ML25266A206

Issuance of Amendment Nos. 303 and 297 to Eliminate Certain Pressurizer Heater Requirements

ML25266A206
Person / Time
Site:	Turkey Point   (DPR-031, DPR-041)
Issue date:	09/25/2025
From:	Blake Purnell Plant Licensing Branch II
To:	Coffey R Florida Power & Light Co
B. Purnell
References
EPID L-2025-LLA-0060
Download: ML25266A206 (1)

Text

September 25, 2025 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. 303 AND 297 TO ELIMINATE CERTAIN PRESSURIZER HEATER REQUIREMENTS (EPID L-2025-LLA-0060)

Dear Mr. Coffey:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 303 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 297 to Subsequent Renewed Facility Operating License No. DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively. These amendments are in response to the Florida Power & Light Company application dated March 26, 2025, as supplemented by letter dated July 29, 2025. The amendments revise the technical specifications for Turkey Point Nuclear Generating Unit Nos. 3 and 4, by removing the pressurizer heater group emergency power supply requirements.

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. 303 to DPR-31

2. Amendment No. 297 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. 303 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 26, 2025, as supplemented by letter dated July 29, 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 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. 303, 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 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 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: September 25, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.09.25 08:49:45 -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. 297 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 26, 2025, as supplemented by letter dated July 29, 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 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. 297, 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 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION David Wrona, Chief Plant Licensing Branch II-2 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: September 25, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.09.25 08:50:12 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 303 AND 297 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 the following pages of the Subsequent Renewed Facility Operating Licenses and Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License DPR-31 License DPR-31 Page 3 Page 3 License DPR-41 License DPR-41 Page 3 Page 3 Technical Specifications Technical Specifications 3.4.9-1 3.4.9-1 3.4.9-2 3.4.9-2

3 Subsequent Renewed License No. DPR-31 Amendment No. 303 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. 303, 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. 297 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. 297, 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

Pressurizer 3.4.9 Turkey Point Unit 3 and Unit 4 3.4.9-1 Amendment Nos. 303 and 297 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a.

Pressurizer water level 92% and b.

Two groups of pressurizer heaters OPERABLE with the capacity of each group 125 kW.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not within limit.

A.1 Be in MODE 3.

AND A.2 Fully insert all rods.

AND A.3 Place Rod Control System in a condition incapable of rod withdrawal.

AND A.4 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours B. One required group of pressurizer heaters inoperable.

B.1 Restore required group of pressurizer heaters to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

Pressurizer 3.4.9 Turkey Point Unit 3 and Unit 4 3.4.9-2 Amendment Nos. 303 and 297 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition B not met.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%.

In accordance with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of pressurizer heaters is 125 kW.

In accordance with the Surveillance Frequency Control Program

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 303 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AND AMENDMENT NO. 297 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 26, 2025 (Agencywide Documents Access and Management System Accession No. ML25085A134), as supplemented by letter dated July 29, 2025 (ML25210A368), 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 revise the technical specifications (TSs) for Turkey Point by removing the pressurizer heater group emergency power supply requirements.

The licensees July 29, 2025, supplemental letter was in response to a U.S. Nuclear Regulatory Commission (NRC or Commission) request for additional information dated June 30, 2025 (ML25182A225). The supplemental letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on June 10, 2025 (90 FR 24417).

2.0 REGULATORY EVALUATION

2.1 Description of Proposed Changes Currently, the limiting condition for operation (LCO) in Turkey Point TS 3.4.9, Pressurizer, requires, in part, that two groups of pressurizer heaters be operable and capable of being powered from an emergency power supply while the plant is operating in Modes 1, 2, and 3.

The proposed amendments would eliminate the following requirements in TS 3.4.9:

the LCO 3.4.9 requirement for two groups of pressurizer heaters to be capable of being powered from an emergency power supply; the associated surveillance requirement (SR) 3.4.9.3 used to verify that the required pressurizer heaters to be capable of being powered from an emergency power supply; and the associated actions the licensee must take when a pressurizer heater group is not capable of being powered from an emergency power supply (Condition C).

The proposed amendments would also make editorial changes to TS 3.4.9. A reference to Condition C would be deleted from Condition D. Condition D, Required Action D.1, and Required Action D.2 would be redesignated as Condition C, Required Action C.1, and Required Action C.2, respectively.

2.2 Regulatory Requirements and Guidance The regulatory requirements related to the content of TSs are provided in Section 50.36, Technical specifications, of Title 10 of the Code of Federal Regulations (10 CFR).

Paragraph 50.36(a)(1) of 10 CFR requires each applicant for a license authorizing operation of a utilization facility to include in the application proposed TSs. In addition, 10 CFR 50.36(a)(1) states, in part: A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications.

The regulation at 10 CFR 50.36(b) states, in part:

Each license authorizing operation of a utilization facility will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to [10 CFR] 50.34 [Contents of applications; technical information]. The Commission may include such additional technical specifications as the Commission finds appropriate.

The regulation at 10 CFR 50.36(c)(2) requires TSs to include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met. The regulation at 10 CFR 50.36(c)(3),

requires TSs to include SRs, which 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.

By letter dated July 6, 1981 (ML17340A521), the NRC issued amendments to revise the Turkey Point TSs to include, in part, the emergency power requirements for the pressurizer heaters.

These amendments were in response to lessons learned from the accident at Three Mile Island Nuclear Station, Unit No. 2 (TMI or TMI-2), that occurred on March 28, 1979. Additional information regarding the development of these requirements is provided in NUREG-0578, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations, dated July 1979 (ML090060030), and NUREG-0737, Clarification of TMI Action Plan Requirements, dated November 1980 (ML051400209).

The NRC staffs guidance for the review of TSs is in Chapter 16.0, Revision 3, Technical Specifications (ML100351425), of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water-Reactor] Edition (SRP),

March 2010. As described therein, as part of the regulatory standardization effort, the NRC staff has prepared standard technical specifications (STSs) for each of the LWR nuclear designs.

Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the applicable reference STS (i.e., the current STS), as modified by NRC-approved travelers. The TSs for Turkey Point are based on NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, dated September 2021 (ML21259A155 and ML21259A159, respectively).

3.0 TECHNICAL EVALUATION

Turkey Point TS 3.4.9 is intended, in part, to assure that pressurizer heater capacity is sufficient to maintain the reactor coolant system (RCS) near normal operating pressure to account for heat losses through the pressurizer insulation under conditions that include a loss of offsite power. By maintaining the pressure near the operating conditions, a wide subcooling margin to saturation can be maintained in the RCS loops.

The licensee stated in the LAR that the pressurizer heaters are not credited in the Turkey Point safety analysis for any design-basis accidents. However, an implicit initial condition of the safety analysis is that the RCS is operating at normal pressure. As discussed in Section 2.2 of this safety evaluation, the TS provision requiring pressurizer heaters to be capable of being powered from an emergency power supply originated from the TMI lessons learned. Although the heaters are not specifically credited in the accident analysis, the need to maintain subcooling in the long term during a loss of offsite power is the reason for having an LCO that includes pressurizer heaters.

NUREG-0578, Section 2.1.1, recommended, in part, that licensees provide redundant emergency power for the minimum number of pressurizer heaters required to maintain natural circulation conditions in the event of a loss of offsite power. By letter dated April 7, 1980 (ML17339A962), the NRC staff found that Turkey Point had satisfied NUREG-0578, Section 2.1.1. By letter dated July 2, 1980 (ML093430163), the NRC requested all pressurized-water reactor (PWR) licensees submit LARs to, in part, add TS requirements for the pressurizer heater emergency power supplies. The licensee subsequently submitted the LAR for Turkey Point, and the associated amendments to the TSs were issued by the NRC on July 6, 1981 (ML013400366).

Additional information regarding the recommendation in NUREG-0578, Section 2.1.1, is described in NUREG-0737, Enclosure 3, under Item II.E.3.1, Emergency Power Supply for Pressurizer Heaters. Specifically, NUREG-0737 provides the following NRC position and clarification for Item II.E.3.1:

Position The pressurizer heater power supply design shall provide the capability to supply, from either the offsite power source or the emergency power source (when offsite power is not available), a predetermined number of pressurizer heaters and associated controls necessary to establish and maintain natural circulation at hot standby conditions. The required heaters and their controls shall be connected to the emergency buses in a manner that will provide redundant power supply capability.

Clarification Redundant heater capacity must be provided, and each redundant heater or group of heaters should have access to only one Class 1 E division power supply.

In NUREG-1431, the STS for LCO 3.4.9 indicates that the phrase and capable of being powered from an emergency power supply is plant-specific rather than generally applicable to PWRs. Similarly, the STS SR 3.4.9.3 to verify the required pressurizer heaters are capable of being powered from an emergency power supply is identified as plant specific. In the STS Bases, the description of the SR 3.4.9.3 states, in part, that this SR is not applicable if the heaters are permanently powered by 1E power supplies. Based on this information, the licensee concluded in the LAR that:

Hence, based on the STS, the pressurizer heater emergency power requirements apply to plants not having the required pressurizer heaters normally aligned to an emergency power source. For these facilities, the TS needs to establish requirements which assure for the requisite number of pressurizer heaters the capability to transfer power from the normal, non-Class 1E power source to a Class 1E onsite emergency power source to support RCS subcooling following a loss of off-site power.

The LAR states that the Turkey Point units each have three banks of pressurizer heaters consisting of the Control Group, Backup Group A, and Backup Group B. The LAR states, in part: Though only one heater group is required to maintain natural circulation following a loss of off-site power condition, Backup Group A and Backup Group B each have access to on-site emergency power sources. In its July 29, 2025, letter, the licensee clarified that both Backup Group A and Backup Group B are connected, and thereby aligned, to Class 1E power supplies at all times.

The licensee proposed to eliminate the LCO 3.4.9 requirement for two groups of required pressurizer heaters to be capable of being powered from an emergency power supply because the two required heater groups are normally aligned through safety-grade equipment to separate Class 1E buses. The LAR stated that the LCO requirement only affirms the permanent plant design, and removal of this requirement will not result in a change to the design of the plant. In addition, the pressurizer heaters are not credited in the Turkey Point safety analyses for any design basis accident.

The NRC staff reviewed the information provided in the LAR, as supplemented, and determined that the proposed changes to Turkey Point TS 3.4.9 are consistent with the STS. Specifically, the NRC staff determined that an LCO requirement is not needed because the pressurizers at Turkey Point are equipped with redundant pressurizer heater groups normally connected to an emergency power source. In addition, the NRC staff found that the relevant portions of NUREG-0578, Section 2.1.1, will continue to be satisfied consistent with the associated NRC position described in NUREG-0737, Enclosure 3, Item II.E.3.1, because the required groups of pressurizer heaters are normally aligned (connected) through safety-grade equipment to separate Class 1E buses and the proposed amendments would not change the design of the facility.

If the emergency power supply requirements for the pressurizer heaters are eliminated from LCO 3.4.9, then there is no longer a need to retain a remedial action for the unavailability of the emergency power supply or an SR to verify that emergency power supply requirement is met.

Therefore, the NRC finds it acceptable to delete Condition C, Required Actions C.1 and C.2, and SR 3.4.9.3. The NRC also finds that the other proposed changes to TS 3.4.9 are editorial as they do not change any technical requirements.

Therefore, based on the above, the NRC staff finds that 10 CFR 50.36(c)(2) will continue to be met because, with the proposed changes, the Turkey Point TSs will continue to specify (1) the lowest functional capability or performance levels of equipment required for safe operation of the facility, and (2) remedial actions or shutdown requirements when an LCO is not met. In addition, the NRC staff finds that 10 CFR 50.36(c)(3) will continue to be met because SR 3.4.9.3 is not necessary to provide assurance that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Florida State official was notified of the proposed issuance of the amendments on September 12, 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 24417; June 10, 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: C. Ashley, NRR K. Nguyen, NRR B. Purnell, NRR Date: September 25, 2025

ML25266A206 NRR-058 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/STSB NAME BPurnell ABaxter SMehta DATE 9/24/2025 9/24/2025 8/27/2025 OFFICE NRR/DEX/EEEB NRR/DSS/SNSB NRR/DORL/LPL2-2/BC NAME WMorton NDifrancesco (GVasudevamurthy for) DWrona DATE 8/7/2025 8/4/2025 9/25/2025 OFFICE NRR/DORL/LPL2-2/PM NAME BPurnell DATE 9/25/2025