Text

NUREG-2192, Revision 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, Draft Report for Comment, Corrected Tables 3.1-1 and 3.2-1
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Issue date:	08/04/2023
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1 Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System 2 Evaluated in Chapter IV of the GALL-SLR Report Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 001 Boiling water Steel reactor Cumulative fatigue TLAA, Standard Yes (SRP-SLR IV.A1.RP-201 reactor (BWR) / vessel (RV) closure damage: cracking Review Plan for Section 3.1.2.2.1) IV.A2.RP-54 pressure water flange assembly due to fatigue, Review of reactor (PWR) components cyclic loading Subsequent exposed to air- License Renewal indoor uncontrolled (SRP-SLR)

Section 4.3 Metal Fatigue 3.1-30 002 PWR Nickel-alloy tubes Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.D1.R-46 and sleeves damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.D2.R-46 exposed to reactor due to fatigue, Fatigue coolant, secondary cyclic loading feedwater/steam 003 BWR/PWR Stainless steel Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.B1.R-53 (SS), nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.B2.RP-303 reactor vessel due to fatigue, Fatigue IV.B3.RP-339 internal (RVI) cyclic loading IV.B4.R-53 components exposed to reactor coolant, neutron flux 004 BWR/PWR Steel pressure Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.A1.R-70 vessel support skirt damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.A2.R-70 and attachment due to fatigue, Fatigue welds cyclic loading 3

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 005 PWR Steel, SS, steel Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.C2.R-13 (with SS or nickel damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.C2.R-18 alloy cladding) due to fatigue, Fatigue IV.D1.R-33 steam generator cyclic loading IV.D2.R-33 components, pressurizer relief tank components, piping components, bolting 3.1-31 006 BWR SS, steel (with or Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.C1.R-220 without nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) or SS cladding), due to fatigue, Fatigue nickel alloy reactor cyclic loading coolant pressure boundary components:

piping, piping components; other pressure retaining components exposed to reactor coolant 007 BWR SS, steel (with or Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.A1.R-04 without nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) or SS cladding), due to fatigue, Fatigue nickel-alloy RV cyclic loading components:

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item nozzles, penetrations, safe ends, thermal sleeves, vessel shells, heads and welds exposed to reactor coolant 008 PWR SS, steel (with or Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.D1.R-221 without nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.D2.R-222 3.1-32 or SS cladding), due to fatigue, Fatigue nickel-alloy steam cyclic loading generator components exposed to reactor coolant 009 PWR SS, steel (with or Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.C2.R-223 without nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) or SS cladding), due to fatigue, Fatigue nickel-alloy reactor cyclic loading coolant pressure boundary piping, piping components, other pressure retaining components exposed to reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item E 010 PWR Steel (with or Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.A2.R-219 without nickel alloy damage: cracking Section 4.3 Metal Section 3.1.2.2.1) or stainless steel due to fatigue, Fatigue cladding), SS, or cyclic loading nickel-alloy RV components:

nozzles, penetrations, pressure housings, 3.1-33 safe ends; thermal sleeves, vessel shells, heads and welds exposed to reactor coolant E 011 BWR/PWR Steel or SS pump Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR IV.C1.RP-44 and valve closure damage: cracking Section 4.3 Metal Section 3.1.2.2.1) IV.C2.RP-44 bolting exposed to due to fatigue, Fatigue high temperatures cyclic loading and thermal cycles 012 PWR Steel steam Loss of material AMP XI.M1, Yes (SRP-SLR IV.D1.RP-368 generator due to general, ASME Section XI Sections components: upper pitting, crevice Inservice 3.1.2.2.2.1 and and lower shells, corrosion Inspection, 3.1.2.2.2.2) transition cone, Subsections IWB, new transition cone IWC, and IWD, closure weld and AMP XI.M2, exposed to Water Chemistry

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item secondary feedwater or steam 013 BWR/PWR Steel (with or Loss of fracture TLAA, SRP-SLR Yes (SRP-SLR IV.A1.R-62 without stainless toughness due to Section 4.2 Section 3.1.2.2.3.1) IV.A2.R-84 steel or nickel-alloy neutron irradiation Reactor Pressure cladding) reactor embrittlement Vessel Neutron vessel beltline Embrittlement shell, nozzle, and weld components 3.1-34 exposed to reactor coolant and neutron flux 014 BWR/PWR Steel (with or Loss of fracture AMP XI.M31, Yes (SRP-SLR IV.A1.RP-227 without cladding) toughness due to Reactor Vessel Section 3.1.2.2.3.2) IV.A2.RP-229 reactor vessel neutron irradiation Material beltline shell, embrittlement Surveillance, and nozzle, and weld AMP X.M2, components, Neutron Fluence exposed to reactor Monitoring coolant and neutron flux E 015 PWR Stainless steel Reduction in TLAA, SRP-SLR Yes (SRP-SLR IV.B4.RP-376 Babcock & Wilcox fracture toughness Section 4.7 Other Section 3.1.2.2.3.3)

(B&W) (including due to neutron Plant-Specific cast austenitic irradiation TLAAs stainless steel

[CASS], martensitic

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item SS, and precipitation-hardened [PH] SS) and nickel-alloy RVI components exposed to reactor coolant and neutron flux 016 BWR SS or nickel-alloy Cracking due to AMP XI.M32, Yes (SRP-SLR IV.A1.R-61a 3.1-35 reactor vessel top SCC, intergranular One-Time Section 3.1.2.2.4.1) IV.A1.R-61b head enclosure stress corrosion Inspection, or flange leakage cracking (IGSCC) AMP XI.M36, detection line External Surfaces exposed to air- Monitoring of indoor Mechanical uncontrolled, Components reactor coolant leakage 017 BWR SS isolation Cracking due to AMP XI.M1, Yes (SRP-SLR IV.C1.R-15 condenser SCC, irradiation- ASME Section XI Section 3.1.2.2.4.2) components assisted stress Inservice exposed to reactor corrosion cracking Inspection, coolant (IGSCC) Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 018 PWR RV shell fabricated Crack growth due TLAA, SRP-SLR Yes (SRP-SLR IV.A2.R-85 of SA508-Cl 2 to cyclic loading Section 4.7 Other Section 3.1.2.2.5) forgings clad with Plant-Specific SS using a high- TLAAs heat-input welding process exposed to reactor coolant M 019 PWR SS RV bottom- Cracking due to AMP XI.M1, No IV.A2.RP-154 mounted stress corrosion ASME Section XI 3.1-36 instrument guide cracking (SCC) Inservice tubes (external to Inspection, RV) exposed to Subsections IWB, reactor coolant IWC, and IWD, and AMP XI.M2, Water Chemistry M 020 PWR cast austenitic Cracking due to AMP XI.M1, No IV.C2.R-05 stainless steel SCC ASME Section XI (CASS) Class 1 Inservice piping, piping Inspection, components Subsections IWB, exposed to reactor IWC, and IWD, coolant and AMP XI.M2, Water Chemistry 021 BWR Steel and SS Cracking due to AMP XI.M1, Yes (SRP-SLR IV.C1.R-225 isolation condenser cyclic loading ASME Section XI Section 3.1.2.2.7) components Inservice Inspection,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor Subsections IWB, coolant IWC, and IWD 022 PWR Steel steam Loss of material Plant-specific aging Yes (SRP-SLR IV.D1.R-39 generator (SG) due to erosion management Section 3.1.2.2.8) feedwater program impingement plate and support exposed to secondary 3.1-37 feedwater M 025 PWR Steel (with nickel- Cracking due to AMP XI.M2, Water Yes (SRP-SLR IV.D1.RP-367 alloy cladding) or primary water SCC Chemistry, and Sections IV.D1.RP-385 nickel-alloy SG AMP XI.M19, 3.1.2.2.11.1 and IV.D2.RP-185 (primary side Steam Generator 3.1.2.2.11.2) components: In addition, use of divider plate and the One-Time tube-to-tube sheet Inspection AMP is welds exposed to to be evaluated reactor coolant M 028 PWR Westinghouse- Loss of material AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-355 (if specific Existing due to wear; PWR Vessel Section 3.1.2.2.9) AMP XI.M16A is Programs cracking due to Internals, and credited for aging components: SS, SCC, irradiation- AMP XI.M2, Water management) nickel-alloy, and X- assisted stress Chemistry (for 750 control rod corrosion cracking SCC mechanisms IV.E.R-444 (if guide tube support (IASCC), fatigue only) components are pins (split pins) defined as ASME

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor Section XI category coolant and components and neutron flux the XI.M1 inservice inspection AMP is credited for aging management)

IV.B2.RP-265 (if components can be 3.1-38 placed in the No Additional Measures category)

M 029 BWR Nickel-alloy core Cracking due to AMP XI.M9, BWR No IV.B1.R-94 shroud and core SCC, IGSCC, Vessel Internals, plate access hole IASCC and AMP XI.M2, cover (welded Water Chemistry covers) exposed to reactor coolant 030 BWR Stainless steel, Cracking due to AMP XI.M1, No IV.A1.RP-371 nickel alloy SCC, IGSCC, ASME Section XI penetration: drain cyclic loading Inservice line exposed to Inspection, reactor coolant Subsections IWB, IWC, and IWD, and AMP XI.M2, Water Chemistry

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item (SCC, IGSCC mechanisms only) 031 BWR Steel and SS Loss of material AMP XI.M1, No IV.C1.RP-39 isolation condenser due to general ASME Section XI components (steel only), pitting, Inservice exposed to reactor crevice corrosion, Inspection, coolant wear Subsections IWB, IWC, and IWD, and AMP XI.M2, 3.1-39 Water Chemistry D 032 033 PWR SS, steel with SS Cracking due to AMP XI.M1, No IV.C2.R-09 cladding Class 1 SCC ASME Section XI IV.C2.R-217 reactor coolant Inservice IV.C2.RP-344 pressure boundary Inspection, IV.D1.RP-232 components Subsections IWB, exposed to reactor IWC, and IWD, coolant and AMP XI.M2, Water Chemistry E 034 PWR SS, steel with SS Cracking due to AMP XI.M1, No IV.C2.RP-231 cladding SCC ASME Section XI pressurizer relief Inservice tank (tank shell and Inspection, heads, flanges, Subsections IWB, nozzles) exposed IWC, and IWD, to treated borated and AMP XI.M2, Water Chemistry

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item water >60 °C

(>140 °F) 035 PWR SS, steel with SS Cracking due to AMP XI.M1, No IV.C2.R-56 cladding reactor cyclic loading ASME Section XI coolant system Inservice cold leg, hot leg, Inspection, surge line, and Subsections IWB, spray line piping IWC, and IWD and fittings 3.1-40 exposed to reactor coolant 036 PWR Steel, SS Cracking due to AMP XI.M1, No IV.C2.R-19 pressurizer integral cyclic loading ASME Section XI support exposed to Inservice any environment Inspection, Subsections IWB, IWC, and IWD 037 PWR Steel reactor Loss of material AMP XI.M1, No IV.A2.R-87 vessel flange due to wear ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD 038 BWR/PWR CASS Class 1 Loss of fracture AMP XI.M1, No IV.C1.R-08 valve bodies and toughness due to ASME Section XI IV.C2.R-08 bonnets exposed thermal aging Inservice embrittlement Inspection,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item to reactor coolant Subsections IWB,

>250 °C (>482 °F) IWC, and IWD E 039 BWR/PWR SS, steel (with or Cracking due to AMP XI.M1, No IV.C1.RP-230 without nickel-alloy SCC (for SS or ASME Section XI IV.C2.RP-235 or SS cladding), nickel-alloy Inservice nickel-alloy Class 1 surfaces exposed Inspection, piping, fittings and to reactor coolant Subsections IWB, branch connections only), IGSCC (for IWC, and IWD,

<nominal pipe size stainless steel or AMP XI.M2, Water 3.1-41 (NPS) 4 exposed nickel-alloy Chemistry, and to reactor coolant surfaces exposed XI.M35, ASME to reactor coolant Code Class 1 only), or thermal, Small-Bore Piping mechanical, or vibratory loading 040 PWR Steel with SS or Cracking due to AMP XI.M1, No IV.C2.R-58 nickel-alloy cyclic loading ASME Section XI cladding, or SS Inservice pressurizer Inspection, components Subsections IWB, exposed to reactor IWC, and IWD coolant 040a PWR Nickel-alloy core Cracking due to AMP XI.M1, No IV.A2.RP-57 support pads, core primary water SCC ASME Section XI guide lugs exposed Inservice to reactor coolant Inspection, Subsections IWB,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item IWC, and IWD, and AMP XI.M2, Water Chemistry M 041 BWR Nickel-alloy core Cracking due to AMP XI.M9, BWR No IV.B1.R-95 shroud and core SCC, IGSCC, Vessel Internals, plate access hole IASCC and AMP XI.M2, cover (mechanical Water Chemistry covers) exposed to reactor coolant 3.1-42 042 PWR Steel with SS or Cracking due to AMP XI.M1, No IV.C2.R-25 nickel-alloy SCC, primary ASME Section XI IV.D2.RP-47 cladding, SS water SCC Inservice primary side Inspection, components, SG Subsections IWB, upper and lower IWC, and IWD, heads, and and AMP XI.M2, tubesheet welds Water Chemistry pressurizer components exposed to reactor coolant 043 BWR SS and nickel-alloy Loss of material AMP XI.M1, No IV.B1.RP-26 RVI exposed to due to pitting, ASME Section XI reactor coolant crevice corrosion Inservice Inspection, Subsections IWB, IWC, and IWD,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item and AMP XI.M2, Water Chemistry 044 PWR Steel SG Loss of material AMP XI.M1, No IV.D1.R-31 secondary manway due to erosion ASME Section XI IV.D2.R-31 and handhole Inservice cover seating Inspection, surfaces exposed Subsections IWB, to treated water, IWC, and IWD steam 3.1-43 E 045 PWR Nickel-alloy, steel Cracking due to AMP XI.M1, No IV.A2.R-90 with nickel-alloy primary water SCC ASME Section XI IV.A2.RP-186 cladding reactor Inservice IV.A2.RP-59 coolant pressure Inspection, IV.C2.RP-156 boundary Subsections IWB, IV.C2.RP-159 components IWC and IWD, and IV.C2.RP-37 exposed to reactor AMP XI.M2, IV.D1.RP-36 coolant Water Chemistry, IV.D2.RP-36 and, for nickel-alloy, AMP XI.M11B, Cracking of Nickel-Alloy Components and Loss of Material due to Boric Acid-Induced Corrosion in reactor coolant pressure boundary

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item (RCPB)

Components (PWRs Only)

E 046 PWR SS, nickel-alloy Cracking due to AMP XI.M1, No IV.A2.RP-234 control rod drive SCC, primary ASME Section XI head penetration water SCC Inservice pressure housings, Inspection, RV nozzles, nozzle Subsections IWB, safe ends and IWC and IWD, and 3.1-44 welds exposed to AMP XI.M2, reactor coolant Water Chemistry, and, for nickel-alloy, AMP XI.M11B, Cracking of Nickel-Alloy Components and Loss of Material due to Boric Acid-Induced Corrosion in RCPB Components (PWRs Only) 047 PWR SS, nickel-alloy Cracking due to AMP XI.M1, No IV.A2.RP-55 control rod drive SCC, primary ASME Section XI head penetration water SCC Inservice pressure housing Inspection, Subsections IWB,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor IWC and IWD, and coolant AMP XI.M2, Water Chemistry E 048 PWR Steel external Loss of material AMP XI.M10, No IV.A2.RP-379 surfaces: RV top due to boric acid Boric Acid IV.C2.RP-380 head, RV bottom corrosion Corrosion, and head, reactor AMP XI.M11B, coolant pressure Cracking of boundary piping or Nickel-Alloy 3.1-45 components Components and adjacent to Loss of Material dissimilar metal due to Boric Acid-(Alloy 82/182) Induced Corrosion welds exposed to in RCPB air with borated Components water leakage (PWRs Only) 049 PWR Steel reactor, Loss of material AMP XI.M10, No IV.A2.R-17 vessel, piping, due to boric acid Boric Acid IV.C2.R-17 piping components corrosion Corrosion IV.C2.RP-167 in the reactor IV.D1.R-17 coolant pressure IV.D2.R-17 boundary of PWRs, and applicable exterior attachments, or steel steam generators in

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item PWRs: external surfaces or closure bolting exposed to air with borated water leakage 050 BWR/PWR CASS Class 1 Loss of fracture AMP XI.M12, No IV.A2.R-77 piping, piping toughness due to Thermal Aging IV.C1.R-52 components thermal aging Embrittlement of IV.C2.R-52 (including pump embrittlement Cast Austenitic 3.1-46 casings and control Stainless Steel rod drive pressure (CASS) housings) exposed to reactor coolant

>250 °F (>482 °C)

M 051a PWR SS, nickel-alloy Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B4.RP-241 Babcock and SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B4.RP-241a Wilcox (B&W) fatigue Internals, and IV.B4.RP-242a reactor internal AMP XI.M2, Water IV.B4.RP-247 Primary Chemistry (for IV.B4.RP-247a components SCC mechanisms IV.B4.RP-248 exposed to reactor only) IV.B4.RP-248a coolant, neutron IV.B4.RP-252c flux IV.B4.RP-256 IV.B4.RP-256a IV.B4.RP-261

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item M 051b PWR SS, nickel-alloy Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B4.RP-244 B&W reactor SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B4.RP-245 internal fatigue, overload Internals, and IV.B4.RP-245a Expansion AMP XI.M2, Water IV.B4.RP-246 components Chemistry (for IV.B4.RP-246a exposed to reactor SCC mechanisms IV.B4.RP-246c coolant, neutron only) IV.B4.RP-246d flux IV.B4.RP-260a IV.B4.RP-262 3.1-47 IV.B4.RP-352 M 052a PWR SS, nickel-alloy Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-312 Combustion SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B3.RP-314 Engineering (CE) fatigue Internals, and IV.B3.RP-322 reactor internal AMP XI.M2, Water IV.B3.RP-324 Primary Chemistry (for IV.B3.RP-327 components SCC mechanisms IV.B3.RP-328 exposed to reactor only) IV.B3.RP-338 coolant, neutron IV.B3.RP-342 flux IV.B3.RP-343 IV.B3.RP-358 IV.B3.RP-362a M 052b PWR SS, nickel-alloy CE Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-313 reactor internal SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B3.RP-316 Expansion fatigue Internals, and IV.B3.RP-323 components AMP XI.M2, IV.B3.RP-325 exposed to reactor Water Chemistry IV.B3.RP-329 IV.B3.RP-330

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item coolant, neutron (for SCC IV.B3.RP-333 flux mechanisms only) IV.B3.RP-335 IV.B3.RP-362c IV.B3.RP-363 M 052c PWR SS, nickel-alloy CE Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-320 reactor internal SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B3.RP-320a Existing fatigue Internals, and IV.B3.RP-334 Programs AMP XI.M2, components Water Chemistry 3.1-48 exposed to reactor (for SCC coolant, neutron mechanisms only) flux M 053a PWR SS, nickel-alloy Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-270a Westinghouse SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B2.RP-271 reactor internal fatigue Internals, and IV.B2.RP-275 Primary AMP XI.M2, IV.B2.RP-276 components Water Chemistry IV.B2.RP-296a exposed to reactor (for SCC IV.B2.RP-298 coolant, neutron mechanisms only) IV.B2.RP-302 flux IV.B2.RP-387 M 053b PWR SS Westinghouse Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-273 reactor internal SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B2.RP-280 Expansion fatigue Internals, and IV.B2.RP-286 components AMP XI.M2, IV.B2.RP-291 exposed to reactor Water Chemistry IV.B2.RP-291a coolant and (for SCC IV.B2.RP-291b neutron flux mechanisms only)

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item IV.B2.RP-293 IV.B2.RP-294 IV.B2.RP-298a IV.B2.RP-387a M 053c PWR SS, nickel-alloy, or Cracking due to AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-289 stellite SCC, IASCC, PWR Vessel Section 3.1.2.2.9) IV.B2.RP-301 Westinghouse fatigue Internals, and IV.B2.RP-345a reactor internal AMP XI.M2, IV.B2.RP-346 Existing Water Chemistry IV.B2.RP-399 3.1-49 Programs (for SCC components mechanisms only) exposed to reactor coolant, neutron flux M 054 PWR SS Westinghouse- Loss of material AMP XI.M37, No IV.B2.RP-284 design bottom- due to wear Flux Thimble Tube mounted Inspection instrument system flux thimble tubes (with or without chrome plating) exposed to reactor coolant and neutron flux 055a PWR SS, nickel alloy No additional aging AMP XI.M16A, Yes (SRP-SLR IV.B4.RP-236 B&W reactor management for PWR Vessel Section 3.1.2.2.9) internal No reactor internal No Internals

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item Additional Additional Measures Measures components components unless exposed to reactor required by ASME coolant, neutron Section XI, flux Examination Category B-N-3 or relevant operating experience exists 3.1-50 055b PWR SS, nickel-alloy CE No additional aging AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-306 reactor internal No management for PWR Vessel Section 3.1.2.2.9)

Additional reactor internal No Internals Measures Additional components Measures exposed to reactor components unless coolant, neutron required by ASME flux Section XI, Examination Category B-N-3 or relevant operating experience exists 055c PWR SS, nickel-alloy No additional aging AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-265 Westinghouse management for PWR Vessel Section 3.1.2.2.9) reactor internal No reactor internal No Internals Additional Additional Measures Measures components components unless

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor required by ASME coolant, neutron Section XI, flux Examination Category B-N-3 or relevant operating experience exists M 056a PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-315 CASS, toughness due to PWR Vessel Section 3.1.2.2.9) IV.B3.RP-318 precipitation- neutron irradiation Internals IV.B3.RP-326 3.1-51 hardening (PH) SS embrittlement and IV.B3.RP-338a or martensitic SS for CASS, IV.B3.RP-359 or nickel-alloy CE martensitic SS, and IV.B3.RP-360 reactor internal PH SS due to IV.B3.RP-362 Primary thermal aging IV.B3.RP-365 components embrittlement, IV.B3.RP-366 exposed to reactor changes in coolant and dimensions due to neutron flux void swelling, distortion, loss of preload due to thermal and irradiation-enhanced stress relaxation or creep, loss of material due to wear

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item M 056b PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-317 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B3.RP-331 martensitic SS CE neutron irradiation Internals IV.B3.RP-333a Expansion embrittlement and IV.B3.RP-359a reactor internal for CASS, IV.B3.RP-361 components martensitic SS, and IV.B3.RP-362b exposed to reactor PH SS due to IV.B3.RP-364 coolant and thermal aging IV.B3.R-455 neutron flux embrittlement, 3.1-52 changes in dimensions due to void swelling, distortion, loss of preload due to thermal and irradiation-enhanced stress relaxation or creep, loss of material due to wear M 056c PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B3.RP-319 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B3.RP-332 martensitic SS or neutron irradiation Internals IV.B3.RP-336 nickel-alloy CE embrittlement and IV.B3.RP-357 reactor internal for CASS, Existing martensitic SS, and Programs PH SS due to components thermal aging

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor embrittlement, coolant and changes in neutron flux dimensions due to void swelling, distortion, loss of preload due to thermal and irradiation-enhanced stress 3.1-53 relaxation or creep, loss of material due to wear M 058a PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B4.RP-240 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B4.RP-240a martensitic SS, neutron irradiation Internals IV.B4.RP-242 nickel-alloy B&W embrittlement and IV.B4.RP-247b reactor internal for CASS, IV.B4.RP-247c Primary martensitic SS, and IV.B4.RP-248b components PH SS due to IV.B4.RP-249 exposed to reactor thermal aging IV.B4.RP-251 coolant and embrittlement, or IV.B4.RP-251a neutron flux changes in IV.B4.RP-252 dimensions due to IV.B4.RP-252b void swelling or IV.B4.RP-256b distortion, or loss of IV.B4.RP-258 preload due to IV.B4.RP-259 wear; or loss of

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item material due to wear M 058b PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B4.RP-243 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B4.RP-243a martensitic SS, neutron irradiation Internals IV.B4.RP-245b nickel-alloy B&W embrittlement and IV.B4.RP-245c reactor internal for CASS, IV.B4.RP-246b Expansion martensitic SS, and IV.B4.RP-246e components PH SS due to IV.B4.RP-250 3.1-54 exposed to reactor thermal aging IV.B4.RP-252a coolant and embrittlement, or IV.B4.RP-260 neutron flux changes in iv.B4.RP-386 dimensions due to void swelling, or distortion, or loss of preload due to thermal and irradiation-enhanced stress relaxation or creep, or loss of material due to wear 059a PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-270 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B2.RP-272 martensitic SS or neutron irradiation Internals IV.B2.RP-296 nickel-alloy embrittlement and IV.B2.RP-297 Westinghouse for CASS, IV.B2.RP-302a

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item reactor internal martensitic SS, and IV.B2.RP-354 Primary PH SS due to IV.B2.RP-388 components thermal aging IV.B2.RP-300 exposed to reactor embrittlement, coolant and changes in neutron flux dimensions due to void swelling, distortion, loss of preload due to 3.1-55 thermal and irradiation-enhanced stress relaxation or creep, loss of material due to wear M 059b PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-274 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B2.RP-280a martensitic SS neutron irradiation Internals IV.B2.RP-287 Westinghouse embrittlement and IV.B2.RP-290 reactor internal for CASS, IV.B2.RP-290a Expansion martensitic SS, and IV.B2.RP-290b components PH SS due to IV.B2.RP-292 exposed to reactor thermal aging IV.B2.RP-295 coolant and embrittlement; IV.B2.RP-297a neutron flux changes in IV.B2.RP-388a dimensions due to void swelling, distortion; loss of

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item preload due to thermal and irradiation-enhanced stress relaxation or creep; loss of material due to wear M 059c PWR SS, including Loss of fracture AMP XI.M16A, Yes (SRP-SLR IV.B2.RP-285 CASS, PH SS or toughness due to PWR Vessel Section 3.1.2.2.9) IV.B2.RP-288 3.1-56 martensitic SS, neutron irradiation Internals IV.B2.RP-299 nickel-alloy, or embrittlement and IV.B2.RP-345 stellite for CASS, Westinghouse martensitic SS, and reactor internal PH SS due to Existing thermal aging Programs embrittlement, components changes in exposed to reactor dimensions due to coolant and void swelling, neutron flux distortion, loss of preload due to thermal and irradiation-enhanced stress relaxation or creep, loss of material due to wear

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 060 BWR Steel piping, piping Wall thinning due AMP XI.M17, No IV.C1.R-23 components to flow-accelerated Flow-Accelerated exposed to reactor corrosion Corrosion coolant 061 PWR Steel SG steam Wall thinning due AMP XI.M17, No IV.D1.R-37 nozzle and safe to flow-accelerated Flow-Accelerated IV.D2.R-38 end, feedwater corrosion Corrosion nozzle and safe end, auxiliary 3.1-57 feedwater nozzles and safe ends exposed to secondary feedwater/steam 062 BWR/PWR High-strength steel, Cracking due to AMP XI.M18, No IV.A2.R-78 SS closure bolting; SCC Bolting Integrity IV.C1.R-11 SS control rod IV.C2.R-11 drive head IV.D1.R-10 penetration flange IV.D2.R-10 bolting exposed to air-indoor uncontrolled 063 BWR Steel or SS closure Loss of material AMP XI.M18, No IV.C1.RP-42 bolting exposed to due to general Bolting Integrity air - indoor (steel only), pitting, uncontrolled crevice corrosion, wear

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 064 PWR Steel or SS closure Loss of material AMP XI.M18, No IV.C2.RP-166 bolting exposed to due to general Bolting Integrity IV.D1.RP-166 air - indoor (steel only), pitting, IV.D2.RP-166 uncontrolled crevice corrosion, wear 065 PWR SS control rod Loss of material AMP XI.M18, No IV.A2.R-79 drive head due to wear Bolting Integrity penetration flange bolting exposed to 3.1-58 air-indoor uncontrolled 066 PWR Steel, SS closure Loss of preload AMP XI.M18, No IV.A2.R-80 bolting; SS control due to thermal Bolting Integrity IV.C2.R-12 rod drive head effects, gasket penetration flange creep, self-bolting exposed to loosening air-indoor uncontrolled 067 BWR/PWR Steel or SS closure Loss of preload AMP XI.M18, No IV.C1.RP-43 bolting exposed to due to thermal Bolting Integrity IV.D1.RP-46 air - indoor effects, gasket IV.D2.RP-46 uncontrolled creep, self-(external) loosening 068 PWR Nickel-alloy SG Changes in AMP XI.M19, No IV.D1.R-43 tubes exposed to dimension Steam IV.D2.R-226 secondary (denting) due to Generators, and feedwater or steam corrosion of carbon

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item steel tube support AMP XI.M2, Water plate Chemistry 069 PWR Nickel-alloy SG Cracking due to AMP XI.M19, No IV.D1.R-47 tubes and sleeves outer diameter Steam IV.D2.R-47 exposed to SCC, intergranular Generators, and secondary attack AMP XI.M2, Water feedwater or steam Chemistry 070 PWR Nickel-alloy SG Cracking due to AMP XI.M19, No IV.D1.R-40 tubes, repair primary water SCC Steam IV.D1.R-44 3.1-59 sleeves, and tube Generators, and IV.D2.R-40 plugs exposed to AMP XI.M2, IV.D2.R-44 reactor coolant Water Chemistry 071 PWR Steel, chrome Cracking due to AMP XI.M19, No IV.D1.RP-226 plated steel, SS, SCC or other Steam IV.D1.RP-384 nickel-alloy SG U- mechanism(s); loss Generators, and bend supports of material due AMP XI.M2, including anti- general (steel Water Chemistry vibration bars only), pitting, exposed to crevice corrosion secondary feedwater or steam 072 PWR Steel SG tube Loss of material AMP XI.M19, No IV.D1.R-42 support plate, tube due to general, Steam IV.D1.RP-161 bundle wrapper, pitting, crevice Generators, and IV.D2.R-42 supports and corrosion, erosion, AMP XI.M2, Water IV.D2.RP-162 mounting hardware ligament cracking Chemistry exposed to due to corrosion (corrosion based

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item secondary aging effects and feedwater or steam mechanisms only) 073 PWR Nickel-alloy SG Loss of material AMP XI.M19, No IV.D1.R-50 tubes and sleeves due to wastage, Steam exposed to pitting corrosion Generators, and phosphate AMP XI.M2, Water chemistry in Chemistry secondary feedwater or steam 3.1-60 074 PWR Steel SG upper Wall thinning due AMP XI.M19, No IV.D1.RP-49 assembly and to flow-accelerated Steam separators corrosion Generators, and including feedwater AMP XI.M2, Water inlet ring and Chemistry support exposed to secondary feedwater or steam 075 PWR Steel SG tube Wall thinning due AMP XI.M19, No IV.D1.RP-48 support lattice bars to flow-accelerated Steam exposed to corrosion, general Generators, and secondary corrosion AMP XI.M2, Water feedwater or steam Chemistry 076 PWR Steel, chrome Loss of material AMP XI.M19, No IV.D1.RP-225 plated steel, SS, due to wear, Steam nickel-alloy steam fretting Generators generator U-bend supports including

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item anti-vibration bars exposed to secondary feedwater or steam 077 PWR Nickel-alloy SG Loss of material AMP XI.M19, No IV.D1.RP-233 tubes and sleeves due to wear, Steam IV.D2.RP-233 exposed to fretting Generators secondary feedwater or steam 3.1-61 078 PWR Nickel-alloy SG Cracking due to AMP XI.M2, Water No IV.D2.R-36 components such SCC Chemistry, and as, secondary side AMP XI.M32, nozzles (vent, One-Time drain, and Inspection, or instrumentation) AMP XI.M1, exposed to ASME Section XI secondary Inservice feedwater or steam Inspection, Subsections IWB, IWC, and IWD.

079 BWR SS; steel with Loss of material AMP XI.M2, No IV.C1.RP-158 nickel-alloy or SS due to pitting, Water Chemistry, cladding; and crevice corrosion and AMP XI.M32, nickel-alloy reactor One-Time coolant pressure Inspection boundary components

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor coolant 080 PWR SS or steel with SS Cracking due to AMP XI.M2, No IV.C2.RP-383 cladding SCC Water Chemistry, pressurizer relief and AMP XI.M32, tank: tank shell and One-Time heads, flanges, Inspection nozzles (none-ASME Section XI 3.1-62 components) exposed to treated borated water >60

°C (>140 °F) 081 PWR SS pressurizer Cracking due to AMP XI.M2, No IV.C2.RP-41 spray head SCC Water Chemistry, exposed to reactor and AMP XI.M32, coolant One-Time Inspection 082 PWR Nickel-alloy Cracking due to AMP XI.M2, No IV.C2.RP-40 pressurizer spray SCC, primary Water Chemistry, head exposed to water SCC and AMP XI.M32, reactor coolant One-Time Inspection 083 PWR Steel SG shell Loss of material AMP XI.M2, No IV.D1.RP-372 assembly exposed due to general, Water Chemistry, IV.D2.RP-153 to secondary pitting, crevice and AMP XI.M32, feedwater or steam corrosion

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item One-Time Inspection 084 BWR Steel top head Loss of material AMP XI.M2, No IV.A1.RP-50 enclosure (without due to general, Water Chemistry, cladding): top pitting, crevice and AMP XI.M32, head, top head corrosion One-Time nozzles (vent, top Inspection head spray, reactor core isolation 3.1-63 cooling, spare) exposed to reactor coolant 085 BWR SS, nickel-alloy, Loss of material AMP XI.M2, No IV.A1.RP-157 and steel with due to pitting, Water Chemistry, nickel-alloy or SS crevice corrosion and AMP XI.M32, cladding reactor One-Time vessel flanges, Inspection nozzles, penetrations, safe ends, vessel shells, heads and welds exposed to reactor coolant 086 PWR SS or SG primary Cracking due to AMP XI.M2, No IV.D1.RP-17 side divider plate SCC Water Chemistry exposed to reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 087 PWR SS, nickel-alloy Loss of material AMP XI.M2, No IV.B2.RP-24 PWR reactor due to pitting, Water Chemistry IV.B3.RP-24 internal crevice corrosion IV.B4.RP-24 components exposed to reactor coolant, neutron flux 088 PWR SS; steel with Loss of material AMP XI.M2, No IV.A2.RP-28 nickel-alloy or due to pitting, Water Chemistry IV.C2.RP-23 3.1-64 stainless steel crevice corrosion cladding; and nickel-alloy reactor coolant pressure boundary components exposed to reactor coolant E 089 PWR Steel piping, piping Loss of material AMP XI.M21A, No IV.C2.RP-221 components due to general, Closed Treated exposed to closed- pitting, crevice Water Systems cycle cooling water corrosion, microbiologically-induced corrosion (MIC) 090 PWR Copper alloy Loss of material AMP XI.M21A, No IV.C2.RP-222 piping, piping due to pitting, Closed Treated components Water Systems

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to closed- crevice corrosion, cycle cooling water MIC 091 BWR Steel (including Cracking due to AMP XI.M3, No IV.A1.RP-165 high-strength steel) SCC; loss of Reactor Head IV.A1.RP-51 RV closure flange material due to Closure Stud assembly general, pitting, Bolting components crevice corrosion, (including flanges, wear nut, studs, and 3.1-65 washers) exposed to air-indoor uncontrolled 092 PWR Steel (including Cracking due to AMP XI.M3, No IV.A2.RP-52 high-strength steel) SCC, IGSCC; loss Reactor Head IV.A2.RP-53 RV closure flange of material due to Closure Stud assembly general, pitting, Bolting components crevice corrosion, (including flanges, wear nut, studs, and washers) exposed to air-indoor uncontrolled 093 PWR Copper alloy >15% Loss of material AMP XI.M33, No IV.C2.RP-12 zinc or >8% due to selective Selective aluminum piping, leaching Leaching piping components exposed to closed-

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item cycle cooling water, treated water 094 BWR SS and nickel-alloy Cracking due to AMP XI.M4, BWR No IV.A1.R-64 vessel shell SCC, IGSCC, Vessel ID attachment welds cyclic loading Attachment exposed to reactor Welds, and AMP coolant XI.M2, Water Chemistry 3.1-66 (SCC, IGSCC mechanisms only) 095 BWR Steel (with or Cracking due to AMP XI.M1, No IV.A1.R-65 without SS or cyclic loading ASME Section XI nickel-alloy Inservice cladding) Inspection, feedwater nozzles Subsections IWB, exposed to reactor IWC, and IWD coolant 096 BWR Steel (with or Cracking due to AMP XI.M1, No IV.A1.R-66 without SS SCC, IGSCC, ASME Section XI cladding) control cyclic loading Inservice rod drive return line Inspection, nozzles and their Subsections IWB, nozzle-to-vessel IWC, and IWD welds exposed to reactor coolant in BWR-3, BWR-4,

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item BWR-5, and BWR-6 designs E 097 BWR SS and nickel-alloy Cracking due to AMP XI.M7, BWR No IV.A1.R-412 piping, piping SCC, IGSCC Stress Corrosion IV.C1.R-20 components 4 Cracking, and IV.C1.R-21 NPS; nozzle safe AMP XI.M2, ends and Water Chemistry associated welds, control rod drive 3.1-67 return line nozzle cap and associated cap-to-nozzle weld or cap-to-safe end weld in BWR-3, BWR 4, BWR 5, and BWR-6 designs 098 BWR SS, nickel-alloy Cracking due to AMP XI.M8, BWR No IV.A1.RP-369 penetrations: SCC, IGSCC, Penetrations, and instrumentation cyclic loading AMP XI.M2, and standby liquid Water Chemistry control exposed to (SCC, IGSCC reactor coolant mechanisms only)

M 099 BWR SS (including Loss of fracture AMP XI.M9, No IV.B1.RP-182 CASS; PH toughness due to BWR Vessel IV.B1.RP-200 martensitic SS; thermal aging, Internals IV.B1.RP-219 martensitic SS); IV.B1.RP-220

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item nickel-alloy neutron irradiation IV.B1.R-416 (including X-750 embrittlement IV.B1.R-417 alloy) reactor IV.B1.R-419 internal components exposed to reactor coolant and neutron flux 100 BWR SS RVI Loss of material AMP XI.M9, No IV.B1.RP-377 3.1-68 components (jet due to wear BWR Vessel pump wedge Internals surface) exposed to reactor coolant 101 BWR SS steam dryers Cracking due to AMP XI.M9, No IV.B1.RP-155 exposed to reactor flow-induced BWR Vessel coolant vibration, SCC, Internals IGSCC; loss of material due to wear 102 BWR SS fuel supports Cracking due to AMP XI.M9, No IV.B1.R-104 and control rod SCC, IGSCC BWR Vessel drive assemblies Internals, and control rod drive AMP XI.M2, housing exposed to Water Chemistry reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item M 103 BWR SS, nickel-alloy Cracking due to AMP XI.M9, BWR No IV.B1.R-422 reactor internal SCC, IGSCC, Vessel Internals, IV.B1.R-100 components IASCC and AMP XI.M2, IV.B1.R-105 exposed to reactor Water Chemistry IV.B1.R-92 coolant and IV.B1.R-93 neutron flux IV.B1.R-96 IV.B1.R-97 IV.B1.R-98 IV.B1.R-99 3.1-69 104 BWR Nickel-alloy RVI Cracking due to AMP XI.M9, BWR No IV.B1.RP-381 components IGSCC Vessel Internals, exposed to reactor and AMP XI.M2, coolant and Water Chemistry neutron flux 105 BWR/PWR Steel piping, piping None None Yes (SRP-SLR IV.E.RP-353 components Section 3.1.2.2.15) exposed to concrete 106 BWR/PWR Nickel-alloy piping, None None No IV.E.RP-378 piping components exposed to air with borated water leakage 107 BWR/PWR SS piping, piping None None No IV.E.RP-05 components IV.E.RP-07 exposed to gas, air

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item with borated water leakage 110 BWR Metallic piping, Wall thinning due AMP XI.M17, No IV.C1.R-406 piping components to erosion Flow-Accelerated exposed to reactor Corrosion coolant 111 PWR Nickel-alloy SG Reduction of heat AMP XI.M2, Water No IV.D1.R-407 tubes exposed to transfer due to Chemistry, and IV.D2.R-407 secondary fouling AMP XI.M19, 3.1-70 feedwater or steam Steam Generators 113 BWR Steel RV external Loss of material AMP XI.M1, No IV.A1.R-409 attachments due to general, ASME Section XI exposed to indoor, pitting, crevice Inservice uncontrolled air corrosion, wear Inspection, Subsections IWB, IWC, and IWD M 114 BWR/PWR Reactor coolant Cracking due to AMP XI.M1, No IV.E.R-444 system SCC, IGSCC, ASME Section XI components primary water Inservice defined as ASME stress corrosion Inspection,Section XI Code cracking (PWSCC), Subsections IWB, Class components IASCC (SCC IWC, and IWD, (ASME Code Class mechanisms for and AMP XI.M2, 1 reactor coolant SS, nickel-alloy Water Chemistry pressure boundary components only), (water chemistry-components, RVI fatigue, or cyclic related or

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item attachments, or loading; loss of corrosion-related core support material due to aging effect structure general corrosion mechanisms only) components; or (steel only), pitting ASME Class 2 or 3 corrosion, crevice components corrosion, or wear including ASME defined appurtenances, 3.1-71 component supports, and associated pressure boundary welds, or components subject to plant-specific equivalent classifications for these ASME Code classes) 115 BWR/PWR SS piping, piping None None Yes (SRP-SLR IV.E.RP-06 components Section 3.1.2.2.15) exposed to concrete 116 PWR Nickel-alloy control Loss of material Plant-specific aging Yes (SRP-SLR IV.A2.R-413 rod drive due to wear management Section penetration nozzles program 3.1.2.2.10.1)

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item exposed to reactor coolant 117 PWR SS, nickel-alloy Loss of material Plant-specific aging Yes (SRP-SLR IV.A2.R-414 control rod drive due to wear management Section penetration nozzle program 3.1.2.2.10.2) thermal sleeves exposed to reactor coolant M 118 PWR SS, nickel-alloy Cracking due to Plant-specific aging Yes (SRP-SLR IV.B2.R-423 3.1-72 PWR RVI SCC, IASCC, management Section 3.1.2.2.9) IV.B3.R-423 components or cyclic loading, program or AMP IV.B4.R-423 license renewal fatigue XI.M16A, PWR applications Vessel Internals, (LRA)/subsequent and AMP XI.M2, license renewal Water Chemistry application (SLRA) (SCC and IASCC specified RVI only), with an component adjusted site-exposed to reactor specific or coolant, neutron component-specific flux aging management basis for a specified RVI component M 119 PWR SS, nickel-alloy, Loss of fracture Plant-specific aging Yes (SRP-SLR IV.B2.R-424 stellite PWR RVI toughness due to management Section 3.1.2.2.9) IV.B3.R-424 components or neutron irradiation program or AMP IV.B4.R-424 LRA/SLRA- embrittlement or XI.M16A, PWR

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item specified RVI thermal aging Vessel Internals, component embrittlement; with an adjusted exposed to reactor changes in site-specific or coolant, neutron dimensions due to component-specific flux void swelling or aging management distortion; loss of basis for a specified preload due to reactor vessel thermal and internal component irradiation-3.1-73 enhanced stress relaxation or creep; loss of material due to wear 120 BWR SS core plate rim Loss of preload AMP XI.M9, BWR Yes (SRP-SLR IV.B1.R-420 holddown bolts due to thermal or Vessel Internals, Section 3.1.2.2.14) exposed to reactor irradiation- and TLAA SRP-coolant and enhanced stress SLR 4.7 Other neutron flux relaxation Plant-Specific TLAAs [if an analysis is performed as part of the aging management basis and conforms to the definition of a TLAA in 10 CFR 54.3(a)]

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 121 BWR SS jet pump Loss of preload AMP XI.M9, No IV.B1.R-421 assembly due to thermal or BWR Vessel holddown beam irradiation- Internals bolts exposed to enhanced stress reactor coolant and relaxation neutron flux D 122 124 BWR/PWR Steel piping, piping Loss of material AMP XI.M36, No IV.C1.R-431 components due to general, External Surfaces IV.C2.R-431 3.1-74 exposed to air- pitting, crevice Monitoring of indoor corrosion Mechanical uncontrolled, air Components outdoor, condensation 125 PWR Nickel-alloy SG Cracking due to AMP XI.M19, No IV.D1.R-437 tubes at support flow-induced Steam Generators IV.D2.R-442 plate locations vibration, high-exposed to cycle fatigue secondary feedwater or steam 127 PWR Steel (with SS or Loss of material AMP XI.M2, Water No IV.D1.R-436 nickel-alloy due to boric acid Chemistry, and IV.D2.R-440 cladding) SG corrosion AMP XI.M19, heads and Steam tubesheets Generators exposed to reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item 128 BWR SS, nickel-alloy Cracking due to AMP XI.M7, BWR No IV.A1.R-68 nozzles safe ends SCC, IGSCC Stress Corrosion and welds: high Cracking, and pressure core AMP XI.M2, spray; low pressure Water Chemistry core spray; recirculating water, low pressure coolant injection or 3.1-75 RHR injection mode exposed to reactor coolant 129 BWR Steel and SS Cracking due to AMP XI.M1, No IV.C1.R-432 piping, piping cyclic loading ASME Section XI components Inservice exposed to reactor Inspection, coolant: welded Subsections IWB, connections IWC, and IWD between the re-routed control rod drive return line and the inlet piping system that delivers return line flow to the reactor pressure vessel exposed to reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item D 130 133 BWR/PWR Steel components Long-term loss of AMP XI.M32, No IV.A1.R-448 exposed to treated material due to One-Time IV.C1.R-448 water general corrosion Inspection 134 BWR/PWR Nonmetallic Reduced thermal AMP XI.M36, No IV.A1.R-450 thermal insulation insulation External Surfaces IV.A2.R-450 exposed to air, resistance due to Monitoring of IV.C1.R-450 condensation moisture intrusion Mechanical IV.C2.R-450 Components IV.D1.R-450 3.1-76 IV.D2.R-450 D 135 136 BWR/PWR SS, nickel-alloy Loss of material AMP XI.M32, Yes (SRP-SLR IV.C1.R-452a piping, piping due to pitting, One-Time Section 3.1.2.2.16) IV.C1.R-452b components crevice corrosion Inspection, AMP IV.C1.R-452c exposed to air, XI.M36, External IV.C1.R-452d condensation Surfaces IV.C2.R-452a Monitoring of IV.C2.R-452b Mechanical IV.C2.R-452c Components, IV.C2.R-452d AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components, or AMP XI.M42, Internal

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 137 BWR/PWR Copper alloy None None No IV.E.R-453 piping, piping components 3.1-77 exposed to air, condensation, gas 139 PWR SS, nickel-alloy RV Cracking due to AMP XI.M32, Yes (SRP-SLR IV.A2.R-74a top head enclosure SCC One-Time Section 3.1.2.2.6.3) IV.A2.R-74b flange leakage Inspection, or detection line AMP XI.M36, exposed to air- External Surfaces indoor Monitoring of uncontrolled, Mechanical reactor coolant Components leakage N 140 BWR/PWR Steel, SS or nickel- Cracking due to Plant-specific aging Yes (SRP-SLR IV.C1.R-456 alloy piping, piping thermal fatigue management Section 3.1.2.2.17) IV.C2.R-456 components program exposed to reactor coolant

Table 3.1-1 Summary of Aging Management Programs for Reactor Vessel, Internals, and Reactor Coolant System Evaluated in Chapter IV of the GALL-SLR Report (Continued)

Aging Management Generic Aging New, Program (AMP)/ Lessons Learned Modified, Time-Limited Further for Subsequent Deleted, Aging Aging Analyses Evaluation License Renewal Edited Item ID Type Component Effect/Mechanism (TLAA) Recommended (GALL-SLR) Item N 141 BWR/PWR Steel, SS or nickel- Loss of material Plant-specific or Yes (SRP-SLR IV.A1.R-457 alloy ASME Code due to wear existing aging Section IV.A2.R-457 Class 1 small-bore management 3.1.2.2.10.3) piping, and piping program if loss of components with material is not reflective metal mitigated insulation exposed to air 1 AMP = aging management program; ASME = American Society of Mechanical Engineers; B&W = Babcock and Wilcox; BWR = boiling water reactor; CASS = cast 3.1-78 2 austenitic stainless steel; CE = Combustion Engineering; GALL-SLR = Generic Aging Lessons Learned for Subsequent License Renewal; IASCC = irradiation-3 assisted SCC; IGSCC = intergranular stress corrosion cracking; LRA = license renewal applications; MIC = microbiologically-induced corrosion; NPS = nominal 4 pipe size; PH = precipitation-hardening; PWR = pressure water reactor; PWSCC = primary water stress corrosion cracking; RCPB = reactor coolant pressure 5 boundary; RV = reactor vessel; RVI = reactor vessel internal; SCC = stress corrosion cracking; SG = steam generator; SLRA = subsequent license renewal 6 application; SRP-SLR = Standard Review Plan for Review of Subsequent License Renewal; SS = stainless steel; TLAA = time-limited aging analyses.

7 8

1 Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the 2 Generic Aging Lessons Learned for Subsequent License Renewal Report New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 001 Boiling water Stainless steel (SS), Cumulative fatigue TLAA, Standard Yes (SRP-SLR V.D1.E-13 reactor (BWR)/ steel piping, piping damage due to Review Plan for Section 3.2.2.1) V.D2.E-10 pressurized components fatigue Review of water reactor exposed to any Subsequent License (PWR) environment Renewal (SRP-SLR)

Section 4.3 Metal Fatigue D 002 3.2-21 D 003 004 BWR/PWR SS, nickel-alloy Loss of material due AMP XI.M32, Yes (SRP-SLR V.B.EP-107a piping, piping to pitting, crevice "One-Time Section 3.2.2.2.2) V.B.EP-107b components corrosion Inspection," AMP V.B.EP-107d exposed to air, XI.M36, "External V.C.EP-107a condensation Surfaces Monitoring V.C.EP-107b (external) of Mechanical V.C.EP-107d Components," or V.D1.EP-107a AMP XI.M42, V.D1.EP-107b "Internal V.D1.EP-107d Coatings/Linings for V.D2.EP-107a In-Scope Piping, V.D2.EP-107b Piping Components, V.D2.EP-107d Heat Exchangers, and Tanks" 3

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item E 005 PWR SS orifice (miniflow Loss of material due AMP XI.M32, No V.D1.E-24 recirculation when to erosion One-Time centrifugal high- Inspection pressure safety injection (HPSI) pumps are used for normal charging) exposed to treated borated water 006 BWR Metallic drywell and Loss of material due AMP XI.M32, Yes (SRP-SLR V.D2.EP-113a 3.2-22 suppression to general, pitting, One-Time Section 3.2.2.2.3) V.D2.EP-113b chamber spray crevice corrosion; Inspection, or AMP system (internal flow blockage due to XI.M38, Inspection surfaces): flow fouling of Internal Surfaces orifice; spray in Miscellaneous nozzles exposed to Piping and Ducting air - indoor Components uncontrolled, condensation 007 BWR SS piping, piping Cracking due to AMP XI.M32, One- Yes (SRP-SLR V.A.EP-103b components, tanks stress corrosion Time Inspection, Section 3.2.2.2.4) V.A.EP-103c exposed to air, cracking (SCC) AMP XI.M36, V.A.EP-103d condensation External Surfaces V.A.EP-103e Monitoring V.B.EP-103b of Mechanical V.B.EP-103c Components, AMP V.B.EP-103d XI.M38, Inspection V.B.EP-103e of Internal Surfaces V.C.EP-103b in Miscellaneous V.C.EP-103c

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Piping and Ducting V.C.EP-103d Components, or V.C.EP-103e AMP XI.M42, V.D1.EP-103b Internal V.D1.EP-103c Coatings/Linings for V.D1.EP-103d In-Scope Piping, V.D1.EP-103e Piping Components, V.D2.EP-103b Heat Exchangers, V.D2.EP-103c and Tanks V.D2.EP-103d V.D2.EP-103e 3.2-23 008 PWR Copper alloy (>15% Loss of material due AMP XI.M10, No V.E.EP-38 Zinc) piping, piping to boric acid Boric Acid components corrosion Corrosion exposed to air with borated water leakage 009 PWR Steel external Loss of material due AMP XI.M10, No V.E.E-28 surfaces exposed to to boric acid Boric Acid air with borated corrosion Corrosion water leakage 010 BWR/PWR Cast austenitic Loss of fracture AMP XI.M12, No V.D1.E-47 stainless steel toughness due to Thermal Aging V.D2.E-11 (CASS) piping, thermal aging Embrittlement of piping components embrittlement Cast Austenitic exposed to treated Stainless Steel borated water >250 (CASS)

°C (>482 °F),

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item treated water >250

°C (>482 °F)

E 011 BWR/PWR Steel piping, piping Wall thinning due to AMP XI.M17, Flow No V.C.E-09 components flow-accelerated Accelerated V.D1.E-09 exposed to steam, corrosion Corrosion V.D2.E-07 treated water V.D2.E-09 012 BWR/PWR High-strength steel Cracking due to AMP XI.M18, No V.E.E-03 closure bolting SCC; cyclic Bolting Integrity exposed to air, soil, loading underground 3.2-24 D 013 014 BWR/PWR SS, steel, nickel- Loss of material due AMP XI.M18, No V.E.E-02 alloy closure bolting to general (steel Bolting Integrity exposed to air- only), pitting, crevice indoor uncontrolled, corrosion air outdoor, condensation 015 BWR/PWR Metallic closure Loss of preload due AMP XI.M18, No V.E.EP-116 bolting exposed to to thermal effects, Bolting Integrity any environment, gasket creep, self-soil underground loosening E 016 BWR/PWR Steel piping, piping Loss of material due AMP XI.M2, Water No V.C.EP-62 components to general, pitting, Chemistry, and V.D2.EP-60 exposed to treated crevice corrosion, AMP XI.M32, One-water microbiologically- Time Inspection induced corrosion (MIC)

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item E 017 BWR/PWR Aluminum piping, Loss of material due AMP XI.M2, Water No V.D1.EP-71 piping components to pitting, crevice Chemistry, and V.D2.EP-71 exposed to treated corrosion AMP XI.M32, One-water, treated Time Inspection borated water D 018 M 019 BWR/PWR Stainless steel, Reduction of heat AMP XI.M2, Water No V.A.E-20 nickel-alloy heat transfer due to Chemistry, and V.D2.EP-74 exchanger tubes fouling AMP XI.M32, One- V.D1.E-20 exposed to treated Time Inspection 3.2-25 water, treated borated water 020 PWR SS, steel (with SS or Cracking due to AMP XI.M2, Water No V.A.E-12 nickel-alloy SCC Chemistry, and V.D1.E-12 cladding) piping, AMP XI.M32, One-piping components, Time Inspection tanks exposed to treated borated water >60 °C

(>140 °F)

D 021 022 BWR/PWR Nickel-alloy, SS heat Loss of material due AMP XI.M2, No V.A.E-428 exchanger to pitting, crevice Water Chemistry, V.A.EP-41 components, piping, corrosion, MIC and AMP XI.M32, V.C.EP-63 piping components, One-Time V.D1.E-428 tanks exposed to Inspection V.D2.E-428 treated water, V.D1.EP-41 V.D2.EP-73

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item treated borated water 023 BWR/PWR Steel heat Loss of material due AMP XI.M20, Open No V.A.EP-90 exchanger to general, pitting, Cycle Cooling Water V.C.E-22 components, piping, crevice corrosion, System V.D1.EP-90 piping components MIC; flow blockage V.D2.EP-90 exposed to raw due to fouling water 024 PWR SS piping, piping Loss of material due AMP XI.M20, Open No V.C.E-34 components to pitting, crevice Cycle Cooling Water V.D1.EP-55 3.2-26 exposed to raw corrosion, MIC; flow System water blockage due to fouling 025 BWR/PWR SS heat exchanger Loss of material due AMP XI.M20, Open No V.A.EP-91 components to pitting, crevice Cycle Cooling Water V.D1.EP-91 exposed to raw corrosion, MIC; flow System V.D2.EP-91 water blockage due to fouling D 026 027 BWR/PWR SS, steel heat Reduction of heat AMP XI.M20, Open No V.A.E-21 exchanger tubes transfer due to Cycle Cooling Water V.D1.E-21 exposed to raw fouling System V.D2.E-21 water V.D2.E-23 028 BWR/PWR SS piping, piping Cracking due to AMP XI.M21A, No V.A.EP-98 components SCC Closed Treated V.C.EP-98 exposed to closed- Water Systems V.D1.EP-98 cycle cooling water V.D2.EP-98

>60 °C (>140 °F)

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 029 BWR/PWR Steel piping, piping Loss of material due AMP XI.M21A, No V.C.EP-99 components to general, pitting, Closed Treated exposed to closed- crevice corrosion, Water Systems cycle cooling water MIC 030 BWR/PWR Steel heat Loss of material due AMP XI.M21A, No V.A.EP-92 exchanger to general, pitting, Closed Treated V.D1.EP-92 components crevice corrosion, Water Systems V.D2.EP-92 exposed to closed- MIC cycle cooling water 031 BWR/PWR SS heat exchanger Loss of material due AMP XI.M21A, No V.A.EP-93 3.2-27 components, piping, to pitting, crevice Closed Treated V.A.EP-95 piping components corrosion, MIC Water Systems V.C.EP-95 exposed to closed- V.D1.EP-93 cycle cooling water V.D1.EP-95 V.D2.EP-93 V.D2.EP-95 032 BWR/PWR Copper alloy heat Loss of material due AMP XI.M21A, No V.A.EP-94 exchanger to pitting, crevice Closed Treated V.A.EP-97 components, piping, corrosion, MIC Water Systems V.B.EP-97 piping components V.D1.EP-94 exposed to closed- V.D1.EP-97 cycle cooling water V.D2.EP-94 V.D2.EP-97 033 BWR/PWR Copper alloy, SS Reduction of heat AMP XI.M21A, No V.A.EP-100 heat exchanger transfer due to Closed Treated V.A.EP-96 tubes exposed to fouling Water Systems V.D1.EP-96 closed-cycle cooling V.D2.EP-96 water

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 034 BWR/PWR Copper alloy (>15% Loss of material due AMP XI.M33, No V.A.EP-27 zinc or >8% to selective leaching Selective Leaching V.A.EP-37 aluminum) piping, V.B.EP-27 piping components, V.B.EP-37 heat exchanger V.D1.EP-27 components V.D1.EP-37 exposed to closed- V.D2.EP-27 cycle cooling water, V.D2.EP-37 treated water 035 PWR Gray cast iron motor Loss of material due AMP XI.M33, No V.A.E-43 3.2-28 cooler exposed to to selective leaching Selective Leaching V.D1.E-43 closed-cycle cooling water, treated water M 036 PWR Gray cast iron, Loss of material due AMP XI.M33, No V.D1.EP-52 ductile iron, to selective leaching Selective Leaching malleable iron piping, piping components exposed to closed-cycle cooling water, treated water M 037 BWR/PWR Gray cast iron, Loss of material due AMP XI.M33, No V.B.EP-54 ductile iron, to selective leaching Selective Leaching V.D1.EP-54 malleable iron V.D2.EP-54 piping, piping components exposed to soil

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 038 BWR/PWR Elastomer piping, Hardening or loss of AMP XI.M36, No V.E.EP-59 piping components, strength due to External Surfaces seals exposed to air, elastomer Monitoring of condensation degradation Mechanical Components D 039 040 BWR/PWR Steel external Loss of material due AMP XI.M36, No V.E.E-44 surfaces exposed to to general, pitting, External Surfaces air - indoor crevice corrosion Monitoring of uncontrolled, air - Mechanical 3.2-29 outdoor, Components condensation D 041 042 BWR/PWR Aluminum piping, Loss of material due AMP XI.M32, Yes (SRP-SLR V.E.EP-114b piping components, to pitting, crevice One-Time Section 3.2.2.2.10) V.E.EP-114c tanks exposed to air, corrosion Inspection, AMP V.E.EP-114d condensation XI.M36, External (external) Surfaces Monitoring of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item M 043 BWR/PWR Elastomer piping, Hardening or loss of AMP XI.M38, No V.B.EP-58 piping components, strength due to Inspection of V.A.E-427 seals exposed to air, elastomer Internal Surfaces in V.B.E-427 condensation degradation Miscellaneous V.D1.E-427 Piping and Ducting V.D2.E-427 Components M 044 BWR/PWR Steel piping, piping Loss of material due AMP XI.M38, No V.A.E-29 components, to general, pitting, Inspection of V.B.E-25 ducting, ducting crevice corrosion Internal Surfaces in V.D2.E-29 components Miscellaneous 3.2-30 exposed to air - Piping and Ducting indoor uncontrolled Components 045 PWR Steel encapsulation Loss of material due AMP XI.M38, No V.A.EP-42 components to general, pitting, Inspection of V.C.EP-42 exposed to air - crevice corrosion Internal Surfaces in V.D1.EP-42 indoor uncontrolled Miscellaneous Piping and Ducting Components 046 BWR/PWR Steel piping, piping Loss of material due AMP XI.M38, No V.B.E-27 components to general, pitting, Inspection of V.D1.E-27 exposed to crevice corrosion Internal Surfaces in V.D2.E-27 condensation Miscellaneous Piping and Ducting Components 047 PWR Steel encapsulation Loss of material due AMP XI.M38, No V.A.EP-43 components to general, pitting, Inspection of V.C.EP-43 exposed to air with crevice, boric acid Internal Surfaces in V.D1.EP-43 corrosion Miscellaneous

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item borated water Piping and Ducting leakage Components E 048 BWR/PWR SS, nickel-alloy Loss of material due AMP XI.M29, Yes (SRP-SLR V.A.EP-81a piping, piping to pitting, crevice Outdoor and Large Section 3.2.2.2.2) V.A.EP-81b components, tanks corrosion Atmospheric Metallic V.A.EP-81c exposed to air, Storage Tanks, V.A.EP-81d condensation AMP XI.M32, One- V.D1.EP-81a (internal) Time Inspection, V.D1.EP-81b AMP XI.M38, V.D1.EP-81c Inspection of V.D1.EP-81d 3.2-31 Internal Surfaces in V.D2.EP-61a Miscellaneous V.D2.EP-61b Piping and Ducting V.D2.EP-61c Components, or V.D2.EP-61d AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks E 049 BWR/PWR Steel piping, piping Loss of material due AMP XI.M39, No V.A.EP-77 components to general, pitting, Lubricating Oil V.D1.EP-77 exposed to crevice corrosion, Analysis, and AMP V.D2.EP-77 lubricating oil MIC XI.M32, One-Time Inspection

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item E 050 BWR/PWR Copper alloy, Loss of material due AMP XI.M39, No V.A.EP-76 stainless steel to pitting, crevice Lubricating Oil V.D1.EP-76 piping, piping corrosion, MIC Analysis, and AMP V.D1.EP-80 components XI.M32, One-Time V.D2.EP-76 exposed to Inspection lubricating oil 051 BWR/PWR Steel, copper alloy, Reduction of heat AMP XI.M39, No V.A.EP-75 stainless steel heat transfer due to Lubricating Oil V.A.EP-78 exchanger tubes fouling Analysis, and AMP V.A.EP-79 exposed to XI.M32, One-Time V.D1.EP-75 3.2-32 lubricating oil Inspection V.D1.EP-78 V.D1.EP-79 V.D2.EP-75 V.D2.EP-78 V.D2.EP-79 052 BWR/PWR Steel piping, piping Loss of material due AMP XI.M41, No V.E.EP-111 components to general, pitting, Buried and V.E.EP-123 exposed to soil, crevice corrosion, Underground Piping concrete, MIC (soil only) and Tanks underground 053 BWR/PWR SS, nickel-alloy Loss of material due AMP XI.M41, No V.E.EP-72 piping, piping to pitting, crevice Buried and components, tanks, corrosion, MIC (soil Underground Piping exposed to soil, only) and Tanks concrete D 053a E 054 BWR SS, nickel-alloy Cracking due to AMP XI.M7, BWR No V.D2.E-37 piping, piping SCC, intergranular Stress Corrosion

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item components 4 stress corrosion Cracking, and AMP nominal pipe size cracking (IGSCC) XI.M2, Water exposed to treated Chemistry water >93 °C (>200

°F) 055 BWR/PWR Steel piping, piping None None Yes (SRP-SLR V.F.EP-112 components Section 3.2.2.2.9) exposed to concrete 056 BWR/PWR Aluminum piping, Loss of material due AMP XI.M32, One- Yes (SRP-SLR V.A.EP-3b piping components, to pitting, crevice Time Inspection, Section 3.2.2.2.10) V.A.EP-3c 3.2-33 tanks exposed to air,corrosion AMP XI.M38, V.A.EP-3d condensation Inspection of V.D1.EP-3b (internal) Internal Surfaces in V.D1.EP-3c Miscellaneous V.D1.EP-3d Piping and Ducting V.D2.EP-3b Components, or V.D2.EP-3c AMP XI.M42, V.D2.EP-3d Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 057 BWR/PWR Copper alloy piping, None None No V.F.EP-10 piping components exposed to air, condensation, gas

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 058 PWR Copper alloy, copper None None No V.F.EP-12 alloy (>8%

aluminum) piping, piping components exposed to air with borated water leakage 059 BWR/PWR Galvanized steel None None No V.F.EP-14 ducting, ducting components, piping, 3.2-34 piping components exposed to air -

indoor controlled 060 BWR/PWR Glass piping None None No V.F.EP-15 elements exposed to V.F.EP-16 air, underground, V.F.EP-28 lubricating oil, raw V.F.EP-29 water, treated water, V.F.EP-30 treated borated V.F.EP-65 water, air with V.F.EP-66 borated water V.F.EP-67 leakage, V.F.EP-68 condensation, gas, closed-cycle cooling water D 061 062 BWR/PWR Nickel-alloy piping, None None No V.F.EP-115 piping components

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item exposed to air with borated water leakage 063 BWR/PWR SS piping, piping None None No V.F.EP-19 components V.F.EP-22 exposed to air with borated water leakage, gas 064 BWR/PWR Steel piping, piping None None No V.F.EP-4 components V.F.EP-7 3.2-35 exposed to air -

indoor controlled, gas 065 BWR/PWR Metallic piping, Wall thinning due to AMP XI.M17, Flow No V.D1.E-407 piping components erosion Accelerated V.D2.E-408 exposed to treated Corrosion water, treated borated water 066 BWR/PWR Metallic piping, Loss of material due AMP XI.M38, Yes (SRP-SLR V.A.E-400 piping components, to recurring internal Inspection of Section 3.2.2.2.7) V.B.E-400 tanks exposed to corrosion Internal Surfaces in V.C.E-400 raw water, waste Miscellaneous V.D1.E-400 water Piping and Ducting V.D2.E-400 Components 067 BWR/PWR SS tanks (within the Cracking due to AMP XI.M29, No V.D1.E-405 scope of AMP SCC Outdoor and Large V.D2.E-405 XI.M29, Outdoor Atmospheric Metallic and Large Storage Tanks

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Atmospheric Metallic Storage Tanks) exposed to soil, concrete 068 BWR/PWR Steel tanks (within Loss of material due AMP XI.M29, No V.D1.E-402 the scope of AMP to general, pitting, Outdoor and Large V.D2.E-402 XI.M29, Outdoor crevice corrosion, Atmospheric Metallic and Large MIC (soil only) Storage Tanks Atmospheric Metallic Storage Tanks) 3.2-36 exposed to soil, concrete, air, condensation 069 BWR/PWR Insulated steel Loss of material due AMP XI.M36, No V.E.E-403a piping, piping to general, pitting, External Surfaces V.E.E-403b components, tanks crevice corrosion Monitoring of (within the scope of Mechanical AMP XI.M29, Components or Outdoor and Large AMP XI.M29, Atmospheric Metallic Outdoor and Large Storage Tanks) Atmospheric Metallic exposed to air, Storage Tanks condensation 070 BWR/PWR Steel, SS, aluminum Loss of material due AMP XI.M29, No V.A.E-404 tanks (within the to general (steel Outdoor and Large V.D1.E-404 scope of AMP only), pitting, crevice Atmospheric Metallic V.D2.E-404 XI.M29, Outdoor corrosion, MIC Storage Tanks and Large

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Atmospheric Metallic (steel, stainless Storage Tanks) steel only) exposed to treated water, treated borated water 071 BWR/PWR Insulated copper Cracking due to AMP XI.M36, No V.E.E-406 alloy (>15% zinc or SCC External Surfaces

>8% aluminum) Monitoring of piping, piping Mechanical components, tanks Components 3.2-37 exposed to air, condensation M 072 BWR/PWR Any material piping, Loss of coating or AMP XI.M42, No V.A.E-401 piping components, lining integrity due to Internal V.B.E-401 heat exchangers, blistering, cracking, Coatings/Linings for V.C.E-401 tanks with internal flaking, peeling, In-Scope Piping, V.D1.E-401 coatings/linings delamination, Piping Components, V.D2.E-401 exposed to closed- rusting, or physical Heat Exchangers, cycle cooling water, damage; loss of and Tanks raw water, treated material or cracking water, treated for cementitious borated water, coatings/linings lubricating oil, condensation 073 BWR/PWR Any material piping, Loss of material due AMP XI.M42, No V.A.E-414 piping components, to general, pitting, Internal V.B.E-414 heat exchangers, crevice corrosion, Coatings/Linings for V.C.E-414 tanks with internal MIC In-Scope Piping,

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item coatings/linings Piping Components, V.D1.E-414 exposed to closed- Heat Exchangers, V.D2.E-414 cycle cooling water, and Tanks raw water, treated water, treated borated water, lubricating oil, condensation 074 BWR/PWR Gray cast iron, Loss of material due AMP XI.M42, No V.A.E-415 ductile iron, to selective leaching Internal V.B.E-415 3.2-38 malleable iron Coatings/Linings for V.C.E-415 piping, piping In-Scope Piping, V.D1.E-415 components with Piping Components, V.D2.E-415 internal Heat Exchangers, coatings/linings and Tanks exposed to closed-cycle cooling water, raw water, treated water, treated borated water, waste water D 075 076 BWR/PWR SS, steel, nickel- Loss of material due AMP XI.M18, No V.E.E-418 alloy, copper alloy to general, pitting, Bolting Integrity closure bolting crevice corrosion, exposed to treated MIC (steel, copper water, treated alloy in raw water, borated water, raw waste water only)

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item water, waste water, lubricating oil D 077 078 BWR/PWR SS, steel, aluminum Cracking due to AMP XI.M41, No V.E.E-420 piping, piping SCC (steel in Buried and components, tanks carbonate/bicarbona Underground Piping exposed to soil, te environment only) and Tanks concrete 079 BWR/PWR SS closure bolting Cracking due to AMP XI.M18, No V.E.E-421 exposed to air, soil, SCC Bolting Integrity 3.2-39 concrete, underground E 080 BWR/PWR SS underground Cracking due to AMP XI.M32, Yes (SRP-SLR V.E.E-423a piping, piping SCC One Time Section 3.2.2.2.4) V.E.E-423b components, tanks Inspection, AMP V.E.E-423c XI.M41, Buried and Underground Piping and Tanks, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 081 BWR/PWR SS, steel, aluminum, Reduction of heat AMP XI.M36, No V.E.E-424 copper alloy, transfer due to External Surfaces titanium heat fouling Monitoring of exchanger tubes

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item exposed to air, Mechanical condensation Components D 083 D 084 D 085 D 086 087 BWR/PWR Nonmetallic thermal Reduced thermal AMP XI.M36, No V.E.E-422 insulation exposed insulation resistance External Surfaces to air, condensation due to moisture Monitoring of 3.2-40 intrusion Mechanical Components D 089 090 BWR/PWR Steel components Long-term loss of AMP XI.M32, No V.A.E-434 exposed to treated material due to One Time V.B.E-434 water, treated general corrosion Inspection V.C.E-434 borated water, raw V.D1.E-434 water V.D2.E-434 091 BWR/PWR SS piping, piping None None Yes (SRP-SLR V.F.EP-20 components Section 3.2.2.2.9) exposed to concrete D 092 D 095 096 BWR/PWR Steel, SS piping, Loss of material due AMP XI.M38, No V.D1.E-439 piping components to general (steel Inspection of V.D2.E-440 exposed to raw only), pitting, crevice Internal Surfaces in water (for corrosion, MIC; flow Miscellaneous components not

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item covered by NRC GL blockage due to Piping and Ducting 89-13) fouling Components D 097 098 BWR/PWR Copper alloy (>15% Loss of material due AMP XI.M33, No V.D1.E-441 zinc or >8% to selective leaching Selective Leaching V.D2.E-441 aluminium) piping, piping components exposed to soil 099 BWR/PWR SS, nickel-alloy Loss of material due AMP XI.M32, Yes (SRP-SLR V.E.E-442a tanks exposed to air, to pitting, crevice One Time Section 3.2.2.2.2) V.E.E-442b 3.2-41 condensation corrosion Inspection, AMP V.E.E-442c XI.M36, External V.E.E-442d Surfaces Monitoring of Mechanical Components, AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 100 BWR/PWR Aluminum piping, Cracking due to AMP XI.M32, Yes (SRP-SLR V.A.E-443b piping components, SCC One Time Section 3.2.2.2.8) V.A.E-443c tanks exposed to air, Inspection, AMP V.A.E-443d condensation XI.M38, Inspection V.B.E-443b (internal), raw water, of Internal Surfaces V.B.E-443c waste water in Miscellaneous V.B.E-443d Piping and Ducting V.D1.E-443b Components, or V.D1.E-443c AMP XI.M42, V.D1.E-443d Internal V.D2.E-443b 3.2-42 Coatings/Linings for V.D2.E-443c In-Scope Piping, V.D2.E-443d Piping Components, Heat Exchangers, and Tanks 101 BWR/PWR Aluminum piping, Cracking due to AMP XI.M32, Yes (SRP-SLR V.E.E-444b piping components, SCC One Time Section 3.2.2.2.8) V.E.E-444c tanks exposed to air, Inspection, AMP V.E.E-444d condensation XI.M36, External (external) Surfaces Monitoring of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 102 BWR/PWR Aluminum tanks Cracking due to AMP XI.M29, Yes (SRP-SLR V.D1.E-445a (within the scope of SCC Outdoor and Large Section 3.2.2.2.8) V.D1.E-445b AMP XI.M29, Atmospheric Metallic V.D1.E-445c Outdoor and Large Storage Tanks, V.D2.E-445a Atmospheric Metallic AMP XI.M32, One- V.D2.E-445b Storage Tanks) Time Inspection, or V.D2.E-445c exposed to air, AMP XI.M42, condensation, soil, Internal concrete, raw water, Coatings/Linings for waste water In-Scope Piping, 3.2-43 Piping Components, Heat Exchangers, and Tanks 103 BWR/PWR SS tanks (within the Cracking due to AMP XI.M29, Yes (SRP-SLR V.D1.E-446a scope of AMP SCC Outdoor and Large Section 3.2.2.2.4) V.D1.E-446b XI.M29, Outdoor Atmospheric Metallic V.D1.E-446c and Large Storage Tanks, V.D2.E-446a Atmospheric Metallic AMP XI.M32, One V.D2.E-446b Storage Tanks) Time Inspection, or V.D2.E-446c exposed to air, AMP XI.M42, condensation Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 104 BWR/PWR Aluminum tanks Loss of material due AMP XI.M29, No V.D1.E-447 (within the scope of to pitting, crevice Outdoor and Large V.D2.E-447 AMP XI.M29, corrosion

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Outdoor and Large Atmospheric Metallic Atmospheric Metallic Storage Tanks Storage Tanks) exposed to soil, concrete 105 BWR/PWR Aluminum tanks Loss of material due AMP XI.M29, Yes (SRP-SLR V.D1.E-448a (within the scope of to pitting, crevice Outdoor and Large Section 3.2.2.2.10) V.D1.E-448b AMP XI.M29, corrosion Atmospheric Metallic V.D1.E-448c Outdoor and Large Storage Tanks, V.D2.E-448a Atmospheric Metallic AMP XI.M32, One V.D2.E-448b 3.2-44 Storage Tanks) Time Inspection, or V.D2.E-448c exposed to air, AMP XI.M42, condensation Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks N 106 BWR/PWR SS, nickel alloy Loss of material due AMP XI.M29, Yes (SRP-SLR V.D1.E-449a tanks (within the to pitting, crevice Outdoor and Large Section 3.2.2.2.2) V.D1.E-449b scope of AMP corrosion Atmospheric Metallic V.D1.E-449c XI.M29, Outdoor Storage Tanks, V.D2.E-449a and Large AMP XI.M32, One V.D2.E-449b Atmospheric Metallic Time Inspection, or V.D2.E-449c Storage Tanks) AMP XI.M42, exposed to air, Internal condensation Coatings/Linings for In-Scope Piping, Piping Components,

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Heat Exchangers, and Tanks 107 BWR/PWR Insulated SS, nickel- Loss of material due AMP XI.M29, Yes (SRP-SLR V.E.E-450a alloy piping, piping to pitting, crevice Outdoor and Large Section 3.2.2.2.2) V.E.E-450b components, tanks corrosion Atmospheric Metallic V.E.E-450c exposed to air, Storage Tanks, V.E.E-450d condensation AMP XI.M32, One Time Inspection, AMP XI.M36, External 3.2-45 Surfaces Monitoring of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 108 BWR/PWR Insulated SS piping, Cracking due to AMP XI.M29, Yes (SRP-SLR V.E.E-451a piping components, SCC Outdoor and Large Section 3.2.2.2.4) V.E.E-451b tanks exposed to air, Atmospheric Metallic V.E.E-451c condensation Storage Tanks, V.E.E-451d AMP XI.M32, One-Time Inspection, AMP XI.M36, External Surfaces Monitoring

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 109 BWR/PWR Insulated aluminum Cracking due to AMP XI.M29, Yes (SRP-SLR V.E.E-452a 3.2-46 piping, piping SCC Outdoor and Large Section 3.2.2.2.8) V.E.E-452b components, tanks Atmospheric Metallic V.E.E-452c exposed to air, Storage Tanks, V.E.E-452d condensation AMP XI.M32, One Time Inspection, AMP XI.M36, External Surfaces Monitoring of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 110 BWR/PWR Aluminum Cracking due to AMP XI.M32, One Yes (SRP-SLR V.E.E-453a underground piping, SCC Time Inspection, Section 3.2.2.2.8) V.E.E-453b piping components, AMP XI.M41, V.E.E-453c tanks Buried and Underground Piping and Tanks, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, 3.2-47 Heat Exchangers, and Tanks 111 BWR/PWR Aluminum Loss of material due AMP XI.M32, Yes (SRP-SLR V.E.E-454a underground piping, to pitting, crevice One-Time Section 3.2.2.2.10) V.E.E-454b piping components, corrosion Inspection, AMP V.E.E-454c tanks XI.M41, Buried and Underground Piping and Tanks, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 112 BWR/PWR Stainless steel, Loss of material due AMP XI.M32, One Yes (SRP-SLR V.E.E-455a nickel-alloy to pitting, crevice Time Inspection, Section 3.2.2.2.2) V.E.E-455b underground piping, corrosion AMP XI.M41, V.E.E-455c piping components, Buried and tanks Underground Piping

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item and Tanks, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks D 113 114 BWR/PWR SS, nickel-alloy Cracking due to AMP XI.M2, Water No V.B.E-457 piping, piping SCC Chemistry, and V.C.E-457 3.2-48 components AMP XI.M32, V.D2.E-457 exposed to treated One-Time water >60 °C Inspection

(>140 °F) 115 BWR/PWR Titanium heat Cracking due to AMP XI.M2, Water No V.A.E-458 exchanger tubes SCC, reduction of Chemistry, and V.D1.E-458 exposed to treated heat transfer due to AMP XI.M32, V.D2.E-458 water fouling One-Time Inspection E 116 BWR/PWR Titanium ([ASTM] None None No V.F.E-459 Grades 1, 2, 7, 9, 11, or 12) heat exchanger components other than tubes, piping, piping components exposed to treated water

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 117 BWR/PWR Titanium heat Cracking due to AMP XI.M21A, No V.A.E-460 exchanger tubes SCC, reduction of Closed Treated V.D1.E-460 exposed to closed- heat transfer due to Water Systems V.D2.E-460 cycle cooling water fouling 118 BWR/PWR Titanium (ASTM None None No V.F.E-461 Grades 1, 2, 7, 9, 11, or 12) heat exchanger components other than tubes, piping, 3.2-49 piping components exposed to closed-cycle cooling water E 119 BWR/PWR Insulated aluminum Loss of material due AMP XI.M29, Yes (SRP-SLR V.E.E-462a piping, piping to pitting, crevice Outdoor and Large Section 3.2.2.2.10) V.E.E-462b components, tanks corrosion Atmospheric Metallic V.E.E-462c exposed to air, Storage Tanks, V.E.E-462d condensation AMP XI.M32, One-Time Inspection, AMP XI.M36, External Surfaces Monitoring of Mechanical Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components,

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Heat Exchangers, and Tanks 120 BWR/PWR Aluminum piping, Loss of material due AMP XI.M41, No V.E.E-463 piping components, to pitting, crevice Buried and tanks exposed to corrosion Underground Piping soil, concrete and Tanks 121 BWR/PWR Aluminum piping, Loss of material due AMP XI.M29, Yes (SRP-SLR V.E.E-464a piping components, to pitting, crevice Outdoor and Large Section 3.2.2.2.10) V.E.E-464b tanks exposed to corrosion Atmospheric Metallic V.E.E-464c raw water, waste Storage Tanks, V.E.E-464d 3.2-50 water AMP XI.M32, One-Time Inspection, AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components, or AMP XI.M42, Internal Coatings/Linings for In-Scope Piping, Piping Components, Heat Exchangers, and Tanks 122 BWR/PWR Elastomer piping, Loss of material due AMP XI.M36, No V.E.E-465 piping components, to wear External Surfaces seals exposed to air Monitoring of

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item Mechanical Components 123 BWR/PWR Elastomer piping, Loss of material due AMP XI.M38, No V.A.E-466 piping components, to wear Inspection of V.B.E-466 seals exposed to air Internal Surfaces in V.C.E-466 Miscellaneous V.D1.E-466 Piping and Ducting V.D2.E-466 Components 124 BWR/PWR Aluminum piping, None None No V.F.E-467 piping components, 3.2-51 tanks exposed to air with borated water leakage 125 BWR/PWR Steel closure bolting Loss of material due AMP XI.M41, No V.E.E-468 exposed to soil, to general, pitting, Buried and concrete, crevice corrosion, Underground Piping underground MIC (soil only) and Tanks 126 BWR/PWR Titanium, super Loss of material due AMP XI.M41, No V.E.E-469 austenitic piping, to pitting, crevice Buried and piping components, corrosion, MIC Underground Piping tanks, closure (except for titanium; and Tanks bolting exposed to soil environment soil, concrete, only) underground 127 BWR/PWR Copper alloy piping, None None No V.F.E-470 piping components exposed to concrete

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 128 BWR/PWR Copper alloy piping, Loss of material due AMP XI.M41, No V.E.E-471 piping components to general, pitting, Buried and exposed to soil, crevice corrosion, Underground Piping underground MIC (soil only) and Tanks 129 BWR/PWR Stainless steel tanks Loss of material due AMP XI.M29, No V.D1.E-472 exposed to soil, to pitting, crevice Outdoor and Large V.D2.E-472 concrete corrosion, MIC (soil Atmospheric Metallic only) Storage Tanks 130 BWR/PWR Steel heat Loss of material due AMP XI.M39, No V.A.E-473 exchanger to general, pitting, Lubricating Oil V.D1.E-473 3.2-52 components crevice corrosion, Analysis, and AMP V.D2.E-473 exposed to MIC XI.M32, One Time lubricating oil Inspection 131 BWR/PWR Aluminum piping, Flow blockage due AMP XI.M38, No V.A.E-474 piping components to fouling Inspection of V.B.E-474 exposed to raw Internal Surfaces in V.D1.E-474 water Miscellaneous V.D2.E-474 Piping and Ducting Components M 132 BWR/PWR Titanium (ASTM Cracking due to AMP XI.M20, Open No V.A.E-475 Grades 3, 4, or 5) SCC, flow blockage Cycle Cooling Water V.D1.E-475 heat exchanger due to fouling System V.D2.E-475 tubes exposed to raw water

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item 133 BWR/PWR Titanium piping, Cracking due to AMP XI.M20, Open No V.B.E-476 piping components, SCC, flow blockage Cycle Cooling Water V.C.E-476 heat exchanger due to fouling System V.D2.E-476 components exposed to raw water M 134 BWR/PWR Polymeric piping, Hardening or loss of AMP XI.M36, No V.A.E-477b piping components, strength due to External Surfaces V.B.E-477b ducting, ducting polymeric Monitoring of V.D1.E-477b components, seals degradation; loss of Mechanical V.D2.E-477b 3.2-53 exposed to air, material due to Components, AMP V.E.E-477a condensation, raw peeling, XI.M38, Inspection water, raw water delamination, wear; of Internal Surfaces (potable), treated cracking or blistering in Miscellaneous water, waste water, due to exposure to Piping and Ducting underground, ultraviolet light, Components concrete, soil ozone, radiation, or chemical attack; flow blockage due to fouling (Inspection of Internal Surfaces only)

Table 3.2-1 Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the Generic Aging Lessons Learned for Subsequent License Renewal Report (Continued)

New, Aging Management Generic Aging Modified, Program Lessons Learned Deleted, (AMP)/Time- for Subsequent Edited Aging Effect/ Limited Aging Further Evaluation License Renewal Item ID Type Component Mechanism Analyses (TLAA) Recommended Item N 135 BWR/PWR Steel, stainless steel Loss of material due Plant-specific or Yes (SRP-SLR V.A.E-457 or nickel-alloy ASME to wear existing aging Section 3.2.2.2.11) V.B.E-457 Code Class 2 small- management V.C.E-457 bore piping, and program if loss of V.D1.E-457 piping components material is not V.D2.E-457 with reflective metal mitigated V.E.E-457 insulation exposed to air 1 AMP = aging management program; BWR = boiling water reactor; CASS = cast austenitic stainless steel; HPSI = high-pressure safety injection; IGSCC =

2 intergranular stress corrosion cracking; MIC = microbiologically-induced corrosion; PWR = pressurized water reactor; SCC = stress corrosion cracking; SRP-SLR =

3.2-54 3 Standard Review Plan for Review of Subsequent License Renewal; SS = stainless steel; TLAA = Time-Limited Aging Analyses.

NUREG-2192, Revision 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, Draft Report for Comment, Corrected Tables 3.1-1 and 3.2-1

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