ML25342A056
| ML25342A056 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/09/2025 |
| From: | Shawn Smith NRC/RGN-II/DORS/PB6 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| IR 2025003 | |
| Download: ML25342A056 (0) | |
Text
Robert Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company 700 Universe Blvd Mail Stop: EX/JB Juno Beach, FL 33408
SUBJECT:
SAINT LUCIE PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000335/2025003 AND 05000389/2025003
Dear Robert Coffey:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Saint Lucie Plant, Units 1 and 2 and discussed the results of this inspection with Mr. Carlos Santos, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.
However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
No findings or violations of more than minor significance were identified during this inspection.
December 9, 2025
R. Coffey 2
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. 05000335 and 05000389 License Nos. DPR-67 and NPF-16
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Smith, Steven on 12/09/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME P. Carman J. Baptist S. Smith DATE 12/08/2025 12/09/2025 12/09/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000335 and 05000389 License Numbers:
DPR-67 and NPF-16 Report Numbers:
05000335/2025003 and 05000389/2025003 Enterprise Identifier:
I-2025-003-0015 Licensee:
Florida Power & Light Company Facility:
Saint Lucie Plant, Units 1 and 2 Location:
Jensen Beach, FL 34957 Inspection Dates:
July 01, 2025 to September 30, 2025 Inspectors:
J. Baptist, Senior Resident Inspector S. Bruneau, Project Engineer S. Roberts, Resident 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 Saint Lucie Plant, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS Unit 1 began the inspection period at or near rated thermal power. The unit was down powered to 45% percent on August 30, 2025, and returned to rated thermal power on September 3, 2025, due to a ground on the 1A main feed water (MFW) pump. The unit was shutdown for a planned refueling outage on September 20, 2025, and remained shutdown for the remainder of the inspection period.
Unit 2 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 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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)
Unit 2 fire zones (FZs) 35 and 36, 43 ft level of reactor auxiliary building (RAB), on July 9, 2025 (2)
Unit 1 FZs 34 and 35, 1A and 1B emergency core cooling room, on August 26, 2025 (3)
Unit 2 FZ F-F/6, auxiliary feedwater (AFW) pump steam trestle, on September 10, 2025 71111.06 - Flood Protection Measures Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections in the Unit 1 and Unit 2 RAB at the -0.5 ft levels and the engineered safeguards rooms.
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)
4 (1)
The inspectors observed and evaluated licensed operator performance in the control room during the Unit 1 shutdown and cooldown for the refueling outage (RFO) SL1-33, on September 20, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated a licensed operator continuing training evaluation in the control room simulator that included a 2B main feed isolation valve (MFIV) failure, a loss of ventilation unit HVS-4a, a 2B steam generator tube rupture, and the 2B atmospheric dump valve (ADV) that would not close in auto, on July 28, 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)
Action request (AR) 2518581 MV-21-2 (motor operated valve for intake cooling water (ICW) Train B supply to TCE HX's), failure to close causing the 1B ICW to be declared inoperable, failure on July 1, 2025 (2)
AR 02522123 and work order (WO) 41028644, RE-26-80A Ex-Core Radiation Monitor inoperable due to failing at 15% percent power, failure on August 23, 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 1 elevated risk while the 1B ICW header was out of service (OOS) due to the inability to close MV-21-2. MOTOR OPERATED VLV FOR TCW TRAIN B SUPPLY TO TCW HX'S, on July 1, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
AR 2515541, Unit 2 2A shutdown cooling return to 2A low pressure safety injection (LPSI) pump over thrust/torque event, on September 11, 2025 (2)
AR 2519712, Unit 1 1B ICW pump discharge piping identified water leaks, review completed July 22, 2025
5 (3)
ARs 2519947 and 2519964, Unit 2 PI-8013A, pressure indicator for 2A steam generator, failure and entry into abnormal operating procedure, review completed on August 5, 2025 (4)
AR 25111102, Unit 1 thru-wall leak on the A train component cooling water (CCW) heat exchanger header, on September 18, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated RFO SL1-33 activities from September 20, 2025, through September 30, 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) (1 Sample)
(1)
WO 41002482, Unit 1, 1-CME-02.02, coupled motor test run using "Overhaul of Charging Pump Motors CHG PP-1A 1B, &1C" following excessive oil leak. Review completed on August 20, 2025.
Surveillance Testing (IP Section 03.01) (2 Samples)
(1) 1-OSP-69.13B, "ESF - Staggered 36-month surveillance for SIAS/CIS/CSAS - Train B." Review completed on September 25, 2025.
(2)
WO 40914432, 1-SMM-08.08, "Main Steam Safety Valve Setpoint Surveillance Using Furmanite Trevitest Mark VIII Equipment," on main steam safety valves v8203, v8209, v8206, v8214. Review completed September 30, 2025.
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1) 1-OSP-68.02, Local Leak Rate Test, Penetration P-48c,1A H2 Analyzer Sample Return, on September 25, 2025 71114.06 - Drill Evaluation Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
(1)
On July 15, 2025, the inspectors evaluated an emergency response drill that included increased reactor coolant system activity followed by a steam generator tube leak, subsequent steam generator tube rupture, rapid reactor downpower, manual reactor trip, loss of B train emergency core cooling system suction, loss of emergency diesel generator, reactor fuel failure, and failed open steam generator steam safety valve.
The scenario included situations that resulted in declarations of an Unusual Event, Alert, Site Area Emergency, and General Emergency.
6 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)
(1)
Unit 1, July 1, 2024, through June 30, 2025 (2)
Unit 2, July 1, 2024, through June 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 for potential adverse trends associated with ICW system piping, that might be indicative of a more significant safety issue.
INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On September 30, 2025, the inspectors presented the integrated inspection results to Mr. Carlos Santos, Site Vice President and other members of the licensee staff.