ML25115A006
| 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
Robert Coffey Executive Vice President, Nuclear Division Chief Nuclear Officer Florida Power & Light Company 700 Universe Blvd Juno Beach, FL 33408
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 cc w/ encl: Distribution via LISTSERV April 29, 2025 Signed by Smith, Steven on 04/29/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME P. Carman A Donley S. Smith DATE 4/25/2025 4/28/2025 4/29/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000250 and 05000251 License Numbers:
DPR-31 and DPR-41 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
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Turkey Point Nuclear Generating, Units 3 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
3 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 (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) (1 Sample)
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)
5 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 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
6 (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)
7 (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) (2 Samples)
(1)
Unit 3 (January 1 through December 31, 2024)
(2)
Unit 4 (January 1 through December 31, 2024)
8 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) (2 Samples)
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 Sample)
9 (1)
The inspectors evaluated automatic actuation of EDG and licensees response on March 13, 2025.
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.
10 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 21 5613-M-3030 Component Cooling Water 27 Drawings 5613-M-3068 Containment Spray System 23 300456 Acceptability of B.5.b pump for use as alternate backup pump 0
Engineering Evaluations PTN-ENG-SEMS-22-006 Engineering Evaluation to Perform PCTM for Alternate Backup Fire Pump Capability 1
0-NOP-025 Control Room Ventilation System 25 0-ONOP-016.7 Emergency Makeup Water to the Fire Protection System 08/07/2024 3-NOP-030 Component Cooling Water System 47 3-NOP-068 Containment Spray System 8
71111.04 Procedures 3-OSP-068.5B 3B CS Pump Inservice Test 16 Corrective Action Documents Resulting from Inspection action requests 2505409, 2510711 PFP-4-CTMT-18 Unit 4 Containment 1
PFP-AB-18 Unit 3 & 4 Auxiliary Building 3
PFP-CB-18 Unit 3&4 Control Building 2
Fire Plans PFP-CB-30 Unit 3&4 Control Building 5
0-ADM-016.1 Transient Combustible and Flammable Substances Program 20 0-AMD-016.1 Transient Combustible and Flammable Substances Program 21 0-ONOP-016.10 Safe Shutdown Manual Actions 4
0-SME-091.3 Fire and Smoke Detection System Annual Test Circuits 6, 15 and 32 1
71111.05 Procedures MA-SR-100-1016 Control of Temporary Power and Lighting 2
Corrective Action Documents action requests 2506259, 2506260 71111.07A Corrective Action Documents action requests 2508246, 2508559
11 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 71111.08P Work Orders 40821680-28 U4 Concrete Repairs Per AR 2509924 3/22/2025 Operability Evaluations 3-OP-050 Residual Heat Removal System 34 3-GOP-103 Power Operation to Hot Standby 41 3-GOP-305 Hot Standby to Cold Shutdown 45 71111.11Q Procedures 3-ONOP-41.1 Reactor Coolant Pump Off-Normal 22 0-ADM-009 Containment Entries when Containment Integrity is Established 28 0-ADM-051 Outage Risk Assessment 09/04/2024 0-ADM-225 On Line Risk Assessment and Management 19 ODI-CO-056 Initial Event Response Checklist 07/12/24 OP-AA-102-1003 Guarded Equipment 48 71111.13 Procedures WM-AA-100-1000 Work Activity Risk Management 27 Corrective Action Documents action request 2502365, 2500812, 2501747, 2501865, 2410712, 2410779, 2305849, 2502849, 2509225 Miscellaneous V000981 Instruction Manual for Main Steam Isolation Valve 6
3-PMM-022.3 Emergency Diesel Generator 36 Month Preventive Maintenance 26 Procedures 4-OSP-206.1 Inservice Valve Testing - Cold Shutdown 17 work order 40880977, 40819286, 41007344, 40948369 71111.15 Work Orders work request 94267861, 94267942, Corrective Action Documents action requests 2510604 71111.20 Corrective Action Documents Action Request 2510071, 2509376
12 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 6
4-NOP-040.02 Refueling Core Shuffle 23 4-NOP-051 Containment Personnel Air lock 8
Procedures AD-AA-101-1004 Work Hour Controls 25 Corrective Action Documents action request 250097, 2499419, 2502825, 2510602, 2504426, 2511353, 2509225 Corrective Action Documents Resulting from Inspection action request 2506475, 2508559 Miscellaneous 12TURKY2817 Control Room Habitability Tracer Gas Leak Testing at Turkey Point Nuclear Power Station 0
0-ADM-502 In-Service Testing (IST) Program 47 0-CMP-102.01 Troubleshooting and Repair Guidelines 7A 0-NOP-025 Control Room Ventilation System 25 0-NOP-025.02 Control Room Envelope Breach Control 4
0-OSP-025.4 Control Room Habitability Test 15 0-PMM-030.03 Component Cooling Water Pump Overhaul 1
3-GMI-041.21 Unit 3 Eagle 21 Channel Reset 3
3-PMI-041.8 RCS Temperature Loop C Protection Channel Set III Calibration 22 3-SMI-041.106 PRZR Level Protection Channel III Loop L-3-461 Calibration 6
4-OSP-030.1 Component Cooling Water Pump Inservice Test 14 4-OSP-041.4 Overpressure Mitigating System Nitrogen Backup Leak and Functional Test 13 4-PMI-072.10 Main Steam Isolation Valve (MSIV) Actuator Testing and Overhaul 3
71111.24 Procedures 4-SMI-072.02A P-4-466, P-4-475, P-4-485, and P-4-495 Steam Pressures COT, Protection Channel III 12
13 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 71114.04 Procedures F699 Emergency Action Level Matrix - COLD Rev. 12 Corrective Action Documents action requests 2506788, 2506790 71114.06 Miscellaneous Drill Report for January 28, 2025 ERO Drill 71151 Procedures 0-ADM-032 NRC Performance Indicators Turkey Point 14 71152A Corrective Action Documents Resulting from Inspection action requests 2510929, 2510930 71153 Miscellaneous EN 57603 and 57604 Reactor Plant Event Notification 03/13/2025