IR 05000250/2025010
| ML25213A039 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/08/2025 |
| From: | Daniel Bacon NRC/RGN-II/DORS/EB2 |
| To: | Coffey R Florida Power & Light Co |
| References | |
| IR 2025010 | |
| Download: ML25213A039 (1) | |
Text
SUBJECT:
TURKEY POINT - FIRE PROTECTION TEAM INSPECTION REPORT 05000250/2025010 AND 05000251/2025010
Dear Robert Coffey:
On June 26, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Turkey Point and discussed the results of this inspection with Michael Strope 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, Daniel M. Bacon, Chief Engineering Br 2 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:
05000250/2025010 and 05000251/2025010
Enterprise Identifier:
I-2025-010-0046
Licensee:
Florida Power & Light Company
Facility:
Turkey Point
Location:
Florida City, FL
Inspection Dates:
June 09, 2025 to June 26, 2025
Inspectors:
P. Braaten, Senior Reactor Inspector
T. Fanelli, Senior Resident Inspector
J. Montgomery, Senior Reactor Inspector
Approved By:
Daniel M. Bacon, Chief
Engineering Br 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team inspection at Turkey Point, 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.
REACTOR SAFETY
71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)
The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
- (1) Unit 4 Charging Pump Room Pre-Action Sprinkler (Fire Zone 45)
- (2) North - South Breezeway Deluge System (Fire Zone 79A)
- (3) Unit 4 Auxiliary Feedwater System
- (4) Unit 4 4160V Distribution System
Fire Protection Program Administrative Controls (IP Section 03.02) (1 Sample)
The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) Fire Protection Compensatory Measures Management
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors verified the following:
a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.
b. The adequacy of the design modification, if applicable.
c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.
d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, FHA, and SSA were updated consistently with the FPP or design change.
e. Post-fire SSD operating procedures, such as abnormal operating procedures affected by the modification were updated.
- (1) DCN 0000290435 - Calc PTN-BFJE-91-019 (Major Revision) CCN02, CNN04, CCN06, CCN09 and Breaker Curve Updates
- (2) DCN 0000293446 - U4 Reactor Coolant Pump Seal Water Injection Cooling Modification
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On June 26, 2025, the inspectors presented the fire protection team inspection results to Michael Strope and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PTN-BFJE-91-019
AC Emergency Power System Coordination Calculation
Rev 13
Calculations
sealand firw (005)
Dose Calculation for a Burning Sea-Land Container
04/11/2013
Corrective Action
Documents
Resulting from
Inspection
Surveillance Optimization PM Frequency
06/12/2025
5610-E-5-112
Circulating Water Pump 4B1 Internal Wiring Diagram
Rev 6
5610-M-3075,
Sheet 1
Auxiliary Feedwater System Turbine Drive for AFW Pumps
Rev. 30
5610-M-3075,
Sheet 2
Auxiliary Feedwater System Auxiliary Feedwater Pumps
Rev. 25
5613-E-353
Intake Area Motor Control Center 3E
Rev 10
5614-E-12
Rev 10
5614-E-18 Sh. 1
Aux and Startup Transformer Metering and Relay
Schematic Bus 4A
Rev 18
5614-E-18 Sh. 2
Aux and Startup Transformer Metering and Relay
Schematic Bus 4B
Rev 16
5614-E-25 Sh. 1C
Reactor Coolant Pump 4C Breaker 4AB06 Elementary
Diagram
Rev 6
5614-E-25 Sh. 1C1 Reactor Coolant Pump 4C Breaker 4AB06 Elementary
Diagram
Rev 2
5614-E-25 Sh. 2B
Component Cooling Water Breaker 4AB13 Elementary
Diagram
Rev 10
5614-E-25 Sh. 2B1 Component Cooling Water Breaker 4AB13 Elementary
Diagram
Rev 2
5614-E-25 Sh. 2B2 Component Cooling Water Breaker 4AB13 Elementary
Diagram
Rev 3
5614-E-26 Sh. 1A
Steam Generator Feed Pump 4A Breaker 4AA03
Elementary Diagram
Rev 15
5614-E-26 Sh. 1A1 Steam Generator Feed Pump 4A Breaker 4AA03
Elementary Diagram
Rev 7
71111.21N.05
Drawings
5614-E-26 Sh. 1A2 Steam Generator Feed Pump 4A Breaker 4AA03
Rev 7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Elementary Diagram
5614-E-26 Sh. 4C
Circulating Water Pump 4B1 Breaker 4AB16 Elementary
Diagram
Rev 9
5614-E-26 Sh. 4C1 Circulating Water Pump 4B1 Breaker 4AB16 Elementary
Diagram
Rev 0
5614-E-26 Sh. 4C2 Circulating Water Pump 4B1 Breaker 4AB16 Elementary
Diagram
Rev 1
5614-E-27A-10
Load Seq 4C23A Cubical Rear D
Rev 4
5614-E-27A-11
Load Seq 4C23A Cubical Panel RP
Rev 4
5614-E-27A-12
Load Seq 4C23A Cubical Panel SP
Rev 4
5614-E-28 Sh. 13A Electrical Auxiliaries Metering and Relaying 480V Load
Center 4A
Rev 7
5614-E-28 Sh.
13A1
Electrical Auxiliaries Metering and Relaying 480V Load
Center 4A
Rev 5
5614-E-28 Sh. 13B Electrical Auxiliaries Metering and Relaying 480V Load
Center 4B
Rev 7
5614-E-28 Sh.
13B1
Electrical Auxiliaries Metering and Relaying 480V Load
Center 4B
Rev 8
5614-E-28 Sh.
13C1
Electrical Auxiliaries Metering and Relaying 480V Load
Center 4C
Rev 5
5614-E-28 Sh. 14A 4160V Switchgear Bus 4A Lock Out Relay
Rev 2
5614-E-28 Sh. 15A 4160V Switchgear Bus 4B Lock Out Relay
Rev 2
5614-E-28 Sh. 21A 4160V Bus 4A Bus Clearing
Rev 3
5614-E-28 Sh.
21A1
4160V Bus 4A Bus Clearing
Rev 3
5614-E-28 Sh. 21C 4160V Bus 4A Bus Clearing
Rev 2
5614-E-28 Sh. 24A Electrical Auxiliaries Diesel Generator Sequencer 4C23A
Rev 8
5614-E-28 Sh.
24A1
Electrical Auxiliaries Diesel Generator Sequencer 4C23A
Rev 2
5614-E-28 Sh.
24A3
Electrical Auxiliaries Diesel Generator Sequencer Relay
Development 4C23A
Rev 7
5614-E-28 Sh.
24A4
Electrical Auxiliaries Diesel Generator Sequencer Relay
Development 4C23A
Rev 1
5614-E-28 Sh.
Electrical Auxiliaries Diesel Generator Sequencer Relay
Rev 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
24A5
Development 4C23A
5614-E-28 Sh.
24AB
Electrical Auxiliaries Diesel Generator Sequencer 4C23B
Rev 6
5614-E-28 Sh.
24B1
Electrical Auxiliaries Diesel Generator Sequencer 4C23B
Rev 2
5614-E-28 Sh. 8A
Electrical Auxiliaries Diesel Generator Breaker 4AA20
Rev 6
5614-E-28 Sh. 9A
Electrical Auxiliaries Loss of Voltage Bus 4A
Rev 6
5614-E-28 Sh. 9A1 Electrical Auxiliaries Loss of Voltage Bus 4A
Rev 4
5614-E-28 Sh. 9A2 Electrical Auxiliaries Loss of Voltage Bus 4A
Rev 8
5614-E-28 Sh. 9A3 Electrical Auxiliaries Loss of Voltage Bus 4A Relay
Development
Rev 4
5614-E-28 Sh. 9A4 Electrical Auxiliaries Loss of Voltage Bus 4A Relay
Development
Rev 3
5614-E-28 Sh. 9A5 Electrical Auxiliaries Loss of Voltage Bus 4A Relay
Development Rev 3
Rev 3
5614-E-28 Sh. 9A6 Electrical Auxiliaries Loss of Voltage Bus 4A Relay
Development
Rev 2
5614-E-334
4160V Switchgear Bus 4A Connection Diagram
Rev 11
5614-E-335
4160V Switchgear Bus 4A Connection Diagram
Rev 4
5614-E-336
4160V Switchgear Bus 4A Connection Diagram
Rev 8
5614-E-341
480V Load Center 4C and 4D Connection Diagram
Rev 6
5614-E-5
480 Volt System Load Centers 4A, 4B, 4C, 4D, and 4H
Rev 21
5614-E-5-10
Steam Generator Feed Pump 4A Breaker 4AA03 Internal
Wiring
Rev 5
5614-E-5-42
Component Cooling Water Pump 4B Bus 4B Breaker
4AB13
Rev 2
5614-E-5-52 Sh. 4
Bus 4B Breakers 4AB13 - 4AB16 Interconnection Diagram
Rev 0
5614-E-9-4 Sh. 1A
Indoor Metal Enclosed Switchgear 480/277 Volts, 3PH,
3W, 60Hz Rev
Rev 3
5614-E-9-4 Sh. 3A
Indoor Metal Enclosed Switchgear Load Center 4C and 4D
Rev 4
5614-M-3075,
Sheet 1
Auxiliary Feedwater System Steam to Auxiliary Feedwater
Pump Turbines
Rev. 17
5614-M-3075,
Sheet 2
Auxiliary Feedwater System Auxiliary Feedwater to Steam
Generators
Rev. 19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Perform a major revision to calculation PTN-BFJE-91-019
to incorporate CCN02, CCN04, CCN06, CCN09 & perform
breaker curve updates. This major revision also
incorporates EC 283459
Rev 0
5177-265-M-650
Technical Specification for Water Suppression Systems for
Appendix "R" Modifications
Rev. 4
5610-016-DB-001
Fire Protection System NFPA 805 Design Basis
Rev. 6
5610-E-2000A
Nuclear Safety Capability Assessment Essential Cable List
Rev. 13
5610-M-722A
Nuclear Safety Capability Assessment Fire Shutdown
Analysis Basis Document
Rev. 13
5610-M-722B
Nuclear Safety Capability Assessment Fire Safe Shutdown
Analysis
Rev. 10
5610-M-723A
Nuclear Safety Capability Assessment Essential
Equipment List
Rev. 8
PTN-BFJM-91-052
Fire Protection System Pipe Flow Analysis
Rev. 0
PTN-FPER-07-013
Turkey Point Nuclear Power Plant Units 3 and 4 Fire
Protection Evaluation Record
Rev. 0
PTN-FPER-07-
2D
Turkey Point Nuclear Power Plant Units 3 and 4 Fire
Protection Evaluation Record
Rev. 2
PTN-FPER-07-
2E
Turkey Point Nuclear Power Plant Units 3 and 4 Fire
Protection Evaluation Record
Rev. 0
PTN-FPER-08-004
PTN NFPA 805 Radioactive Release Review
Rev. 2
PTN-FPER-08-005
Turkey Point Nuclear Power Plant Units 3 and 4 NFPA 805
Chapter 3 Compliance Review
Rev. 0
PTN-FPER-08-012
Application of RIS 2005-07 Guidance to Use of Cameras
for Detection
Rev. 0
PTN-FPER-10-006
Alternative Compensatory Measures to Continuous Fire
Watch for Manhole 429
Rev. 0
PTN-FPER-21-002
Compensatory Measures
Rev. 0
PTN-FPER-21-012
Compensatory Measures Phase 2
Rev. 0
PTN-FPER-23-001
PTN Detection Compensatory Measure
Rev. 0
PTN-FPER-85-004
Fire Suppression System - North/South Breezeway
Rev. 0
Engineering
Evaluations
PTN-PRA-FR-DS-
Turkey Point Units 3 and 4 NSP Cals Combining NUREG-
2180 and NUREG-2230
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PTN-PRA-FR-SD
Turkey Point Units 3 and 4 Fire Probabilistic Risk
Assessment Fire Scenario Report NUREG/CR-6850 Tasks
and 11
Rev. 0
Report_0019_8145
Fire Safety Analysis
Rev.
043.00.000
5614-E-320
Vital Dc Bus 4D23 & 4D23A Load List
Rev 40
5614-E-674
Inverter 4Y07 (4D) Load List (Panels 4P09, 4P24 and
4C228A)
Rev 32
Miscellaneous
PTN-PRA-FR-
QUANT
Turkey Point Nuclear Plant FPRA Summary Report
Rev. 1
0-ADM-016
Rev. 43
0-ONOP-016.10
Safe Shutdown Manual Action
Rev. 48
Procedures
0-ONOP-105
Control Room Evacuation
Rev. 29