ML25195A044
| ML25195A044 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/09/2025 |
| From: | John Lamb NRC/NRR/DORL/LPL2-1 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| EPID L-2025-LLA-0085 | |
| Download: ML25195A044 (1) | |
Text
J. Coleman September 9, 2025 Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway, Bin N-274-EC Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 ISSUANCE OF AMENDMENTS REGARDING SPENT FUEL ASSEMBLIES MAXIMUM ENRICHMENT (EPID L-2025-LLA-0085)
Dear Ms. Coleman:
In response to your application dated May 22, 2025, as supplemented by \
letter dated July 9, 2025, the U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 207 and 205 to Combined License (COL) Nos. NPF-91 and 92 for Vogtle Electric Generating Plant (Vogtle), Units 3 and 4, respectively. The amendments revise the Technical Specifications (TSs) related to spent fuel assemblies maximum enrichment. The amendments change the TSs to include nominal to clarify requirements for spent fuel assembly initial enrichment.
A copy of the related Safety Evaluation, which includes the NRC staffs evaluation of the amendment, is enclosed. The notice of issuance of the amendment documents included in this letter will be published in the Federal Register.
If you have questions, please contact me at 301-415-3100 or John.Lamb@nrc.gov.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 52-025 and 52-026
Enclosures:
- 1. Amendment No. 207 to Vogtle, Unit 3, COL
- 2. Amendment No. 205 to Vogtle, Unit 4, COL
- 3. Safety Evaluation cc: Listserv
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 3 DOCKET NO.52-025 AMENDMENT TO FACILITY COMBINED LICENSE Amendment No. 207 License No. NPF-91
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company (SNC),
dated May 22, 2025, as supplemented by letter July 9, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions regulations set forth in 10 CFR Chapter I; B.
The facility will be constructed and 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 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.
The License is also amended by changes to Appendix A, Technical Specifications, of the facility Combined License as indicated in the attachment to this license amendment.
Paragraph 2.D(8) of facility Combined License No. NPF-91 is hereby amendment to read as follows:
(8) Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 207, are hereby incorporated into this license.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION:
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: September 9, 2025.
Attachment:
- 1. Page 4 of the facility Combined License and affected pages of Appendix A of the facility Combined License MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.09.09 12:05:48 -04'00'
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 DOCKET NO.52-026 AMENDMENT TO FACILITY COMBINED LICENSE Amendment No.205 License No. NPF-92
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company (SNC),
dated May 22, 2025, as supplemented by \
letter dated July 9, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions regulations set forth in 10 CFR Chapter I; B.
The facility will be constructed and 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 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.
The License is also amended by changes to Appendix A, Technical Specifications, of the facility Combined License as indicated in the attachment to this license amendment.
Paragraph 2.D(8) of facility Combined License No. NPF-92 is hereby amendment to read as follows:
(8) Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 205, are hereby incorporated into this license.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION:
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: September 9, 2025.
Attachment:
Page 4 of the facility Combined License and affected pages of Appendix C of the facility Combined License MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.09.09 12:06:25 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 207 AND 205 TO FACILITY COMBINED LICENSE NOS. NPF-91 AND NPF-92 DOCKET NOS.52-025 AND 52-026 Replace the following pages of the facility licenses and 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 Pages Insert Pages License License License No. NPF-91, page 4 License No. NPF-91, page 4 License No. NPF-92, page 4 License No. NPF-92, page 4 Appendix A TSs Appendix A TSs 3.7.12-1 3.7.12-1 3.7.12-2 3.7.12-2 4.0-2 4.0-2
D.
The license is subject to, and SNC shall comply with, the conditions specified and incorporated below:
(1)
Changes during Construction - Removed by Amendment No. 202 (2)
Pre-operational Testing - Removed by Amendment Nos. 192 and 202 (3)
Nuclear Fuel Loading and Pre-critical Testing - Removed by Amendment Nos. 192 and 202 (4)
Initial Criticality and Low-Power Testing - Removed by Amendment No. 202 (5)
Power Ascension Testing - Removed by Amendment No. 202 (6)
Maximum Power Level (7)
(8)
SNC is authorized to operate the facility at steady state reactor core power levels not to exceed 3400 MW thermal (100-percent thermal power), as described in the UFSAR, in accordance with the conditions specified herein.
Reporting Requirements - Removed by Amendment No. 202 Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 207, are hereby incorporated into this license.
(9)
Technical Specifications - Removed by Amendment No. 202 (10)
Operational Program Implementation - Removed by Amendment No. 202 (11)
Operational Program Implementation Schedule - Removed by Amendment No.202 (12)
Site-and Unit-specific Conditions - Removed by Amendment No. 202
[Blank Pages 5 through 14 removed by Amendment No. 202.]
4 Amendment No. 207
D.
The license is subject to, and SNC shall comply with, the conditions specified and incorporated below:
(1)
Changes during Construction - Removed by Amendment No. 199 (2)
Pre-operational Testing - Removed by Amendment Nos. 194 and 199 (3)
Nuclear Fuel Loading and Pre-critical Testing - Removed by Amendment Nos. 194 and 199 (4)
Initial Criticality and Low-Power Testing - Removed by Amendment No. 199 (5)
Power Ascension Testing - Removed by Amendment No. 199 (6)
Maximum Power Level (7)
(8)
SNC is authorized to operate the facility at steady state reactor core power levels not to exceed 3400 MW thermal (100-percent thermal power), as described in the UFSAR, in accordance with the conditions specified herein.
Reporting Requirements - Removed by Amendment No. 199 Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 205, are hereby incorporated into this license.
(9)
Technical Specifications - Removed by Amendment No. 199 (10)
Operational Program Implementation - Removed by Amendment No. 199 (11)
Operational Program Implementation Schedule - Removed by Amendment No. 199 (12)
Site-and Unit-specific Conditions - Removed by Amendment No. 199
[Blank Pages 5 through 14 removed by Amendment No. 199.]
4 Amendment No. 205
Technical Specifications Spent Fuel Pool Storage 3.7.12
- 3. 7 PLANT SYSTEMS 3.7.12 Spent Fuel Pool Storage LCO 3.7.12 The combination of initial nominal enrichment and burnup of each fuel assembly stored in Region 2 shall be within the limits specified in Figure 3.7.12-1.
APPLICABILITY:
Whenever any fuel assembly is stored in Region 2 of the spent fuel pool.
ACTIONS LCO 3.0.3 is not applicable.
CONDITION A.
Requirements of the LCO not met.
A.1 SURVEILLANCE REQUIREMENTS
- NOTE -
REQUIRED ACTION COMPLETION TIME Initiate action to move the Immediately noncomplying fuel assembly to an acceptable storage location.
SURVEILLANCE FREQUENCY SR 3.7.12.1 Verify by administrative means the initial nominal enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.12-1.
Prior to storing the fuel assembly in Region 2 VEGP Units 3 and 4 3.7.12 - 1 Amendment No. 207 (Unit 3)
Amendment No. 205 (Unit 4)
45 40 35 I
s-30 25 20 15 10 5 /
0 2
Technical Specifications Region 2 Loading Curve Acceptable Region I
/
/ V
/
Spent Fuel Pool Storage 3.7.12 V
/,/
I Unacceptable Region I 2.5 3
3.5 4
4.5 5
Nominal Enrichment (wt% U-235)
Figure 3.7.12-1 Minimum Fuel Assembly Burnup Versus Initial Nominal Enrichment for Region 2 Spent Fuel Cells VEGP Units 3 and 4 3.7.12 -2 Amendment No. 207 (Unit 3)
Amendment No. 205 (Unit 4)
Technical Specifications Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having a maximum nominal U-235 enrichment of 4.95 weight percent; b.
kett::; 0.95 if flooded with unborated water which includes an allowance for uncertainties (Region 1 racks);
c.
A nominal 10.93 inch center-to-center distance between fuel assemblies placed in Region 1 of the spent fuel storage racks; d.
A nominal 9.04 inch center-to-center distance between fuel assemblies placed in Region 2 of the spent fuel storage racks; e.
A nominal 11.65 inch center-to-center distance between fuel assemblies placed in the Defective Fuel Cells; f.
New or partially spent fuel assemblies with any discharge burnup may be allowed unrestricted storage in Region 1 and the Defective Fuel Cells of Figure 4.3-1; g.
Partially spent fuel assemblies meeting the initial nominal enrichment and burnup requirements of LCO 3.7.12, "Spent Fuel Pool Storage,"
may be stored in Region 2 of Figure 4.3-1; and h.
kett < 1.0 if flooded with unborated water and kett::; 0.95 if flooded with borated water at a minimum soluble boron concentration described in the Bases for LCO 3. 7.12 for normal and design basis criticality related accident conditions, which includes an allowance for uncertainties (Region 2 racks).
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
VEGP Units 3 and 4 a.
Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; b.
The maximum kett value, including all biases and uncertainties, shall be less than or equal to 0.95 with full density unborated water; 4.0 - 2 Amendment No. 207 (Unit 3)
Amendment No. 205 (Unit 4)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 207 AND 205 TO THE COMBINED LICENSE NOS. NPF-91 AND NPF-92 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 DOCKET NOS.52-025 AND 52-026 1.0 INTRODUCTION By \
letter dated May 22, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25142A172), as supplemented by \
letter dated July 9, 2025 (ML25190A671), Southern Nuclear Operating Company (SNC, the licensee) requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) amend Vogtle Electric Generating Plant (Vogtle), Units 3 and 4, Combined License (COL) Numbers NPF-91 and NPF-92, respectively.
The proposed amendments revise the Technical Specifications (TSs) related to spent fuel assemblies maximum enrichment. The amendments change the TSs to include nominal to clarify requirements for spent fuel assembly initial enrichment. Specifically, the proposed amendments would revise TS 4.3.1.1.a and TS 4.3.1.1.g to add nominal to clarify the maximum nominal enrichment of 4.95 weight percent (wt%) uranium-235 (U-235). The proposed amendments would also change TS 3.7.12 and Figure 3. 7.12-1 to clarify that the initial enrichment is initial nominal enrichment.
The supplement dated July 9, 2025, 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 July 8, 2025 (90 FR 30114).
1.1 Proposed TS Changes
Limiting Condition for Operation (LCO) 3.7.12 Current TS 3.7.12, Spent Fuel Pool Storage, LCO 3.7.12 states:
The combination of initial enrichment and burnup of each fuel assembly stored in Region 2 shall be within the limits specified in Figure 3.7.12-1.
Revised LCO 3.7.12 would state:
The combination of initial nominal enrichment and burnup of each fuel assembly stored in Region 2 shall be within the limits specified in Figure 3.7.12-1.
Surveillance Requirement (SR) 3.7.12.1 Current SR 3.7.12.1 states:
Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.12-1.
Revised SR 3.7.12.1 would state:
Verify by administrative means the initial nominal enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.12-1.
Figure 3.7.12-1 Current title of Figure 3.7.12-1 states:
Minimum Fuel Assembly Burnup Versus Initial Enrichment for Region 2 Spent Fuel Cells Revised title of Figure 3.7.12-1 would state:
Minimum Fuel Assembly Burnup Versus Initial Nominal Enrichment for Region 2 Spent Fuel Cells Current x-axis of Figure 3.7.12-1 states:
Enrichment (wt% U-235)
Revised x-axis of Figure 3.7.12-1 would state:
Nominal Enrichment (wt% U-235)
TS 4.3.1.1.a Current TS 4.3.1.1.a states:
Fuel assemblies having a maximum U-235 enrichment of 4.95 weight percent; Revised TS 4.3.1.1.a would state:
Fuel assemblies having a maximum nominal U-235 enrichment of 4.95 weight percent; TS 4.3.1.1.g Current TS 4.3.1.1.g states:
Partially spent fuel assemblies meeting the initial enrichment and burnup requirements of LCO 3.7.12, Spent Fuel Pool Storage, may be stored in Region 2 of Figure 4.3-1; and Revised TS 4.3.1.1.g would state:
Partially spent fuel assemblies meeting the initial nominal enrichment and burnup requirements of LCO 3.7.12, Spent Fuel Pool Storage, may be stored in Region 2 of Figure 4.3-1; and
2.0 REGULATORY EVALUATION
In accordance with paragraph C.6. of Section VIII of the Code of Federal Regulations (10 CFR)
Processes for Changes and Departures of Appendix D to Part 52 Design Certification Rule for the AP1000 Design, changes to the plant-specific TS will be treated as license amendments under 10 CFR 50.90. Pursuant to 10 CFR 50.90, whenever a COL holder desires to amend the license, application for an amendment must be filed with the Commission fully describing the changes desired and following, as far as applicable, the form prescribed for original applications.
Per 10 CFR 52.79(a)(30), the application for a COL shall include proposed TSs prepared in accordance with the requirements of 10 CFR 50.36. The regulation at 10 CFR 50.36(c)(2) requires that TSs includes LCO. Per 10 CFR 50.36(c)(2)(i), LCO are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
Regulation 10 CFR 50.68(b)(4) states:
If no credit for soluble boron is taken, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. If credit is taken for soluble boron, the k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with borated water, and the k-effective must remain below 1.0 (subcritical), at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. The maximum nominal U-235 enrichment of the fresh fuel assemblies is limited to five (5.0) percent by weight.
Regulation 10 CFR 50.68(b)(7) states:
The maximum nominal U-235 enrichment of the fresh fuel assemblies is limited to five (5.0) percent by weight.
Regulation 10 CFR 50, Appendix A, General Design Criterion (GDC) 62, Prevention of criticality in fuel storage and handling, states:
Criticality in the fuel storage and handling system shall be prevented by physical systems or processes, preferably by use of geometrically safe configurations.
The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG 0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition (SRP), March 2010 (ML100351425).
As described therein, as part of the regulatory standardization effort, the NRC staff has prepared standard technical specifications for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the NUREG-2194, Revision 11, as modified by NRC approved travelers.
3.0 TECHNICAL EVALUATION
By \
letter dated July 9, 2025, SNC confirmed that Vogtle, Units 3 and 4, spent fuel pool (SFP) nuclear criticality safety analysis of record was performed up to a maximum U-235 enrichment of 4.95 weight percent (wt/%) and included a manufacturing tolerance on the enrichment that was used to calculate an uncertainty which was in turn used in the determination that 10 CFR 50.68(b)(4) was met.
In the \
letter dated July 9, 2025, SNC stated:
The spent fuel pool nuclear criticality safety analysis, APP-GW-GLR-029, was docketed under ADAMS as ML110670298. The current analysis of record continues to contain the same language regarding the maximum nominal U-235 1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000)
Plants, NUREG 2194, Volume 1 Specifications, and Volume 2, Bases, Revision 1, dated January 2024 (ADAMS Accession Nos.
ML24026A214 and ML24026A234, respectively).
enrichment of 4.95 weight percent (wt/%) (Sections 7.1, and 7.2) and the inclusion of an additional manufacturing tolerance (Sections 7.1.2 and 7.2.6).
The NRC staff reviewed APP-GW-GLR-029, as docketed under ADAMS as ML110670298, and confirmed that the estimations of k-effective were for maximum nominal initial enrichment of 4.95 wt/% of 235U.
The NRC staff finds the proposed TS changes acceptable, because the Vogtle, Units 3 and 4, SFP nuclear criticality safety analysis of record was performed up to a maximum U-235 enrichment of 4.95 weight percent (wt/%) and included a manufacturing tolerance on the enrichment that was used to calculate an uncertainty which was in turn used in the determination that 10 CFR 50.68(b)(4) was met. The NRC staff also finds the proposed TS changes acceptable, because the proposed TS changes continue to meet 10 CFR 50.68(b)(4),10 CFR 50.68(b)(7), and 10 CFR 50.36(c)(2).
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia State official was notified of the proposed issuance of the amendments on July 14, 2025. On July 21, 2025, the State official confirmed they had no comments.
5.0 ENVIRONMENTAL CONSIDERATION The amendments change the requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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, published in the Federal Register on July 8, 2025, 2025 (90 FR 30114). 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: K. Wood, NRR T. Sweat, NRR Date: September 9, 2025.
- via eConcurrence NRO-002 OFFICE NRR/DORL/LPL2-1/PM*
NRR/DORL/LPL2-1/LA*
NRR/DSS/STSB/BC*
NRR/DSS/SFNB/BC*
NAME JLamb KZeleznock SMehta SKrepel DATE 7/14/2025 7/16/2025 7/25/2025 7/23/2025 OFFICE NRR/DSS/SNSB/BC*
NRR/DORL/LPL2-1/BC*
NRR/DORL/LPL2-1/PM*
NAME NDifrancesco (SHaider for) MMarkley JLamb DATE 7/23/2025 9/9/2025 9/9/2025