ML24365A040
| ML24365A040 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/28/2025 |
| From: | Dawnmathews Kalathiveettil, John Lamb Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| Kalathiveettil, D | |
| References | |
| EPID L-2024-LLA-0122 | |
| Download: ML24365A040 (21) | |
Text
January 28, 2025 Jamie M. Coleman Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS NOS. 326 AND 271, REGARDING LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-591, REVISE RISK INFORMED COMPLETION TIME PROGRAM (EPID L-2024-LLA-0122)
Dear Jamie Coleman:
The U.S. Nuclear Regulatory Commission (NRC, or the Commission) has issued the enclosed Amendment No. 326 to the Renewed Facility Operating License (RFOL) No. DPR-57 and Amendment No. 271 to RFOL No. NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, respectively, in response to your application dated September 11, 2024, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24255A892.
The amendments approve the licensees request to adopt Technical Specification Task Force (TSTF) Traveler TSTF-591, Revise Risk Informed Completion Time (RICT) Program, into the Hatch Unit Nos. 1 and 2 Technical Specifications (TSs). TSTF-591 revises the TSs Section 5.5.16, Risk Informed Completion Time Program, to reference Regulatory Guide 1.200, Revision 3, instead of Revision 2, and to make other changes. The amendments add a new TS Section 5.6.8, Risk Informed Completion Time (RICT) Program Upgrade Report, to report to NRC of newly developed methods and their implementation.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
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. 326 to DPR-57
- 2. Amendment No. 271 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. 326 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 September 11, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by the new license condition and page changes to the Technical Specifications as indicated in the attachment to this license amendment, and the first paragraph of 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. 326, 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 its date of issuance and shall be implemented within 90 days from 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
Attachment:
Changes to Renewed Facility Operating License No. DPR-57 and Technical Specifications Date of Issuance: January 28, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.01.28 17:27:31 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 326 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License Page 4 Page 4 TS TS 5.0-19a 5.0-19a 5.0-23 5.0-23 Renewed License No. DPR-57 Amendment No. 326 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. 326, 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.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Risk Informed Completion Time Program (continued) c.
When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
1.
For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.
2.
For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
3.
Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
d.
For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
1.
Numerically accounting for increased possibility of CCF in the RICT calculation; or 2.
Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
e.
A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
g.
A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
(continued)
HATCH UNIT 1 5.0-19a Amendment No. 326
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 5.6.8 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued) ii.
BWROG-TP-11-023-A, Revision O (0900876.401, Revision 0-A),
"Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure Temperature Curve Evaluations," dated May 2013.
c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
a.
The PRA models upgraded to include newly developed methods; b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
c.
Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and d.
All changes to key assumptions related to newly developed methods or their implementation.
HATCH UNIT 1 5.0-23 Amendment No. 326
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. 271 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 September 11, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by the new license condition and page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. 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. 271 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 its date of issuance and shall be implemented within 90 days from 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
Attachment:
Changes to Renewed Facility Operating License No. NPF-5 and Technical Specifications Date of Issuance: January 28, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.01.28 17:28:35 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 271 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License Page 4 Page 4 TS TS 5.0-19a 5.0-19a 5.0-23 5.0-23
Renewed License No. NPF-5 Amendment No. 271 (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. 271 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.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Risk Informed Completion Time Program (continued) c.
When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
1.
For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.
2.
For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e.,
not the RICT) or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change, whichever is less.
3.
Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.
d.
For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
1.
Numerically accounting for the increased possibility of CCF in the RICT calculation; or 2.
Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
e.
A RICT calculation must include the following hazard groups: Internal Events PRA model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
g.
A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
(continued)
HATCH UNIT 2 5.0-19a Amendment No. 271
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 5.6.8 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued) ii.
BWROG-TP-11-023-A, Revision O (0900876.401, Revision 0-A),
"Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," dated May 2013.
c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
a.
The PRA models upgraded to include newly developed methods; b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, "Newly Developed Method Requirements and Peer Review;"
c.
Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and d.
All changes to key assumptions related to newly developed methods or their implementation.
HATCH UNIT 2 5.0-23 Amendment No. 271
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 326 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 271 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 PROPOSED CHANGE
S By letter dated September 11, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24255A892), Southern Nuclear Operating Company (SNC, the licensee) requested changes to the Technical Specifications (TSs) for Edwin I, Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, by license amendment request (application). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP).1 The proposed changes would revise the TS based on Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT)
Program (TSTF-591) (ML22081A224), and the associated NRC staff safety evaluation (SE) of Traveler TSTF-591 (ML23262B230).
The proposed changes would revise the TS 5.5.16, Risk Informed Completion Time Program, to incorporate Regulatory Guide (RG) 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, Revision 3, December 2020 (ML20238B871), in the current licensing basis and delete RG 1.200, Revision 2, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities, March 2009 (ML090410014). The proposed changes would add a new TS Section 5.6.8, Risk Informed Completion Time (RICT) Program Upgrade Report, for the licensee to report to the NRC newly developed methods and their implementation prior to first use of those methods.
1 The CLIIP refers to a method used by the NRC to streamline and enhance its existing license amendment request (LAR) regulatory processes, often involving increased stakeholder participation in the licensing procedures through the Technical Specifications Task Force (TSTF).
Description of Risk-Informed Completion Time Program As described in Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c)(2)(i), the TS limiting conditions for operation (LCO) are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee must shut down the reactor or follow any remedial or required action (e.g., testing, maintenance, or repair activity) permitted by the TSs until the condition can be met. The remedial actions (i.e.,
ACTIONS) associated with an LCO contain Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and completion times (CTs). The CTs are referred to as the front stops in the context of this SE. For certain Conditions, the TSs require exiting the Mode of Applicability of an LCO (i.e., shutdown the reactor).
Topical Report (TR) Nuclear Energy Institute (NEI) 06-09, Risk Informed Technical Specifications Initiative 4b: Risk Managed Technical Specifications (RMTS), Revision 0-A (NEI 06-09-A) (Package ML122860402), provides an NRC-endorsed methodology for extending existing CTs, and thereby delay exiting the operational mode of applicability or taking Required Actions, if risk is assessed and managed within the limits and programmatic requirements established by a RICT Program. By letter dated December 22, 2022, the NRC issued Amendment Nos. 319 and 264 to revise the TS for Hatch, Units 1 and 2, respectively, to permit the use of risk-informed completion times for actions to be taken when limiting conditions for operation are not met. The changes were based on Technical Specifications Task Force (TSTF)
Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.
1.1 Proposed TS Changes to Adopt TSTF-591 TS 5.5.16 Risk Informed Completion Time Program The licensee is proposing to revise TS 5.5.16, which describes the RICT program at Hatch, Unit Nos. 1 and 2. Existing paragraph e. would be replaced with the revised paragraph e., and new paragraphs f. and g. would be added as follows:
- e.
A RICT calculation must include the following hazard groups: Internal Events PRA [probabilistic risk assessment] model, Internal Flooding PRA model, Internal Fire Events PRA model, and seismic hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
- f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities."
- g.
A report shall be submitted in accordance with Specification 5.6.8 before a newly developed method is used to calculate a RICT.
TS 5.6.8, Risk Informed Completion Time (RICT) Program Upgrade Report The licensee is proposing to add a new specification, TS 5.6.8, as follows:
Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
- a.
The PRA models upgraded to include newly developed methods;
- b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review;
- c.
Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and
- d.
All changes to key assumptions related to newly developed methods or their implementation.
2.0 REGULATORY EVALUATION
2.1 Applicable Regulatory Requirements and Guidance The regulation 10 CFR) 50.36(b), Technical Specifications, 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 then listed in 10 CFR 50.36(c).
The regulation at 10 CFR 50.36(c)(5), states, in part, that administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
Hatch, Unit 1, was designed and constructed based on the proposed General Design Criteria (GDC), issued for comment in the Federal Register (32 FR 10213) by the Atomic Energy Commission (AEC) on July 11, 1967 (hereafter draft GDC). The AEC published the final rule that added Appendix A to 10 CFR Part 50, General Design Criteria for Nuclear Power Plants, in the Federal Register on February 20, 1971 (36 FR 3255, as corrected, 36 FR 12733; July 7, 1971) (hereafter adopted GDC or GDC). As discussed in the NRC Staff Requirements Memorandum (SRM) for SECY-92-223, Resolution of Deviations Identified During the Systematic Evaluation Program, dated September 18, 1992 (ML18100B279), the Commission decided not to apply the adopted GDC to plants with construction permits issued prior to May 21, 1971. The Commission stated in this SRM that the plants licensed before the GDC were formally adopted were evaluated on a plant-specific basis, determined to be safe, and that current regulatory processes are sufficient to ensure that plants continue to be safe and comply with the intent of the GDC. This SRM also notes that the GDC were not new requirements and were promulgated to more clearly articulate the licensing requirements and practice in effect at that time. The Hatch, Unit 1, Updated Final Safety Analysis Report (UFSAR) (ML24249A052),
Appendix F, Conformance to the Atomic Energy Commission (AEC) Criteria contains an evaluation of the Hatch, Unit 1, design basis against the adopted GDC.
By letter dated December 22, 2022 (ML22297A146), the NRC staff issued the Amendment Nos.
319 and 264 for Hatch, Units 1 and 2, respectively. Amendment Nos. 319 and 264 revised TSs requirements to permit the use of risk-informed completion times for actions to be taken when limiting conditions for operation are not met. The changes were based on Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.
NRC Regulatory Guides (RGs) provide one way for licensees to ensure compliance with the NRCs regulations. The NRC staff considered the following NRC guidance and industry guidance endorsed by the NRC, during its review of the proposed changes:
RG 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, December 2020 (ML20238B871).
NUREG-0800, Revision 3, Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [light-water reactor] Edition:
Chapter 19, Section 19.2, Review of Risk Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, dated June 2007 (ML071700658).
Chapter 16, Section 16.0, Technical Specifications, March 2010 (ML100351425). The NRC staffs review includes consideration of whether the proposed changes are consistent with the NRC NUREG-1433, Standard Technical Specifications, General Electric, [boiling-water reactor] BWR/4 Plants Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ML21272A357 and ML21272A358, respectively).
Chapter 16, Section 16.1, Risk-Informed Decision Making: Technical Specifications, March 2007 (ML070380228).
NEI 06-09-A, Revision 0, Risk-Informed Technical Specifications Initiative-4b, Risk-Managed Technical Specifications (RMTS) Guidelines (ML063390639), provides guidance for risk-informed TS. The NRC staff issued a final SE approving NEI 06-09 on May 17, 2007 (ML071200238).
NEI 17-07, Revision 2, Performance of PRA Peer Reviews Using the ASME/ANS PRA Standard, provides guidance material for conducting and documenting a PRA peer review using the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA Standard, issued August 2019 (ML19231A182).
Pressurized-Water Reactor (PWR) Owners Group (PWROG) topical report PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review, establishes the definitions, processes, and technical requirements necessary to implement newly developed methods, issued July 2020 (ML20213C660). RG 1.200, Revision 3, endorsed specified portions of PWROG-19027-NP.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-591 The NRC staff compared the licensees proposed TS changes described in Section 1.1 of this SE against the changes approved in Traveler TSTF-591 and finds that the licensees proposed changes to the Hatch, Unit Nos. 1 and 2, TSs are consistent with those found acceptable in the NRC evaluation of TSTF-591.
In its final SE for Traveler TSTF-591, the NRC staff concluded that the TSTF-591 proposed changes to Standard Technical Specification (STS) 5.5.20, Risk Informed Completion Time Program, and the proposed addition of STS 5.6.8, Risk Informed Completion Time (RICT)
Program Upgrade Report, were acceptable. These modifications were acceptable because they continued to ensure the PRA models used to calculate a RICT are maintained and upgraded by the licensees appropriate use of endorsed guidance (i.e., the ASME/ANS PRA Standard requirements and specific industry guidance that the NRC staff has determined are sufficient for determining the acceptability of PRA models and newly developed methods for use in the RICT program).
Furthermore, as discussed in the traveler TSTF-591 SE, the addition of reporting requirements does not preclude any NRC staff oversight of PRA changes performed to ensure the PRA model(s) continue to be maintained and upgraded consistent with RG 1.200, Revision 3. Based on the above, the NRC staff found that the proposed changes to the RICT Program in TS 5.5.16 and addition of the RICT Program Upgrade Report requirements in TS 5.6.8 would continue to meet the requirements of 10 CFR 50.36(c)(5), by providing administrative controls necessary to assure operation of the facility in a safe manner, and are, therefore, acceptable.
3.2 TS Change Consistency The NRC staff reviewed the licensees 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 Hatch plant-specific design criteria and are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the State of Georgia official was notified of the proposed issuance of the amendments on December 29, 2024. The State official confirmed the State of Georgia had no comments on December 30, 2024.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. 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 had previously issued a proposed finding that the amendments involve no significant hazards consideration in the Federal Register on October 29, 2024 (89 FR 85996),
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 to be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: A. Russell, NRR Date: January 28, 2025.
ML24365A040 OFFICE NRR/DORL/LPL2-1/PM*
NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME JLamb KZeleznock SMehta DATE 12/29/2024 12/31/2024 01/07/2025 OFFICE OGC - NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MChwedczuk MMarkley DKalathiveettil (JLamb for)
DATE 01/23/2025 01/28/2025 01/28/2025