ML25343A075

Issuance of Amendment Nos. 304 and 298 Regarding Extension of Certain Surveillance Intervals

ML25343A075
Person / Time
Site:	Turkey Point
Issue date:	01/06/2026
From:	Blake Purnell NRC/NRR/DORL/LPL2-2
To:	Coffey R Florida Power & Light Co
References
EPID L-2025-LLA-0101
Download: ML25343A075 (0)

Text

January 6, 2026 Robert Coffey Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.

Juno Beach, FL 33408

SUBJECT:

TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - ISSUANCE OF AMENDMENT NOS. 304 AND 298 REGARDING EXTENSION OF CERTAIN SURVEILLANCE INTERVALS (EPID L-2025-LLA-0101)

Dear Robert Coffey:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 304 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 298 to Subsequent Renewed Facility Operating License No. DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point), respectively. The amendments are in response to the Florida Power & Light Company application dated March 3, 2025.

The amendments would extend certain surveillance intervals from 36 months to 48 months to support the transition to 24-month fuel cycles at Turkey Point. The NRC staff previously approved the transition to 24-month fuel cycles by amendments issued on February 12, 2025.

A copy of the related safety evaluation is also enclosed. Notice of issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Blake A. Purnell, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251

Enclosures:

1. Amendment No. 304 to DPR-31

2. Amendment No. 298 to DPR-41

3. Safety Evaluation cc: Listserv

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 304 Subsequent Renewed License No. DPR-31

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power & Light Company dated March 3, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the surveillance frequencies listed in the Surveillance Frequency Control Program, as described in the application for amendment dated March 3, 2025.

3.

This license amendment is effective as of its date of issuance and shall be implemented before entering Mode 4 following the Spring 2026 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: January 6, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.06 07:18:11 -05'00'

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 298 Subsequent Renewed License No. DPR-41

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power & Light Company dated March 3, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the surveillance frequencies listed in the Surveillance Frequency Control Program, as described in the application for amendment dated March 3, 2025.

3.

This license amendment is effective as of its date of issuance and shall be implemented before entering Mode 4 following the Spring 2027 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: January 6, 2026 DAVID WRONA Digitally signed by DAVID WRONA Date: 2026.01.06 07:18:53 -05'00'

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 304 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AND AMENDMENT NO. 298 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251

1.0 INTRODUCTION

By application dated March 3, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25062A213), the Florida Power & Light Company (FPL, the licensee) submitted a license amendment request (LAR) for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The amendments would extend certain surveillance intervals from 36 months to 48 months to support the transition to 24-month fuel cycles at Turkey Point.

The U.S. Nuclear Regulatory Commission (NRC) staff previously approved the transition to 24-month fuel cycles by amendments issued on February 12, 2025 (ML25043A428).

2.0 REGULATORY EVALUATION

2.1 Background and Description of Proposed Changes The Turkey Point Technical Specification (TS) 5.5.16, Surveillance Frequency Control Program

[SFCP], ensures that TS surveillance requirements (SRs) within the scope of the program are performed at intervals sufficient to assure the associated limiting conditions for operation (LCOs) are met. For SRs within the scope of the program, the associated surveillance frequencies are listed in a licensee-controlled document instead of the TSs. The licensee may make changes to these surveillance frequencies using the NRC-approved, risk-informed methodology referenced in TS 5.5.16 or the licensee may request NRC approval of the changes without using the referenced methodology.

The licensee requested extending the surveillance intervals for several SRs within the scope of the SFCP from 36 months to 48 months. The SFCP states that SR 3.0.2 is applicable to the surveillance frequencies within the SFCP. In accordance with SR 3.0.2, the surveillance frequency is met if the SR is performed with 1.25 times the specified surveillance interval.

Therefore, the proposed 48-month surveillance intervals with SR 3.0.2 allow for a maximum of 60 months between surveillances. The LAR states that these SRs fall into the following two categories: (1) non-calibration SRs, and (2) calibration SRs without setpoints. The first category of SRs included in the LAR are performed on a staggered test basis (STB) and the second category of SRs are not. The LAR states that of the requested SRs associated with the LAR, none involve calibration SRs with setpoints. The LAR and section 3.0 of this safety evaluation describe the specific SRs that would be affected by the proposed amendments. The LAR does not propose any changes to the program requirements; it only proposes to make changes to surveillance frequencies included within the scope of the SFCP.

2.2 Regulatory Requirements The regulations in 10 CFR 50.36, Technical specifications, establish the requirements related to the content of TSs. This regulation requires that TSs include LCOs, SRs, and administrative controls, among other things. In accordance with 10 CFR 50.36(c)(3), SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. In accordance with 10 CFR 50.36(c)(5), administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

The NRC staff used the guidance in section 2.3 of this safety evaluation to review the proposed TS changes against these requirements to ensure that there is reasonable assurance that the systems affected by the proposed TS changes will perform their required safety functions.

2.3 Regulatory Guidance On April 2, 1991, the NRC staff issued Generic Letter (GL) 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle (ML031140501).

GL 91-04 provides guidance to licensees for preparing LARs to extend surveillance intervals from 18 months to 24 months. Although the LAR is not within the scope of GL 91-04, the licensee provided certain information described in GL 91-04 to support the proposed extension of surveillance intervals from 36 months to 48 months. The NRC staff does not object to the licensees use of GL 91-04 for this LAR, as most of the guidance in GL 91-04 was written in general terms and not to the specific interval extension.

According to GL 91-04 guidance, the licensee should perform an evaluation and provide the result of this evaluation in the LAR showing that the effects of the proposed surveillance interval extension on safety are small, historical plant maintenance and surveillance data support this conclusion, and performance of the SR at the bounding limit of the proposed surveillance interval would not invalidate assumptions made in the plant licensing basis.

For SRs where the evaluation accomplishes these goals, GL 91-04 states that the licensee need not quantify the effect of the change in surveillance intervals on the availability of individual systems or components. The LAR provided this information for all the SRs included in the application.

3.0 TECHNICAL EVALUATION

The licensee provided information based on GL 91-04 for each of the proposed surveillance interval extensions. The licensee stated, in part, that it performed an evaluation of each SR identified in the request which included:

a review of the associated components function and features to determine the impact on safety with consideration for more frequent testing by other plant requirements, system/component redundancy and single failure tolerance, and overall system/component reliability; surveillance failure analyses based on historical surveillance data and maintenance records over the previous 5 cycles [8 years] to the extent possible; and

[a review of the] licensing basis to confirm that the licensing basis assumptions associated with the Turkey Point nuclear units are not affected by the requested surveillance interval extensions.

The licensees evaluation of these extensions accounted for the fact that SR 3.0.2 could be applied and, as such, with the proposed 48-month surveillance intervals, the SRs could be performed up to a maximum of 60 months apart. More detailed information is provided in the LAR and is not repeated in this safety evaluation.

3.1 Reactor Trip System Instrumentation The Turkey Point LCO 3.3.1 requires the reactor trip system instrumentation for each function in TS Table 3.3.1-1 to be operable during specific modes or conditions. The table also identifies the applicable SRs for each function.

SR 3.3.1.12 requires the licensee to perform a trip actuating device operational test (TADOT) for certain reactor trip system instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.1.12 from 36 months STB to 48 months STB for the following instrumentation functions listed TS Table 3.3.1-1:

Function 1.

Manual Reactor Trip Function 16.

Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS)

Function 18.a.

Reactor Coolant Pump (RCP) Breaker Position: Single Loop Function 18.b.

Reactor Coolant Pump (RCP) Breaker Position: Two Loops The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance interval for SR 3.3.1.12 for the instrument functions listed above. The NRC staff finds the proposed interval extension acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed change. Therefore, the NRC staff determined that the proposed surveillance interval extension for SR 3.3.1.12 for the instrument functions listed above meets the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance interval provides assurance that the necessary quality of systems and components is maintained and that LCO 3.3.1 will be met.

3.2 Engineered Safety Features Actuation System Instrumentation The Turkey Point LCO 3.3.2 requires the ESFAS instrumentation for each function in TS Table 3.3.2-1 to be operable during specific modes or conditions. The table also identifies the applicable SRs for each function.

SR 3.3.2.2 requires the licensee to perform an actuation logic test for certain ESFAS instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.2.2 from 36 months STB to 48 months STB for the following instrumentation functions listed TS Table 3.3.2-1:

Function 5.a.

Feedwater Isolation: Automatic Actuation Logic and Actuation Relays Function 6.a.

Auxiliary Feedwater: Automatic Actuation Logic and Actuation Relays SR 3.3.2.4 requires the licensee to perform a TADOT for certain ESFAS instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.2.4 from 36 months STB to 48 months STB for the following instrumentation functions listed TS Table 3.3.2-1:

Function 2.b.

Containment Spray: Containment Pressure - High High, Coincident with Containment Pressure - High Function 3.b.(3)

Containment Isolation: Phase B Isolation: Containment Pressure -

High High, Coincident with Containment Pressure - High Function 4.c.

Steam Line Isolation: Containment Pressure - High High, Coincident with Containment Pressure - High Function 6.d.

Auxiliary Feedwater: Bus Stripping Function 6.e.

Auxiliary Feedwater: Trip Of All Main Feedwater Pumps Breakers SR 3.3.2.5 requires the licensee to perform a TADOT for certain ESFAS instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.2.5 from 36 months STB to 48 months STB for the following instrumentation functions listed TS Table 3.3.2-1:

Function 1.a.

Safety Injection: Manual Initiation Function 3.a.(1)

Containment Isolation: Phase A Isolation: Manual Initiation Function 3.b.(1)

Containment Isolation: Phase B Isolation: Manual Initiation Function 4.a.

Steam Line Isolation: Manual Initiation The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.3.2.2, 3.3.2.4, and 3.3.2.5 for the instrument functions listed above. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes. Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.3.2.2, 3.3.2.4, and 3.3.2.5 for the instrument functions listed above meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.3.2 will be met.

3.3 Loss of Power Emergency Diesel Generator Start Instrumentation The Turkey Point LCO 3.3.5 requires two channels per bus of the loss of power emergency diesel generator (EDG) start instrumentation for each function in TS Table 3.3.5-1 to be operable for each EDG required by LCO 3.8.1 in modes 1, 2, 3, and 4. The table also identifies the applicable SRs for each function.

SR 3.3.5.2 requires the licensee to perform a TADOT for certain loss of power EDG start instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.5.2 from 36 months STB to 48 months STB for the following instrumentation function listed TS Table 3.3.5-1:

Function 1.a.

4.16 kV [kilovolt] Busses A and B (Loss of Voltage): Bus Undervoltage SR 3.3.5.3 requires the licensee to perform a channel calibration for certain loss of power EDG start instrumentation functions in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.3.5.3 from 36 months to 48 months for the following instrumentation functions listed TS Table 3.3.5-1:

Function 2.a.

480 V [volt] Load Centers (Undervoltage): Bus Undervoltage Function 2.b.

480 V Load Centers (Undervoltage): Time Delay Function 3.a.

480 V Load Centers (Degraded Voltage): Bus Undervoltage Function 3.b.

480 V Load Centers (Degraded Voltage): Time Delay The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.3.5.2 and 3.3.5.3 for the instrument functions listed above.

The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes. Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.3.5.2 and 3.3.5.3 for the instrument functions listed above meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.3.5 will be met.

3.4 Emergency Core Cooling System The Turkey Point LCO 3.5.2 requires three high head safety injection subsystems and two residual heat removal subsystems of the emergency core cooling system (ECCS) to be operable in modes 1, 2, and 3.

SR 3.5.2.5 requires the licensee to verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.5.2.5 from 36 months STB to 48 months STB.

SR 3.5.2.6 requires the licensee to verify each ECCS pump starts automatically on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.5.2.6 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.5.2.5 and 3.5.2.6. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes.

Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.5.2.5 and 3.5.2.6 meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.5.2 will be met.

3.5 Containment Isolation Valves The Turkey Point LCO 3.6.3 requires each containment isolation valve (CIV) to be operable in modes 1, 2, 3, and 4. SR 3.6.3.6 requires the licensee to verify each automatic CIV that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.6.3.6 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance interval for SR 3.6.3.6. The NRC staff finds the proposed interval extension acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed change. Therefore, the NRC staff determined that the proposed surveillance interval extension for SR 3.6.3.6 meets the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance interval provides assurance that the necessary quality of systems and components is maintained and that LCO 3.6.3 will be met.

3.6 Containment Spray and Cooling Systems The Turkey Point LCO 3.6.6 requires two containment spray trains and three emergency containment cooling units to be operable in modes 1, 2, 3, and 4.

SR 3.6.6.6 requires the licensee to verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.6.6.6 from 36 months STB to 48 months STB.

SR 3.6.6.7 requires the licensee to verify each containment spray pump starts automatically on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.6.6.7 from 36 months STB to 48 months STB.

SR 3.6.6.8 requires the licensee to verify each emergency containment cooling unit starts automatically on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.6.6.8 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.6.6.6, 3.6.6.7, and 3.6.6.8. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes. Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.6.6.6, 3.6.6.7, and 3.6.6.8 meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.6.6 will be met.

3.7 Feedwater Valves The Turkey Point LCO 3.7.3 requires three feedwater isolation valves, three feedwater control valves, and associated bypass valves to be operable in modes 1, 2, and 3 except when closed and de-activated or isolated by a closed manual valve. SR 3.7.3.2 requires the licensee to verify each feedwater isolation valve, feedwater control valve, and associated bypass valves actuate to the isolation position on an actual or simulated actuation signal in accordance with the SFCP.

The proposed amendments would extend the surveillance interval for SR 3.7.3.2 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance interval for SR 3.7.3.2. The NRC staff finds the proposed interval extension acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed change. Therefore, the NRC staff determined that the proposed surveillance interval extension for SR 3.7.3.2 meets the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance interval provides assurance that the necessary quality of systems and components is maintained and that LCO 3.7.3 will be met.

3.8 Component Cooling Water System The Turkey Point LCO 3.7.7 requires two component cooling water (CCW) trains to be operable in modes 1, 2, 3, and 4.

SR 3.7.7.2 requires the licensee to verify each CCW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.7.7.2 from 36 months STB to 48 months STB.

SR 3.7.7.3 requires the licensee to verify each CCW pump starts automatically on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.7.7.3 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.7.7.2 and 3.7.7.3. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes.

Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.7.7.2 and 3.7.7.3 meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.7.7 will be met.

3.9 Intake Cooling Water System The Turkey Point LCO 3.7.8 requires two intake cooling water (ICW) trains to be operable in modes 1, 2, 3, and 4.

SR 3.7.8.2 requires the licensee to verify each ICW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.7.8.2 from 36 months STB to 48 months STB.

SR 3.7.8.3 requires the licensee to verify each ICW pump starts automatically on an actual or simulated actuation signal in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.7.8.3 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.7.8.2 and 3.7.8.3. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes.

Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.7.8.2 and 3.7.8.3 meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.7.8 will be met.

3.10 Control Room Emergency Ventilation System The Turkey Point LCO 3.7.10 requires two control room emergency ventilation system (CREVS) trains and three control room air handling units to be operatable during modes 1 through 6 and during movement of irradiated fuel assemblies. SR 3.7.10.3 requires the licensee to verify each CREVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position in accordance with the SFCP. The proposed amendments would extend the surveillance interval for SR 3.7.10.3 from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance interval for SR 3.7.10.3. The NRC staff finds the proposed interval extension acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed change. Therefore, the NRC staff determined that the proposed surveillance interval extension for SR 3.7.10.3 meets the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance interval provides assurance that the necessary quality of systems and components is maintained and that LCO 3.7.10 will be met.

3.11 Alternating Current Sources The Turkey Point LCO 3.8.1 requires the following alternating current (ac) electrical sources to be operable in modes 1, 2, 3, and 4:

a. Two qualified circuits between the offsite transmission network and the unit onsite Class 1E ac electrical power distribution system,

b. Two unit EDGs capable of supplying the onsite Class 1E power distribution subsystem(s),

c. One qualified circuit between the offsite transmission network and the opposite unit onsite Class 1E ac electrical power distribution train(s) needed to support equipment required by LCOs 3.5.2, 3.7.10, 3.7.11, and 3.8.4,

d. Required opposite unit EDG(s) capable of supplying power to equipment required by LCOs 3.5.2, 3.7.10, 3.7.11, and 3.8.4, and

e. Automatic load sequencers for train A and train B.

The proposed amendments would extend the surveillance intervals in the SFCP for the following SRs from 36 months STB to 48 months STB:

SR 3.8.1.9 Verify each EDG rejects a load greater than or equal to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is 66.25 Hz [hertz],

b. Within 2 seconds following load rejection, the voltage is 3950 V and 4350 V, and

c. Within 2 seconds following load rejection, the frequency is 59.4 Hz and 60.6 Hz.

SR 3.8.1.10 Verify each EDG does not trip and voltage returns to 4784 V within 2 seconds following a load rejection of 2500 kW [kilowatt]

(Unit 3), 2874 kW (Unit 4).

SR 3.8.1.11 Verify on an actual or simulated loss of offsite power signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses,

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in 15 seconds,

2. Energizes auto-connected shutdown loads through automatic load sequencer,

3. Maintains steady state voltage 3950 V and 4350 V,

4. Maintains steady state frequency 59.4 Hz and 60.6 Hz, and

5. Supplies permanently connected and auto-connected shutdown loads for 5 minutes.

SR 3.8.1.12 Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each EDG auto-starts from standby condition and:

a. In 15 seconds after auto-start and during tests, achieves voltage 3950 V and frequency 59.4 Hz,

b. Achieves steady state voltage 3950 V and 4350 V and frequency 59.4 Hz and 60.6 Hz,

c. Operates for 5 minutes,

d. Permanently connected loads remain energized from the offsite power system, and

e. Emergency loads are energized or auto-connected through the automatic load sequencer from the offsite power system.

SR 3.8.1.13 Verify EDG trips made OPERABLE during the test mode of EDG operation are inoperable on actual or simulated loss of voltage signal on the emergency bus concurrent with an actual or simulated ESF actuation signal.

SR 3.8.1.16 Verify each EDG:

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite

power,

b. Transfers loads to offsite power source, and

c. Returns to ready-to-load operation.

SR 3.8.1.17 Verify, with a EDG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:

a. Returning EDG to ready-to-load operation and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 Verify interval between each sequenced load block is within

+/- 10% of design interval for each emergency load sequencer.

SR 3.8.1.19 Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses, and

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in 15 seconds,

2. Energizes auto-connected emergency loads through load sequencer,

3. Achieves steady state voltage 3950 V and 4350 V,

4. Achieves steady state frequency 59.4 Hz and 60.6 Hz, and

5. Supplies permanently connected and auto-connected emergency loads for 5 minutes.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance intervals for SRs 3.8.1.9, 3.8.1.10, 3.8.1.11, 3.8.1.12, 3.8.1.13, 3.8.1.16, 3.8.1.17, 3.8.1.18, and 3.8.1.19. The NRC staff finds the proposed interval extensions acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed changes. Therefore, the NRC staff determined that the proposed surveillance interval extensions for SRs 3.8.1.9, 3.8.1.10, 3.8.1.11, 3.8.1.12, 3.8.1.13, 3.8.1.16, 3.8.1.17, 3.8.1.18, and 3.8.1.19 meet the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance intervals provide assurance that the necessary quality of systems and components is maintained and that LCO 3.8.1 will be met.

3.12 Control Room Envelope Habitability Program TS 5.5.15, Control Room Envelope (CRE) Habitability Program, specifies the requirements for the CRE habitability program at Turkey Point. Among other requirements, the program shall include the following SR specified in TS 5.5.15.d:

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation with one CREVS [control room emergency ventilation system] train operating at the flow rate required by the VFTP [ventilation filter testing program],

at a Frequency in accordance with the Surveillance Frequency Control Program.

The results shall be trended and used as part of the assessment of the CRE boundary.

The proposed amendments would extend the surveillance interval in the SFCP for the SR specified in TS 5.5.15.d from 36 months STB to 48 months STB.

The NRC staff reviewed the information provided in the LAR supporting the proposed extension of the surveillance interval for the SR specified in TS 5.5.15.d. The NRC staff finds the proposed interval extension acceptable because the licensees analysis showed that (1) the effect on safety would be small, (2) historical data does not contradict this conclusion, and (3) no assumptions in the plant licensing basis would be invalidated because of the proposed change.

Therefore, the NRC staff determined that the proposed surveillance interval extension for the SR specified in TS 5.5.15.d meets the requirements in 10 CFR 50.36(c)(3) because the proposed surveillance interval provides assurance that the necessary quality of systems and components is maintained. Additionally, the NRC staff determined that the proposed change meets the requirements of 10 CFR 50.36(c)(5) because the CRE Habitability Program will continue to include administrative controls necessary to assure operation of the facility in a safe manner.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Florida State official was notified of the proposed issuance of the amendments on November 20, 2025. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (90 FR 20513; May 14, 2025). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: BPurnell, NRR HWagage, NRR GBedi, NRR TScarbrough, NRR KJames, NRR NCarte, NRR Date: January 6, 2026

ML25343A075 NRR-058 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DEX/EMIB/BC NAME BPurnell ABaxter SBailey DATE 12/17/2025 12/16/2025 9/24/2025 OFFICE NRR/DSS/SCPB/BC NRR/DEX/EICB/BC (A)

NRR/DEX/EEEB/BC NAME MValentin SDarbali WMorton (LRamadan for)

DATE 9/24/2025 11/21/2025 11/20/2025 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona BPurnell DATE 1/6/2026 1/6/2026