ML25224A024
| ML25224A024 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/05/2025 |
| From: | Robert Davis Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| EPID L-2025-LLA-0074 | |
| Download: ML25224A024 (1) | |
Text
September 5, 2025 Ms. Jamie M. Coleman Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
3535 Colonnade Parkway, N 274.EC Birmingham, AL 35243
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 329 AND 274 TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-584, ELIMINATE AUTOMATIC RWCU SYSTEM ISOLATION ON SLC INITIATION (EPID L-2025-LLA-0074)
Dear Ms. Coleman:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 329 to Renewed Facility Operating License No. DPR-57 and Amendment No. 274 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch), respectively, in response to the application dated April 18, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25108A112).
The amendments revise Hatch Technical Specification (TS) 3.3.6.1, Primary Containment Isolation Instrumentation, to remove the requirement that the reactor water cleanup (RWCU) system automatically isolate on manual initiation of the standby liquid control (SLC) system. The SLC system is manually actuated in response to an anticipated transient without scram event.
The amendment is based on NRC-approved Technical Specifications Task Force (TSTF)
Traveler TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
If you have any questions, please contact me at Rachael.Davis@nrc.gov.
Sincerely,
/RA/
Rachael Davis, Project Manager Licensing Data Analytics and Assessments Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 329 to DPR-57
- 2. Amendment No. 274 to NPF-5
- 3. Safety Evaluation cc: Listserv
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 329 Renewed License No. DPR-57
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners),dated April 18, 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, paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 329, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:
SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-57 and the Technical Specifications Date of Issuance: September 5, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.09.05 11:25:18 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 329 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 4
4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.3-53 3.3-53 3.3-58 3.3-58 Renewed License No. DPR-57 Amendment No. 329 for sample analysis or instrument calibration, or associated with radioactive apparatus or components (6)
Southern Nuclear, 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 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below:
(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady-state reactor core power levels not in excess of 2,804 megawatts thermal.
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 329, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:
SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.
(3)
Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated April 4, 2018, supplemented by letters dated May 28, August 9, October 7, and December 13, 2019, and February 5, and March 13, 2020, and as approved in the NRC safety evaluation (SE) dated June 11, 2020. 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.
Primary Containment Isolation Instrumentation 3.3.6.1 HATCH UNIT 1 3.3-53 Amendment No. 329 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
E.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
F.1 Isolate the affected penetration flow path(s).
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> G.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
G.1 Isolate the affected penetration flow path(s).
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> H.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
OR Required Action and associated Completion Time of Condition F or G not met.
H.1 Be in MODE 3.
AND H.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours I.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
I.1 Initiate action to restore channel to OPERABLE status.
Immediately
Primary Containment Isolation Instrumentation 3.3.6.1 HATCH UNIT 1 3.3-58 Amendment No. 329 Table 3.3.6.1-1 (page 4 of 5)
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.
RCIC System Isolation (continued) g.
RCIC Suppression Pool Area Differential Temperature - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 42°F h.
Emergency Area Cooler Temperature - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 169°F 5.
RWCU System Isolation a.
Area Temperature - High 1,2,3 1 per area F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 150°F b.
Area Ventilation Differential Temperature -
High 1,2,3 1 per area F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 67°F c.
(Deleted) d.
Reactor Vessel Water Level - Low Low, Level 2 1,2,3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
-47 inches 6.
RHR Shutdown Cooling System Isolation a.
Reactor Steam Dome Pressure - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 145 psig b.
Reactor Vessel Water Level - Low, Level 3 3
2 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 0 inches (continued)
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 274 Renewed License No. NPF-5
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated April 18, 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, paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 274, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-5 and the Technical Specifications Date of Issuance: September 5, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.09.05 11:26:35 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 274 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 4
4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.3-53 3.3-53 3.3-58 3.3-58
Renewed License No.
NPF-5 Amendment No. 274 (6)
Southern Nuclear, 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 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions2 specified or incorporated below:
(1)
Maximum Power Level Southern Nuclear is authorized to operate the facility at steady sate reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B); as revised through Amendment No. 274 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.
(a)
Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated April 4, 2018, supplemented by letters dated May 28, August 9, October 7, and December 13, 2019, and February 5, and March 13, 2020, and as approved in the NRC safety evaluation (SE) dated June 11, 2020. 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 2
The original licensee authorized to possess, use, and operate the facility with Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.
Primary Containment Isolation Instrumentation 3.3.6.1 HATCH UNIT 2 3.3-53 Amendment No. 274 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
E.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
F.1 Isolate the affected penetration flow path(s).
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> G.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
G.1 Isolate the affected penetration flow path(s).
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> H.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
OR Required Action and associated Completion Time of Condition F or G not met.
H.1 Be in MODE 3.
AND H.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours I.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
I.1 Initiate action to restore channel to OPERABLE status.
Immediately
Primary Containment Isolation Instrumentation 3.3.6.1 HATCH UNIT 2 3.3-58 Amendment No. 274 Table 3.3.6.1-1 (page 4 of 5)
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.
RCIC System Isolation (continued) g.
RCIC Suppression Pool Area Differential Temperature - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 42°F h.
Emergency Area Cooler Temperature - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 169°F 5.
RWCU System Isolation a.
Area Temperature - High 1,2,3 1 per area F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 150°F b.
Area Ventilation Differential Temperature -
High 1,2,3 1 per area F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 67°F c.
(Deleted) d.
Reactor Vessel Water Level - Low Low, Level 2 1,2,3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6
- 47 inches 6.
RHR Shutdown Cooling System Isolation a.
Reactor Steam Dome Pressure - High 1,2,3 1
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 145 psig b.
Reactor Vessel Water Level - Low, Level 3 3
2 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 0 inches (continued)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ADOPTION OF TSTF-584, ELIMINATE AUTOMATIC RWCU SYSTEM ISOLATION ON SLC SYSTEM INITIATION AMENDMENT NO. 329 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366
1.0 INTRODUCTION
By letter dated April 18, 2025 (Agencywide Documents Access and Management System Accession No. ML25108A112), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested changes to the license and technical specifications (TSs) for Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2 (Hatch). In its application, the licensee requested that the U.S.
Nuclear Regulatory Commission (NRC, the Commission) approve the proposed amendments under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the primary containment isolation instrumentation TS based on Technical Specifications Task Force (TSTF) Traveler TSTF-584, Revision 0, Eliminate Automatic RWCU [reactor water cleanup] System Isolation on SLC [standby liquid control] Initiation (TSTF-584)
(ML22054A292), and the associated NRC staff safety evaluation (SE) of TSTF-584 (ML23206A076). The NRC approved TSTF-584 under the CLIIP.
The amendments revise TS 3.3.6.1, Primary Containment Isolation Instrumentation, to remove the requirement that the RWCU system automatically isolate on manual initiation of the SLC system. The SLC system is manually actuated in response to an anticipated transient without scram (ATWS) event. Additionally, the licensee confirmed that the emergency operating procedures only credit manual initiation of the SLC system.
2.0 REGULATORY EVALUATION
2.1 System Descriptions 2.1.1 Reactor Water Cleanup System The following automatic signals to the RWCU system supply and/or return isolation valves indicate that the RWCU piping or components have been breached:
Low reactor vessel water level; RWCU system high differential flow; Main steam tunnel penetration area temperature high; and RWCU heat exchanger/pump/filter demineralizer unit area high temperature.
The TSs require the above functions to be operable. The automatic closure of the supply and/or return isolation valves, coupled with the dual check valves in each RWCU system return line isolates the RWCU system from the reactor coolant pressure boundary.
The automatic signal for RWCU system isolation on SLC system initiation that is proposed to be removed is not used to indicate any breach of RWCU piping or components.
2.1.2 Standby Liquid Control System During an ATWS event, the SLC system would bring the reactor from full power to a subcritical condition without crediting the control rods. The SLC system injects a quantity of borated water into the reactor core that adds negative reactivity sufficient to compensate for all of the various positive reactivity effects that could occur during shutdown. The licensee confirmed that the plant response to an ATWS event which requires SLC system actuation would also result in automatic isolation of RWCU.
2.2 Proposed Changes to Hatch Technical Specifications 2.2.1 Proposed TS Changes to TS 3.3.6.1 In accordance with the NRC staff approved Traveler TSTF-584 under the CLIIP dated July 31, 2023 (ML23206A124), the licensee proposed changes that would revise TS 3.3.6.1, Primary Containment Isolation Instrumentation for Hatch, Units 1 and 2. Specifically, the licensee proposed the following changes to adopt Traveler TSTF-584:
Technical Change:
Table 3.3.6.1-1, Function 5.c, RWCU System Isolation - SLC System Initiation, is deleted.
Editorial changes needed for consistency:
Table 3.3.6.1-1, Function 6.b, reference to Action J is revised to reference Action I.
TS 3.3.6.1, Actions, Condition I, which is only referenced in Function 5.c, is deleted.
TS 3.3.6.1, Actions, Condition J, is renumbered Action I.
2.2.2 Proposed Variation to TSTF-584 SNC will retain the Function numbering in TS Table 3.3.6.1-1 by replacing the Function description with the word (Deleted). The same variation is made in the TS Bases.
2.3 Applicable Regulatory Requirements and Guidance The regulation under paragraph 50.36(a)(1) of Title 10 of the Code of Federal Regulations (10 CFR) requires that:
Each applicant for a license authorizing operation of a utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. 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 under 10 CFR 50.36(b) requires that:
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 categories of items required to be in the TSs are listed in 10 CFR 50.36(c). Per 10 CFR 50.36(c)(2)(i), LCO [limiting conditions for operation] 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 TS until the condition can be met.
The regulation at 10 CFR 50.62(b) defines an ATWS as an anticipated operational occurrence as defined in Appendix A of this part followed by the failure of the reactor trip portion of the protection system specified in General Design Criterion 20 of Appendix A of this part.
The NRC staffs guidance for the review of TSs is in Chapter16.0, Technical Specifications, of NUREG-0800, Revision3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition (SRP), dated March2010 (ML100351425). Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the traveler TSTF-584.
NUREG-1433, Revision 5.0, Standard Technical Specifications, General Electric BWR/4 Plants, dated September 2021 (ML21272A357).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to TS 3.3.6.1 The NRC staff compared the licensees proposed TS changes in Section2.2 of this SE against the changes approved in NRC SE for TSTF-584. The NRC also evaluated the proposed
changes using review guidance in SRP Chapter16.0 and determined that the Standard Technical Specification changes approved in TSTF-584 are applicable to BWR/4 designs, as described in NUREG-1433, and the Hatch plant-specific design and licensing basis. The NRC staff finds that the licensees proposed changes to the Hatch TSs in Section2.2 of this SE are consistent with those found acceptable in the NRC SE for TSTF-584.
Based on the above, the NRC staff concludes that the proposal to eliminate automatic isolation of the RWCU system on the initiation of the SLC system by deleting Table 3.3.6.1-1, Function 5.c is acceptable because the specified acceptable fuel design limits will not be affected during an ATWS event. Therefore, 10 CFR 50.62(b) will continue to be met.
Additionally, 10 CFR 50.36(c)(2)(i) will continue to be met because TS3.3.6.1 continues to provide remedial actions and shuts down the reactor if the remedial actions cannot be met.
Thus, the proposed changes would continue to meet the requirements of 10CFR 50.62(b) and 10 CFR 50.36(c)(2)(i) and is, therefore, acceptable.
3.2 Proposed Variation to TSTF-584 The licensee proposed to retain the Function numbering in TS Table 3.3.6.1-1 by replacing the Function description with the word (Deleted). The NRC staff finds this change to be editorial in nature and does not alter TS requirements and is, therefore, acceptable.
3.3 Consideration of the Proposed TS Bases The NRC reviewed the TS Bases for consistency and clarity with the proposed TS changes to adopt TSTF-584. The NRC staff does not; however, approve TS Bases that are managed under a licensee-controlled program.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia State official was notified of the proposed issuance of the amendment on July 28, 2025. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10CFR Part 20. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration as published in the Federal Register on June 10, 2025 (90 FR 24417), and there has been no public comment on such finding. Accordingly, the amendment meets 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 amendment.
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 Contributor: T. Sweat, NRR Date: September 5, 2025
ML25224A024 NRR-058 OFFICE NRR/DORL/LDATA/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME RDavis KZeleznock SMehta (ARussell for)
DATE 08/11/2025 08/18/2025 08/19/2025 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LDATA/PM NAME MMarkley RDavis DATE 09/05/2025 09/05/2025