ML25241A019
| ML25241A019 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/08/2025 |
| From: | Kimberly Green Plant Licensing Branch II |
| To: | Erb D Tennessee Valley Authority |
| Green K | |
| References | |
| EPID L-2025-LLA-0104 | |
| Download: ML25241A019 (1) | |
Text
September 8, 2025 Mr. Delson C. Erb Vice President, OPS Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 ISSUANCE OF AMENDMENT NOS. 336, 359, AND 319 REGARDING REVISION OF TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.8.4.5 FOR MINIMUM BATTERY CHARGER CAPACITY FOR SHUTDOWN BOARD SUBSYSTEMS (EPID L-2025-LLA-0104)
Dear Mr. Erb:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 336, 359, and 319 to Renewed Facility Operating Licenses Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2, and 3, respectively. These amendments are in response to your application dated July 10, 2025, as supplemented by letter dated August 14, 2025.
The amendments revise the Browns Ferry Nuclear Plant, Units 1, 2, and 3, Technical Specification Surveillance Requirement 3.8.4.5 to modify the minimum battery charger capacity for the direct current shutdown board subsystems.
A copy of our related safety evaluation is also enclosed. A notice of issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosures:
- 1. Amendment No. 336 to DPR-33
- 2. Amendment No. 359 to DPR-52
- 3. Amendment No. 319 to DPR-68
- 4. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 336 Renewed License No. DPR-33
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (the licensee) dated July 10, 2025, as supplemented by letter dated August 14, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 2.C.(2) of Renewed Facility Operating License No. DPR-33 is hereby amended, in part, to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 336, are hereby incorporated in the renewed operating license. The licensee 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 10 days from the date of issuance.
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: September 8, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.09.08 15:31:36 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 336 RENEWED FACILITY OPERATING LICENSE NO. DPR-33 BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), 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-33 License DPR-33 Page 3 Page 3 TSs TSs 3.8-25 3.8-25
BFN-UNIT 1 Renewed License No. DPR-33 Amendment No. 336 (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3952 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 336, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.
DC Sources - Operating 3.8.4 BFN-UNIT 1 3.8-25 Amendment No. 234, 315, 336 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of expected life with capacity
< 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%
of manufacturer's rating SR 3.8.4.5
NOTE-------------------------
Credit may be taken for unplanned events that satisfy this SR.
Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.
In accordance with the Surveillance Frequency Control Program
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 359 Renewed License No. DPR-52
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated July 10, 2025, as supplemented by letter dated August 14, 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 Title 10 of the Code of Federal Regulations (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 Commission's 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 2.C.(2) of Renewed Facility Operating License No. DPR-52 is hereby amended, in part, to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 359, are hereby incorporated in the renewed operating license. The licensee 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 10 days from the date of issuance.
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: September 8, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.09.08 15:32:16 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 359 RENEWED FACILITY OPERATING LICENSE NO. DPR-52 BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), 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-52 License DPR-52 Page 3 Page 3 TSs TSs 3.8-25 3.8-25
BFN-UNIT 2 Renewed License No. DPR-52 Amendment No. 359 sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3952 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 359, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 253. For SRs that existed prior to Amendment 253, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 253.
(3)
The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's
DC Sources - Operating 3.8.4 BFN-UNIT 2 3.8-25 Amendment No. 253, 338, 359 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of expected life with capacity
< 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%
of manufacturer's rating SR 3.8.4.5
NOTE-------------------------
Credit may be taken for unplanned events that satisfy this SR.
Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.
In accordance with the Surveillance Frequency Control Program
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 319 Renewed License No. DPR-68
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated July 10, 2025, as supplemented by letter dated August 14, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (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 2.C.(2) of Renewed Facility Operating License No. DPR-68 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 319, are hereby incorporated in the renewed operating license. The licensee 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 10 days from the date of issuance.
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: September 8, 2025 DAVID WRONA Digitally signed by DAVID WRONA Date: 2025.09.08 15:32:45 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 319 RENEWED FACILITY OPERATING LICENSE NO. DPR-68 BROWNS FERRY NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-296 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), 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-68 License DPR-68 Page 3 Page 3 TSs TSs 3.8-25 3.8-25
BFN-UNIT 3 Renewed License No. DPR-68 Amendment No. 319 (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3952 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 319, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 212.
DC Sources - Operating 3.8.4 BFN-UNIT 3 3.8-25 Amendment No. 212, 298, 319 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.4.4 Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of expected life with capacity
< 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected life with capacity 100%
of manufacturer's rating SR 3.8.4.5
NOTE-------------------------
Credit may be taken for unplanned events that satisfy this SR.
Verify each required battery charger supplies 300 amps for the Unit and 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.
In accordance with the Surveillance Frequency Control Program
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 336, 359, AND 319 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-33, DPR-52, AND DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296
1.0 INTRODUCTION
By application dated July 10, 2025 (Agencywide Documents Access and Management System Accession No. ML25191A239), as supplemented by letter dated August 14, 2025 (ML25226A098), the Tennessee Valley Authority (TVA, the licensee), submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (Browns Ferry or BFN), Units 1, 2, and 3. The proposed changes would revise each Browns Ferry units Technical Specification (TS) Surveillance Requirement (SR) 3.8.4.5 to modify the minimum battery charger capacity for the direct current (DC) shutdown board subsystems.
The supplement dated August 14, 2025, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 6, 2025 (90 FR 37891).
2.0 REGULATORY EVALUATION
2.1
System Description
As described in section 8.6 of the Browns Ferry Updated Final Safety Analysis Report (UFSAR)
(ML23335A067) and summarized in the LAR, the Browns Ferry DC electrical power system provides the alternating current (AC) emergency power system with control power. The 250 volt (V) DC (VDC) power system consists of two subsystems: a six-battery unit system and a five-battery control power system (shutdown board batteries).
Five 250 VDC shutdown board subsystems supply control power for 4.16 kilovolt (kV) shutdown boards A, B, C, D, and 3EB, respectively, and 480 V shutdown boards 1A, 1B, 2A, and 2B.
Each DC shutdown board subsystem consists of a battery together with the associated charger, circuitry, switches, indicators, and alarms. Each shutdown board DC subsystem can receive power from its own battery, battery charger, or from the spare charger.
The batteries for the shutdown board DC electrical power subsystem are sized to produce the required capacity at 80 percent of nameplate rating, corresponding to warranted capacity at end of life cycles and the 100 percent design demand. The minimum design voltage limit for the shutdown board DC subsystem is 210 V.
Each battery charger for the shutdown board DC electrical power subsystem has ample power output capacity for the steady state operation of the connected loads required during normal operation, while at the same time maintaining its battery bank fully charged. Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while supplying normal steady state loads.
UFSAR section 8.6.3 states that each charger in the 250 VDC power system shall be sized to recharge its battery from the design minimum charge based on actual duty cycle ampere-hour discharge in approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> under load conditions.
2.2 Proposed TS Changes
The licensee proposed the following change to each Browns Ferry units TS SR 3.8.4.5 (deletion shown in strikeout, addition shown in bold):
Verify each required battery charger supplies 300 amps for the Unit and 50 48 amps for the Shutdown Board subsystems at 210 V and 15 amps for DG subsystems at 105 V.
2.3 Regulations and Regulatory Guidance Under Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Application for amendment of license, construction permit, or early site permit, whenever a holder of a license wishes to amend the license, including TSs in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. Both the common standards for licenses in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public, and that the applicant will comply with the Commissions regulations.
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36, Technical Specifications, which require, in pertinent part, that the TSs include:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
As stated in 10 CFR 50.36(b), each license authorizing operation of a production or utilization facility will include technical specifications. The TSs will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto.
The regulation at 10 CFR 50.36(c) states the categories of items that must be included in TSs. Among other items, the regulation requires that TSs include SRs. The regulation at 10 CFR 50.36(c)(3) states:
Surveillance requirements 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 limiting conditions for operation will be met.
Paragraph 50.34(a)(3)(i) of 10 CFR states that Appendix A, General Design Criteria [GDC] for Nuclear Power Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes the minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission. The principal design criteria establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.
The Browns Ferry units were designed and constructed based on the proposed GDC published by the Atomic Energy Commission (AEC) in the Federal Register (32 FR 10213) on July 11, 1967 (draft GDC). The AEC published the final rule that added Appendix A to 10 CFR Part 50, GDC for Nuclear Power Plants, in the Federal Register (36 FR 3255) on February 20, 1971, (final GDC). Final GDC 17 is approximately equivalent to draft GDC 24 and GDC 39. As discussed in Appendix A of the Browns Ferry UFSAR, TVA describes its compliance with the draft GDC as follows:
Sensors and electrical circuits necessary to the functioning of the protection systems are physically and electrically separated to prevent any single event from compromising the protection function (Criteria 23, 24). Electrical power is supplied from independent redundant sources (Criterion 24): loss of all offsite power cannot prevent the reactor protection system from functioning, if required.
The capacity of the standby power sources are adequate to accomplish all required safety functions under postulated design basis accident conditions (Criterion 39).
The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]
Edition (SRP), Chapter 16, Section 16.0, Technical Specifications, Revision 3, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1433, Vol. 1, Rev. 5, Standard Technical Specifications
[STS] General Electric [Boiling-Water Reactor] BWR/4 Plants: Specifications (ML21272A357);
and NUREG-1433, Vol. 2, Rev. 5, Standard Technical Specifications General Electric BWR/4 Plants: Bases (ML21272A358).
Revision 2 of Regulatory Guide (RG) 1.32, Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants, endorses Institute of Electrical and Electronics Engineers (IEEE)
Standard 308-1974, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, for the battery charger supply.
3.0 TECHNICAL EVALUATION
LAR section 2.3 states:
In September 2023, BFN replaced the 250 volt DC (VDC) main bank and shutdown board battery chargers. The C&D battery chargers that were replaced provided a minimum of 50 amps [A] to the 250 VDC shutdown board subsystem.
The replacement Gutor battery chargers have a tighter tolerance and, in some cases, may provide less than 50 amps.
Further, LAR section 3.0 states that:
The replacement battery chargers have the same design function as the previous battery chargers. The chargers are designed to provide the 250 VDC supply during normal operations, keep its associated battery fully charged at all times, and recharge the battery after a discharge.
In section 3.0 of the LAR, the licensee states that the maximum continuous load during a loss of offsite power with postulated fire events is 27.584 A. Further, the licensee states that the 250 VDC shutdown board battery chargers are designed to fulfill their safety function with a minimum of 47.180 A, such that (1) the battery charger is adequate to recharge the battery and simultaneously supply the connected continuous control load at the shutdown battery distribution boards, and (2) the battery will not continue to discharge once the charger becomes available. A conservative amperage limit of 48 A is proposed in the TS. The NRC staff finds that since the battery chargers are required to supply 47.180 A to fulfill the safety function, specifying 48 A as the revised amperage acceptance criterion in SR 3.8.4.5 is adequate and, therefore, is acceptable.
For the battery charger replacement, the licensee evaluated impacts to the electrical power systems, including loading, ampacity, circuit protection, and voltage drop. The licensee concluded, as stated in section 3.0 of the LAR, that the design functions of the 250 VDC electrical power system are not adversely affected. In accordance with its audit plan (ML25199A137), the NRC staff performed an audit of calculations and technical evaluations related to the Class 1E electrical power systems, including, but not limited to, load study, sizing, load flow, short circuit, voltage drop, and cable ampacity, as discussed in the audit summary report (ML25227A148). As noted in the audit summary report, the staff verified that the calculations and technical evaluations on the Class 1E power systems evaluated the impact due to the change of the battery charger. The staff verified that the battery charger is sized to recharge the battery from the worst-case duty cycle discharge within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while supplying normal continuous loads and, therefore, the shutdown battery chargers are adequately sized to perform their safety function. Based on the calculations and technical evaluations, the staff confirmed that (1) Class 1E power systems remain adequate to accomplish all required safety functions under postulated design-basis accident conditions, (2) the protection devices in the Class 1E power systems remain adequate to perform their safety functions, (3) design functions of the 250 VDC power system are not adversely affected, (4) the ampere requirement in SR 3.8.4.5 is within the battery charger design capacity, and (5) the Class 1E power systems continue to meet RG 1.32, Revision 2.
Based on the above, the NRC staff finds: (1) the battery chargers will continue to be capable of supplying the required loads under design-basis events and recharge the batteries in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from minimum design charge state to the full charge after the event, and (2) the minimum ampere requirement is within the battery charger design capacity that provides assurance that each safety-related battery charger will be capable of supplying the largest combined demands of the various continuous steady-state loads and recharge the battery from design minimum charge state to a fully charged state, while staying within the capacity of the protective devices.
Modifying the current limit verified in SR 3.8.4.5 from 50 A to 48 A, which is within the battery charger design rating, confirms that the SR will be a test that ensures that the necessary capability of the shutdown board battery chargers is maintained and that the LCO will continue to be met. The NRC staff concludes that with the proposed change, SR 3.8.4.5 will continue to meet the requirements of 10 CFR 50.36(c)(3) and draft GDC 24 and 39 (final GDC 17) and will continue to conform to the guidance in RG 1.32, Revision 2. Therefore, the NRC staff finds the change proposed in the LAR to be acceptable.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
The NRCs regulations in 10 CFR 50.92 state that the NRC may make a final determination that a license amendment involves no significant hazards consideration if operation of the facility, in accordance with the amendment, would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
As required by 10 CFR 50.91(a), an evaluation of the issue of no significant hazards consideration is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequence of an accident previously evaluated?
Response: No The proposed change to the battery charger amperage requirements of SR 3.8.4.5 contained in BFN TS 3.8.4 does not impact the physical function of plant structures, systems, or components (SSC) or the manner in which SSCs perform their design function. The proposed change does not authorize the addition of any new plant equipment or systems, nor does it alter the assumptions of any accident analyses. The DC electrical power system, including the battery chargers, is not an initiator of any accident sequence analyzed in the BFN UFSAR. Rather, the DC electrical power system supports operation of equipment used to mitigate accidents. Specifically, the purpose of the battery chargers is to continuously maintain their respective battery in a charged standby condition while providing power to the system loads. The proposed change does not adversely affect accident initiators or precursors, nor does it alter the design assumptions, conditions, and configuration or the manner in which the plant is operated and maintained.
Therefore, the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change to the battery charger amperage requirements of SR 3.8.4.5 contained in BFN TS 3.8.4 does not require any modification to the plant or change equipment operation. The proposed change will not introduce failure modes that could result in a new accident, and the change does not alter assumptions made in the safety analysis. Performance of battery testing is not a precursor to any accident previously evaluated. The proposed change will not alter the design configuration, or method of operation of plant equipment beyond its normal functional capabilities. The proposed change does not create any new credible failure mechanisms, malfunctions, or accident initiators.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No The proposed change to the battery charger amperage requirements of SR 3.8.4.5 contained in BFN TS 3.8.4 does not alter or exceed a design basis or safety limit. There is no change being made to safety analysis assumptions or the safety limits that would adversely affect plant safety as a result of the proposed change. Margins of safety are unaffected by the proposed change and the applicable requirements of 10 CFR 50.36(c)(2)(ii) and 10 CFR 50, Appendix A will continue to be met.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above evaluation, the NRC staff concludes that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff has made a final determination that no significant hazards consideration is involved for the proposed amendment and that the amendment should be issued as allowed by the criteria contained in 10 CFR 50.91.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Alabama State official was notified of the proposed issuance of the amendment on August 6, 2025. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20, and changes a surveillance requirement. 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 previously issued a proposed finding that the amendment involves no significant hazards consideration published in the Federal Register on August 6, 2025 (90 FR 37891), and there has been no public comment on such finding.
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: S. Ray, NRR L. Ramadan, NRR Date: September 8, 2025
ML25241A019 NRR-058 OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA NRR/DEX/EEEB/BC NAME KGreen ABaxter WMorton DATE 08/26/2025 09/02/2025 09/08/2025 OFFICE NRR/DSS/STSB/BC NRR/DORL/LPLII-2/BC NRR/DORL/LPLII-2/PM NAME SMehta DWrona KGreen DATE 09/04/2025 09/08/2025 09/08/2025