ML25101A190

Issuance of Amendment No. 278, 280, 256, 211, 302, and 296

ML25101A190
Person / Time
Site:	Saint Lucie, Point Beach, Turkey Point
Issue date:	06/02/2025
From:	Marshall M NRC/NRR/DORL/LPL1
To:	Coffey R Florida Power & Light Co
References
EPID L-2024-LLA-0141
Download: ML25101A190 (1)

Text

June 2, 2025 Robert Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd Juno Beach, FL 33408

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2; ST. LUCIE PLANT, UNIT NOS. 1 AND 2; AND TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - ISSUANCE OF AMENDMENT NOS. 278, 280, 256, 211, 302, AND 296 RE: RELOCATION OF STAFF QUALIFICATIONS FROM TECHNICAL SPECIFICATIONS TO THE FLORIDA POWER AND LIGHT AND NEXTERA ENERGY QUALITY ASSURANCE TOPICAL REPORT (EPID L-2024-LLA-0141)

Dear Mr. Coffey:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the following enclosed amendments:

Amendment Nos. 278 and 280 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively.

Amendment Nos. 256 and 211 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively.

Amendment Nos. 302 and 296 to Subsequent Renewed Facility Operating License Nos. DPR-31 and DPR-41 for the Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively.

These amendments consist of changes to the technical specifications (TSs) in response to your application dated October 8, 2024 (Agencywide Documents Access and Management System Accession No. ML24282A904). The amendments revise the technical specifications for each facility Renewed Facility Operating License by relocating the staff qualification requirements to the Florida Power and Light and NextEra Energy Quality Assurance Topical Report.

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

Sincerely,

/RA/

Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266, 50-301, 50-335, 50-389, 50-250, and 50-251

Enclosures:

1. Amendment No. 278 to DPR-24

2. Amendment No. 280 to DPR-27

3. Amendment No. 256 to DPR-67

4. Amendment No. 211 to NPF-16

5. Amendment No. 302 to DPR-31

6. Amendment No. 296 to DPR-41

7. Safety Evaluation cc: Listserv

NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 278 Renewed License No. DPR-24

1.

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

A.

The application for amendment by NextEra Energy Point Beach, LLC (the licensee), dated October 8, 2024, 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 4.B of the Renewed Facility Operating License No. DPR-24 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 278, are hereby incorporated in the renewed operating license. NextEra Energy Point Beach shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:05:50 -04'00'

NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 280 Renewed License No. DPR-27

1.

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

A.

The application for amendment by NextEra Energy Point Beach, LLC (the licensee), October 8, 2024, 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 4.B of the Renewed Facility Operating License No. DPR-27 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 280, are hereby incorporated in the renewed operating license. NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:06:16 -04'00'

ATTACHMENT TO LICENSE AMENDMENTS POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 AMENDMENT NO. 278 RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 280 RENEWED FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following page of Renewed Facility Operating License No. DPR-24 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace the following page of Renewed Facility Operating License No. DPR-27 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.

Remove Insert 5.3-1 5.3-1 Renewed License No. DPR-24 Amendment No. 278 D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.

Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.

4.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A.

Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 278, are hereby incorporated in the renewed operating license.

NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.

C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensees application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.

Renewed License No. DPR-27 Amendment No. 280 C. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed source for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.

Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.

4.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A.

Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 280, are hereby incorporated in the renewed operating license.

NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.

C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensees application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.

5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications Unit Staff Qualifications 5.3 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1 ).

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

5.3.3 In the event the position of Health Physicist is vacated and the proposed replacement does not meet all the qualifications of TS 5.3.1, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual.

Point Beach 5.3-1 Unit 1 - Amendment No. 278 Unit 2 - Amendment No. 280

FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 256 Renewed License No. DPR-67

1.

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

A.

The application for amendment by Florida Power & Light Company (FPL, the licensee), dated October 8, 2024, 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, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B, in part, to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 256, are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:07:05 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 256 ST. LUCIE PLANT UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following page of Renewed Facility Operating License No. DPR-67 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications, with the attached page.

The revised page is identified by amendment number and contains a marginal line indicating the areas of change.

Remove Insert 5.3-1 5.3-1 Renewed License No. DPR-67 Amendment No. 256 applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

A.

Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 256 are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C.

DELETED D.

Sustained Core Uncovery Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.

E.

Fire Protection Florida Power & Light Company (FPL) St. Lucie Plant Unit 1 shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated March 22, 2013, and May 2, 2017, and supplements dated June 14, 2013, February 24, 2014, March 25, 2014, April 25, 2014, July 14, 2014, August 27, 2014, September 10, 2014, October 10, 2014, March 10, 2015, April 1, 2015, April 20, 2015, May 12, 2015, August 21, 2015, and October 22, 2015, and as approved in the safety evaluations (SE) dated March 31, 2016, and October 23, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Unit Staff Qualifications 5.3 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1 ).

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

St. Lucie - Unit 1 5.3-1 Amendment 256

FLORIDA POWER AND LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 211 Renewed License No. NPF-16

1.

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

A.

The application for amendment by Florida Power & Light Company, et al. (FPL, the licensee), dated October 8, 2024, 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, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B, in part, to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:07:41 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 211 ST. LUCIE PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following page of Renewed Facility Operating License No. NPF-16 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications, with the attached page.

The revised page is identified by amendment number and contains a marginal line indicating the areas of change.

Remove Insert 5.3-1 5.3-1 Renewed License No. NPF-16 Amendment No. 211 neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D.

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FPL to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.

Pursuant to the Act and 10 CFR Parts 30 and 70, FPL to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

3.

This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A.

Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C.

DELETED D.

Antitrust Conditions FPL shall comply with the antitrust conditions in Appendices C and D to this renewed license.

E.

Fire Protection Florida Power & Light Company (FPL) St. Lucie Plant Unit 2 shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated March 22, 2013, and May 2, 2017, and supplements dated June 14, 2013, February 24, 2014, March 25, 2014, April 25, 2014, July 14,

5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Unit Staff Qualifications 5.3 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1 ).

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

St. Lucie - Unit 2 5.3-1 Amendment 211

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 302 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 (the licensee) dated October 8, 2024, 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Subsequent Renewed Facility Operating License No. DPR-31 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 302, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Subsequent Renewed Facility Operating License and Technical Specifications Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:08:14 -04'00'

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 296 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 (the licensee) dated October 8, 2024, 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 Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Subsequent Renewed Facility Operating License No. DPR-41 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 296, are hereby incorporated into this subsequent renewed operating license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Subsequent Renewed Facility Operating License and Technical Specifications Date of Issuance: June 2, 2025 AUDREY KLETT Digitally signed by AUDREY KLETT Date: 2025.06.02 15:08:40 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 302 AND 296 TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NOS. DPR-31 AND DPR-41 DOCKET NOS. 50-250 AND 50-251 Replace page 3 of Subsequent Renewed Facility Operating License No. DPR-31 with the attached page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace page 3 of Subsequent Renewed Facility Operating License No. DPR-41 with the attached page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert Page 3 Page 3 Replace the following page of the Appendix A, Technical Specifications with the attached pages. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

Remove Insert 5.3-1 5.3-1

3 Subsequent Renewed License No. DPR-31 Amendment No. 302 applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A.

Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 302, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C.

Deleted.

D.

Fire Protection FPL shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated June 28, 2012 and October 17, 2018 (and supplements dated September 19, 2012; March 18, April 16, and May 15, 2013; January 7, April 4, June 6, July 18, September 12, November 5, and December 2, 2014; and February 18, 2015; October 24, and December 3, 2018; and January 31, 2019), and as approved in the safety evaluations dated May 28, 2015 and March 27, 2019. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the

3 Subsequent Renewed License No. DPR-41 Amendment No. 296 A.

Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 296, are hereby incorporated into this subsequent renewed operating license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C.

Deleted.

D.

Fire Protection FPL shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated June 28, 2012 and October 17, 2018 (and supplements dated September 19, 2012; March 18, April 16, and May 15, 2013; January 7, April 4, June 6, July 18, September 12, November 5, and December 2, 2014; and February 18, 2015; October 24, and December 3, 2018; and January 31, 2019), and as approved in the safety evaluations dated May 28, 2015 and March 27, 2019. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the

5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Unit Staff Qualifications 5.3 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1 ).

5.3.2 For the purpose of 10 CFR 55.4, a licensed senior reactor operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

Turkey Point Unit 3 and Unit 4 5.3-1 Amendment Nos. 302 and 296

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 280 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 AMENDMENT NO. 211 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 AMENDMENT NO. 302 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 296 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER AND LIGHT COMPANY AND NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 ST. LUCIE PLANT, UNIT NOS. 1 AND 2 TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-266, 50-301, 50-335, 50-389, 50-250, AND 50-251

1.0 INTRODUCTION

By application dated October 8, 2024 (Agencywide Documents Access and Management System Accession No. ML24282A904), Florida Power and Light Company and NextEra Energy Point Beach, LLC (collectively referred to as the licensee), submitted a license amendment request (LAR), application to the U.S. Nuclear Regulatory Commission (NRC or the Commission), to change technical specifications (TSs) for Point Beach Nuclear Plant (Point Beach), Units 1 and 2, St. Lucie Plant (St. Lucie), Units 1 and 2, and Turkey Point Nuclear Generating (Turkey Point), Units 3 and 4.The LAR proposed to relocate the staff qualification requirements in the TSs for Point Beach, St. Lucie, and Turkey Point, to the existing Florida Power and Light and NextEra Energy Quality Assurance Topical Report (QATR).

2.0 REGULATORY EVALUATION

The NRC staff considered the following regulations during its review of the LAR:

Paragraph (c)(5) of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36, Technical specifications, describes that 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.

Paragraph (a)(3) of 10 CFR Part 50.54 contains requirements for making changes to quality assurance programs. That paragraph states, in part:

Each licensee described in paragraph (a)(1) of this section may make a change to a previously accepted quality assurance program description included or referenced in the Safety Analysis Report without prior NRC approval, provided the change does not reduce the commitments in the program description as accepted by the NRC. Changes to the quality assurance program description that do not reduce the commitments must be submitted to the NRC in accordance with the requirements of Sec. 50.71(e).

Section 120 of 10 CFR 50, Training and qualification of nuclear power plant personnel, requires training and qualification for personnel to operate and maintain the facility in a safe manner in all modes of operation and requires that each nuclear power plant licensee establish, implement, and maintain the training and qualification programs that are derived from a systems approach to training as defined in 10 CFR 55.4, Definitions.

The NRC staff considered the following guidance during its review of the LAR:

NRC Administrative Letter (AL) 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, contains guidance for relocating requirements from the administrative controls section of TS in cases where adequate controls are provided by other methods. AL 95-06 states that quality assurance plans are a logical candidate for such relocations because of the controls imposed on quality assurance plans by regulations (e.g., 10 CFR Part 50, Appendix B, and 10 CFR 50.54(a)) and the existence of NRC-approved quality assurance plans and commitments to industry quality assurance standards.

Regulatory Guide (RG) 1.8, Revision 1, Personnel Selection and Training, describe methods acceptable for complying with those portions of the Commissions regulations regarding the training and qualifications of nuclear power plant personnel. Revision 1 of RG 1.8 endorsed ANSI N18.1-1971 with one exception.

3.0 TECHNICAL EVALUATION

The proposed LAR relocates the staff qualification requirements in the TSs for Point Beach, Units 1 and 2, St. Lucie, Units 1 and 2, and Turkey Point, Units 3 and 4, to the existing Florida Power and Light and NextEra Energy QATR for these staff qualification requirements. The current revision of the Florida Power and Light and NextEra Energy QATR is Revision 31.

3.1 Description of Proposed Changes The Point Beach, Units 1 and 2, TS 5.3.1 currently states:

Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, for comparable positions, except:

a.

The education and experience eligibility requirements for license applicants, and changes thereto, shall be those previously reviewed by the NRC, specifically those referenced in NRC Safety Evaluation letter dated October 24, 2003.

b.

The Operations Manager shall meet one of the following:

i. Hold a Senior Operators license, or ii. Have held a Senior Operators license on a similar unit (PWR), or iii. Have been certified for equivalent Senior Operator knowledge.

The proposed change will revise Point Beach, Units 1 and 2, TS 5.3.1 to read as follows:

Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1).

The St. Lucie, Unit 1, TS 5.3.1 currently states:

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS-3.1-1978 for comparable positions, except for the radiation protection manager. The radiation protection manager shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 1, September 1975.

The proposed change will revise St. Lucie, Unit 1, TS 5.3.1 to read as follows:

Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1).

The St. Lucie, Unit 2, TS 5.3.1 currently states:

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS-3.1-1978 for comparable positions, except for the radiation protection manager. The radiation protection manager shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 1, September 1975.

The proposed change will revise St. Lucie, Unit 2, TS 5.3.1 to read as follows:

Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1).

The Turkey Point, Units 3 and 4, TS 5.3.1 currently states:

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, except for the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The staff not covered by ANSI N18.1-1971 shall meet or exceed the minimum qualifications of Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff.

The proposed change will revise Turkey Point, Units 3 and 4, TS 5.3.1 to read as follows:

Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions, as specified in the Florida Power and Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1).

3.2 Evaluation of Proposed Changes The NRC staff evaluated the licensees request to decide whether the proposed change is consistent with the regulations and guidance discussed in this safety evaluation. The NRC staff reviewed the proposed changes to decide whether relocating the staff qualification requirements in the TS 5.3.1 for Point Beach, Units 1 and 2, St. Lucie, Units 1 and 2, and Turkey Point, Units 3 and 4, will continue to acceptably define the staff qualification requirements sufficient to meet the requirements of 10 CFR 50.36(c)(5) and assure that the referenced unit staff qualification requirements in the Florida Power and Light and NextEra Energy QATR will acceptably maintain the training and qualification programs in accordance with 10 CFR 50.120.

The licensee proposed to relocate the staff qualification requirements in TS 5.3.1 for Point Beach, Units 1 and 2, St. Lucie, Units 1 and 2, and Turkey Point, Units 3 and 4, to the existing Florida Power and Light and NextEra Energy QATR. In its request, the licensee stated that the amendment is consistent with NRC Administrative Letter 95-06 and would not change any current staff qualification requirements. Additionally, the licensee cited examples of similar, recently submitted LARs by other licensees that have received NRC approval.

The Florida Power and Light and NextEra Energy QATR, Section A.5.1, Point Beach, Units 1 and 2, states:

Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, as supplemented by Regulatory Guide 1.8, Revision 1, September 1975, for comparable positions, except:

a. The education and experience eligibility requirements for license applicants, and changes thereto, shall be those previously reviewed by the NRC, specifically those referenced in the NRC Safety Evaluation letter dated October 24, 2003.

b.

The Operations Manager shall meet one of the following:

i. Hold a Senior Operators license, or ii. Have held a Senior Operators license on a similar unit (PWR), or iii. Have been certified for equivalent Senior Operator knowledge.

The Florida Power and Light and NextEra Energy QATR statement is consistent with the information in the current Point Beach, Units 1 and 2, TS 5.3.1. In addition, the application does not propose any reduction in commitments in the quality assurance program. Therefore, the licensees unit staff qualification requirements will not be changed by this amendment, and these requirements remain consistent with RG 1.8. In addition, the relocation of the licensees unit staff qualification requirements to the Florida Power and Light and NextEra Energy QATR is consistent with the guidance in AL 95-06.

The Florida Power and Light and NextEra Energy QATR, Section A.5.3, St. Lucie, Units 1 and 2, states:

Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS-3.1-1978 for comparable positions, except for the radiation protection manager. The radiation protection manager shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 1, September 1975.

The Florida Power and Light and NextEra Energy QATR statement is consistent with the information in the current St. Lucie, Units 1 and 2, TS 5.3.1. In addition, the application does not propose any reduction in commitments in the quality assurance program. Therefore, the licensees unit staff qualification requirements will not be changed by this amendment, and these requirements remain consistent with RG 1.8. In addition, the relocation of the licensees unit staff qualification requirements to the Florida Power and Light and NextEra Energy QATR is consistent with the guidance in AL 95-06.

The Florida Power and Light and NextEra Energy QATR, Section A.5.2, Turkey Point, Units 3 and 4, states:

Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, except for the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The staff not covered by ANSI N18.1-1971 shall meet or exceed the minimum qualification of Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff.

The Florida Power and Light and NextEra Energy QATR statement is consistent with the information in the current Turkey Point, Units 3 and 4, TS 5.3.1. In addition, the application does not propose any reduction in commitments in the quality assurance program. Therefore, the licensees unit staff qualification requirements will not be changed by this amendment, and these requirements remain consistent with RG 1.8. In addition, the relocation of the licensees unit staff qualification requirements to the Florida Power and Light and NextEra Energy QATR is consistent with the guidance in AL 95-06.

Based on the above, the NRC staff conclude that the proposed changes are acceptable as they will remove redundant references and will refer to the existing equivalent commitments to RG 1.8, Revision 1 in the Florida Power and Light and NextEra Energy QATR. The proposed changes are consistent with 10 CFR 50.36(c)(5) and 10 CFR 50.120, and these regulations will continue to be met because the licensees staff qualification requirements will not be changed by these amendments. In addition, future reductions in commitments associated with the licensees staff qualification requirements must be made in accordance with Appendix B to 10 CFR 50 and 10 CFR 50.54(a). Any reductions in commitments associated with the licensees staff qualification requirements that are relocated to the Florida Power and Light and NextEra Energy QATR will require NRC approval prior to the implementation in accordance with 10 CFR 50.54(a)(4). Therefore, the NRC staff finds that the proposed TS changes and relocation of the licensees staff qualification requirements to the Florida Power and Light and NextEra Energy QATR are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the NRC staff notified officials from the States of Wisconsin and Florida on April 23, 2025, of the proposed issuance of the amendments. Each official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change administrative requirements. The staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding published in the Federal Register on December 23, 2024 (89 FR 104571). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these 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 Commission's 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.

7.0 REFERENCES

1. Mack, K., Florida Power & Light Company letter to U.S. Nuclear Regulatory Commission, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Florida Power and Light and NextEra Energy Quality Assurance Topical Report (FPL-1), dated October 8, 2024 (ML24282A904).

2. Florida Power & Light Company and NextEra Energy Quality Assurance Topical Report (FPL-1) Annual Submittal, Revision 31, dated July 10, 2024 (ML24192A229).

3. Regulatory Guide 1.8, Revision 1, Personnel Selection and Training, dated September 1975 and reissued in May 1977 as Revision 1-R (ML12305A250).

4. Administrative Letter 95-06, Relocation of Technical Specification Administrative Controls Related to Quality Assurance, dated December 12, 1995 (ML031110271).

5. American National Standards Institute, ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel, dated March 18, 1971.

6. American Nuclear Society, ANSI/ANS 3.1-1978, Selection, Qualification and Training of Personnel for Nuclear Power Plants, dated January 17, 1978.

Principal Contributor: R. Romero-Devore, NRR Date of Issuance: June 2, 2025

ML25101A190

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