IR 05000250/2025011
| ML25230A102 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/28/2025 |
| From: | Shawn Smith NRC/RGN-II/DORS/PB6 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| IR 2025011 | |
| Download: ML25230A102 (10) | |
Text
SUBJECT:
TURKEY POINT NUCLEAR GENERATING, UNITS 3 AND 4 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000250/2025011 AND 05000251/2025011
Dear Robert Coffey:
On July 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Turkey Point Nuclear Generating, Units 3 and 4 and 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.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
August 28, 2025 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 Reactor 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:
05000250/2025011 and 05000251/2025011
Enterprise Identifier:
I-2025-011-0024
Licensee:
Florida Power & Light Company
Facility:
Turkey Point Nuclear Generating, Units 3 and 4
Location:
Homestead, FL 33035
Inspection Dates:
July 14, 2025 to July 31, 2025
Inspectors:
W. Deschaine, Senior Project Engineer
P. Carman, Senior Project Engineer
L. Colon Fuentes, Construction Project Inspector
A. Knotts, Resident Inspector
Approved By:
Steven P. Smith, Chief
Reactor Projects Branch #6
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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
None.
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 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The inspectors performed a biennial assessment of the effectiveness of the licensees problem identification and resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees problem identification and resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth corrective action program review of the following systems or portions thereof: intake cooling water, emergency diesel generators for Units 3 and 4, residual heat removal system for Units 3 and 4.
The corrective actions for the following non-cited violations, minor violations, and findings were evaluated as part of the assessment: 2023004-07, 2023004-08, 2023004, 2023010-01, 2023010-02, 2024001-01, 2024002, 2024003-01, 2024003-02, 2024003-03, 2024004-01, 2024004-03, 2024010-01, 2024010-02, 2024010-03, 2024010-04, 2024010-05, 2024011-01, 2024011-02, 2024301-01, 2025401-01.
- Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
- Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Turkey Point Biennial PI&R Assessment 1) Corrective Action Program Effectiveness Problem Identification: The inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program (which included the work management system), and there was a low threshold for entering issues into the corrective action program. This conclusion was based on a review of the requirements for initiating condition reports as described in licensee procedure PI-AA-01, "Corrective Action Program and Condition Reporting." Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.
Problem Prioritization and Evaluation: Based on the review of condition reports, work orders, and work requests, the inspectors concluded that problems were prioritized and evaluated in accordance with licensee guidance. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that, in general, plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and cause determinations were appropriate, and considered the significance of the issues being evaluated.
Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that, generally, corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. The team determined that the licensee was generally effective in developing corrective actions that were appropriately focused. The inspectors found that issue evaluations were generally sound.
Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.
2) Operating Experience The team determined that the stations processes for the use of industry and NRC operating experience information were effective and complied with regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented in accordance with applicable procedures.
3) Self-Assessments and Audits The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance. The self-assessments and audits were adequately self-critical and performance-related issues were being appropriately identified.
The inspectors verified that action requests were created to document areas for improvement and findings, and verified that actions generally had been completed consistent with those recommendations.
4) Safety-Conscious Work Environment As part of the safety culture inspection activities, inspectors conducted a random sample of both formal and informal interviews with licensee personnel across several organizations and reviewed the latest safety culture assessments. Results of the interviews indicated that staff were knowledgeable of the different avenues available to raise safety concerns, which included the use of the Employee Concerns Program (ECP), and that staff were willing to raise concerns when necessary. Inspectors also reviewed action request (AR) 02516689 which documented the ECPs identification of a declining trend in the Chemistry department safety culture. As part of the AR review, the inspectors reviewed immediate actions, long-term actions, and the results of an independent chemistry work environment assessment performed in July 2025. Additional interviews were conducted with a random sample of Chemistry department personnel where most noted that the actions taken related to safety culture had been effective. Chemistry staff interviewed also indicated that they felt the safety culture would continue to improve. No issues or concerns were identified as part of the AR review. NRC staff will continue to monitor the safety culture work environment (SCWE) as part of their baseline activities. Based on the teams inspection activities, the team determined that the conditions at the site were conducive to a SCWE.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 31, 2025, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Michael Durbin, 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
2359905, 02482110, 02415921, 02489935, 02415332,
2482654, 02482284, 02482109, 02484951, 2461441,
2467223, 2467718, 2469513, 2470236, 02504970,
2501004, 2474058, 2470068, 2468709, 2474202, 2470610,
2430592, 2464946, 2489515, 2495191, 02460841,
2488728, 02499359, 02500030, 02500155, 02505137,
2505848, 02509203, 02510200, 02510714, 02460654,
2467071, 02469095, 02469614, 02487209, 02487635,
2488221, 02491680, 02492010, 02501055, 02507878,
2516689, 02517215, 02462142, 02467820, 02476733,
2478448, 02483417, 02487820, 02506224, 02514185,
2515868, 02516332, 02468709, 02489598, 02475170,
2492940, 02486577, 02493598, 02478058, 02212419,
2464725, 2466159, 02467841, 02470297, 02478849,
2475859, 02489315, 02492262, 02467223, 02401787,
2357180, 02481030, 02481032, 2482014
Corrective Action
Documents
Resulting from
Inspection
Action Requests
20269, 2520263
Engineering
Changes
Repair of ICW Pump Conduit and Motor Heater Junction Box
Supports
Revision 5
Engineering
Changes
Intake and ICCP Replacement and Structural Repairs
Revision 2
Engineering
Changes
Acceptability of B.5.b PDFP for Use as an Alternate Backup
Pump
Revision 0
Engineering
Changes
Temporary scaffold support for 3A ICW Pump Motor Heater
Support
Revision 0
Engineering
Evaluations
PTN-ENG-SEES-
2-0009
Extend the Interval of the Selected Unit 4 Emergency Diesel
Generators Maintenance Activities
Revision 13
Engineering
Evaluations
PTN-ENG-SEMJ-
25-006
Evaluate Deferral of MOV Static Periodic Verification Tests
on MOV-4-861B, MOV-4-863A&B, and MOV-4-880B
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
5610-019-DB-001
Design Basis Document - INTAKE COOLING WATER
SYSTEM
2/13/2024
Procedures
Corrective Action Program and Condition Reporting
Revision 4
Procedures
COMMON CAUSE EVALUATION
Revision 16
Procedures
CONDITION REPORTING
Revision 38
Procedures
CONDITION REPORTING
Revision 48
Self-Assessments
PTN 23-003
Maintenance Audit Report
08/10/2023
Self-Assessments
PTN 25-001
Operations Audit Report
04/10/2025
Work Orders
4085552126, 40981549-01, 40854600-01, 40854601-01,
40979651-03