IR 05000250/2025001
| ML25115A006 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 04/29/2025 |
| From: | Shawn Smith NRC/RGN-II/DORS/PB6 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| IR 2025001 | |
| Download: ML25115A006 (1) | |
Text
SUBJECT:
TURKEY POINT NUCLEAR GENERATING, UNITS 3 AND 4 - INTEGRATED INSPECTION REPORT 05000250/2025001 AND 05000251/2025001
Dear Robert Coffey:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Turkey Point Nuclear Generating, Units 3 and 4. On April 16, 2025, the NRC inspectors discussed the results of this inspection with Mr. Roger Montgomery, Organizational Effectiveness Site Director 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 License Nos. DPR-31 and DPR-41
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000250 and 05000251
License Numbers:
Report Numbers:
05000250/2025001 and 05000251/2025001
Enterprise Identifier:
I-2025-001-0034
Licensee:
Florida Power & Light Company
Facility:
Turkey Point Nuclear Generating, Units 3 and 4
Location:
Homestead, FL 33035
Inspection Dates:
January 01, 2025 to March 31, 2025
Inspectors:
P. Cooper, Senior Reactor Inspector
A. Donley, Senior Resident Inspector
J. Hickman, Senior Resident Inspector
A. Knotts, Resident Inspector
K. Lei, Emergency Preparedness Inspector
D. Orr, Senior Project Engineer
R. Reyes, Project Engineer
D. Strickland, Senior Reactor Inspector
J. Walker, Senior Emergency Preparedness 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
Type Issue Number Title Report Section Status NOV 05000250/2024003-03 Unsecured Debris in the Unit 3 RHR Heat Exchanger Room 71152A Closed
PLANT STATUS
Unit 3 operated at or near rated thermal power (RTP) for the entire inspection period.
Unit 4 began the inspection period at RTP. On February 27, 2025, the unit reduced power to 44 percent RTP for main steam safety valve testing. On March 1, 2025, the unit was taken offline for refueling outage, PT4-35, where the unit remained for the rest 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) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Control room ventilation system after completion of control room habitability test on January 14, 2025 (2)3B train of closed cooling water (CCW) following restoration from eddy current testing on February 03, 2025 (3)3B containment spray pump (CSP) standby alignment on January 31, 2025
- (4) Alignment of the B.5.b pump, portable diesel fire pump, and electric service water pump to the east fire main when the diesel driven fire pump failed to start on March 5, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 62, computer room on January 8, 2025
- (2) Fire Zone 54 and 47, Unit 3 and 4 CCW pump and heat exchanger rooms on January 10, 2025
- (3) Fire Zone 101 and 104, 3A and 4B DC equipment rooms on January 17, 2025
- (4) Fire Zone 59, Unit 4 containment building on March 12, 2025
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 4A CCW heat exchanger
===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 4 during refueling outage PT4-35 from March 10, 2025, to March 17, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
Ultrasonic Examination
1. 4-RCP-FSC-1 Thru 24, Flange Studs, ASME Class 1
2. 3-CH-1401-34, MRP-146 of Pipe to Elbow Weld, Augmented Exam
3. 3-CH-1401-37, MRP-146 of Elbow to Branch Connection, Augmented Exam
Dye Penetrant Examination
1. Nozzle/Adapter, Nozzle/Guide Tube #6, Class 1, this included a review of the
associated welding activities Visual Examination
1. 4-RCP-FNC-1 Thru 24, Flange Nuts, ASME Class 1
2. Thermal Shield Support Block at 15 deg, Remote IVVI
3. Liner Plate: Reactor Vessel Sump, Liner Plate (General Visual), Class MC
4. 4-Reactor Support 1 Thru 6, Reactor Vessel Supports, Class 1 Supports
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
1. Boric Acid Walkdown on March 10, 2025
2. Reviewed engineering evaluations in work order (WO) 40288872 and 41002634
3. Reviewed action requests (ARs) 02509245 and 02509253
PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
Eddy Current Examination
1. Steam Generator 4A: Row 14 Column 57
2. Steam Generator 4B: Row 2 Column 36 and Row 33 Column 18
3. Steam Generator 4C: Row 25 Column 33
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 planned shutdown and cooldown for Unit 4 refueling outage (PT4-35) on February 28 and March 1, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator just in time training in the simulator for shutdown prior to refueling outage on February 24, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Unit 3 elevated risk after a loss of power to 3P06-4 breaker while in a load threat condition on 13 January, 2025
- (2) Unit 3 high risk for emergent containment entry at full power to troubleshoot LI-30-926, 3B accumulator level indicator on January 22, 2025
- (3) Unit 3 elevated risk during 3A residual heat removal (RHR) pump inservice test (IST)on February 05, 2025
- (4) Unit 4 high risk for emergent containment entry at full power to trouble shoot flux map D detector stuck in E 10-path on February 12, 2025
- (5) Unit 4 yellow shutdown risk during lowered inventory and high decay heat load on March 3, 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 2502363 and 2501844, N-3-43, channel III power range nuclear instrument failure and subsequent past inoperability evaluation
- (2) AR 2502842, 3B emergency diesel generator (EDG) air filter water intrusion from blowdown relief valve lifting
- (3) AR 2510848, coolant leak from 4B EDG air box drain
- (4) AR 2510510, Penetration 14, reactor coolant system letdown, failed as found local leak rate testing
- (5) AR 2509225, 4A main steam isolation valve (MSIV) failed to close on demand during unit 4 shutdown
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated Unit 4 refueling outage, PT4-35, activities from March 1, 2025, to March 31, 2025.
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) (7 Samples)
- (1) WO 41000786, Eagle 21 channel III circuit card replacement after reactor trip
- (2) WO 40981063, 3B CCW heat exchanger thermal performance following cleaning and eddy current testing
- (3) WO 40956802, PCV-4-455C pressurizer power operated relief valve leakage and functional test after overhaul
- (4) WO 40885257 and 41001508, Unit 3 pressurizer control group heater controller and isolator calibration following controller replacement
- (5) WO 41009327, 4B CCW pump test after carbon seal and bearing replacement
- (6) WO 41007344, 4A MSIV stroke following actuator solenoid valve replacement
- (7) WO 40934396, 2A auxiliary feedwater interlock; inspect, calibrate, and replace time delay relay
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)0-OSP-025.4, Control Room Habitability Test, on January 8, 2025 (2)0-ADM-531, Containment Leakage Rate Testing Program, for Unit 3, on January 16, 2025 (3)4-OSP-072.6, Main Steam Safety Valve Setpoint Surveillance Using Team Trevitest Mark VIII Equipment, on February 28, 2025 (4)4-OSP-203.2, Train B Engineered Safeguards Integrated Test, on March 09, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)3-OSP-050.2A, RHR Train A Test - Standby Alignment, on February 5, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)4-OSP-051.5, Local Leak Rate Testing, Penetration 63, Instrument Air Bleed, on March 24, 2025
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise during the week of February 10, 2025. The simulated scenario began with condensate pump discharge flange leakage, which led to lowering steam generator levels and a manual reactor trip. At the moment the reactor was tripped, a loss of all offsite AC power was experienced, and an Unusual Event was declared. A short time later, the emergency diesel generator failed, which met the conditions for declaring an Alert. As the event progressed, a reactor coolant system (RCS) leak began, and then increased until a containment spray actuation signal occurred. When the containment spray pump failed to start, emergency action level conditions were met, and a Site Area Emergency was declared. The scenario provided opportunities for the offsite response organizations to demonstrate their ability to implement emergency actions.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of February 10, 2025. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
(1)2025 January Emergency Response Drill on January 28, 2025
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed and evaluated the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.
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 3 (January 1 through December 31, 2024)
- (2) Unit 4 (January 1 through December 31, 2024)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 3 (January 1 through December 31, 2024)
- (2) Unit 4 (January 1 through December 31, 2024)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 3 (January 1 through December 31, 2024)
- (2) Unit 4 (January 1 through December 31, 2024)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2023, through December 31, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2023, through December 31, 2024 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14)
This is a new NRC performance indicator, described in NEI 99-02, Revision 8 (ML24331A114). Licensees began collecting data for this performance indicator January 1, 2025. Therefore, at the time of inspection there was no quarterly data compiled and submitted to the NRC.
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) AR 2502673, inconsistencies in sampling of closed cooling water systems and the corrective actions associated with missed samples for EDG cooling jacket water samples in 2024.
- (2) AR 2492940, issue investigation and completed corrective actions for NRC identified debris in the 3B RHR pump room
1. The inspectors reviewed the licensees response to NOV 05000250/2024003-
03, Unsecured Debris in the Unit 3 RHR Heat Exchanger Room (ADAMS Accession No. ML24317A212), and determined that the reason, corrective actions taken to address recurrence, and the date when full compliance was achieved for this violation is adequately addressed and captured on the docket. This NOV is Closed.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated automatic actuation of EDG and licensees response on March 13,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 16, 2025, the inspectors presented the integrated inspection results to Mr.
Roger Montgomery, Organizational Effectiveness Site Director and other members of the licensee staff.
- On February 13, 2025, the inspectors presented the emergency preparedness exercise inspection results to Mr. Michael Strope, Site Vice President and other members of the licensee staff.
- On March 18, 2025, the inspectors presented the inservice inspection results to Mr.
Michael Strope, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
action requests
2505277, 2480734, 2508311
5610-M-3025
Control Building Ventilation Control Room HVAC
5613-M-3030
Component Cooling Water
Drawings
5613-M-3068
Containment Spray System
300456
Acceptability of B.5.b pump for use as alternate backup
pump
Engineering
Evaluations
PTN-ENG-SEMS-
2-006
Engineering Evaluation to Perform PCTM for Alternate
Backup Fire Pump Capability
0-NOP-025
Control Room Ventilation System
0-ONOP-016.7
Emergency Makeup Water to the Fire Protection System
08/07/2024
3-NOP-030
Component Cooling Water System
3-NOP-068
Containment Spray System
Procedures
3-OSP-068.5B
3B CS Pump Inservice Test
Corrective Action
Documents
Resulting from
Inspection
action requests
2505409, 2510711
PFP-4-CTMT-18
Unit 4 Containment
Unit 3 & 4 Auxiliary Building
Unit 3&4 Control Building
Fire Plans
Unit 3&4 Control Building
0-ADM-016.1
Transient Combustible and Flammable Substances Program
0-AMD-016.1
Transient Combustible and Flammable Substances Program
0-ONOP-016.10
Safe Shutdown Manual Actions
0-SME-091.3
Fire and Smoke Detection System Annual Test Circuits 6, 15
and 32
Procedures
MA-SR-100-1016
Control of Temporary Power and Lighting
Corrective Action
Documents
action requests
2506259, 2506260
Corrective Action
Documents
action requests
2508246, 2508559
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Work Orders
work orders
40888947, 40999660, 40941029
CR 02509495
results of snubber visual examination
3/9/2025
CR 02509884
moisture barrier condition observations
3/8/2025
CR 02509885
sump liner condition observations
3/8/2025
CR 02509901
snubber condition observations
3/8/2025
Corrective Action
Documents
CR 02509924
moisture barrier condition observations
3/8/2025
Work Orders
40821680-28
U4 Concrete Repairs Per AR 2509924
3/22/2025
Operability
Evaluations
3-OP-050
Residual Heat Removal System
3-GOP-103
Power Operation to Hot Standby
3-GOP-305
Hot Standby to Cold Shutdown
Procedures
3-ONOP-41.1
Reactor Coolant Pump Off-Normal
0-ADM-009
Containment Entries when Containment Integrity is
Established
0-ADM-051
Outage Risk Assessment
09/04/2024
0-ADM-225
On Line Risk Assessment and Management
ODI-CO-056
Initial Event Response Checklist
07/12/24
Guarded Equipment
Procedures
Work Activity Risk Management
Corrective Action
Documents
action request
2502365, 2500812, 2501747, 2501865, 2410712, 2410779,
2305849, 2502849, 2509225
Miscellaneous
V000981
Instruction Manual for Main Steam Isolation Valve
3-PMM-022.3
Emergency Diesel Generator 36 Month Preventive
Maintenance
Procedures
4-OSP-206.1
Inservice Valve Testing - Cold Shutdown
work order 40880977, 40819286, 41007344, 40948369
Work Orders
work request 267861, 94267942,
Corrective Action
Documents
action requests
2510604
Corrective Action
Documents
Action Request
2510071, 2509376
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Miscellaneous
Clearance Order
4-062-869 OPT-001
0-ADM-051
Outage Risk Management
0-OSP-059
Core Mapping Following Core Loading
4-NOP-040.02
Refueling Core Shuffle
4-NOP-051
Containment Personnel Air lock
Procedures
Work Hour Controls
Corrective Action
Documents
action request
250097, 2499419, 2502825, 2510602, 2504426, 2511353,
2509225
Corrective Action
Documents
Resulting from
Inspection
action request
2506475, 2508559
Miscellaneous
2TURKY2817
Control Room Habitability Tracer Gas Leak Testing at
Turkey Point Nuclear Power Station
0-ADM-502
In-Service Testing (IST) Program
0-CMP-102.01
Troubleshooting and Repair Guidelines
7A
0-NOP-025
Control Room Ventilation System
0-NOP-025.02
Control Room Envelope Breach Control
0-OSP-025.4
Control Room Habitability Test
0-PMM-030.03
Component Cooling Water Pump Overhaul
3-GMI-041.21
Unit 3 Eagle 21 Channel Reset
3-PMI-041.8
RCS Temperature Loop C Protection Channel Set III
Calibration
3-SMI-041.106
PRZR Level Protection Channel III Loop L-3-461 Calibration
4-OSP-030.1
Component Cooling Water Pump Inservice Test
4-OSP-041.4
Overpressure Mitigating System Nitrogen Backup Leak and
Functional Test
4-PMI-072.10
Main Steam Isolation Valve (MSIV) Actuator Testing and
Overhaul
Procedures
4-SMI-072.02A
P-4-466, P-4-475, P-4-485, and P-4-495 Steam Pressures
COT, Protection Channel III
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
Work Orders
40948983, 40858286, 40858924, 40880386, 40880484,
40880365, 40876534, 40858983, 40858285, 40858948,
40972624, 40942075, 40858385, 41001816, 40819286,
40948369, 40858617
Turkey Point Radiological Emergency Plan
Rev. 77
F668
Emergency Action Level Matrix - HOT
Rev. 18
Procedures
F699
Emergency Action Level Matrix - COLD
Rev. 12
Corrective Action
Documents
action requests
2506788, 2506790
Miscellaneous
Drill Report for January 28, 2025 ERO Drill
71151
Procedures
0-ADM-032
NRC Performance Indicators Turkey Point
Corrective Action
Documents
Resulting from
Inspection
action requests
2510929, 2510930
Miscellaneous
EN 57603 and
57604
Reactor Plant Event Notification
03/13/2025