Aging Management Programs (AMPs) are created in both the US and internationally to manage aging effects for component types identified during the aging management review (AMR) portion of the integrated plant assessment (IPA) process or the LTO assessment. US NRC previously approved generic AMP descriptions and requirements are included in Chapter XI of the Generic Aging Lessons Learned (GALL) reports for both initial (see NUREG-1801) and subsequent license renewal (SLR) (see NUREG-2191). Plant-specific AMPs may also be created when necessary to manage any unique aging effects or components at a nuclear site or if a plant-specific AMP will more effectively manage the aging effect of interest for that plant.

10 Element Approach[edit]

Whether generic or plant-specific, an AMP must include ten elements that serve as the technical basis for the program. These elements are:

Scope of Program
Preventive Actions
Parameters Monitored or Inspected
Detection of Aging Effects
Monitoring and Trending
Acceptance Criteria
Corrective Actions
Confirmation Process
Administrative Controls
Operating Experience

AMPs can also include pre-existing plant programs with or without enhancements or have exceptions.

Element 1 provides the direct connection to the AMR through the definition of component types, structures, or specific materials, environments, or aging effects that will be managed by a particular AMP.

Elements 2 through 5 provide a means to prevent, identify, and disposition aging of components and to expand the scope of the program, should significant aging be detected. These elements include provisions for recommended inspection types, frequency, and sample size, as well as applicable mitigative actions.

Elements 6 through 8 provide guidance regarding acceptable practices for dispositioning identified aging, including extent of condition and recommended actions. These elements ensure that aging effects which exceed acceptance criteria are appropriately entered into the site’s corrective action program. Entering identified age-related degradation into the corrective action program ensures that:

The resolution of that specific degradation is tracked.
Timely action can be taken to identify and prevent or mitigate further and future aging in related SSCs before the degradation challenges the intended function of the components.
Corrective actions are adequate and effective.

Element 9 provides a link to a site’s existing quality assurance program, ensuring that administrative controls provide a formal review and approval process for actions related to a given AMP.

Element 10 outlines the obligation to continuously review and disposition both industry and plant-specific operating experience related to the other elements of a given AMP.

Disposition of, and consistency with, each of the ten elements for a specific AMP at a given site forms the basis for adequate aging management of LR components. Therefore, any exceptions or enhancements to the guidance within the applicable Generic Aging Lessons Learned (GALL) report for a generic AMP element must be appropriately identified and justified for regulatory review and acceptance during the license renewal application (LRA) process.

Existing vs New AMPs:

Existing programs are programs at a NPP which are currently being implemented and very closely align with the AMP as described in the GALL Report. These existing site programs are credited as the LR AMP upon entering the period of extended operation (PEO). An existing site program can become an LR AMP with no changes or with enhancements and/or exceptions. Some examples of existing programs often credited for LR include: Underground Piping and Tanks, Flow Accelerated Corrosion, Fire Protection, and ASME Section XI, Subsection IWE.

New AMPs are created as a result of the LR integrated plant assessment (IPA) process to manage specific SSC’s and aging mechanisms that an existing plant program does not or cannot be modified to effectively meet the requirements or intent of a LR AMP as described in the GALL Report.

Enhancements are changes made to an existing plant program being credited as a license renewal AMP. These changes are made:

To ensure consistency with the ten elements of the generic AMP as described in the applicable GALL report, or
As a result of operating experience (OE) reviews.

Enhancements are annotated in the license renewal application (LRA) and in the Safety Evaluation Report (SER) issued by the US NRC. Typically, enhancements are treated as LR commitments.

Exceptions are intentional deviations from the generic ten elements of an AMP as described in the applicable GALL report. These deviations may be due to the unique configuration or design of a plant (e.g. equipment functions, plant layout, materials, environments, etc.) or the result of site specific OE. Exceptions are annotated in the LRA and in the Safety Evaluation Report (SER) issued by the US NRC.

GALL AMP Descriptions[edit]

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The GALL Report and its corresponding Standard Review Plan (SRP), issued by the US NRC, have gone through several revisions since their initial issuance in 2001. These documents essentially lay a framework for LR application development, and subsequently the development of AMPs. Like the guidance documents themselves, the AMPs have also evolved over time to incorporate items such as industry OE, revised codes and standards, and new aging mechanisms. The table below, contains the AMP descriptions contained in each GALL revision for both initial LR and subsequent LR (SLR).

Click here for information on AMPs with significant changes as a result of GALL revision.

Operating Experience[edit]

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To ensure adequate management of aging mechanisms, AMPs must exist in a constant feedback loop in which OE (industry and plant-specific) is reviewed, considered, and used to either improve the AMP or justify the existing conduct of the program.

NEI 14-12, “Aging Management Program Effectiveness” is the industry standard used to periodically assess the effectiveness of each plant AMP. AMP effectiveness reviews should be performed at a minimum recommended typical frequency of every five years within the period of extended operation (PEO). These self-performed effectiveness reviews/self-assessments typically coincide with and/or provide readiness for the US NRC IP-71003 - "Post-Approval Site Inspection for License Renewal" (Phase IV Inspection) conducted within the first five to ten years of the PEO.
NEI 14-13 “Use of OE for Age-Related Degradation and AMPs” details a methodology for screening and evaluating operating experience and incorporating this OE into an AMP, if deemed necessary. It also provides an industry approach for the review and sharing of OE pertaining to age-related degradation of SSC’s.
As newer revisions of the GALL report are issued, plants are responsible for identifying and evaluating “gaps” between the version of the GALL report that was the latest version when the initial AMP was developed, and the new standard set forth in the updated GALL report. AMPs may be revised if the latest version of the GALL report identifies changes that are appropriate for the plant. Note: GALL gap-analysis for a specific AMP can result in an increase or decrease in requirements for AMP implementation.

EPRI References for AMPs[edit]

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GALL-SLR AMPs	Key EPRI Guidance Documents	Title	Key ISG's
X.M2 - Neutron Fluence Monitoring			SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)
X.S1 - Concrete Containment Unbonded Tendon Prestress
X.E1 - Environmental Qualification (EQ) of Electric Components
XI.M1 - ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD	1019075	TR-105696-R12 (BWRVIP-03) Revision 12: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
XI.M2 - Water Chemistry	3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis	SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)
	3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8
	3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
XI.M3, "Reactor Head Closure Stud Bolting"
XI.M4, "BWR Vessel ID Attachment Welds"	1019075	TR-105696-R12 (BWRVIP-03) Revision 12: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
	1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
	1009948	BWRVIP-48-A: BWR Vessel and Internals Project, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines
	1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
	1008871	BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
	3002014434	BWRVIP-62-A (2018 Update): BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
XI.M7, "BWR Stress Corrosion Cracking"	1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
	1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
	1008871	BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
	3002014434	BWRVIP-62-A (2018 Update): BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
	TR-112076	Induction Heating Stress Improvement Effectiveness on Crack Growth in Operating Plants (BWRVIP-61)
	1012621	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules
XI.M8, "BWR Penetrations"	3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
	3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8
	1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
	1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
	1007279	BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines
	1009947	BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines
	1006602	BWRVIP-49-A: BWR Vessel and Internals Project, Instrument Penetration Inspection and Flaw Evaluation Guidelines
	1012120	BWRVIP-53-A: BWR Vessel and lnternals Project, Standby Liquid Control Line Repair Design Criteria
	3002020995	BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria
XI.M9, "BWR Vessel Internals"	1019075	TR-105696-R12 (BWRVIP-03) Revision 12: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
	3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
	3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8
	1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
	1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
	1008871	BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
	3002014434	BWRVIP-62-A (2018 Update): BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
	1009947	BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines
	3002020995	BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria
	1012837	BWRVIP-02-A: BWR Vessel and Internals Project, BWR Core Shrould Repair Design Criteria, Rev. 2
	1012113	BWRVIP-16-A: BWR Vessel and Internals Project, Internal Core Spraying Piping and Sparger Replacement Design Criteria
	3002008089	BWRVIP-18, Revision 2-A: BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines
	1012114	BWRVIP-19-A: BWR Vessel and Internals Project, Internal Core Spray Piping and Sparger Repair Design Criteria
	3002018310	BWRVIP-25, Rev. 1-A, BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines
	1009946	BWRVIP-26-A: BWR Vessel and Internals Project, BWR Top Guide Inspection and Flaw Evaluation Guidelines
	TR-108823	BWR Vessel and Internals Project: BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38)
	3002014254	BWRVIP-41, Revision 4-A BWR Vessel and Internals Project: Jet Pump Assembly Inspection and Flaw Evaluation Guidelines
	3002010548	BWRVIP-42, Revision 1-A: BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines
	1014352	BWRVIP-44-A: BWR Vessel and Internals Project: Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals
	TR-108707	BWR Vessel and Internals Project: Weldability of Irradiated LWR Structural Components (BWRVIP-45)
	1012115	BWRVIP-50-A: BWR Vessel and Internals Project, Top Guide/Core Plate Repair Design Criteria
	1012116	BWRVIP-51-A: BWR Vessel and Internals Project, Jet Pump Repair Design Criteria
	1012119	BWRVIP-52-A: BWR Vessel and Internals Project, Shroud Support and Vessel Bracket Repair Design Criteria
	1012118	BWRVIP-56-A: BWR Vessel and Internals Project, LPCI Coupling Repair Design Criteria
	1012618	BWRVIP-58-A: BWR Vessel and Internals Project, CRD Internal Access Weld Repair
	3002000650	BWRVIP-278: BWR Vessel and Internals Project, Technical Bases for Revision of the BWRVIP-76 Core Shroud Inspection Program
	1015457	BWRVIP-80-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Shroud Vertical Welds
	1016566	BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components
	3002010541	BWRVIP-139, Revision 1-A: BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines
	3002018319	BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables
	3002010551	BWRVIP-183-A: BWR Vessel and Internals Project, Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines
	3002013781	EPRI Materials Degradation Matrix, Revision 4
XI.M10, "Boric Acid Corrosion"
XI.M11B, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components (PWRs Only)"
XI.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)"	1019075	TR-105696-R12 (BWRVIP-03) Revision 12: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines	SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)
XI.M16A, "PWR Vessel Internals"	3002017168	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-A)
XI.M16A, "PWR Vessel Internals"	3002026460	Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5)
XI.M17, "Flow-Accelerated Corrosion"	3002000563	Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4)	LR-ISG-2012-01, Wall Thinning Due to Erosion Mechanisms
XI.M18, "Bolting Integrity"	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
XI.M18, "Bolting Integrity"	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
XI.M19, "Steam Generators"	3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8	LR-ISG-2011-02, Aging Management Program for Steam Generators LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components
	3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
	3002018267	Steam Generator Management Program: PWR Primary-to-Secondary Leak Guidelines-Revision 5
	3002020909	Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Revision 5
	3002007572	Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 8
	3002007856	Steam Generator Management Program: Steam Generator In Situ Pressure Test Guidelines, Revision 5
XI.M20, "Open-Cycle Cooling Water System"	3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8	LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
XI.M20, "Open-Cycle Cooling Water System"	3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
XI.M21A, "Closed-Cycle Cooling Water Systems"	3002000590	Closed Cooling Water Chemistry Guideline: Revision 2	LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)
XI.M22, "Boraflex Monitoring"	NP-6159	An Assessment of Boraflex Performance in Spent-Nuclear-Fuel Storage Racks
	1003413	Guidance and Recommended Procedures for Maintaining and Using RACKLIFE Version 1.10 Models
	TR-101986	Boraflex Test Results and Evaluation
	TR-103300	Guidelines for Boraflex Use in Spent-Fuel Storage Racks
XI.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems"
XI.M24, "Compressed Air Monitoring"	3002022576	Compressed Air Systems and Equipment Guide: Update and Consolidation of TR-108147 and 1006677	LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
XI.M25, "BWR Reactor Water Cleanup System"
XI.M26, "Fire Protection"
XI.M27, "Fire Water System"			LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
XI.M29, "Outdoor and Large Atmospheric Metallic Storage Tanks"			LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
XI.M30, "Fuel Oil Chemistry"			LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
XI.M31, "Reactor Vessel Material Surveillance"	Materials Reliability Program (MRP) - Materials Research Focus Area(MRFA)4- Low Alloy Steels Wiki	Materials Research Focus Area (MRFA)4 - Low Alloy Steels
	3002020910	Materials Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326, Revision 1)
	3002007964	Materials Reliability Program: PWR Supplemental Surveillance Program (PSSP) Capsule Fabrication Report (MRP-412)
	3002026457	Materials Reliability Program: Guidance on Timing for Technical Specification Revision Following Surveillance Capsule Testing (MRP-484)
XI.M32, "One-Time Inspection"	1019075	TR-105696-R12 (BWRVIP-03) Revision 12: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
XI.M33, "Selective Leaching"	TR-107514	Age-Related Degradation Inspection Method and Demonstration: In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application	LR-ISG-2011-03, Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, "Buried and Underground Piping and Tanks" LR-ISG-2015-01, Changes to Buried and Underground Piping and Tank Recommendations
XI.M35, "ASME Code Class 1 Small-Bore Piping"	3002007853	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 2)
XI.M35, "ASME Code Class 1 Small-Bore Piping"	1018330	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines -Supplemental Guidance (MRP-146S)
XI.M36, "External Surfaces Monitoring of Mechanical Components"	1007933	Aging Assessment Field Guide	LR-ISG-2011-03, Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, "Buried and Underground Piping and Tanks" LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation
	1009743	Aging Identification and Assessment Checklist: Mechanical Components
XI.M37, "Flux Thimble Tube Inspection"
XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"	1007933	Aging Assessment Field Guide	LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks
	1009743	Aging Identification and Assessment Checklist: Mechanical Components
XI.M39, "Lubricating Oil Analysis"
XI.M40, "Monitoring of Neutron-Absorbing Materials other than Boraflex"
XI.M41, "Buried and Underground Piping and Tanks"			LR-ISG-2011-03, Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, "Buried and Underground Piping and Tanks" LR-ISG-2015-01, Changes to Buried and Underground Piping and Tank Recommendations
XI.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"			LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)
XI.S1, "ASME Section XI, Subsection IWE"	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
XI.S1, "ASME Section XI, Subsection IWE"	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
XI.S2, "ASME Section XI, Subsection IWL"
XI.S3, "ASME Section XI, Subsection IWF"	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
XI.S3, "ASME Section XI, Subsection IWF"	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
XI.S5, "Masonry Walls"
XI.S6, "Structures Monitoring"	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
XI.S6, "Structures Monitoring"	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
XI.S8, "Protective Coating Monitoring and Maintenance"	1019157	Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102)
XI.E1, "Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	TR-109619	Guideline for the Management of Adverse Localized Equipment
XI.E2, "Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits"	TR-109619	Guideline for the Management of Adverse Localized Equipment
XI.E3A, "Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"	1013475	Plant Support Engineering: License Renewal Electrical Handbook	SLR-ISG-2021-04-ELECTRICAL, Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance
	3002010401	Long-Term Operations: Subsequent License Renewal Electrical Handbook
	TR-109619	Guideline for the Management of Adverse Localized Equipment
XI.E3B, "Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"			SLR-ISG-2021-04-ELECTRICAL, Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance
XI.E3C, "Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"	1013475	Plant Support Engineering: License Renewal Electrical Handbook	SLR-ISG-2021-04-ELECTRICAL, Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance
	3002010401	Long-Term Operations: Subsequent License Renewal Electrical Handbook
	TR-109619	Guideline for the Management of Adverse Localized Equipment
XI.E4, "Metal-Enclosed Bus"
XI.E5, "Fuse Holders"
' XI.E6, "Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	3002011484	Reliability and Maintenance of Bolted Busbar Connections
	1003471	Electrical Connector Application Guidelines
	TR-109619	Guideline for the Management of Adverse Localized Equipment
XI.E7, "High-Voltage Insulators"			SLR-ISG-2021-04-ELECTRICAL, Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance

International Aging Management Programs[edit]

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The proven international AMPs are collected by the IAEA Extrabudgetary Programme on International Generic Ageing Lessons Learned (IGALL ) for NPPs. The IGALL has used AMPs in the US NRC’s NUREG-1801 (GALL report) as a reference. IGALL has included aging management operating experience from other plants with different technologies (WWER, CANDU) than those already incorporated in NUREG-1801 (PWR and BWR). Furthermore, new AMPs focused on components (e.g., reactor coolant pump, pressurizer, safety related valves) have been introduced to reflect approaches to aging management followed in other countries. Owing to this, the IGALL offers more alternative AMPs for aging management of some selected components (e.g., a reactor coolant pump casing might be managed within the In-service Inspection AMP, or within a component specific AMP for Reactor Coolant Pumps). All IGALL AMPs can be found in the periodically updated database.

The IGALL has defined the following nine attributes of an effective AMP and it is recommended that all AMPs address these attributes:

Scope of the AMP based on understanding aging
Preventive actions to minimize and control aging effects
Detection of aging effects
Monitoring and trending of aging effects
Mitigation of aging effects
Acceptance criteria
Corrective actions
Operating experience feedback and feedback of research and development results
Quality management

Both the GALL and the IGALL reports define criteria for an effective AMP. Some differences in how these attributes are organized are as follows:

While the GALL report outlines 10 attributes/elements for an effective AMP, the IGALL has established only 9.
Attributes 8 (Confirmation process) and 9 (Administrative controls) from GALL report are covered by the attribute 9 from the IGALL (Quality management).
The GALL report defines attribute/element 3 (Parameters Monitored/Inspected) which is addressed in IGALL's attribute 3 on Detection of aging effects.
The IGALL defines attribute 5 (Mitigation of Aging Effects),however, the GALL report addresses mitigative actions across multiple “elements”; depending on the specific AMP.

IGALL AMPs that are NOT included in GALL[edit]

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The following table (current as of 9/5/24) provides an overview of IGALL AMPs that are not included in GALL report along with a brief description and some corresponding EPRI Guidance documents. The IGALL methodology includes active and passive components in the scope of aging management. Active components can be managed by IGALL AMPs or other appropriate tools. These components in their respected AMPs are marked in purple.

AMP	IGALL	Brief AMP description	REF. EPRI	TITLE EPRI
Reactor Coolant Pump	AMP138	The purpose of this AMP is to manage aging effects of loss of material due to wear, erosion, boric acid corrosion, general corrosion; cracking due to SCC or fatigue; and loss of fracture toughness due to thermal aging which can lead to the loss of intended function of reactor coolant pump components including its active components (e.g., rotating parts). The most adequate inspection and testing techniques to carry out are non-destructive methods such as visual examination, capillary test, dimensional control, ultrasonic examination, hardness measurements, He bubble test, pressure and tightness test. These inspections should be conducted periodically.
CANDU/PHWR Fuel Coolant Channels	AMP139	The aim of this AMP, devoted to PHWRs, is to manage aging effects of movement or shifting due to sustained vibratory loading, change in material properties due to hydrogen/deuterium uptake, neutron irradiation embrittelement, thermal aging; increase in flow resistance due to fouling; cracking due to fatigue, flow-induced vibration and delayed hydride cracking; change in material properties due to irradiation-assisted deformation that can lead to the loss of intended function of fuel coolant channels components. The most adequate inspection and surveillance techniques to carry out are inspection of the full volume of the tube, inside diameter measurements, direct measurement of PT-CT annular gap and monitoring of many important parameters such as irradiation induced dimensional changes, PT wall thinning, location of annulus spacers, and more. The frequency of the inspection depends on its type.
CANDU/PHWR Feeder Piping	AMP140	This AMP, devoted to PHWRs, is focused on management of aging effects of cumulative fatigue damage due to fatigue; increase in flow resistance due to fouling; loss of fracture toughness due to dynamic strain or thermal aging; cracking due to SCC; loss of material due to general corrosion, fretting, wear and wall thinning due to preferential weld attack that can lead to the loss of intended function of feeder piping in the primary heat transport system. The most adequate inspection and monitoring techniques to carry out to detect degradations mechanisms in feeders are NDEs, ultrasonic testing to measure remaining wall thickness, visual inspections and superficial techniques like liquid penetrant test, or magnetic particle test. These inspections should be conducted periodically.	1009561	Materials Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126)
CANDU/PHWR Reactor Assembly	AMP141	The purpose of this AMP, devoted to PHWRs, is to manage aging effects of loss of material due to cracking, erosion, general corrosion, flow-accelerated corrosion, crevice corrosion; cracking due to SCC, fatigue, flow-induced vibration; loss of fracture toughness due to neutron irradiation embrittlement; loss of leak tightness due to stress relaxation and loss of strength due to elastomer degradation that can lead to the loss of intended function of critical reactor assembly components. The most adequate inspection and techniques to carry out are visual and ultrasonic NDEs, gap measurements between PTs, gap measurements between CTs, measurements of the guide tube, and more addressed in the AMP. Many of these inspections can be conducted only during refurbishment and large scale fuel channel replacement outage after approximately 25-30 years of operation.
CANDU/PHWR Fuel Handling	AMP142	The aim of this AMP, devoted to PHWRs, is to manage aging effects of loss of material due to wear, erosion, corrosion; loss of fracture toughness due to neutron irradiation embrittlement; change in dimensions due to creep; cracking due to fatigue; loss of preload due to strees relaxation; and loss of toughness due to radiation damage. Those effects can lead to the loss of intended function of fuel handling systems of PHWR. The most adequate inspection techniques to carry out are visual inspections, and manual or physical manipulation of the material. These inspections should be conducted periodically.
Safety-related Valves	AMP143	This AMP, devoted to PHWRs, is focused on management of aging effects of loss of material due to erosion, wear, general corrosion, flow accelerated, pitting and crevice corrosion; wall thinning due to corrosion, erosion; cracking due to fatigue, hardening and loss of strength due to elastomer degradation that can lead to the loss of intended function of important to safety valves such as motor operated valves, air operated valves, solenoid operated valves, manual valves, check valves, pressure relief valves including their active parts (e.g., actuator). The most adequate inspection and testing techniques to carry out are pressure test, leak tightness test and nondestructive testing methods such as visual tests, dimension tests, screw joint tightening tests and liquid penetrant test. These inspections should be conducted periodically.
Safety-related Pumps	AMP144	The purpose of this AMP is to manage aging effects of loss of material due to erosion, wear, flow accelerated and general corrosion; cracking due to fatigue, SCC; wall thinning due to cavitation, corrosion and erosion that can lead to the loss of intended function of important to safety pumps such as centrifugal and positive displacement pumps, centrifugal horizontal-vertical pumps including their active parts (e.g., impeller). The most adequate inspection and testing techniques to carry out are nondestructive methods such as visual examination, ultrasonic examination, capillary test, or dimensional control. These inspections should be conducted periodically.	TR-107252	Centrifugal and Positive Displacement Charging Pump Maintenance Guide
CANDU/PHWR Moderator and Moderator Purification Heat Exchangers	AMP145	The aim of this AMP, devoted to PHWRs, is to manage aging effects of loss of material due to erosion, crevice corrosion, general corrosion, pitting, MIC, fretting; cracking due to SCC; cumulative fatigue damage due to fatigue and reduction in heat transfer due to fouling that can lead to the loss of intended function of heat exchangers of shell-and-tube type used in moderator system and moderator purification in PHWR. The most adequate inspection techniques to carry out are NDEs, visual, dimensional, surface and volumetric inspections; additionally leak testing of heat exchangers can be performed. The frequency of inspections is adjusted based on the results of degradation detected and in accordance with national regulations or governing documents.	1018089	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide
			PMBD	Preventive Maintenance Basis, Volume 32: Heat Exchangers – Tube Type
			1003320	Supplemental Guidance for Testing and Monitoring Service Water Heat Exchangers
			3002005340	Service Water Heat Exchanger Testing Guidelines
			NP-7552	Heat Exchangers Performance Monitor Guidelines
CANDU/PHWR Inspection Programmes	AMP146	This AMP, devoted to PHWRs, is focused on management of aging effects of loss of material due to wear, crevice corrosion, fouling, general corrosion, MIC, pitting; reduction in heat transfer due to fouling; cracking due to fatigue, PWSCC and SCC; increase in flow resistance due to fouling; loss of fracture toughness due to thermal aging; change in dimensions due to irradiation-induced creep; distortion due to swelling; wall thinning due to preferential weld attack; movement or shifting due to sustained vibratory loading that can lead to the loss of intended function of components of systems containing fluid that directly transports heat from nuclear fuel, systems essential for the safe shutdown, safe cooling system, or other systems whose failure could affect the integrity of the previously listed systems. The most adequate inspection techniques to carry out are NDEs such as visual, dimensional, surface and volumetric ones. Additionally, overall monitoring, leak detection, acoustic emission and strain measurement can be performed. These inspections should be conducted periodically.	3002013781	EPRI Materials Degradation Matrix, Revision 4
CANDU/PHWR Inspection Programmes	AMP146		3002000563	Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4)
Containment Bellows	AMP147	The purpose of this AMP is to manage aging effects of cracking due to vibrational fatigue and SCC and cumulative fatigue damage due to fatigue, which can lead to the loss of intended function of containment bellows. The most adequate inspection techniques to carry out are nondestructive examinations such are visual and surface inspections, Additionally, leak rate tests may be performed. The frequency of the inspections and leak testing is determined by the service and environmental conditions involved, degradations detected, and in compliance with other requirements.	1008035	Expansion Joint Maintenance Guide
CANDU/PHWR Reactor Shutdown Systems	AMP148	The aim of this AMP, devoted to PHWRs, is to manage aging effects of change in dimensions due to irradiation induced creep; cracking due to flow induced vibration and fatigue; loss of material due to wear, erosion, corrosion; distortion due to swelling; and loss of fracture toughness due to neutron irradiation embrittlement, These aging degradation mechanisms can lead to the loss of intended function of components of the reactor shutdown systems in PHWR. The most adequate inspection techniques to manage them are NDEs such as visual, dimensional, surface and volumetric inspections. Additionally, SDS-1 rod drop tests may be performed. These inspections should be conducted periodically.
CANDU/PHWR Heavy Water Management	AMP149	This AMP, devoted to PHWRs, is focused on management of aging effects of loss of material due to corrosion that can lead to the loss of intended function of components of heavy water collection, supply, vapor and liquid recovery systems to minimize heavy water leakages and losses. This program is based mainly on online tritium monitoring and chemistry monitoring complemented by plant system periodic inspections and walkdowns.
CANDU/PHWR Annulus Gas System	AMP150	In this AMP, the aging effects managed are loss of material due to corrosion or wear; loss of sealing function due to hardening; and cracking due to fatigue, which can lead to the loss of intended function of components of annulus gas system. This program is based mainly on monitoring of flow by each group of channels, dew point temperatures, concentrations of deuterium, oxygen and nitrogen and complemented by periodic maintenance of major components.
CANDU/PHWR Primary Heat Transport Instrument Tubing	AMP151	The purpose of this AMP devoted to PHWRs is to manage aging effects of loss of material due to fretting or wear, and cracking due to SCC and they can lead to the loss of intended function of instrument line tubing and transmitter impulse line tubing that contain primary heat transport coolant. The most adequate inspection techniques to carry out are visual inspections. These inspections should be conducted periodically.
WWER Reactor Pressure Vessel Surveillance	AMP152	The aim of this AMP, devoted to WWERs is to manage aging effects of loss of fracture toughness due to thermal aging and neutron irradiation embrittlement that can lead to the loss of intended function of reactor pressure vessel beltline. This AMP is a surveillance program based on surveillance of the representative limiting materials of the reactor pressure vessel by testing of irradiated capsules.
WWER Main Gate Valves	AMP153	This AMP, devoted to WWERs, is focuses on management of aging effects of cracking due to SCC; loss of fracture toughness due to thermal aging; cumulative fatigue damage due to fatigue; loss of preload due to gasket creep, self-loosening, thermal effects and loss of material due to boric acid corrosion. These aging effects can lead to the loss of intended function of main gate valves including their active parts (e.g., actuator). The most adequate inspection and testing techniques to manage them are NDEs such as visual inspections, dimension control, ultrasonic inspection, and dye penetrant, pressure and tightness tests. These inspections should be conducted periodically.
PWR Pressurizer	AMP154	In this AMP, the aging effects managed are loss of material due to boric acid corrosion; cracking due to fatigue and SCC, that can lead to the loss of intended function of components of pressurizer. The most adequate inspection and testing techniques to carry out are nondestructive methods such as visual examination, capillary test, dimensional control and ultrasonic examination. These inspections should be conducted periodically.
PWR Residual Heat Removal Heat Exchangers	AMP155	The purpose of this AMP is to manage aging effects of loss of preload due to stress relaxation; cracking due to SCC and fatigue; loss of material due to crevice corrosion, erosion, general corrosion, fretting, wear; reduction in heat transfer due to fouling that can lead to the loss of intended function of shell-and-U-tube heat exchangers of residual heat removal system. The most adequate inspection techniques to carry out are NDEs such as visual, dimensional, surface and volumetric inspections; additionally, leak-testing can be performed. These inspections should be conducted periodically.	1018089	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide
			PMBD	Preventive Maintenance Basis, Volume 32: Heat exchangers Condition Assessment Program
			NP-7552	Heat Exchanger Performance Monitoring Guidelines
PWR Main Coolant Piping	AMP156	The aim of this AMP is to manage aging effects of loss of fracture toughness due to thermal aging, cracking due to SCC, cumulative fatigue damage due to fatigue. Those can lead to the loss of intended function of main coolant piping. The most adequate inspection techniques to carry out are visual, dye penetrant, ultrasonic inspections and magnetic particle method. These inspections should be conducted periodically.
Passive Hydrogen Recombiiners	AMP158	The objetive of this AMP is to address the aging effects of loss of material due to general corrosion, pitting corrosion or wear, and reduction of hydrogen recombining capacity due to fouling. Those can lead to the loss of intended function of hydrogen recombiners. Periodic functional test and visual inspection are performed to detect the mentioned aging effects.	3002013781	EPRI Materials Degradation Matrix, Revision 4
PWR Emergency Core Cooling System Hydro-accumulators	AMP159	This AMP is focused on management of aging effects of loss of material due to pitting, crevice, general and boric acid corrosion and those can lead to the loss of intended function of components of emergency core cooling system hydro-accumulators. The most adequate inspection and testing techniques to carry out are visual, dimensional control, ultrasonic inspections and penetration tests to detect surface cracks. These inspections should be conducted periodically.	3002013781	EPRI Materials Degradation Matrix, Revision 4
PWR Reactor Pressure Vessel	AMP162	In this AMP, the aging effects managed are loss of fracture toughness due to thermal aging and neutron irradiation embrittlement; loss of material due to boric acid, wear, crevice and pitting corrosion; cracking due to fatigue and SCC; cumulative fatigue damage due to fatigue; crack growth due to cyclic loading. Those can lead to the loss of intended function of reactor vessel, flange joint, upper and bottom heads and RPV control rod drive mechanism and bottom-mounted instrumentation nozzles. The most adequate inspection techniques to manage them are visual inspection, dye penetrant, magnetic particle, eddy current, or ultrasonic testing. These inspections should be conducted periodically.	3002016009	Materials Reliability Program: Effects of Thermal Ageing on Reactor Coolant System Pressure Boundary Materials (MRP-438), Low Alloy Ferritic Steels
PWR Reactor Pressure Vessel	AMP162		3002017168	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-A)
Dissimilar Metal Welds	AMP163	The purpose of this AMP is to manage aging effects of loss of material due to boric acid corrosion; cracking due to SCC or fatigue; cumulative fatigue damage due to fatigue; and loss of fracture toughness due to thermal aging. Those can lead to the loss of intended function of dissimilar welds. The most adequate inspection techniques to carry out are visual, dye penetrant, eddy current, or volumetric ultrasonic testing. These inspections should be conducted periodically.	3002013781	EPRI Materials Degradation Matrix, Revision 4
			1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
			1012621	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules
			1015009	MRP-139 Revision 1: Primary System Piping Butt Welds Inspection and Evaluation Guideline
			1006603	Materials Reliability Program: GE Experience Report on Cracking in Alloy 182 (MRP-57): BWR Alloy 182 Stress Corrosion Cracking
			1003523	Materials Reliability Program: A Review of Thermal Aging Embrittlement in Pressurized Water Reactors (MRP-80)
			1021023	Materials Reliability Program: Primary Water Stress Corrosion Cracking (PWSCC) Flaw Evaluation Guidance (MRP-287)
			3002012244	Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds, Revision 3
			1015400	Materials Reliability Program: Advanced FEA Evaluation of Growth of Postulated Circumferential PWSCC Flaws in Pressurizer Nozzle Dissimilar Metal Welds (MRP-216, Rev. 1)
			1009378	Materials Reliability Program: Welding Residual and Operating Stresses in PWR Alloy 182 Butt Welds (MRP-106)
			1009549	Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for U.S. PWR Plant Designs (MRP-113)
			1009559	Materials Reliability Program: Evaluation of the Effect of Weld Repairs on Dissimilar Metal Butt Welds (MRP-114)
			1009805	Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for US PWR Plant Designs: Babcock & Wilcox Design Plants (MRP-112)
			1006696	Materials Reliability Program: Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115)
			1009806	Materials Reliability Program: Probabilistic Risk Assessment of Alloy 82/182 Piping Butt Welds (MRP-116)
Outdoor Piping, Tanks and Structures	AMP164	The aim of this AMP is to manage aging effects of loss of material due to fouling, wear, crevice, general, MIC, pitting corrosion; loss of preload due to self-loosening, gasket creep, thermal effects; and cracking due to SCC. These aging effects can lead to the loss of intended function of ferrous and non-ferrous alloy above ground outdoor piping, tanks, structures and their supports. The most adequate inspection techniques to identify and manage them are volumetric examination methods, physical measurements for detecting changes in dimension, ultrasonic testing and visual examinations. These inspections should be conducted periodically.	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
Outdoor Piping, Tanks and Structures	AMP164		3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Essential Chillers	AMP165	This AMP is focused on management of the aging effects of mechanical parts of centrifugal essential chillers used in NPPs. The management of ageing of electrical and electronic devices of essential chillers is addressed in AMP212, AMP215, AMP217, AMP218 and TLAA201. The aging effects managed are cracking due to fatigue; loss of material due to corrosion and wear; loss of sealing function due to hardening; bearing failure and fatigue due to excessive vibration; reduced heat transfer capability and differential pressure increase due to fouling; increase in flow resistance due to fouling due to corrosion and wear which will lead to reduced cooling capbility, their intended function. This AMP includes preventive actions based on chemical and vibration monitoring and tube cleaning. The most adequate inspection and testing techniques to carry out are external and internal visual inspections and eddy current testing. In addition, operator rounds and systems performance are used too. These inspections should be conducted periodically.	1015075	Plant Support Engineering: Life Cycle Management Planning Sourcebooks - Chillers
Dry Storage Cask System	AMP166	The aim of this AMP is to manage aging effects of loss of material due to general, pitting, crevice corrosion; cracking due to SCC. These aging effects can lead to the loss of intended function of metallic components of a dry cask storage systems of various designs in dry storage facilities. The most adequate inspection techniques to identify and manage them are visual inspections, surface and volumetric examinations. For sites conducting a canister examination, there is usually a minimum of one canister examined at each site. Preference is usually given to the canisters with the greatest susceptibility for localized corrosion or SCC. Remote visual examinations of outer surfaces are performed for all accessible dry storage casks. These inspections should be conducted periodically.	3002013781	EPRI Materials Degradation Matrix, Revision 4
Oil-Immersed Power Transformers Not Subject to Equipment Qualification Requirements	AMP211	The described AMP211 aims to ensure the intended safety functions of non-grid connected plant distribution oil-cooled transformers throughout the end of service life. It focuses on monitoring components subject to age-related thermal degradation resulting in reduced insulation resistance, or increased resistance of connection due to corrosion or loosening, or loss of sealing. The AMP implements preventive actions and detection methods, including periodic visual inspections, dissolved gas analysis, periodic electrical testing and monitoring and trending of winding and oil temperatures.	1016301	Power Transformer Guidebook: The "Copper Book"
			1013566	Plant Support Engineering: Large Transformer End-of-Expected-Life Considerations and the Need for Planning
			1025261	Plant Engineering: Medium-Voltage Transformer End of Expected Life Guidance
			3002000753	On-Line Monitoring Diagnostic Analysis for Large Power Transformers
Electrical Enclosures Not Subject to Equipment Qualification Requirements	AMP212	This AMP is focused on management the age-related degradation effects such as loss of material, loss of preload, and loss of sealing functions on electrical enclosures. The program entails visual inspections of both internal and external surfaces, with the inspection frequency determined by the type of electrical enclosure and operational experience. Visual inspections cover 100 percent of accessible component surfaces. Manual or physical manipulation of at least 10 percent of the available surface area can be used to enhance visual inspection, ensuring the absence of hardening or loss of strength in elastomers and flexible polymeric materials. Preventive measures include maintaining specified environmental conditions.	1007933	Aging Assessment Field Guide
	AMP212		1009743	Aging Identification and Assessment Checklist: Mechanical Components
Whiskers and Capacitors with Liquid Electrolyte	AMP213	The described AMP213 focuses on periodic inspections to identify aging effects in electronic and electrical equipment caused by whiskers and degradation of capacitors with liquid electrolyte. Whiskers can only be detected through regular visual inspections using a microscope with at least 10 times magnification and suitable lighting. Aging progress of capacitors is monitored by periodic measurement of residual capacity or direct capacitance measurement. Under certain construction circumstances, the equivalent series resistance of capacitors may also be periodically measured. Generally, after 7-9 years of operation, these measurements are recommended annually. If measurements are not feasible, replacement every 9 to 15 years is probably the only solution to address aging process.	1008166	Guidelines for the Monitoring of Aging of I&C Electronic Components
Electrical Insulation of Rotating Electrical Machines and Actuators Not Subject to Equipment Qualification Requirements	AMP214	This AMP aims to ensure that the insulation function of rotating electrical machine and actuators components remains consistent with the current licensing basis throughout their operational lifetime. Degradation mechanisms such us reduced insulation resistance and loss of dielectric strength, can weaken insulation materials. The program involves periodic visual inspections to detect surface anomalies in insulation materials. Insulation diagnosis for a component is done regularly. For medium voltage components, it confirms no major change in insulation characteristics, involving electrical and mechanical diagnosis. Electrical diagnosis may cover insulation resistance, polarization index, dielectric strength, alternating current, tan delta, and partial discharge testing.	1014908	Guide for Rotating Machine Stator Winding Hipot Testing
			3002016077	Medium-Voltage Motor and Cable, Very-Low-Frequency (VLF) Tan Delta Testing from the Cable Termination: VLF Motor and Cable Testing
			1007423	Life Cycle Management Planning Sourcebooks, Volume 5: Main Generator
			1003095	Electric Motor Tiered Maintenance Program
Switchgears, Breakers, Distribution Panels, Contactors, Protection Relays, Relays Not Subject to Equipment Qualification Requirements	AMP215	The AMP215 is focused on identify age-related degradation in indoor low and medium voltage switchgears and active components (e.g., protection relay) typically found in switchgear cabinets. The aging effects that this AMP manage are increase in resistance of connection, loss of electrical function, loss of material, loss of mechanical function, reduction of insulation, characteristic change, contact sticking and increase in friction. Periodic visual inspections, including cleaning and thermography, are conducted to ensure the proper functioning of components. Thermography is utilized to detect high-resistance connections or abnormal heating patterns across all accessible components and connections. Airborne acoustic testing may be employed in medium voltage switchgear to identify discharges. Preventive maintenance on breakers is carried out periodically according to manufacturer recommendations, and functional tests are performed on breakers and protection relays based on the same guidelines. Surveillance testing is conducted to assess the safety functions of switchgear and its components.	1007933	Aging Assessment Field Guide
			1013457	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide
			1011223	Aging Identification and Assessment Checklist: Electrical Components
Lead Batteries Not Subject to Environmental Qualification Requirements	AMP216	This AMP outlines an aging management program for wet cell lead batteries used in standby operation, parallel to rectifier units, within nuclear power plants. The program focuses on visual inspections, surveillance tests, and monitoring of battery voltage, current, and room temperature to detect aging effects resulting in decreased capacity due to corrosion or chemical processes as well as leakage due tp cracking. Periodic testing, including capacity tests, is conducted out every 1-5 years.
Sensors and Transmitters Not Subject to Equipment Qualification Requirements	AMP217	The described AMP217 is a condition monitoring program for I&C sensors and transmitters crucial for safety functions but not part of the Environmental Qualification (EQ) program in NPPs. Preventive actions are limited to periodic replacement of consumables, and detection of aging effects, such as characteristic change, degradation of electronic components, loss of sealing function, loss of vibration alarm or indication, loss of winding temperature indication, and reduction in insulation, are managed carrying out techniques like calibration, component installation verification, visual inspection, and response time testing. The program includes periodic visual inspection as part of periodical walkdowns of each system or during routine maintenance tasks, periodic calibration determined and venturi fouling observation by trending independent plan parameters.	1008166	Guidelines for the Monitoring of Aging of I&C Electronic Components
			1003568	Collected Field Data on Electronic Part Failures and Aging in Nuclear Power Plant Instrumentation and Control (I&C) Systems
			NP-7121	Technical Guidance for Detection of Oil-Loss Failure of Rosemount Pressure Transmitters
			1021429	Nuclear Maintenance Applications Center: Guidelines for the Maintenance Management of Plant Sensors
			TR-100514-V2	Survey and Characterization of Feedwater Venturi Fouling at Nuclear Power Plants: Volume 2: Photomicrograph and Chemical Analyses
Electronic Equipment Not Subject to Equipment Qualification Requirements	AMP218	This AMP outlines a program to maintain electronic equipment installed in I&C systems with respect to IEC 62342, focusing on mitigating environmental conditions, detecting failure mechanisms, and predicting end-of-life for critical components. It addresses preventing generic failure mechanisms from affecting safety and managing limitations due to obsolescence and physical aging. The program includes tasks for the establishment of an aging data base such as identifying critical components, conducting functional tests, failure analysis, evaluating residual lifetime, environmental monitoring, and performing visual inspections. Aging effects such as characteristic change, degradation of electronic components, increase in resistance of connection, loss of electrical function and reduction in insulation resistance are detected through periodic visual inspections, and in-situ testing or periodic electrical measurements. Environmental conditions are measured and tracked during a mid/long-term period. Periodic electric measurements and visual inspections are implemented to identify electronic components experiencing failures, which are then documented in a database.	1008166	Guidelines for the Monitoring of Aging of I&C Electronic Components
			1011709	Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants
			1003568	Collected Field Data on Electronic Part Failures and Aging in Nuclear Power Plant Instrumentation and Control (I&C) Systems
			1022246	Guidance for Aging Management of Instrumentation and Control (I&C) Circuit Cards and Components Based on Electricite de France (EDF)Experience
Fuses Not Subject to Equipment Qualification Requirements	AMP219	The AMP219 is focused on managing the aging effects of fuses installed to ensure their intended functions are maintained throughout their operational lifetime. It addresses aging effects such as characteristic change or loss of electrical function due to due to electrical transients, elevated temperature or thermal cycling. Periodic resistance testing during manufacturing ensures fuse acceptability. Aged fuse populations undergo cycling tests within national regulations, verifying they don't open unexpectedly. Following cycling, an overcurrent test confirms proper fuse response. Testing applies to a representative sample designated by the NPP; extensions occur if negative OPEX is found. Failure rates are monitored to identify the most common fuse failures. Fuses operated at under 60% of their rated current may have an indefinite lifetime, a factor to consider when selecting fuses.
Lightning Protection, Grounding Grid and Surge Arresters Not Subject to Equipment Qualification Requirements	AMP220	The purpose of this AMP is to manage aging effects of cracking, loss of material properties due to surge or voltage spike; increase in resistance of connection due to corrosion, surge, or voltage spike; loss of electrical function due to corrosion, fatigue which can lead to the loss of intended function of lightning protection, grounding systems, and medium voltage and high voltage surge arresters. The most adequate inspection techniques to carry out are low ohmic resistance measurements of all connections attached to the protective equipotential bonding, control of earth-termination system, visual inspections of all accessible parts of lightning protection and grounding systems. Medium voltage and high voltage arresters can be inspected by non-invasive thermographic surveys and visual inspections of accessible parts. These inspections should be performed periodically. Inspections should be complemented by online monitoring of selected paramaters, such as leakage currents to ground.	1013457	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide
			3002018920	Surge Arresters—Mechanical and Aging Testing
			1026664	Nuclear Maintenance Applications Center: Switchyard Equipment Application and Maintenance Guide
Fiber Optic Cables and Connections not Subject to Equipment Qualification Requirements	AMP222	AMP222 focuses on ensuring the proper functioning of fiber optic cables and connections exposed to adverse localized environments (high temperature, radiation, moisture, wear, and chemicals) without environmental qualification requirements. The program implements condition monitoring to detect aging effects, such as loss of signal, loss of mechanical properties, loose connection, increased signal time dispersion, increased attenuation, hardening or loss of strength and decrease in optical power transmission. The program includes periodic visual inspections and signal transmission performance evaluations.
Electrical Insulation for Medium Voltage Shielded Cables and Connections Not Subject to Equipment Qualification Requirements	AMP223	The AMP223 focuses on effectively managing aging effects on the electrical insulation of medium voltage shielded cables and connections exposed to adverse localized environments (temperature, radiation, significant moisture, wear, and or chemical). Preventive measures include maintaining thermal insulation (accessible cables) and periodic drainage of accumulated water (inaccessible cables). Through detection and monitoring techniques such as periodic visual inspections, infrared thermography or tan testing, the program aims to prevent premature failures in medium voltage cable circuits due to cracking, discoloration, elastomer degradation, embrittlement, hardening or loss of strength, loss of dielectric, loss of mechanical properties, reduction in insulation resistance or swelling. For cables in service, testing is recommended before the first failure or after 15-20 years of service. Subsequent tests occur every 6-10 years, with no 25% grace period allowed for longer intervals. All cables under the aging management program are tested at least once before extended operation, and then every 6-10 years thereafter.	TR-109619	Guideline for the Management of Adverse Localized Equipment
			1021070	Medium Voltage Cable Aging Management Guide, Revision 1
			3002000557	Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1
			1024044	Aging Power Cable Maintenance Guideline
			1022969	Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants
			3002000576	Long-Term Operations Program: Assessment of Research and Development Supporting Aging Management Programs for Long-Term Operation
			1022968	Plant Engineering: Cable Aging Management Program Implementation Guidance
			1008560	Equipment Failure Model and Data for Underground Distribution Cables: A PM Basis Application
			1011873	Cable Polymer Aging and Condition Monitoring Research at Sandia National Laboratories Under the Nuclear Energy Plant Optimization (NEPO) Program
Electrical Motors not Subject to Equipment Qualification	AMP224	The AMP 224 addresses the aging of motors in NPPs, its subcomponents and support structures, focusing on both large and small motors. It recognizes the environmental stressors faced by these motors, including radiation, temperature, humidity, and vibration. The aging effects this AMP manages are bearing failures, increased heating in stator core, loss of insulation or reduced insulation resistance, loss of vibration alar or indication, loss of winding temperature indication, motor failure, rotor heating, and stator heating. Different strategies for detecting aging effects are provided, such as comparative surge tests, motor circuit analysis, internal visual inspection, visual or borescope inspection, vibration monitoring, bearing temperature monitoring, periodic checks of lube oil system parameters, polarization index checks, and motor circuit analysis.	NP-7502	Electric Motor Predictive and Preventive Maintenance Guide
Fans Used in I&C and Power Electronics Cabinets	AMP226	AMP226 outlines that fans used in Instrumentation and Control (I&C) or power electronics cabinets intended functions are maintained in line with the CLB throughout their operational lifetime. Fans exposed to indoor controlled air are susceptible to calibration drift, degradation of electronic components, loss of mechanical function, polymer degradation or winding/coil failure. As a basic preventive measure, normal environmental condition is respected, and cabinet’s air filters are cleaned or replaced periodically. Periodic visual inspections and surveillance tests are regularly conducted to detect potential anomalies.	PMBD	EPRI Preventive Maintenance Basis Database (PMBD), Inverter template
Low-Voltage Coils of Control Rod Drive System Not Subject to Equipment Qualification Requirements	AMP227	The purpose of this AMP is to manage aging effects of reduced insulation resistance due to thermal degradation of organic material, embrittlement, degradation caused by ohmic heating; coil failure due to fatigue of conductor material that can lead to the loss of intended function of low voltage coils of control rod drive system. This AMP is based on condition monitoring of electrical properties such as insulation resistance measurement and measurement of coil resistance.
Capacitor Voltage Transformer Not Subject to Equipment Qualification Requirements	AMP228	The aim of this AMP is to manage aging effects of loss of dielectric strength due to ohmic heating, moisture intrusion; reduced insulation resistance due to ohmic heating and thermal degradation of organic materials; loss of sealing function due to moisture intrusion, erosion; winding/coil failure due to ohmic heating. These aging effects can lead to the loss of intended function of capacitor voltage transformers. The most adequate techniques to identify and manage them is monitoring of selected parameters. For some electrical parts of the capacitor voltage transformers, an oil and dissolve gas analysis shall be performed.
Power Transformer Tap-Changers Not Subject To Equipment Qualification Requirements	AMP229	AMP229 focuses on ensuring the proper functions of on-load tap-changers (OLTC) associated with oil-immersed transformers. This AMP covers OLTCs found on oil-immersed transformers e.g. generator transformers, auxiliary power transformers, or standby auxiliary power transformers. The aging effects managed are loss of mechanical function due to overload or wear of pivots and linkages; loss of electrical function due to ohmic heating or abrasion of contacts; loss of dielectric stenght due to moisture or chemical degradation of oil, or due to presence of moisture or suface contamination. This AMP focuses on the demands for the inspections and the surveillance test programme which should be conducted periodically. In addition, routine oil sample checks are also applicable to the OLTCs as well as infrared thermography of the diverter and selector compartments.	1012350	New Equipment and Performance Design Review - LTC Management Course Materials
			1002048	Development of a Filter Using Absorbent Technologies for the Removal of Coking Precursors: Laboratory Evaluation
			1011708	Development of a New Acoustic Emissions Technique for the Detection and Location of Gassing Sources in Power Transformers and LTCs: Phase 2 Results
			1016261	Load Tap Changer Management Seminar
			1001946	Development of Load Tap Changer Monitoring Technique: Mechanism of Coking
Generators for Emergency Diesel Generator Systems not Subject to Equipment Qualification Requirements	AMP230	The aim of this AMP is to manage aging effects of bearing failures due to mechanical vibration, loss of lubrication, surface contamination or chemical contamination; loss of mechanical function due to fatigue, vibration, surface contamination, elevated temperature, moisture intrusion, corrosion, overload; rotor heating due to thermal degradation of organic materials or mechanical vibration; reduced insulation resistance and/or loss of dielectric strength due to thermal degradation of organic materials, moisture and debris intrusion, surface contaminants. These agings effects can lead to the loss of intended function of generators of emergency diesel generators. The most adequate techniques to identify and manage them are vibration and parameter monitoring, thermography, electrical tests, visual inspections, or borescope inspections. These inspections should be conducted periodically.	3002005014	Generator Maintenance Guide for Emergency Diesel Generators
			3002005014	Generator Maintenance Guide for Emergency Diesel Generators
			3002000742	On-Line Monitoring of Emergency Diesel Generators
Isolated Phase Bus Not Subject To Equipment Qualification Requirements	AMP231	The purpose of this AMP is to manage internal and external aging effects of isolated phase bus components. The aging effects managed are hardening, loss of strength due to moisture intrusion, surface contamination or thermal degradation of organic materials; loss of sealing due to moisture intrusion; loss of material due to corrosion; reduced insulation resistance and/or dielectric strength due to moisture and debris intrusion, surface contamination, thermal degradation of organic materials; loss of mechanical function due to thermal fatigue or vibrational fatigue; increased resistance due to loosening of bolted connections, significant ohmic heating, electrical transients, vibration, contamination, corrosion or oxidation; cracking due to fatigue; and loss of electrical function due to electrical transients or thermal cycling. The most adequate inspection and testing techniques to carry out are visual inspection, thermographic inspections, ultrasonics and electrical test. These inspections should be conducted periodically.	1015057	Nuclear Maintenance Applications Center: Isolated Phase Bus Maintenance Guide
			3002026348	Guideline for System Monitoring by System Engineers
			3002012582	Infrared Thermography Guide
			1013457	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide
Non-metallic Liner	AMP309	This AMP is focused on management of aging effects of damage due to irradiation, loss of sealing function due to abrasions, adhesion loss, blister, burns, cracks, cuts, delamination, tears; premature local failure due to irradiation, reduction in leak tightness due to irradiation and chemical evolution of the product with time that can lead to the loss of intended function of non-metallic liners of concrete containment structures. The most adequate inspection and testing techniques to carry out are visual inspection and leak rate test. These inspections should be conducted periodically.
Ground Movement due to Expansive Soils	AMP310	In this AMP, the aging effects managed are cracking and distortion due to increase in stress levels from settlement; reduction of strength and mechanical properties of concrete due to irradiation; cracking due to differential settlement, erosion of porous concrete; reduction in foundation strength due to differential settlement, erosion of porous concrete sub-foundation; increase in porosity and permeability due to leaching of calcium hydroxide; and tilt mechanism due to differential settlement or heave effect from expansive soil. These effects can lead to the loss of intended function of all structures and components included in the scope of AMP302, AMP305, AMP307, AMP318 and AMP319. This AMP is based on monitoring of the ground movements by, for example, topographic leveling gauges, or extensometers embedded deep into the ground.
Containment Monitoring System	AMP311	The purpose of this AMP is to manage aging effects of failure of monitoring in concrete structure due to corrosion, component rupture or excess concrete strain, lack of electrical continuity, mechanical dislocation; and loss of prestress due to creep, elevated temperature, relaxation, shrinkage. Those can lead to the loss of intended function of monitoring system components installed in concrete structure. This AMP is based on periodic testing of vibrating wire strain gauges. The electrical systems dedicated to concrete strain and temperature are continuously monitored. In case of pendulums and invar wires, an inspection in accessible areas is suggested.	3002007819	Program on Technology Innovation: Retrofitted Sensors for Nuclear Containment Structures
Concrete Expansion Detection and Monitoring System	AMP312	This AMP is focused on management of aging effects of cracking due to aggressive chemical attack and corrosion of embedded steel and distortion due to increase in stress levels from settlement; increase in porosity and permeability due to aggressive chemical attack; loss of material due to aggressive chemical attack and corrosion of embedded steel; building deformation due to alkali-aggregate reaction or delayed ettringite formation; concrete expansion and cracking due to alkali-aggregate reaction or delayed ettringite formation; cracking and distortion due to increase in stress levels from settlement; loss of bond due to corrosion of embedded steel; reduction in concrete anchor capacity due to local concrete degradation, service-induced cracking or other concrete degradation mechanisms. These effects can lead to the loss of intended function of all concrete structures that are initially inspected in accordance with AMP302, AMP307 and AMP318, and determined to have cracking patterns that may indicate the presence of alkali aggregate reaction or delayed enttringite formation. The most adequate inspection techniques to carry out are visual inspections and expansion monitoring based on strain measurements.	3002005389	Tools for Early Detection of ASR in Concrete Structures
			3002007806	Concrete Nondestructive Evaluation for Damage Due to Pattern Cracking - Alkali Silica Reaction and Freeze-Thaw Damage
			3002016056	Long-Term Operations: Aging Management of Concrete Structures Affected by Alkali-Silica Reaction
			3002010300	Mitigation and Repair of Concrete Structures Affected by Alkali-Silica Reaction (ASR)
Containment Prestressing System	AMP313	In this AMP, the aging effects managed are loss of prestress due to creep, elevated temperature, relaxation, shrinkage; loss of strength due to creep shrinkage; and loss of material due to corrosion. Those can lead to the loss of intended function of components of prestressing system of prestressed concrete containments. The most adequate periodic testing techniques to carry out are lift-off tests, measurements of strains, displacements of the containment structure measured during periodic containment pressure tests. The parameters monitored are the containment tendon pre-stressing forces in accordance with AMP302.
Seismic Isolation	AMP314	The purpose of this AMP is to manage aging effects of delamination of the elastomer from the reinforcing steel plate due to cracking of polymer material or loss of adhesion from steel plate; increase in rigidity of aseismic bearing supports due to polymer aging; loss of material due to cracking, crumbling and erosion of polymer; and loss of material due to corrosion of steel plates of aseismic bearing. Those effects can lead to the loss of intended function of aseismic bearings. The most adequate inspection techniques to carry out are visual inspections complemented by mechanical tests on representative samples. These inspections should be conducted periodically.
Spent Fuel Pool	AMP315	This AMP is focused on management of aging effects of cracking due to fatigue or SCC; loss of material due to crevice, general, pitting corrosion, or defects of material surface layer due to chemical attack; and welding imperfection propagation due to thermal cyclic loading. Those can lead to the loss of intended function of spent fuel and fuel handling pools with stainless steel liners. The most adequate inspection techniques to carry out are visual inspection of accessible parts, remote visual inspections. Leak tightness can be monitored by data obtained from leakage collection systems. These inspections should be conducted periodically.
Subsurface Engineered Backfill Materials	AMP316	In this AMP, the aging effects managed are changes in mechanical properties due to chemical degradation, dynamic loads and other phenomena; and changes in chemical properties due to chemical degradation, leaching and other phenomena of subsurface engineered backfill material, which can lead to the loss of intended function of embedded structures. The AMP consists of periodic in-situ tests on engineered backfill in which the foundations of nuclear safety related structures are embedded. In-situ tests are supplemented by conducting mechanical tests and visual inspections on representative samples.
Settlement of Structures	AMP317	The purpose of this AMP is to manage aging effects of cracking of concrete structures due to displacement of the settlement that can lead to the loss of intended function of civil structures from groups 1 to 9, containment structures and their component supports. The most adequate testing techniques are tests carried out on sands, clays, rocks. Moreover, visual inspections within cracking monitoring program can verify whether the cracks in concrete structures are active or passive.	1015078	Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools)
Vibration and Cyclic Loading on Civil Structures	AMP320	The aim of this AMP is to manage aging effects of cracking due to cyclic loading, cracking, cumulative fatigue damage, loss of leak tightness, loss of material properties and plate bulging, that can lead to the loss of intended function of concrete and non-concrete structures, structural components, component supports, and structural commodities subjected to vibration and cyclic loads. The most adequate periodic inspection, monitoring and surveillance techniques to carry out are visual inspections and monitoring of selected parameters.	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1
Vibration and Cyclic Loading on Civil Structures	AMP320		3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Monitoring of Concrete Structures During Delayed Construction	AMP321	This is a plant specific AMP developed to ensure that the prolonged delays in the construction of an NPP do not result in irreversible or irreparable dagames of civil structures and civil components. The purpose of this AMP is to manage aging effects of cracking due to corrosion of embedded steel, differential settlement, erosion settlement, creep, freeze and thaw-frost action, aggressive chemical attack, shrinkage; expansion and cracking due to reaction with aggregate or delayed ettringite formation; loss of material due to corrosion of embedded steel, aggressive chemical attack; increase in porosity and permeability due to aggressive chemical attack; loss of strength due to leaching of calcium hydroxide and carbonation that can lead to the loss of intended function of concrete structures and masonry block walls, constructed completely or partially. The most adequate inspection techniques to carry out are periodic visual inspections.	3002013084	Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools)
			3002007799	Field Guide: Visual Inspection of Concrete Structures in the Nuclear Fleet
			1025627	Program on Technology Innovation: Nondestructive Evaluation Inspection of Concrete Structures Subjected to Corrosion
			1023006	Advanced Nuclear Technology: Embedded Sensors in Concrete
			3002007810(Archived)	Program on Technology Innovation: Assessment of Software Platforms for Aging Management of Large Civil Structures
			3002003090(Archived)	Corrosion Mitigation of Conventionally Reinforced Concrete Structures
Preservation of Non-Concrete Structures During Delayed Construction	AMP322	The purpose of this AMP is to manage aging effects of cracking due to SCC; loss of material due to general, galvanic, crevice, pitting, MIC corrosion; and change in material properties due to ultraviolet radiation, ozone and thermal exposure, which can lead to the loss of intended function of non-concrete structures and components in a condition of delayed construction. This is a condition monitoring program that consists of monitoring of selected parameters by periodic visual inspections, supplemented as needed by nondestructive tests and other methods.	1025323	Field Guide: Coatings Assessment
	AMP322		1015078	Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools)
Spent Fuel Dry Storage Concrete Structures	AMP323	This AMP applies to interim spent fuel dry storage concrete structures above ground. The aim of this AMP is to manage aging effects of cracking, loss of material, ingress of harmful substances, reduction in concrete pH due to leaching of calcium hydroxide, concrete carbonation, corrosion of rebar, fatigue due to cyclical loading, vibration and thermal cycling, irradiation of concrete, loss of pre-stressing force, radiation dose rate, thermal and pressure transients, boron depletion, creep and erosion. The monitoring of chemical composition of groundwater and movement and settlement are covered in AMP318, AMP307 and AMP317. The most adequate periodic inspection is visual inspection and it is supplemented using non-destructive test as well as laboratory test and analyses on samples. In addition, radiation surveys may also be performed to monitor radiation shielding effectiveness, as applicable.
Inaccessible Areas	AMP324	This is a plant specific AMP developed for the nuclear power structures and structural components that are inaccessible for periodic inspection. The significant ageing effects are loss of material due to general corrosion and pitting, cracking due to freeze-thaw, cracking due to expansive reactions in concrete, increase in porosity and permeability due to leaching of calcium hydroxide and carbonation in inaccessible areas of structural elements of concrete and steel containments. The monitoring of groundwater chemistry should be carried out periodically to assess its impact on the structures. The most adequate inspection techniques to carry out are improved routine and in-depth examination techniques, such as non-contact NDT, embedded wireless sensors and NDT techniques with higher penetration. In addition, optical aids, such as fiberscopes and borescopes even video cameras, allow inspection of inaccessible regions.

IGALL AMPs that are also included in the GALL[edit]

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The IGALL AMPs that are also included in the GALL report, along with corresponding EPRI Guidance documents, are listed in the following table:

AMP	IGALL	REF. EPRI	TITLE EPRI	Note
Low Cycle Fatigue Monitoring	AMP101	3002000684	Materials Reliability Program: Thermal Fatigue Licensing Basis Monitoring Guideline MRP-149, Revision 1
Low Cycle Fatigue Monitoring	AMP101	3002016012	Materials Reliability Program: Thermal Fatigue Monitoring Guidelines MRP-32, Revision 2
In-service Inspection/Periodic Inspection	AMP102	3002013781	EPRI Materials Degradation Matrix, Revision 4
		3002010268	Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175, Revision 1)
		3002018319	BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables
Water Chemistry	AMP103	3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
		3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8
		3002017199	BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
BWR Vessel ID Attachment Welds	AMP105	1009948	BWRVIP-48-A: BWR Vessel and Internals Project, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines
		3002018321	BWRVIP-48, Revision 2: BWR Vessel and Internals Project: Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines
		3002002623	style="text-align:left;" \| BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
		3002013026	BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
		1016566	BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components
		3002023756	BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components	Revision 1 (3002008388(Archived)) is referenced in the IGALL AMP.
		3002003103	Models of Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments: Volume 1: Disposition Curves Development; Volume 2: Disposition Curves Application
BWR Stress Corrosion Cracking in Coolant Pressure Boundary Components	AMP107	1012621	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules
		3002013781	EPRI Materials Degradation Matrix, Revision 4
		3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		3002017199	BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
		1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
		3002016000	Materials Handbook for Nuclear Plant Pressure Boundary Applications (2019)	2018 Revision (3002012420(Archived)) referenced in the IGALL AMP.
		3002005474	Irradiation-Assisted Stress Corrosion Cracking (IASCC) Initiation Model for Stainless Steels	Validation of Stress Corrosion Cracking Initiation Model for Stainless Steel and Nickel Alloys (1025121(Archived)) is referenced in the IGALL AMP.
		3002018002	Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 2 (MRP-448)
BWR Penetrations	AMP108	1007279	BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines
		3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
		3002013026	BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
		1016566	BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components
		3002023756	BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components
		3002005474	Irradiation-Assisted Stress Corrosion Cracking (IASCC) Initiation Model for Stainless Steels	Validation of Stress Corrosion Cracking Initiation Model for Stainless Steel and Nickel Alloys (1025121(Archived)) is referenced in the IGALL AMP.
		3002018002	Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 2 (MRP-448)
		1009947	BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines
		1006602	BWRVIP-49-A: BWR Vessel and Internals Project, Instrument Penetration Inspection and Flaw Evaluation Guidelines
		1008871	BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
		TR-106712	BWR Vessel and Internals Project: Role/Expansion Repair of Control Rod Drive and In-Core Instrument Penetrations in BWR Vessels (B WRVIP-17)
		1012120	BWRVIP-53-A: BWR Vessel and lnternals Project, Standby Liquid Control Line Repair Design Criteria
		3002020995	BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria
		1016586	BWRVIP-146NP, Revision 1: BWR Vessel and Internals Project, Technical Basis for ASME Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive Bottom Head Penetrations in BWRs"
BWR Vessel Internals	AMP109	1012837	BWRVIP-02-A: BWR Vessel and Internals Project, BWR Core Shrould Repair Design Criteria, Rev. 2
		1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
		3002023756	BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components
		1007279	BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw EvaluationGuidelines
		1009947	BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines
		1008871	BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
		3002020995	BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria
		3002008095	TR-105696-R19 (BWRVIP-03) Revision 19: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
		1012113	BWRVIP-16-A: BWR Vessel and Internals Project, Internal Core Spraying Piping and Sparger Replacement Design Criteria
		3002008089	BWRVIP-18, Revision 2-A: BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines
		1012114	BWRVIP-19-A: BWR Vessel and Internals Project, Internal Core Spray Piping and Sparger Repair Design Criteria
		3002018310	BWRVIP-25, Rev. 1-A, BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines	Revision 1 (3002005594(Archived)) is also referenced in the IGALL AMP.
		1009946	BWRVIP-26-A: BWR Vessel and Internals Project, BWR Top Guide Inspection and Flaw Evaluation Guidelines
		TR-108823	BWR Vessel and Internals Project: BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38)
		3002003093	BWRVIP-41, Revision 4: BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines
		3002010548	BWRVIP-42, Revision 1-A: BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines
		1014352	BWRVIP-44-A: BWR Vessel and Internals Project: Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals
		TR-108707	BWR Vessel and Internals Project: Weldability of Irradiated LWR Structural Components (BWRVIP-45)
		1012115	BWRVIP-50-A: BWR Vessel and Internals Project, Top Guide/Core Plate Repair Design Criteria
		1012116	BWRVIP-51-A: BWR Vessel and Internals Project, Jet Pump Repair Design Criteria
		1012119	BWRVIP-52-A: BWR Vessel and Internals Project, Shroud Support and Vessel Bracket Repair Design Criteria
		1012118	BWRVIP-56-A: BWR Vessel and Internals Project, LPCI Coupling Repair Design Criteria
		1012618	BWRVIP-58-A: BWR Vessel and Internals Project, CRD Internal Access Weld Repair
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
		3002013026	BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment
		3002014434	BWRVIP-62-A (2018 Update): BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection
		3002000650	BWRVIP-278: BWR Vessel and Internals Project, Technical Bases for Revision of the BWRVIP-76 Core Shroud Inspection Program	BWRVIP-76, Revision 2: BWR Vessel and Internals Project, BWR Core Shroud Inspection and Flaw Evaluation Guidelines (3002003095(Archived)) is referenced in IGALL AMP
		1015457	BWRVIP-80-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Shroud Vertical Welds
		3002010552	BWRVIP-84, Revision 3: BWRVIP Vessel and Internals Project, Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components
		3002005568	BWRVIP-97, Revision 1: BWR Vessel and Internals Project, Guidelines for Performing Weld Repairs to Irradiated BWR Internals
		1016566	BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components
		3002023754	BWRVIP-138, Revision 2: BWR Vessel and Internals Project—Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines	Revision 1-A (1025139(Archived)) is referenced in IGALL AMP
		3002010541	BWRVIP-139, Revision 1-A: BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines
		3002018319	BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables
		3002018312	BWRVIP-180, Revision 1: BWR Vessel and Internals Project-Access Hole Cover Inspection and Flaw Evaluation Guidelines	Initial version (1013402(Archived)) is referenced in IGALL AMP
		3002005567	BWRVIP-181, Revision 2: BWR Vessel and Internals Project, Steam Dryer Repair Design Criteria
		1020802	BWRVIP-182-A: BWR Vessel and Internals Project, Guidance for Demonstration of Steam Dryer Integrity for Power Uprate
		3002010551	BWRVIP-183-A: BWR Vessel and Internals Project, Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines
		3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		3002010550	BWRVIP-234-A: BWR Vessel and Internals Project, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steels for BWR Internals
		3002012535	BWRVIP-315: BWR Vessel and Internals Project, Reactor Internals Aging Management Evaluation for Extended Operations
PWR Boric Acid Corrosion	AMP110	1025145	Materials Reliability Program: Boric Acid Corrosion Guidebook, Revision 2: Managing Boric Acid Corrosion Issues at PWR Power Stations (MRP-058, Rev 2)
PWR Cracking of Nickel Alloy Reactor Coolant Pressure Boundary Components	AMP111	1016591	Materials Reliability Program: Safety Evaluation for Boric Acid Wastage of PWR Reactor Vessel Bottom Heads Due to Bottom-Mounted Nozzle Leakage (MRP-167)
		1025145	Materials Reliability Program: Boric Acid Corrosion Guidebook, Revision 2: Managing Boric Acid Corrosion Issues at PWR Power Stations (MRP-058, Rev 2)
		1015009	MRP-139 Revision 1: Primary System Piping Butt Welds Inspection and Evaluation Guideline
		3002014244	Materials Reliability Program: Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-Wall Alloy 600 Materials and Alloy 82, 182, and 132 Welds (MRP-420, Revision 1)
		3002010756	Materials Reliability Program: Recommended Factors of Improvement for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) Growth Rates of Thick-Wall Alloy 690 Materials and Alloy 52, 152, and Variants Welds (MRP 386)
Thermal Ageing Embrittlement of Cast Austenitic Stainless Steel	AMP112	3002005571	TR-105696-R18 (BWRVIP-03) Revision 18: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines
	AMP112	3002010675	BWRVIP-03, Revision 20: BWR Vessel and Internals Project-Reactor Pressure Vessel and Internals Examination Guidelines
PWR Vessel Internals	AMP113	3002026460	Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5)	Revision 4 (3002018245(Archived)) is reference in IGALL AMP
		3002020105	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2)	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines MRP-227-A (1022863(Archived)) is also referenced in the IGALL In addition EPRI submits a bienial letter to US NRC detailing MRP-227-A results for the previous 24 months.
		3002017168	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-A)
		3002003083	Materials Reliability Program: Improvement of the Cluster Dynamics Model for the Prediction of Void Swelling in Austenitic Stainless Steel (MRP-391)
		3002010268	Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175, Revision 1)	Initial Revision (1012081(Archived)) is also referenced in the IGALL AMP
Flow Accelerated Corrosion and Erosion	AMP114	3002008071	Flow-Accelerated Corrosion in Power Plants: Revision 2
		3002000563	Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4)
		3002023786	Recommendations for an Effective Program Against Erosive Attack: Revision 1	Initial Revision (3002005530(Archived)) is referenced in the IGALL AMP
		3002010594	CHECWORKS™ Steam/Feedwater Application Guidelines for Plant Modeling and Evaluation of Component Inspection Data: Revision 1
Bolting Integrity	AMP115	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Degradation and Failure of Bolting in Nuclear Power Plants (NP-5769(Archived)) is referenced in the IGALL AMP
Bolting Integrity	AMP115	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Steam Generators	AMP116	3002020909	Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Revision 5	Revision 4 (3002007571(Archived)) is referenced in the IGALL AMP
		3002007572	Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 8
		3002007856	Steam Generator Management Program: Steam Generator In Situ Pressure Test Guidelines, Revision 5	Revision 4 (1025132(Archived)) is referenced in the IGALL AMP
		3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
		3002010645	Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8
		LR-ISG-2016-01(No longer an EPRI maintained document)	Changes to Aging Management Guidance for Various Steam Generator Components	Changes to Aging Management Guidance for Steam Generator Chanel Head Components (SGMP-IL-16-02(Archived)) is reference in the IGALL AMP but has since been transferred to NRC as LR-ISG-2016-01
		3002002850	Steam Generator Management Program: Investigation of Crack Initiation and Propagation in the Steam Generator Channel Head Assembly
		3002018267	Steam Generator Management Program: PWR Primary-to-Secondary Leak Guidelines-Revision 5	Revision 4 (1022832(Archived)) is referenced in the IGALL AMP
Closed Treated Water Systems	AMP117	3002000590	Closed Cooling Water Chemistry Guideline: Revision 2
Reactor Vessel Surveillance	AMP118	3002018322	Materials Handbook for Nuclear Plant Pressure Boundary Applications (2020)	Application of Master Curve Fracture Toughness Methodology for Ferritic Steels (PWRMRP-01): PWR Materials Reliability Project (PWRMRP), Final Report (TR-108390-R1(Archived)) is also referenced in the IGALL AMP Materials Reliability Program: Developing on Embrittlement Trend Curve Using the Charpy “Master Curve” Transition Reference Temperature (MRP-289) (1020703(Archived)) is also referenced in the IGALL AMP
		3002016008	Technical Basis for ASME Code Case N-830-1, Revision 1 (MRP-418, Revision 1): Direct Use of Master Curve Fracture Toughness for Pressure-Retaining Materials of Class 1 Vessels, Section XI
		3002003040	Materials Reliability Program: Development of a T0-Based Embrittlement Trend Curve and Comparison With the Charpy Master Curve Embrittlement Trend Curve (MRP-389)
		3002023871	Materials Reliability Program: Technical Basis and Implied Margins of ASME Code, Section XI, Appendix G (MRP-450, Revision 1): Fracture Toughness Criteria for Protection Against Failure
		3002013223	Materials Reliability Program: Consolidated Fracture Toughness Models for Ferritic RPV Steels (MRP-432)
		1025144	BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan
One-time Inspection	AMP119	3002010675	BWRVIP-03, Revision 20: BWR Vessel and Internals Project-Reactor Pressure Vessel and Internals Examination Guidelines
		3002026460	Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5)	Revision 3 (3002010399(Archived)) is referenced in the IGALL AMP
		1022931	Nondestructive Evaluation: Update on License Renewal One Time Inspection and Best NDE Practices
Selective Leaching	AMP120	TR-107514	Age-Related Degradation Inspection Method and Demonstration: In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application
		3002013168	Nondestructive Evaluation: Guidance for Conducting Ultrasonic Examinations for the Detection of Selective Leaching
		3002016057	Selective Leaching: State-of-the-Art Technical Update
		1018939	Nondestructive Evaluation: NDE for Selective Leaching of Gray Cast Iron Components
		1019111	Nondestructive Evaluation: Update to NDE for Selective Leaching of Gray Cast Iron Components
		1025218	Nondestructive Evaluation: Correlation of Selectively Leached Thickness to Hardness for Gray Cast Iron and Brass
		1010639	Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools
		3002008013	Assessment of Available Nondestructive Evaluation Techniques for Selective Leaching: Technology Review
		3002020830	Ultrasonic NDE Techniques for Detection of Selective Leaching in Complex Shaped Gray Cast Iron Components
		3002020832	Electromagnetic NDE Techniques for Detection of Selective Leaching in Gray Cast Iron Piping
		3002020713	Leveraging Risk Insights for Aging Management Program Implementation: 2022	Initial revision (3002018403(Archived)) is referenced in IGALL AMP
		3002020822	Accelerated Testing and Evaluation of Factors Affecting Selective Leaching Susceptibility
One-time Inspection of Class 1 Small Bore Piping	AMP121	3002007853	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 2)
		1018330	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines -Supplemental Guidance (MRP-146S)
		3002013099	BWRVIP-196, Revision 1: BWR Vessel and Internals Project: Assessment of Mixing Tee Thermal Fatigue Susceptibility in BWR Plant
		3002013098	BWRVIP-155, Revision 1: BWR Vessel and Internals Project: Evaluation of Thermal Fatigue Susceptibility in BWR Stagnant Branch Lines
		1003666	Materials Reliability Program: Lessons Learned from PWR Thermal Fatigue Management Training (MRP-83)
		3002000505	Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2
		3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
Open Cycle Cooling Water System	AMP124	1010059	Service Water Piping Guideline
		1008282	Life Cycle Management Sourcebook for Nuclear Plant Service Water Systems
		NP-4582	A Study of Microbiologically Influenced Corrosion in Nuclear Power Plants and a Practical Guide for Countermeasures
Buried and Underground Piping and Tanks	AMP125	3002004395	Nondestructive Evaluation: Buried Pipe NDE Reference Guide—Revision 3	Nondestructive Evaluation: Remote Field Technology Assessment for Piping Inspection, Including Buried and Limited Access Components (1021153(Archived)) is also reference in the IGALL AMP
		3002010027	Nondestructive Evaluation: Assessment and Development of Buried Pipe NDE Technology, Revision 1
		1025231	Nondestructive Evaluation: Buried Pipe In-Line NDE Depth Sizing Procedure
		3002008032	Development and Evaluation of Guided Wave Structural Health Monitoring for Buried Pipe
		3002000468	Obtaining Credit for Guided Wave as a Buried Pipe Direct Examination
		1019115	Buried Pipe Guided Wave Examination Reference Document
		3002018352	Recommendations for an Effective Program to Control the Degradation of Buried and Underground Piping and Tanks (1016456, Revision 2)
		3002002949	Recommendations for Managing an Effective Cathodic Protection System
Boraflex Monitoring	AMP126	NP-6159	An Assessment of Boraflex Performance in Spent-Nuclear-Fuel Storage Racks
		TR-101986	Boraflex Test Results and Evaluation
		TR-103300	Guidelines for Boraflex Use in Spent-Fuel Storage Racks
		1003413	Guidance and Recommended Procedures for Maintaining and Using RACKLIFE Version 1.10 Models
		1019110	Handbook of Neutron Absorber Materials for Spent Nuclear Fuel Transportation and Storage Applications
Compressed Air Monitoring	AMP128	3002022576	Compressed Air Systems and Equipment Guide: Update and Consolidation of TR-108147 and 1006677	This document is the current revision of: Instrument Air System: A Guide for Power Plant Maintenance Personnel (NP-7079(Archived)) and Compressor and Instrument Air System Maintenance Guide: Revision to NP-7079 (TR-108147(Archived)) which are referenced in the IGALL AMP
BWR Reactor Water Cleanup System	AMP129	1012621	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules
		3002002623	BWRVIP-190 Revision 1: BWR Vessel and Internals Project, Volume 1: BWR Water Chemistry Guidelines - Mandatory, Needed, and Good Practice Guidance and Volume 2: BWR Water Chemistry Guidelines - Technical Basis
		1016569	BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
Fuel Oil Chemistry	AMP133	1015061	Nuclear Maintenance Applications Center: Guide for the Storage and Handling of Fuel Oil for Standby Diesel Generator Systems, Revision 3
		3002010609	Storage and Use of Low-Concentration (5%) Biodiesel Blends in Nuclear Plant Emergency Diesel Generators
		TR-104843	Winterizing Diesel Fuel
External Surfaces Monitoring of Mechanical Components	AMP134	1007933	style="text-align:left;" \| Aging Assessment Field Guide
		1009743	Aging Identification and Assessment Checklist: Mechanical Components
		3002011822	Long-Term Operations: Subsequent License Renewal Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools
Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components	AMP135	1009743	Aging Identification and Assessment Checklist: Mechanical Components
CANDU/PHWR Feeder Piping	AMP140	1009561	Materials Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126)
Safety Related Pumps	AMP144	TR-107252	Centrifugal and Positive Displacement Charging Pump Maintenance Guide
CANDU/PHWR Moderator and Moderator Purification Heat Exchangers	AMP145	1018089	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide	Heat exchangers: Over of Maintenance and Operation (TR-106741(Archived)) is referenced in the IGALL AMP
		PMBD	Preventive Maintenance Basis, Volume 32: Heat Exchangers – Tube Type	Preventive Maintenance Basis, Volume 32: Heat Exchangers – Tube Type (TR-106857(Archived)) is referenced in the IGALL AMP
		1003320	Supplemental Guidance for Testing and Monitoring Service Water Heat Exchangers	Balance-of-Plant Heat Exchanger Condition Assessment and Inspection Guide (TR-108009(Archived)) is referenced in the IGALL AMP
		3002005340	Service Water Heat Exchanger Testing Guidelines
		NP-7552	Heat Exchangers Performance Monitor Guidelines
CANDU/PHWR Inspection Programmes	AMP146	3002000563	Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4)
CANDU/PHWR Inspection Programmes	AMP146	3002013781	EPRI Materials Degradation Matrix, Revision 4
Containment Bellows	AMP147	1008035	Expansion Joint Maintenance Guide
PWR Residual Heat Removal Heat Exchangers	AMP155	1018089	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide	Heat exchangers: Over of Maintenance and Operation (TR-106741(Archived)) is referenced in the IGALL AMP
		PMBD	Preventive Maintenance Basis, Volume 32: Heat Exchangers	Preventive Maintenance Basis, Volume 32: Heat Exchangers – Tube Type (TR-106857(Archived)) is referenced in the IGALL AMP
		NP-7552	Heat Exchanger Performance Monitoring Guidelines
Internal Coatings and Linings	AMP157	1019157	Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102)
PWR Emergency Core Cooling System Hydro-Accumulators	AMP159	3002013781	EPRI Materials Degradation Matrix, Revision 4
High Cycle Fatigue Monitoring	AMP161	3002016011	Materials Reliability Program: Temperature Monitoring Data Evaluation for Reactor Coolant System Branch Lines Subject to Thermal Fatigue (MRP-365, Revision 1)
		3002007853	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 2)
		3002013099	BWRVIP-196, Revision 1: BWR Vessel and Internals Project: Assessment of Mixing Tee Thermal Fatigue Susceptibility in BWR Plant
		1022563	Materials Reliability Program: Thermal Fatigue Monitoring Guidelines (MRP-32, Revision 1)
		3002017285	NDE Technology for Detection of Thermal Fatigue Damage in Piping, MRP-23 Revision 3
		3002018246	Materials Reliability Program: Fatigue Management Handbook (MRP-235, Revision 3)
		3002023891	Materials Reliability Program: Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR Plants (MRP-192, Revision 4)	Revision 3 (3002013266(Archived)) is referenced in the IGALL AMP
		3002013098	BWRVIP-155, Revision 1: BWR Vessel and Internals Project: Evaluation of Thermal Fatigue Susceptibility in BWR Stagnant Branch Lines
		3002013263	Materials Reliability Program: Operating Experience Regarding Thermal Fatigue of Piping Connected to PWR Reactor Coolant Systems (MRP-85, Revision 2)
PWR Reactor Pressure Vessel	AMP162	3002016009	Materials Reliability Program: Effects of Thermal Ageing on Reactor Coolant System Pressure Boundary Materials (MRP-438), Low Alloy Ferritic Steels
PWR Reactor Pressure Vessel	AMP162	3002017168	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-A)
Dissimilar Metal Welds	AMP163	1006603	Materials Reliability Program: GE Experience Report on Cracking in Alloy 182 (MRP-57): BWR Alloy 182 Stress Corrosion Cracking
		3002013781	EPRI Materials Degradation Matrix, Revision 4
		1014874	BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals
		1012621	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules
		1015009	MRP-139 Revision 1: Primary System Piping Butt Welds Inspection and Evaluation Guideline
		1003523	Materials Reliability Program: A Review of Thermal Aging Embrittlement in Pressurized Water Reactors (MRP-80)
		1021023	Materials Reliability Program: Primary Water Stress Corrosion Cracking (PWSCC) Flaw Evaluation Guidance (MRP-287)
		3002012244	Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds, Revision 3
		1015400	Materials Reliability Program: Advanced FEA Evaluation of Growth of Postulated Circumferential PWSCC Flaws in Pressurizer Nozzle Dissimilar Metal Welds (MRP-216, Rev. 1)	Initial revision (1015383(Archived)) is referenced in IGALL AMP
		1009378	Materials Reliability Program: Welding Residual and Operating Stresses in PWR Alloy 182 Butt Welds (MRP-106)
		1009549	Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for U.S. PWR Plant Designs (MRP-113)
		1009559	Materials Reliability Program: Evaluation of the Effect of Weld Repairs on Dissimilar Metal Butt Welds (MRP-114)
		1009805	Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for US PWR Plant Designs: Babcock & Wilcox Design Plants (MRP-112)
		1006696	Materials Reliability Program: Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115)
		1009806	Materials Reliability Program: Probabilistic Risk Assessment of Alloy 82/182 Piping Butt Welds (MRP-116)
Outdoor Piping, Tanks and Structures	AMP164	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Good Bolting Practices: A Reference Manual for Nuclear Power Plant Maintenance Personnel, Volume 1: Large Bolt Manual (NP-5067(Archived)) is referenced in the IGALL AMP
Outdoor Piping, Tanks and Structures	AMP164	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Electrical Insulation for Electrical Cables and Connections Not Subject to Equipment Qualification Requirements	AMP201	TR-109619	Guideline for the Management of Adverse Localized Equipment
		TR-017218-R1	Guideline for Sampling in the Commercial-Grade Item Acceptance Process
		1021070	Medium Voltage Cable Aging Management Guide, Revision 1
		3002000557	Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1
		1024044	Aging Power Cable Maintenance Guideline
		1022969	Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants
		TR-107514	Age-Related Degradation Inspection Method and Demonstration: In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application
		3002010641	Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1
Electrical Insulation for Electrical Cables and Connections Not Subject to Equipment Qualification Requirements Used in Instrumentation Circuits	AMP202	TR-110379	High Range Radiation Monitor Cable Study: Phase I
		TR-109619	Guideline for the Management of Adverse Localized Equipment
		3002010641	Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1
		TR-112582	High Range Radiation Monitor Cable Study: Phase II
Electrical Insulation for Inaccessible Instrumentation and Control and Low and Medium Voltage Power Cables Not Subject to Equipment Qualification Requirements	AMP203	3002007991	Plant Engineering: Low-Voltage Cable Susceptibility to Wet Aging
		TR-109619	Guideline for the Management of Adverse Localized Equipment
		1021070	Medium Voltage Cable Aging Management Guide, Revision 1
		3002000557	Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1
		1022969	Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants
		3002010641	Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1
		1025262	Plant Engineering: Evaluation and Insights from Nuclear Power Plant Tan Delta Testing and Data Analysis
		3002000576	Long-Term Operations Program: Assessment of Research and Development Supporting Aging Management Programs for Long-Term Operation
Metal Enclosed Bus Not Subject to Equipment Qualification Requirements	AMP204	1013457	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide
Electrical Cable Connections Not Subject to Equipment Qualification Requirements	AMP206	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Initial version (1015336(Archived)) is referenced in the IGALL AMP
High Voltage Insulators and Transmission Conductors	AMP208	3002026920	Overhead Transmission Inspection, Assessment, and Asset Management Reference Guide—2023	Parameters that Influence the Aging and Degradation of Overhead Conductors (1001997(Archived)) is referenced in the IGALL AMP
		1000174	Oconee Electrical Component Integrated Plant Assessment and Time Limited Aging Analyses for License Renewal: Revision 1
		3002010401	Long-Term Operations: Subsequent License Renewal Electrical Handbook
Condition Monitoring of Electrical and I&C Cables Subject to Equipment Qualification Requirements	AMP210	1021067	Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1
		1021070	Medium Voltage Cable Aging Management Guide, Revision 1
		3002000557	Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1
		1024044	Aging Power Cable Maintenance Guideline
		1022969	Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants
		3002010641	Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1
		1008211	Initial Acceptance Criteria Concepts and Data for Assessing Longevity of Low-Voltage Cable Insulations and Jackets
		1015209	Plant Support Engineering: Line Impedance Resonance Analysis for the Detection of Cable Damage and Degradation
		1001391	Training Aids for Visual / Tactile Inspection of Electrical Cables for Detection of Aging
		TR-106687	Cable Aging Management Program for D.C. Cook Nuclear Plant Units 1 and 2
		3002012582	Infrared Thermography Guide	Previous revision (1006524(Archived)) is referenced in the IGALL AMP
		1022968	Plant Engineering: Cable Aging Management Program Implementation Guidance
		3002005322	Plant Engineering: Cable Polymer Handbook - Medium Voltage Insulations
		3002010591	Effects of 0.1 Hertz Withstand Testing on Medium-Voltage Cable Insulation
		3002018283	A Review of Equipment Aging Theory and Technology: Revision 1 of NP-1558
Equipment Qualification Preservation and Reassessment	AMP221	3002010401	Long-Term Operations: Subsequent License Renewal Electrical Handbook
Equipment Qualification Preservation and Reassessment	AMP221	1021067	Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1
Fans Used in I&C and Power Electronics Cabinets	AMP226	PMBD	“EPRI Preventive Maintenance Basis Database (PMBD)”, Inverter template
In-service Inspection for Containment Steel Elements	AMP301	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Degradation and Failure of Bolting in Nuclear Power Plants (NP-5769(Archived)), Good Bolting Practices: A Reference Manual for Nuclear Power Plant Maintenance Personnel, Volume 1: Large Bolt Manual (NP-5067(Archived)), and Bolted Joint Maintenance and Applications Guide (TR-104213(Archived)) are referenced in the IGALL AMP.
		3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
		TR-114881	Aging Effects for Structures and Structural Components (Structural Tools): B&W Owners Group Generic License Renewal Program, BAW-2279P, 1997
		3002013084	Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools)
		TR-104514	How to Conduct Material Condition Inspections: September, 1994
Safety Class 1, 2 and 3 Piping and Metal Containment Components Supports	AMP303	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Degradation and Failure of Bolting in Nuclear Power Plants (NP-5769(Archived)), Good Bolting Practices: A Reference Manual for Nuclear Power Plant Maintenance Personnel, Volume 1: Large Bolt Manual (NP-5067(Archived)), and Bolted Joint Maintenance and Applications Guide (TR-104213(Archived)) are referenced in the IGALL AMP.
	AMP303	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Masonry Walls	AMP305	3002013084	Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools)
Water Control Structures	AMP307	3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Good Bolting Practices: A Reference Manual for Nuclear Power Plant Maintenance Personnel, Volume 1: Large Bolt Manual (NP-5067(Archived)), and Bolted Joint Maintenance and Applications Guide (TR-104213(Archived)) are referenced in the IGALL AMP.
Water Control Structures	AMP307	3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
Protective Coating Monitoring and Maintenance Programme	AMP308	1025323	Field Guide: Coatings Assessment
Protective Coating Monitoring and Maintenance Programme	AMP308	1019157	Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102)
Concrete Structures Monitoring	AMP318	1011224	Aging Identification and Assessment Checklist: Civil and Structural Components
Concrete Structures Monitoring	AMP318	1007933	Aging Assessment Field Guide
Non-concrete structures monitoring	AMP319	1007933	Aging Assessment Field Guide
		3002015824	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1	Degradation and Failure of Bolting in Nuclear Power Plants ((Archived)), Good Bolting Practices: A Reference Manual for Nuclear Power Plant Maintenance Personnel, Volume 1: Large Bolt Manual (NP-5067(Archived)), and Nuclear Maintenance Applications Center: Bolted Joint Fundamentals (1015336(Archived)) are referenced in the IGALL AMP
		3002023823	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061
		1011224	Aging Identification and Assessment Checklist: Civil and Structural Components

Record of Revisions[edit]

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Number	Date	Description of Changes
0	6/11/2024	Initial version

Aging Management Programs (AMPs)

Contents

10 Element Approach[edit]

GALL AMP Descriptions[edit]

Operating Experience[edit]

EPRI References for AMPs[edit]

International Aging Management Programs[edit]

IGALL AMPs that are NOT included in GALL[edit]

IGALL AMPs that are also included in the GALL[edit]

Record of Revisions[edit]

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Aging Management Programs (AMPs)

10 Element Approach[edit]

GALL AMP Descriptions[edit]

Operating Experience[edit]

EPRI References for AMPs[edit]

International Aging Management Programs[edit]

IGALL AMPs that are NOT included in GALL[edit]

IGALL AMPs that are also included in the GALL[edit]

Record of Revisions[edit]

Navigation menu

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