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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 in the US or the LTO assessment internationally.

GALL vs IGALL Elements of an Effective Aging Management Program[edit]

GALL	IGALL
Whether generic or plant-specific, the GALL defines an effective aging management program consists of the following ten elements:	The IGALL has defined the following nine attributes of an effective AMP and it is recommended that all AMPs address these attributes:
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	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.

Aging Management Programs in the GALL[edit]

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In the United States the US NRC previously approved generic AMP descriptions as acceptable approaches to aging management and included those AMPs 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.

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.

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.

Enhancements and Exceptions[edit]

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Enhancements are changes made to an existing plant program being credited as a license renewal AMP. Enhancements to the existing plant program may be needed for the following reasons:

Activities or recommendations in the GALL program are not currently in place as part of the existing program. Therefore, the existing program must be enhanced to ensure consistency with the ten elements of the generic AMP as described in the applicable GALL report, or
To address unique site-specific operating experience for which the underlying assumptions of the generic GALL program may not account for.

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. The regulator will review these exceptions on a case-by-case basis and dispositions of acceptance are documented in the Safety Evaluation Report (SER) issued by the US NRC.

Aging Management Programs in the IGALL[edit]

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Internationally, the proven international AMPs are collected by the IAEA Extrabudgetary Programme on International Generic Ageing Lessons Learned (IGALL) for NPPs. The IGALL's approach to aging management is consistent with the US NRC’s NUREG-1801 (GALL report) which was used as a reference. The IGALL is reviewed and updated periodically as appropriate. Additionally, the 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.

US GALL[edit]

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.

Interim Staff Guidance (ISG) Affecting AMPs[edit]

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Interim staff guidance is temporary guidance created to facilitate expedited resolution of technical or licensing issues within established regulatory processes. Interim staff guidance is often used to clarify or expand on guidance found in standard review plans or regulatory guides.

The table below connects key ISGs to the AMPs they affected.

Key ISG's	Affected GALL AMPs	Affected GALL-SLR AMPs
SLR-ISG-2021-02-MECHANICAL, Updated Aging Management Criteria for Mechanical Portions of Subsequent License Renewal Guidance (Addresses 2020 Errata)		X.M2 - Neutron Fluence Monitoring
		XI.M2 - Water Chemistry
		XI.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)"
		XI.M16A, "PWR Vessel Internals"
		XI.M21A, "Closed-Cycle Cooling Water Systems"
		XI.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"
LR-ISG-2012-01, Wall Thinning Due to Erosion Mechanisms	XI.M17, "Flow-Accelerated Corrosion"	XI.M17, "Flow-Accelerated Corrosion"
LR-ISG-2011-02, Aging Management Program for Steam Generators	XI.M19, "Steam Generators"	XI.M19, "Steam Generators"
LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components	XI.M19, "Steam Generators"	GALL-SLR XI.M19, "Steam Generators"
LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation	XI.M20, "Open-Cycle Cooling Water System"	XI.M20, "Open-Cycle Cooling Water System"
	XI.M21A, "Closed-Cycle Cooling Water Systems"	XI.M21A, "Closed-Cycle Cooling Water Systems"
	XI.M27, "Fire Water System"	XI.M27, "Fire Water System"
	XI.M29, "Aboveground Metallic Tanks"	XI.M29, "Outdoor and Large Atmospheric Metallic Storage Tanks"
	XI.M36, "External Surfaces Monitoring of Mechanical Components"	XI.M36, "External Surfaces Monitoring of Mechanical Components"
	XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"	XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"
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"	XI.M20, "Open-Cycle Cooling Water System"
	XI.M24, "Compressed Air Monitoring"	XI.M24, "Compressed Air Monitoring"
	XI.M27, "Fire Water System"	XI.M27, "Fire Water System"
	XI.M29, "Aboveground Metallic Tanks"	XI.M29, "Outdoor and Large Atmospheric Metallic Storage Tanks"
	XI.M30, "Fuel Oil Chemistry"	XI.M30, "Fuel Oil Chemistry"
	XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"	XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"
		XI.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"
LR-ISG-2011-03, Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, "Buried and Underground Piping and Tanks"	XI.M33, "Selective Leaching"	XI.M33, "Selective Leaching"
	XI.M36, "External Surfaces Monitoring of Mechanical Components"	XI.M36, "External Surfaces Monitoring of Mechanical Components"
	XI.M41, "Buried and Underground Piping and Tanks"	XI.M41, "Buried and Underground Piping and Tanks"
LR-ISG-2015-01, Changes to Buried and Underground Piping and Tank Recommendations	XI.M33, "Selective Leaching"	XI.M33, "Selective Leaching"
	XI.M41, "Buried and Underground Piping and Tanks"	XI.M41, "Buried and Underground Piping and Tanks"
SLR-ISG-2021-04-ELECTRICAL, Updated Aging Management Criteria for Electrical Portions of Subsequent License Renewal Guidance		XI.E3A, "Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"
		XI.E3B, "Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"
		XI.E3C, "Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"
		XI.E7, "High-Voltage Insulators"

EPRI References by AMP[edit]

Matching GALL, GALL-SLR and IGALL AMPs[edit]

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GALL (R2) AMP	GALL-SLR AMP	IGALL AMP	EPRI REF	Note
X.M1, "Fatigue Monitoring"	X.M1, "Fatigue Monitoring"	AMP101, "Low Cycle Fatigue Monitoring" AMP161, "High Cycle Fatigue Monitoring" AMP320, "Vibration and Cyclic Loading on Civil Structures"	Materials Reliability Program: Thermal Fatigue Licensing Basis Monitoring Guideline MRP-149, Revision 1 (3002000684)
			Materials Reliability Program: Thermal Fatigue Monitoring Guidelines MRP-32, Revision 2 (3002016012)	Revision 1 (1022563) is referenced in the IGALL AMP
			Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 2) (3002007853)
			Materials Reliability Program: Temperature Monitoring Data Evaluation for Reactor Coolant System Branch Lines Subject to Thermal Fatigue (MRP-365, Revision 1) (3002016011)
			NDE Technology for Detection of Thermal Fatigue Damage in Piping, MRP-23 Revision 3 (3002017285)
			Materials Reliability Program: Fatigue Management Handbook (MRP-235, Revision 3) (3002018246)
			BWRVIP-196, Revision 1: BWR Vessel and Internals Project: Assessment of Mixing Tee Thermal Fatigue Susceptibility in BWR Plant (3002013099)
			Materials Reliability Program: Assessment of Residual Heat Removal Mixing Tee Thermal Fatigue in PWR Plants (MRP-192, Revision 4) (3002023891)	Revision 3 (3002013266 (Archived)) is referenced in the IGALL AMP
			BWRVIP-155, Revision 1: BWR Vessel and Internals Project: Evaluation of Thermal Fatigue Susceptibility in BWR Stagnant Branch Lines (3002013098)
			Materials Reliability Program: Operating Experience Regarding Thermal Fatigue of Piping Connected to PWR Reactor Coolant Systems (MRP-85, Revision 2) (3002013263)
			Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)), Degradation of Failure of Bolting (NP-5769(Archived)) and Initial Version of Bolted Joint Fundamentals (TR-104213(Archived)) is referenced in the IGALL AMP
			Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
			Aging Identification and Assessment Checklist: Civil and Structural Components (1011224)
			Aging Assessment Field Guide (1007933)
X.E1, "Environmental Qualification (EQ) of Electric Components"	X.E1, "Environmental Qualification of Electric Equipment"	AMP210, "Condition Monitoring of Electrical and I&C Cables Subject to Equipment Qualification Requirements" AMP221, "Equipment Qualification Preservation and Reassessment"	Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1 (1021067)
			Long-Term Operations: Subsequent License Renewal Electrical Handbook (3002010401)
			Plant Support Engineering: License Renewal Electrical Handbook (1013475)
			Initial Acceptance Criteria Concepts and Data for Assessing Longevity of Low-Voltage Cable Insulations and Jackets (1008211)
			Plant Support Engineering: Line Impedance Resonance Analysis for the Detection of Cable Damage and Degradation (1015209)
			Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1 (3002010641)
			Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1 (3002000557)
			Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants (1022969)
			Training Aids for Visual / Tactile Inspection of Electrical Cables for Detection of Aging (1001391)
			Cable Aging Management Program for D.C. Cook Nuclear Plant Units 1 and 2 (TR-106687)
			Medium Voltage Cable Aging Management Guide, Revision 1 (1021070)
			Infrared Thermography Guide (3002012582)	Initial Version (1006524 (Archived)) is referenced in the IGALL AMP.
			Aging Power Cable Maintenance Guideline (1024044)
			Plant Engineering: Cable Aging Management Program Implementation Guidance (1022968)
			Plant Engineering: Cable Polymer Handbook - Medium Voltage Insulations (3002005322)
			Effects of 0.1 Hertz Withstand Testing on Medium-Voltage Cable Insulation (3002010591)
			A Review of Equipment Aging Theory and Technology: Revision 1 of NP-1558 (3002018283)
XI.M1, "ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD"	XI.M1, "ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD"	AMP102, "In-service Inspection/Periodic Inspection"	EPRI Materials Degradation Matrix, Revision 4 (3002013781)
			Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175, Revision 1) (3002010268)
			BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables (3002018319)
			BWRVIP-03, Revision 21: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines (3002026476)	BWRVIP-03 Revision 1 (TR-105696 R1 (Archived)) is referenced in the GALL (R2) AMP. BWRVIP-03 Revision 6 (TR-105696-R6(Archived)) is referenced in the GALL-SLR AMP
XI.M2, "Water Chemistry"	XI.M2, "Water Chemistry"	AMP103, "Water Chemistry"	BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	Initial Revision (1016579(Archived)) is referenced in the GALL (R2) AMP and GALL-SLR AMP Revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8 (3002010645)	Revision 7 (1016555(Archived)) is referenced in the GALL (R2) AMP and GALL-SLR AMP
			Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2 (3002000505)	Revision 6 (1014986(Archived)) is referenced in the GALL (R2) AMP and GALL-SLR AMP
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002017199)	Revision 1 (1022844(Archived)) is referenced in the IGALL AMP.
XI.M4, "BWR Vessel ID Attachment Welds"	XI.M4, "BWR Vessel ID Attachment Welds"	AMP105, "BWR Vessel ID Attachment Welds"	BWRVIP-48-A: BWR Vessel and Internals Project, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines (1009948)
			BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (1016569)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
			BWRVIP-48, Revision 2: BWR Vessel and Internals Project: Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines (3002018321)
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	BWRVIP-190 revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (3002013026)
			BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (1016566)
			BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components (3002023756)	Revision 1-A (3002008388(Archived)) is referenced in the IGALL AMP.
			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 (3002003103)
			BWRVIP-03, Revision 21: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines (3002026476)	BWRVIP-03 Revision 1 (TR-105696 R1 (Archived)) is referenced in the GALL (R2) AMP. BWRVIP-03 Revision 6 (TR-105696-R6(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (1008871)
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 1: Implementation Criteria for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002020993)	Initial revision of BWRVIP-62 (108705(Archived)) is referenced in GALL (R2) AMP
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002017199)
XI.M7, "BWR Stress Corrosion Cracking"	XI.M7, "BWR Stress Corrosion Cracking"	AMP107, "BWR Stress Corrosion Cracking in Coolant Pressure Boundary Components"	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (1012621)
			BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (1016569)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
			EPRI Materials Degradation Matrix, Revision 4 (3002013781)
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	BWRVIP-190 revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 1: Implementation Criteria for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002020993)	Initial revision of BWRVIP-62 (108705(Archived)) is referenced in GALL (R2) AMP Revision BWRVIP-62-A (1021006(Archived)) is referenced in GALL-SLR AMP Revsion 1 (1022844(Archived)) is referenced in IGALL AMP
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002017199)
			Materials Handbook for Nuclear Plant Pressure Boundary Applications (IMR-100) (3002026521)	2018 Revision (3002012420(Archived)) referenced in the IGALL AMP.
			Irradiation-Assisted Stress Corrosion Cracking (IASCC) Initiation Model for Stainless Steels (3002005474)	Validation of Stress Corrosion Cracking Initiation Model for Stainless Steel and Nickel Alloys (1025121(Archived)) is referenced in the IGALL AMP.
			Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 2 (MRP-448) (3002018002)
			BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (1008871)
			Induction Heating Stress Improvement Effectiveness on Crack Growth in Operating Plants (BWRVIP-61) (TR-112076)
XI.M8, "BWR Penetrations"	XI.M8, "BWR Penetrations"	AMP108. "BWR Penetrations"	BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines (1007279)
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	Initial Revision (1016579(Archived)) is referenced in the GALL (R2) AMP and GALL-SLR AMP Revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (1016569)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
			BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines (1009947)
			BWRVIP-49, Revision 1: BWR Vessel and Internals Project, Instrument Penetration Inspection and Flaw Evaluation Guidelines (3002026484)	BWRVIP-49-A (1006602) is referenced in GALL (R2), GALL-SLR and IGALL AMP
			BWRVIP-53-A: BWR Vessel and lnternals Project, Standby Liquid Control Line Repair Design Criteria (1012120)
			BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria (3002020995)	BWRVIP-57-A (1012111(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP .
			BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (3002013026)
			BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (1008871)
			BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (1016566)
			BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components (3002023756)
			Irradiation-Assisted Stress Corrosion Cracking (IASCC) Initiation Model for Stainless Steels (3002005474)	Validation of Stress Corrosion Cracking Initiation Model for Stainless Steel and Nickel Alloys (1025121(Archived)) is referenced in the IGALL AMP.
			Materials Reliability Program: Stress Corrosion Crack (SCC) Initiation Testing of Ni-Base Alloys for PWR Applications Part 2 (MRP-448) (3002018002)
			BWR Vessel and Internals Project: Role/Expansion Repair of Control Rod Drive and In-Core Instrument Penetrations in BWR Vessels (BWRVIP-17) (TR-106712)
			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" (1016586)
			Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8 (3002010645)
			BWRVIP-55-A: BWR Vessel and Internals Project, Lower Plenum Repair Design Criteria (1012117)
			BWRVIP-58-A: BWR Vessel and Internals Project, CRD Internal Access Weld Repair (1012618)
XI.M9, "BWR Vessel Internals"	XI.M9, "BWR Vessel Internals"	AMP108. "BWR Penetrations"	BWRVIP-02-A: BWR Vessel and Internals Project, BWR Core Shroud Repair Design Criteria, Rev. 2 (1012837)
			BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (1016569)
			BWRVIP-47-A: BWR Vessel and Internals Project, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines (1009947)
			BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (1008871)
			BWRVIP-57, Revision 1: BWR Vessel and Internals Project—Instrument Penetration Repair Design Criteria (3002020995)	BWRVIP-57-A (1012111(Archived)) is referenced in GALL (R2) AMP
			BWRVIP-16-A: BWR Vessel and Internals Project, Internal Core Spraying Piping and Sparger Replacement Design Criteria (1012113)
			BWRVIP-18, Revision 2-A: BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (3002008089)	BWRVIP-18-A (1011469(Archived)) is referenced in GALL (R2) AMP. BWRVIP-18-A Rev 1-A (1025060(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-19-A: BWR Vessel and Internals Project, Internal Core Spray Piping and Sparger Repair Design Criteria (1012114)
			BWRVIP-25, Rev. 1-A, BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines (3002018310)	BWRVIP-25 (107284(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP Revision 1 (3002005594(Archived)) is also referenced in the IGALL AMP.
			BWRVIP-26-A: BWR Vessel and Internals Project, BWR Top Guide Inspection and Flaw Evaluation Guidelines (1009946)
			BWRVIP-03, Revision 21: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines (3002026476)	BWRVIP-03 Revision 1 (TR-105696 R1 (Archived)) is referenced in the GALL (R2) and GALL-SLR AMP. Revision 20 (3002010675) is referenced in the IGALL AMP
			BWRVIP-38, Revision 1: BWR Vessel and Internals Project—BWR Shroud Support Inspection and Flaw Evaluation Guideline (3002020997)	Initial version (TR-108823(Archived)) is referenced in the GALL(R2), GALL-SLR and IGALL AMP.
			BWRVIP-41, Revision 4-A BWR Vessel and Internals Project: Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (3002014254)	BWRVIP-41 Initial revision (108728(Archived)) is referenced in GALL (R2) and GALL-SLR AMP.
			BWRVIP-42, Revision 1-A: BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines (3002010548)	BWRVIP-42-A (1011470(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP.
			BWRVIP-44-A: BWR Vessel and Internals Project: Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals (1014352)
			BWR Vessel and Internals Project: Weldability of Irradiated LWR Structural Components (BWRVIP-45) (TR-108707)
			BWRVIP-50-A: BWR Vessel and Internals Project, Top Guide/Core Plate Repair Design Criteria (1012115)
			BWRVIP-51-A: BWR Vessel and Internals Project, Jet Pump Repair Design Criteria (1012116)
			BWRVIP-52-A: BWR Vessel and Internals Project, Shroud Support and Vessel Bracket Repair Design Criteria (1012119)
			BWRVIP-56-A: BWR Vessel and Internals Project, LPCI Coupling Repair Design Criteria (1012118)
			BWRVIP-58-A: BWR Vessel and Internals Project, CRD Internal Access Weld Repair (1012618)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 1: Implementation Criteria for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002020993)	Initial revision of BWRVIP-62 (108705(Archived)) is referenced in GALL (R2) AMP BWRVIP-62-A (1021006(Archived)) is referenced in GALL-SLR AMP
			BWRVIP-62 Revision 2: BWR Vessel and Internals Project: Volume 2: Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection (3002017199)
			BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines (1007279)	Initial revision of BWRVIP-62 (108705(Archived)) is referenced in GALL (R2) AMP
			BWRVIP-76, Revision 1-A: BWR Vessel and Internals Project: BWR Core Shroud Inspection and Flaw Evaluation Guidelines (3002005566)	BWRVIP-76-A (1019057(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP Revision 2 (3002003095(Archived)) is referenced in IGALL AMP.
			BWRVIP-80-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Shroud Vertical Welds (1015457)	NP version (1015457NP(Archived)) is referenced in the GALL (R2) AMP
			BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (1016566)
			BWRVIP-139, Revision 1-A: BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines (3002010541)	Initial version (1011463(Archived)) is referenced in the GALL (R2) AMP BWRVIP-139-A (1018794(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables (3002018319)	BWRVIP-167NP Rev 1 (1018111(Archived)) is referenced in the GALL (R2) AMP BWRVIP-167NP Revision 3 (3002000690(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-181, Revision 2: BWR Vessel and Internals Project, Steam Dryer Repair Design Criteria (3002005567)	Initial version (1013403(Archived)) is referenced in the GALL (R2) AMP BWRVIP-181-A (1020997) is referenced in the GALL-SLR AMP
			BWRVIP-183-A: BWR Vessel and Internals Project, Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines (3002010551)	Initial version (1013401(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	Initial version (1016579(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP BWRVIP-190 revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			BWRVIP-84, Revision 3: BWRVIP Vessel and Internals Project, Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components (3002010552)	Revision 2 (1026603(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-97, Revision 1: BWR Vessel and Internals Project, Guidelines for Performing Weld Repairs to Irradiated BWR Internals (3002005568 )	BWRVIP-97-A (1019054) is referenced in the GALL-SLR AMP
			BWRVIP-100, Revision 2: BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components (3002023756)	BWRVIP-100-A (1013396(Archived)) is referenced in the GALL-SLR AMP BWRVIP-100 Revision 1-A (3002008388(Archived)) is referenced in the IGALL AMP.
			BWRVIP-138, Revision 2: BWR Vessel and Internals Project—Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines (3002023754)	Revision 1-A (1025139(Archived)) is referenced in the GALL-SLR and the IGALL AMP.
			BWRVIP-180, Revision 1: BWR Vessel and Internals Project-Access Hole Cover Inspection and Flaw Evaluation Guidelines (3002018312)	Initial version (1013402(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-233, Rev. 2: Updated Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (3002013026)
			BWRVIP-182-A: BWR Vessel and Internals Project, Guidance for Demonstration of Steam Dryer Integrity for Power Uprate (1020802)
			BWRVIP-315-A: BWR Vessel and Internals Project: Reactor Internals Aging Management Evaluation for Extended Operations (3002029071)	Initial version (3002012535(Archived)) is referenced in the IGALL AMP
			BWRVIP-234-A: BWR Vessel and Internals Project, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steels for BWR Internals (3002010550)
			EPRI Materials Degradation Matrix, Revision 4 (3002013781)	Materials Degradation Matrix Rev 1 (1016486(Archived)) is referenced in the GALL (R2) AMP and Rev 3 (3002000628(Archived)) is referenced in the GALL-SLR AMP
			BWRVIP-06, Revision 1-A: BWR Vessel and Internals Project, Safety Assessment of BWR Reactor Internals (1019058)
			BWRVIP-55-A: BWR Vessel and Internals Project, Lower Plenum Repair Design Criteria (1012117)
			BWRVIP-217: BWR Vessel and Internals Project, Access Hole Cover Repair Design Criteria (1019067)
XI.M10, "Boric Acid Corrosion"	XI.M10, "Boric Acid Corrosion"	AMP110, "PWR Boric Acid Corrosion"	Materials Reliability Program: Thermal Fatigue Licensing Basis Monitoring Guideline MRP-149, Revision 1 (3002000684)
			Materials Reliability Program: Thermal Fatigue Monitoring Guidelines MRP-32, Revision 2 (3002016012)
			Materials Reliability Program: Boric Acid Corrosion Guidebook, Revision 2: Managing Boric Acid Corrosion Issues at PWR Power Stations (MRP-058, Rev 2) (1025145)	MRP-058, Revision 1 (1000975(Archived)) is referenced in the GALL-SLR AMP.
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.M11B, "Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components (PWRs Only)"	AMP111, "PWR Cracking of Nickel Alloy Reactor Coolant Pressure Boundary Components"	MRP-139 Revision 1: Primary System Piping Butt Welds Inspection and Evaluation Guideline (1015009)
			Materials Reliability Program: Boric Acid Corrosion Guidebook, Revision 2: Managing Boric Acid Corrosion Issues at PWR Power Stations (MRP-058, Rev 2) (1025145)
			Materials Reliability Program: Safety Evaluation for Boric Acid Wastage of PWR Reactor Vessel Bottom Heads Due to Bottom-Mounted Nozzle Leakage (MRP-167) (1016591)
			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) (3002014244)
			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) (3002010756)
			Materials Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126) (1009561)
XI.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)"	XI.M12, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)"	AMP112, "Thermal Ageing Embrittlement of Cast Austenitic Stainless Steel"	BWRVIP-03, Revision 21: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines (3002026476)	Rev. 6 (TR-105696(Archived)) is referenced in GALL (R2) and GALL-SLR AMP Rev. 20 (3002010675 is referenced in IGALL AMP
			Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5) (3002026460)	Initial revision (1016609(Archived)) is referenced in GALL (R2) and GALL-SLR AMP Rev. 4 (3002018245(Archived)) is referenced in the IGALL AMP
XI.M16A, "PWR Vessel Internals"	XI.M16A, "PWR Vessel Internals"	AMP113, "PWR Vessel Internals"	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2) (3002020105)	Initial revision (1016596(Archived)) is referenced in the GALL (R2) AMP Revsion A (1022863(Archived)) is referenced in the GALL-SLR and IGALL AMP Revsion 1-A (3002017168) is also referenced in the IGALL AMP
			Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5) (3002026460)	Initial revision (1016609(Archived)) is referenced in GALL (R2) and GALL-SLR AMP Rev. 4 (3002018245(Archived)) is referenced in the IGALL AMP
			Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175, Revision 1) (3002010268)	Initial Revision (1012081(Archived)) is also referenced in the IGALL AMP
			Materials Reliability Program: Improvement of the Cluster Dynamics Model for the Prediction of Void Swelling in Austenitic Stainless Steel (MRP-391) (3002003083)
			Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2 (3002000505)	PWR Primary Water Chemistry Guidelines Revision 6 (1014986(Archived)) is referenced in the GALL (R2) AMP
XI.M17, "Flow-Accelerated Corrosion"	XI.M17, "Flow-Accelerated Corrosion"	AMP114, "Flow Accelerated Corrosion and Erosion"	Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4) (3002000563)	Recommendations for Controling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Partical Errosion in Nuclear Power Plant Systems (1011231(Archived)), NSAC-202L-R2(Archived) and -R3(Archived) are also referenced in the GALL-SLR AMP
			Flow-Accelerated Corrosion in Power Plants: Revision 2 (3002008071)
			Recommendations for an Effective Program Against Erosive Attack: Revision 1 (3002023786)	Recommendations for an Effective Program Against Erosive Attack initial revision (3002005530(Archived)) is referenced in the IGALL AMP
			CHECWORKS™ Steam/Feedwater Application Guidelines for Plant Modeling and Evaluation of Component Inspection Data: Revision 1 (3002010594)
			CHECWORKS(TM) Steam/Feedwater Application (SFA), version 4.2 (3002010583)	The beta for v5.0 is also available at https://checworks.epri.com/
			Flow-Accelerated Corrosion - The Entrance Effect (1015072)
			Revised Risk-Informed Inservice Inspection Evaluation Procedure (TR-112657REVB-A)
XI.M18, "Bolting Integrity"	XI.M18, "Bolting Integrity"	AMP115, "Bolting Integrity"	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Bolted Joint Maintenance & Application Guide (NP-5769(Archived)) is referenced in the IGALL AMP Bolted Joint Maintenance & Application Guide (NP-5769(Archived)) and Bolted Joint Maintenance and Application Guide (TR-104213(Archived)) are referenced in the GALL (R2) AMP Bolted Joint Maintenance & Application Guide (NP-5769(Archived)), Bolted Joint Fundamentals initial revision (1015336(Archived)) and Assembling Gasketed Flanged Bolted Joints initial revision (1015337(Archived)) are referenced in the GALL-SLR AMP
XI.M18, "Bolting Integrity"	XI.M18, "Bolting Integrity"	AMP115, "Bolting Integrity"	Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
XI.M19, "Steam Generators"	XI.M19, "Steam Generators"	AMP116, "Steam Generators"	Steam Generator Management Program: PWR Primary-to-Secondary Leak Guidelines-Revision 5 (3002018267)	Revision 3 (1008219(Archived)) is referenced in the GALL (R2) AMP Revision 4 (1022832(Archived)) is referenced in the GALL-SLR and the IGALL AMP
			Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Revision 5 (3002020909)	Revison 2 (1012987(Archived)) is referenced in the GALL (R2) AMP Revison 4 (3002007571(Archived)) is referenced in the GALL-SLR and the IGALL AMP
			Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 8 (3002007572)	Revision 7 (1013706(Archived)) is referenced in the GALL (R2) AMP
			Steam Generator Management Program: Steam Generator In Situ Pressure Test Guidelines, Revision 5 (3002007856)	Revision 3 (1014983(Archived)) is referenced in the GALL (R2) AMP Revision 4 (1025132(Archived)) is referenced in the GALL-SLR and the IGALL AMP
			Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2 (3002000505)	Pressurized Water Reactor Primary Water Chemistry Guidelines Revision 6 (1014986(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP
			Pressurized Water Reactor Secondary Water Chemistry Guidelines: Revision 8 (3002010645)	Pressurized Water Reactor Secondary Water Chemistry Guidelines Revision 7 (1016555(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP
			N/A	Changes to Aging Management Guidance for Steam Generator Chanel Head Components (SGMP-IL-16-02(Archived)) is reference in the IGALL and was rolled into LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components
			Steam Generator Management Program: Investigation of Crack Initiation and Propagation in the Steam Generator Channel Head Assembly (3002002850)
XI.M20, "Open-Cycle Cooling Water System"	XI.M20, "Open-Cycle Cooling Water System"	AMP124. "Open Cycle Cooling Water System"	Life Cycle Management Sourcebook for Nuclear Plant Service Water Systems (1008282)
			Service Water Piping Guideline (1010059)
			Open Cooling Water Chemistry Guideline, Revision 1 (3002019654)
			A Study of Microbiologically Influenced Corrosion in Nuclear Power Plants and a Practical Guide for Countermeasures (NP-4582)
			Intake Systems Maintenance Guide, Volume 1: Stop Gates, Trash Racks, and Trash Rakes (3002020354)
			Intake Systems Maintenance Guide Volume 2: Fine Screens (3002023772)
			Intake System Maintenance Guide: Volume 3 - Debris Management and Disposal (3002026349)
XI.M21A, "Closed-Cycle Cooling Water Systems"	XI.M21A, "Closed-Cycle Cooling Water Systems"	AMP117, "Closed Treated Water Systems"	Closed Cooling Water Chemistry Guideline: Revision 2 (3002000590)	Initial Revision (1007820(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP
XI.M22, "Boraflex Monitoring"	XI.M22, "Boraflex Monitoring"	AMP126, "Boraflex Monitoring"	An Assessment of Boraflex Performance in Spent-Nuclear-Fuel Storage Racks (NP-6159)
			Guidance and Recommended Procedures for Maintaining and Using RACKLIFE Version 1.10 Models (1003413)
			Boraflex Test Results and Evaluation (TR-101986)
			Guidelines for Boraflex Use in Spent-Fuel Storage Racks (TR-103300)
			Handbook of Neutron Absorber Materials for Spent Nuclear Fuel Storage and Transportation Applications, Revision 1: 2022 Update (3002018496)	2009 Edition (1019110) is referenced in IGALL AMP
XI.M24, "Compressed Air Monitoring"	XI.M24, "Compressed Air Monitoring"	AMP128, "Compressed Air Monitoring"	Compressed Air Systems and Equipment Guide: Update and Consolidation of TR-108147 and 1006677 (3002022576)	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)) is referenced in the GALL (R2) AMP and IGALL AMP Compressor and Instrument Air System Maintenance Guide: Revision to NP-7079 (TR-108147(Archived)) is referenced in the GALL-SLR AMP
XI.M25, "BWR Reactor Water Cleanup System"	XI.M25, "BWR Reactor Water Cleanup System"	AMP129, "BWR Reactor Water Cleanup System	BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (1012621)
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	Revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
			BWRVIP-14-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (1016569)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
XI.M27, "Fire Water System"	XI.M27, "Fire Water System"	AMP131, "Fire Water System"	Guideline for the Evaluation and Treatment of Corrosion and Fouling in Fire Protection Systems (TR-109633)
XI.M29, "Aboveground Metallic Tanks"	XI.M29, "Outdoor and Large Atmospheric Metallic Storage Tanks"	AMP164, "Outdoor Piping, Tanks and Structures"	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)) is referenced in the IGALL AMP
			Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
			Guidelines for Tank Inspections (3002003071)
			Nondestructive Evaluation (NDE): Assessments for Tanks and Containment Liners: Readily Available NDE Methods to Inspect Tanks and Containment Liners (3002013172)
XI.M30. "Fuel Oil Chemistry"	XI.M30. "Fuel Oil Chemistry"	AMP133, "Fuel Oil Chemistry"	Nuclear Maintenance Applications Center: Guide for the Storage and Handling of Fuel Oil for Standby Diesel Generator Systems, Revision 3 (1015061)
			Storage and Use of Low-Concentration (5%) Biodiesel Blends in Nuclear Plant Emergency Diesel Generators (3002010609)
			Winterizing Diesel Fuel (TR-104843)
XI.M31, "Reactor Vessel Surveillance"	XI.M31, "Reactor Vessel Material Surveillance"	AMP118, "Reactor Vessel Surveillance"	Materials Reliability Program (MRP) - Materials Research Focus Area(MRFA)4- Low Alloy Steels Wiki
			Materials Reliability Program: Consolidated Fracture Toughness Models for Ferritic RPV Steels (MRP-432) (3002013223)	Application of Master Curve Fracture Toughness Methodology for Ferritic Steels (PWRMRP-01): PWR Materials Reliability Project (PWRMRP), Final Report (TR-108390-R1(Archived)) is referenced in the IGALL AMP
			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 (3002016008)
			Methods to Address the Effects of Irradiation Embrittlement in Section XI of the ASME Code (MRP-462): Estimation of an Irradiated Reference Temperature Using Either Traditional Charpy Approaches or Master Curve Data (3002020911)	Materials Reliability Program: Developing on Embrittlement Trend Curve Using the Charpy “Master Curve” Transition Reference Temperature (MRP-289)) (1020703(Archived)) is referenced in the IGALL AMP. Expect to have an updated version of MRP-289 in 2024
			Materials Reliability Program: Development of a T0-Based Embrittlement Trend Curve and Comparison With the Charpy Master Curve Embrittlement Trend Curve (MRP-389) (3002003040)
			BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan (1025144)
			BWRVIP-321, Revision 1-A, BWR Vessel and Internals Project: Plan for Extension of the BWR Integrated Surveillance Program (ISP) Through the Second License Renewal (SLR) (3002026169)	BWRVIP-321 Initial Revision (3002013097(Archived)) is referenced in the IGALL AMP
			Materials Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326, Revision 1) (3002020910)
			Materials Reliability Program: PWR Supplemental Surveillance Program (PSSP) Capsule Fabrication Report (MRP-412) (3002007964)
			Materials Reliability Program: Guidance on Timing for Technical Specification Revision Following Surveillance Capsule Testing (MRP-484) (3002026457)
XI.M32, "One-Time Inspection"	XI.M32, "One-Time Inspection"	AMP119, "One-time Inspection"	BWRVIP-03, Revision 21: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines (3002026476)	Revision 6 (TR-105696-R6(Archived)) is referenced in the GALL(R2) and GALL-SLR AMP Revision 15 (1025142-R15(Archived)) is referenced in the IGALL AMP
			Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2023 Update (MRP-228, Rev. 5) (3002026460)	Initial revision (1016609(Archived)) is referenced in GALL (R2) and GALL-SLR AMP Revision 3 (3002010399(Archived)) is referenced in the IGALL AMP
			Nondestructive Evaluation: Update on License Renewal One-Time Inspection and Best Nondestructive Evaluation Practices - Rev. 1 (3002000459)	Initial Revision (1022931) is referenced in the IGALL AMP
XI.M33, "Selective Leaching"	XI.M33, "Selective Leaching"	AMP120, "Selective Leaching"	Nondestructive Evaluation: Guidance for Conducting Ultrasonic Examinations for the Detection of Selective Leaching (3002013168)
			Selective Leaching: State-of-the-Art Technical Update (3002016057)
			Electromagnetic NDE Techniques for Detection of Selective Leaching in Gray Cast Iron Piping (3002020832)
			Nondestructive Evaluation: Update to NDE for Selective Leaching of Gray Cast Iron Components (1019111)	Initial Revision (1018939) is also referenced in the IGALL AMP
			Nondestructive Evaluation: Correlation of Selectively Leached Thickness to Hardness for Gray Cast Iron and Brass (1025218)
			Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools (1010639)
			Long-Term Operations: Subsequent License Renewal Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools (3002011822)
			Assessment of Available Nondestructive Evaluation Techniques for Selective Leaching: Technology Review (3002008013)
			Ultrasonic NDE Techniques for Detection of Selective Leaching in Complex Shaped Gray Cast Iron Components (3002020830)
			Evaluation of Electromagnetic NDE Techniques for Detection of Wall Thinning Due to Selective Leaching Degradation in Gray Cast Iron Piping (3002023785)	Initial Revision (3002020832) is referenced in the IGALL AMP
			Leveraging Risk Insights for Aging Management Program Implementation: 2022 (3002020713)	Initial Revision (3002018403(Archived)) is referenced in the IGALL AMP
			Accelerated Testing and Evaluation of Factors Affecting Selective Leaching Susceptibility (3002020822)
			Recommendations for Implementing an Effective Program to Manage Selective Leaching Degradation (3002026340)
XI.M35, "One-Time Inspections of ASME Code Class 1 Small-Bore Piping"	XI.M35, "ASME Code Class 1 Small-Bore Piping"	AMP121, "One-time Inspection of Class 1 Small Bore Piping"	Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-146, Revision 2) (3002007853)	MRP-146 Initial Revision (10119553(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP
			Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines – Supplemental Guidance (MRP-146S, Revision 1) (3002013264)	MRP-146S Initial Revision (1018330) is referenced in the GALL (R2), GALL-SLR and IGALL AMP
			BWRVIP-196, Revision 1: BWR Vessel and Internals Project: Assessment of Mixing Tee Thermal Fatigue Susceptibility in BWR Plant (3002013099)
			BWRVIP-155, Revision 1: BWR Vessel and Internals Project: Evaluation of Thermal Fatigue Susceptibility in BWR Stagnant Branch Lines (3002013098)
			Materials Reliability Program: Lessons Learned from PWR Thermal Fatigue Management Training (MRP-83) (1003666)
			Pressurized Water Reactor Primary Water Chemistry Guidelines: Revision 7, Volumes 1 and 2 (3002000505)
			BWRVIP-190 Revision 2: BWR Vessel and Internals Project, Volumes 1 and 2 (3002025550)	Revision 1 (3002002623(Archived)) is referenced in the IGALL AMP
XI.M36, "External Surfaces Monitoring of Mechanical Components"	XI.M36, "External Surfaces Monitoring of Mechanical Components"	AMP134, "External Surfaces Monitoring of Mechanical Components"	Aging Assessment Field Guide (1007933)
			Aging Identification and Assessment Checklist: Mechanical Components (1009743)
			Long-Term Operations: Subsequent License Renewal Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools (3002011822)
XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"	XI.M38, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components"	AMP135, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components	Aging Assessment Field Guide (1007933)
			Aging Identification and Assessment Checklist: Mechanical Components (1009743)
XI.M39, "Lubricating Oil Analysis"	XI.M39, "Lubricating Oil Analysis"		CBM Lubrication Wiki
XI.M39, "Lubricating Oil Analysis"	XI.M39, "Lubricating Oil Analysis"		Reliability and Maintenance Strategies-Condition Based Maintenance Documents
XI.M40, "Monitoring of Neutron-Absorbing Materials Other than Boraflex"	XI.M40, "Monitoring of Neutron-Absorbing Materials Other than Boraflex"	AMP315, "Spent Fuel Pool"	Investigation of Eddy Current Arrays and Ultrasonic Techniques to Inspect Spent Fuel Pool and Transfer Canal Liners (3002021030)	Initial Revision (1025214(Archived)) is referenced in the IGALL AMP
			Welding and Repair Technology Center: Boric Acid Attack of Concrete and Reinforcing Steel in PWR Fuel Handling Buildings (1025166)
			Welding and Repair Technology Center: Non-Metallic Repair of Nuclear Fuel Pool Liners (3002021072)	Welding and Repair Technology Center: Guideline for Nuclear Fuel Pool Repair Strategy (3002007902(Archived)) is referenced in the IGALL AMP
XI.M41, "Buried and Underground Piping and Tanks"	XI.M41, "Buried and Underground Piping and Tanks"	AMP125, "Buried and Underground Piping and Tanks AMP316, "Subsurface Engineered Backfill Materials"	Recommendations for an Effective Program to Control the Degradation of Buried and Underground Piping and Tanks (1016456, Revision 2) (3002018352)	Revision 1 (1021175(Archived)) is referenced in the GALL-SLR AMP
			The Buried and Underground Piping and Tank Reference Guide: Revision 2 (3002018353)	Remote Field Technology Assessment for Piping Inspection, Including Buried and Limited Access Components (1021153(Archived)) is referenced in the IGALL AMP
			Nondestructive Evaluation: Buried Pipe NDE Reference Guide—Revision 3 (3002004395)
			Nondestructive Evaluation: Assessment and Development of Buried Pipe NDE Technology, Revision 1 (3002010027)
			Nondestructive Evaluation: Buried Pipe In-Line NDE Depth Sizing Procedure (1025231)
			Development and Evaluation of Guided Wave Structural Health Monitoring for Buried Pipe (3002008032)
			Obtaining Credit for Guided Wave as a Buried Pipe Direct Examination (3002000468)
			Buried Pipe Guided Wave Examination Reference Document (1019115)
			Cathodic Protection Application and Maintenance Guide: Volume 1 and Volume 2 ([1])
			Recommendations for Managing an Effective Cathodic Protection System (3002002949)
			Criteria for Determining the Effectiveness of Cathodic Protection (3002005253)
			Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping (3002013156)
			BPWORKS V3.0: Data Management and Risk Ranking for Buried, Underground, and Raw Water Piping (3002013207)
			Soil Sampling and Testing Methods to Evaluate the Corrosivity of the Environment for Buried Piping and Tanks at Nuclear Power Plants (3002005294)
			Ultrasonic Pipe Wall Thickness Measurement of Coated Buried Pipe: Phase II Report (3002008067)
	XI.M42, "Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks"	AMP157, "Internal Coatings and Linings"	Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102) (1019157)
			Plant Engineering: Aging Degradation of Coating Service Level I Coatings—Summary of EPRI Coating Aging Project Activities (3002000629)
			Field Guide: Coatings Assessment (1025323)
XI.S1, "ASME Section XI, Subsection IWE"	XI.S1, "ASME Section XI, Subsection IWE"	AMP147, "Containment Bellows" AMP163, "Dissimilar Metal Welds" AMP301, "In-service Inspection for Containment Steel Elements"	Expansion Joint Maintenance Guide (1008035)
			EPRI Materials Degradation Matrix, Revision 4 (3002013781)
			Age-Related Degradation Inspection Method and Demonstration: In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application (TR-107514)
			Materials Reliability Program: GE Experience Report on Cracking in Alloy 182 (MRP-57): BWR Alloy 182 Stress Corrosion Cracking (1006603)
			Materials Reliability Program: A Review of Thermal Aging Embrittlement in Pressurized Water Reactors (MRP-80) (1003523)
			BWRVIP-75-A: BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (1012621)
			MRP-139 Revision 1: Primary System Piping Butt Welds Inspection and Evaluation Guideline (1015009)
			Materials Reliability Program: Primary Water Stress Corrosion Cracking (PWSCC) Flaw Evaluation Guidance (MRP-287) (1021023)
			BWRVIP-59-A: BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Nickel Base Austenitic Alloys in RPV Internals (1014874)
			Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds, Revision 3 (3002012244)
			Materials Reliability Program: Advanced FEA Evaluation of Growth of Postulated Circumferential PWSCC Flaws in Pressurizer Nozzle Dissimilar Metal Welds (MRP-216, Rev. 1) (1015400)	Initial Revision (1015383(Archived)) is referenced in the IGALL AMP
			Materials Reliability Program: Welding Residual and Operating Stresses in PWR Alloy 182 Butt Welds (MRP-106) (1009378)
			Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for U.S. PWR Plant Designs (MRP-113) (1009549)
			Materials Reliability Program: Evaluation of the Effect of Weld Repairs on Dissimilar Metal Butt Welds (MRP-114) (1009559)
			Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for US PWR Plant Designs: Babcock & Wilcox Design Plants (MRP-112) (1009805)
			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) (3002014244)	MRP-115 (1006696) is referenced in IGALL AMP
			Materials Reliability Program: Probabilistic Risk Assessment of Alloy 82/182 Piping Butt Welds (MRP-116) (1009806)
			Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)), Bolted Joint Maintenance & Application Guide (NP-5769(Archived)) and Bolted Joint Maintenance and Application Guide (TR-104213(Archived)) are referenced in the GALL (R2) and GALL-SLR AMP Degradation and Failure of Bolting in Nuclear Power Plants, Volumes 1 and 2 (NP-5769(Archived)) and Initial version of Bolted Joint Fundamentals (1015336(Archived)) is referenced in the IGALL AMP
			Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
			Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools) (1015078)	Aging Effects for Structures and Structural Components (Structural Tools): B&W Owners Group Generic License Renewal Programme, BAW-2279P (TR-114881) is referenced in the IGALL AMP
			Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools) (3002013084)
			How to Conduct Material Condition Inspections: September, 1994 (TR-104514)
XI.S3, "ASME Section XI, Subsection IWF"	XI.S3, "ASME Section XI, Subsection IWF"	AMP303, "Safety Class 1, 2 and 3 Piping and Metal Containment Components Supports"	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)), Degradation of Failure of Bolting (NP-5769(Archived)) and Bolted Joint Maintenance & Application Guide (TR-104213(Archived)) is referenced in the GALL (R2), GALL-SLR and IGALL AMP
XI.S3, "ASME Section XI, Subsection IWF"	XI.S3, "ASME Section XI, Subsection IWF"		Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
XI.S5, "Masonry Walls"	XI.S5, "Masonry Walls"	AMP305, "Masonry Walls"	Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools) (3002013084)
XI.S6, "Structures Monitoring"	XI.S6, "Structures Monitoring"	AMP318, "Concrete Structures Monitoring" AMP319, "Non-concrete structures monitoring" AMP317, "Settlement of Structures"	Aging Identification and Assessment Checklist: Civil and Structural Components (1011224)
			Aging Assessment Field Guide (1007933)
			Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools) (1015078)
			Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools) (3002013084)
			Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)), Degradation of Failure of Bolting (NP-5769(Archived)) and Initial Version of Bolted Joint Fundamentals (TR-104213(Archived)) is referenced in the GALL (R2) AMP and IGALL AMP Good Bolting Practices (NP-5067(Archived)) and Bolted Joint Maintenance & Application Guide (TR-104213(Archived)) is referenced in the GALL-SLR
			Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
XI.S7, "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants"	XI.S7, "Inspection of Water-Control Structures Associated with Nuclear Power Plants"	AMP307, "Water Control Structures" AMP317, "Settlement of Structures"	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Good Bolting Practices (NP-5067(Archived)), Degradation of Failure of Bolting (NP-5769(Archived)) and Initial Version of Bolted Joint Fundamentals (TR-104213(Archived)) is referenced in the GALL (R2) AMP Good Bolting Practices (NP-5067(Archived)) and Bolted Joint Maintenance & Application Guide (TR-104213(Archived)) is referenced in the GALL-SLR and IGALL AMP
			Assembling Gasketed Bolted Flange Joints: Update of Report 3002008061 (3002023823)
			Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools) (1015078)
			Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools) (3002013084)
XI.S8, "Protective Coating Monitoring and Maintenance"	XI.S8, "Protective Coating Monitoring and Maintenance"	AMP308, "Protective Coating Monitoring and Maintenance Programme"	Plant Support Engineering: Guideline on Nuclear Safety-Related Coatings, Revision 2 (Formerly TR-109937 and 1003102) (1019157)	Guideline on Nuclear Safety-Related Coatings Revision 1 (1003102(Archived)) is also referenced in the GALL (R2) and GALL-SLR AMP
XI.S8, "Protective Coating Monitoring and Maintenance"	XI.S8, "Protective Coating Monitoring and Maintenance"		Field Guide: Coatings Assessment (1025323)
XI.E1, "Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	XI.E1, "Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	AMP201, "Electrical Insulation for Electrical Cables and Connections Not Subject to Equipment Qualification Requirements"	Guideline for the Management of Adverse Localized Equipment (TR-109619)
			Guideline for Sampling in the Commercial-Grade Item Acceptance Process (TR-017218-R1)
			Age-Related Degradation Inspection Method and Demonstration: In Behalf of Calvert Cliffs Nuclear Power Plant License Renewal Application (TR-107514)
			Medium Voltage Cable Aging Management Guide, Revision 1 (1021070)
			Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1 (3002000557)
			Aging Power Cable Maintenance Guideline (1024044)
			Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants (1022969)
			Long-Term Operations Program: Assessment of Research and Development Supporting Aging Management Programs for Long-Term Operation (3002000576)
			Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1 (3002010641)
XI.E2, "Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits"	XI.E2, "Electrical Insulation for Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits"	AMP202, "Electrical Insulation for Electrical Cables and Connections Not Subject to Equipment Qualification Requirements Used in Instrumentation Circuits"	Guideline for the Management of Adverse Localized Equipment (TR-109619)
			High Range Radiation Monitor Cable Study: Phase I (TR-110379)
			High Range Radiation Monitor Cable Study: Phase II (TR-112582)
			Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1 (3002010641)
XI.E3A, "Inaccessible Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"	XI.E3A, "Electrical Insulation for Inaccessible Medium-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements" XI.E3B, "Electrical Insulation for Inaccessible Instrument and Control Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements" XI.E3C, "Electrical Insulation for Inaccessible Low-Voltage Power Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements"	AMP203, "Electrical Insulation for Inaccessible Instrumentation and Control and Low and Medium Voltage Power Cables Not Subject to Equipment Qualification Requirements" AMP 223, "Electrical Insulation for Medium Voltage Shielded Cables and Connections Not Subject to Equipment Qualification Requirements"	Guideline for the Management of Adverse Localized Equipment (TR-109619)
			Plant Support Engineering: License Renewal Electrical Handbook (1013475)	Effects of Moisture on the Life of Power Plant Cables (TR-103834-P1-2(Archived)) is referenced in the GALL (R2) AMP
			Long-Term Operations: Subsequent License Renewal Electrical Handbook (3002010401)
			Plant Engineering: Low-Voltage Cable Susceptibility to Wet Aging (3002007991)
			Plant Engineering: Cable Aging Management Program Implementation Guidance (1022968)
			Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants (1022969)
			Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1 (3002000557)
			Plant Engineering: Evaluation and Insights from Nuclear Power Plant Tan Delta Testing and Data Analysis - Update (3002005321)	Initial Version (1025262) is referenced in the IGALL AMP
			Low-Voltage and Instrumentation and Control Cable Aging Management Guide, Revision 1 (3002010641)
			Instrumentation and Control Connector Operating Experience and Maintenance Guide (3002018370)
			Long-Term Operations Program: Assessment of Research and Development Supporting Aging Management Programs for Long-Term Operation (3002000576)
			Medium Voltage Cable Aging Management Guide, Revision 1 (1021070)
			Cable Polymer Aging and Condition Monitoring Research at Sandia National Laboratories Under the Nuclear Energy Plant Optimization (NEPO) Program (1011873)
			Aging Power Cable Maintenance Guideline (1024044)
			Equipment Failure Modeling for Underground Distribution Cables (1012498)	Initial Revision (1008560) is referenced in IGALL AMP
XI.E4, "Metal-Enclosed Bus"	XI.E4, "Metal-Enclosed Bus"	AMP204, "Metal Enclosed Bus Not Subject to Equipment Qualification Requirements"	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide (1013457)
			Electrical Connector Application Guidelines (1003471)
			Infrared Thermography Guide (3002012582)	2002 Version(Archived) of the Infrared Thermography Guide is referenced in the GALL-SLR AMP
			Plant Support Engineering: License Renewal Electrical Handbook (1013475)	2001 Version(Archived) of the LR Electrical Handbook is referenced in the GALL-SLR AMP
			Long-Term Operations: Subsequent License Renewal Electrical Handbook (3002010401)
XI.E6, "Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	XI.E6, "Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements"	AMP206, "Electrical Cable Connections Not Subject to Equipment Qualification Requirements"	Nuclear Maintenance Applications Center: Bolted Joint Fundamentals, Revision 1 (3002015824)	Bolted Joint Maintenance & Application Guide (104213(Archived)) is referenced in the GALL (R2) and GALL-SLR AMP Initial version of Bolted Joint Fundamentals (1015336(Archived)) is referenced in the IGALL AMP
			Guideline for the Management of Adverse Localized Equipment (TR-109619)
			Electrical Connector Application Guidelines (1003471)
	XI.E7, "High-Voltage Insulators"	AMP208, "High Voltage Insulators and Transmission Conductors"	Long-Term Operations: Subsequent License Renewal Electrical Handbook (3002010401)	Parameters that influence the Aging and Degradation of Overhead Conductors (1001997(Archived)) is also referenced in the GALL-SLR and IGALL AMP
			Plant Support Engineering: License Renewal Electrical Handbook (1013475)
			Oconee Electrical Component Integrated Plant Assessment and Time Limited Aging Analyses for License Renewal: Revision 1 (1000174)
XI.M2, "Water Chemistry" XI.M20, "Open-Cycle Cooling Water System" XI.M21A, "Closed-Cycle Cooling Water Systems" XI.M32, "One-Time Inspection"	XI.M2, "Water Chemistry" XI.M20, "Open-Cycle Cooling Water System" XI.M21A, "Closed-Cycle Cooling Water Systems" XI.M32, "One-Time Inspection"	AMP155, "PWR Residual Heat Removal Heat Exchangers	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide (1018089)	Heat Exchangers: Over of Maintenance and Operation (TR-106741(Archived)) is referenced in the IGALL AMP
			Preventive Maintenance Basis Database (PMBD) v7.0 (PMBD), Heat Exchanger Templates	Preventive Maintenance Basis, Volume 32: Heat exchangers Condition Assessment Program (BOPHX-01, Rev 1(Archived)) is referenced in the IGALL AMP
			Heat Exchanger Performance Monitoring Guidelines (NP-7552)
XI.M1, "ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD" XI.M2, "Water Chemistry" XI.M10, "Boric Acid Corrosion"	XI.M1, "ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD" XI.M2, "Water Chemistry" XI.M10, "Boric Acid Corrosion"	AMP159, "PWR Emergency Core Cooling System Hydro-Accumulators"	EPRI Materials Degradation Matrix, Revision 4 (3002013781)
X.M1, "Fatigue Monitoring" 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.M31, "Reactor Vessel Surveillance"	X.M1, "Fatigue Monitoring" 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.M31, "Reactor Vessel Material Surveillance" X.M2, "Neutron Fluence Monitoring"	AMP162, "PWR Reactor Pressure Vessel"	Materials Reliability Program: Effects of Thermal Ageing on Reactor Coolant System Pressure Boundary Materials (MRP-438), Low Alloy Ferritic Steels (3002016009)
		AMP162, "PWR Reactor Pressure Vessel"	Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 2) (3002020105)	Revsion 1-A (3002017168) is also referenced in the IGALL 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	Note
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.	Materials Reliability Program: Generic Guidance for Alloy 600 Management (MRP-126) (1009561)
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.	Preventive Maintenance Basis Database (PMBD) v7.0 (PMBD)
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.	Centrifugal and Positive Displacement Charging Pump Maintenance Guide (TR-107252)
Safety-related Pumps	AMP144		Preventive Maintenance Basis Database (PMBD) v7.0 (PMBD)
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.	Nuclear Maintenance Applications Center: Heat Exchanger Maintenance Guide (1018089)
			Preventive Maintenance Basis Database (PMBD) v7.0 (PMBD), Heat Exchanger Templates
			Supplemental Guidance for Testing and Monitoring Service Water Heat Exchangers (1003320)
			Service Water Heat Exchanger Testing Guidelines (3002005340)
			Heat Exchanger Performance Monitoring Guidelines (NP-7552)
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.	EPRI Materials Degradation Matrix, Revision 4 (3002013781)
CANDU/PHWR Inspection Programmes	AMP146		Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4) (3002000563)
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 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.	EPRI Materials Degradation Matrix, Revision 4 (3002013781)
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.	Plant Support Engineering: Life Cycle Management Planning Sourcebooks - Chillers (1015075)
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.	EPRI Materials Degradation Matrix, Revision 4 (3002013781)
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.	EPRI Power Transformer Guidebook: The Copper Book (3002026941)	Previous Revision (3002021342(Archived)) is referenced in the IGALL AMP
			Plant Support Engineering: Large Transformer End-of-Expected-Life Considerations and the Need for Planning (1013566)
			Plant Engineering: Medium-Voltage Transformer End of Expected Life Guidance (1025261)
			On-Line Monitoring Diagnostic Analysis for Large Power Transformers (3002000753)
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.	Aging Assessment Field Guide (1007933)
	AMP212		Aging Identification and Assessment Checklist: Mechanical Components (1009743)
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.	Guidelines for the Monitoring of Aging of I&C Electronic Components (1008166)
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.	Guide for Rotating Machine Stator Winding Hipot Testing (1014908)
			Medium-Voltage Motor and Cable, Very-Low-Frequency (VLF) Tan Delta Testing from the Cable Termination: VLF Motor and Cable Testing (3002016077)
			Life Cycle Management Planning Sourcebooks, Volume 5: Main Generator (1007423)
			Electric Motor Tiered Maintenance Program (1003095)
			Minimum Recommendations to Maintain Electric Motor Reliability (3002016079)
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.	Aging Assessment Field Guide (1007933)
			Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide (1013457)
			Aging Identification and Assessment Checklist: Electrical Components (1011223)
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.	Guidelines for the Monitoring of Aging of I&C Electronic Components (1008166)
			Collected Field Data on Electronic Part Failures and Aging in Nuclear Power Plant Instrumentation and Control (I&C) Systems (1003568)
			Technical Guidance for Detection of Oil-Loss Failure of Rosemount Pressure Transmitters (NP-7121)
			Nuclear Maintenance Applications Center: Guidelines for the Maintenance Management of Plant Sensors (1021429)
			Survey and Characterization of Feedwater Venturi Fouling at Nuclear Power Plants (TR-100514-V1)
			Survey and Characterization of Feedwater Venturi Fouling at Nuclear Power Plants: Volume 2: Photomicrograph and Chemical Analyses (TR-100514-V2)
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.	Guidelines for the Monitoring of Aging of I&C Electronic Components (1008166)
			Evaluating the Effects of Aging on Electronic Instrument and Control Circuit Boards and Components in Nuclear Power Plants (1011709)
			Collected Field Data on Electronic Part Failures and Aging in Nuclear Power Plant Instrumentation and Control (I&C) Systems (1003568)
			Guidance for Aging Management of Instrumentation and Control (I&C) Circuit Cards and Components Based on Electricite de France (EDF)Experience (1022246)
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.	Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide (1013457)
			Industry Practices Related to the Application and Maintenance of Grounding Systems for Nuclear Power Plant Switchyards ([2])	Transmission Line Surge Arrestor - White Paper (1010233(Archived)) is referenced in the IGALL AMP
			Surge Arresters—Mechanical and Aging Testing (3002018920)
			Nuclear Maintenance Applications Center: Switchyard Equipment Application and Maintenance Guide (1026664)
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 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.	Electric Motor Predictive and Preventive Maintenance Guide (NP-7502)
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.	Preventive Maintenance Basis Database (PMBD) v7.0 (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.	New Equipment and Performance Design Review - LTC Management Course Materials (1012350)
			Development of a Filter Using Absorbent Technologies for the Removal of Coking Precursors: Laboratory Evaluation (1002048)
			Development of a New Acoustic Emissions Technique for the Detection and Location of Gassing Sources in Power Transformers and LTCs: Phase 2 Results (1011708)	Development of On-Line Monitoring to Detect Gassing in Load Tap Changers (1008811(Archived)) is referenced in IGALL AMP
			Quick Guide: Continuous Online Monitoring (COLM)—Station MPT_GSU with De-Energized Tap Changer (DETC) (3002016977)
			Load Tap Changer Management Seminar (1016261)
			Development of Load Tap Changer Monitoring Technique: Mechanism of Coking (1001946)
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.	Generator Maintenance Guide for Emergency Diesel Generators (3002005014)	Previous Revision (1019146(Archived)) is also referenced in IGALL AMP
	AMP230		On-Line Monitoring of Emergency Diesel Generators (3002000742)
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.	Nuclear Maintenance Applications Center: Isolated Phase Bus Maintenance Guide (1015057)
			Preventive Maintenance Basis Database (PMBD) v7.0 (PMBD)
			Guideline for System Monitoring by System Engineers (3002026348)	Initial Revision (TR-107668(Archived)) is referenced in the IGALL AMP
			Infrared Thermography Guide (3002012582)	Revision 3 (1006534(Archived)) is referenced in the IGALL AMP
			Nuclear Maintenance Applications Center: Switchgear and Bus Maintenance Guide (1013457)
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.	Program on Technology Innovation: Retrofitted Sensors for Nuclear Containment Structures (3002007819)
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.	Tools for Early Detection of ASR in Concrete Structures (3002005389)
			Concrete Nondestructive Evaluation for Damage Due to Pattern Cracking - Alkali Silica Reaction and Freeze-Thaw Damage (3002007806)
			Long-Term Operations: Aging Management of Concrete Structures Affected by Alkali-Silica Reaction (3002016056)
			Mitigation and Repair of Concrete Structures Affected by Alkali-Silica Reaction (ASR) (3002010300)
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.
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.	Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools) (3002013084)	Program on Technology Innovation: Assessment of Software Platforms for Aging Management of Large Civil Structure (3002007810(Archived)) and Corrosion Mitigation of Conventionally Reinforced Concrete Structures (3002003090(Archived)) are also referenced in the IGALL AMP
			Field Guide: Visual Inspection of Concrete Structures in the Nuclear Fleet (3002007799)
			Program on Technology Innovation: Nondestructive Evaluation Inspection of Concrete Structures Subjected to Corrosion (1025627)
			Advanced Nuclear Technology: Embedded Sensors in Concrete (1023006)
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.	Field Guide: Coatings Assessment (1025323)
	AMP322		Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools) (1015078)
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.

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0	6/11/2024	Initial version

Aging Management Programs (AMPs)

Contents

GALL vs IGALL Elements of an Effective Aging Management Program[edit]

Aging Management Programs in the GALL[edit]

Operating Experience[edit]

Enhancements and Exceptions[edit]

Aging Management Programs in the IGALL[edit]

US GALL[edit]

GALL AMP Descriptions[edit]

Interim Staff Guidance (ISG) Affecting AMPs[edit]

EPRI References by AMP[edit]

Matching GALL, GALL-SLR and IGALL AMPs[edit]

IGALL AMPs that are NOT included in GALL[edit]

Record of Revisions[edit]

Navigation menu

Aging Management Programs (AMPs)

GALL vs IGALL Elements of an Effective Aging Management Program[edit]

Aging Management Programs in the GALL[edit]

Operating Experience[edit]

Enhancements and Exceptions[edit]

Aging Management Programs in the IGALL[edit]

US GALL[edit]

GALL AMP Descriptions[edit]

Interim Staff Guidance (ISG) Affecting AMPs[edit]

EPRI References by AMP[edit]

Matching GALL, GALL-SLR and IGALL AMPs[edit]

IGALL AMPs that are NOT included in GALL[edit]

Record of Revisions[edit]

Navigation menu

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