IR 05000250/2025004
| ML26021A087 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point, 07200062  |
| Issue date: | 01/23/2026 |
| From: | Shawn Smith NRC/RGN-II/DORS/PB6 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| IR 2025004, IR 2024001 | |
| Download: ML26021A087 (0) | |
Text
SUBJECT:
TURKEY POINT NUCLEAR GENERATING, UNITS 3 AND 4 - INTEGRATED INSPECTION REPORT 05000250/2025004 AND 05000251/2025004 AND 07200062/2024001
Dear Robert Coffey:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Turkey Point Nuclear Generating, Units 3 and 4. On January 8, 2026, the NRC inspectors discussed the results of this inspection with Mr. Michael Durbin, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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,
?
Steven P. Smith, Chief Projects Branch 6 Division of Operating Reactor Safety Docket Nos. 05000250 and 05000251 and 07200062 License Nos. DPR-31 and DPR-41
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000250, 05000251, and 07200062
License Numbers:
Report Numbers:
05000250/2025004 and 05000251/2025004
Enterprise Identifier:
I-2025-004-0016; I-2024-001-0151
Licensee:
Florida Power & Light Company
Facility:
Turkey Point Nuclear Generating, Units 3 and 4
Location:
Homestead, FL 33035
Inspection Dates:
October 01, 2025 to December 31, 2025
Inspectors:
B. Bowker, Senior Reactor Inspector
J. Bundy, Senior Operations Engineer
M. Donithan, Senior Operations Engineer
A. Donley, Senior Resident Inspector
V. Furr, Senior Operations Engineer
A. Knotts, Senior Resident Inspector
Approved By:
Steven P. Smith, Chief
Projects Branch 6
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Turkey Point Nuclear Generating, Units and 4, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Units 3 and 4 operated at or near rated thermal power for the entire 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) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather prior to the onset of expected freezing temperatures on December 30, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Fire water to suppression systems for the Unit 3 emergency diesel generator (EDG)building and start-up transformer following installation of a blind flange in the 10-inch fire water header on October 29, 2025
- (2) Auxiliary feedwater (AFW) train two after operability testing on December 4, 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 zone 86, Unit 3 main and startup transformers on October 29, 2025
- (2) Fire zone 118, auxiliary building roof on November 26, 2025
- (3) Fire zone 138, Unit 4 EDG room on December 18, 2025
- (4) Fire zone 81 and 83, Unit 4 startup transformer and Unit 3 instrument air area on December 19, 2025
- (5) Fire zone 106, control room on December 22, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill at the Unit 4 hydrogen seal oil pumps on October 27, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on November 12, 2025, and the biennial written examinations completed on November 13, 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on October 2, 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during a 10 MW turbine load reduction on Unit 3 as a part of train 1 AFW operability testing on November 10, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator simulator scenario as part of annual requalification on October 28, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Action requests (ARs) 2523033 and 2522718, and maintenance rule evaluations, EVT-019-2025-52682 and EVT-019-2025-52739, for 4A intake cooling water (ICW)pump motor failures on September 1, 2025, and September 5, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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) Unit 4 elevated risk due to failed steam flow protection channel IV on November 19, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) AR 2524373, steam generator 3A feedwater flow transmitter, FT-3-477, as found calibration data found out of spec high
- (2) AR 2526796, POV-4-4882, intake cooling water (ICW) to turbine plant cooling water, valve failed to open
- (3) AR 2526985, structural cracking in 3A residual heat removal (RHR) room
- (4) AR 2528789, painting in control room and impact on control room emergency ventilation operations
- (5) AR 2516002, active boric acid leak at valve packing of MOV-3-872, RHR alternate low head safety injection to cold legs
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) Work order (WO) 40988476, charcoal filter sampling, inspection, replacement and subsequent control room emergency ventilation testing
- (2) WO 41038332, FM-4-495D, Unit 4 loop C steam flow channel IV protection module calibration after replacement
- (3) WO 41003196, functional test of the diesel-driven D service water pump following battery and battery charger replacement
- (4) WO 41041135, Unit 4 turbine control valve #1 LVDT-1 testing after replacement
Surveillance Testing (IP Section 03.01) (2 Samples)
(1)3-OSP-023.2, "3B Diesel Generator 24-Hour Full Load Test and Load Reject,"
Revision 25, on October 3, 2025 (2)4-OSP-023.2, "4B Diesel Generator 24-Hour Full Load Test and Load Reject,"
Revision 33, on December 8, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)4-OSP-062.2A, "Safety Injection Pump 4A Group B Pump Test," Revision 11, on October 17, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) A training tabletop drill of the licensee's emergency classification and emergency notification processes on November 14, 2025
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 3 (July 1, 2024, through September 30, 2025)
- (2) Unit 4 (July 1, 2024, through September 30, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 3 (July 1, 2024, through September 30, 2025)
- (2) Unit 4 (July 1, 2024, through September 30, 2025)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 3 (July 1, 2024, through September 30, 2025)
- (2) Unit 4 (July 1, 2024, through September 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 3 (July 1, 2024, through September 30, 2025)
- (2) Unit 4 (July 1, 2024, through September 30, 2025)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 3 (July 1, 2024, through September 30, 2025)
- (2) Unit 4 (July 1, 2024, through September 30, 2025)
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in instrument air compressor performance that might be indicative of a more significant safety issue. No negative trends that could lead to a safety significant issue were identified.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60853 - Onsite Fabrication of Components and Construction of an Independent Spent Fuel Storage Installation 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) 2690, Inspection Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Waste at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Transportation Packagings."
Pad Construction Inspection [02.01, 02.04, 02.05, 02.06] (1 Sample)
- (1) The existing ISFSI pads were designed and constructed to store TN NUHOMS Horizontal Storage Modules (HSMs). The inspectors verified that the licensee completed additional evaluations which establish that the ISFSI storage pads and areas have been designed to adequately support the static and dynamic loads of the HOLTEC HI-STORM FW system, considering potential amplification of earthquakes through soil-structure interaction, and soil liquefaction potential or other soil instability due to vibratory ground motion.
60854 - Preoperational Testing Of An ISFSI The inspectors evaluated the licensee's performance during NRC observed preoperational testing and training exercises to verify that the licensee has developed, implemented, and evaluated preoperational testing activities to safely load spent fuel from the spent fuel pool (SFP) into a dry storage system (DSS), transfer the loaded DSS to the independent spent fuel storage installation (ISFSI), and retrieve spent fuel from an ISFSI.
Preoperational Testing Of An ISFSI (1 Sample)
- (1) The inspectors reviewed preoperational and operational procedures and verified that hold points and critical tasks are clearly marked. In accordance with NRC-issued certificate of compliance (CoC) No. 1032, Amendment 7 the inspectors observed the implementation of the following activities:
- December 9 - 13, 2024 MPC sealing and processing at the Holtec Camden, NJ Facility:
o Multi-purpose canister (MPC) welding, non-destructive examination (NDE) inspections, pressure testing, draining, moisture removal by vacuum drying, and helium backfilling
- September 15 - 19, 2025 at the Turkey Point Nuclear Plant:
o Transfer of the MPC from the transfer cask to the overpack o
Placement of the HI-STORM FW MPC Storage System at the ISFSI
- December 1 - 4, 2025 fuel loading at the Turkey Point Nuclear Plant (NRC inspectors were unable to observe the licensees dry run evolution for the following activities, but did assess them through document review, employee interviews and observations during the loading campaign):
o Preparation of the HI-STORM FW MPC Storage System for fuel loading o
Selection and verification of specific fuel assemblies to ensure type conformance o
Loading specific assemblies and placing assemblies into the MPC, including appropriate independent verification o
Remote installation of the MPC lid and removal of the MPC and transfer cask from the spent fuel pool or cask loading pool Additionally, the inspectors evaluated the effectiveness of the licensees corrective actions and oversight (including contractor oversight), by reviewing the ISFSI quality assurance program, corrective actions documents, and records associated with the dispositioning of nonconforming conditions to ensure that issues were being properly identified, prioritized, and evaluated commensurate with their safety significance.
60855 - Operation of an Independent Spent Fuel Storage Installation The inspectors performed a review of the licensees ISFSI activities to verify compliance with regulatory requirements.
Operation of an Independent Spent Fuel Storage Installation (1 Sample)
- (1) From December 1 - December 4, 2025, during the on-site inspection, the inspectors observed and reviewed licensee activities in each of the five safety focus areas including occupational exposure, public exposure, fuel damage, confinement, and impact to plant operations.
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. Additionally, the inspectors performed independent walkdowns of the heavy load lifting equipment, ISFSI storage pad, and the ISFSI haul path. The inspectors also performed an independent radiation survey of the ISFSI pad.
60856 - Review of 10 CFR 72.212(b) Evaluations The inspectors evaluated the licensees compliance with the requirements of 10 CFR 72.212.
Review of 10 CFR 72.212(b) Evaluations (1 Sample)
- (1) The inspectors reviewed the licensees written evaluations to determine if they were in accordance with 10 CFR 72.212(b)(5) and evaluated the conditions set forth in the CoC to determine if conditions had been met prior to use. The inspectors examined applicable reactor site parameters, such as hypothetical fire and explosions, tornadoes, wind generated missile impacts, seismic qualifications, lightning, flooding and temperature, to determine if they had been evaluated for acceptability with bounding values specified in the Updated Final Safety Analysis Report (UFSAR) and the NRC Safety Evaluation Report (SER). The inspectors also examined 10 CFR 50.59 evaluations related to the construction and operation of the ISFSI and plant interfaces to determine if they were performed and to determine if changes to certain facility design bases and FSAR commitments required prior NRC approval. The inspectors reviewed 10 CFR 72.48 evaluations associated with changes to the 10 CFR 72.212 evaluations in accordance with 10 CFR 72.212(b)(7) to determine if changes made to implement the new cask system required prior NRC approval. The emergency plan, quality assurance program, training program, and radiation protection program were reviewed to determine if there was a decrease in effectiveness and if changes made required prior NRC approval.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 8, 2026, the inspectors presented the integrated inspection results to Mr.
Michael Durbin, Site Vice President and other members of the licensee staff.
- On December 4, 2025, the inspectors presented the ISFSI inspection results to Brian Vander Velde, Operations Director and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60854
Miscellaneous
HI-2114830
Final Safety Analysis Report on the HI-STORM FW MPC
Storage System
SYSTEM
Rev. 11
60855
Corrective Action
Documents
Resulting from
Inspection
Incomplete Semi-Annual ISFSI Pad Survey
Low Margin Exists for ISFSI Pad Max Temp Assumption (80
degrees max average)
Corrective Action
Documents
Resulting from
Inspection
25 ISFSI Inspection CHF Transfer Cask Thermal
Calculation Observation
60856
Miscellaneous
HI-2251297
2.212 Evaluation Report for the Holtec HI-STORM FW
System at Turkey Point
Rev. 1
Corrective Action
Documents
Action Request
(AR)
2531175
Procedures
0-ONOP-103.2
Cold/Hot Weather Conditions
Corrective Action
Documents
2501406, 2526503, 2526818, 2523349
5610-M-3016-
SH4
Fire Protection System Units 1 and 4 Fire Main Header
Loops
Drawings
5610-M-3016-
SH5-EC301098
Fire Protection System Units 3 and 4 Turbine Plant Area
Loop
10/20/2025
Engineering
Changes
301098
Fire Header Isolation - Blind Flange Installation at Valves
10/30/2025
Procedures
4-OSP-075.2
Auxiliary Feedwater Train 2 Operability Verification
2/23/23
Corrective Action
Documents
2506932, 2526399, 2504145
Corrective Action
Documents
Resulting from
Inspection
2530726, 2530838
Fire Plans
PFP-4-EDG-18
Unit 4 Emergency Diesel Generator Building
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unit 3 and 4 Control Building Elevation 42
0-ADM-016.2
Fire Brigade Program
0-PME-016.03
FALCP 4C287 Inspection and Equipment Functional Tests
0-SME-091.2
Fire and Smoke Detection System Annual Test Circuits 16,
and Fire Alarm Control C40 Test
2/16/2022
Procedures
PFP-3-TB-18
Unit 3 Turbine Building Elevation 18
Work Orders
Work Orders
(WOs)
41000862, 41024677
Procedures
3-OSP-075.6
Auxiliary Feedwater Train 1 Backup Nitrogen Test
Work Orders
40988207, 41031368
019-BI-01
Maintenance Rule Scoping Evaluation System 019 - Intake
Cooling Water System
2/19/2024
Miscellaneous
PTN REC
258894
Receipt Inspection Report
Procedures
4-OSP-019.1
Intake Cooling Water Inservice Test
Work Orders
41029271, 41029534
0-ADM-225
On Line Risk Assessment and Management
Procedures
Guarded Equipment
Corrective Action
Documents
2314293, 2528890, 2528929, 2513951
0-ADM-537
Boric Acid Corrosion Control Program
0-ADM-559
Control Room Habitability Program
Procedures
Boric Acid Corrosion Control Program
Work Orders
40987224, 40881283, 40987224, 41035014, 41036148,
40988746, 41009448, 40990354
Corrective Action
Documents
26785, 2526843, 2525790, 2529732, 2529570, 2530154,
2501748, 2452791, 2213048, 2213044
Corrective Action
Documents
Resulting from
Inspection
28034, 2530366, 2528789, 2528890, 2530905
Drawings
5614-J-982 sheet
1B
Turbine Digital Control 4C89B Chassis 1 Slot 2
Interconnection Diagram
Miscellaneous
V001043
Vendor Manual - Turbine Control System TCS Software
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Design Description SDO
0-GMI-102.48
ELCO Connector Inspection and Replacement
0-OSP-012.1
Diesel-Driven Service Water Pump Functionality Test
4-ARP-097.CR.E
CONTROL ROOM RESPONSE - PANEL E TURKEY POINT
UNIT 4
4-PMI-093.01
AMSAC Cabinet 4C391 Calibration and Test Instruction
Procedures
4-SMI-072.05
P-4-447, F-4-475, F-4-485, and F-4-495 Channel Calibration
Channel IV
Work Orders
40963328, 41004440, 41004432, 40952196, 40988712,
40998485, 40982953
Procedures
EP-AA-ADMFM-
016
Drill & Exercise Objectives Evaluation
71151
Miscellaneous
Operator Logs
Operator logs July 1, 2024 to September 30, 2025
Corrective Action
Documents
2516598, 2516611, 2516835, 2516843, 2517126, 2517130,
2517202, 2518587, 2518759, 2518794, 2518862, 2518881,
2518906, 2519368, 2519871, 2520709, 2520710, 2520712,
21293, 2522696, 2523622, 2524003, 2524052, 2524459,
24687, 2525198, 2525219, 2525221, 2525283, 2525302,
25742, 2525867, 2525885, 2528411, 2528584, 2528585,
29595