ML25122A101
| ML25122A101 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/30/2025 |
| From: | Geoffrey Miller NRC/NRR/DORL/LPL2-1 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| EPID L-2024-LLA-0166 | |
| Download: ML25122A101 (1) | |
Text
May 30, 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 THE ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-554, REVISION 1 (EPID L-2024-LLA-0166)
Dear Ms. Coleman:
In response to your application dated December 13, 2024 (Agencywide Documents Access and Management System Accession No. ML24348A233), the U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment Nos. 201 and 198 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 reactor coolant system operational leakage and the definition of the term LEAKAGE based on Technical Specifications Task Force (TSTF) Traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements.
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 301-415-2481 or ed.miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, 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. 201 to Vogtle, Unit 3, COL
- 2. Amendment No. 198 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. 201 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 December 13, 2024, 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. 201, are hereby incorporated into this license.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 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: May 30, 2025
Attachment:
Page 7 of the facility Combined License and affected pages of Appendix A of the facility Combined License MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.05.30 12:22:13 -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. 198 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 December 13, 2024, 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. 198, are hereby incorporated into this license.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 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: May 30, 2025
Attachment:
Page 7 of the facility Combined License and affected pages of Appendix C of the facility Combined License MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.05.30 12:22:48 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 201 AND 198 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 7 License No. NPF-91, page 7 License No. NPF-92, page 7 License No. NPF-92, page 7 Appendix A TSs Appendix A TSs 1.1-3 1.1-3 3.4.7-1 3.4.7-1 3.4.7-2 3.4.7-2
(7)
Reporting Requirements (a)
Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
(b)
SNC shall report any violation of a requirement in Section 2.D.(3),
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
(8)
Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 201, are hereby incorporated into this license.
(9)
Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).
(10)
Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:
(a)
Environmental Qualification Program implemented before initial fuel load; (b)
Reactor Vessel Material Surveillance Program implemented before initial criticality; (c)
Preservice Testing Program implemented before initial fuel load; (d)
Containment Leakage Rate Testing Program implemented before initial fuel load; (e)
The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7
Amendment No. 201
(7)
Reporting Requirements (a)
Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
(b)
SNC shall report any violation of a requirement in Section 2.D.(3),
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
(8)
Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 198, are hereby incorporated into this license.
(9)
Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g) with the following exceptions:
(a)
Prior to initial criticality of the reactor core while operating in plant operational Mode 5 (Cold Shutdown) or Mode 6 (Refueling) the following TS are temporarily excluded from becoming effective:
TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation, Table 3.3.8-1 o Function 14, RCS Wide Range Pressure - Low o Function 15, Core Makeup Tank (CMT) Level - Low 3 o Function 16, CMT Level - Low 6 o Function 18, IRWST Lower Narrow Range Level - Low 3 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)
Manual Initiation, Table 3.3.9-1 o Function 1, Safeguards Actuation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 9, Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation 7
Amendment No. 198
1.1 Definitions ENGINEERED SAFETY FEATURE(ESF) RESPONSE TIME LEAKAGE VEGP Units 3 and 4 Technical Specifications Definitions 1.1 The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions). The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
LEAKAGE shall be:
a.
Identified LEAKAGE 1.
LEAKAGE, such as that from seals or valve packing, that is captured and conducted to collection systems or a sump or collecting tank; 2.
LEAKAGE into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems; 3.
Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE); or 4.
RCS LEAKAGE through the passive residual heat removal heat exchanger (PRHR HX) to the In-containment Refueling Water Storage Tank (IRWST).
b.
Unidentified LEAKAGE All LEAKAGE that is not identified LEAKAGE.
c.
Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE and PRHR HX tube LEAKAGE) through a fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.
1.1 - 3 Amendment No.
Amendment No.
201 (Unit 3) 198(Unit 4)
Technical Specifications RCS Operational LEAKAGE 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Operational LEAKAGE LCO 3.4.7 RCS operational LEAKAGE shall be limited to:
a.
No pressure boundary LEAKAGE, b.
0.5 gpm unidentified LEAKAGE, c.
10 gpm identified LEAKAGE from the RCS, d.
150 gallons per day primary to secondary LEAKAGE through any one Steam Generator (SG), and e.
500 gallons per day primary to In-Containment Refueling Water Storage Tank (IRWST) LEAKAGE through the passive residual heat removal heat exchanger (PRHR HX).
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION A.
Pressure boundary A.1 LEAKAGE exists.
B.
RCS operational B.1 LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.
VEGP Units 3 and 4 REQUIRED ACTION COMPLETION TIME Isolate affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> component, pipe, or vessel from the RCS by use of a closed manual valve, closed and de-activated automatic valve, blind flange, or check valve.
Reduce LEAKAGE to within limits.
3.4.7 - 1 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Amendment No. 201 (Unit 3)
Amendment No. 198 (Unit 4)
Technical Specifications RCS Operational LEAKAGE 3.4.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Action and associated Completion Time not met.
C.1 AND C.2 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Primary to secondary LEAKAGE not within limit.
SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4.7.2 SURVEILLANCE
- NOTES -
1.
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
2.
Not applicable to primary to secondary LEAKAGE.
Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance.
- NOTE -
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
Verify primary to secondary LEAKAGE is ::; 150 gallons per day through any one SG.
FREQUENCY 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours VEGP Units 3 and 4 3.4.7 - 2 Amendment No. 201 (Unit 3)
Amendment No. 198 (Unit 4)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 201 AND 198 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 December 13, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24348A233), 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.
In its application, SNC requested that the NRC process the proposed amendment under the Consolidated Line-Item Improvement Process (CLIIP). The proposed changes would revise the technical specifications (TSs) related to reactor coolant system (RCS) operational leakage and the definition of the term LEAKAGE based on Technical Specifications Task Force (TSTF)
Traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements, (TSTF-554)
(ML20016A233), and the associated NRC staff safety evaluation (SE) of TSTF-554 (ML20322A024).
Components that contain or transport the coolant to or from the reactor core comprise the RCS.
Component joints are made by welding, bolting, rolling, or pressure loading, and valves isolate connecting systems from the RCS. During plant life, the joint and valve interfaces can produce varying amounts of reactor coolant leakage, through either normal operational wear or mechanical deterioration. The purpose of the RCS operational leakage specification is to limit operation in the presence of leakage to amounts that do not compromise integrity of the system and safety.
The safety significance of RCS leakage varies widely depending on its source, rate, and duration. Therefore, detecting and monitoring RCS leakage into the containment area is necessary. Quickly separating the identified leakage from the unidentified leakage is necessary to provide quantitative information to the operators, allowing them to take corrective action should a leak occur that is detrimental to the safety of the facility and the public.
1.1 Proposed TS Changes to Adopt TSTF-554 In accordance with NRC staff approved TSTF-554, the licensee proposed changes that would revise the TSs related to RCS operational leakage and the definition of leakage. Specifically, the licensee proposed the following changes to adopt TSTF-554:
The TS 1.1 LEAKAGE definition for Identified LEAKAGE, item a.2, would be revised to remove the exclusion of pressure boundary leakage by deleting either and the phrase or not to be pressure boundary LEAKAGE.
The TS 1.1 LEAKAGE definition for Pressure Boundary LEAKAGE, item c, would be revised to delete the word nonisolatable. The sentence, LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE, would be relocated from the Bases and added to the definition.
Additionally, the LEAKAGE definition would be revised by other editorial changes to address the deleted wording.
The Actions portion of TS 3.4.7, RCS Operational LEAKAGE, would be revised as follows:
o New Condition A. would be added to address the Condition when Pressure boundary LEAKAGE exists with a new Required Action A.1 to Isolate affected component, pipe, or vessel from the RCS by use of a closed manual valve, closed and de-activated automatic valve, blind flange, or check valve within a Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
o Existing Conditions A. and B. would be renumbered as Conditions B.
and C. to reflect the new Condition A. The existing Condition B. would be revised to delete OR Pressure boundary LEAKAGE exists because pressure boundary leakage would be addressed by the new Condition A.
1.2 Additional Proposed TS Changes In addition to the changes proposed consistent with TSTF-554 discussed in Section 1.1 above, there are editorial differences described below.
The Vogtle TS 1.1 definition of Pressure Boundary LEAKAGE replaced the indefinite article a with an to read, an RCS component because the use of articles should agree with the pronunciation of the acronyms they introduce.
The Vogtle TS 1.1 definition of Pressure Boundary LEAKAGE deleted the word nonisolatable in lieu of nonisolable. The licensee explained that While both words are undefined and are therefore subject to inconsistent interpretation as discussed in TSTF-554, they are generally considered to be the same.
Accordingly, the TSTF-554 justification for removing the word nonisolable is equally applicable to removal of the word nonisolatable from Vogtle TS 1.1.
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, Design Certification Rule for the AP1000 Design, to Part 52, 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 include limiting conditions for operation (LCO). Per 10 CFR 50.36(c)(2)(i),
LCOs 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.
The regulation at 10 CFR 50.2 defines reactor coolant pressure boundary, in part, as all those pressure-containing components of boiling and pressurized water-cooled nuclear power reactors, such as pressure vessels, piping, pumps, and valves. Regulatory Guide (RG) 1.45, Revision 1, Guidance on Monitoring and Responding to Reactor Coolant System Leakage, May 2008, Section B, Discussion, on Leakage Separation, provides information related to separation between identified and unidentified leakage (ML073200271).
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 (STSs) 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.
Traveler TSTF-554 revised the STSs related to RCS operational leakage and the definition of the term LEAKAGE. The NRC staff approved TSTF-554, under the CLIIP, on December 18, 2020 (ADAMS Package No. ML20324A083).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-554 The NRC staff compared the licensees proposed TS changes identified in Section 1.1 of this SE against the changes approved in TSTF-554. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-554 are applicable to Vogtle, Units 3 and 4, TSs because Vogtle, Units 3 and 4, are pressurized-water reactors (PWRs) and the NRC staff approved the TSTF-554 changes for PWR designs including proposed changes to TS applicable to NUREG-2149 for the AP1000. The NRC staff finds that the licensees proposed changes to the Vogtle, Units 3 and 4, TSs identified in Section 1.1 of this SE are consistent with those determined to be acceptable in TSTF-554.
In the SE for TSTF-554, the NRC staff concluded that TSTF-554 changes to STS 1.1 definition of LEAKAGE and to STS 3.4.7, which addressed conditions and required actions when reactor coolant system pressure boundary leakage exists, were acceptable. The NRC staff found that removing the term nonisolatable provided a clearer definition of pressure boundary leakage and that the source of the leakage was not relevant to this capability provided that separate, appropriate limits on pressure boundary leakage have been established. Therefore, the proposed change to the definition of leakage was acceptable as it did not conflict with 10 CFR 50.2 and was consistent with RG 1.45. The NRC staff further found that proposed new Condition A. on pressure boundary leakage, including its associated new Required Action A.1 and Completion Time, was acceptable because the LCO revisions would continue to specify the lowest functionable capability of equipment, identify remedial actions and require shutdown of the reactor if the remedial actions cannot be met.
The NRC staff finds that the proposed changes to the Vogtle, Units 3 and 4, TS are acceptable because the licensees proposed changes are consistent with those found acceptable in TSTF-554. Specifically, the proposed changes to TS 1.1 leakage definition clarifies what constitutes pressure boundary leakage and LCO 3.4.7 specifies correctly the lowest functional capability or performance levels of equipment required for safe operation of the facility. In addition, the NRC staff finds the proposed changes to the TS 3.4.7 Actions provide sufficient remedial actions to be taken until the LCO can be met and, therefore, provide reasonable assurance that the health and safety of the public will not be endangered. Thus, the NRC staff finds the proposed changes continue to meet the requirements of 10 CFR 50.36(c)(2)(i).
3.2 Additional Proposed TS Changes The licensee noted that the proposed TS changes for Vogtle, Units 3 and 4, resolve two editorial inconsistencies. These editorial inconsistencies are described in LAR Section 2.3, Other Editorial Differences, and are summarized in SE Section 1.2. The NRC staff finds that the proposed changes are consistent with the STS wording used in NUREG-2194 as modified by TSTF-554 and are, therefore, acceptable.
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).
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia State official was notified of the proposed issuance of the amendments on April 24, 2025. On May 2, 2025, the State official confirmed they had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a 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 February 18, 2025 (90 FR 9743). 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: C. Ashley, NRR Date: May 30, 2025
NAME GEMiller KZeleznock SMehta MWoods DATE 05/02/2025 05/15/2025 05/19/2025 05/23/2025 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley GEMiller DATE 5/30/2025 5/30/2025