ML26044A156
| ML26044A156 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/25/2026 |
| From: | Clinton Hobbs NRC/NRR/DNRL/NLRP |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| EPID L-2025-SLR-0002 | |
| Download: ML26044A156 (0) | |
Text
Jamie M. Coleman Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2-AGING MANAGEMENT AUDIT REPORT REGARDING THE SUBSEQUENT LICENSE RENEWAL APPLICATION REVIEW (EPID NO. L-2025-SLR-0002)
Dear Jamie Coleman:
By letter dated May 15, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession Package No. ML25135A390), as supplemented by letter dated December 22, 2025 (ML25356A513), Southern Nuclear Operating Company (Southern Nuclear) submitted an application for subsequent license renewal of Facility Operating License No. DPR-57 and NPF-5 for Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) to the U.S.
Nuclear Regulatory Commission (NRC, staff). Southern Nuclear submitted the application pursuant to Title 10 of the Code of Federal Regulations Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, for SLR.
The NRC staff completed its Aging Management Audit from June 16, 2025 - September 25, 2025, in accordance with a regulatory audit plan (ML25157A010). The Aging Management Audit was conducted at NRC Headquarters and at Hatch. If you have any questions, please contact Brian Harris at Brian.Harris2@nrc.gov.
Sincerely, Clinton L. Hobbs, Acting Chief License Renewal Projects Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket Nos: 50-321 & 50-366
Enclosure:
Aging Management Audit Report February 25, 2026 Signed by Hobbs, Clinton on 02/25/26
Pkg: ML26044A149 Letter: ML26044A156 Breakout Questions: ML26044A157 via* e-concurrence NRR-106 OFFICE BC: NPHP: DNRL (A) BC: NCSG: DNRL BC: NVIB: DNRL NAME MMitchell LTerry ABuford DATE 2/13/26 2/18/26 1/14/26 OFFICE BC: ESEB: DEX BC: ELTB: DEX BC: SCPB: DSS NAME ITseng JPaige MValentin DATE 2/2/26 1/12/26 2/13/26 OFFICE BC: SNSB:DSS PM: NLRP:DNRL (A) BC: NLRP:DNRL NAME NDifrancesco BHarris CHobbs DATE 2/13/26 2/23/26
Enclosure AUDIT REPORT Edwin I. Hatch Nuclear Plant, Units 1 and 2 Subsequent License Renewal Application Aging Management Regulatory Audit June 16, 2025 - September 25, 2025 Division of New and Renewed Licenses Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION DIVISION OF NEW AND RENEWED LICENSES Docket Nos:
50-321 and 50-366 License No:
Southern Nuclear Operating Company Facility:
Edwin I. Hatch Nuclear Plant, Units 1 and 2 Locations:
Rockville, Maryland Baxley, Georgia Dates:
July 28, 2025 - July 31, 2025 Approved By:
Leslie S. Terry, Acting Chief Corrosion and Steam Generator Branch Division of New and Renewed Licenses Angie R. Buford, Chief Vessels and Internals Branch Division of New and Renewed Licenses Clinton Hobbs, Acting Chief License Renewal Projects Branch Division of New and Renewed Licenses Matthew A. Mitchell, Chief Piping and Head Penetrations Branch Division of New and Renewed Licenses Jason Paige, Chief Long-Term Operations and Modernization Branch Division of Engineering and External Hazards Milton Valentin, Chief Containment and Plant Systems Branch Division of Safety Systems Ian Tseng, Chief Structural, Civil, Geotech Engineering Branch B Division of Engineering and External Hazards Reviewers:
Name Branch/Division Naeem Iqbal PRA Licensing B (APLB)/Division of Risk Assessment Daniel Ju APLB/DRA Adakou Foli Electrical Engineering Branch (EEEB)/Division of Engineering and External Hazards (DEX)
Liliana Ramadan EEEB/DEX Brian Correll Long Term Operations & Modernization Branch (ELTB)/Division of Engineering and External Hazards (DEX)
Jorge Cintron-Rivera ELTB/DEX Kenn Miller ELTB/DEX Landen Kwan ELTB/DEX Matthew McConnell ELTB/DEX Mo Sadollah Instrumentation Controls and Electrical Engineering Branch (ICEEB)/Division of Engineering (DE)
Andrew Prinaris Structural, Civil, Geotech Engineering (ESEB)/DEX Si-Hwan Park ESEB/DEX Shao Lai ESEB/DEX Aaron Gallman ESEB/DEX George Wang ESEB/DEX Dan Hoang ESEB/DEX Andy Johnson Corrosion and Steam Generator (NCSG)/Division of New and Renewed Licenses (DNRL)
Brian Allik NCSG/DNRL Dev Ray NCSG/DNRL Greg Makar NCSG/DNRL James Gavula NCSG/DNRL Joel Jenkins NCSG/DNRL Leslie Terry NCSG/DNRL Lydiana Alvarado NCSG/DNRL Matthew Yoder NCSG/DNRL Miranda McGuire NCSG/DNRL Paul Klein NCSG/DNRL Reena Boruk NCSG/DNRL Tony Gardner NCSG/DNRL Ali Rezai Piping and Head Penetrations (NPHP)/DNRL Bart Fu NPHP/DNRL Karen Sida NPHP/DNRL Seung Min NPHP/DNRL Varoujan Kalikian NPHP/DNRL David Dijamco Vessels and Internals (NVIB)/DNRL Eric Palmer NVIB/DNRL Emma Haywood NVIB/DNRL John Tsao NVIB/DNRL On Yee NVIB/DNRL Angelo Stubbs Containment and Plant Systems (SCPB)/Division of Safety Systems (DSS)
Hanry Wagage SCPB/DSS David Coy SCPB/DSS Gordon Curran SCPB/DSS Joseph Messina Nuclear Methods and Fuels (SFNB)/DSS Logan Gaul Nuclear Systems Performance (SNSB)/DSS Jo Ambrosini SNSB/DSS Chris Tyree License Renewal Projects Branch (NLRP)/DNRL Brian Harris NLRP/DNRL TABLE OF CONTENTS AUDIT REPORT....................................................................................................................... ACRONYMS............................................................................................................................. 1.
Introduction..........................................................................................................................10 2.
Audit Activities......................................................................................................................11 SLRA Section 2.1, Scoping and Screening Methodology...........................................................12 SLRA AMP B.2.2.1, Environmental Qualification of Electric Components..................................12 SLRA AMP B.2.2.2, Fatigue Monitoring......................................................................................14 SLRA AMP B 2.3.36, Electrical Insulation for Electrical Cables and Connections Not subject to 10 CFR 50.49 Environmental Qualification Requirements..................................................15 SLRA AMP B.2.3.37, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements used in Instrumentation Circuits
.............................................................................................................................................16 SLRA AMP B 2.3.38, Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.................................17 SLRA AMP B 2.3.39, Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.................................19 SLRA AMP B.2.3.40, Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.................................20 SLRA AMP B.2.3.41, Fuse Holders............................................................................................21 SLRA AMP B.2.3.42, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements..................................................................................................22 SLRA AMP B.2.3.43, High Voltage Insulators.............................................................................23 SLRA AMP B. 2.3.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD24 SLRA AMP B.2.3.2, Water Chemistry.........................................................................................25 SLRA AMP B.2.3.3, Reactor Head Closure Stud Bolting............................................................26 SLRA AMP B.2.3.4, BWR Vessel ID Attachment Welds.............................................................28 SLRA AMP B.2.3.5, BWR Stress Corrosion Cracking................................................................28 SLRA AMP B.2.3.6, BWR Penetrations......................................................................................29 SLRA AMP B.2.3.7, BWR Vessel Internals.................................................................................29 SLRA AMP B.2.3.8, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel...............31 SLRA AMP 2.3.9, Flow-Accelerated Corrosion...........................................................................31 SLRA AMP B.2.3.10, Bolting Integrity.........................................................................................33 SLRA AMP B.2.3.11, Open-Cycle Cooling Water System..........................................................33 SLRA AMP B.2.3.12, Closed Treated Water System..................................................................34 SLRA AMP B.2.3.13, Inspection of Overhead Heavy Load and Light Load (Related to Refueling)
Handling Systems................................................................................................................35 SLRA AMP B.2.3.14, Compressed Air Monitoring......................................................................36 SLRA AMP B.2.3.15, Fire Protection..........................................................................................37 SLRA AMP B.2.3.16, Fire Water System....................................................................................38 SLRA AMP B.2.3.17, Outdoor and Large Atmospheric Metallic Storage Tanks.........................39 SLRA AMP B.2.3.18, Fuel Oil Chemistry....................................................................................41 SLRA AMP B.2.3.19, Reactor Vessel Material Surveillance.......................................................42 SLRA AMP B.2.3.20, One-Time Inspection................................................................................43 SLRA AMP B.2.3.21, Selective Leaching....................................................................................43 SLRA AMP B.2.3.22, ASME Code Class 1 Small-Bore Piping...................................................44 SLRA AMP B.2.3.23, External Surfaces Monitoring of Mechanical Components.......................45 SLRA AMP B.2.3.24, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components.........................................................................................................................46 SLRA AMP B.2.3.25, Lubricating Oil Analysis............................................................................46 SLRA AMP B.2.3.26, Monitoring of Neutron-Absorbing Materials Other Than Boraflex.............47 SLRA AMP B.2.3.27, Buried and Underground Piping and Tanks..............................................48 SLRA AMP B.2.3.28, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks.......................................................................................................49 SLRA AMP B.2.3.29, ASME Section XI, Subsection IWE...........................................................50 SLRA AMP B.2.3.30, ASME Section XI, Subsection IWF...........................................................51 SLRA AMP B.2.3.31, 10 CFR Part 50, Appendix J.....................................................................52 SLRA AMP B.2.3.32, Masonry Walls..........................................................................................53 SLRA AMP B.2.3.34, RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants........................................................................................................................54 SLRA AMP B.2.3.35, Protective Coating Monitoring and Maintenance......................................56 SLRA AMP B.2.4.1, RHR Heat Exchanger Augmented Inspection (Plant Specific)...................58 SLRA AMP B.2.4.2, Torus Submerged Components Inspection (Plant Specific).......................59 SLRA TLAA Section 4.2.2, RPV Materials Upper Shelf Energy (USE) Reduction due to Neutron Embrittlement.......................................................................................................................60 SLRA TLAA Section 4.2.3, Adjusted Reference Temperature (ART) for RPV Materials due to Neutron Embrittlement.........................................................................................................61 SLRA TLAA Section 4.2.4, RPV Thermal Limit Analysis: Operating Pressure-Temperature (P-T)
Limits....................................................................................................................................63 SLRA TLAA Section 4.2.5, RPV Circumferential Weld Examination Relief................................64 SLRA TLAA Section 4.2.6, Axial Weld Failure Probability..........................................................65 SLRA TLAA Section4.2.7, Reflood Thermal Shock Analysis of the RPV....................................67 SLRA TLAA Section 4.2.8, Susceptibility to IASCC....................................................................67 SLRA TLAA Section 4.3.1, 80-Year Transient Cycle Projections...............................................68 SLRA TLAA Section 4.3.2, ASME Section III, Class 1 Fatigue Waivers.....................................69 SLRA TLAA Section 4.3.3, RPV Fatigue Analyses.....................................................................69 SLRA TLAA Section 4.3.4 Fatigue Analyses of the Reactor Pressure Vessel Internals.............70 SLRA TLAA Section 4.3.5, ASME Section III, Class I Fatigue Analysis.....................................71 SLAR TLAA Section 4.3.6, ASME Section III, Class 2 and 3 and ANSI B31.1 and Associated HELB Analyses....................................................................................................................72 SLRA TLAA Section 4.3.7, Environmentally Assisted Fatigue....................................................72 SLRA TLAA Section 4.3.8, High Energy Line Break Analyses Based on Cumulative Fatigue Usage...................................................................................................................................74 SLRA TLAA Section 4.3.9, Cycle-dependent Fracture Mechanics on Flaw Evaluations............74 SLRA TLAA Section 4.5, Concrete Containment Tendon Prestress...........................................75 SLRA TLAA Section 4.6, Liner Plate, Metal Containments, and Penetrations Fatigue Analyses
.............................................................................................................................................75 SLRA TLAA Section 4.6.1, Fatigue Analysis of the Vessel Shell to Ring Girder........................77 SLRA TLAA Section 4.6.2, Fatigue Exemption (Waivers) for Mainstream Penetration Backing Ring and Containment Penetrations....................................................................................77 SLRA TLAA Section 4.7, Other Plant Specific TLAAs................................................................77 SLRA TLAA Section 4.7.1, Crane Load Cycle Limits..................................................................77 SLRA TLAA Section 4.7.1, Fatigue of Cranes (Crane Cycle Limits)...........................................77 SLRA TLAA Section 4.7.2, Corrosion Allowance Calculations...................................................78 3.
Audit Questions Provided to SNC........................................................................................79 4.
Applicant Personnel Contacted During the Audit.................................................................80 5.
Exit Meeting.........................................................................................................................81 ACRONYMS ADAMS Agencywide Documents Access and Management System AMP aging management program AMR aging management review ASME American Society of Mechanical Engineers CAP corrective action program CASS cast austenitic stainless-steel CFR Code of Federal Regulations CLB current licensing basis CRDM control rod drive mechanism CRGT control rod guide tube CUF cumulative usage factor CUFen environmentally adjusted cumulative usage factor DBD design-basis document DBE design-basis event EAF environmentally assisted fatigue EI&C electrical and instrumentation and controls EPRI Electric Power Research Institute EQ electrical qualification ERR electronic reading room FAC flow-accelerated corrosion FSAR final safety analysis report GALL-SLR generic aging lessons learned for subsequent license renewal HELB high energy line break I&C instrumentation and control IASCC irradiation-assisted stress corrosion cracking IPA integrated plant assessment ISG Interim Staff Guidance ISI Inservice inspection Kv Kilo volt LAR license amendment request LR license renewal LTOP low temperature overpressure protection MRP materials reliability program NDE nondestructive examination NEI Nuclear Energy Institute NRC U.S. Nuclear Regulatory Commission OE Operating experience PTLR pressure-temperature limits report PWR pressurized-water reactor PWROG Pressurized-Water Reactor Owners Group PWRVI pressurized-water reactor vessel internals PWRVIP pressurized-water reactor vessel internals program PWSCC primary water stress corrosion cracking RAI request for additional information RCI Request for confirmation of information RCP reactor coolant pump RCS reactor coolant system RG Regulatory Guide RHR residual heat removal RIS Regulatory issue summary RPV reactor pressure vessel RV reactor vessel RVI reactor vessel internal SC structures and components SE safety evaluation SG steam generator SLRA subsequent license renewal application SRP Standard Review Plan TLAA Time-limited aging analyses QA quality assurance
10 Report on the Aging Management Audit Edwin I. Hatch Nuclear Plant, Unit 1 and 2 Subsequent License Renewal Application 1.
Introduction The U.S. Nuclear Regulatory Commission (NRC) staff conducted an aging management audit of Southern Nuclear Operating Company (SNC or the applicant) (1) plant-specific operating experience (OE), (2) methodology to identify the systems, structures, and components (SSCs) to be included within the scope of subsequent license renewal (SLR) and subject to an aging management review (AMR) (Scoping and Screening Portion), and (3) aging management programs (AMPs), AMR items, time-limited aging analyses (TLAA) and associated bases and documentation as applicable (AMP and TLAA Portion) for the SLR of Renewed Facility Operating License Nos. DPR-57 and NPF-5 for Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch, or the applicant).
The purpose of the plant-specific OE portion of the audit is to identify examples of age-related degradation, as documented in the applicants corrective action program (CAP) database, and to provide a basis for the NRC staffs conclusions on the ability of the applicants proposed AMPs to manage the effects of aging in the period of extended operation. SNC searched their OE database and provided the results for the associated AMPs and TLAAs for staff review.
Additional work searches were performed by SNC upon the staffs request, and the results were provided to the staff for review.
The purpose of the Scoping and Screening Portion of the audit is to evaluate the scoping and screening process as documented in the subsequent license renewal application (SLRA),
implementing procedures, reports, and drawings, such as the NRC staff:
Obtains an understanding of the process used to identify the SSCs within the scope of SLR and to identify the structures and components subject to an AMR.
Has sufficient docketed information to allow the staff to reach a conclusion on the adequacy of the scoping and screening methodology as documented and applied.
The purpose of the AMP and TLAA Portion of the audit is to:
Examine SNCs AMPs, AMR items, and TLAAs for Hatch Verify SNCs claims of consistency with the corresponding NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL) Report, (GALL-SLR Report),
Revision 1, issued in July 2025 (ML25113A021 and ML25113A022), AMPs, and AMR items; and Assess the adequacy of the TLAAs.
Enhancements and exceptions will be evaluated on a case-by-case basis. The NRC staffs review of enhancements and exceptions will be documented in the safety evaluation (SE).
11 The regulatory basis for the audit was Title 10 of the Code of Federal Regulations (10 CFR)
Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. The NRC staff also considered the guidance contained in NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants (SRP-SLR),
Revision 1, dated July 2025 (ML25113A023). The SRP-SLR allows an applicant to reference in its SLRA the AMPs described in the GALL-SLR Report. By referencing the GALL-SLR Report AMPs, the applicant concludes that its AMPs correspond to those AMPs reviewed and approved in the GALL-SLR Report and that no further staff review is required. If an applicant credits an AMP for being consistent with a GALL-SLR Report program, it is incumbent on the applicant to ensure that the plant program contains all of the elements of the referenced GALL-SLR Report program. The applicant should document this determination in an auditable form and maintain the documentation on-site.
2.
Audit Activities A regulatory audit is a planned, license-related activity that includes the examination and evaluation of primarily non-docketed information. A regulatory audit is conducted with the intent to gain greater understanding of an application, to verify information, and, if applicable, to identify information that will require docketing to support the NRC staffs conclusions that form the basis of the licensing or regulatory decision.
The SLRA states that every AMP in the SLRA is consistent with the program elements of the GALL-SLR Report. To verify this claim of consistency, the staff audited each AMP, including any enhancements or exceptions associated with an AMP.
The SLRA discusses each time-limited aging analyses, the disposition of the TLAA in accordance with 10 CFR 54.21(c)(1), and the basis for that disposition. To verify that the applicant provided a basis to support its disposition of the TLAA, the NRC staff audited each TLAA.
The NRC staff also audited AMR items not associated with an AMP to determine if the information in the SLRA is consistent with the further evaluation information in the SRP-SLR.
Furthermore, the NRC staff audited the FSAR descriptions for each AMP and TLAA for consistency with the SRP-SLR. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via the e-Portal.
For the OE review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and OE by reviewing documentation contained in the SLRA and e-Portal.
Licensing conclusions or NRC staff findings are not made in the audit reports since licensing and regulatory decisions cannot be made solely based on an audit. Therefore, items identified but not resolved within the scope of the audit will be followed using other NRC processes, such as requests for additional information (RAIs), requests for confirmation of information (RCIs),
and public meetings. Licensing conclusions, staff findings, staff review of enhancement and exceptions, and resolution of audit items will be documented in the staffs SE.
The following sections discuss the SLRA areas reviewed by the staff.
12 SLRA Section 2.1, Scoping and Screening Methodology Summary of Information in the Application. SLRA Section 2.1 describes the process for identifying and determining the HNP systems, structures, and components (SSCs) that are included within the scope of license renewal and subject to an aging management review (AMR). 10 CFR 54.21, Contents of Application - Technical Information, requires that each application for license renewal contain an integrated plant assessment (IPA). The IPA must list, for SSCs within the scope of license renewal, the structures and components (SCs) that are subject to an AMR. 10 CFR 54.4(a), Scope, provides the criteria for inclusion of SSCs within the scope of license renewal. 10 CFR 54.21(a)(1) requires that SCs within the scope of license, that are determined to be passive and not periodically replaced (long-lived), are subject to an AMR.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal. The table below lists the document that was reviewed by the staff and was found relevant to SLRA section 2.1, Scoping and Screening Methodology.
The staff will document its review of this information in the SE.
Relevant Documents Reviewed Document Title Revision /
Date SNCH00384-REPT-001 Hatch Units 1 and 2 Subsequent License Renewal System/Structure Scoping Report Revision 1 SNCH00384-REPT-002 Hatch Units 1 and 2 Subsequent License Renewal Non-Safety SSCs that Act as Anchors for or Spatially Interact with Safety-Related SSCs Report Revision 0 During the audit, the staff verified that the applicants scoping and screening process was performed in accordance with its written requirements was consistent with the guidance provided in the SRP-SLR, and consistent with the guidance in NEI 17-01 (ML17339A599). The staff determined that the scoping and screening methodology was consistent with the requirements of 10 CFR Part 54 for the identification of SSCs that meet the scoping and screening criteria.
SLRA AMP B.2.2.1, Environmental Qualification of Electric Components Summary of Information in the Application.
The SLRA states that AMP B.2.2.1, Environmental Qualification of Electric Equipment, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP X.E1, Environmental Qualification of Electric Equipment. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
13 Document Title Revision /
Date SNCH00384-REPT-040 Project Report Cover Sheet Subsequent License Renewal Aging Management Program Basis Document Environmental Qualification of Electric Equipment Revision 1 NMP-ES-016 Environmental Qualification Program Version 13.1 NA Aging Management Program (AMP) Effectiveness Review NA NA EQ Program Health KPI Summary Scorecard -
2023 2/17/2024 CR 10092978 External OE determination of applicability for Hatch (316556) 12/30/2016 CR 10117146 G&O Enhancement CR to update EQ Central File 09/16/2015 NMP-ES-051-003 Adverse Localized Equipment Environment Walkdown Version 2.5 1BRO05176.000 Plant Hatch ALEE Walkdown Summary - Cable and Connector Inspection Revision 1 CR 10712920 Missed EQPM component replacements 06/12/2020 WO # SNC1229010 Replace Lug on Ground 02/16/2022 CR 10346786 Dent in casing of EQ ASCO solenoid 03/28/2017 CR 10802655 SMNH-89-051 undocumented uncertainty (DBAI) 06/09/2021 CR 11198870 Electric Power Research Institute (EPRI) Report NP-1558 Review 7/31/2025 SMNH 89-051 (Unit 1)
Determine Qualified Lives for EQ Equipment in the Drywell, Steam Chase & Personnel Access Revision 14 SMNH-89-052 (Unit 2)
Determine Qualified Lives for EQ Equipment in Drywell, Steam Chase & Personnel Access Revision 10 SMNH-98-011 Assess the impact of life extension from 40 to 60 years on the equipment qualification radiation exposures.
Version 3 Specification No. SS-2102-238 Environmental Qualification Requirements for Safety-Related Class 1E Electrical Equipment, Components, and Instrumentation Revision 13 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
14 During the audit, the staff made the following observations:
The staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via the e-Portal. The applicant explained how the data for environmental parameters were monitored and how adverse localized environments were identified. The applicant did not have any revised EQ packages (i.e.,
to address the subsequent license renewal period) ready for the staff to review.
The staff requested the applicant to explain how it has addressed concerns with lack of technical references for activation energies for certain materials that were initially provided in Electric Power Research Institute (EPRI) Report NP-1558, A review of Equipment Aging Theory and Technology, Revision 0. NP-1558, Revision 1, resulted in the removal of about 30% of the referenced activation energies due to lack of supporting documentation. The applicant mentioned that they were aware of the issues related to the removal of activation energies in this revision and has created a corrective action report (CR 11198870) to ensure the use of any activation energy values obtained from EPRI NP-1558, Revision 0, remain valid.
The staff also audited the description of the SLRA Environmental Qualification of Electric Equipment provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.2.2, Fatigue Monitoring Summary of Information in the Application. The SLRA states that AMP B.2.2.2, Fatigue Monitoring, is an existing preventive program with enhancements that is consistent with the program elements in GALL-SLR AMP X.M1, Fatigue Monitoring. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date N/A OE Review Results with the Keyword, fatigue July 2025 N/A OE Review Results with the Keyword, crack July 2025 N/A OE Review Results with the Keyword, fracture July 2025 N/A OE Review Results with the Keyword, cycl July 2025 SNCH00384-REPT-004 Hatch Units 1 and 2 Subsequent License Renewal Aging Effects Operating Experience Revision 1 4/17/2025 SNCH00384-REPT-041 Subsequent License Renewal Aging Management Program Basis Document Fatigue Monitoring Revision 1 4/22/2025 N/A Hatch SLR OE Presentation July 1, 2025
15 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, detection of aging effects, parameter monitored or inspected, monitoring and trending, acceptance criteria and corrective actions program elements of the SLRA AMP, are consistent with the corresponding elements of the GALL-SLR Report AMP, or will be consistent after implementation of the identified enhancements.
The staff also audited the description of the SLRA Fatigue Monitoring AMP provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B 2.3.36, Electrical Insulation for Electrical Cables and Connections Not subject to 10 CFR 50.49 Environmental Qualification Requirements Summary of Information in the Application. The SLRA states that AMP B.2.3.36, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements, is an existing program with enhancement that will be consistent with the program elements in GALL-SLR Report AMP XI. E1, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-043 Subsequent License Renewal Aging Management Program Basis Document Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements - Hatch Nuclear Plant Revision 1 NMP-ES-051-003 Adverse Localized Equipment Environment Walkdown Version 2.5 NMP-ES-051 Cable Monitoring Program Version 10.1 Condition Report 774951 Multiple cables with wire insulation damage found inside frame 19B of 1R24S012 MCC Print Date:
03/02/2017 Document Title Revision /
Date CR 10382616 Error Discovered with Previous Unit 2 Cumulative Fatigue Calculations 6/30/2017 Structural Integrity Associates (SIA)
FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023
16 Condition Report 10034760 2N11F004B MOV power cable degrading Print Date:
03/02/2017 Condition Report 10660943 Mechanically torn jacket on cable GRX801G40 Print Date:
11/07/19 Condition Report 10688117 2020 1RF029 Adverse Localized Equipment Environment Walkdown Yellow Observation Print Date:
02/19/20 Condition Report 10778517 Adverse Localized Equipment (ALEE) observation Print Date:
02/27/21 Work Order SNC610942Repair Insulation Damage on Ground Cable Print Date:
07/15/2021 Work Order SNC636671ELET (Deficient Maintenance) 03/12/15 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancement.
The staff also audited the description of the SLRA Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.37, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements used in Instrumentation Circuits Summary of Information in the Application. The SLRA states that AMP B.2.3.37, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits, is an existing program with enhancement that will be consistent with the program elements in GALL-SLR Report AMP XI.E2, Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-044 Subsequent License Renewal Aging Management Program Basis Document Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Requirements Used in Instrumentation Circuits Revision 1
17 57SV-D11-007-1 Refueling Floor Exhaust Vent Radiation Monitor Instrument Version 6.12 57SV-C51-008-0 IRM Calibration Version 6.1 NMP-ES-051 Cable Monitoring Program Version 10.0 FSAR 18.4.8 Insulated Cables and Connections Program Revision 34 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancement.
During the audit, the staff made the following observations:
The staff requested clarification on wording in section 4.4 Detection of Aging Effects where the applicant referred to performing actions prior to the second period of extended operation. The applicant clarified that the use of the word second is intended to be synonymous with subsequent.
The staff requested whether the twelve OE examples resulted in the instrument not being able to perform its intended function prior to corrective actions. The applicant clarified that the plant replaces cables and connections with any indications of degradation, vice assessing the level of degradation. During discussions at the onsite audit activities the applicant presented that four of the twelve events resulted in loss of intended function of the component but were not due to cable aging concerns.
The staff also audited the description of the SLRA Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B 2.3.38, Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Summary of Information in the Application. The SLRA states that AMP B.2.3.38, Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI.E3A, Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
18 Document Title Revision / Date SNCH00384-REPT-045 Subsequent License Renewal Aging Management Program Basis Document Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Revision 1 NMP-ES-051 Cable Monitoring Program Version 10.1 NMP-ES-051-004 Pull Box Inspection Version 7.1 H-12369, Sh. 001 Substation Concrete Cable Trench Layout - Neat line Sheet No. 1 Reinforcing for Typical 40 Ft Section Revision 05 H-24219, Sh. 001 Conduit Plan 4 500KV Switchyard Revision 06 10058443 Tan Delta Required to Assess if Cable Health is Stable or Degrading Printed 3/2/2017 10168909 Yard Pull box Issues PB1-DH, CK, CR and PB-1 Printed 11/8/2016 10690454 Tan Delta Test for 1E21C001B in Further Study Required Range Printed 2/28/2020 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
During the audit, the staff made the following observations:
The staff recognized that the applicant did not take credit for a potential relaxation in pull box (i.e. manhole) inspections allowed by the GALL-SLR following event-driven occurrences where inspection of manholes equipped with water level monitoring and alarms that result in consistent and subsequent pump out of accumulated water prior to the wetting or submergence of cables can be performed at least once every 5 years versus after every event-driven occurrence. In addition to inspecting at least once every 5 years, inspections of manholes equipped with water level monitoring and alarms would be performed following event-driven occurrences if water accumulation is indicated by the monitoring system (e.g., frequent level alarm). The applicant plans to submit a supplement to include taking credit for not inspecting pull boxes following event-driven occurrences and five-year inspection frequencies for pull boxes with water level monitoring and alarms (if installed).
The staff identified a potential exception where the applicant credits a cable routing database in lieu of implementing a cable test matrix that documents inspection methods, test methods, and acceptance criteria for the plant-specific in-scope inaccessible medium-voltage power cables. The applicant provided verbal justification of how this cable routing database meets the requirements listed in the GALL-SLR and plans to modify the wording in a future supplement and update the program basis document to describe how the cable monitoring database meets the GALL-SLR requirements.
19 During its review of the Preventive Actions program element, the staff identified that the implementing procedure, NMP-ES-051-004, Pull Box Inspections, Version 7.1, allows up to two years for pull box inspections, whereas the GALL-SLR and the applicants SLRA indicates pull box inspections will occur at least once annually. The applicant plans to modify the implementing procedure to clearly define Hatch Plants requirement to inspect at least once annually.
The staff also audited the description of the SLRA Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR report.
The staff made the following observations during walkdowns:
During a walkdown of pull box water level monitoring, the staff noted that the licensee staff did not measure the as-left water level after pumping down the pull box. This data is necessary to ensure reliability of the water pump and associated battery. The applicant noted that it will review the pull box inspection procedure (NMP-ES-054-004) to ensure that the as-left water levels are expected to be measured and recorded.
SLRA AMP B 2.3.39, Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Summary of Information in the Application. The SLRA states that AMP B.2.3.39, Electrical Insulation for Inaccessible Instrumentation and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.E3B, Electrical Insulation for Inaccessible Instrumentation and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-046 Subsequent License Renewal Aging Management Program Basis Document Electrical Insulation for Inaccessible Instrumentation and Control Cables Not Subject to 10 CFR 50/49 Environmental Qualification Requirements Revision 1 NMP-ES-051-004 Pull Box Inspection Version 7.1 CR 10448542 Water Found in Flex Conduit for Flow Monitors Printed 1/23/2018 CR 10842801 Carbon Bed Vault ARM Cable Replacement Printed 11/29/2021
20 CR 10738747 Weekly Pull Box Inspection Printed 10/2/2020 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding element of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Electrical Insulation for Inaccessible Instrumentation and Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.40, Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Summary of Information in the Application. The SLRA states that AMP B.2.3.40, Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.E3C, Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-047 Subsequent License Renewal Aging Management Program Basis Document Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Revision 1 SNC27718 License Renewal - 18.2.1.6 Wetted Cable Activities Printed 11/20/2014 05176-RPT-01 Plant Hatch ALEE Walkdown Summary - Cable and Connector Inspection 7/6/2021 10168909 Yard Pull box Issues PH1-DH, CK, CR and PB-1 Printed 11/18/2016 10738747 Weekly Pull Box Inspection Printed 10/2/2020 10740407 Tan Delta Testing Frequency Changes Printed 9/22/2020 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and
21 trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
During the audit, the staff made the following observations:
The staff recognized that the applicant did not take credit for a potential relaxation in pull box (i.e. manhole) inspections allowed by the GALL-SLR following event-driven occurrences where inspection of manholes equipped with water level monitoring and alarms that result in consistent and subsequent pump out of accumulated water prior to the wetting or submergence of cables can be performed at least once every 5 years versus after every event-driven occurrence. In addition to inspecting at least once every 5 years, inspections of manholes equipped with water level monitoring and alarms would be performed following event-driven occurrences if water accumulation is indicated by the monitoring system (e.g., frequent level alarm). The applicant plans to submit a supplement to include taking credit for not inspecting pull boxes following event-driven occurrences and five-year inspection frequencies for pull boxes with water level monitoring and alarms (if installed).
The staff also audited the description of the SLRA Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
The staff made the following observations during walkdowns:
During a walkdown of pull box water level monitoring, the staff noted that the licensee staff did not measure the as-left water level after pumping down the pull box. This data is necessary to ensure reliability of the water pump and associated battery. The applicant noted that it will review the pull box inspection procedure (NMP-ES-054-004) to ensure that the as-left water levels are expected to be measured and recorded.
SLRA AMP B.2.3.41, Fuse Holders Summary of Information in the Application. The SLRA states that AMP B.2.3.41, Fuse Holders, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI. E5, Fuse Holders. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
22 Document Title Revision / Date SNCH00384-REPT-049 Project Report Cover Sheet Subsequent License Renewal Aging Management Program Basis Document Fuse Holders Revision 1 CR 10206216 Fuse Holder in panel 2C71-P003c Print Date:
4/07/16 CR 10207947 Lose Connection on 1X43-A001 Control Power Fuse Print Date:
4/12/16 CR 10295995 Broken fuse holder discovered during 2A FLEX Inverter Tie-in causes Abort of tie-in Print Date:
11/16/16 CR 10818216 CR for documentation purposes only - Fuse Holder Replaced for Print Date:
8/09/21 CR 10296314 Broken fuse holder discovered in 2B Flex Inverter Bypass Switch during 2A FLEX Inverter Bypass Switch Print Date:
11/16/16 WO SNC780109 Fuse holder in panel 2C71-P003C 9/22/20 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Fuse Holders provided in the FSAR supplement. The staff verified this descriptionisconsistent with the description provided in the GALL-SLRReport.
SLRA AMP B.2.3.42, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Summary of Information in the Application. The SLRA states that AMP B.2.3.42, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.
E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the applicants basis documents and referenced documents.
Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-050 Subsequent License Renewal Aging Management Program Basis Document Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements - Hatch Nuclear Plant Revision 1
23 Condition Report 639442 Overheated Isophase Buss Support Grounds Print Date:
06/05/2024 Condition Report 10339512 Main Transformer Phase 2 Print Date:
03/09/2017 Work Order SNC812074 Infrared Survey of Switchyard Components Print Date:
06/05/2024 Work Order SNC570739 Hot Isophase Bus Ground Connection at U2 LVSY 03/12/2015 Condition Report 792932 H11 Control Room Panels (Single Plant)
Print Date:
03/02/2017 Work Order SNC563666 CBM Finding-Tighten/Repair Connections Print Date:
07/11/2014 Work Order SNC509649 Thermography Testing Print Date:
06/26/2014 Condition Report 10484278 C71 Reactor Protection System Print Date:
04/24/2018 Work Order SNC711913 Perform Thermograph Pictures on RPS Power Monitoring Breakers Print Date:
06/05/2024 Work Order SNC939983 Check the proper torque values of this electrical connection for possible looseness 04/23/18 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements provided in the FSAR supplement.
The staff verified this description is consistent with the description provided in the GALL-SLR Report.
The staff made the following observations during walkdowns:
During the onsite audit, the staff interviewed the applicants staff and performed walkdowns of the facility. The staff also discussed operating experience related to electrical cable connections that are in the scope of subsequent license renewal. The staff did not observe any significant aging management issues during its review of operating experience or during walkdowns of electrical cable connections in the scope of subsequent license renewal.
SLRA AMP B.2.3.43, High Voltage Insulators Summary of Information in the Application. The SLRA states that AMP B.2.3.43, High-Voltage Insulators, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI. E7, High-Voltage Insulators. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document, available procedures, and referenced documents.
24 Audit Activities. An on-site audit was performed July 29 to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-037 Subsequent License Renewal Screening and Aging Management Review Results Electrical Commodities Revision 0 SNCH00384-REPT-001 Hatch Units 1 and 2 Subsequent License Renewal System/Structure Scoping Report Revision 1 SNCH00384-REPT-051 Subsequent License Renewal Aging Management Program Basis Document High-Voltage Insulators Revision 1 Condition Report 585740 Hot Spot Indications on Thalmann Line HNPS Print date:
04/30/2025 OE Category:
VOLTAGE.pdf (search summary)
Condition Report 673471 Summary 7/18/2013 OE Category:
VOLTAGE.pdf (search summary)
Condition Report 10008483 Summary - Procedure Change Needed for NMP-GM-025 1/7/2015 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA High-Voltage Insulators provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
The staff made the following observations during walkdowns:
During the onsite audit, the staff performed a walkdown of the station blackout offsite power recovery path from the switchyard to the plant startup transformers. The staff did not observe any adverse or abnormal signs of age-related degradation with in-scope high-voltage electrical insulators.
SLRA AMP B. 2.3.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Summary of Information in the Application. The SLRA states that AMP B.2.3.1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M1, ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD. To verify this claim of consistency, the staff audited the SLRA AMP.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
25 RELEVANT DOCUMENTS REVIEWED Document Title Revision /
Date SNCH00384-REPT-052 Hatch Nuclear Plant Subsequent License Renewal Aging Management Program Basis Document - ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Revision 1 04/17/2025 SNCH00384-REPT-004 Hatch Units 1 and 2 Subsequent license Renewal Aging Effects Operating Experience Revision 1 04/17/2025 CR: 10038060 2B21-1FW-12AA-8 Weld Overlay PT 03/19/2015 CR:10058892 1B31 Safe End to Nozzle Welds 04/21/2015 CR: 10303145 Potential Deviation from NEI 03-08 Needed Guidance Due to Low HNP-1 Shroud Support Weld Exam Coverage 11/29/2016 TE: 1061497 1R29 - Hatch 1 RPV Closure Head Weld UT Indications 02/12/2020 CR: 11029633 Hatch-2 BWRVIP-75A Category D Welds 12/06/2023 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD program provided in the FSAR supplement. The staff verified that this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.2, Water Chemistry Summary of Information in the Application. The SLRA states that AMP B.2.3.2, Water Chemistry, is an existing program with one exception that is consistent with the program elements in GALL-SLR Report AMP XI.M2, Water Chemistry.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH-00384-REPT-053 Subsequent License Renewal Aging Management Program Basis Document Water Chemistry Revision 1 CR-901691 External OE Determination of Applicability for Hatch (313638) 12/03/14 TE-1070719 U1 Suppression Pool Parameters Outside of EPRI Limits 7/20/2020 CR-813325 Water Chemistry Guidelines Rev 1 Evaluation 05/15/14
26 CR-10652796 U2 Feedwater DO Has Exceeded EPRI A.L. 1 10/05/2019 TE-1053488 U2 Feedwater DO Has Exceeded EPRI A.L. 1 10/7/2019 CR-10721390 U1 Suppression Pool Parameters Outside of EPRI Limits 07/10/20 TE-1156918 Chemistry to Review and Implement Updated EPRI BWRVIP-190 Rev 2 Guidance 6/23/2024 CR-11087036 Chemistry to Review and Implement Updated EPRI BWRVIP-190 Rev 2 Guidance 06/21/24 EPRI Report 3002025550 BWRVIP-190: BWR Vessel and Internals Project:
BWR Water Chemistry Guidelines. Proprietary Information.
Revision 2 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also verified the applicants claim that aspects of the parameters monitored or inspected, monitoring and trending, and acceptance criteria, program elements not associated with the exception identified in the SLRA are consistent with the corresponding program elements inthe GALL-SLR Report AMP.
In addition, the staff found that for the detection of aging effects, program element, sufficient information was not available to determine whether it was consistent with the corresponding program elements of the GALL-SLR Report AMP. The staff will consider issuing an RAI in order to obtain the information necessary to verify whether this element is consistent with the corresponding program element of the GALL-SLR Report AMP.
The staff also audited the description of the Water Chemistry program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.3, Reactor Head Closure Stud Bolting Summary of Information in the Application. The SLRA states that AMP B.2.3.3, Reactor Head Closure Stud Bolting Program, is a new program with an exception that will be consistent with the program elements in GALL-SLR Report AMP XI.M3, Reactor Head Closure Stud Bolting.
Audit Activities. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SER.
27 Document Title Revision /
Date SNCH00384-REPT-054 Subsequent License Renewal Aging Management Program Basis Document Reactor Head Closure Stud Bolting Revision 1 ISI-1R31-2024 Inservice Inspection Final Report for Edwin I. Hatch Nuclear Plant Unit 1 Refueling Outage 1R31 07/2024 ISI-2R28 Inservice Inspection Final Report for Edwin I. Hatch Nuclear Plant Unit 2 Refueling Outage 2R28 06/2025 Hatch Unit 1 and 2 Final Safety Analysis Report Revisions 38 and 39 SNC2316898 Hatch Unit 2 RPV Closure Hardware (Stud #33)
Modification Revision 1 ML19035A550 Relief Request HNP-ISI-RR-05-02 Regarding ISI of Reactor Pressure Vessel Head Stud No. 33 Safety Evaluation 02/2019 ML23032A332 Amendment No. 332 to Renewed Facility Operating License No. DPR-57 and Amendment No. 267 to Renewed Facility Operating License No. NPF-5 Safety Evaluation 04/2024 During the audit, the staff verified the applicants claim that the scope of program, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP. The staff also verified the applicants claim that aspects of the preventative actions program element not associated with the exception identified in the SLRA is consistent with the corresponding program element in the GALL-SLR Report AMP.
During the audit, the staff made the followingobservations:
Some studs have ultimate tensile strength greater than 170 ksi, which is above the recommended value in NUREG-2191, as a preventive measure to reduce the potential for stress corrosion cracking (SCC).
Reactor head closure studs at Hatch Nuclear Plant (HNP) are not metal plated and the material for the closure studs and nuts is SA540.
Use of molybdenum disulfide (MoS2) as a lubricant for reactor vessel closure studs is not used as it is susceptible to SCC.
A dry film (DAG-156) lubricant or equivalent is applied to the threads of the reactor head closure studs at HNP.
A relevant indication on HNP Unit 2 stud #33 was discovered during the 2017 spring refueling outage.
The staff also audited the description of the Reactor Head Closure Stud Bolting Program provided in the FSAR supplement. The staff verified this descriptionisconsistent with the description provided in the SRP-SLR Report.
28 SLRA AMP B.2.3.4, BWR Vessel ID Attachment Welds Summary of Information in the Application. The SLRA states that AMP B.2.3.4, BWR Vessel ID Attachment Welds, is an existing program with an exception that is consistent with the program elements in GALL-SLR Report AMP XI.M4, BWR Vessel ID Attachment Welds.
Audit Activities. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-055 Subsequent License Renewal - Aging Management Program Basis Document - BWR Vessel ID Attachment Welds Revision 1 During the audit, the staff verified the applicants claim that the preventive actions program element of the SLRA AMP is consistent with the corresponding element of the GALL-SLR Report AMP. The staff also verified the applicants claim that aspects of the scope of program, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements not associated with the exception identified in the SLRA are consistent with the corresponding program elements inthe GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP B.2.3.4, BWR Vessel ID Attachment Welds provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.5, BWR Stress Corrosion Cracking Summary of Information in the Application. The SLRA states that AMP B.2.3.5, BWR Stress Corrosion Cracking is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M7, BWR Stress Corrosion Cracking. To verify this claim of consistency, the staff audited the SLRA AMP.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
RELEVANT DOCUMENTS REVIEWED Document Title Revision /
Date SNCH00384-REPT-056 Hatch Nuclear Plant Subsequent License Renewal Aging Management Program Basis Document -
BWR Stress Corrosion Cracking Revision 1 4/21/2025 SNCH00384-REPT-004 Hatch Units 1 and 2 Subsequent license Renewal Aging Effects Operating Experience Revision 1 04/17/2025
29 Document Title Revision /
Date TE: 951095 Unit 1 Startup Issue - Document Results of Extent of Condition for Weld Overlay at 1B31-1RC-12BR-E-5 02/23/2016 During the audit, the staff verified applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA BWR Stress Corrosion program are consistent with the corresponding program elements in the GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP provided in the FSAR Supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.6, BWR Penetrations Summary of Information in the Application. The SLRA states that AMP B.2.3.6, BWR Penetrations, is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M8, BWR Penetrations.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Relevant Documents Reviewed Document Title Revision / Date SNCH00384-REPT-057 AMP Basis Document BWR Penetrations Revision 1 04/22/2025 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA BWR Penetrations provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.7, BWR Vessel Internals Summary of Information in the Application. The SLRA states that AMP B.2.3.7, BWR Vessel Internals, is an existing program with three enhancements that is consistent with the program elements in GALL-SLR Report AMP XI.M9, BWR Vessel Internals.
Audit Activities. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
30 The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-058 Subsequent License Renewal - Aging Management Program Basis Document - BWR Vessel Internals Revision 2 Technical Evaluation 1136226 Review BWRVIP-100 Revision 2 for Applicability September 2023 Technical Evaluation 1148778 Review NMP-ES-010-GL17 for BWRVIP-100 Revision 2 February 2024 EPRI Letter: 2021-028 Status Update on Potential Non-Conservatism in EPRI Report BWRVIP-100, Rev 1-A, 3002008388 and EPRI Software, BWRVIP-235, 1018251 March 19, 2021 EPRI Letter: 2021-028, Reference 2 Update regarding 10 CFR Part 21 Transfer of Information Notice - Potential Non-Conservatism in EPRI Software (BWRVIP-235) and Inspection and Evaluation Guidance for BWR Core Shroud (BWRVIP-76 Revision 1-A, BWRVIP-76 Revision 2, and BWRVIP Letter 2016-30)
March 19, 2021 EPRI Letter: 2023-050 Recently Published BWRVIP Report - BWRVIP-100 Revision 2 July 12, 2023 EPRI Letter: 2023-073 Clarification Regarding BWRVIP-100, Revision 2 Implementation October 13, 2023 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP is consistent with the corresponding element of the GALL-SLR Report AMP.
During the audit, the staff made the followingobservations:
The staff noted that the applicants enhancements and implementation actions associated with BWRVIP-315-A, Reactor Internals Aging Management Evaluation for Extended Operations (ML24191A417) including the associated limitations and conditions, lack clarity, and durability when implemented for the subsequent period of extended operation. The staff will consider issuing RAI to obtain clarity on associated with BWRVIP-315-A, including the associated limitations and conditions as part of the applicants BWR Vessel Internals AMP.
The staff confirmed the applicants procedure (i.e., NMP-ES-010-GL17) implements BWRVIP-180, BWR Vessel and Internals Project-Access Hole Cover Inspection and Flaw Evaluation Guidelines, Revision 0 and BWRVIP-38, BWR Shroud Support Inspection and Flaw Evaluation Guidelines, Revision 0, consistent with GALL-SLR AMP XI.M9. Furthermore, the staff confirmed the revisions cited in the applicants internal program basis document for the AMP (i.e., SNCH00384-REPT-058) are incorrect and will be revised.
BWRVIP-100 Revision 1-A was subject to a 10 CFR Part 21 notice (ML21084A165) due to non-conservatism on fracture toughness of reactor vessel shell material. During its audit, the staff confirmed (Technical Evaluation 1136226 and Technical Evaluation 1148778) that the applicant performed an assessment to address the 10 CFR Part 21 notice, which determined that Hatch Nuclear Plant (HNP), Units 1 and 2, is not currently
31 impacted and corrective actions are being taken to address this issue in future flaw evaluations.
The staff also audited the description of the SLRA AMP B.2.3.7, BWR Vessel Internals provided in the FSAR supplement. The staff found that sufficient information was not available to determine whether the description provided in the FSAR supplement was an adequate description of the SLRA "BWR Vessel Internals" AMP. The SLRA states in Appendix A that the applicant utilizes an NRC Approved Request for Alternative Implementation of the BWRVIP Program for Vessel Internals in lieu of the requirements of ASME Code,Section XI. The staff noted that such an alternative may not be granted as part of the SLR and must be granted in accordance with the regulatory process in 10 CFR 50.55a. The staff will consider issuing RAls to obtain the information necessary to verify the sufficiency of the FSAR supplement program description.
SLRA AMP B.2.3.8, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Summary of Information in the Application. The SLRA states that AMP B.2.3.8, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS), is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Relevant Documents Reviewed Document Title Revision / Date SNCH00384-REPT-059 AMP Basis Document Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Revision 1 04/21/2025 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP 2.3.9, Flow-Accelerated Corrosion Summary of Information in the Application. The SLRA states that AMP B.2.3.9, Flow-Accelerated Corrosion, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI.M17, Flow-Accelerated Corrosion. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
32 Document Title Revision /
Date SNCH00384-REPT-060_Rev1 Aging Management Program Basis Document Flow-Accelerated Corrosion Rev 1 1R28-SNC789247-04 Hatch 1R28 FAC Program Activities 3/26/2018 1R29-SNC982958-02 Hatch 1R29 (Spring 2020) FAC Program Activities 4/13/2020 1R30-SNC1156348-03 Hatch 1R30 (Spring 2022) FAC Program Activities 8/29/2024 1R31-SNC1472267-03 Hatch 1R31 (Spring 2024) FAC Program Activities 1/07/2025 2R25-SNC854176-03 Hatch 2R25 (Spring 2019) FAC Program Activities 6/11/2019 2R26-SNC1095523-05 Hatch 2R26 (Spring 2021) FAC Program Activities 3/18/2024 2R27-SNC1316334-03 Hatch 2R27 (2023) FAC Program Activities 1/24/2025 2R28-SNC1781839-02 Hatch 2R28 (Spring 2025) FAC Program Activities 2025 NMP-ES-011-001 Flow-Accelerated Corrosion (FAC) Program Implementation Rev 14 TE 621558 Technical Evaluation from Hatch 2R22 OE from SJAE (Steam Jet Air Injectors) Steam Inlet Supply Piping 6/08/2013 EPRI 3002005530 Recommendations for an Effective Program Against Erosive Attack July 2015 EPRI 3002023786 Recommendations for an Effective Program Against Erosive Attack April 2023 CR 769911 FAC NDE Examinations 2/14/2014 CR 10331076 Condenser Connection #58 Fails FAC Inspection 2/16/2017 CR 10355404 12th Stage A FWH Vent Restricting Orifice Inspection Request 4/21/2017 CR 10355407 12th Stage B FWH Vent Restricting Orifice Inspection 4/21/2017 CR 10493938 1P41F202 Valve Replacement 5/22/2018 CR 10559058 LMP 3 (STEAM)-10th Stage Heater Leak 12/02/2018 CR 11048275 FAC point (1-CF-123) needs Repair or Replacement 2/08/2024 TE 913877 FAC Component 2-OG-2 Passes Eng Evaluation 4/15/2015 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP
33 will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
The staff also audited the description of the SLRA Flow-Accelerated Corrosion program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.10, Bolting Integrity Summary of Information in the Application. The SLRA states that AMP B2.1.9, Bolting Integrity, is an existing program with enhancements that are consistent with the program elements in GALL-SLR Report AMP XI.M18, Bolting Integrity. -
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search of its operating experience database.
An on-site audit was performed July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SCH00384-REPT-061 AMP Basis Document: Bolting Integrity Revision 1 CR 10028377 RPV Support Skirt Bolting Corrosion 02/18/2015 CR 10584407 Failed VT-1 exam on 2B21F077A 02/21/2019 CR 10838423 Temporary Diesel Fire Pump Flange Bolting not Flush with Nuts 11/01/2021 CR 10858391 Failed VT-1 Examination of SRV Bolting 02/12/2022 WO SNC870100
- TECH SPECS REQUIREMENT** MAIN STEAM THREE STAGE SAFETY RELIEF VALVE 05/25/2017 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
The staff also audited the description of the SLRA Bolting Integrity AMP provided in the UFSAR supplement. The staff verified this description is consistent with the description provided in the GALLSLR Report.
SLRA AMP B.2.3.11, Open-Cycle Cooling Water System Summary of Information in the Application. The SLRA states that AMP B.2.3.11, Open Cycle Cooling Water, is an existing program that, with enhancements, will be consistent with the program elements in GALL-SLR Report AMP XI.M20, Open Cycle Cooling Water System. At the time of the audit, the applicant had not yet fully developed the documents necessary to
34 implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-062 AMP Basis Document - Open Cycle Cooling Water System Rev. 1 64CH-OPS-006-0 Plant Service Water and Circulating Water Treatment Systems Version 78.0 HNP-ES-012-001 Inspection of Heat Exchangers Version 3.1 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding element of the GALL-SLR Report AMP, after implementation of the identified enhancements.
The staff also audited the description of the Open Cycle Cooling Water AMP provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.12, Closed Treated Water System Summary of Information in the Application. The SLRA states that AMP B.2.3.12, Closed Treated Water Systems, is an existing program that, with enhancements, will be consistent with the program elements in GALL-SLR Report AMP XI.M21A, Closed Treated Water Systems. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-063 Subsequent License Renewal Aging Management Program Basis Document - Closed Treated Water Systems Rev. 1 NMP-GM-003-F18 Hatch Unit 1 and 2 License Renewal IP-71003 Phase IV Preparation Assessment Version 4.0 CAR-257334 U2 PCCW and RBCCW outside EPRI limits 05/07/2015 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP
35 will be consistent with the corresponding elements of the GALL-SLR Report AMP, after implementation of the identified enhancements.
The staff also audited the description of the Closed Treated Water Systems AMP provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.13, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Summary of Information in the Application. The SLRA states that AMP B.2.3.13, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems, is an existing program with enhancements that will be consistent, with the program elements in the GALL-SLR Report AMP XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal. An on-site audit was performed from July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-064 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems, Basis Document Revision 1 52SV-MLH-001-0 Overhead Crane Inspection Revision 0 52IT-MLH-008-0 Overhead Hoist Inspection Revision 0 51GM-MLH-004-0 Rigging and Lifting Program Plant Hatch Specifics Revision 0 NMP-ES-021 Structural Monitoring Program for the Maintenance Rule Revision 0 CR-618294 U-1 Turbine building, west ridge rail has loose bolting 04/15/2013 SNC482550 Work Order for Turbine building torque/replace bolts if required 07/02/2013 CR-10122206 U-2 refueling platform south-west seismic restraint is rubbing rail 09/10/2015 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP
36 will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
The staff also audited the description of the SLRA Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems provided in the FSAR supplement Section A.2.2.13. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.14, Compressed Air Monitoring Summary of Information in the Application. The SLRA states that AMP B.2.3.14, Compressed Air Monitoring, is an existing program that will be consistent with the program elements in GALL-SLR Report AMP XI.M24, Compressed Air Monitoring. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal. For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and OE by reviewing documentation contained in the SLRA and e-Portal. The staff will evaluate any identified plant-specific OE in the SE.
The table below lists the documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-065 Aging Management Program Basis Document Compressed Air Monitoring Evaluation Report GALL-SLR Program XI.M.24 Revision 1 C.R. 10073277 High Dew Point Alarm 05/21/2015 C.R. 10326245 Dryer Dew Point Tempt High 02/03/2017 C.R. 10380919 The dryer Dew Point Temperature is Reading High for the 1P51C010B 06/26/2017 C.R. 10249550 Dryer Dew Point Output Temperature Reading LL (Low Level) 07/17/2016 C.R. 10710570 IA Dryer Dewpoint Output Temperature Out of Specification High at -40.0 05/21/2020 C.R. 10509632 Unit One Instrument Air Dew Point Out of Specifications 06/27/2018 W.O. SNC881701 1P51N326C-Service Air Dryer C Output Moisture Analyzer Revision 0 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLRReport AMP.
37 The staff also audited the description of the SLRA AMP Compressed Air Monitoring program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.15, Fire Protection Summary of Information in the Application. The SLRA states that AMP B.2.3.15, Fire Protection, is an existing program that is consistent with the program elements in GALLSLR Report AMP XI.M26, Fire Protection. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document and in the SLRA.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-067 Fire Protection - Aging Management Program Basis Document Revision 1 NMP-ES-035-016-002 Hatch Fire Barrier and Penetration Seal Inspection Version 3.0 NMP-ES-035-017 Fleet Fire Doors Functional Inspection Governance and Acceptance Criteria Version 2.0 NMP-ES-035-017-002 Hatch Fire Door Inspection Procedure Version 2.0 NMP-ES-035-016 Fleet Fire Barrier and Penetration Seal Program Version 3.1 NMP-ES-035 Fire Protection Program Version 7.0 CR10470178 Degraded Cat 1 Fire Barrier March 8, 2018 CR850819 Fire Rated Wall Issue August 7, 2014 N/A Hatch SLR OE N/A SNCH00384-REPT-004 Aging Effect OE for Mechanical Systems and Components Revision 1 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Fire Protection program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
38 SLRA AMP B.2.3.16, Fire Water System Summary of Information in the Application. The SLRA states that AMP B.2.3.16, Fire Water System, is an existing program with enhancements that will be consistent, with an exception, with the program elements in GALL-SLR Report AMP XI.M27, Fire Water System. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document and in the SLRA.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title/Description Revision / Date SNCH00384-REPT-068 Fire Water System Aging Management Program Basis Document Revision 1 NMP-ES-035 Fire Protection Program Version 7.0 52SV-FPX-016-1 Sprinkler System Surveillance-Safety Related Areas Version 4.11 52SV-FPX-016-2 Sprinkler System Surveillance-Safety Related Areas Version 3.4 42SV-FPX-022-0 Fire Hydrant and Hydrant Hose Houses Version 2.10 42SV-FPX-008-0 Fire Protection Water Suppression System Flow Test Version 5.1 42SV-FPX-042-0 Inspection of Fire Tanks Version 2.9 42SV-FPX-015-0 System Flush - Fire Protection Water Version 2.1 52SV-FPX-017-1 Surveillance of Water Fire Suppression Systems Version 1.2 52SV-X43-002-1 Diesel-driven Fire Pump Inspection Version 14.10 34SV-X43-001-1 Fire Pump Test Version 5.3 52PM-X43-006-1 Electric Fire Pump Cleaning & Inspection Version 4.8 52SV-FPX-005-0 Surveillance of Low Voltage Switchyard Fixed Water Spray Systems Version 1.2 52SV-FPX-045-0 Deluge System Strainer Inspection and Cleaning Version 1.0 52SV-FPX-047-0 Sprinkler Head Inspection Version 1.2 CR10434019 Main Fire Header Leak November 27, 2017 CR10434022 Underground Leak in Vicinity of Hydrant November 28, 2017 CR10474337 Cognitive Trend CR on Underground Fire Water Leaks March 21, 2018
39 Document Title/Description Revision / Date CR10610511 Excessive Corrosion of Overfill Line Internal to Fire Water Storage Tanks May 14, 2019 CR10707104 Fire Water Tank Inspection Results May 5, 2020 CR10709001 Fire Protection Water Tank Piping Conditions May 14, 2020 CR10923890 Sediment Buildup in Sprinkler System November 15, 2022 NMP-MA-011-001 Program for Qualification and Certification of Paintings/Coatings Application Personnel Version 4.0 NMP-MA-011-006 Procedure for Coating Condition Assessments Version 9.1 SNC1404839 Remove Sediment Found in Sprinkler Piping November 16, 2022 SNC909925 Underground Leak in Vicinity of Hydrant November 28, 2017 NMP-ES-050-F01 (SNC1043705)
Frequency Extension (1 refueling cycle to 2 refueling cycles)
Version 4.0 NMP-ES-050-F01 (SNC1054816)
Frequency Extension (to 36 months)
Version 4.0 52SV-X43-003-1 Diesel-Driven Fire Pump Major Overhaul/Inspection Version 8.1 N/A Pump Engine Photos N/A CR10831536 Failure of B Fire Diesel October 1, 2021 S-78095 Installation, Operation, and Maintenance Manual, Fire Pump Driven Engine Version 3.0 CR10147267 Fluid Under Fire Pump on Floor November 15, 2015 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
The staff also audited the description of the SLRA Fire Protection program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.17, Outdoor and Large Atmospheric Metallic Storage Tanks Summary of Information in the Application. The SLRA states that AMP B.2.3.17, Outdoor and Large Atmospheric Metallic Storage Tanks Program, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI.M29, Outdoor and Large Atmospheric Metallic Storage Tanks Program. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and
40 the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal. For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and OE by reviewing documentation contained in the SLRA and e-Portal. The staff will evaluate any identified plant-specific OE in the SE.
The table below lists the documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-069 Aging Management Program Basis Document Outdoor and Large Atmospheric Metallic Storage Tanks Revision 1 421T-P11-001-0 Visual Examination Procedure for Condensate Storage Tanks Version 2.4 C.R. 10035830 High Silica in Unit 2 CST 03/04/2015 C.R. 10251017 Unit 2 CST LRI Coatings Inspection Findings 07/20/2016 C.R. 10435308 Unit 2 CST LRI Exterior Inspection 12/01/2017 C.R. 10800267 Leak Near Unit 2 CST 05/24/2021 W.O. SNC366236 Clean and Inspect the Inside of the U-1 CST Revision 0 W.O. SNC804614 Clean and re-inspect J bolts: U2 CST LRI Coatings Inspection (should be completed in 2016) 12/18/2016 W.O. SNC910721 Buff/Clean and Perform QC examination of U2 CST shell Behind the ELET (Deficient Maintenance)
Revision 0 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, and parameters monitored and inspected, program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLRReport AMP.
During the audit, the staff verified the applicants claim that the detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent after implementation of the identified enhancements with the corresponding elements of the GALL-SLR Report AMP.
41 The staff also audited the description of the SLRA Outdoor and Large Atmospheric Metallic Storage Tanks program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.18, Fuel Oil Chemistry Summary of Information in the Application. The SLRA states that AMP B.2.3.18, Fuel Oil Chemistry, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI.M30, Fuel Oil Chemistry. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
To verify this claim of consistency, the staff audited the SLRA AMP. During the audit, the staff also reviewed the enhancements associated with this AMP. The staff will document its review of the enhancements in the SE.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal. For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-070 Subsequent License Renewal Aging Management Program Basis Document Fuel Oil Chemistry Revision 1 C.R. 646355 Evaluate the Use 5% Biodiesel in our EDGs 05/28/2013 C.R. 10373331
- 2 Fuel Oil Delivery Rejected due to Water Contamination 06/05/2017 C.R. 10407845 Fire Pumps Diesel Storage Tank A and B Sediment Above Allowable Levels 09/12/2017 C.R. 10572553 1C D/G Fuel Oil Day Tank Microbe Results 01/18/2019 C.R. 10622839 Check in Self-Assessment on Review of NISP-301 06/24/2019 C.R. 10656293 Engineering Evaluation Required for 1B EDG FOST Microbes Exceeding Spec. Limit 10/17/2019 C.R.10728101 Quarter 2020 NRC Integrated Inspection Report Non-Cited Violation (NCV) 08/05/2020 C.R. 10778029 There is a Fuel Oil Leak on Fire Pump Fuel Tank 1X43-A002B 02/24/2021
42 During the audit, the staff verified the applicants claim that the scope of program and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLRReport AMP.
During the audit, the staff verified Hatch claims that the preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, and acceptance criteria, program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
The staff also audited the description of the SLRA AMP Fuel Oil Chemistry provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.19, Reactor Vessel Material Surveillance Summary of Information in the Application. The SLRA states that AMP B.2.3.19, Reactor Vessel Material Surveillance Program, is an existing program with an enhancement that will be consistent with the program elements in GALL-SLR Report AMP XI.M31, Reactor Vessel Material Surveillance.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search of its operating experience database using the keywords: (surveillance material, capsule, pressure and temperature limit report, ISP, and reactor vessel material surveillance).
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Document Title Revision /
Date BWRVIP-321 BWR Vessel and Internals Project: Plan for Extension of the BWR Integrated Surveillance Program (ISP)
Through the Second License Renewal (SLR)
Revision 1-A SNCH00384-REPT-071 Subsequent License Renewal Aging Management Program Basis Document Reactor Vessel Material Surveillance Revision 0 SNCH00384-REPT-004 Subsequent License Renewal Aging Effects Operating Experience Revision 1 Hatch Unit 2 Final Safety Analysis Report - Section 5 Revision 39 992529 Technical Evaluations Quality Record - External OE determination of applicability for Hatch 8/24/2024 275179 Corrective Action - Hatch 2 RPV Surveillance Capsule Holders at 30 & 300 5/4/2019
43 1020529 Technical Evaluations Quality Record - Receipt of NEI 03-08 needed guidance - BWRVIP letter 2018-045, RPV Surv. Capsule inspection 12/20/2018 ML030690457 Hatch, Units 1 and 2, License Amendments 237 &
179 3/10/2003 During the audit, the staff verified the applicants claim that the preventive actions, acceptance criteria, and corrective actions program elements of the SLRA AMP is consistent with the corresponding elements of the GALL-SLR Report AMP. The staff also verified the applicants claim that aspects of the scope of program, parameters monitored or inspected, detection of aging effects, and monitoring and trending program elements will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancement.
SLRA AMP B.2.3.20, One-Time Inspection Summary of Information in the Application. The SLRA states that AMP B.2.3.20, One-Time Inspection, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.M32, "One-Time Inspection. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-072 Subsequent License Renewal Aging Management Program Basis Document One-Time Inspection Revision 1 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA One-Time Inspection provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.21, Selective Leaching Summary of Information in the Application. The SLRA states that AMP B.2.3.21, Selective Leaching, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.M33, Selective Leaching. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff reviewed the applicants search results of its operating experience database using the keyword graphiti (to search for instances of graphitic corrosion or graphitization).
44 The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-073 Subsequent License Renewal Aging Management Program Basis Document Selective Leaching Revision 1 CR 10931889 Hatch License Renewal NRC Phase IV CISA (RHRSW & PSW) 12/15/2022 CR 10925361 Large Fire Water Leak 11/19/2022 CAR 332462 Fire Water Main Rupture 11/19/2022 SNCH00384-REPT-004 Hatch Units 1 and 2 Subsequent Licensee Renewal Aging Effects Operating Experience Revision 1 H-24-0027 Hatch Fire Main Piping Asset Management Plan 04/25/2024 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP. In addition, the staff found that for the operating experience program element, sufficient information was not available for the staff to conclude that the applicants proposed program can adequately manage the effects of aging in the subsequent period of extended operation. The staff will consider issuing an RAI in relation the operating experience program element.
The staff also audited the description of the SLRA Selective Leaching program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.22, ASME Code Class 1 Small-Bore Piping Summary of Information in the Application. The SLRA states that AMP B.2.3.22, ASME Code Class 1 Small-Bore Piping is a new condition monitoring program that will be consistent with the program elements in GALL-SLR Report AMP XI.M35, ASME Code Class 1 Small-Bore Piping. To verify this claim of consistency, the staff audited the SLRA AMP.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
RELEVANT DOCUMENTS REVIEWED Document Title Revision / Date SNCH00384-REPT-074 Hatch Nuclear Plant Subsequent License Renewal Aging Management Program Basis Document - ASME Code Class 1 Small-Bore Piping Revision 1 04/21/2025 SNCH00384-REPT-004 Hatch Units 1 and 2 Subsequent license Renewal Aging Effects Operating Experience Revision 1 04/17/2025 CAR: 173909 1 Inch Line Between Main Steam Line A and 1B21-D006B Has a Pin Hole Leak at the Toe of the Weld 05/30/2008
45 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA ASME Code Class 1 Small-Bore Piping program are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP provided in the FSAR supplement. The staff verified that this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.23, External Surfaces Monitoring of Mechanical Components Summary of Information in the Application. The SLRA states that AMP B2.3.23, External Surfaces Monitoring of Mechanical Components, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.M32, External Surfaces Monitoring of Mechanical Components. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-075 Subsequent License Renewal Aging Management Program Basis Document - External Surfaces Monitoring of Mechanical Components Revision 1 CR-10772667 Paint Peeling off Ventilation Duct 02/08/2021 CR-10621430 2A Turbine Building Chiller - Economizer Vessel Degradation 06/19/2019 CR-10428865 Material Condition Walkdown - West Cableway -
Oxidation/Corrosion/Rust 11/09/2017 CR-10027398 2E41-XJ59 Expansion Joint 02/17/2015 CR-610760 Pipe Support Loose 03/21/2013 CR-838327 Blistered Paint on Unit 1 Main Condenser (1N61) 07/10/2014 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP External Surfaces Monitoring of Mechanical Components provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
46 SLRA AMP B.2.3.24, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Summary of Information in the Application. The SLRA states that AMP B.2.3.24, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-076 Subsequent License Renewal Aging Management Program Basis Document Revision 1 CR-10750916 Unit 2 RHRSW Piping Below Min Wall 11/02/2020 CR-10776387 As Found Condition of 2E11F068B 02/19/2021 CR-10918366 Internal Condition of Piping 10/26/2022 CR-10921846 Internal Surface Conditions of 1R43A007B 11/08/2022 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.25, Lubricating Oil Analysis Summary of Information in the Application. The SLRA states that AMP B.2.3.25, Lubricating Oil Analysis, is an existing program that is consistent with the program elements in GALL-SLR Report AMP XI.M39, Lubricating Oil Analysis. To verify this claim of consistency, the staff audited the SLRA AMP.
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal. For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
47 The table below lists the documents that were reviewed by the staff and were found relevant to the Lubricating Oil Analysis. The staff will document its review of relevant operating experience in the SE.
Document Title Revision / Date SNCH00384-REPT-077 Subsequent License Renewal Aging Management Program Basis Document Lubricating Oil Analysis Revision 1 C.R. 878673 CBM Finding 10/10/2014 Technical Evaluation 997808 ICES Report 425952 Deficient Oil Conditions in Condensate Pump Motor 11/08/2017 C.R. 10422942 CBM Finding 10/24/2017 C.R. 10901776 2B Circ. Water Pump-WPC Uptick on the Motor Upper Oil Reservoir 08/17/2022 SNC1323499 Replace U2 Bravo Circ. Water Pump Motor Oil Carbon Pipe Replacement 10/11/2022 C.R. 10887191 IP41-C001B Top Motor Oil has Unusual (Creamy)
Color 06/11/2022 CAR 213000 This CAR Contains the IDO for CR 878673 10/10/2014 During the audit, the staff verified applicants claim that the scope of program, preventive actions, parameters monitored or inspected, monitoring and trending, detection of aging effects, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA AMP Lubricating Oil Analysis program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.26, Monitoring of Neutron-Absorbing Materials Other Than Boraflex Summary of Information in the Application. The SLRA states that AMP B.2.3.26, Monitoring of Neutron-Absorbing Materials Other Than Boraflex, is an existing program with one enhancement that will be consistent with the program elements in GALL-SLR Report AMP XI.M40, Monitoring of Neutron-Absorbing Materials Other Than Boraflex.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-078 Subsequent License Renewal Aging Management Program Basis Document Monitoring of Neutron-Absorbing Materials Other Than Boraflex Revision 2 CR-10139338 Changes Needed to Procedure 42FH-SUV-001-0 and Form ENG-0594 10/26/15 CR-813408 Monitoring of SFP chemistry to prevent Boral degradation 05/15/14
48 NET-300080-01 Inspection and Testing of Boral Surveillance Coupons from Hatch Generating Station Revision 0 NET-28203-000-01 Inspection and Testing of Boral Surveillance Coupon 18-C from Hatch Nuclear Plant Revision 0 SNC463029 HDFSS Surveillance Samples Removal and Installation 2/6/2013 TE 814994 Monitoring of SFP Chemistry to Prevent Boral Degradation 5/19/2014 TE 814711 Monitoring of SFP Chemistry to Prevent Boral Degradation 5/19/2014 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancement.
The staff also audited the description of the Monitoring of Neutron-Absorbing Materials Other Than Boraflex program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.27, Buried and Underground Piping and Tanks Summary of Information in the Application. The SLRA states that AMP B.2.3.27, Buried and Underground Piping and Tanks, is an existing program with enhancements and exceptions that will be consistent with the program elements in GALL-SLR Report AMP XI.M41, Buried and Underground Piping and Tanks. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-079 Subsequent License Renewal Aging Management Program Basis Document Buried and Underground Piping and Tanks Revision 0 PDCR-PSOC 001 SPEC 2 General Specification for Excavation and Backfill 10/30/1984 NMP-ES-036-001 Underground Pipe and Tanks Monitoring Program Implementation Version 12.0 45QC-MNT-001-01 Excavation & Earthwork Quality Control Version 2.8 CR 859296 Pitting Identified on 1P41 Radwaste Discharge Piping 08/29/2014 CR 861616 Pitting on 1P41 Radwaste Discharge Piping in 2nd Excavation 09/04/2014 CR 10581729 CFAM Area of Concern - Hatch Underground Fire Protection Piping System Leaks 02/13/2019
49 CAR 276603 CY.3 INPO AFI 08/06/2019 CR 10740249 Leakage on Unit 1 Div 1 RHRSW Piping 09/21/2020 7022-0008-RPT-001 Southern Nuclear Buried Asset Program Review Revision 0 2301424.401 Engineering Soil Analysis for Buried Piping Asset Management Revision 0 In addition, the staff found that for the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements, sufficient information was not available to determine whether they were consistent with the corresponding program elements of the GALL-SLR Report AMP. The staff will consider issuing RAIs to obtain the information necessary to verify whether these program elements are consistent with the corresponding program elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Buried and Underground Piping and Tanks program provided in the FSAR supplement. The staff found that sufficient information was not available to determine whether the description provided in the FSAR supplement was an adequate description of the SLRA Buried and Underground Piping and Tanks program. The staff will consider issuing RAI to obtain the information necessary to verify the sufficiency of the FSAR supplement program description.
SLRA AMP B.2.3.28, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks Summary of Information in the Application. The SLRA states that AMP B.2.3.28, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks, is a new program that will be consistent with the program elements in GALL-SLR Report AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this new program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-080 Aging Management Program Basis Document Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks Revision 2 CR 847115 Fleet Coatings Procedure NMP-MA-011-006 Needs to Define Inspector Qualifications for Non-SL 1 Coating 03/03/2017 NMP-MA-011-006 Procedure for Coating Condition Assessments Revision 9.0 CR 850758 Fleet Coatings Procedure NMP-MA-011-006 Needs to Define Inspector Qualifications for Non-SL 1 Coating 05/05/2016
50 CR 10535021 Internal Inspection Results of the 1C Emergency Diesel Generator Lube Oil Cooler 09/18/2018 WO SNC1395927 1C EDG As-Found Inspection Results 10/25/2022 CR 10687715 As-found condition of 1B RHR 02/24/2020 WO SNC1078268 Repair Heat Exchanger Sealing Surface 1E11B001B 02/10/2022 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks program provided in the FSAR supplement.
The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.29, ASME Section XI, Subsection IWE Summary of Information in the Application. The SLRA states that AMP B2.3.29, ASME Section XI, Subsection IWE, is an existing program with enhancements that will be consistent with the program elements in GALLSLR Report AMP XI. S1, ASME Section XI, Subsection IWE.
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search of its operating experience database.
An on-site audit was performed July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-081 AGING MANAGEMENT PROGRAM BASIS DOCUMENT ASME SECTION XI, SUBSECTION IWE Revision 1 CR - 10859661 Spot of Corrosion - Underwater Torus Inspection 02/17/2022 CR - 10859779 Additional Spots of Corrosion - Underwater Torus Inspection 02/17/2022 CR - 10881418 Degraded Coatings (Torus Interior) 05/17/2022 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP
51 will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
During the on-site audit, the staff made the following observations during walkdowns:
During the walkdown, the staff noted that the adverse conditions in the ASME XI-IWE AMP were consistent with the descriptions in the OE documents provided in the e-Portal.
The staff also audited the description of the SLRA ASME Section XI, Subsection IWE AMP provided in the USAR supplement Section A2.2.29. The staff verified this description is consistent with the description provided in the GALLSLR Report.
SLRA AMP B.2.3.30, ASME Section XI, Subsection IWF Summary of Information in the Application. The SLRA states that AMP B2.1.30, ASME Section XI, Subsection IWF, is an existing program with enhancements that are consistent with the program elements in GALL-SLR Report AMP XI. S3, ASME Section XI, Subsection IWF.
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search of its operating experience database.
An on-site audit was performed from July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-082 AGING MANAGEMENT PROGRAM BASIS DOCUMENT ASME SECTION XI, SUBSECTION IWF Revision 1 WO SNC761842 DIV 2 VISUALLY INSPECT THE COATINGS AND BOLTING ON THE SEISMIC SUPPORTS IS (Inspection Task) 02/11/2016 CR 603883 Pipe Hanger Torn from Wall in 2B RWCU Pump Room 03/11/2013 CR 605172 2E11-RHR-R82 Found Damaged 03/12/2013 CR 607441 Failed VT-3 Examination 03/16/2013 WO SCN1719889 Snubber Found Unpinned 02/16/2024 CR 10319598 1B and 1D PSW Lower Seismic Restraint Corrosion 01/18/2017 WO SNC1231769 PERFORM REPAIR OF 1-BEAM 1N11-MSH-16 02/17/2022 WO SNC1717396 REPAIR/INSTALL PIPE SADDLE ON RESTRAINT 1E41-HPSEH-32 02/09/2024 CAR 205901 Pipe Hanger torn from wall in 2B RWCU Pump Room 03/11/2013
52 CR 605172 2E11-RHR-R82 Found Damaged 03/12/2013 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
During the on-site audit, the staff made the following observations during walkdowns:
During the walkdown, the staff noted that the adverse conditions in ASME Section XI, Subsection IWF, were consistent with the descriptions in the OE documents provided in the e-Portal.
During the walkdown, the licensee provided images of IWF supports around the torus chamber. The staff noticed the adverse conditions in the torus room in ASME Section XI, Subsection IWF were consistent with the descriptions in the OE documents provided in the e-Portal.
The licensee provided examples of IWF inspection not meeting acceptance criteria. The staff found the OE are consistent with the aging management program.
The staff also audited the description of the SLRA ASME Section XI, Subsection IWF provided in the UFSAR supplement Section A2.2.30. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.31, 10 CFR Part 50, Appendix J Summary of Information in the Application. The SLRA states that AMP B2.3.31, Appendix J, is an existing program that is consistent with the program elements in GALL-SLR Report AMP X1.S4, Appendix J.
Audit Activities. An on-site audit was performed July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-083 AMP Basis Document: 10 CFR Part 50, Appendix J Revision 1 CR 10333178 Primary containment penetration failure 02/19/2017 CR 10685609 1T48-F335A failed LLRT due to Excessive Leakage 02/08/2020 CR 10776891 LLRT failure of 2B31F019 02/21/2021 CR 10776895 LLRT failure of 2B31F020 02/21/2021
53 CR 10946508 Appendix J Program - LLRT Penetration Failure Associated with 2T23 - X026 (2T48-F319 & 2T48 -
F320) 02/07/2023 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent with the corresponding elements of the GALL-SLR Report AMP.
The staff also audited the description of the SLRA Appendix J provided in the UFSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report/SRPSLR.
SLRA AMP B.2.3.32, Masonry Walls Summary of Information in the Application. The SLRA states that AMP B.2.3.32, Masonry Walls, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI. S5, Masonry Walls. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. An on-site audit was performed from July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-084 Subsequent License Renewal Aging Management Program Basis Document - Masonry Walls Revision 1 UFSAR Edwin I. Hatch Nuclear Plant, Unit 1 and Unit 2 Final Safety Analysis Report (FSAR); NRC Docket Nos. 50-321 and 50-366 Revision 40 NMP-ES-063 License Renewal Program Version 6.1 NMP-ES-021 Structural Monitoring Program for the Maintenance Rule Version 12.0 NMP-GM-002 Corrective Action Program Version 12.1 SNC-1 Quality Assurance Topical Report Version 26.0 NMP-AD-025 Quality Assurance and Non-Quality Assurance Records Administration Version 14.3 NMP-GM-008 Operating Experience Program Version 24.0 SNC634027 Plant Hatch Unit 2 Structural Monitoring Inspection Report - 2015 NA CR 850819 Fire Rated Wall Issue in the 1B Battery Room 08/07/2014
54 CR 10002490 A New Work Order is Needed to Fix Previously Identified Gaps in CMU (Concrete Masonry Unit) Wall 12/17/2014 CR 10423795 Degraded Fire Barrier in Zone 1008 to Zone 0001 10/26/2017 CR 10459108 Cracking of Masonry Mortar Joint in Reactor Building Railroad Airlock 02/07/2018 Work Order SNC594234 Fire Rated Wall Issue in the 1B Battery Room 08/08/2014 Work Order SNC623936 A New Work Order is Needed to Fix Previously Identified Gaps in CMU (Concrete Masonry Unit) Wall 12/18/2014 Work Order SNC904169 Degraded Fire Barrier in Zone 1008 to Zone 0001 10/30/2017 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
During the audit, the staff also observed how the applicants planned enhancement to the detection of aging effect program element is intended to support consistency with the corresponding GALL-SLR Report AMP element.
During the on-site audit, the staff performed walkdowns of masonry walls within the scope of SLRA and made the following observation during walkdowns:
During the walkdown of the masonry walls, the staff noted that the conditions of the masonry walls were found to be consistent with the descriptions in the OE documents provided in the SLRA and e-Portal.
The staff also audited the description of the SLRA Masonry Walls provided in the UFSAR supplement Section A.2.2.32. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.34, RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Summary of Information in the Application. The SLRA states that AMP B.2.3.34, Inspection of Water-Control Structures Associated with Nuclear Power Plants, is an existing program with enhancements that will be consistent with the program elements in GALL-SLR Report AMP XI.
S7, Inspection of Water-Control Structures Associated with Nuclear Power Plants. At the time of the audit, the applicant had not yet fully developed the documents necessary to implement this enhanced program, and the staffs audit addressed only the program elements described in the applicants basis document.
Audit Activities. An on-site audit was performed from July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
55 Document Title Revision / Date SNCH00384-REPT-086 Subsequent License Renewal Aging Management Program Basis Document - Inspection of Water-Control Structures Associated with Nuclear Power Plants Revision 1 UFSAR Edwin I. Hatch Nuclear Plant, Unit 1 and Unit 2 Final Safety Analysis Report (FSAR); NRC Docket Nos. 50-321 and 50-366 Revision 40 NMP-ES-063 License Renewal Program Version 6.1 NMP-ES-021 Structural Monitoring Program for the Maintenance Rule Version 12.0 52PM-MME-006-0 Intake Structure Pit Inspection/Diving Activities Version 9.6 NMP-GM-002 Corrective Action Program Version 12.1 SNC-1 Quality Assurance topical Report Version 26.0 NMP-AD-025 Quality Assurance and Non-Quality Assurance Records Administration Version 14.3 NMP-GM-008 Operating Experience Program Version 24.0 SNC997891 Plant Hatch Unit 2 Structural Monitoring Inspection Report - 2019 NA SNC634027 Plant Hatch Unit 2 Structural Monitoring Inspection Report - 2015 NA Work Order SNC1141223 Intake Suction Pit Inspection 02/06/2021 CR 10184227 Concrete degradation observed at EL. 98 of Unit 1 and Unit 2 Suction Pit of Intake Structure 02/17/2016 CR 10328460 Concrete cracking observed at EL. 128 of Unit 1 and Unit 2 Intake Structure Roof 02/08/2017 Word Order SNC869364 Perform 12 Month Preventive Maintenance 05/23/2017 CR 11014095 Grating at Traveling Water Screens on suction pit side condition unsatisfactory 10/10/2023 CR 11014380 Intake Structure Grating Extent of Condition 10/11/2023 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, acceptance criteria, and corrective actions program elements of the SLRA AMP are consistent or will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
In addition, the staff found that for the detection of aging effects and monitoring and trending program elements, sufficient information was not available to verify whether it was consistent with the corresponding program element of the GALL-SLR Report AMP. The staff will consider issuing RAIs or use a voluntary SLRA supplement to obtain the information necessary to verify whether these program elements are consistent with the corresponding program elements of the GALL-SLR Report AMP.
56 During the audit, the staff made the following observations:
The staff noted that applicants implementing procedures lack provisions for special inspections immediately following the occurrence of significant natural phenomena.
The staff noted that the Inspection of Water-Control Structures Associated with Nuclear Power Plants AMP lacks the enhancements to manage the aging effects associated with aggressive groundwater/soil environment.
During the on-site audit, the staff made the following observations during walkdowns:
During the walk down of the Intake Structure, the staff did not find any significant degradations of the structure and noted that the conditions of the Intake Structure were found to be consistent with the descriptions in the OE documents provided in the SLRA and e-Portal.
The staff also audited the description of the SLRA Inspection of Water-Control Structures Associated with Nuclear Power Plant provided in the UFSAR supplement Section A.2.2.34.
The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.3.35, Protective Coating Monitoring and Maintenance Summary of Information in the Application. The SLRA states that AMP B.2.3.35, Protective Coating Monitoring and Maintenance, is an existing program with enhancements that will be consistent with NUREG-2191,Section XI. S8, Protective Coating Monitoring and Maintenance.
Audit Activities. The table below lists the documents that were reviewed by the staff and were found relevant to the Protective Coating Monitoring and Maintenance Program. The staff will document its review of this information in the SE.
RELEVANT DOCUMENTS REVIEWED Document Title Revision /
Date SNCH00384-REPT-087 Program Basis Document Protective Coating Monitoring and Maintenance Rev. 1 CR627037 Condition Report 2R22 Coating Inspection 04/23/13 CR627041 Condition Report 2R22 Coating Inspection 04/23/13 CR10209445 Condition Report Degraded Coatings in Unit 1 Torus proper 04/13/16 CR10209465 Condition Report Degraded Coatings in Unit 1 drywell 04/13/16 CR10693048 Condition Report Degraded Coatings (Drywell) 03/05/20 CR10786303 Condition Report Degraded Coatings (Inside Drywell) 03/30/21 CR10493682 Degraded Unit 1 Coatings 05/15/18
57 Document Title Revision /
Date SNC482603 Work Order Prep & Coat Junction Box 07/25/14 SNC482604 Work Order Prep & Coat Weld Connections 10/09/14 SNC482605 Work Order Prep & Coat 2X15 Flat Stock 10/09/14 SNC482607 Work Order Prep & Coat 14 Blank Penetration 01/07/15 SNC482612 Work Order Prep & Coat Fan Housing 07/25/14 SNC482613 Work Order Prep & Coat Housing 07/25/14 SNC482614 Work Order Prep & Coat Dollar Plate 07/25/14 SNC482615 Work Order Prep & Coat Embedded Plate on Drywell Liner 07/28/14 SNC482616 Work Order Prep & Coat Duct Work Flange and Stiffener 07/28/14 SNC482617 Work Order Prep & Coat Duct Work Flange and Stiffener 07/28/14 SNC482618 Work Order Prep & Coat 2 X 3 Area of Steel 07/28/14 SNC782682 Work Order Verify/Clean & Repair -Degraded coatings in Unit 1 Torus proper 01/23/18 SNC782683 Work Order Verify/Clean & Repair -Degraded coatings in Unit 1 drywell 01/23/18 SNC946471 Work Order Degraded Coatings in SNC805848 not completed during 1R28 outage 09/26/19 SNC1079454 Work Order Perform Coatings Repair AT Various Location in Drywell 12/08/21 SNC1095997 Work Order Perform Repair of Degraded Coatings (Drywell) 12/15/22 During the audit, the staff verified the applicants claim that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP will be consistent with the corresponding elements of the GALL-SLR Report AMP after implementation of the identified enhancements.
58 The staff also audited the description of the SLRA AMP Protective Coating Monitoring and Maintenance program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA AMP B.2.4.1, RHR Heat Exchanger Augmented Inspection (Plant Specific)
Summary of Information in the Application. The SLRA states that AMP B.2.4.1, RHR Heat Exchanger Augmented Inspection, is an existing plant-specific aging management program.
The staff audited the SLRA AMP to determine consistency with SRP-SLR Section A.1.2.3, Aging Management Program Elements.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Relevant Documents Reviewed Document Title Revision /
Date SNCH00384-REPT-088 Subsequent License Renewal Aging Management Program Basis Document RHR [Residual Heat Removal] Heat Exchanger Augmented Inspection Revision 1 /
4/21/2025 WO#SNC143764 2
Repair 2B RHR Heat Exchanger 2/4/2023 CR10505033 Indication of tube leak on 1B RHR heat exchanger 6/15/2018 CR10664568 Generate WO [Work Order] for RHR tube plug removal 11/14/2019 CR10687715 As found condition of 1B RHR 2/15/2020 CR10689171 Recommendation for tube plugging in the 1E11B001B1B 2/20/2020 CR10945505 2B RHR heat exchanger as-found inspection 2/3/2023 During the audit, the staff verified that the applicant addressed the guidance in SRP SLR Section A.1.2.3 for the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of SLRA AMP.
During the audit, the staff made the following observations:
The staff reviewed the AMP basis document with plant-specific operating experience (OE) and noted that this AMP is consistent with the existing licensing basis from the original license renewal (LR). However, the guidance in SRP-SLR Section 3.3.2.2.7, Loss of Material Due to Recurring Internal Corrosion, recommends that recurring internal corrosion may result in the need to augment AMP beyond the recommendations in the GALL-SLR Report. The criteria for potentially needing to augment the AMP beyond the recommendations in the GALL-SLR report are: (i) a 10 year search of plant-specific operating experience (OE) reveals the aging effect has
59 occurred in three or more refueling outage cycles, or (ii) a five year search of plant-specific OE reveals the aging effect has occurred in two or more refueling outage cycles and resulted in the component either not meeting plant-specific acceptance criteria or experiencing a reduction in wall thickness greater than 50 percent (regardless of the minimum wall thickness). The staff noted that according to plant-specific OE, there have been more than 4 instances of corrosion and/or degradation of the Hatch RHR heat exchanger passive components within 10 years.
During a breakout session, the staff asked the applicant for clarification on: (a) whether the plant-specific RHR Heat Exchanger Augmented Inspection AMP was developed in response to the RHR heat exchanger OE, and (b) why the 8-year inspection frequency is adequate to managing aging of the component. After the breakout session discussions, the applicant provided the following additional supplemental information in portal to address the staffs concerns.
The RHR Heat Exchanger Augmented Inspection program is the augmentation created in response to Hatch RHR heat exchanger OE to assist in managing loss of material due to recurring internal corrosion for the RHR heat exchanger components. It is noted in SLRA Sections A.2.3.1 and B.2.4.1 that the inspections performed by this program are done at least every 8 years or whenever leakage is suspected. Utilization of the Open-Cycle Cooling Water System program which inspects heat exchanger components on a frequency of at least 5 years in conjunction with the RHR Heat Exchanger Augmented Inspection program will adequately manage aging of these components. It is also noted that both the Open-Cycle Cooling Water System program and the RHR Heat Exchanger Augmented Inspection program are informed and enhanced, when necessary, through review of the plant-specific and industry OE to ensure efficiency.
The staff also audited the description of the SLRA RHR Heat Exchanger Augmented Inspection program provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA AMP B.2.4.2, Torus Submerged Components Inspection (Plant Specific)
Summary of Information in the Application. The SLRA states that AMP Torus Submerged Components Inspection, is an existing plant specific aging management program. The staff audited the SLRA AMP to determine consistency with SRPSLR Section A.1.2.3, Aging Management Program Elements.
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search for its operating experience database.
An on-site audit was performed July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-089 AMP Basis Document: Torus Submerged Component Inspection Revision 1 CR 777284 Degraded Conditions on RCIC Suction Strainer in U1 Torus Proper 02/21/2014 CR 10030240 Deformation found in Unit 2 Torus Shell Wetted Surface 02/22/2015
60 CR 10859661 Spot of Corrosion - Underwater Torus Inspection 02/17/2022 CR 10860060 Loose Quencher Arm Support Bolts in Torus 02/18/2022 CR 11051177 While performing Torus diving T-quencher Inspections per SNC1093557 IAW 42IT-PES-002-0, the Following Bolts were Found Loose.
02/17/2024 During the audit, the staff verified that the applicant addressed the guidance in SRPSLR Section A.1.2.3 for the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA AMP.
The staff also audited the description of the SLRA Torus Submerged Components Inspection provided in the UFSAR supplement Section A.2.3.2. The staff verified this description is consistent with the description provided in the GALL-SLR Report.
SLRA TLAA Section 4.2.2, RPV Materials Upper Shelf Energy (USE) Reduction due to Neutron Embrittlement Summary of Information in the Application. SLRA Section 4.2.2, RPV Materials Upper Shelf Energy Due to Neutron Embrittlement discusses the analysis for assessing the projected reduction in the upper-shelf energy (USE) properties of RPV base metal and weld components.
The applicant dispositioned the TLAA in accordance with 10 CFR 54.21(c)(1)(ii).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
Document Title Revision /
Date SIA 2300749.302NP Evaluation of Upper Shelf Energy for SLR Revision 0 SIA 2300749.301 Evaluation of Adjusted Reference Temperature and Reference Temperature Shifts Revision 0 BWRVIP-74-A BWR Vessel and Internals Project: BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal 06/2003 Hatch Unit 1 Final Safety Analysis Report Revision 38 Hatch Unit 2 Final Safety Analysis Report Revision 35 ML22332A455 BWRVIP-135, BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations (Non-Proprietary Version)
Revision 4
61 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(ii) for the projected reduction in the USE properties of RPV base metal and weld components.
During the audit, the staff made the following observations:
The staff verified that the material information (e.g., initial USE and %Cu) for the RPV materials contained in SLRA Tables 4.2.2-1, 4.2.2-2, 4.2.2-3, 4.2.2-4 are consistent with the applicants current licensing basis (i.e., FSAR).
The staff noted that the USE values were updated with fluence projections to the end of the subsequent period of operation (SPEO) for Units 1 and 2 (i.e., 68.6 and 66 EFPY, respectively).
The staff noted that the applicant considered surveillance data from the latest revision of the EPRI Integrated Surveillance Program (ISP) (i.e., BWRVIP-135, Revision 4) that is applicable to HNP Units 1 and 2.
The applicant stated that the final limiting %USE decrease is adjusted if surveillance data %USE is higher than the RG 1.99, Revision 2 %USE decrease.
Based on information in SLRA Tables 4.2.2-3 and 4.2.2-4, the staff confirmed the limiting plate (Heat No. C4337-1) and weld (Heat No. IP2815) for HNP Unit 1 were calculated using an equivalent margin analysis (EMA) consistent with the criterion set by BWRVIP-74A.
Based on information in SLRA Table 4.2.2-2, the staff confirmed that the limiting plate (Heat No. C8579-2) and weld (Heat No. 51874) were calculated using the generic attenuated 1/4T fluence values, consistent with RG 1.99, Revision 2.
The staff noted that the N16 instrumentation nozzle forging and weld are fabricated from non-ferritic materials which do not require impact toughness evaluation.
The staff also audited the description of the TLAA for the projected reduction in the upper-shelf energy (USE) properties of RPV base metal and weld components provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.2.3, Adjusted Reference Temperature (ART) for RPV Materials due to Neutron Embrittlement Summary of Information in the Application. SLRA Section 4.2.3, Adjusted Reference Temperature for RPV Materials Due to Neutron Embrittlement discusses the analysis for assessing the use of adjusted reference temperature (ART) to adjust the pressure temperature limit curves to account for irradiation effects. The applicant dispositioned the TLAA in accordance with 10 CFR 54.21(c)(1)(ii).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document its review of this information in the SE.
62 Document Title Revision /
Date SIA 2300749.302NP Evaluation of Upper Shelf Energy for SLR Revision 0 SIA 2300749.301 Evaluation of Adjusted Reference Temperature and Reference Temperature Shifts Revision 0 BWRVIP-74-A BWR Vessel and Internals Project: BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal 06/2003 Hatch Unit 1 Final Safety Analysis Report Revision 38 Hatch Unit 2 Final Safety Analysis Report Revision 35 ML22332A455 BWRVIP-135, BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations (Non-Proprietary Version)
Revision 4 ML15103A309 Updated Analysis for Combustion Engineering Fabricated Reactor Vessel Welds Best Estimate Copper and Nickel Content Revision 1 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(ii) for its ART analyses related to its reactor pressure vessel materials.
During the audit, the staff made the following observations:
The staff verified that the material information (e.g., initial RTNDT, %Cu, %Ni, initial USE, margin values) for the RPV materials contained in SLRA Tables 4.2.3-1, 4.2.3-2, 4.2.3-3, 4.2.3-4, 4.2.3-5, and 4.2.3-6 are consistent with the applicants current licensing basis (i.e., FSAR) or are supported by NRC-approved updates to material chemistry values.
The staff reviewed the applicants ART methodology and confirmed that the analyses were performed in accordance with RG 1.99, Revision 2.
The staff verified that projected neutron fluence values at the 1/4T location were determined using the generic attenuation method described in RG 1.99, Revision 2, and were used as inputs to the ART calculations.
The staff reviewed the applicants treatment of non-ferritic components (e.g., N16 instrumentation nozzle materials) and verified that these components were appropriately excluded from Appendix G impact toughness requirements, with ART values determined using the surrounding ferritic plate material properties.
The staff reviewed the applicants use of surveillance data in the ART analyses and verified that the applicant evaluated the surveillance data applicability consistent with RG 1.99, Revision 2.
The staff noted a discrepancy in the applicants ART calculation associated with Heat No. 90099. The staff will consider issuing RAI to seek clarification.
The staff also audited the description of the TLAA for the change in adjusted reference temperature for the reactor pressure vessel materials due to neutron embrittlement provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
63 SLRA TLAA Section 4.2.4, RPV Thermal Limit Analysis: Operating Pressure-Temperature (P-T) Limits Summary of Information in the Application. SLRA Section 4.2.4, RPV Thermal Limit Analysis:
Operating P-T Limits discusses the analysis for the Pressure-Temperature (P-T) limits for the reactor pressure vessel. The applicant dispositioned the TLAA in accordance with10 CFR54.21(c)(1)(iii), such that the effects of aging on the intended function(s) of the reactor vessels will be adequately managed through the subsequent period of extended operation using the 10 CFR 50.90 process for changes to P-T limits located in the Technical Specifications (TS).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-038 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exemptions Identification Revision 2 Hatch Nuclear Plant, Unit 1 Pressure and Temperature Limit Report (PTLR) for 38 and 49.3 Effective Full-Power Years (EFPY)
Revision 1 Hatch Nuclear Plant, Unit 2 Pressure and Temperature Limit Report (PTLR) for 37 and 50.1 Effective Full-Power Years (EFPY)
Revision 0 Edwin I. Hatch Nuclear Plant Technical Specifications Units 1 and 2 ML15092A856 Edwin I. Hatch Nuclear Plant Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T)
Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A 4/2/2015 ML16049A302 Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Safety Evaluation Related to Revised Pressure-Temperature Limits 2/23/2016 During the audit of the TLAA, the staff verified that the applicant has provided itsbasis that supports its disposition of 10CFR54.21(c)(1)(iii).
During the audit, the staff made the followingobservations:
The staff noted that the applicant submitted a license amendment request (LAR) to revise Unit 1 and Unit 2 TSs to relocate the P-T limit curves and associate references to
64 a Pressure and Temperature Limits Report (PTLR) (ML15092A856), which was approved by the NRC in 2016 (ML16049A302).
The period of applicability for the current P-T limits is 49.3 EFPY for Unit 1 and 50.1 EFPY for Unit 2. The reactor coolant system (RCS) pressure, temperature, heat up and cooldown rates, and recirculation pump starting temperature shall be maintained within the limits specified in the PTLRs (defined in TS Section 3.4.9).
The staff also audited the description of the SLRA RPV Thermal Limit Analysis: Operating P-T Limits TLAA (SLRA Section A.3.2.4) provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.2.5, RPV Circumferential Weld Examination Relief Summary of Information in the Application. SLRASection 4.2.5, RPV Circumferential Weld Examination Relief, discusses the failure probability analyses associated with neutron embrittlement of the RPV circumferential welds. The applicantdispositioned the TLAAs in accordance with10 CFR54.21(c)(1)(iii).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to TLAA. The staff will document its review of this information in the SE.
Document Title Revision /
Date BWRVIP-329-A BWR Vessels and Internals Program: Updated Probabilistic Fracture Mechanics Analyses for BWR RPV Welds to Address Extended Operations December 2021 BWRVIP-05 BWR Vessels and Internals Project: BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations September 1995 SIA 2300749.402NP Reactor Pressure Vessel Axial and Circumferential Weld Analysis with BWRVIP-329-A for Hatch Units 1 and 2 Revision 0 SIA 2300749.302NP Evaluation of Upper Shelf Energy for SLR Revision 0 SIA 2300749.301 Evaluation of Adjusted Reference Temperature and Reference Temperature Shifts Revision 0 Hatch Unit 2 Final Safety Analysis Report - Section 5 Revision 39 During the audit of the TLAA, the staff verified that the applicant has provided itsbasis that supports its disposition of 10CFR54.21(c)(1)(iii) for the failure probability analyses associated with the RPV circumferential welds.
65 During the audit, the staff made the followingconfirmations and observations:
The plant-specific reactor pressure vessel dimensions for Units 1 and 2, used in the applicants assessment of these TLAAs (SIA 2300749.402NP), are within the limits of applicability established in Table 5-1 of BWRVIP-329-A.
The plant-specific end-of-interval RTmax values for the limiting plate and circumferential weld for Units 1 and 2 were less than the corresponding limiting RTmax value for plate materials and circumferential welds in BWRVIP-329-A.
The staff confirmed based on information in SLRA Tables 4.2.5-1 through 4.2.5-3 the limiting plate and axial weld were addressed o
Based on information in SLRA Tables 4.2.5-1 through 4.2.5-3, the staff confirmed the following regarding the limiting RPV materials at Unit 1:
Limiting plate - Heat No.C4114-2
Limiting axial weld - Heat No. IP2815 o
Based on information in SLRA Tables 4.2.5-1 through 4.2.5-3, the staff confirmed the following regarding the limiting RPV materials at Unit 2:
Limiting plate - Heat No. C8553-1
Limiting axial weld - Heat No.10137 o
The plant-specific end-of-interval RTmax values for the limiting plate and axial weld for Units 1 and 2 were calculated based on material properties of the reactor pressure vessel based on 68.6 and 66 EFPY, respectively.
The plant-specific end-of-interval RTmax values were calculated using methodologies consistent with BWRVIP-329-A.
The plant-specific end-of-interval RTmax values for the limiting plate and axial weld for Units 1 and 2, were less than the corresponding limiting RTmax value for plate materials and axial welds in BWRVIP-329-A.
The staff also audited the description of the TLAA for the RPV Axial Weld Failure Probability provided in the FSAR supplement. The staff verified the description is consistent with the description provided in the SRP-SLR Report.
SLRA TLAA Section 4.2.6, Axial Weld Failure Probability Summary of Information in the Application. SLRASection 4.2.6, RPV Axial Weld Failure Probability, discusses the failure probability analyses associated with neutron embrittlement of the RPV axial welds. The applicantdispositioned the TLAAs in accordance with10 CFR54.21(c)(1)(ii).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to TLAA. The staff will document its review of this information in the SE.
66 Document Title Revision /
Date BWRVIP-329-A BWR Vessels and Internals Program: Updated Probabilistic Fracture Mechanics Analyses for BWR RPV Welds to Address Extended Operations December 2021 BWRVIP-05 BWR Vessels and Internals Project: BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations September 1995 SIA 2300749.402NP Reactor Pressure Vessel Axial and Circumferential Weld Analysis with BWRVIP-329-A for Hatch Units 1 and 2 Revision 0 SIA 2300749.302NP Evaluation of Upper Shelf Energy for SLR Revision 0 SIA 2300749.301 Evaluation of Adjusted Reference Temperature and Reference Temperature Shifts Revision 0 Hatch Unit 2 Final Safety Analysis Report - Section 5 Revision 39 During the audit of the TLAA, the staff verified that the applicant has provided itsbasis that supports its disposition of 10CFR54.21(c)(1)(ii) for the failure probability analyses associated with the RPV axial welds.
During the audit, the staff made the followingconfirmations and observations:
The plant-specific reactor pressure vessel dimensions for Units 1 and 2, used in the applicants assessment of these TLAAs (SIA 2300749.402NP), are within the limits of applicability established in Table 5-1 of BWRVIP-329-A.
The staff confirmed based on information in SLRA Tables 4.2.5-1 through 4.2.5-3 the limiting plate and axial weld were addressed o
Based on information in SLRA Tables 4.2.5-1 through 4.2.5-3, the staff confirmed the following regarding the limiting RPV materials at Unit 1:
Limiting plate - Heat No. C4114-2
Limiting axial weld - Heat No. IP2815 o
Based on information in SLRA Tables 4.2.5-1 through 4.2.5-3, the staff confirmed the following regarding the limiting RPV materials at Unit 2:
Limiting plate - Heat No. C8553-1
Limiting axial weld - Heat No. 10137 o
The plant-specific end-of-interval RTmax values for the limiting plate and axial weld for Units 1 and 2 were calculated based on material properties of the reactor pressure vessel based on 68.6 and 66 EFPY, respectively.
The plant-specific end-of-interval RTmax values were calculated using methodologies consistent with BWRVIP-329-A.
The plant-specific end-of-interval RTmax values for the limiting plate and axial weld for Units 1 and 2, were less than the corresponding limiting RTmax value for plate materials and axial welds in BWRVIP-329-A.
The staff also audited the description of the TLAA for the RPV Axial Weld Failure Probability provided in the FSAR supplement. The staff verified the description is consistent with the description provided in the SRP-SLR Report.
67 SLRA TLAA Section4.2.7, Reflood Thermal Shock Analysis of the RPV Summary of Information in the Application. SLRA Section 4.2.7, Reflood Thermal Shock Analysis of the RPV discusses the analysis for the non-ductile failure of the reactor pressure vessel for all postulated plant conditions. The applicant dispositioned the TLAA in accordance with10 CFR54.21(c)(1)(ii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
Document Title Revision /
Date SIA File No. 2300749.303Reactor Pressure Vessel Reflood Thermal Shock Evaluation for Hatch Units 1 and 2 Revision 0 SIA File No. 2300749.301Evaluation of Adjusted Reference Temperature and Reference Temperature Shifts Revision 0 During the audit of the TLAA, the staff verified that the applicant has provided itsbasis that supports its disposition of 10CFR54.21(c)(1)(ii).
During the audit, the staff made the followingobservations:
The staff verified that the maximum KIapplied in the vessel at any time during the steam line break transient is 105 ksi-in1/2, consistent with the Ranganath analysis.
The staff verified that Unit 1 limiting ART at 0T for 68.6 EFPY is 152.1°F and Unit 2 limiting ART at 0T for 66 EFPY is 89.3°F.
The staff noted an inconsistency in SLRA Tables 4.2.7-1 and 4.2.7-2 related to the expected EFPY values for Units 1 and 2 at the end of the SPEO. The staff will consider issuing RAI.
The staff also audited the description of the SLRA TLAA Reflood Thermal Shock Analysis of the RPV (SLRA Section A.3.2.7) provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.2.8, Susceptibility to IASCC Summary of Information in the Application.SLRA Section 4.2.8, Susceptibility to IASCC discusses the analysis for the Irradiation-Assisted Stress Corrosion Cracking (IASCC) of reactor vessel internals for Hatch Units 1 and 2. The applicant dispositioned the TLAA in accordance with10 CFR54.21(c)(1)(iii).
Audit Activities. During its audit, the staff reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to the program. The staff will document their review of this information in the SE.
68 Document Title Revision /
Date BWRVIP-315 BWR Vessel and Internals Project Reactor Internals Aging Management Evaluation for Extended Operations 07/2019 BWRVIP-315-A Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report BWRVIP-315; Reactor Internals Aging Management Evaluation for Extended Operations 04/2024 During the audit of the TLAA, the staff verified that the applicant has provided itsbasis that supports its disposition of 10CFR54.21(c)(1)(iii).
During the audit, the staff made the followingobservations:
The staff noted that the aging effects of IASCC and embrittlement on the top guide, core shroud, and jet assembly components will be managed in the subsequent period of extended operation in accordance with the BWR Vessel Internals AMP.
The staff also audited the description of the SLRA Susceptibility to IASCC TLAA (SLRA Section A.3.2.8) provided in the FSAR supplement.The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.3.1, 80-Year Transient Cycle Projections Summary of Information in the Application. SLRA Section 4.3.1, 80-Year Transient Cycle Projections, discusses the 80-year transient cycles for fatigue analyses. The applicant did not identify the transient cycle projections as a TLAA because (1) the transient cycle projections are used only as the input to fatigue TLAAs and (2) the specific dispositions of fatigue TLAAs, which involve transient cycles, are separately described in SLRA Sections 4.3.2 through 4.3.9. To verify the adequacy of the projections of transient cycles, the staff audited the 80-year cycle projections. The staff will address issues identified but not resolved in this audit report in the SE.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the 80-year cycle projections for fatigue analyses. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 During the audit of the 80-year cycle projections, the staff verified that the applicant has provided its basis that supports the adequacy of cycle projections. However, the staff found that sufficient information was not available to complete its review of the projections. In order to obtain the necessary information, the staff will consider issuing RAI in relation to the observation discussed below.
69 During the audit, the staff made the following observation. SLRA Section 4.3.1 explains that the applicant extrapolated the most recent cycle data over a period of 10 years (i.e., 1/1/2013 -
12/31/2022), which is expected to yield the best estimate of future cycles and fatigue since it is based on the most recent plant experience.
In contrast, the following reference indicates that the 80-year cycle projections use the short-term (10-year) and long-term cycle accumulation rates (since the start of the plant operation) rather than the use of the short-term cycle accumulation rate only (
Reference:
SIA FP-HTCH-307, Revision 0, Section 4.7). Therefore, the staff needs clarification on whether the 80-year cycle projections use the short-term and long-term cycle accumulation rates.
The staff also audited the description of the 80-year cycle projections provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.2, ASME Section III, Class 1 Fatigue Waivers Summary of Information in the Application. SLRA Section 4.3.2, ASME Section III, Class 1 Fatigue Waivers, discusses the fatigue waiver time-limited aging analyses (TLAAs) for ASME Code Section III, Class 1 components. The applicant dispositioned the TLAAs in accordance with 10 CFR54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the fatigue waiver TLAAs. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA 2201085.307 Fatigue Exemptions (Waivers) for Hatch Class 1 Components Revision 0 1/19/2024 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the fatigue waiver TLAAs for ASME Code Section III, Class 1 components provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.3, RPV Fatigue Analyses Summary of Information in the Application. SLRA Section 4.3.3, RPV Fatigue Analyses, discusses the fatigue TLAAs for the reactor pressure vessel (RPV) components. The applicant dispositioned the TLAAs in accordance with 10 CFR54.21(c)(1)(iii). To verify that the applicant provided a basis to support its disposition of the TLAAs, the staff audited the TLAAs.
70 Audit Activities. During its audit, the staff interviewed the applicants staff and reviewed documentation contained in the SLRA and provided by the applicant via e-Portal.
For the operating experience (OE) review, the applicant made a presentation on the process used to identify and evaluate the pertinent OE. Afterwards, the staff conducted its review of the applicants methodology and OE by reviewing documentation contained in the SLRA and e-Portal.
The table below lists documents that were reviewed by the staff and were found relevant to fatigue TLAAs for the RPV components. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 SIA 2201085.301 80-Year Fatigue Analysis of Reactor Pressure Vessel (RPV), Reactor Vessel Internals (RVI), and Penetrations, Revision 0 8/5/2024 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the fatigue TLAAs for the RPV components provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.4 Fatigue Analyses of the Reactor Pressure Vessel Internals Summary of Information in the Application. SLRA Section 4.3.4, Fatigue Analysis of RPV Internals, discusses the fatigue TLAA for the RPV internal components. The applicant dispositioned the TLAA in accordance with 10 CFR54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the fatigue TLAA for the RPV internal components. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025
71 Document Title Revision /
Date SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 including 60- and 80-Year Projections Revision 0 9/6/2023 SIA 2201085.301 80-Year Fatigue Analysis of Reactor Pressure Vessel (RPV), Reactor Vessel Internals (RVI), and Penetrations Revision 0 8/5/2024 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the fatigue TLAA for the RPV internal components provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.5, ASME Section III, Class I Fatigue Analysis Summary of Information in the Application. SLRA Section 4.3.5, ASME Section III, Class 1 Fatigue Analysis, discusses the fatigue TLAA for ASME Code Section III, Class 1 piping systems. The applicant dispositioned the TLAA in accordance with 10 CFR54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the fatigue TLAA for the Class 1 piping systems. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 SIA 2201085.303 80-Year Fatigue Analysis of Class 1 Piping Locations Revision 0 12/7/2023 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the fatigue TLAA for the Class 1 piping systems provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
72 SLAR TLAA Section 4.3.6, ASME Section III, Class 2 and 3 and ANSI B31.1 and Associated HELB Analyses Summary of Information in the Application. SLRA Section 4.3.6, ASME Section III, Class 2 and 3 and ANSI B31.1 and Associated Line Break Analyses, discusses the fatigue and pipe break TLAAs for the ASME Section III, Class 2 and 3 and ANSI B31.1 piping systems (also called non-Class 1 piping systems). The applicant dispositioned the TLAAs in accordance with 10 CFR54.21(c)(1)(i).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the fatigue and pipe break TLAAs for the non-Class 1 piping systems. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 SIA 2201085.304 Evaluation of ANSI B31.1 and AMSE Class 2 and 3 Piping and Components (Non-Class 1 Fatigue)
Revision 0 12/19/2023 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(i). However, the staff found that sufficient information was not available to complete its review of the projections. In order to obtain the necessary information, the staff will consider issuing RAI in relation to the observation discussed below.
During the audit, the staff made the following observation. SLRA Section 4.3.6 indicates that non-Class 1 components are excluded from the transient cycle evaluation for fatigue if they are in systems that may have normal/upset condition operating temperatures that do not exceed 220°F. In comparison, SLRA Table 4.3.6-1 indicates that non-Class 1 components are excluded from the transient cycle evaluation if the temperature range is not greater than 220 °F, as opposed to the maximum normal/upset condition operating temperature. The staff needs to resolve the potential inconsistency between the maximum operating temperature and the temperature range discussed above.
The staff also audited the description of the fatigue and pipe break TLAAs for the non-Class 1 piping systems provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.7, Environmentally Assisted Fatigue Summary of Information in the Application. SLRA Section 4.3.7, Environmentally Assisted Fatigue, discusses the environmentally assisted fatigue (EAF) TLAAs for the reactor coolant
73 pressure boundary components. The applicant dispositioned the TLAAs in accordance with 10 CFR54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found to be relevant to the EAF TLAAs for the reactor coolant pressure boundary components. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 SIA 2201085.306P Environmentally Assisted Fatigue Screening for Hatch Revision 0 7/22/2024 SIA 2201085.305 Hatch Units 1/2 Environmentally Assisted Fatigue Analysis for 80 Years, NUREG/CR-6260 Locations Revision 1 12/3/2024 SIA 2201085.310 Environmentally Assisted Fatigue Calculations for Sentinel Locations at Hatch Revision 0 8/26/2024 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii). However, the staff found that sufficient information was not available to complete its review of the TLAAs. To obtain the necessary information, the staff will consider issuing an RAI in relation to the observations discussed below.
During the audit, the staff made the following observations. SLRA Section 4.3.7 does not clearly describe how the detailed evaluation reduces the excessive conservatism associated with the screening CUFen values that are based on conservative temperature, strain rate, and sulfur content in steels.
In addition, SLRA Section 4.3.7 does not clearly discuss the following: (1) whether the average temperature approach is used for the environmental fatigue correction factor (Fen) calculation in the detailed evaluation after the screening evaluation; (2) if so, whether the average temperature approach is used only for a simple, linear transient and whether the Fen threshold temperature for each material type is used per NUREG/CR-6909, Revision 1; and (3) if the average temperature approach is used for a complex transient, why the conservatism of the applicants approach is comparable to or greater than that of the modified rate approach described in NUREG/CR-6909, Revision 1, Section 4.4.
74 The staff also audited the description of the EAF TLAAs for the reactor coolant pressure boundary components provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.8, High Energy Line Break Analyses Based on Cumulative Fatigue Usage Summary of Information in the Application. SLRA Section 4.3.8, High Energy Line Break Analyses Based on Cumulative Fatigue Usage, discusses the CUF-based high energy line break (HELB) TLAAs for the Class 1 piping systems. The applicant dispositioned the TLAA in accordance with 10 CFR54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the CUF-based HELB TLAAs for the Class 1 piping systems. The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025 SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 Including 60- and 80-Year Projections Revision 0 9/6/2023 During the audit of the TLAAs, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the CUF-based HELB TLAAs for the Class 1 piping systems provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.3.9, Cycle-dependent Fracture Mechanics on Flaw Evaluations Summary of Information in the Application. SLRA Section 4.3.9, Cycle-dependent Fracture Mechanics or Flaw Evaluations, discusses the fatigue crack growth TLAA for the Unti 1 RPV closure head dollar plate weld (i.e., HC-1 weld). The applicant dispositioned the TLAA in accordance with 10 CFR54.21(c)(1)(ii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the fatigue crack growth TLAA for the Unit 1 RPV closure head dollar plate weld (HC-1). The staff will document its review of this information in the SE.
Document Title Revision /
Date SNCH00384-REPT-039 Hatch Units 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exception Evaluation Revision 1 5/9/2025
75 Document Title Revision /
Date SIA FP-HTCH-307 Fatigue Update for Hatch Units 1 and 2 from 1/1/2021 to 12/31/2022 including 60- and 80-Year Projections Revision 0 9/6/2023 NL-21-0905 Edwin I. Hatch Nuclear Plant - Unit 1 Inservice Inspection Program Owners Activity Report (OAR-
- 1) for Outage 1R29 (ML22027A845) 1/26/2022 GE Verona Hitachi 010N2830 Response to NRC RAI on SLRA Section 4.3.9 Revision 0 August 2025 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(ii). However, the staff found that sufficient information was not available to complete its review of the TLAA. To obtain the necessary information, the staff will consider issuing an RAI in relation to the observations discussed below.
During the audit, the staff made the following observations.
The following document indicates that the startup/shutdown cycles evaluated in the fatigue crack growth analysis are 51 cycles for 34 years from 2020 to 2054 (
Reference:
GE Verona Hitachi 010N2830, Revision 0, August 2025).
In comparison, SLRA Table 4.3.1-1 indicates that the startup cycles accumulated up to December 31, 2012, and December 31, 2022, are 273 cycles and 298 cycles, respectively.
These observed cycles correspond to a cycle accumulation rate of 2.5 cycles/yr (i.e., (298 -
273)/10). The same cycle accumulation rate is also applied to the shutdown transient. For the evaluation period of the fatigue crack growth analysis (34 years from 2020 to 2054), this cycle accumulation rate leads to a projected cycle of 85 (i.e., 2.5 x 34).
Since the evaluated cycles (51 cycles) are less than the projected cycles (85 cycles), the staff needs clarification on whether the fatigue crack growth analysis is still valid for the projected cycles (85 cycles) of the startup/shutdown transient.
The staff also audited the description of the fatigue crack growth TLAA for the Unit 1 RPV closure head dollar plate weld provided in the FSAR supplement. The staff verified this description is consistent with the guidance in SRP-SLR Section 4.3.2.2.
SLRA TLAA Section 4.5, Concrete Containment Tendon Prestress Not Applicable SLRA TLAA Section 4.6, Liner Plate, Metal Containments, and Penetrations Fatigue Analyses Summary of Information in the Application.
76 1.
4.6.1 Fatigue Analysis of the Vessel Shell to Ring Girder, the 80-year projected fatigue screening values (U80) for the torus vessel at the ring girder or saddle/shell intersection are 0.714 for Unit 1 and 0.622 for Unit 2.
2.
4.6.2 Fatigue Exemption (Waivers) for Main Steam Penetration Backing Ring and Containment Penetrations, fatigue exemption evaluation shows that all general and N-415-1 criteria are met, therefore the backing ring for the Unit 1 main steam containment penetrations, as well as HNP Units 1 and 2 containment and containment penetrations, are exempt from fatigue analysis for an 80-year life.
The SLRA discusses the analysis for the following Unit 1 and 2 torus locations:
3.
Unit 1 torus locations:
o Vent: header/vent pipe intersection.
o Vessel: ring girder / or saddle/shell intersection o
Torus penetration X-207 4.
Unit 2 torus locations:
o Vent system: downcomer penetration.
o Vessel: ring girder / or saddle/shell intersection.
o Torus penetration X-205 o
Torus penetrations X-204A-D and X-208A/B.
The applicant dispositioned the TLAA in accordance with 10 CFR 54.21(c)(1)(iii).
Audit Activities. In addition to the OE documentation contained in the SLRA and e-Portal, the staff observed the applicants search of its operating experience database.
An on-site audit was performed July 29, 2025, to July 31, 2025.
The table below lists documents that were reviewed by the staff and were reviewed by the staff and were found to be relevant to TLAA. The staff will document its review of this information in the SE.
Document Title Revision / Date SNCH00384-REPT-039 Hatch Unites 1 and 2 Subsequent License Renewal Time-Limited Aging Analyses and Exemption Evaluation Revision 1 2201085.302 80-Year Fatigue Analysis of Suppression Chamber Revision 0 2201085.308 Updated Fatigue Exemption (Waiver) for Hatch Unit 1 Main Steam Penetration Backing Ring Revision 0 2201085.309 Fatigue Exemptions (Waivers) for Hatch Containment Penetrations Revision 0 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the Containment Liner Plate, Metal Containments, and Penetrations Fatigue Analyses Evaluation TLAA provided in the UFSAR supplement. The staff verified that this description is consistent with the description provided in the SRP-SLR.
77 SLRA TLAA Section 4.6.1, Fatigue Analysis of the Vessel Shell to Ring Girder See Section 4.6.
SLRA TLAA Section 4.6.2, Fatigue Exemption (Waivers) for Mainstream Penetration Backing Ring and Containment Penetrations See Section 4.6.
SLRA TLAA Section 4.7, Other Plant Specific TLAAs SLRA TLAA Section 4.7.1, Crane Load Cycle Limits Summary of Information in the Application. SLRA Section 4.7.1, Crane Load Cycle Limits, discusses the 60-year limits for each evaluated crane, where the total number of projected load cycles is less than the maximum design allowable 2,000,000 cycles for the Category 1, Service Class F cranes. Therefore, the load cycle analyses remain valid for the subsequent period of extended operation. The applicant disposed of the TLAA in accordance with 10 CFR 54.21(c)(1)(i).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to TLAA. The staff will document its review of this information in the SE.
Document Title Revision /
Date Association of Iron and Steel Engineers (AISE)
Standard No. 6, Specification for Electric Overhead Traveling Crane for Steel Mill Service May 1, 1969 DCPP DCM S-42B Fuel Handling Cranes & Storage Racks, Appendix D, Spent Fuel Pool Bridge Crane.
Revision 6. July 13, 2020 CMAA Specification
- 70 Specifications for Electric Overhead Traveling Cranes Revised 1975 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(i).
The staff also audited the description of the Crane Load Cycle Limits TLAA provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.7.1, Fatigue of Cranes (Crane Cycle Limits)
Summary of Information in the Application. SLRA Section 4.7.1, Crane Load Cycle Limits, discusses the 80-year load cycle limits for each evaluated crane, the total number of projected load cycles is less than the maximum design allowable 100,000 cycles for Service Class A cranes. Therefore, the load cycle analyses remain valid for the subsequent period of extended operation. The applicant dispositioned the TLAA in accordance with 10 CFR 54.21(c)(1)(i).
From April 29 to May 3, 2024, the staff participated in an on-site audit at BFNPP in Athens, AL to gain a general overview of current conditions of the structures compared to the provided
78 operating experience (OE). While onsite, the staff engaged with the applicant staff, conducted walkdowns, and reviewed documents provided by the applicant.
For the OE review, the staff conducted its review of the applicants methodology and operating experience by reviewing documentation contained in the SLRA and ePortal.
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to the TLAA. The staff will document its review of this information in the SE.
Document Title Revision /
Date ETE-SLR-2023-3316 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) handling Systems Revision 0 CMAA Specification # 70 Specifications for Electric Overhead Traveling Cranes Revised 1975 During the on-site audit, the staff performed walkdowns of the Spent Fuel Pools, Reactor Building, Turbine Building, Service Water Intake Structure, Service Water Cannel Structures and Yard.
During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(i).
The staff also audited the description of the Crane Load Cycle Limits TLAA provided in the FSAR supplement. The staff verified that this description is consistent with the description provided in the SRP-SLR.
SLRA TLAA Section 4.7.2, Corrosion Allowance Calculations Summary of Information in the Application. SLRA Section 4.7.2, Corrosion Allowance Calculation, discusses the analyses of the RHR Service Water and Plant Service Water System piping. The applicant dispositioned the TLAA in accordance with 10 CFR 54.21(c)(1)(iii).
Audit Activities. The table below lists documents that were reviewed by the staff and were found relevant to TLAA. The staff will document its review of this information in the SE.
Document ID Number Document Title Revision /Date BDF9912 (DRF B11-00827-00)
Corrosion Allowance for the Hatch 1 and 2 Vessel/Piping Systems Sept 15, 1999 SNCH00384-REPT-038 Hatch Units 1 and 2 SLR TLAA and Exceptions Identification Revision 2 During the audit of the TLAA, the staff verified that the applicant has provided its basis that supports its disposition of 10 CFR 54.21(c)(1)(iii).
The staff also audited the description of the SLRA Corrosion Allowance Calculations provided in the FSAR supplement. The staff verified this description is consistent with the description provided in the SRP-SLR.
79 3.
Audit Questions Provided to SNC Over the course of the audit, the NRC staff provided audit questions to SNC to facilitate the audit discussions (ML26044A157).
Subject Area Meeting Date Onsite Audit 7/28/25 - 7/31/25 Breakout Session: Water Chemistry AMP 8/25/25 Breakout Session: Buried and Underground Piping and Tanks AMP 8/27/25 Breakout Session: Selective Leaching AMP 8/27/25 Breakout Session: Fire Protection 8/27/25 Breakout Session: Fire Water System AMP 8/27/25 Breakout Session: Scoping of Auxiliary System 9/2/25 Breakout Session: Recurring Internal Corrosion 9/3/25 Breakout Session: Flow-Accelerated Corrosion 9/3/25 Breakout Session: Scoping of Structures 9/4/25 Breakout Session: Inspection of Water-Control Structures Associated with Nuclear Power Plants 9/4/25 Breakout Session: Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Breakout Session: Structures Monitoring Program 9/9/25 Breakout Session: Concrete 9/9/25 Breakout Session: Inaccessible Medium Voltage Cables 9/9/25 Breakout Session: Fatigue Monitoring Program 9/10/25 Breakout Session: Metal Fatigue 9/10/25 Breakout Session: 80-Year Transient Cycle Projections 9/10/25 Breakout Session: ASME Section III, Class 1 Fatigue Waivers 9/10/25 Breakout Session: RPV Fatigue Analyses 9/10/25 Breakout Session: Fatigue Analyses of RPV Internals 9/10/25 Breakout Session: ASME Section III, Class 1 Fatigue Analysis 9/10/25 Breakout Session: ASME Section III, Class 2 and 3 and ANSI B31.1 9/10/25 Breakout Session: Environmentally Assisted Fatigue 9/11/25 Breakout Session: High Energy Line Break Analyses Based on Cumulative Fatigue Usage 9/11/25 Breakout Session: Cycle-Dependent Fracture Mechanics or Flaw Evaluations 9/11/25 Breakout Session: Irradiation-Structural 9/17/25 Breakout Session: Stainless Steel Nickel Alloy Aluminum Alloy Further Evaluations 9/18/25
80 4.
Applicant Personnel Contacted During the Audit Name Affiliation Brad Deen Southern Nuclear Michael Todd Southern Nuclear Brad Creek Southern Nuclear Adam Wilcher Southern Nuclear Brandon Marlow Southern Nuclear Amy Aughtman Southern Nuclear DeLisa Pournaras Southern Nuclear Lindsey Grissom Southern Nuclear Chris Dunham Southern Nuclear Chris Lowe Southern Nuclear Ally Humphries Southern Nuclear Aaron Phillippe Southern Nuclear Isaac Carter Southern Nuclear Alston Sweat Southern Nuclear Cotasha Blackburn Southern Nuclear David Reno Southern Nuclear April Perkins Southern Nuclear Josh Hunter Southern Nuclear DJ Vaughn Southern Nuclear Scott Pellet Southern Nuclear Hunter Knight Southern Nuclear Len Casella Southern Nuclear John Lattner Southern Nuclear Jimmy Collins Southern Nuclear Mark Hunt Southern Nuclear Jeff Head Enercon Ian Miller Enercon Olivia Roster Enercon James Hamlen Enercon Mitch McFarland Enercon Jacob Barnes Enercon Ron Hepp Enercon Steve Franzone Consultant to SNC Steve Hardy Consultant to SNC Keith Evon Structural Integrity Associates Dan Denis Structural Integrity Associates Terry Herrmann Structural Integrity Associates Laura Perez Structural Integrity Associates Kevin Wong Structural Integrity Associates Josh Motley GE Dean Jones Transware Greg Lupia GSE Solutions Annessa Lippincott GSE Solutions
81 5.
Exit Meeting An exit meeting was held with the applicant on September 25, 2025, to discuss the results of the regulatory audit. The NRC staff is considering the issuance of RAIs and RCIs to support the completion of the NRC staffs SLRA review.