15, 2025, the licensee was performing a monthly operability test for G-02, the Unit 2, A-train emergency diesel generator (EDG). Following the successful start of the EDG, operators noticed that the south starting air bank was continuously depressurizing. Upon further investigation, the licensee identified that the south bank air start valve remained open, causing the south air bank pressure to lower until the receivers were completely depressurized. The EDG was secured, and the starting air inlet isolation was shut to isolate the leak. The licensee declared the starting air system for G-02 inoperable, declared G-02 inoperable, and aligned the Unit 1 A-train EDG to provide power to the Unit 2 safety related buses. This is also when the inspectors became aware of the issue.
The licensee began troubleshooting this issue and identified that DA-3058B, the south air bank air start valve, was stuck in the open position due to corrosion in the spring cap. The valve was repaired and the EDG was returned to service following satisfactory post-maintenance testing.
Additional investigation revealed that the likely cause of the corrosion was increased moisture buildup in the south bank air receivers. Operators blow down the EDG air receivers every month and measure the amount of liquid removed using procedure PC 45 Part 1, Periodic Blowdown of Air Receivers and Piping. Over the past 2 years, there has been a significant increase in the amount of moisture in this bank of air receivers. However, there was no condition report written for this issue until after the failure.
Industry operating experience has shown that moisture buildup in air tanks and receivers can lead to corrosion of various components. In this case, the increased moisture in the south air bank led to corrosion buildup in the cap of the safety-related air start valve. This corrosion resulted in the air receivers completely depressurizing and operators declaring the EDG inoperable. The increase in moisture levels documented in the monthly blowdowns in the air receivers was well within the licensees ability to identify and investigate prior to it leading to the inoperability of the EDG.
Corrective Actions:
The licensee repaired the stuck open air start valve. They are working to identify and repair any air leaks in the system.
Corrective Action References: ARs 2523634, 2524042, 2524061, 2524063, 2532458
Performance Assessment:
Performance Deficiency:
The inspectors determined that the licensees failure to promptly identify the increased moisture buildup in the G-02 EDG south bank air receivers, as required by 10 CFR 50 Appendix B, Criterion XVI, Corrective Action, was a performance deficiency.
Screening:
The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the 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, the licensee failed to promptly identify a condition adverse to quality that resulted in the emergency diesel generator being declared inoperable.
Significance:
The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
Specifically, the inspectors determined the finding was of very low safety significance (Green)because the inspectors answered no to all the screening questions in Exhibit 2.
Cross-Cutting Aspect:
H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. Specifically, no one questioned the amount of moisture being removed from the G-02 south bank air receivers despite this amount being much higher than any of the other air receivers.
Enforcement:
Violation:
10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures be established to assure that conditions adverse to quality, such as deficiencies and nonconformances, are promptly identified.
Contrary to the above, prior to September 15, 2025, the licensee failed to identify a condition adverse to quality associated with increased moisture in the safety-related south bank air receivers. Specifically, this increased moisture in the system led to corrosion of the south air bank air start valve, which was a condition adverse to quality that rendered the G-02 emergency diesel generator inoperable.
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 December 3, 2025, the inspectors presented the emergency preparedness inspection results to Mr. D. Smith, EP Manager, and other members of the licensee staff.
- On January 20, 2026, the inspectors presented the integrated inspection results to Thad Edmonds, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
110E017 Sheet 1
P&ID Safety Injection System Unit 1
110E017 Sheet 2
P&ID Safety Injection System Unit 1
110E017 Sheet 3
P&ID Safety Injection System Unit 1
110E018 Sheet 1
P&ID Auxiliary Coolant System
110E018 Sheet 2
P&ID Auxiliary Coolant System
110E018 Sheet 3
P&ID Auxiliary Coolant System
110E018 Sheet 4
P&ID Auxiliary Coolant System
110E029 Sheet 1
P&ID Auxiliary Coolant System Unit 2
110E035 Sheet 1
P&ID Safety Injection System Unit 2
110E035 Sheet 2
P&ID Safety Injection System Unit 2
Drawings
110E035 Sheet 3
P&ID Safety Injection System Unit 2
1-CL-CC-001
Component Cooling Unit 1
CL 7A Unit 1
Safety Injection System Checklist Modes 1,2,3, and 4
(With Both ECCS Trains Aligned for Injection) Unit 1
Procedures
CL 7A Unit 2
Safety Injection System Checklist Unit 2 Modes 1,2,3, and 4
(With Both ECCS Trains Aligned for Injection)
PFP-0-PAB-46
Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 46 FT
PFP-0-PAB-8
Pre-Fire Plan Primary Auxiliary Building Elevations 8' and
Below
Fire Plans
PFP-1-TB-26
Pre-Fire Plan Unit 1 Turbine Hall Building 26'
Miscellaneous
Email from Jesse
Seymour and
Jacob Brott to
Brett Jebbia
Email Correspondence - NEXTERA (J. Seymour/J. Brott) to
NRC (B. Jebbia) Subj: Licensed Operator Requalification
Exam Results
11/19/2025
Miscellaneous
SEG PBN LOC
000 069 E
NRC Annual Operating Exam
Work Orders
40980966
1ICP-13.016G - Feedwater Flow Instrument Calibration
10/07/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40991527
Crossover Steam Dump Test Unit 2
10/07/2025
2476569
PPCS T-3272 Indicates 7*F Below C01 2TI-3272
01/14/2024
2479404
PPCS T-3272 Indicates 8F Below C01 2TI-3272
2/17/2025
2485250
Z-66A Manhole Full of Water and Cables Under Water
04/30/2024
2485277
C-326 Ground Fault Alarm on Zone 2 Which Feeds M-067A
04/30/2024
2485741
Manhole #13 Alarm Panel C-321 Fuse Blown
05/06/2024
2486507
2TI-3293 Reading 3 Degrees Higher Than 2TI-3292
05/16/2024
2490486
Proactively Replace 2HYA-964 Partial Pressure Sensor
07/11/2024
2502645
1TI-3292 66" Foot Containment Temperature Indicator
2/03/2024
2510844
Containment H2 Analyzer 2HA-967 (Yellow Chan) Will Not Cal 03/19/2025
2512819
Hydrogen Monitor Reading High
04/08/2025
2514745
Z-066A Manhole Found with High Water Level
05/05/2025
2514957
1TI-3292 Cont Temp Indication Drifting Low Declared OOS
05/08/2025
2516412
Excess Cal 3 Alarm During Performance of 1ICP 13.002
05/29/2025
2519194
Trouble Alarm for 2HYA-964 Received During 2ICP-13.002
07/10/2025
2519311
Trouble Alarm for 2HYA-965 Received During 2ICP-13.002
07/11/2025
21604
U2 Containment Hydrogen Monitors Exceed Channel Check
08/15/2025
22524
Received Excess Cal3 Alarm During 1ICP 13.002 for
08/28/2025
22525
Manhole #67A Repairs Performed
08/28/2025
22535
C-326 Ground Fault Alarm Repaired
08/28/2025
Corrective Action
Documents
25677
2HI-964 Channel Check Abnormally High
10/09/2025
Miscellaneous
PRA 14.0
Risk-Informed Applications Notebook
Procedures
Maintenance Rule Program Administration
Work Activity Risk
Management Plan
ICP 02.003A(B) Reactor Protection Logic Testing
Miscellaneous
Work Activity Risk 1 ICP 02.005A(B) Safeguards Logic Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Management Plan
Work Activity Risk
Management Plan
New Fuel Receipt
Work Activity Risk
Management Plan
2-PT-MS-003
Crossover Steam Dump Testing
1ICP 02.003B
Reactor Protection System Logic Train B Surveillance Test
1ICP 02.005B
Engineered Safety Features System Logic Train B Actuation
Logic Test
2-PT-MS-003
Crossover Steam Dump
Procedures
RP 2C
New Fuel and Fuel Insert Inspection
2511842
T-173 New Fuel out of Spec for Distillation Recovery
03/29/2025
23634
G-02 South Air Bank Depressurized During TS-82
09/15/2025
24042
G-02 Air Receivers Moisture Content Higher than Normal
09/19/2025
24061
Braided Hose Leaking Air
09/19/2025
24063
G-02 EDG Starting Air Air Leakage List
09/19/2025
24333
P-010A Residual Heat Removal Pump
09/24/2025
24384
1P-10A Increased Test Frequent due to High Vibration
09/24/2025
24414
As-Found & As-Left Resistance Values for Bus H-01 Knife
Switch D-51A
09/24/2025
27584
2X-06 Temperature Monitor Breaker Off
11/03/2025
28492
T-173 Fuel Minimum Testing SAT, Requires Additional Tests
11/14/2025
Corrective Action
Documents
29107
T-173 New Fuel out of Spec for Distillation Recovery
11/24/2025
29921
Incomplete WO Record
2/09/2025
2530413
PC 45 Part 1 Performance and Data Evaluation
2/16/2025
Corrective Action
Documents
Resulting from
Inspection
2532458
Potential Green NCV Corrective Action
01/19/2026
PBF-3006
- 2 Fuel Oil Acceptance Criteria
11/24/2025
Miscellaneous
VTM 1547
500 KVA VPE Ventilated Dry Type Transformer
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OI 92A
Fuel Oil Ordering, Receipt Sampling, and Offloading
PC 45 Part 1
Periodic Blowdown of Air Receivers and Piping
RMP 9043-23
Emergency Diesel Generator G-02 Mechanical Inspection
RMP 9370-H-01
Bus Inspection, Cleaning, and Maintenance
TLB 57
Diesel Generator Fuel Oil Fill Tank T-173
Procedures
TLB 58
Diesel Fuel Oil Storage Tank T-175A/B
40878453-01
G-02, 6Y Group B PMs
2/20/2024
41007722
IT-03, Train A, 1P-10A Low Head SI Pumps/Vlvs.
09/24/2025
Work Orders
41031172-07
DA-03058A/Inspect/Replace
10/20/2025
2479654
G-02 Tachometer Reading Off
2/27/2024
2518785
D-305 4 Cells Below Admin Limit on Specific Gravity
07/03/2025
20386
RMP 9359-6C - D-305 Station Battery, D-109 Battery Charger
Maintenance
07/28/2025
21576
Additional Battery Charger Return to Service Testing
08/14/2025
24867
Station Battery D-305, Cell 26
09/30/2025
24871
WR Needed for Equalize Charge on Battery D-305 - Based
upon CR 02524867
09/30/2025
25656
D-305 Cell 26 Issue/Concern - Follow up to CR 02524867
10/08/2025
28342
T-24B CST As-Found Condition of Internal Coatings
11/12/2025
Corrective Action
Documents
28693
T-24A CST As-Found Condition of Internal Coatings
11/18/2025
Inservice Testing Procedure
ER-AA-113-1007-
10000
Preconditioning of Structures, Systems and Components
IT 08B
TDAFP Suction from SW MOV Exercise Test (Quarterly)
Unit 1
OI 163
SI, RHR, and CS Pump Runs and Venting SI Pump Casings
Procedures
TS-82
Emergency Diesel Generator G-02 Monthly
104
Work Orders
40888191
1P-002C-Z/Perform Replacement/Refurbishment of VFD
10/12/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40964913
D-305, 125V Swing Station Battery is Reaching End-of-Life
07/06/2025
40988162
T-024A, South Condensate Storage Tank Inspection
10/20/2025
40988163
T-024B, North Condensate Storage Tank Inspection
11/30/2025
40989582-01
1PT-629 - Replace Transmitter
2/01/2025
40989582-03
2/01/2025
41007828-01
TS-82, G-02 Emergency Diesel Generator Operability Test
11/10/2025
41032577
WR Needed for Equalize Charge on Battery D-305
10/14/2025
EP-AA-100-1007-
F01
EPR Comparison 50.54q Screen Evaluation for the Transition
of the Current Point Beach Emergency Plan to the New
N/A
EP-AA-100-1007-
F01
10CFR50.54(q) Screening Form of a Change to the
07/06/2022
Calculations
N/A
EPM Comparison 50.54q Screen Evaluation for the Transition
of the Current Point Beach Emergency Plan to the New
N/A
Miscellaneous
Safety Evaluation Report
2/13/2024
Miscellaneous
MSPI Unavailability and Verification Report for: Residual Heat
Removal and Cooling Water Systems (Service Water and
Component Cooling Water) from 10/01/2024 through
09/30/2025
71151
Procedures
NP 5.2.16
NRC Performance Indicators
2506164
Rod Position H-12 for U2 Shows Sign of Failure
01/22/2025
2514371
Part 21 Associated with ASCO NP8321 Series Solenoid
Valves
04/29/2025
20960
Unit 2 Control Rod Shroud Temperature High Alarm
08/06/2025
21022
ODM for Elevated Shroud Fan Temperature
08/07/2025
21212
Unit 2 RPI I-5 Failed High
08/10/2025
21220
RPI E-09 Showing Signs of Failure
08/10/2025
Corrective Action
Documents
21458
Unit 2 RPI I-5 Primary Coil Found Open
08/13/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22176
Evaluate Relocation of 2TC-3220A-C Selector Switch A Lower
Dose Area
08/24/2025
24017
Review of PPCS Trends Shows no Abnormal Signs of Failure
09/19/2025
25404
Unit 2 RPI E-9 Declared Inoperable due to Erratic Indication
10/06/2025
25448
Trend: Elevated Unit 2 CRDM Temperature and IRPI Failures
10/07/2025
26765
Measure Unit 2 H-12 RPI Primary/Secondary Coils
10/22/2025
28744
Unit 2 IRPI E-9 Rod Bottom Light
11/19/2025
PBN 8321 Valves
Equipment list of PBNs ASCO NP8321 Valves
04/29/2025
PBN ASCO NP
Valves
Equipment list of PBNs ASCO NP Valves
04/29/2025
Miscellaneous
PC25-031-01*
10CFR21.21(b) Notification of Licensee to Perform
Defect Determination Related to the ASCO NP8321 Series
Solenoid Used in Applications with Extended Periods of
De-Energization
04/25/2025
2148978
Z-2005A Failed Crank Over Test (0-SOP-FLEX-005)
08/10/2016
2164624
Z-2005A Failed Crank Over Test (0-SOP-FLEX-005)
10/23/2016
288466
Z-2005A RCS FLEX Makeup Pump Engine will not Crank
10/29/2018
2391180
Z-2005B, Portable RCS Makeup Pump Failed to Crank Over
04/26/2021
2446548
Bad Battery
01/23/2023
2485200
Z-2005B Failed to Turn Over
04/29/2024
2487042
Z-2004B FLEX Inj Pump Failed to Start
05/23/2024
2514329
Z-2005B Failed to Crank Over During 0-SOP-FLEX-005
04/28/2025
2516913
Z-2005A Did Not Crank Over With Battery
06/05/2025
2517133
Z-2004B Failed to Start During 0-SOP-FLEX-004
06/09/2025
20439
Z-2005B RCS Makeup Portable Diesel Driven Pump (FLEX)
Battery Found Dead
07/29/2025
Corrective Action
Documents
24996
Z-2004B Failed PMT After Maintenance
10/01/2025
Procedures
Condition Reporting
48