ML25350C117
| ML25350C117 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/30/2025 |
| From: | Dawnmathews Kalathiveettil Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| Kalathiveettil, D | |
| References | |
| EPID L-2025-LLA-0028 | |
| Download: ML25350C117 (0) | |
Text
December 30, 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. 330 AND 275 TO REVISE TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.8.1.2 AND 3.8.1.5 FOR DIESEL GENERATOR LOADING (EPID L-2025-LLA-0028)
Dear Ms. Coleman:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 330 to Renewed Facility Operating License No. DPR-57 and Amendment No. 275 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, respectively, in response to the application dated February 6, 2025.
The amendments revise Hatch Technical Specification (TS) Surveillance Requirement (SR) diesel generator (DG) loading required by SR 3.8.1.2 and SR 3.8.1.5. Specifically, the proposed change would replace the current DG loading requirements with a loading requirement of 90 to 100% of the continuous rating for the DGs.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions monthly Federal Register notice.
J. Coleman If you have any questions, please contact me at dawnmathews.kalathiveettil@nrc.gov or 301-415-5905.
Sincerely,
/RA John G. Lamb for/
Dawnmathews T. Kalathiveettil, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 330 to DPR-57
- 2. Amendment No. 275 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. 330 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 February 6, 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. 330, 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 120 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: December 30, 2025 SHAWN WILLIAMS Digitally signed by SHAWN WILLIAMS Date: 2025.12.30 14:06:56 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 330 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 3.8-8 3.8-8 3.8-9 3.8-9
Renewed License No. DPR-57 Amendment No. 330 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. 330, 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.
AC Sources - Operating 3.8.1 HATCH UNIT 1 3.8-8 Amendment No. 330 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.2
NOTES-----------------------------
(continued)
- 6.
Starting transients above the upper voltage limit do not invalidate this test.
- 7.
Momentary transients outside the load range do not invalidate this test.
- 8.
This Surveillance shall be conducted on only one DG at a time.
Verify each DG:
- a.
Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b.
Operates for 60 minutes at a load 2565 kW and 2850 kW.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.3 Verify each day tank contains 500 gallons of fuel oil.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.4 Check for and remove accumulated water from each day tank.
In accordance with the Surveillance Frequency Control Program (continued)
AC Sources - Operating 3.8.1 HATCH UNIT 1 3.8-9 Amendment No. 330 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.5
NOTES-----------------------------
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
DG loadings may include gradual loading as recommended by the manufacturer.
- 3.
Momentary load transients outside the load range do not invalidate this test.
- 4.
This Surveillance shall be conducted on only one DG at a time.
- 5.
For the swing DG, a single test will satisfy this Surveillance for both units, using the starting circuitry of Unit 1 and synchronized to 4160 V bus 1F for one periodic test and the starting circuitry of Unit 2 and synchronized to 4160 V bus 2F during the next periodic test.
Verify each DG:
- a.
Starts from standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b.
Operates for 60 minutes at a load 2565 kW and 2850 kW.
In accordance with the Surveillance Frequency Control Program (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. 275 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 February 6, 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. 275, 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 120 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: December 30, 2025 SHAWN WILLIAMS Digitally signed by SHAWN WILLIAMS Date: 2025.12.30 14:07:33 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 275 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 3.8-8 3.8-8 3.8-9 3.8-9 (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. 275 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.
Renewed License No. NPF-5 Amendment No. 275
AC Sources - Operating 3.8.1 HATCH UNIT 2 3.8-8 Amendment No. 275 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.2
NOTES---------------------------
(continued)
- 6.
Starting transients above the upper voltage limit do not invalidate this test.
- 7.
Momentary transients outside the load range do not invalidate this test.
- 8.
This Surveillance shall be conducted on only one DG at a time.
Verify each DG:
- a.
Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b.
Operates for 60 minutes at a load 2565 kW and 2850 kW.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.3 Verify each day tank contains 500 gallons of fuel oil.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.4 Check for and remove accumulated water from each day tank.
In accordance with the Surveillance Frequency Control Program (continued)
AC Sources - Operating 3.8.1 HATCH UNIT 2 3.8-9 Amendment No. 275 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.5
NOTES-----------------------------
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
DG loadings may include gradual loading as recommended by the manufacturer.
- 3.
Momentary load transients outside the load range do not invalidate this test.
- 4.
This Surveillance shall be conducted on only one DG at a time.
- 5.
For the swing DG, a single test will satisfy this Surveillance for both units, using the starting circuitry of Unit 2 and synchronized to 4160 V bus 2F for one periodic test and the starting circuitry of Unit 1 and synchronized to 4160 V bus 1F during the next periodic test.
Verify each DG:
- a.
Starts from standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b.
Operates for 60 minutes at a load 2565 kW and 2850 kW.
In accordance with the Surveillance Frequency Control Program (continued)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 330 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 275 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 February 6, 2025 (Agencywide Documents Access and Management System Accession No. ML25037A316), Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC, the Commission) for the Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.90, Application for amendment of license, construction permit or early site permit. The amendments revise Surveillance Requirement (SR) diesel generator (DG) loading required by SR 3.8.1.2 and SR 3.8.1.5. Specifically, the proposed change would replace the current DG loading requirements with a loading requirement of 90 to 100% of the continuous rating for the DGs.
2.0 REGULATORY EVALUATION
2.1 Description Hatch Updated Final Safety Analysis Report (UFSAR), Revision 40, section 8.3.1.1.3, Standby ac [alternating current] Power, (ML24249A056) states:
The onsite standby ac power supply for [Hatch Nuclear Plant] HNP-1 and HNP-2 consists of five diesel generator units, which supply standby power to 4160-V
[Volts] essential buses 1E, 1F, 1G, 2E, 2F, and 2G. Diesel generators 1A and 1C supply Unit 1 essential buses 1E and 1G, respectively. Diesel generators 2A and 2C supply Unit 2 essential buses 2E and 2G, respectively. Diesel generator 1B is a shared facility and can supply either Unit 1 essential bus 1F or Unit 2 essential bus 2F.
Automatic starting of the diesel generator units supplying Unit 2 is initiated by any of the following conditions:
Loss-of-coolant accident (LOCA) signal.
Reactor low-water level signal.
High drywell pressure signal.
Undervoltage on essential buses 2E, 2F, and 2G, as a result of a complete loss-of-offsite power (LOSP), a sustained degraded voltage condition, or a failure in any of the redundant instrument trains sensing voltage will start the diesel associated with that individual bus.
2.2 Proposed Changes In attachment 1 of the LAR, SNC discusses the proposed change to SR 3.8.1.2 and SR 3.8.1.5. of the LAR provides the clean retyped SR 3.8.1.2 and SR 3.8.1.5. Attachment 3 of the LAR provides a mark-up of the TS Bases for information only. An additional markup is included in the Hatch, Unit 1, TS Bases to correct the DG ratings.
2.3 Reason for Proposed Changes In the LAR section 2.3, Description of, and Reason for, the Proposed Change, the licensee stated that the changes are proposed to will improve DG testing by demonstrating the ability of the DGs to run loaded to between 90 and 100% of their continuous rating during performance of SR 3.8.1.2 (monthly test) and SR 3.8.1.5 (semi-annual test).
2.4 Applicable Regulatory Requirements and Guidance The regulations under Title 10 of the Code of Federal Regulations (10 CFR) 50.36, provide the requirements for Technical Specifications (TSs). Paragraph 10 CFR 50.36(c)(3) states that 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.
The Hatch, Unit 1, is a pre-general design criteria (GDC) plant under the Atomic Energy Commission (AEC), and the Hatch, Unit 1, construction permit was received under the 70 GDC discussed in section F.2 of the Updated Final Safety Analysis Report (UFSAR) (ML24249A052).
The Hatch, Unit 1, design bases were not, therefore, developed in consideration of the 64 new GDC discussed in section F.3. However, SNC evaluated the Hatch, Unit 1, design bases against the new criteria.
The regulation 10 CFR Part 50, Appendix A, General Design Criteria [GDC] for Nuclear Power Plants, includes the following GDCs applicable to the licensees LAR:
GDC 17, (Criterion 17), Electric Power Systems, requires, in part, that onsite electric power systems possess sufficient independence, capacity, redundancy, and testability to perform their safety functions, assuming a single failure.
GDC 18 (Criterion 18), Inspection and Testing of Electric Power Systems, requires that electric power systems important to safety be designed to allow for appropriate periodic inspection and testing to assess continuity of the systems and the condition of their components
The NRC staff considered the following regulatory guidance during its review of the proposed changes:
Regulatory Guide (RG) 1.9, Revision 0, Selection of Diesel Generator Set Capacity for Standby Power Supplies, dated November 30, 1978 (ML012410194);
RG 1.9, Revision 3, Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants, dated July 31, 1993 (ML003739929)
RG 1.108, Revision 1, Please add this reference since it is in the SE (ML12216A011)
3.0 TECHNICAL EVALUATION
3.1 Current Surveillance Requirements Unit 1, SR 3.8.1.2 states:
Verify each DG:
- a. Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 1710 kW and 2000 kW.
Unit 1, SR 3.8.1.5 states:
Verify each DG:
- a. Starts by standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2250 kW and 2400 kW for DGs 1A and 1C, and 2360 kW and 2425 kW for DG 1B.
Unit 2, SR 3.8.1.2 states:
Verify each DG:
- a. Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 1710 kW and 2000 kW Unit 2, SR 3.8.1.5 states:
Verify each DG:
- a. Starts from standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2764 kW and 2825 kW for DG 2A, and 2360 kW and 2425 kW for DG 1B, and 2742 kW and 2825 kW for DG 2C.
3.2 Proposed Surveillance Requirements Proposed Unit 1, SR 3.8.1.2 states:
Verify each DG:
- a. Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2565 kW and 2850 kW.
Proposed Unit 1, SR 3.8.1.5 states:
Verify each DG:
- a. Starts by standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2565 kW and 2850 kW.
Proposed Unit 2, SR 3.8.1.2 states:
Verify each DG:
- a. Starts from standby conditions and achieves steady state voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2565 kW and 2850 kW.
Proposed Unit 2, SR 3.8.1.5 states:
Verify each DG:
- a. Starts from standby conditions and achieves, in 12 seconds, voltage 3740 V and frequency 58.8 Hz and after steady state conditions are reached, maintains voltage 3740 V and 4243 V and frequency 58.8 Hz and 61.2 Hz; and
- b. Operates for 60 minutes at a load 2565 kW and 2850 kW.
3.3
NRC Staff Evaluation
SNC stated in Section 2.3 of the LAR that the proposed change will improve DG testing by demonstrating the ability of the DGs to run loaded between 90 and 100% of their continuous rating during performance of SR 3.8.1.2 (monthly test) and SR 3.8.1.5 (semi-annual test).
The licensee stated in Section 3.1.3 of the LAR that the AC sources are designed to permit inspection and testing of all important areas and features, especially those that have a standby function, in accordance with 10 CFR 50, General Design Criterion 18. Periodic component tests are supplemented by extensive functional tests during refueling outages under simulated accident conditions.
RG 1.108, Revision 1 (ML12216A011), which describes design and operational provisions for the performance of periodic testing of diesel generator units used for onsite electric power for nuclear power plants, states:
(1) Demonstrate proper startup and verify that the required voltage and frequency are automatically attained within acceptable limits and time. This test should also verify that the components of the diesel generator unit required for automatic startup are operable.
(2) Demonstrate full-load-carrying capability (continuous rating) for an interval of not less than one hour. The test should also verify that the cooling system functions within design limits. This test could be accomplished by synchronizing the generator with the offsite power and assuming a load at the maximum practical rate.
The NRC staff finds this proposed change is consistent with RG 1.108, because the testing of DGs for Hatch, Units 1and 2, ensures the DGs availability and reliability. The revised surveillance verifies DG performance under representative loading conditions, specifically, the full-load carrying capability by testing at 90-100% of the continuous rating, to ensure DG capability.
Hatch, Units 1 and 2, SR 3.8.1.2 Bases states:
This SR helps to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition, and verifies that the DGs are capable of proper startup, synchronizing, and accepting a load approximately 60% of the continuous load rating. This demonstrates DG capability while minimizing the mechanical stress and wear on the engine. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the DG is connected to the offsite source.
The proposed changes in the SR 3.8.1.2 Bases modify the test load to greater to 90%. Thereby, the NRC staff finds this change ensures standby power availability and DG capability for startup, synchronization, and load acceptance since the testing is at greater than 90% of the continuous load rating.
Per the Hatch, Units 1 and 2, TS Bases Section 3.8.1, AC Sources - Operating, the current ratings for DGs 2A and 2C are as follows:
2850 kW - Continuous rating 3100 kW - 2000-hour rating 3250 kW - 300-hour rating 3500 kW minute rating DG 1B is currently rated as:
2850 kW - 1000-hour rating 3250 kW - 168-hour rating The proposed LAR will standardize the ratings for all DGs in Hatch, Units 1 and 2, to the following:
2850 kW - Continuous rating 3100 kW - 2000-hour rating 3250 kW - 300-hour rating 3500 kW minute rating
The NRC staff finds the proposed change in ratings of all DGs acceptable, because the proposed ratings are within the design capabilities of the DGs.
Surveillance Requirement (SR) 3.8.1.5 - Current Load Ranges:
Unit 1 DGs 1A and 1C:
2250 kW and 2400 kW (79%-84% of continuous rating)
Unit 1 DG 1B:
2360 kW and 2425 kW (83%-85% of continuous rating)
Unit 2 DG 2A:
2764 kW and 2825 kW (97%-99% of continuous rating)
Unit 2 DG 2C:
2742 kW and 2825 kW (96%-99% of continuous rating)
Proposed SR 3.8.1.5 Load Range (All DGs, Hatch, Units 1 and 2):
2565 kW and 2850 kW (90%-100% of continuous rating)
The purpose of the 1-hour surveillance is to verify that the diesel can start and is ready to accept load, not to verify the endurance limits of the DGs. DG loading levels are verified during the performance of the 24-hour endurance run. Since the loading criteria for the 24-hour endurance test is unchanged, changing the loading level for the 1-hour surveillance test will not affect the current verification of the diesel's ability to sustain the loading for a continued period of time.
RG 1.9, Revision 3, Section 2.3.2.1, Monthly Testing describes how to start and load the DG.
Specifically, Section 2.2.2, Load-Run Test" states that the monthly test operates the DG at a load of 90% to 100% of the DG continuous rating for not less than 1-hour. Therefore, the NRC staff finds that loading the Hatch, Units 1 and 2, DGs at a minimum of 90% is acceptable for the 1-hour surveillance test since it is consistent with agency position in RG 1.9, Revision 3.
An engine malfunction is not expected to be influenced by a 10% variation in loading within the manufacturers rating limit. Therefore, modifying the minimum loading during the surveillance test to 90% (2565 KW) is acceptable. The acceptance criterion for the test remains the stabilization of the voltage and frequency within the prescribed acceptable limits. In addition, all parameters monitoring the condition of the running engine are expected to stabilize within the 1-hour test duration. When the DG starts, any malfunction of the engine or its supporting systems will immediately be indicated by abnormal display of such parameters such as rapid rising lube oil/jacket water temperature, fluid leakage, vibration, governor malfunction, and fuel delivery. Therefore, the staff finds that loading the DG at a minimum of 90% is acceptable for the 1-hour surveillance test.
GDC 17 requires that onsite electric power systems have sufficient capacity and capability to permit functioning of structures, systems, and components important to safety. The proposed change is to test the DGs at 90-100% of their continuous rating, and the NRC staff finds that testing at 90-100% of the continuous rating verifies that the DG will be able to perform its safety function. The proposed change enhances the reliability of the DGs by verifying their performance under realistic load conditions and remains within the design and licensing basis of the facility. Therefore, the NRC staff finds that the proposed change continues to comply with GDC 17, and is consistent with the recommendations RG 1.9, does not introduce any new safety concerns and remains within the current licensing basis.
SR 3.8.1.2 and SR 3.8.1.5 continue to allow inspection and testing to verify system continuity and component condition therefore the proposed change ensures the operability of the DGs maintains the plants design and licensing basis and the staff finds that the proposed change continues to comply with GDC 18.
The NRC staff notes that, although the original application requested a 60-day implementation period, the licensee subsequently made a verbal request to extend the implementation period to 120 days. The licensee indicated that this extension was requested to accommodate the possibility that NRC approval may be granted earlier than originally estimated.
3.4 Technical Conclusion The NRC staff reviewed the licensees proposed changes for Hatch, Units 1 and 2, which would require operation of the diesel generators between 90% and 100% of their continuous rating during SR 3.8.1.2 (monthly) and SR 3.8.1.5 (semi-annual) surveillance testing. Based on the technical evaluation above, the NRC staff finds that the proposed Technical Specification changes are acceptable because the revised surveillance requirements continue to demonstrate sufficient capacity, capability, and testability to ensure the diesel generators can perform their safety function. Therefore, the NRC staff concludes that the changes do not impact the licensees continued compliance with the regulatory requirements in 10 CFR 50.36(c)(3), 10 CFR Part 50, Appendix A, GDC 17 and GDC 18, and applicable Regulatory Guides.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Georgia State official was notified of the proposed issuance of the amendment on December 10, 2025. The State official confirmed the State of Georgia had no comments on December 18, 2025.
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 10CFR Part 20 and changes surveillance requirements. 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 April 15, 2025 (90 FR 15727), 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 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 Contributors: K. James, NRR S. Ray, NRR T. Sweat, NRR Date: December 30, 2025
ML25350C117 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DEX/EEEB/BC NAME DKalathiveettil (JLamb for)
KZeleznock WMorton DATE 12/09/2025 12/22/2025 09/16/2025 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley (SWilliams for)
DKalathiveettil (JLamb for)
DATE 12/30/2025 12/30/2025