ML083510614
| ML083510614 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/11/2008 |
| From: | APS, Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 102-05937-DCM/GAM | |
| Download: ML083510614 (296) | |
Text
{{#Wiki_filter:Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-13 Auxiliary Systems - Summary of Aging Management Evaluation- Fuel Building HVAC System Component I ntended ~Material~ Environment ~Aginig Effect 1Aing Management ~NUREG- ~Table 1 Itemh Notes Requiring ~ 1801 Vol. Typ Fucto Type 1unctin ~M~anagement 1< Program> 2Item~ 2 ____ --I__ Blower PB Carbon Steel Indoor Air tPlant ;Loss of material External Surfaces VII.F2-2 3.3.1.56 B Monitoring Program (B2.1.20) Blower PB Carbon Steel SVentilation Loss of material Inspection Of Internal VII.F2-3 3.3.1.72 B
'Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components _(B2.1.22L__
G, 1 Closure Bolting NSRS, PB Carbon Steel Atmosphere/ iLoss of preload Bolting Integrity (B2.1.7) None None Weather (Ext) _ Closure Bolting NSRS, PB Carbon Steel Atmosphere/ !Loss of material Bolting Integrity (B2.1.7) V1II.I-1 3.3.1.43 B Weather (Ext) _ Closure BoltingtNSRS, PB Carbon Steel Plant Indoor Air Loss of material External Surfaces fVII.F2-4 '3.3.1.55 B (Ext) Monitoring Program (B2.1.20) 4>' 4 Closure Bolting NSRS, PB Carbon Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.7) jVII.I-4 3.3.1.43 B LExt ____ Closure Bolting {NSRS, PBlCarbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) VII.I-5 13.3.1.45 (Ext) _ Damper NSRS Carbon Steel Atmosphere/ Loss of material External Surfaces 1VII.l-9 3.3.1.58 (Galvanized) Weather (Ext) Monitoring Program (B2.1.20)_ Damper fFB, NSRSTCarbon Steel TEncased in None -__ None VII.J-21 3.3.1.96 (Galvanized)I Concrete (Ext Damper PB Carbon Steel Plant Indoor Air INone None VIIJ-6 13.3.1.92 (Galvanized) -(-xtD - Palo Verde Nuclear Generating Station Page 3.3-151 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS INone IVlI.J-6 (Galvanized) Atmosphere (Ext) _ Carbon Steel jVentilation 13.3.1.92 Damper FB, Carbon Steel Ventilation I None None IVlI.J-6 NSRS, pR I(Ga'*lvani7edl lAtmospnhe~r (Int'l
.I.. .. .I ...
PB-- NSRS, Pbj Carbon Steel Loss of material iVII.I-9 3.3.1.58 Ductwork Atmosphere/ External Surfaces I(Galvanized) Weather (Ext) Monitoring Program (B2.1.20) Ductwork INSRS, PB Carbon Steel Plant Indoor Air None None IVlI.J-6 3.3.1.92 (Galvanized) (Ext) Ductwork NSRS, PB Carbon Steel Ventilation None None VII.J-6 3.3.1.92 (Galvanized) Atmosphere (Int) Flex NSRS, PB Elastomer Plant Indoor Air Hardening and External Surfaces VII.F2-7 3.3.1.11 Connectors (Ext) loss of strength Monitoring Program 17Hardeng and (B2.1.20) i
----------------------
PB Elastomer Ventilation Inspection Of Internal VII.F2-7 l 3.3.1.11 E Connectors Atmosphere (Ext) loss of strength Surfaces In Miscellaneous Piping And Ducting Hardening and Components (B2.1.22) NSRS, PB Elastomer 1~ I i Flex Ventilation Inspection Of Internal VII.F2-7 13.3.1.11 E Connectors Atmosphere (Int) 'loss of strength Surfaces In Miscellaneous Piping And Ducting Components (B2.1 .22) None VII.J-15 Flow Element IPB Stainless Plant Indoor Air None 3.3.1.94 Steel (Ext) Flow Element IPB Stainless Ventilation None None VII.J-15 3.3.1.94 A, 2 Steel Atmosphere (Int) Palo Verde Nuclear Generating Station Page 3.3-152 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS miping uarbon i-'lant inaoor LOSS OT materiai txternai surraces !Vll.l-t i.i.1.0b (Ext) Monitoring Program (B2.1.20) ,.__ __ Piping NS RS Carbon Steel Wetted Gas (Int) Loss of material Inspection Of Internal VII.F2-3 13.3.1.72 B Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Piping Stainless Atmosphere! None None iNone None Steel Weather Ext)_ Piping PB Stainless Plant Indoor Air None None 1VII.J-15 3.3.1.94 A Steel P ip iing PB Stainless Ventilation None None IVII.J-15 13.3.1.94 A, 2 Steel Atmosphere (Int) Tubing PB Stainless Atmosphere/ INone None None ]None G Steel Weather (Ext)__ Tubing PB Stainless Plant Indoor Air None None IVII.J-15 13.3.1.94 Steel (Ext) Tubing PB Stainless Ventilation None None IVII.J-15 3.3.1.94 A, 2 Steel Atmosphere O(Int) 1_. Valve NSRS Carbon Steel Plant Indoor Air Loss of material External Surfaces - iVI .1-8 3.3.1.58 B (Ext) Monitoring Program B(32.1.20) ..... ...... . Valve Carbon Steel rWetted Gas (Int) Loss of material Inspection Of Internal VII.F2-3 3.3.1.72 Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) I Palo Verde Nuclear Generating Station Page 3.3-153 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-13 Auxiliary Systems - Summary of Aging Management Evaluation- Fuel Buildin HVAC tem (Continued) Co6mponent, Intended Material Environment Aging Effect Aging Management NUREG- Table I Item~ Notesv Type &&Function Requiring ~ ~ Program 18 01 Vol 0 Management ~Item 2j2 Valve PB Stainless Atmosphere/ None None None INone G Steel Weather (Ext) _ __ _ _ _ _ __ Valve PB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A Steel *(Ext) Valve PB Stainless Ventilation None None VII.J-15 3.3.1.94 A, 2 Steel AtopeeInt) ________________.....________ _____ Notes for Table 3.3.2-13: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 Line VII.I-5 has loss of preload/thermal effects, gasket creep, and self-loosening for steel closure bolting in indoor uncontrolled (external) air. This aging effect would also exist in the environment or outdoor (external) air, therefore this non-NUREG-1 801 line has been added to also address loss of preload for the component/material/environment of line VII.-11. 2 Stainless steel valves and tubing in HVAC systems with an internal environment of ventilation atmosphere are used for air sampling, flow measurement and as differential pressure instrument lines. Condensation is not expected in these applications. The NUREG-1801 line referenced for the aging evaluation is VII.J-15 which is for Air-Uncontrolled (external). In ventilation systems, the internal and external air environments are evaluated as equivalent. Palo Verde Nuclear Generating Station Page 3.3-154 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS AA~qn~qynim~nn Punin~,.tirn - flnntninmpnt Ruilii~~ Carbon Steel Plant Indoor Air Loss ot material External Surfaces VII.F3-2 B (Ext) Monitoring Program ((B2.11.20) Blower NSRS Carbon Steel i entilation tLoss of material Inspection Of Internal :VII.F3-3 3.3.1.72 B Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) , Closure Bolting NSRS Carbon Steel !Plant Indoor Air Loss of material External Surfaces VII.F3-4 3.3.1.55 B i(Ext) Monitoring Program
........... ..... .............. (B2.1.20)
Closure Bolting LBS, Carbon Steel Pant Indoor Air Loss of material Bolting Integrity (B2.1.7) ;Vll.l-4 13.3.1.43 B NSRS, PB (Ext) Bolting Integrity (B2.1.7) :VII.l-5 B--------- Closure Bolting LBS, Carbon Steel Plant Indoor Air !Loss of preload 3.3.1.45 NSRS, PB (Ext). _ -4 Damper NSRS Carbon Steel Plant Indoor Air 1None None iVII.J-6 3.3.1.92 c (Galvanized) Ext Damper NSRS Carbon Steel Ventilation None NoInIe C (Galvanized) Atmosphere (Int) Ductwork NSRS Carbon Steel Plant Indoor Air jNone None VII.J-6 13.3.1.92 C (Galvanized) (Ext) Ductwork INSRS Carbon Steel Ventilation 1None None VII.J-6 3.3.1.92 (Galvanized) Atmosphere (Int) Palo Verde Nuclear Generating Station Page 3.3-155 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS nmant Punhinf~inn - (nntinmanf Rtifirlinry MI(U Vt ' nntinitpri) LJUU LVVUJI IM Stainless Plant Indoor Air Steel (Ext) Ductwork NSRS Stainless Ventilation Loss of material Inspection Of Internal iVII.F3-1 3.3.1.27 Steel Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Flex NSRS Elastomer Plant Indoor Air Hardening and External Surfaces VII.F3-7 3.3.1.11 E Connectors (Ext) loss of strength Monitoring Program (B2.1.20) Flex NSRS Elastomer Ventilation Hardening and Inspection Of Internal VIL.F3-7 3.3.1.11 E Connectors Atmosphere (Int) loss of strength Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22)1 Fle xi-ble Hoses PB Stainless Plant Indoor Air None None IVII.J-15 3.3.1.94 Steel (Ext) A, 1 Flexible Hoses TPB Stainless Plant Indoor Air None None 1VII.J-15 3.3.1.94 Steel (Int) Heat LBS, Copper Alloy Closed-Cycle Loss of material Closed-Cycle Cooling IVII.F3-8 3.3.1.51 B Exchanger NSRS Cooling Water (Int)i Water System (B2.1.10) (Containment Bldg) Heat LBS, Copper Alloy Ventilation Loss of material Inspection Of Internal VII.F3-16 3.3.1.25 E Exchanger NSRS Atmosphere (Ext) Surfaces In (Containment Miscellane6us Piping Bldg) +/- And Ducting Components _(B 2.22.)L Palo Verde Nuclear Generating Station Page 3.3-156 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Closed-Cycle Cooling Exchanger NSRS Cooling Water (Int), Water System (B2.1.10) (Containment C E DM) Heat LBS, Copper Alloy Ventilation Loss of material Inspection Of Internal VII.F3-16 3.3.1.25 Exchanger NSRS Atmosphere (Ext) Surfaces In (Containment Miscellaneous Piping CEDM) And Ducting Components (B2.1.22) Heater Stainless Plant Indoor Air None None VlI.J-15 i3.3.1.94 C Steel Heater NSRS Stainless Ventilation Loss of material Inspection Of Internal VII.F3-1 T3..27 Steel Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components B2.1.22) Piping PB Carbon Stee I Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 (Ext) Monitoring Program (B2.1.20) Piping Carbon Ste eI Plant Indoor Air Loss of material Inspection Of Internal V.A-19 3.2.1.32 (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Piping PB, SIA Stainless Plant Indoor Air None None ýVII.J-15 3.3.1.94 A Steel (Ext) PB, SIA Stainless Indoor..Air Plant................... None iVII.J-15 3.3.1.94 A, 1 Piping Steel
.......... None Palo Verde Nuclear Generating Station Page 3.3-157 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS i uoing tiainiess riani (Ext) inaoor/-xir rione ___
'None v IVI.J-i1 0.,. I.
I/ Steel Tubing PB Stainless Plant Indoor Air None None IVII.J-15 3.3.1.94 A, 1 Steel (Int)
..........
........... F......
..............
......... C Valve PB Carbon Steel Plant Indoor Air Loss )f material External Surfaces [VII.1-8 3.3.1.58 B (Ext) Monitoring Program (B2.1.20)
Valve tPB jCarbon Steel Plant Indoor Air !Loss of material Inspection Of Internal V.A-19 3.2.1.32 B (Int) Surfaces In Miscellaneous Piping And Ducting Components B2.1.22) Valve PB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 Steel (Ext) Valve PB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A, 1 Steel (Int) Notes for Table 3.3.2-14: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1 801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. Palo Verde Nuclear Generating Station Page 3.3-158 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Plant Specific Note: 1 Stainless steel piping and piping components associated with containment building HVAC are used in containment pressure monitoring instrument lines. Condensation is not expected in these applications. The NUREG-1801 line referenced for the aging evaluation is VII.J-15 which is for Air-Uncontrolled (external). In this application, the internal and external air environments are evaluated as equivalent. Palo Verde Nuclear Generating Station Page 3.3-:159 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ment Evaluation - Diesel GeneratorBi Dlower I,40mo, Plant Indoor Air LOS5 U1 miiadrlai r-xernial oUldUus (Ext) Monitoring Program (B2.1.20) Blower NSRS, PB Carbon Steel Ventilation 1 Loss of material Inspection Of Internal VII. F4-2 3.3.1.72 Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting 4 ComDonents (B2.1.22)
- __________ 4 -
Closure Bolting fNSRS, PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.F4-3 13.3.1.55 B (Ext) Monitoring Program (B2.1.20) _,_ ._ , Closure Bolting 7NSRS, PB Carbon Steef Plant Indoor Air ILoss of material Bolting Integrity (B2.1.7) VII.l-4 13.3.1.43 B (Ext) Damper _ _ I_ Closure Bolting NSRS, PB Carbon Steel Plant Indoor Air Exts __ iFB, NSRS jCarbon Steel Encased in Loss of preload Bolting Integrity (B2.1.7) VII.1-5 None ] 13.3.1.45 13.3.1.96 B (Galvanized) Concrete (Ext) oneT I. Damper NSRS, PB Carbon Steel Plant Indoor Air None None VII.J-6 3.3.1.92 C (Galvanized) (Ext) Damper FB, Carbon Steel Ventilation None None VII.J-6 3.3.1.92 NSRS, PB Galvanized Atm re Int) Ductwork NSRS, PB Carbon Steel Plant Indoor Air None None VII.J-6 3.3.1.92 C (Galvanized) (Ext) Ductwork NSRS, PB Carbon Steel Ventilation iNone None '3.3.1.92 (Galvanized) Atmosphere!!nt) Palo Verde Nuclear Generating Station Page 3.3-160 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-15 Auxiliary Systems - Summary of Aging Management Evaluation - Diesel Generator Building HVAC System (Continued) 1-lex I'Jbrb, rD clasiomer rian inoaor Mir Sriaraening ana r-xiernai ourraces Connectors (Ext) loss of strength Monitoring Program _(B2.1.20) Flex -NSRS,PgiElastomer Ventilation Hardening and Inspection Of Internal iVII.F4-6 !3.3.1.11 E Connectors Atmosphere (Int) loss of strength Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Heater INSRS Carbon Steel Plant Indoor Air Loss of material External Surfaces IVII.F4-1 3.3.1.56 B (Ext) Monitoring Program (B2.1.20) _ Heater NSRS 1Carbon Steel Ventilation Loss of material Inspection Of Internal IVII.F4-2 13.3.1.72 lB Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting ComNonents 32.1.22 None IVlll.1-2 Piping Copper Alloy Plant Indoor Air None 3.4.1.41 A NSRS W(Ext LEBS, Wetted Gas (Int) Loss of material Inspection Of Internal VII.G-9 3.3.1.28 IE Piping Copper Alloy NSRS Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22L___ Strainer LBS +Con-ppeýrAAoy Plant Indoor Air None None IVII.I-2 13.4.1.41 A ______________ _______
..I ____________ (Ext)
Palo Verde Nuclear Generating Station Page 3.3-161 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-15 Auxiliary Systems - Summary of Aging Management Evaluation - Diesel Generator Building HVAC System (Continued)
.urainer LJj inspecuon UT imernai vii.u Surfaces In Miscellaneous Piping And Ducting
____________
........................
. _______I __
Components (B2.1.22) Tubing PB Copper Alloy Plant Indoor Air None None VIIl- -2 13.4.1.41 A (Ext) i Tubing P13 Copper Alloy Ventilation None None 3.4.1.41 IVIII.1-2 Al Atmosphere (Int) Valve LBS, Copper Alloy Plant Indoor Air None None VIII.I-2 23.4.1.41 - IA NSRS _(Ext Valve LBS, Copper Alloy Wetted Gas (Int) Loss of material Inspection Of Internal IVII.G-9 3.3.1.28 NSRS Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Notes for Table 3.3.2-15: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. Palo Verde Nuclear Generating Station Page 3.3-162 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Plant Specific Note: 1 Copper alloyvalves and tubing in HVAC systems with an internal environment of ventilation atmosphere are used for air sampling, flow measurement and as differential pressure instrument lines. Condensation is not expected in these applications. The NUREG-1801 line referenced for the aging evaluation is VIII.I-2 which is for Air-Indoor-Uncontrolled (External). In ventilation systems, the internal and external air environments are evaluated as equivalent. Palo Verde Nuclear Generating Station Page 3.3-163 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS T--4h/jm 1 '4 9-1 OR A itvi1iqn1.qv1cztPm-,z -. qtimmqn1 nf )
-xternai ziurraces 1VII.-z-(Ext) Monitoring Program (B2.1.20)
Closure Bolting PB Carbon i Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.7) IVII.l-4 3.3.1.43 B I!Carbon S (Ext_ Closure Bolting PB Steel Plant Indoor Air Loss of pr eload Bolting Integrity (B2.1.7) IVII.I-5 3.3.1.45 B (Ext) Damper Carbon Steel Encased in None None 1VII.J-21 i3.3.1.96 C (Galvanized) Concrete (Ext) Damper Carbon Steel Ventilation None None iVII.J-6 3.3.1.92 C GaronizSde) Atmosphere (Int) Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 3.3.1.58 B Piping LBS (Ext) Monitoring Program (B2.1.20) Piping LBS§ Carbon Stel Wetted Gas (Int) Loss of material Inspection Of Internal VII.F2-3 3.3.1 72 B Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) _ Notes for Table 3.3.2-16: Standard Notes: B Consistent with NUREG-1 801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.3-164 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Blower PB ýAluminum Plant Indoor Air None None VII.J-1 3.3.1.95 C Blower PB lAluminum Ventilation Loss of material Inspection Of Internal V1112-12 3.3.1.27 E
,Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting
... .. ............. om ponents(B2@ 1.22)
Closure Bolting PB Carbon Steel Atmosphere! Loss of preload Bolting Integrity (B2.1.7) None None G PBWeather (Ext) Closure Bolting PB Carbon Steel Atmosphere/ iLoss of material Boltingtegrity (B2.1.7) 3.3.1.43 _Weather (Ext) PB Carbon Sieel iPlIant Indioor Air Loss of material External Surfaces VII.F2-4 3.3.1.55 B (Ext) Monitoring Program Closure Bolting (B2.1.20) PB -Carbon Steel Plant Indoor Air iLossof material Bolting Integrity (B2--.i) VILI-4 3.3.1.43 B
*(xt)
Closure Bolting PB Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) NVI.l-5 3.3.1.45 B __ _ (Ext) PB iAluminum Atmosphere! G IDamper Loss of material External Surfaces None None Damper Weather (Ext) Monitoring Program (B2.1-.20) PB Aluminum Ventilation 1Loss of material Inspection Of Internal . VII.F2-12 3.3.1.27 E
,Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components-(B2-..22)
Damper FB, PB !Carbon Steel Encased in None None VII.J-21 3.3.1.6 J I(Galvanized) Concrete (Ext) Damper ÷FB,]B Carbon Steýl Ventilation.... 'None None VII.J-6 3.3.1.92 1C S......(Galvanized) kAtmosphere (Int)__ Palo Verde Nuclear Generating Station Page 3.3-165 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-17: Standard Notes: B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1 801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.3-166 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-18 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Site Structures/Spray Pond Pumo House HVAC Svstem ilant Inaoor mxternai surraces (Ext) Monitoring Program (B2.1.20) Blower PB Carbon Steel Ventilation ILoss of material Inspection Of Internal VII.F2-3 ,3.3.1.72 B Atmosphere (Int) I Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Closure Bolting JPB Carbon Steel Plant Indoor Air ILoss of material External Surfaces VII.F2-4 3.3.1.55 B (Ext) Monitoring Program Plant Indoor Air ILoss of material (B2.1.20) Closure Bolting PB Carbon Steel (Ext) Air !osfma Bolting Integrity (B2.1.7) IVI1.I-4 13.3.1.43 B Plant Indoor Air Loss of preload Closure Bolting IPB Carbon Steel (Ext) Indoo A L o a Bolting Integrity (B2.1.7) IVII.l-5 13.3.1.45 B Plant Indoor Air None 3 Ductwork PB Carbon Steel P(Ext Idr,_ o None IV II.J-6 (Galvanized 13.3.1.92 Ductwork Carbon Steel Ventilation B None None i3.3.1.92 C JVll.J-6 i(Galvanized) Atmosphere (Int) PB Elastomer Plant Indoor Air Hardening and External Surfaces VII.F2-7 -!3.3.1.11 Connectors (Ext) 'loss of strength Monitoring Program (B2.1.20) i --- +- Flex PB Elastomer Ventilation Hardening and Inspection Of Internal VII.F2-7 3.3.1.11 E Connectors Atmosphere (Int) loss of strength Surfaces In Miscellaneous Piping And Ducting
,Compnents (B2,12)
Palo Verde Nuclear Generating Station Page 3.3-167 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-18 Standard Notes: B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.3-168 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS tl4UbUI U DUILl11ily ID r- %ýCl IUUI O10 LU 1 Weather (Ext IB Closure Bolting +PB ^Carbon Steel Atmosphere/ Loss of material Bolting Integrity (B2.1.7) IVII.l-1 13.3.1.43 Weather (Ext) + Closure Bolting IPB lCarbon Steel Buried (Ext) Loss of nnaterial Buried Piping and Tanks:VII.G-25 3.3.1.19 D Inspection (B2.1.18) Closure Bolting LBS, P B Carbon Steel Plant Indoor Air Loss of nnaterial Bolting Integrity (B2.1.7) VII.l-4 3.3.1.43 (Ext) B Closure Bolting LBS, P B Carbon Steel Plant Indoor Air iLoss of preload Bolting Integrity (B2.1.7)V1II.I-5 3.3.1.45 (Ext) Expansion PB Stainless Diesel Exhaust Cracking Inspection Of Internal VII.H2-1 3.3.1.06 Joint Steel (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2_1.22)__ ! Expansion PB Stainless Diesel Exhaust TLoss of material Inspection Of Internal VII.H2-2 *3.3.1.18 Joint Steel (Int) Surfaces In Miscellaneous Piping And Ducting Compone nt s B2. 1.22 _________ Expansion 1PB Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry tVil.G-17 3.3.1.32 B Joint Steel (B2.1.14) and One-Time i Inspection (B2.1.16) __, Expansion iPB Stainless Plant Indoor Air INone None IVII.J-15 13.3.1.94 Joint _ Steel (Ext) Filter E FIL, PE Aluminum. Drjy Gas I(t) None None 1ll.J-2 13.3.1.97 A Palo Verde Nuclear Generating Station Page 3.3-169 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 3m~ont Puhnfn - IPira Prtcor-fin queha~tvm ICntinitinM Plant Indoor Air (Ext) Flame Arrestor PB Aluminum Atmosphere/ Loss of material External Surfaces iNone None Weather (Ext) Monitoring Program _(B2.1:.20)* .............. .. Flame Arrestor PB JAll uni num Atmosphere/ Loss of material External Surfaces None None G, 4 Weather (Int) Monitoring Program (B2.1.20) Flexible Hoses PB Stainless Dry Gas (Int) None None 'VII.J-19 3.3.1.97 _ Steel Flexible Hoses PB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 i Steel (Ext) Flow Element PB Stainless Plant Indoor Air None None 1VII.J-15 3.3.1.94 A Steel (Ext), Fl:ow Element PB Stainless Raw Water (Int) Loss of material Fire Water System IVII.G-19 3.3.1.69 B Steel (B2-1.13) ......... ..... Hydrant iPB Cast Iron Atmosphere/ !Loss of material External Surfaces VII.I-9 3.3.1.58 B (Gray Cast Weather (Ext) Monitoring Program Iro n) ................... Burie d I .......................... (B2.1.20) i n ..f .............
.ail
......................
...... v i - : i ......... 3 3 :i 8 ..........
Hydrant PB Cast Iron Loss of material Selective Leaching of :VIG1 3.3.1.85 (Gray Cast Materials (B2.1.17) [Iron) Buried (Ext) B Hydrant PB Cast Iron Loss of material Buried Piping and TanksVIlI.G-25 3.3.1.19
,(Gray Cast Inspection (B2.1.18) B
-+
lIron) 4 Hydrant 1 *B Cast Iron Raw Water (Int) Loss of material Selective Leaching of IVII.G-14 3.3.1.85 S(Gray Cast Materials (B2.1.17) ______ l -roN) Palo Verde Nuclear Generating Station Page 3.3-170 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-19 Auxiliary Systems - Summary of Aaina Management Evaluation - Fire Protection System (Continued) 1 Corponent Intended Materil Ev rEAging Management NUREG- Table 1 Itm Notes Type Function Requiring Program 1801 Vol. ____________ _____ I________ Managemient> 2________ Item L Hydrant PB Cast Iron Raw Water (Int) 'Loss of material Fire Water System VII.G-24 3.3.1.68 B (Gray Cast (B2.1.13) Iron) Piping PB Carbon Steel Atmosphere/ ELoss of material External Surfaces IVII.l-9 13.3.1.58 B Weather (Ext) Monitoring Program (B2.1.20) ___ SPiping PB !Carbon Steel Atmosphere/ SLoss of material Inspection Of Internal VII.l-9 3.3.1.58 E, 4 Weather (Int) Surfaces In Miscellaneous Piping And Ducting Components (.B2.1.22) _ __ PSi~ping Carbon SteeltBuried (Ext) 'Loss of material Buried Piping and Tanks Vl.G-25 13.3.1.19 B Inspection (B2.1.18) _ Piping PB Carbon Steel Diesel Exhaust Loss of material Inspection Of Internal VII.H2-2 !3.3.1.18 E (Int) Surfaces In Miscellaneous Piping I And Ducting I Components (B2.1.22?j 1 PB Carbon Steel 1 Dry Gas.l None None IVII.J-22 33.1.98 A Piping PB Carbon Steel IFuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-24 13.3.1.20 B (B2.1.14) and One-Time' Inspection (B2.1.16). , IPiping __ LBS, Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 13.3.1.58 B NSRS, PB (Ext) Monitoring Program (B2.1.20) _ _______ _ Palo Verde Nuclear Generating Station Page 3.3-171 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Plant Indoor Air II IýjJ*t LIUI I %.JI IIIL IIICI I V 11.1-U (Int) Surfaces In Miscellaneous Piping And Ducting Components B2.1.22 _- Piping LBS, PBWTCarbon Steel Raw Water (Int Loss of material Fire Water System IVII.G-24 3.3.1.68 1B (B2.1.13) Piping NSRS, PB Carbon Steel Wetted Gas (Int) Loss of material Inspection Of Internal ItVlI.G-23 3.3.1.71 B Surfaces In Miscellaneous Piping And Ducting Componentsa-s- (B2.1.22)
................
xte rn.....
........ ii..9 ..........
Piping PB Carbon Steel Atmosphere/ Loss of material External Surfces IVII.l-91 3.3.1.58 B (Galvanized) Weather (Ext) Monitoring Program (B2.1.20) 1 Piping PB Carbon Steel Dry Gas (Int) None None VII.J-22 3.3.1.98 A (Galvanized) Piping Carbon Steel Plant Indoor Air r None None 3.3.1.92 A (Galvanized) (Ext) Piping -P-B Carbon Steel Plant Indoor Air INone None 3.3.1.92 A (Galvanized) (Int) . Piping PB Carbon Steel Raw Water (Int) Loss of material Fire Water Syster Galvanized) (B_2.1.13) . PB Cast Iron Dry Gas*(nt) None None -- VI I.J-22 3.3.1.98 A Piping Cast Iron Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 B (Ext) Monitoring Progr* (B2.1.20) II__ I Palo Verde Nuclear Generating Station Page 3.3-172 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
-, -,F A-;-^~r A) __97irn Drr~fn m (I i-i Table 3.3.2-19 Auxiliary Systems -
riping 'L,as irun r-'IdIlL I11lUOU1/-%I LUb UI IllidLUIldl iVII.I-O s).O. I .;JO 0 (Gray Cast (Ext) Monitoring Program Iron) (B2.1.20) Piping PB Cast Iron Raw Water (Int) Loss of material Selective Leaching of TVII.G-14 13.3.1.85 (Gray Cast Materials (B2.1.17) Iron) PB Cast Iron Raw Water (Int) 1Loss of material Fire Water System VIL.G-24 3.3.1.68 B (Gray Cast (B2.1.13) Lron) Piping PB Copper Alloy Atmosphere/ Loss of material External Surfaces None 'None G (Zinc >15%) Weather (Ext) Monitoring Program (B32.1.20 Plant Indoor Air iNone None VIII.I-2 3.4.1.41 Piping PB Copper Alloy (Zinc >15%) (Ext) Piping PB Copper Alloy Raw Water (Int) 'Loss of material Fire Water System VII.G-12 13.3.1.70 B (132.1.13). (Zinc >15%) Piping Copper Alloy Raw Water (Int) Loss of material Selective Leaching of IVII.G-13 3.3.1.84 PB Piping (Zinc >15%) Materials (B2.1.17) 1 PB Copper Alloy Wetted Gas (Int) Loss of material Selective Leaching of None None DZinc >15%) Materials (B2.1.17) _ _ _ Piping Ductile Iron Buried (Ext) Loss of material Buried Piping and TanksVIl.G-25 3.3 1.19 B Piping nspn on (B,2_n(13.11. PB Ductile Iron Raw Water (Int) ILoss of material Fire Water System VII.G-24 ÷3.3.1.68 (B2.1.13) ___ Piping IPB Fiberglass Buried (Ext) None None iNone !None F, 3 Reinforced Plastic Palo Verde Nuclear Generating Station Page 3.3-173 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-19 Auxiliary Svstems - Summarv of / riuuyibb Reinforced Plastic Piping TPB Stainless Atmosphere/ INone None None None Steel Weather (Ext) Piping PB Stainless Buried (Ext) Loss of material Buried Piping and Tanks VII.G-20 13.3.1.29 Steel Inspection (B2.1.18) Piping PB Stainless Raw Water (Int) Loss of material Fire Water System VII.G-19 3.3.1.69 B Steel (B2.1.13) Cast Iron Plant Indoor Air !Loss of material External Surfaces IVII.1-8 23.3.1.58 B (Gray Cast (Ext) Monitoring Program PB (82.1.20) !Pump Cast Iron Raw Water (Int) Loss of material Selective Leaching of VII.G-14 3.3.1.85 (Gray Cast Materials (B2.1.17) Iron) Pump PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G-24 3.3.1.68 B (Gray Cast (B2.1.13) Iron) Silencer TPB Stainless Diesel Exhaust Cracking Inspection Of Internal VII.1H2-1 3.3.1.06 E Steel (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Silencer PB Stainless Diesel Exhaust Loss of material Inspection Of Internal VII.H2-2 13.3.1.18 Steel (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Palo Verde Nuclear Generating Station Page 3.3-174 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
)iiencer i--b c[tainiess riant inaoor Air None None lV.F-12 3.2.1.53 A
___ __Steel (Ext) Spray Nozzle PB Copper Alloy Plant Indoor Air None None JVIII.I-2 3.4.1.41 A, 2 (Zinc >15%) Lon 3.4.1.41 VIIJ fA,2 Spray Nozzle SP Copper Alloy `(Ext Indoor AirNone (_(Zinc >15%) Plant Indoor Air None Spray Nozzle SP Copper Alloy PlantIndoorAir None None IVIII.I-2 3.4.1.41 A (Zinc >15% Spray Nozzle [SP Copper Alloy EInt) [ None VIIl.l-2 13.4.1.41 A, 2 (Zinc >15%) Plant Indoor Air F None Spray Nozzle SP Copper Alloy _(Int)_ None VIII.I-2 j3.4.1.41 A _(Zinc >15%) Plant Indoor Air None Spray Nozzle 1PB Copper Alloy None VIII.I-2 3.4.1.41 A i _(Zinc >15%) Spray Nozzle SP Stainless Atmosphere/ None None None iNone G Steel Weather (Ext) Spray Nozzle SP Stainless Atmosphere/ None None None None G,4 ___ Steel Weather_(Int) Spray Nozzle SPID Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A I _Steel (Ext) Spray Nozzle SSP Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A, 2 Steel Sprinkler Head PB, SP Copper Alloy Plant Indoor Air i None None VIII.1-2 3.4.1.41 A (Zinc >15%-O- (Ext)__- i Sprinkler Head PB, SP Copper Alloy Raw Water (Int) I Loss of mate rial Fire Water System IVII.G-12 13.3.1.70 B (Zinc >15%) dPB, SP Copper Alloy Raw Water (Int) Loss of mate rial Selective Leaching of !VII.G-13 13.3.1.84 B (Zinc >15%) Materials (B2.1.17) I _ Palo Verde Nuclear Generating Station Page 3.3-175 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-19 Auxiliary Svstems - Summary of/ .ment Evaluation - Fire Protection Svstem (Continued) Cast Iron Plant Indoor Air External Surfaces (Gray Cast (Ext) Monitoring Program Iron) (B2.1.20) Strainer Cast Iron Raw Water (Int) Loss of material Selective Leaching of VII.G-14 3.3.1.85 B (Gray Cast Materials (B2.1.17) Iron) Strainer PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G-24 3.3.1.68 B (Gray Cast Iron) (B21i.13) I Strainer FIL, PB Copper Alloy Dry Gas (Int), 1None None IVII.J-3 3.3.1.98 A Strainer FIL, PB Copper Alloy Plant Indoor Air None None !VIII.1-2 3.4.1.41 A (Ext) Strainer Copper Alloy Raw Water (Int) !Loss of material
+
Fire Water System IVII.G-12 3.3.1.70 B (B2.1.13)__.. Strainer Stainless Raw Water (Ext) Loss of material Fire Water System 1VII.G-19 3.3.1.69 B Steel Tank PPB PB Carbon Steel Atmosphere/ Loss of material External Surfaces IVII.l-9 13.3.1.58 B Weather (Ext) i Monitoring Program B2.1 .2 I_ _ Tank PB Carbon Steel Dry Gas (Int) None None II FJ--2 3.3.1.98 C Tank PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry IVlI.H2-24 3.3.1.20 B (B2.1.14) and One-Time Inspection (2.1. I Tank PB Carbon Steel Plant Indoor Air Loss of material External Surfaces tVII.l-8 3.3.1.58 (Ext) Monitoring Program (B2.1.20) _ Tank Carbon Steel Raw Water (Int) !Loss of material Fire Water System 1VII.G-24 13.3.1.68 D I (B2.1.13)
+i Tubing LPB Copper Alloy IDryGas (Int)t 1None None IVII.J-3 3.3.1.98 JA Palo Verde Nuclear Generating Station Page 3.3-176 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS uopper/Aidioy rianiinaoor/-iur i,4one
~Li, N~one iV I I1."1-4 i 0.1-'l. I .1" 1 Tubing LIS, PB uGopper Alloy Itaw Water (In) LOSS or material Fire Water System 1VII.G-12 3.3.1.70 (B2.1.13) _
Tubing LBS, PB Copper Alloy'Plant Indoor Air None None fVIII.I-2 3.4.1.41 TB (Zinc>15%) (Ent) o gLBS, PB Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G-12 3.3.1.70 I_ (Zinc >15% _ B2_j.1 ,3_, Tubing LBS, PB Copper Alloy Raw Water (Int) Loss of material Selective Leaching of VIlI.G-13 3.3.1.84 __ _ (Zinc >15%) Materials (B2.1.17) i Tubing LBS, PB Stainless Plant Indoor Air None None IVI.J-15 3.3.1.94 A
- Steel . Ext)
Tubing LBS, PB Stainless Raw Water (Int) ILoss of material Fire Water System VIG-19 3.3.1.69 Steel _ .13)__ 1B2. Valve PB Carbon Steel Atmosphere/ Loss of material External Surfaces VII.1-9 3.3.1.58 B Weather (Ext) Monitoring Program (B2.1.20) .. ... Valve PB . . ICarbon Steel Dry Gas (Int) [None None _ _2 3.3.1.98 A Valve PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-24 3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16)___ Valve NSRS, PB -a / Steel Plant Indoor Air (Ext) Loss of material External Surfaces Monitoring Program VII.I-8 3.3.1.58 B1 (32..20)__20) Valve 1 PB I Carbon Steel Plant Indoor Air
'(Int)
Loss of material Inspection Of Internal Surfaces In VII.I-8 13.3.1.58 E,%2 Miscellaneous Piping And Ducting i Components (B2.1.22) _ Palo Verde Nuclear Generating Station Page 3.3-177 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS LOSS OT matenal (132..13 _ Valve NSRS, PB Carbon Stee IWetted Gas (Int) !Loss of material Inspection Of Internal 12VII.G-23 3.3.1.71 B Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) ast Iron __ _ Valve PB ICast Iron Dry Gas (Int) None None iVII.J-22 3.3.1.98 A Valve PB Plant Indoor Air Loss of material External Surfaces 1VII I8 3.3.1.58 B (Ext) Monitoring Program (B2.1.20) Valve PB lCast Iron Atmosphere/ Loss of material External Surfaces VII.l-9 3.3.1.58 B (Gray Cast Weather (Ext) Monitoring Program ________Iron) (B2. 1.20) Valve PB Cast Iron Buried (Ext) Loss of material Selective Leaching of VII.G-15 3.3.1.85 B (Gray Cast Materials (B2.1.17) Iron) Valve PB Cast Iron Buried (Ext) Loss of material Buried Piping and Tanks VII.G-25 3.3.1.19 (Gray Cast Inspection (B2.1.18) Iron! B Valve LBS, PB Cast Iron Plant Indoor Air Loss of material External Surfaces VII.l-8 3.3.1.58 (Gray Cast (Ext) Monitoring Program B2.1.20) Valve PB Cast Iron Plant Indoor Air Loss of material Inspection Of Internal VII.I-8 13.3.1.58 E, 2 (Gray Cast (Int) Surfaces In Iron) Miscellaneous Piping I. And Ducting Components (B2.1.22) I _________________________________ ______________________________ Palo Verde Nuclear Generating Station Page 3.3-178 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-19 Auxiliarv Svstems - Si ent Evaluation - Fire Protection Svstem (Continued) t.ast iron OeIecIIve Leacning OT (Gray Cast Materials (B2.1.17) Iron) Valve LBS, PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G-24 3.3.1.68 B (Gray Cast (B2.1.13) Iron)
+
Valve IPB Copper Alloy Atmosphere/ 'Loss of material External Surfaces None None B Weather (Ext) Monitoring Program (B2.1.20) + +
-4~
Valve JPB Dry Gas (Int) None None VII.J-3 13.3.1.98 A Valve I PB Copper Alloy Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.G-10 13.3.1.32 B (B2.1.14) and One-Time Inspection (B2.1.16) Valve LBS, PB Plant Indoor Air None None VIII.1-2 3.4.1.41 Copper Alloy Valve LBS, PB Raw Water (Int) i Loss of material Fire Water System jVIL.G-12 13.3.1.70 B (B2.1.13)_ _ _ _ Valve Copper Alloy Atmosphere/ Loss of material External Surfaces jNone None (Zinc>15%) Weather (Ext) Monitoring Program (B2.1.20) Valve PB Copper Alloy Dry Gas (Int) None None V/I.J-3 13.3.1.98 A Zinc >15%) _ _ Valve [BS, PB Copper Alloy Plant Indoor Air None None !VIII.l- 2 3.4.1.41 A (Zinc>15% (Ext) Valve LBS, PB Copper Alloy Raw Water (Int) Loss of material Fire Water System IVII.G-12 3.3.1.70 Valve [BS, P (Zinc >15%) 1 (B2.1.13) _ _ _ B Copper Alloy Raw Water (Int) Loss of material Selective Leaching of VII.G-13 13.3.1.84 L4Zinc >15%)_ Materials B2..1 _ Palo Verde Nuclear Generating Station Page 3.3-179 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-19 Auxiliary Systems - Summa of Agin Management Evaluation - Fire Protection System Continued Coi 0tpo lhrt rIntendedaMaterial
- Environment Aging Effect Aging Management NUEG- Table, 1Itemt*i .Notes.. ..
Type ~Functio~n .K Requiring ~ Pro~gram 1801 Vol. Management 2 I]tem~ Valve PB Copper Alloy Wetted Gas (Int) Loss of material Selective Leaching of 'None 1NNone G (Zinc >1 5%) Materials B12.1 17) ___ Valve PB Stainless Atmosphere! Nn None None INone G iSteel Weather (Ext) __________ ____ Valve PB Stainless Raw Water (Int) Loss of material Fire Water System IVII.G-19 .3.3.1.69 B Steel (132.1.13)_ _____________ Notes for Table 3.3.2-19: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent withNUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. F Material not in NUREG-1801 for this component. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 Loss of Preload is.considered to be applicable for all closure bolting. 2 These items are assigned the environment of "Plant Indoor Air (internal)". The items are vented or open to the plant atmosphere so the distinction between internal and external is not relevant for aging purposes. Palo Verde Nuclear Generating Station Page 3.3-180 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 3 Millstone Unit 2 SER Section 3.3A.2.3.2 notes "The NRC's review of the applicant's technical report, current industry research, and operating experience, finds that fiberglass components in air and seawater environments are not exposed to high levels of ultraviolet radiation, high temperatures, or ozone, and therefore has no aging effects that require aging management. Fiberglass reinforced plastic in Atmosphere/ Weather and Soil environments are not exposed to high levels of ultraviolet radiation, high temperatures, or ozone, and therefore do not have aging effects that require aging management". 4 These items are assigned the environment of "Atmosphere/ Weather (internal)". The items are vented or open to the outside atmosphere so the distinction between internal and external is not relevant for aging purposes. Palo Verde Nuclear Generating Station Page 3.3-181 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation -Diesel GeneratorFuel Oil Storage and Transfer Carbon Steel Atmosphere/ LBltILII IL Inte r IL ty ( B2.1 ) VNLIII-1 1143 [13 Weather (Ext) Closure Bolting TPB Carbon Steel Atmosphere/ ILoss of material Bolting Integrity (B2.1.7) VI~- 3.3.1 .4ý3 B
'Weather (Ext)
Closure Bolting PB Carbon Steel jFue OI Ext) Loss of preload Bolting Integr~it~y Bý2.1.7 N!one None__ G, 1 Closure Bolting PB Carbon Steel Fuel Oil (Ext) Fuel Oil Chemistry VII.HI -10 13.3.1.20 D Loss of material (B2.1.14) and One-Time! Inspection (B12.1.16 1 Closure Bolting IPB Carbon Steel Plant Indoor Air i Loss of material Bolting Integrity (B2.1.7) IVII.I-4 13.3.1.43 B (Ext_9__ Closure Bolting Carbon Steel Plant Indoor Air *oss of preload Bolting Integrity (B2.1.7) IVII.l-5 13.3.1.45 B
,(Ext)
Flame Arrestor Aluminum Atmosphere/ Loss of material External Surfaces N ne G Weather (Ext) Monitoring Program
---.-..--- I i ý - Is nB.1.20 .11 ___
Flame Arrestor IPB Aluminum Fuel Oil (Int) I Loss of material Fuel Oil Chemistry VII.H1-1 3.3.1.32 B (B2.1.14) and One-Time Inspection (B2.1.16) low Element PB Stainless Fuel Oil (Int) +Loss of material Fuel Oil Chemistry IVI.H 1-6 3.3.1.3-2 -B Steel (B32.1 .14) and One-Time Inspection (B32.1.16) ____ Flow Element PB Stainless Plant Indoor Air I None None JVII.J-15 3.3.1.94 Steel __Ext) _ Piping LBS, PE3, Carbon Steel Atmosphere/ Loss of material External Surfaces 1V/./1--8 3.3.1.60 B SIA Weather (Ext) Monitoring Program (B2.1.20) ...... __ _ Palo Verde Nuclear Generating Station Page 3.3-182 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation -Diesel GeneratorFuel Oil Storage and Transfer rIpingy
-I I Carbon Steel Buried (Ext)
*Maniagement:
Loss of material Buried Piping and Tanks!VII.H1-9 3.3.1.19 B Inspection_(B2.1.18)_____ Piping PB- Carbon Steel Encased in None None . 1VII.J-21 3.3.1.96 A Concrete (Ext) I Piping PB Carbon Steel Fuel Oil (Ext) 1Loss of material Fuel Oil Chemistry VII.HI-10 3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16)__ Piping ]BLBS, 156B, Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-10 3.3.1.20 B
'SIA (B2.1.14) and One-Time Carbon Steel Plant Indoor Air Loss of material lnspeton (B2.1.16). __i I LBS, PB, Piping External Surfaces VII.l-8 3.3.1.58 B (Ext) Monitoring Program IPB (B2.1.20) ___
Piping Carbon Steel Wetted Gas (Int) I Loss of material Inspection Of Internal VII.H2-21 13.3.1.71 B Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) i _ Pump PB Stainless Fuel Oil (Ext) Loss of material Fuel Oil Chemistry VII.H1-6 33.1.3-2 B Steel (B2.1.14) and One-Time Inspection (B2.1.16) _ Pump 1 PB Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H 1-6 '3.3.1.32 Steel (B2.1.14) and One-Time Inspection (B2.1.16) Strainer FIL, PB, Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.HI-1 3.3.1.20 B SIA (B2.1.14) and One-Time Inspection (B2.1.1 __Pe 3 Palo Verde Nuclear Generating Station z Page 3.3-1 83 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation -Diesel GeneratorFuel Oil Storage and Transfer Pilant inooor Air LOSS OT material Itxternal ,5urraces il~- 331b SIA (Ext) Monitoring Program (B2.1.20) ,__ Strainer FIL Stainless Fuel Oil (Ext) !Loss of material Fuel Oil Chemistry 1VII.H1-6 3.3.1.32 B Steel (B2.1.14) and One-Time Inspection (B2.1.16) __ Strainer FIL Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-6 '3.3.1.32 B1 Steel (B2.1.14) and One-Time
- + +
Inspection (B2.1.16) _
+
Tank 1PB Carbon Steel Buried (Ext) Loss of material Buried Piping and Tanks VII.H1-9 3.3.1.19 D Inspection (B2.1.18) _ C Tank PB Carbon Steel Encased in None None VII.J-21 [3.3.1.96 i ......... Concrete (Exjt) Tank Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-10 i3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16). Tank Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.1-8 13.3.1.58 D (Ext) Monitoring Program (B2.1.20) Tubing LBS Copper Alloy IFuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-3 13.3.1.32 (B2.1.14) and One-Time t Inspection (B2.1.16) 4-
------ +
Tubing LBS Copper Alloy Plant Indoor Air None None VIII.1-2 :3.4.1.41 A _(Ex)__ Tubiin~g Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-6 3.3.1.32 B Steel (B2.1.14) and One-Time Inspection (B2.1.16) Palo Verde Nuclear Generating Station Page 3.3-184 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation -Diesel GeneratorFuel Oil Storage and Transfer R.qvztp.m 1('.nntinii*r1) Tubing Stainless Plant Indoor Air None None \VII.J-15 13.3.1.94 A Steel (Ext) Carbon Steel Fuel Oil (Int) ILoss of material Fuel Oil Chemistry VII.H1-10 3.3.1.20 B Valve PB, SIA (B2.1.14) and One-Time Inspection @2.1.16 _ PB, SIA Carbon Stel lant indoor Air Loss of material External Surfaces L VII.I-8 13.3.1.58 (Ext) Monitoring Program (1B2.1.20) _ Valve s Fuel Oil (Int) ILoss of material Fuel Oil Chemistry IVII.H1-6 331.32 Valve PB Steel (B2.1.14) and One-Time!
.nection. B2..16). i A7 Stainless Steel Plant Indoor Air Ext______
1None
"
None I_ _ _ _
!VII.J-15
_ _ _ 3.3.1.94 Notes for Table 3.3.2-20: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. G Environment not in NUREG-1801 for this component and material. Plant Specific Note: 1 Loss of Preload is considered to be applicable for all closure bolting. Palo Verde Nuclear Generating Station Page 3.3-185 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS, ment Evaluation - Diesel GeneratorSvstem ury Uas tint) ill,)n e ! v/1 - lo.o. I.uO-Plant Indoor Air External Surfaces 1V11.1-8 3.3.1.58 (Ext) Monitoring Program (132.1.20) _ _ _ _ _ Blower HT, PB Cast Iron Closed Cycle Reduction of heat Closed-Cycle Cooling VII.F4-9 3.3.1.52 Cooling Water (Int) transfer Water System (B2.1.10) Blower HT, PB Cast Iron Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-23 13.3.1.47 Cooling er Int) Water Svstem (B2.1.1_ _ _ Blower PB Cast Iron Diesel Exhaust Loss of material Inspection Of Internal VII.H2-2 13.3.1.18 E (Int) Surfaces In Miscellaneous Piping And Ducting Blower Components (B2.1.22) PB ICast Iron Plant Indoor Air Loss of material External Surfaces iVII.H2-3 3.3.1.59 B (Ext) Monitoring Program
.(B2.1. 20).........
Blower HT, PB Ca6st Iron Ventilation Loss of material External Surfaces VII.I-8 3.3.1.58 D Atmosphere (Ext) Monitoring Program (B2.1.20) _ _ Blower PB Cast Iron fWetted Gas (Int) FLoss of material Inspection Of Internal VII.H2-21 13.3.1.71 Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) ,1 Closure Bolting PB Carbon Steel Plant Indoor Air Loss of material B1olting Integrity (B2.1.7) VII.I-4 13.3.1.43 B (Ext).. . .i_ - Palo Verde Nuclear Generating Station Page 3.3-186 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Closure Bolting PB UUl I ,Lt:
%,11I:Ll Fl lCHllL I, II IUUUI r-I I LUt.,* UI 1
,JIUiIU DUILly 11IL IIL kD/. I.() VI1.1-J 3.o. +I.'Ij D (Ext)
Closure Bolting PB Stainless Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7)INone None G Steel (Ext) __ Dryer iSIA Carbon Steel Dry Gas (Int) None None IVII.J-22 3.3.1.98 A Dryer SIA Carbon Steel Plant Indoor Air Loss of material External Surfaces IVII.I-8 B3.31.58 (Ext) Monitoring Program (B2.1.20) i Expansion 1PB Carbon Steel Lubricating Oil ILoss of material Lubricating Oil Analysis lVII.H2-20 3.3.1.14 B Joint (Int)I (B2.1.23) and One-Time Inspection (1B2.11.16) __ _ Expansion Carbon Steel Plant Indoor Air ILoss of material External Surfaces VII.l-8 13.3.1.58 B Joint (Ext) Monitoring Program (1B2.1.20) iExpansion Stainless ]Closed Cycle Loss of material Closed-Cycle Cooling VII.C2-10 i3.3.1.50 B Joint Steel Cooling Water (Int)I Water Svstem (1B2..1.10) ___, Expansion 1PB Stainless Diesel Ex .au.s.tCracking -.....
... Inspection Of Internal IVII.H2-1 13.3.1.06 E Joint Steel (Int) Surfaces In I Miscellaneous Piping And Ducting Components (B2.1.22) _
xpansion Stainless Diesel Exhaust EsLoss of material Inspection Of Internal iVII.H2-2 3.3.1.18 E Joint - Steel (Int) Surfaces In I Miscellaneous Piping __________________ ~1____________ And Ducting Components (B2.1.22) ___ Palo Verde Nuclear Generating Station Page 3.3-187 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
-xpansion LOSS OT m Luoricaung uii /.naiysis Joint Steel (Int) (B2.1.23) and One-Time Inspection (B2.1.16)
Expansion PB Stainless Plant Indoor Air [None None VII.J-15 3.3.1.94 Joint Steel Expansion 5 SP1B tai nless Wetted Gas (Int) Loss of material Inspection Of Internal V.D1-29 3.2.1.08 E Joint Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Filter IFIL, PB, Aluminum Dry Gas (Int) None None VII.J-2 13.3.1.97 A SIA il-ter FIL, PB Aluminum Plant Indoor Air None None V.F-2 13.2.1.50 A Filter SIA Aluminum
ý(xt)
Plant Indoor Air None None VII.J-1 13.3.1.95 A1 Filter FIL, PB Carbon Steel Diesel Exhaust Loss of material Inspection Of Internal VII.H2-2 13.3.1.18 (Int) Surfaces In Miscellaneous Piping And Ducting Components B2.1 .22) Filte~r FiI PE3_R lC 'rhb6nn StAA T-Fiiei flili(Int) Loss of material Fuel Oil Chemistry VII.H2-24 i3.3.1.20 B-(B2.1.14) and One-Time Inspection (B2.1.16L_ Filter FIL, PB Carbon Steel Lubricati g Oil Loss of material Lubricating Oil Analysis VII. H2-20 3.3.1.14 B (Int) ng _t _ __ _ (B2.1.23) and One-Time Inspection @Bý.116 Palo Verde Nuclear Generating Station Page 3.3-188 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Filter FIL, PB Carbon Steel Plant Indoor Air Loss of material t-At*[[Id:l 0U1Jll:Ub IV II.I-O J.,.). I .;.ju (Ext) Monitoring Program (B2-.120) Filter FIL, PB Carbon Steel Wetted Gas (Int) Lss of material Inspection Of Internal TVII.H2-21 3.3.1.71 B Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22?) Flame Arrestor PB Aluminum Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-7 3.3.1.32 D (B2.1.14) and One-Time 1 Inspection (B2.1.16) _ _ _ Flame Arrestor PB Aluminum Plant Indoor Air None None V. F-2 3.2.1.50 C (Ext) I Fuel Oil (Int) Loss of material Fuel Oil Chemistry 'VII.H2-7 13.3.1.32 D Heat PB Aluminum Exchanger (DG (B2.1.14) and One-Time Fuel Oil) _ Inspection (B2.1.16) ....... _ Plant Indoor Air None IV.F-2 3.2.1.50 A Heat PB Aluminum None Exchanger (DG (Ext) Fuel Oil)_ 4. 4 Heat PB Copper Alloy Fuel Oil (Ext) Loss of material Fuel Oil Chemistry 'VII.H2-9 3.3.1.32 B Exchanger (DG (B2.1.14) and One-Time Heat POB Copper Alloy Raw Water (Int) i Loss of material lnsec on ,B2.1.16) __,_ ________ Open-Cycle Cooling VII.H2-11 3.3.1.80 A Exchanger (DG Water System (B2.1.9) Fuel Oil) _ Heat PB Carbon Steel Closed Cycle -- Loss of material Closed-Cycle Cooling VI1.C2-1 13.3.1.48 B Exchanger (DG Cooling Water (Int) Water System (B2.1.10) Jacket Water) __ Palo Verde Nuclear Generating Station Page 3.3-189 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Heat i-ant inaoor Ixternai zsurraces Exchanger (DG (Ext) Monitoring Program Jacket Water) (B2.1.20) Heat HT, PB Copper Alloy Closed Cycle Reduction of heat Closed-Cycle Cooling iVI1.C2-2 3.3.1.52 Exchanger (DG (Zinc >15%) Cooling Water transfer Water System (B2.1.10) Jacket Water) (Ext) Heat HT, PB Copper Alloy Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-8 3.3.1.51 D, 1 Exchanger (DG (Zinc >15%) Cooling Water Water System (B2.1.10) Jacket Water) RExt e Heat HT, PB Copper Alloy Raw Water (Int) Reduction of heat Open-Cycle Cooling Vll.C1-6 +3.3.1.83 A, 1 Exchanger (DG (Zinc >15%) transfer Water System (B2.1.9 Jacket Water) Copper Alloy Heat HT, PB Raw Water (Int) Loss of material Open-Cycle Cooling V11.1-2-11 :3.3.1.80 Exchanger (DG (Zinc >15%) Water System (B2.1.9 Jacket Water) +/- Heat PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-5 13.3.1.21 B Exchanger (DG (Int) (B2.1.23) and One-Time Lube Oil) Inspection (12.1.16) _ _ _ Heat PB Carbon Steel Plant Indoor Air Loss of material External Surfaces IVII.H2-3 13.3.1.59 B Exchanger (DG (Ext) Monitoring Program Lube Oil) (B2.1.20) ____ Heat HT, PB Copper Alloy Lubricating Oil Loss of material Lubricating Oil Analysis [VII.H2-10 13.3.1.26 B, 1 Exchanger (DG (Zinc >15%) (Ext) (B2.1.23) and One-Time i Lube Oil) Inspection (B2.1.16) _ _ _ Heat HT, PB Copper Alloy Lubricating Oil i Reduction of heat Lubricating Oil Analysis IVIII.G-8 t 3 .4 .1.10 B, 1 Exchanger (DG Lube Oil) (Zinc >15%) (Ext) transfer (B2.1.23) and One-Time Inspection (B2.1.16) I _ _ Palo Verde Nuclear Generating Station Page 3.3-190 License Renewal Application
. Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS omcrnt Punhw~infin - flitevl (nntinitiard) tr~tr Open-Cycle Cooling (Zinc >15%) trnn.*f~r Water System (B2.1.9)
Exchanger (DG Lube Oil) Heat HT,PiB- Copper Alloy Raw Water (Int) Loss of material Open-Cycle Cooling r IVII. H2-11 i3.3.1.80 C,1 Water System (B2. 1.9) Exchanger (DG (Zinc >15%) Lube Oil) Heat HT lAluminum Ventilation None None V.F-2 3.2.1.50 C Exchanger (DG Atmosphere (Ext) I Turbo Air Intercooler) Heat PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.H2-3 3.3.1.59 B Exchanger (DG (Ext) Monitoring Program Turbo Air (B2.1.20) Intercooler) 4, I Heat PB Carbon Steel Wetted Gas (Int) Loss of material Inspection Of Internal VII.H2-21 3.3.1.71 D Exchanger (DGI Surfaces In Turbo Air Miscellaneous Piping Intercooler) And Ducting Components (B2.1.22) Heat HT,.PB Copper Alloy Closed Cycle Reduction of heat Closed-Cycle Cooling 'VII. C2-2 3.3.1.52 B Exchanger (DG Cooling Water (Int)itransfer Water System (B2.1.10) Turbo Air Intercooler) Heat HT, PB TCopper Alloy Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-8 3.3.1.51 Cooling Water (Int) Water System (B2.1.10) I Exchanger (DG Turbo Air Intercooler) -- _____ Palo Verde Nuclear Generating Station Page 3.3-191 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS meaw i-eaucuic upen-uycie uooiing Exchanger (DG transfer Water System (B2.1.9) Turbo Air Intercooler)_ Heat HT, PB Copper Alloy Ventilation None None VIII.1-2 3.4.1.41 C Exchanger (DG Atmosphere (Ext) Turbo Air Intercooler) Heat PB Aluminum Lubricating Oil !Loss of material Lubricating Oil Analysis None None G Exchanger (Int) (B2.1.23) and One-Time (Governor Oil Inspection (B2.1.16) Cooler) B..-_
-P ............ .....is Jo oiniin r
- r ........... [*~ n e .........................
....................
.....
o....e...........
....................................
.......... .. . . . ..
Heat Aluminum IPlant Indoor Air INone None V.F-2 3.2.1.50 C Exchanger (Ext) (Governor Oil Cooler) Heat HT, PB Copper Alloy Closed Cycle - Reduction of heat Closed-Cycle Cooling VII.C2-2 3.3.1.52 B Exchanger Cooling Water (Int)ltransfer Water System (B2.1.10) (Governor Oil Cooler) + + Heat HT, PB Copper Alloy Closed Cycle Loss of material Closed-Cycle Cooling VII.C2-4 3.3.1.51 D Exchanger Cooling Water (Int)I Water System (B2.1.10) (Governor Oil Cooler) Heat PB Copper Alloy Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-8 3.3.1.51 B Exchanger Cooling Water (Int)i Water System (B2.1.10) (Governor Oil Palo Verde Nuclear Generating Station Page 3.3-192 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS fl~dL f1IFD LULUI iL,d3LII ly LU00 UlI II ICILI I11 ILULkII; .,OLl
+;
l nil i' A I tllily . i VItI iV i" Exchanger (Ext) (B2.1.23) and One-Time (Governor Oil Inspection (B2.1.16) 13.4.1.10 "!B Cooler). HT, PB Heat Copper Alloy Lubricating Oil Reduction of heat Lubricating Oil Analysis VIII.G-8 Exchanger (Ext) transfer (B2.1.23) and One-TimeI (Governor Oil Inspection (B2.1.16) CoolerL___ Heat PB Copper Alloy Plant Indoor Air None None VIII.I-2 7d3.4.1.41 A Exchanger (Ext) (Governor Oil Cooler) Loss of material Heater PB Carbon Steel Lubricating Oil Lubricating Oil Analysis 2VII.H2-20 3.3.1.14 D (Int) (B2.1.23) and One-Time Loss of material Inspection (B2.1.16) Heater PB Carbon Steel Plant Indoor Air External Surfaces VII.H2-3 .3.1. 59 (Ext) Monitoring Program (1B2.1.20) Heater PB t(Carbon Steel Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-23 3.3.1.47 B (Galvanized) Cooling Water (Int) Water System (B2.1.10) 1 Heater PB Carbon Steel Plant Indoor Air None None 1VII.J-6 3.3.1.92 C Galvanized (Ext)_ Heater PB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.1H2-17 3.3.1.33 ID Steel (Int) (B2.1.23) and One-Time Inspection (B2.1.16) Heater PB Stainless Plant Indoor Air tNone None VII.J-15 1 3.3.1.94
,(,Ext) ......
Steel Insulation INS IInsulation Plant Indoor Air None None None None Ii ____L Mineral Wool (Ext) Palo Verde Nuclear Generating Station Page 3.3-193 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
/\mospnere/ r-xiernai ourraces VI1.1-t Weather (Ext) Monitoring Program (B2.1.20)
Piping LBS, PB, 1Carbon Steel Closed Cycle Loss of material Closed-Cycle Cooling Vll.H2-2:3 3.3.1.47 B SIA Cooling Water*(I nt) Water System (B2.1.10) Piping PB, SIA Carbon Steel Diesel Exhaust Loss of material Inspection Of Internal VII.H2-2 T3.3.1.18 (Int) Surfaces In Miscellaneous Piping And Ducting i Components (B2.1.22) Piping PB, SIA Carbon Steel Dry Gas (Int) None None IVII.J-22 3.3.1.98 JA Piping LBS, PB, Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry !VII.H2-24 3.3.1.20 B SIA (B2.1.14) and One-Time Inspection (B2.1.16) Piping LBS, PB, Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis 3.3.1.14 SIA (Int) (B2.1.23) and One-Time Inspection (B2.1.16) Piping LBS, PB, Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 B SIA (Ext) Monitoring Program (132. 1.20) Piping LBS, PB, Carbon Steel Wetted Gas (Int) Loss of material Inspection Of Internal VII.H2-21 3.3.1.71 B SIA Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Piping PB -jStainless Closed Cycle Loss of material Closed-Cycle Cooling VII.C2-10 3.3.1.50 Stee Cooling W ater (/nt)l . ....... Water System (B2.1.10) Palo Verde Nuclear Generating Station Page 3.3-194 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS SIA Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Stainless Diesel Exhaust Cracking Inspection Of Internal IVII.H2-1 3.3.1.06 Piping Steel i(Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.t.22) Piping PB Stainless Diesel Exhaust Loss of material Inspection Of Internal VII. H2-2 3.3.1.18 E Steel (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1 .22) Piping PB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis IVII.H2-17 13.3.1.33 B Steel (Int) (B2.1.23) and One-Time Inspection (B2.1.16) .9 Piping LBS, PB, Stainless Plant Indoor Air iNone None IVII.J-15 13.3.1.94 A SIA Steel (Ext ___
,A,-
SIA Stainless Plant Indoor Air None None 1VII.J-15 13.3.1.94-Steel (Int) i Piping PB Stainless Secondary Water Loss )f material Water Chemistry jVIII.E-29 13.4.1.16 A Steel (Int) (B2.1.2) and One-Time I Inspection (B2.1.16) Piping LBS, PB Stainless Wetted Gas (Int) Loss of material Inspection Of Internal V.D1-29 3.2.1.08 E Steel Surfaces In Miscellaneous Piping And Ducting
ýq*ýiets_@2_.1.22)_
Palo Verde Nuclear Generating Station Page 3.3-195 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ILOSS Or materiai i-uei ui L;nemistry (B2.1.14) and One-Time Inspection (B2.1.16) Pump PB Carbon Steel Lubricating Oil iLoss of material Lubricating Oil Analysis VII.1H2-20 13.3.1.14 B (Int) (B2.1.23) and One-Time Inspection (B2.1.16) __,,,- __ _ Pump PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 3.3.1.58 B (Ext) Monitoring Program (B2.1.20)_ _ Pump Cast Iron Closed Cycle Loss of material Closed-Cycle Cooling VII.H2-23 3.3.1.47 1B
+
Cooling Water (Int) Water System (B2.1.10)'4 I 4 4 4 - Pump PB Cast Iron Plant Indoor Air Loss of material External Surfaces gVII.I-8 3.3.1.58 B (Ext) Monitoring Program (12.1.20) ! Pump PB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-17 ,3.3.1.33 Steel (Int) (B2.1.23) and One-Time Inspection (2.1.16) Pump PB Stainless Plant Indoor Air None None VII.J-15 13.3.1.94 A Steel (Ext) Sight Gauge LBS, Carbon Steel P1 i lotluIntý I nee ,,f mntariol Fuel Oil Chemistry VIIl.H2-24 13.3.1.20 B NSRS (B2.11.14) and One-Time Inspection (B2.1.16) i__ Sight Gauge LBS, Carbon Steel Plant Indoor Air Loss of material External Surfaces 1vll'l'8i I 3.3.1.58 NSRS (Ext) Monitoring Program I (132.1.20) _ _ _ _ _ _ _ _ Sight Gauge IPB iGlass Closed Cycle ,None None IVII.J-13 3.3.1.93 A Cooling Water Sight Gauge jLBS, IGlass Fuel Oil (Int) None None iVIJ-9 3.3.1.93 NSRS Palo Verde Nuclear Generating Station Page 3.3-196. License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS igni~uauge Lb5, uiass ianam inooor Air 'None None Vii.J-0 i..i.i.5 A ____ NSRS, PB (Ext) Sight Gauge PB Stainless Closed Cycle ILoss of material Closed-Cycle Cooling 1VII.C2-10 13.3.1.50 B Steel Cooling Water (Int)l Water System (B2.1.10) None None VII.J-15 13.3.1.94 Sight Gauge PB LBS Stainless Steel Carbon Steel Plant Indoor Air E(Ex )........ Atmosphere/ FLoss of material IExternal Surfaces VII I-9 13.3.1.58
-- -- - -- -- -
Strainer Weather (Ext) jMonitoring Program FulOl(n) Loss of mtril - (B2.1.20) OilChemistry F......el..... - __ VII.H2-24 13.3.1.20_ Stfraiiner FIL, LBS, Carbon Steel PB (B2.1.14) and One-Time; Inspection (B2.1.16) _ Strainer FIL, PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis IVII.H2-20 !3.3.1.14 B (Int) (B2.1.23) and One-Time Inspection (12.1.16) Strainer FIL, PB Carbon Steel Plant Indoor Air ILoss of material External Surfaces 'VII.1-8 3.3.1.58 B (Ext) Monitoring Program (B2.1.20) Strainer FIL, PB Stainless Lubricating Oil 'Loss of material 3.3.1.33 B Lubricatingand Analysis VII.H-2-17 OilOne-Time Steel (Int) (B2.1.23) NnecVion(1(32.-*1) 1 Stainless Plant Indoor Air None No4n~e_ VII.J-15 f3 . 3 . 1 194 A Strainer FIL, PB Steel (ExEL_____ ______
!Loss of material B Tank PB Carbon Steel Fuel Oil (Int) Fuel Oil Chemistry TVII.H2-24 ,F3.3.1.20
((B2.1.14)and One-Time Inspection( B2.1.1ý) I Tank PB -C;-arbon Steel Plant Indoor Air ILoss of material External Surfaces IVII.I-8 3.3.1.58 (Ext) Monitoring Program Palo Verde Nuclear Generating Station Page 3.3-197 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
.1:.1 2-21 r'._ .. Z i anK L;ast iron LUDrl oss OT mater LuDricating u11 Anaiysis I-IZ-ZU JL1.6.3.
(Int) (B2.1.23) and One-Time Inspection (B2.1.16) Tank PB Cast Iron 7 Pla-nt4 n-door A .i.r. Loss, of ma-terial External Surfaces VII.l-8 13.3.1.58 B (Ext) Monitoring Program
+
(B2.1.20) Tubing PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry _VII.H2-24 3.3.1.20
* "]
oE*.I Il "V_1 - II II11 Inspection B2.1.16L__ Tubing 1PB Carbon Steel Plant Indoor Air Loss of material External Surfaces 1VI.1-8 3.3.1.58 (Ext) Monitoring Program (132.1.20) Tubing PB Copper Alloy Dry Gas (Int) None None VII.J-3 3.3.1.98 A Tubing PB Copper Alloy Plant Indoor Air None None VIII.I-2 13.4.1.41 A2_ (Ext Tubing ]LBS, PB, Stainless Closed Cycle Loss of material Closed-Cycle Cooling VII.C2-10 13.3.1.50 SIA Steel Cooling Water (Int) Water System (B2.1.10) ___ Tubing PB, SIA Stainless Dry Gas (Int) None None iVII.J-18 i3.3.1.98 A Steel Tubing LBS, PB, Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-16 3.3.1.32 B SIA Steel (B2.1.14) and One-Time - Inspection (132.116) Tubing LBS, PB, Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2- 17 3.3.1.33 1SIA Steel (Int) (B2.1.23) and One-Time I Inspection (g2.1.16). - Tubing LBS, PB, Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 SIA Steel Ext i. .. . Palo Verde Nuclear Generating Station Page 3.3-198 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS vaive LIO, IN II +V 1I,0 ý,O.Q. 1.V1 r%- NSRS, PB, SIA Valve LBS, Aluminum Plant Indoor Air None None V. F-2 3.2. 50 A 1NSRS, (Ext) PB, SIA Valve LBS, SIA Carbon Steel Atmosphere/ Loss of material External Surfaces iVIl.l-9 3.31.58 B Weather (Ext) Monitoring Program SB2.1.20) _ Valve PB ]Carbon Steel Closed Cycle Loss of material lClosed-Cycle Cooling :VII.H2-23 13.3.1.47 B lCooling Water (Int): Water System (B2.1.10) _ Valve PB Carbon Steel Diesel Exhaust Loss of material Inspection Of Internal iVII.H2-2 3.3.1.18 E (Int) Surfaces In Miscellaneous Piping I And Ducting Components (B2.1.22) __ _ Vale PB, SIA Carbon Steel Dry Gas (Int) None None MVI.J-22 13.3.1.98 A Valve LBS, PB, Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry IVII.H2-24 3.3.1.20 B SIA (B2.1.14) and One-Time Inspection (12.1.16) Valve PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-20 13.3.1.14 B (Int) (B2.1.23) and One-Time I Inspection B .2.1..1 _.. Valve LBS, PB, Carbon Steel Plant Indoor Air FLoss of material External Surfaces TVII.I-8 3.3.1.58 B SIA [(Ext) Monitoring Program I j(B2.1.20) _ Palo Verde Nuclear Generating Station Page 3.3-199 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Valve LBS, PB Inspection Of Internal Surfaces In Miscellaneous Piping And Ducting None Components (B2.1.22) Valve PB Cast Iron Dry Gas (Int) None VIlI.J-22 13.3.1.98 A Valve PB Cast Iron Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-24 13.3.1.20 B (B2.1.14) and One-Time Inspection (12.1.16) Valve PB Cast Iron Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-20 i3.3.1.14 B (Int) :(B2.1.23) and One-Time Ispection B2.1.16 Plant Indoor A Valve Cast Iron ir Loss of material External Surfaces VII.l-8 3.3.1.58 B (Ext) Monitoring Program N(32.1.20 Valve ]PB, SIA Co per Alloy Dry Gas (nt)_ None None IVII.J-3 33.1.98 A Valve 11PB, SIA Copper Alloy Plant Indoor Air None None 1VIII.1-2 3.4.1.41 A (Ext) _ _ Valve PB rCopper Alloy Wetted Gas (Int) Loss of material Inspection Of Internal ýVILG-9 3.3,1.28 E Surfaces In Miscellaneous Piping And Ducting _Components (B2.1.22.) _ Valve LBS Copper Alloy Plant Indoor Air None None VIII.l-2 134141 A (Zinc >15%) (Ext) _"_ Valve Copper Alloy Wetted Gas (Int) 1Loss of material Selective Leaching of None None G (Zinc >15%) _ _ __ _Materials (B2.1.17) i Valve [PB Nickel Alloys Dry Gas (Int) None None INone None G Palo Verde Nuclear Generating Station Page 3.3-200 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Plant Indoor Air 1None None iVlI.J-14 13.3.1.94 A Ext _ _ _ _ _ _ _ Valve PB Stainless Closed Cycle Loss of material Closed-Cycle Cooling IVII.C2-10 3.3.1.50 'B Steel Coolin Water (Int)l _ Water Sy sem B12. 1.10)____ ____ ___ Valve PB Stainless De.iner lized Loss of material Water Chemistry VIII.E-29 3.4.116 IA Steel Water (Int) (B2.1.2) and One-Time Inspectioný B2.1.16) ____ _____ ___ Valve PB, SIA Stainless Dry Gas (Int) None None -VII.J-18 13.3.1.98 A Steel Valve PB Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-16 13.3.1.32 B Steel (B2.1.14) and One-Time Inspection (B2.1.16) ! Valve PB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-17 13.3.1.33 B Steel (Int) (B2.1.23)and One-Time Inspection B2.1.16) Valve JPB, SIA Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A Steel (Ext) Valve PB Secondary Water Loss of material Water Chemistry VIII.E-29 3.4.1.16 A Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Valve S§tainIe Mss Wetted Gas (Int) i Loss of material Inspection Of Internal V..1-2t9 T3.2.1.08 Steel Surfaces In ____P Miscellaneous Piping And Ducting Components (12.1.22) Palo Verde Nuclear Generating Station Page 3.3-201 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-21: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Note: 1 The DG Jacket Water Cooler and DG Lube Oil Cooler heat exchanger tubes are fabricated of Admiralty Brass (nominal Cu-71 %, Zn-28%, Sn-1%). EPRI Rpt 1010639 "Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools" Rev. 4, Appendices A, B and C state that the addition of tin to brass effectively inhibits dezincification and significantly reduces the susceptibility of the material to selective leaching. This is consistent with NUREG 1801, IX.C which states that selective leaching is not a consideration for inhibited brass. Therefore, loss of material due to selective leaching has not been selected as an aging effect for Admiralty Brass heat exchanger tubes in Closed-Cycle Cooling Water, Raw Water and Lubricating Oil environments. Palo Verde Nuclear Generating Station Page 3.3-202 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ouusure DunlIrI .,;dIUUII ,LUUI r-idllL IIIUUUI M11 13.3.1.43 _Ext i - Closure Bolting LBS Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) VII.l-5 13.3.1.45 B _ Plant t) In(Ex o iNone Copper Alloy JPlant Indoor Air Loss of preload IBolting Integrity (B2.1.7) SNone G Closure BoltingfLBS (Ext) IClosure Bolting IPB Stainless [Plant Indoor Air Loss of preload Bolting Integrity (B2. 1.7) None -Non et-- G Steel (Ext Flow Indicator TLBS, PB Cast Iron PIant Indoor Air Loss of material External Surfaces iVII.l1-8 3.3.1.58 B 1(Ext) Monitoring Program _(B2.1.20) _ Flow Indicator ILBS ICast Iron Potable Water (Int)y Loss of material Inspection Of Internal None iNone Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Flow Indicator PB Cast Iron Raw Water (Int) Loss of material Fire Water System :VII.G-24 3.3.1.68 B (B2.1.13) Palo Verde Nuclear Generating Station Page 3.3-203 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS L;aroon tsteei viant Indoor Air LOSS OT materiai txternai burraces (Ext) Monitoring Program
+ +
(B2.1.20) Piping LBS Carbon Steel Potable Water t Loss of material Inspection Of Internal None 1None G Surfaces In Miscellaneous Piping And Ducting Piping Com!poneýnts Bq2.1 .22) PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.GI-8 i3.3.1.58 with (Ext) Monitoring Program Elastomer (B2.1.20) Piping Lining ('VII.G-24 PB Carbon Steel Raw Water (Int) Loss of material Fire Water System 3.3.1.68 B with (B2.1.13) Elastomer Piping Lining LBS Copper Alloy Plant Indoor Air None None VIII.1-2 3.4.1.41 A Piping LBS Copper Alloy Potable Water (Int)l Loss of material Inspection Of Internal {None None Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Piping PB Polyethylene Buried (Ext) None........ . ...None None INone __None 1None F PB Polyethylene Plant Indoor Air None None F fExt) ___ Piping PB Polyethylene Raw Water (Int) Lone None None Nlone L_ Palo Verde Nuclear Generating Station Page 3.3-204 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-22 Coimponent Inti
~Type Fui Piping PB Stainless Plant Indoor Air None IV I 1.1j- 10 0.1).
Steel (Ext* PipingP Stainless Raw Water (Int) Loss of material Fire
-Water System VII.G-19 3.3.1.69 B 4
Steel
+/-
(B2.1.13) _ __ Pump PB Cast Iron Raw Water (Ext) loss of material 4Fire Water System ]VII.G-24 3.3.1.68 (132.1.13)__ _ _ _ _ _ _ _ _ Pump IPB Cast Iron Raw Water (Int) ILoss of material Fire Water System IVII.G-24 3.3.1.68 (132.1.13)__ _ _ _ _ _ _ _ _ 4 4- 4- 4 Pump LBS Copper Alloy Plant Indoor Air None None ]VI1.1-2 3.4.1.41 A (Ext) ,__ Pump LBS Copper Alloy Potable Water (Int) Loss of material Inspection Of Internal None 'None G Surfaces In Miscellaneous Piping And Ducting Components (12.1.22) i Strainer LBS 1Carbon Steel Plant Indoor Air TLoss of material External Surfaces VII.I-8 3.3.1.58 (Ext) Monitoring Program 4 (B2.1.20) 4 4-Strainer LBS Carbon Steel Potable Water (Int)I Lossof material Inspection Of Internal None None G Surfaces In Miscellaneous Piping And Ducting Components (132.1.22) 4 + Strainer LBS Copper Alloy Plant Indoor Air None None VIII.1-2 3.4.1.41 A (Ext) Palo Verde Nuclear Generating Station Page 3.3-205 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ement Evaluation - Domestic Water S] Aging Man~agemient~ NUREG-Program~ 1801 Vol. I2 Ite m Inspection Of Internal iNone Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22 Tank LBS Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 (Ext) Monitoring Program (132.1.20) Tank LBS Carbon Steel Potable Water (Int)I Loss of material Inspection Of Internal None Surfaces In Miscellaneous Piping And Ducting I Comp onents (1B2.1.22) Valve Cast Iron Buried (Ext) Loss of material Buried Piping and Tanks.VIll.G-25 Inspection (B2.1.18) Valve Cast Iron Plant Indoor Air Loss of material External Surfaces VII.1-8 (Ext) Monitoring Program 1(B2.1.20) PB Valve Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G-24 (B2.1.13) Valve LBS Copper Alloy Atmosphere/ Loss of material External Surfaces None Weather (Ext) Monitoring Program B2.1.20) Valve LBS Copper Alloy Plant Indoor Air None None VIII.I-2 (Ext) Palo Verde Nuclear Generating Station Page 3.3-206 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Surfaces In Miscellaneous Piping And Ducting, Componentsl(B-1.22) Valve LBS, PB Stainless Plant Indoor Air None None VI 1.J-15 3.3.1.94 ISteel (Ext) _ Valve LBS tStainless Potable Water (lnt)I Loss of material Inspection Of Internal None None
~Steel Surfaces In Miscellaneous Piping And Ducting .
Valve V. ............ ................ . . IB
. .......... . ...
Stainless
.Steel Raw Water (Int) Loss of material Components (B2.1.22)
I..........
----
Fire Water System (132.1.13) m I........... ...I.v.i.i. ..................
.......
3.3.1.69 B Notes for Table 3.3.2-22: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. F Material not in NUREG-1801 for this component. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.3-207 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS uiosure b0olng jLbb, b/A jýLarmon bteei Weather ____ ___ Aimospnere/ Ext LOSS or _ preioaa Closure Bolting LBS, SIA Carbon Steel Atmosphere/ Loss of material Bolting Integrity (B2.1.7) iVIl.lI-1 3.3.1.43 B _ _ _ Weather (Ext) Closure Bolting LBS, PB, Carbon Steel Plant Indoor Air ,Loss of material Bolting Integrity (B2.1.7) VII.1-4 3.3.1.43 B BSIA C r o (Ext ........... L Cl-osure Bolti-ng ýL-B-S", ,PB, "Carbon Steel Plant Indoor Air !Loss of preload Bolting Integrity (B2.1.7) VII I-5 3.3.1.45 B Closure Bolting LBS, SIA Stainless (Ext) Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) None None G, 1 Steel (Ext) Piping LBS, SIA Stainless Atmosphere/ None None !None None G, 2 Steel Weather (Ext) Piping LBS, PB, Stainless Demineralized Loss of material Water Chemistry VIII.E-29 3.4.1.16 A SIA Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Piping *3.3.1 .94 K-LB6.S, PBS,-SB tainless Plant IndoorAir jNone None JVII.J-15 SIA Steel (Ext)__ _ _ _ _ _ Valve LBS Stainless Atmosphere/ None None None None G, 2 Steel Weather (Ext) Valve LBS, PB, Stainless Demineralized Loss of material Water Chemistry VIII.E-29 3.4.1.16 A _SIA !Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Valve LBS, PB, IStainless Plant Indoor Air None None ;VII.J-15 3.3.1.94 A _SIA I Steel (Ext) Palo Verde Nuclear Generating Station Page 3.3-208 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-23: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 The PVNGS plant outdoor environment is not subject to aggressive contaminants or saline environment. Stainless steel does not experience any appreciable aging effects in this environment. Palo Verde Nuclear Generating Station Page 3.3-209 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 2 ItemonWI7 uiosure onlting 1-1::: uarDon ,ieei /Amospnere/ LOSS OT preioaa Bolting Integrity (B2.1.7) None None Weather (Ext)____ Closure Bolting PB Carbon Steel Atmosphere/ Loss of material Bolting Integrity (B2.1.7) VII.l-1 3.3.1.43 B Weather (Ext) _ Filter 1FIL, PB Carbon Steel Atmosphere/ I Loss of material External Surfaces IVII.H1-8 3.3.1.60 B Weather (Ext) Monitoring Program I (B2.1.20) 1 4
-4 4 Filter FIL, PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry 1VII.HI-IO 3.3.1.20 i
B (B2.1.14) and One-Time Inspection _(B2,.1.16)_........... Flame Arrestor PB Aluminum Atmosphere/ Loss of material External Surfaces 1None None G Weather (Ext) Monitoring Program (B2.1.20) i Flame Arrestor PB Aluminum Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-1 13.3.1.32 D (B2.1.14) and One-Time Inspection 1.16_ Flexible Hoses Stainless Atmosphere/ i None None None None G Steel Weather (Ext) I Flexible Hoses Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-6 13.3.1.32 B PB Steel (B2.1.14) and One-Time Inspection (B2.1 .16) Flow Indicator PB Cast Iron Atmosphere/ Loss of material External Surfaces VII.H1-8 13.3.1.60 B,_2 (Gray Cast Weather (Ext) Monitoring Program Iron) (B2.1.20) ___ Palo Verde Nuclear Generating Station Page 3.3-210 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Cast Iron i-uei uiI unemistry (Gray Cast (B2.1.14) and One-Time Iron) Inspection (B2.1.16) Piping PB Carbon Steel Atmosphere/ Loss of material External Surfaces VII.H1-8 3.3.1.60 B Weather (Ext) Monitoring Program (B2.1.20)
*1'
- I Piping tPB ICarbon Steel {Buried (Ext) Los,, Buried Piping and Tanks VII.1H 1-9 3.3.1.19 B Inspection (B2.1.18)
Piping IPB Carbon Steel Encased in None None VII.J-21 3.3.1.96 A Concrete (ExtL Piping IPB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-10 3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16)
-Loss of material External Surfaces B Pump {PB Carbon Steel Atmosphere/ VII.1H 1-8 3.3.1.60 Weather (Ext) Monitoring Program (B2.1.20)
Pump PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.1HI-10 3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16) Sight Gauge PB Copper Alloy Atmosphere/ .Loss of material External Surfaces None None G Weather (Ext) Monitoring Program (B2.1.20 Sight Gauge PB Copper AlloyrFuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-3 13.3.1.32 B (B2.1.14) and One-Time
-------- -...............
I -- -- Inspection (B2.1.16) PB Glass Atmosphere/ None .................................
....... ....... ...................
None e........ ................
... .............
..........
.......
.......
................................
No Nonee .............
................
None ....................... ne.. ............. G Fueather (Ext) SightGauge _j.ss _ il
]e None 1None VIJ _:3'_' A_
Palo Verde Nuclear Generating Station Page 3.3-211 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Atmospnere/ LOSS or materiai -xiernai ,urraces Weather (Ext) Monitoring Program (B2.1.20) S§t rain er PB Copper Alloy Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-3 3.3.1.32 B (B2.1.14) and One-Time Inspection (B2.1.16) i j Tank PB Carbon Steel Atmosphere/ Loss of material External Surfaces VII.H1-8 3.3.1.60 D Weather (Ext) Monitoring Program (B2.1.20) it i Tank PB arbon Steel Fuel Oil (Int) !Loss of material Fuel Oil Chemistry VII.1H1-10 3.3.1.20 B (B2.1.14) and One-Time Inspection (B2.1.16) Valve PB, PR Aluminum Atmosphere/ !Loss of material External Surfaces None None Weather (Ext) Monitoring Program (B2.1.20) Valve PB, PR Aluminum Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-1 3.3.1.32 B (B2.1.14) and One-Time Inspection (2.1.16 Valve Carbon Steel Atmosphere/ Loss of material External Surfaces VII.H1-8 3.3. 1.60 B Weather (Ext) Monitoring Program
@B2.1.20 _ _
Valve PB Carbon Steel IFuel Oil (Int) Loss of material Fuel Oil Chemistry V\II.HI-1013.3.1.20 (B2.1.14) and One-Time Inspection (B2.1.16) Valve PB Copper Alloy Atmosphere/ Loss of material External Surfaces None None G Weather (Ext) Monitoring Program (B2 .1.20)ý Palo Verde Nuclear Generating Station Page 3.3-212 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS om5ant Fuhntn - WPF Ptup! jctzhm (frnntir IFuel Oil Chemistry i(B2.1.14) and One-Time Inspection (B2.1.16) Vent PB, PR lAluminum Atmosphere/ ILoss of material External Surfaces None 1None (Emergency) Weather (Ext) Monitoring Program (1B2.1.20) Vent PB, PR lAluminum IFuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H1-1 133.13.32 lB (Emergency) (B2.1.14) and One-Time Inspctin (2.1 .16) Vent PB, PR Carbon Steel Atmosphere! .Loss of material External Surfaces VII.1-9 03.3.1.58 (Emergency) Weather (Ext) Monitoring Program (B2.1.20) Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry V11.1-1-10 13.3.1.20 Vent PB, PR (Emergency) (B2.1.14) and One-Time Inspection (B2.1.16) Notes for Table 3.3.2-24 Standard Notes: A. Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 The Mechanical Tools (EPRI Report 1010639), Revision 4, Appendix E, "External Surfaces", Section 4.4 states: "Cast iron is included with "steel" in NUREG-1801 for environments addressed by this tool, except where gray cast iron is identified in "soil" environments". Palo Verde Nuclear Generating Station Page 3.3-213 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS. Iuarmon (Ext) Closure Bolting SFIA Carbon Steel Plant Indoor Air !Loss of preload Bolting Integrity (B2.1.7) 1VII.I-5 13.3.1.45 (Ext) 4,+
--
Filter PB Carbon Steel None _V_/.J-22 13.3.1.98 A Filter Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 13.3.1.58 B PB (Ext) Monitoring Program.. Flexible Hoses . 2-..........
............
.............
.............................
.......................
-.........................
I PB Stainless Dry Gas (Int) None None A
ýVII.J-18 i 3.3.1-98 Flexible Hoses Steel Stainless Plant Indoor Air rNone None 1VIU.-15 3.3.1.94 Orifice Steel (Ext)
SIA Stainless Dry Gas (Int) None None ;VII.J-18 3.3.1.98 Orifice Steel Stainless Plant Indoor Air None None MIV.J:15 3.3.1.94
+ +
Steel (Ext) + Pipi ng PB, SIA ICarbon Steel DrG nt) . None None VlI.J-22 13.3.1.98 A
!VII.I-8 PB, SIA Carbon Steel Plant Indoor Air iLoss of material External Surfaces Ii 13.3.1.58 (Ext) Monitoring Program [
Piping (132.1.20) PB Stainless Dry Gas (Int) None None 3.3.1.98W Steel 4 Piping Stainless Plant Indoor Air None None IVII.J-15 + 3.3.1.94 A Steel (Ext) _ IVII.J-12 None Valve PB, SIA ICarbon Steel Dry Gas (Int) INon T3.3.1.98 Valve PB, SIA Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 B (Ext) Monitoring Program i (B2.1.20) Palo Verde Nuclear Generating Station Page 3.3-214 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ment Evaluation - Service Gases (N2 and H2) vaive - Iz *ainiess ury L.as (inf) i one Steel Ion Valve PB l Stainless Plant Indoor Air None Steel (Ext) Notes for Table 3.3.2-25: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.3-215 License Renewal Application
Section.3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
,ation- Gaseous Radwaste Svstem Bolting Integrity (B2.1.7) IVII.l-4 13.3.1.43 B
.SIA LBP CaoSe (Ext)
Closure Bolting ILBS, PB, 1 Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) IVIL-5 13.3.1.45 B SIA (Ext) iSIA 4 Piping LBS, PB, Stainless Plant Indoor Air None None VII.J-15 13.3.1.94 A Steel (Axt _ ._- Piping LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal 1VII.C1-15 3.3.1.79 E, 1 Steel Surfaces In Miscellaneous Piping And Ducting Components (B12.1.22)____ rnD cIA Stainless Wetted Gas (Int) Loss of material Inspection Of Internal 1VII.F2-1 3.3.1.27 E Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) _ None VII.J-8 3.3.1.93 A Sight Gauge LBS Plant Indoor Air None Sight Gauge LBS None VII.J-11 13.3.1.93 A Glass Raw Water (Int) None Sight Gauge ILBS Stainless Plant Indoor Air None None VII.J-15 13.3.1.94 A (Ext) Steel Sight Gauge [LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.C1-15 3.3.1.79 E, 1 Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Tubing LBS Stainless Plant Indoor Air None o None VII.J-15 13.3.1.94 A Steel Tubing LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.C1-15 3.3.1.79 E, 1 Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Palo Verde Nuclear Generating Station Page 3.3-216 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS manii Punhinf~inn - r'eOni PnrhA1Jq.,tP ql/-CdtPM (CnntintilPH) OLdll IIZ-ý r-IlIIL IIIUUUI None VII.J-15
-4 4 Steel 4' (Ext)
Valve LBS Stainless Raw Water (Int) ILoss of material Inspection Of Internal VII.C1-15 3.3.1.79 E, 1 Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) _ ValveP Stainless Wetted Gas (Int) !Loss of material Inspection Of Internal IVII.F2-1 13.3.1.27 E Steel Surfaces In Miscellaneous i Piping And Ducting
~
______ _ ~
~ ~ ~ -_ ~
_ _ __~ __ _ _ _~ Components
~ .. ~ (B2.1.22)
.. ...... _ _ __ _ _-
Notes for Table 3.3.2-26: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. Plant Specific Note: 1 The internal component environment of the gaseous radwaste system where gas that has condensed to water may be found is evaluated as a raw water environment. Loss of material on internal component surfaces exposed to the solid radwaste internal environment will be managed by Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.11.22) instead of Open-Cycle Cooling Water System program (B2.1.9). Palo Verde Nuclear Generating Station Page 3.3-217 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS boraiea vvaier 1LOSS OT preioaa V.uz-o IO..I Leakaqe (Ext) Closure Bolting ILBS Carbon Steel Borated Water Loss of material Boric Acid Corrosion VII.1-10 3.3.1.89 LeakaQe (Ext) .............. (B2.1.4) Closure Bolting LBS Stainless Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) None 1None G, 1 Steel Orifice LBS Stainless Atmosphere/ None None None 'None G Steel I Weather (Ext) 4. .. I". ....... 4...... .....
..
Orifice LBS Stainless Plant Indoor Air None None VIIJ-15 13.3.1.94 Orifice Steel (Ext) LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal iVII.C1-15 13.3.1.79 E2 Steel Surfaces In Miscellaneous Piping And Ducting 4 4 + 4- 4 Components (B2.1.22)
. 4-Piping LBS Carbon Steel Borated Water Loss of material Boric Acid Corrosion VIIl.-10 13.3.1.89 A Piping Leakage (Ext) (B2.1.4)
LBS Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal ]VI1.C1-19 3ý.3.1.76 Surfaces In Miscellaneous Piping And Ducting Piping Components (B2.1.22) 4 4- 4- 4-.- 4 . - _________ ___________ LBS Stainless Atmosphere/ None None None None G 4 Steel + Weather (Ext)
-~---'--- 4- I 4 Piping LBS, SIA Stainless Borated Water None None VII.J-16 3.3.1.99 A Steel Leakaae (Ext)
Palo Verde Nuclear Generating Station Page 3.3-218 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Stainless Demineralized water uhemnistry jVlll.l=-zv .5.4. 1.lb3 Steel Water (Int) (B2.1.2) and One-Time I Inspection (B2.1.16) I _ None None IVII.J-17 3.3.1.96 A Piping Stainless Encased in Steel Concrete (Ext) Piping LBS, PB, Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A SIA Steel (Ext) 5 VII.C1-15 13.3.1.79 E, 2 Piping LBS, PB, Stainless Raw Water (Int) Loss of material Inspection Of Internal SIA Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) , _ _ _ Piping LBS, SIA Stainless Treated Borated Loss of material Water Chemistry 'VII.El-17 3.3.1.91 A Steel Water (Int) (B2.1.2) I Sight Gauge LBS Cast Iron Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 B (Ext) Monitoring Program Sight Gauge jLBS Raw Water (Int) ,Loss of material Inspection Of Internal V1C-9 3.3. 1.T6 E, 2 Cast Iron Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) IRaw Sight Gauge LBS Glass Plant Indoor Air None None tVIl.J-8 13.3.1.93 (Ext) Sight Gauge LBS
-~
s........... Glass .. ........... Water (Int)
...........
Atmosphs. erep 'None None "N o-n
.... iIVlI.J-11
....
o e........ t3.3.1.93
..........
.....
.. .............................................. n__o A
...................
Strainer Stainless .None None None None G Steel LWeather (Ext) Palo Verde Nuclear Generating Station Page 3.3-219 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
.m (Continued) tern I Notes itainiess uemineraiizea vvater unemistry VIll.--/l2 !,, 1.. 1a A Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) _ _ _
Strainer LBS Stainless Plant Indoor Air None None IVII.J-15 1:3.3.1.94 A I i Steel fubing LBS§ Stainless Demineralized Loss of material Water Chemistry VIII.E-29 3.4.1.16 A Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) __ Tubing LBS, PB Stainless Plant Indoor Air None None VII.J-15 ]3.3.1.94 A Steel SExt e Tubing LBS, PB Stainless Raw Water (Int-) Loss of material Inspection Of Internal V3.3.1.79 Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.11.22) Valve LBS Carbon Steel Borated Water Loss of material Boric Acid Corrosion IVII.I-10 13.3.1.89 Al Leakage (Ext) (B2.1 .4) Valve LBS Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VII.C1-19 3.3.1.76 E,2 Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Valve Stainless Atmosphere/ None None None iNone IG Steel Weather (Ext) Valve Stainless Borated Water None None VII.J 3.3.1.99 A Steel Leakage (Ext) Valve LBS Stainless Demineralized Loss of material Water Chemistry VIII.E-29 13.4.1.16 !A Steel Water (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Palo Verde Nuclear Generating Station Page 3.3-220 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS tiainiess I-lant inaoor i-ir Steel (Ext) + Valve LBS, PB Stainless Raw Water (Int) Loss of material Inspection Of Internal iVII.C1-15 3.3.1.79 E, 2 Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Valve LBS Stainless "Treated Borated Loss of material Water Chemistry iVII.E1-17 i 13.3.1.91 Steel _W*aIerl n9t _1 (B2.1.2) Notes for Table 3.3.2-27: Standard Notes: A- Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 The component environment for radioactive waste drains that has been evaluated as a raw water environment. Loss of material on internal component surface exposed to floor and equipment drains environment will be managed by Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.22) instead of the Open-Cycle Cooling Water System program (B2.11.9). Palo Verde Nuclear Generating Station Page 3.3-221 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS riant inaoor /ir LOSS OT materiai r-mxernal ourraces (Ext) Monitoring Program (B2.1.20) fAccu m ulator IPB Carbon Steel Ventilation tLoss of material Inspection Of Internal VII.G-23 3.3.1.71 Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components (2.1 .22) Closure Bolting IPB Carbon Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.7) VII.I-4 3.3.1.43 B (Ext) Closure Bolting PB Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) IVII.I-5 13.3.1.45 B Closure Bolting PB Stainles 5 Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) iNone i None G Steel FExtl O£ Filter FIL, PB Aluminu im Loss of material Fuel Oil Chemistry VII.H2-7 3.3.1.32 B (B2.1.14) and One-Time Inspection (B2.1.16) Filter FIL, PB Aluminum Plant Indoor Air None None V.F-2 3.2.1.50 A _ (Ext) _ _____ Filter FIL, PB kAluminum Ventilation 'None None V.F-2 3.2.1.50 A-- SAtmosphere (Int)___ Filter FIL, PB Carbon Steel Fuel Oil (Int) 1Loss of material Fuel Oil Chemistry VII.H2-24 3.3.1.20 B (B2.1.14) and One-Time Insp.ection (B2.1.16 .... Palo Verde Nuclear Generating Station Page 3.3-222 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS TnhhI _qIi 9-RAtiyiliqrt1 qv.,zhnm., - rt GeneratorSystem (Continued) I ~NUREG- ITabl1 _Item I MotesI Filter FIL, PB Carbon Steel Hydraulic i-luid LOSS ot material (Luricating Uii Analysis vii.lz-U *u (Int) (B2.1.23) and One-Time; Inspection (B2.1.16) _ _ _ Filter FIL, PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-20 13.3.1.14 B (Int) (3B2.1.23) and One-Time (Int)_ _ _ Inspection (32.1.16) FIL, PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.1-8 i3.3.1.58 (Ext) j Monitoring Program (B2.1.20) Filter FIL, PB Stainless Plant Indoor Air TNone None :VII.J-15 3.3.1.94 A Steel Ext) ________ 4 Filter FIL, PB Stainless Wetted Gas (Int) Loss C )f material Inspection Of Internal V.D1-29 13.2.1.08 E Steel Surfaces In Miscellaneous Piping And Ducting Components B2.1.22)___ _ Heat HT, PB Copper Alloy Lubricating Oil Loss of material Lubricating Oil Analysis VVII.H2-10 3.3-1.26 Exchanger (Int) (B2.1.23) and One-Time (Generator Inspection (B2.1.16) Bearing il Heat HT, PB ICopper Alloy Lubricating Oil Reduction of heat Lubricating Oil Analysis VIII.G-8 3.4.1.10 B Exchanger (Int) transfer (B2.1.23) and One-Time (Generator Inspection (B2.1.16) Bearing Oi.) Heat HT, PB Copper Alloy Plant Indoor Air None None Vl2 3.4.1.41 Exchanger (Ext) (Generator Býea~ring OIl Palo Verde Nuclear Generating Station Page 3.3-223 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ement Evaluation - Station Blackout GeneratorSvstem (Continued) meai MI miuminum Atmospnerei LOSS 01 materiai External Surfaces iNone None Exchanger Weather (Ext) Monitoring Program o (Lube Oil) (82.1.20) ___ Heat HT, PB Carbon Steel Atmosphere// Los of material External Surfaces ýVII.H2-4 3.3.1.59 B Exchanger Weather (Ext) Monitoring Program t(B2.1.20) ______ _____ _ _ (Lube Oil) Heat HT, PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Knalysis VII.H2-5 3.3.1.21 B Exchanger (Int) ((B2.1.23)and One-Time Lub Oil_ Inspection (B2.1.16) Heat HT, PB Carbon Steel Lubricating Oil Reduction of heat Lubricating Oil Analysis IVIII.G-15 3.4.1. 10 11B Exchanger (Int) transfer (82.1.23) and One-Time .(Lube Oil). Inspection 2.1.16) Orifice PB, TH Carbon Steel Fuel Oil (Int) ILoss of material Fuel Oil Chemistry !VII.H2-24 3.3.1.20 B (82.1.14) and One-Time inspecin 8.11)______ Orifice PB, TH ICarbon Steel Plant Indoor Air Loss of material External Surfaces IVII.I-8 3.3.1.58 B (Ext) Monitoring Program JB2.1_20),. Orifice PB, TH Stainless Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-16 3.3.1.32 TB Steel (82.1.14) and One-Time Inspection (82.1.16) .... _ Orifice PB, TH Stainless Plant Indoor Air None None TVII.J-15 i3.3.1.9 Ak Steel (Ext). I TB Piping PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry !VII.H2-24 13.3.1.20 (82.1.14) and One-Timei Inspection (B2.1.16) - Piping PB Carbon Steel Hydraulic Fluid Loss of material Lubricating Oil Analysis VII.H2-20 3.3.1.14 B (Int) (B2.1.23) and One-Time , Inspection (B2.1.16)j _ Palo Verde Nuclear Generating Station Page 3.3-224 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS IrD dIOUI Lt*:l (EIlLt)IIUUUI (Ext) Monitoring Program (B2.1.20) Piping PB Carbon Steel Ventilation TLoss of material Inspection Of Internal IVII.G-23 3.3.1.71 B Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Piping PB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-17 37...3 Steel (Int) (B2.1.23) and One-Time Inspection (B2.1.16). Piping PB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 A Steel (Ext) _
+
Pump Aluminum Fuel Oil (Int) ILoss of material Fuel Oil Chemistry VII.H2-7 13.3.1.32 B (B2.1.14) and One-Time Inspection (B2.1.16) Pump jPB lAluminum Plant Indoor Air None None V.F-2 3.2.1.50 A (_xt)__ Pump 1PB Carbon Steel Fuel Oil (Int) ;Loss of material Fuel Oil Chemistry VII.H2-24 3.3.1.20 (B2.1.14) and One-Time Inspection (B2.1.16) P5u mp Carbon Steel Lubricating Oil 1Loss of material Lubricating Oil Analysis VII.H2-20 13.3.1.14 (Int) (B2.1.23) and One-Time Inspection (B2.1.16) Pump IPB Carbon Steel Plant Indoor Air ILoss of material External Surfaces VII.1-8 13.3.1.58 B (Ext) Monitoring Program B21. 20j Palo Verde Nuclear Generating Station Page 3.3-225 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS ment Evaluation - Station Blackout GeneratorSystem (Continued) ruiiip r-Uei UII k1I1L) !LUOS Ut maerIal rIUel uii ur, nemlbuy IVII.I-I/--/-I- !O.,.. I ./-U (B2.1.14) and One-Time i Inspection (132.11.16) Lubricating Oil Analysis IVII.1H2-20 3.3.1.14 Pump tCast Iron Lubricating Oil Loss of material B (Int) (B2.1.23) and One-Time Inspection (B2.1.16) I Pump Cast Iron Plant Indoor Air Loss of material External Surfaces VII.l-8 13.3.1.58 B (Ext) Monitoring Program ((B2.1.20) __ _ Sight Gauge PB Glass Lubricating Oil None None TVII.J-10 13.3.1.93 A (Int) Sight Gauge PB Glass Plant Indoor Air iNone None VII.J-8 13.3.1.93 A (Ext) I Tank Carbon S teel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-24 . 1.20 -B Inspection (B2.1.166) ,__ Tank PB Carbon S teel Hydraulic Fluid Loss of material Lubricating Oil Analysis IVII.H2-20 13.3.1.14 D (Int) (B2.1.23) and One-Time Inspection (B2.1.16) _ Tank PB Carbon S teel Plant Indoor Air !Loss of material External Surfaces VII.1-8 13.3.1.58 B (Ext) Monitoring Program _ _ _ (B2.11.20) Tubing PB Carbon Stteel Fuel Oil (Int) FLoss of material Fuel Oil Chemistry IVII.H2-24 3.3.1.20 B (B2.11.14) and One-Time Tubing Inspection (B12.1.16) 1 _ PB Carbon Stteel Plant Indoor Air iLoss of material External Surfaces VII.I-8 13.3.1.58 B (Ext) Monitoring Program B2.1 .20 Palo Verde Nuclear Generating Station Page 3.3-226 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS 12 q2 4 71 1110POUILLIU I V-1 UI 11It::l I:l IC1 Vl1l.g
%;),J' , I-t Atmosphere (Int) Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22)j 2) _
Tubing Copper Alloy tFuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-9 331.32 jB (B2.1.14) and One-Time Inspection( 1632 __11.116 PB Copper Alloy Hydraulic Fluid Loss of material Lubricating Oil Analysis IVII.H2-20 3.3.1.14 Tubing Tub6ing (Int) (B2.1.23) and One-Time PB Copper Alloy Lubricating Oil Loss of material Lubricating Oil Analysis VII.BH2-1 13.3.1.26 B (Int) (B2.11.23) and One-Time I
,hqspection (B2.1.16L,___
Tubing PB Copper Alloy Plant Indoor Air None None V.F-3 13.2.1.53 (Ext) + Tubing PB Stainless Lubricating Oil iLoss of material Lubricating Oil Analysis IVII.H2-17 i3.3.1.33 B Steel (Int) (B2.11.23) and One-Time Inspection (B2.1.116 __)
,f.
Tubing ýPB S§tai nle ss Plant Indoor Air None None VII.J-15 3.3.1.94 B Steel (Ext) 113.3.11.58 IB Turbine PB Ductile Iron Plant Indoor Air ILoss of material External Surfaces IVII.I-8 (Ext) Monitoring Program (B2.11.20) 4. Turbine PB Ductile Iron Wetted Gas (Int) {Loss of material Inspection Of Internal VII.H2-21 3.3.1.71 Surfaces In Miscellaneous Piping And Ducting Components (B2.11.22) I Palo Verde Nuclear Generating Station Page 3.3-227 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS t-uei un tnemisiry IVi.riz-1 (B2.1.14) and One-Time Inspection (B2.1.16) _ Auinum I iihric.*tinri Oil Anl~v.*i. iNnn*. Nnno. ialve Lubricating Oil of-Loss material (Int) (B2.1.23) and One-Time Inspection (B2.1.16) I Valve PB Aluminum Plant Indoor Air None None V.F-2 3.2.1.50 A (Ext) Aluminum Ventilation None None V.F-2 3.2.1.50 A Atmosphere(Int) Valve PB Carbon Steel Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-24 3.3.1.20 B (B2.1.14) and One-Time
-4 Inspection (B2.1.16) _
1----- 4 Valve PB Carbon Steel Hydraulic Fluid Loss of material Lubricating Oil Analysis IVII.H2-20 3.3.1.14 (Int) (B2.1.23) and One-Time Inspection (B2.1.16)_ Valve PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-20 13.3.1.14 B (Int) (B2.1.23) and One-Time Inspection (B2.1.16) Valve PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I-8 3.3.1.58 B (Ext) Monitoring Program (132.1.20) ,, Valve PB Copper Alloy Fuel Oil (Int) Loss of material Fuel Oil Chemistry VII.H2-9 3.3.1.32 B (B2.1.14) and One-Time Inspection (B12.1.16) Valve PB Copper Alloy Hydraulic Fluid Loss of material Lubricating Oil Analysis VII.H2-10 3.3.1.26 B (Int) (B2.1.23) and One-Time , Inspection (B32.1.16) __ _________ Palo Verde Nuclear Generating Station Page 3.3-228 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS
- Management Valve JIPB Copper Alloy Lubricating Oil Loss of material LUDricating U11 Anaiysis vi. i-i-ujiil (Int) (B2.1.23) and One-Time Inspection (B2.1.16)
Valve PB Copper Alloy Plant Indoor Air None None V.F-3 13.2,1.53 Valve PB Copper Alloy Wetted Gas (Int) CLoss of material Inspection Of Internal ,VII.G-9 3.3.1.28 E Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Valve PB Stainless Fuel Oil (Int) ILoss of material Fuel Oil Chemistry VII.H2-16 I13.3.1.32 1 Steel (B2.1.14) and One-Time Inspection (B2.1.16) IVll.H2-17 3.3i1.33 Valve Stainless Hydraulic Fluid Loss of material Lubricating Oil Analysis Steel (Int) (B2.1.23) and One-Time Inspection (B2.1.16) 4 + 4-Valve tPB Stainless Lubricating Oil Loss of material Lubricating Oil Analysis VII.H2-17 13.3.1.33 B Steel (Int) (B2.1.23) and One-Time Inspection (82.1.16) Valve PB Stainless Plant Indoor Air jNone None VlI.J-15 3.3.1.94 !A Steel (Ext) _ Valve PB Stainless Wetted Gas (Int) -'Loss of material Inspection Of Internal V.D1-29 3.2.1.08 . E Steel Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) Palo Verde Nuclear Generating Station Page 3.3-229 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-28: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. D Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: None. Palo Verde Nuclear Generating Station Page 3.3-230 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS IuarDon (Ext) Heavy Load and Light Load (Related to Refueling) Handling Systems (12.1.11) _ Cranes - Rails SNSRS Carbon Steel Plant Indoor Air iLoss of material Inspection of Overhead VII.B-1 3.3.1.74 A (Ext) Heavy Load and Light Load (Related to I Refueling) Handling Systems (B2.1.11) _ Cranes - Rails FtNSRS Ca-rb-on Steel Plant Indoor Air Loss of material Inspection of Overhead VII.B-3 *3.3.1.73 1C (Ext) Heavy Load and Light Load (Related to Refueling) Handling Systems (B2.1.11 ) Hoist NSRS Steel Plant Indoor Air Loss of material Inspection of Overhead VII.B-3 3.3.1.73 1C (Ext) Heavy Load and Light Load (Related to Refueling) Handling Systems (B2.1.11L _.. Trolley NSRS Carbon Steel Plant Indoor Air Loss of material Inspection of Overhead tVII .bB-3 3.3.1.73 C (Ext) Heavy Load and Light Load (Related to Refueling) Handling L______________________________________________ ___________________________ Systems (132. 1.11) ___ Palo Verde Nuclear Generating Station Page 3.3-231 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-29: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None. Palo Verde Nuclear Generating Station Page 3.3-232 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONL Y based on Criterion 10 CFR 54.4 (a)(2) I Vid IdyU4tEUEIL I I! I It Z RU Closure Bolting LBS Carbon Steel Borated Water Loss of preload Bolting Integrity (B2.1.7)I IV.C2-8 13.1.1.52 B Leakage (Ext) Closure Bolting LBS Carbon Steel Borated Water Loss of material Boric-Acid Corrosion V.E-2 3.2.1.45 A ILeakage (Ext) (B2.1.4) i B Closure Bolting LBS Carbon Steel IPlant Indoor Air Loss of material Bolting Integrity (B2.1.7) I 3 (Ext) 1.1-1.-1.1........... ...........
- -.1...........................
..... .......... . ................................
.......................
"J1-.......................
.- t i 2 1 7i * ; * ............ ...
B ..................................... Closure Bolting LBS Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) iVII.-5 1.3..3..1.45. B Closure Bolting LBS, SIA Carbon Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.7) 1VIII.H-4 13.4.1.22 B (Ext) Loss of preload Bolting Integrity (B2.1.7) VIII.H- 3.4.1.22 B Closure Bolting LBS, SIA Carbon Steel Plant Indoor Air (IE) Closure Bolting LBS Copper Alloy Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) None iNone F, 1 (Ext) Closure Bolting LBS Stainless Borated Water 1Loss of preload Bolting Integrity (B2.1.7) IV.C2-8 13.1.1.52 B Steel Leakage (Ext) Closure Bolting LBS, SIA Stainless Plant Indoor Air !,Lossof preload Bolting Integrity (B2.1.7) None 1None G, 1 Steel (Ext)___ Filter LBS Stainless Borated Water None None W.F-13 13.2.1.57 A Steel Leakage (Ext) Filter jLB Stainless Steel Treated Borate J Water (Int) Loss of material Water Chemistry (B2.1.2) 1V 7A27 1321.49 I .... A Palo Verde Nuclear Generating Station Page 3.3-233 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope nAII VA - ,') __o* frfH,-r*4 lD C 9z A */*/P"fi IH
,,-IZ)UU:*i-%yLyl IL-UtU U1I II IdLI Idi LIlUU-%.yLUIt %,UUIIIly Exchanger (AS Cooling Water (lnt) !Water System (B2.1.10)
Condensate Vent Condenser)
+
Heat LBS Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 B Exchanger (AS (Ext) Monitoring Program Condensate (B2.1.20) Vent Condenser)_ Loss of material Water Chemistry (B2.1.2) Heat LBS Carbon Steel Secondary Water A Exchanger (AS (Int) and One-Time Inspection VIII.E-37 13.4.1.03 Condensate (B2.1.16) Vent Condenser) Heat Exchanger LBS Carbon Steel Closed-Cycle Cooling Water (Int'
)itLoss of material Closed-Cycle Cooling Water System (B2.1.10)
VIII.A-1 13.4.1.24 (Sample cooler ... . Heat LBS Carbon Steel Closed-Cycle Loss of material Closed-Cycle Cooling VIII.F-4 3.4.1.24 B Exchanger Cooling Water (Int' Water System (B2.1.10) (Sample Cooler ... ... Heat LBS Carbon Steel Plant Indoor Air 1Loss of material External Surfaces VIII.H-7 13.4.1.28 Exchanger (Ext) Monitoring Program (Sample (B2.1.20) Cooler) 14 Palo Verde Nuclear Generating Station Page 3.3-234 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONL Y based on Criterion 10 CFR 54.4(a)(2) (Continued) Wiwanage uIosea-uycie ILOSS OT MTiaterial Closed-Cycle Cooling Exchanger Cooling Water I Water System (B2.1.10) (Sample (Ext) Cooler r)__, Heat 1LBS Stainless Secondary Water Cracking Water Chemistry (B2.1.2) VIII.F-3 3.4.1.14 A7 Exchanger Steel (Int) land One-Time Inspection (Sample (B2.1.16) Heat LBS Stainrless Secondary Water Loss of mate Water Chemistry (B2.1.2) Wial VIII.F-27 3.4.1.16 Exchange r Steel (Int) and One-Time Inspection (Sample " 1(B2.1.16) Cooler) Orifice LBS Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.1-8 3.3.1.58 (Ext) Monitoring Program Rw(B2.1.20) Orifice LBS Carbon Steel Water (Int) Loss of material Ilnspection Of Internal VII.C1-19 i3.3.1.76
!Surfaces In Miscellaneous
!Piping And Ducting IComponents (B2.1.22)
Orifice LBS Stainless Plant Indoor Air None None VIII.l-10 1:3.4.1.41 Steel ,Ext)__ Orifice LBS Stainless Secondary Water Loss of material lWater Chemistry (B2.1.2) VIII.B1-4 :3.4.1.16 Steel (Int) and One-Time Inspection (B2.1.16) Orifice LBis................ Stainless Secondary Water ICracking 'Water Chemistry (132.1 .2) VIII.B1-5 3.4.1.14 A Steel (Int) land One-Time Inspection _ _i(B2.1.16) Palo Verde Nuclear Generating Station Page 3.3-235 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY based on Criterion 10 CFR 54.4(a)(2) (Continued) Carbon Steel Plant Indoor Air Loss of material External Surfaces (Ext) Monitoring Program (132.1.20m Piping LBS, SIA Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 (Ext) IMonitoring Program Piping LBS Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VILCI-19 13.3.1.76 1Surfaces In Miscellaneous
!Pip'ing And Ducting Loss Inspection Of (B2.1.22) aterial __Components Internal Piping jLBS Carbon Steel Raw Water (Int) VII.C1-19 3.3.1.76 Surfaces In Miscellaneous Piping And Ducting 4 t Piping TSIA Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VII.C1-19 3.3.1.76 E, 2 (B2.1.22)
Surfaces In Miscellaneous _________!Components Piping And Ducting Comrponent (122)1.6 LBS, SIA Carbon Steel Secondary Water !Loss of material Water Chemistry (B2.1.2) VIII.B1-8 3.4.1.37 A Piping Cdarbon S~teel Secondary Water 'Wall thinning .Flow-Accelerated VIII.B1-9 3.4.1.29 LBS i(Int). (Int) Coorrosion (132.16 Carbon Steel Secondary Water L1oss of material Water Chemistry (132.1.2-) land One-Time Inspection VIII.B1-11 3.4.1.04 A _ _____"_ _ _ I(B2.1.16) ___ __1 Palo Verde Nuclear Generating Station Page 3.3-236 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY based on Criterion 10 CFR 54.4 (a)(2) (Continued) 1Lb* uarDon zteei vvetea uas tint) LOSS or matenailiinspecuon UT iniernai VIII.t5I-/ Surfaces In Miscellaneous
'Piping And Ducting
__________ Components ((B2.1.22) ...... Piping LBS Carbon Steel Plant Indoor Air Loss of material 1External Surfaces VII.I-8 3.3.1.58 with (Ext) 'Monitoring Program Elastomer (B2.1.20) L _ _ Lining Piping LBS Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VII.C1-19 3.3.1.76 with ISurfaces In Miscellaneous Elastomer Piping And Ducting 1Lining PComponents (B2.1.22) LBS iCopper Alloy Plant Indoor Air iNone INone IVIII.1-2 Piping 3.4.1.41 A (Ext) Piping LBS Copper Alloy Potable Water (Int) Loss of material Inspection Of Internal None None tSurfaces In Miscellaneous Piping And Ducting s Components (2.1.22 Piping Copper Alloy Raw Water (Int) Los of material ilnspection Of Internal VII.C1 9 3.3.1.81 E, 2 LBS Surfaces In Miscellaneous Piping And Ducting _ _Components (B2.1.22) Piping LBS Stainless Borated Water None None V.F-13 T3.2.1.57 A
..... . Leakage (Ext)
Ste.e................................... I
.i.i..I.
... -..-.3.. .. ..........
.............
Piping LBS, SIA Stainless Demineralized ILoss of materia Water Chemistry (32i ..2) A
'Steel Water (Int) !and One-Time Inspection
. . . .(1 . . ..................... *( 2.1.16) ... ................
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Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY based on Criterion 10 CFR 54.4(a)(2) (Continued) Ll50, 011/A z.-.ainiess riant inaoor mir i'Jone iNone jSteel 1 (Ext LBS, SIA 1Stainless Plant Indoor Air INone None VIII.1-10 .3.4.1.41 A Piping [Steel RExt e LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.C1-15 3.3.1.79 IE, 2 1Steel Surfaces In Miscellaneous Piping And Ducting Pipng C*omponents (B2.1.22) LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.C1-15 3.3.1.79 E, 2 Steel Surfaces In Miscellaneous Piping And Ducting IComponents (B2.1.22) Piping SIA Stainless Raw Water (Int) Loss of material IInspection Of Internal VII.C1-15 3.3.1.79 E, 2 Steel !Surfaces In Miscellaneous Piping And Ducting IComponents (B2.1.22) Piping tLBS IStainless Secondary Water !Loss of material Water Chemistry (B2.1.2) VIII.B1-4 13.4.1.16 A 1Steel (Int) land One-Time Inspection
'(g2.1.16)
Piping LBS Stainless Secondary Water Cracking Water Chemistry (B2.1.2) VIII.B1-5 3.4.1.14 A Steel (Int) iand One-Time Inspection __2. 1.1) Piping LBS, SIA Stainless Secondary Water Loss of material Water Chemistry (B2.1.2) VIII.F-23 3.4. 1.16 A Steel (Int) i and One-Time Inspection _(1B2.1.16) . . ... Piping LBS, SIA Stainless Secondary Water i Cracking !Water Chemistry (B2.1.2) VIII.F-24 3.4.1.14 Steel (Int) (nt). land One-Time Inspection 1(B2.1.16) Palo Verde Nuclear Generating Station Page 3.3-238 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLYbased on Criterion 10 CFR 54.4(a)(2) (Continued) Piping LBS etainiess i reaiea toraiea LOSS OT maieriai vvater unemisiry tb. i.z) Steel Water (Int) ___________I_________________ Pump 'LBS Cast Iron Plant Indoor Air !Loss of material External Surfaces VIII.H-7 13.4.1.28 B (Gray Cast (Ext) Monitoring Program Iron) __(B2.1.20L_____ Pump Cast Iron Secondary Water Wall thinning Flow-Accelerated VIII.B1-9 3.4.1.29 B (Gray Cast (Int) 'Corrosion (B2.1.6) Iron) _ Pump LBS Cast Iron Secondary Water iLoss of material Water Chemistry (B2.1.2) VIII.B1-11 .3.4.1.04 A (Gray Cast (Int) and One-Time Inspection Iron)__ @B2.1.16) Pump Cast Iron Secondary Water Loss of material iSelective Leaching of VIII.E-23 3.4.1.36 (Int) !Materials (B2.1.17) Iron )_ Cast (Gray . ..... ........ . . . . . .... _.... . . _ ILBS Cast Iron Borated Water Loss of material Boric Acid Corrosion V.E-9 .3.2.1.45 A Sight SighGauge Gaue Leakage (Ext) (B2.1.4) LBS Glass oBorated Water iNone None None None Leakage (Ext) Sight Gauge ILBS, SIA Glass Plant Indoor Air None None VII.J-8 3.3.1.93 A (Ext) SFght Gauge fLBS Glass Plant Indoor Air (Ext) ____ None None VIII.I-5 13.4.1.40 A LBS, SIA Sight Gauge Glass Raw Water (Int)._ None None VII.J-11 3.3.1.93 A Sight Gauge LBS Glass Secondary Water None None VIII.I-8 3.4.1.40 A Si-ght Gauge i ILBS Glass Treated Borated None None V.F-9 13.2.1.52 A Water (Int) . Palo Verde Nuclear Generating Station Page 3.3-239 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY h:s.ed on Criterion 10 CRF 54.4(a)(2) (Continued) bioratea vvater None None Steel Leakage (Ext) I Sight Gauge LBS,SIA Stainless Plant Indoor Air None 1None VII.J-15 3.3.1.94 A Steel Sight Gauge Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.CI-15 3.3.1.79 E, 2 1 LBS, SIA Steel !Surfaces In Miscellaneous I ' Piping And Ducting Components (3B2.1.22) Sight Gauge LBS Stainless Treated Borated !Loss of material iWater Chemistry (B2.1.2) V.A-27 13.2.1.49 Steel Water (Ing) Strainer LBS, SIA Carbon Steel Plant Indoor Air !Loss of material External Surfaces VII.1-8 3.3.1.58 (Ext) Monitoring Program (132.1.20) Strainer LBS, SIA Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VII.C1-19 13.3.1.76 E, 2
+/- ISurfaces In Miscellaneous IPiping And Ducting o oComponents (B2.1.22)
Strainer LBS Cast Iron Plant Idoor Air Loss-of mmaterial External Surfaces VIII.H-7 3.4.1.28 B (Gray Cast (Ext) Monitoring Program Strainer LBS ___ ~B2.1.201___ Cast Iron Secondary Water Wall thinning Flow-Accelerated VIII.B1-9 3.4.1.29 (Gray Cast (Int) Corrosion (B2.1.6) Strainer ner LBSLB Cast Iron (Gray Cast Secondary Water (Int) Loss of material IWater Chemistry (B2.1.2) land One-Time Inspection VIII.B1-1 1 3.4.1.04 A Iron) S................ L B2.1.16)
@__ ___. .
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Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope OnNI Y h.,zo.d nn rrit.rinn 10 .FR .F4 4(a)(2) ((nntimiprd) Strainer LBS Cast Iron Secondary Water Loss of material Selective Leaching of VIII.E-23 3.4.1.36 (Gray Cast (Int) Materials (B2.1.17) Iron) _ _ Tank LBS Carbon Steel Plant Indoor Air rLoss of material iExternal Surfaces VIII.H-7 i3.4.1.28 B (Ext) Monitoring Program _____ ___ ____ _____(13 2.1.20 Tank LBS Carbon Steel Secondary Water iLoss of material Water Chemistry (B2.1.2) VIII.B1-11 13.4.1.04 A (Int) and One-Time Inspection j__ _ (B2.1.16) + Tubing LBS Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 13.4.1.28 B (Ext) 'Monitoring Program _ _(B2.1.20) Tubing LBS Carbon Steel Secondary Water Loss of material iWater Chemistry (B2.1.2) VIII.B1-11 3.4.1.04 A (Int) land One-Time Inspection _ __ _ _ _ _ _ _ __ B2.1.16)_ Tubing LBS Stainless Borated Water iNone None V.F-13 3.2.1.57 A Steel Leakage (Ext)__ Tubing LBS Stainless Treated Borated Loss of material Water Chemistry (B2.1.2) V.A-27 3.2.1.49 A Steel Water (Int) _ Valve LBS Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.l-8 13.3.1.58 B Valve LBS (Ext)2. Carbon Steel Plant Indoor Air
} Monitoring Program
- (B32.1 .20)
Loss of material External Surfaces VIII.H-7 13.4.1.28 B (Ext) iMonitoring Program Palo Verde Nuclear Generating Station Page 3.3-241 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONL Y based on Criterion 10 CFR 54.4(a)(2) (Continued) Kaw vvaier kinf) !LOSS OT maieriai inspecuon UT iniernai
'Surfaces In Miscellaneous F- ,Piping And Ducting
_ _Components B2.1.22 Valve LBS Carbon Steel Raw Water (Int) Loss of material Inspection Of Internal VII.C1-19 13.3.1.76 E, 2 iSurfaces In Miscellaneous
!Piping And Ducting
!,Components (B2.1.22)
Valve LBS Carbon Steel Secondary Water iLoss of material Water Chemistry (B2.1.2) VIII.B1-8 3.4.1.37 Valve LBS Carbon Steel Secondary Water Wall thinning Flow-Accelerated VIII.B1-9 3.4.1.29 (Int) -Corrosion (B2.1.6) Valve LBS Carbon Steel Secondary Water Loss of material Water Chemistry (B2.1.2) VIII.B1-11 i3.4.1.04 (Int) iand One-Time Inspection 1ý(B2.1.16) Valve Carbon Steel Wetted Gas (Int) !Loss of material! Inspection Of Internal VII.131-7 3.4.1.30 iSurfaces In Miscellaneous Piping And Ducting Valve Cast Iron Plant Indoor Air Loss of material External Surfaces VIII.H-7 '3.4.1.28 B (Gray Cast (Ext) I :Monitoring Program Iron) (B2.1.20) Valve Cast Iron Secondary Wate r Wall thinning Flow-Accelerated VIII.1i19 13.4. 1.2 B (Gray Cast (Int) Corrosion (B2.1.6) Iron) Valve LB[S Cast Iron Secondary Wate ,r-Loss of material Water Chemistry (B2.1.2) VIII.1-117 3.4.1.04 A (Gray Cast (Int) and One-Time Inspection Iron) (B2.1.16) Palo Verde Nuclear Generating Station Page 3.3-242 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY based on Criterion 10 CFR 54.4(a)(2) (Continued) ed 1IMaterial I Environment I ~AginigEffect Aging Management NUE-ITablel 1 tem INotes> itasi iron Seconaary vvater LOSS O0maierial Ielective Le*Clrig of VuIII. __-,, (Gray Cast (Int) ,Materials (B2.1.17) IronL_)___ Valve ýLBS Copper Alloy Plant ndoor Air None None VIII.1-2 I3413 .4.1.4 A (Ext) a-- Copper Alloy [Potable Water (Int) Loss of material Inspection Of Internal None None G ,Valve LBS
!Surfaces In Miscellaneous riping ina uucting
__Components (B2.1.22) Valve LBS Copper Alloy Secondary Water Loss of material Water Chemistry (B2.1.2) VIII.A-5 13.4.1.15 IA (Int) land One-Time Inspection ____ _1 (32.,1 .,16)___ Valve LBS CoDDerAlIov [Plant Indoor Air 6one None VIII.1-2 :3.4.1.41 I(Zinc>15%) (Ext) A Valve LBS copper Alloy Secondary Water Loss of material!Water Chemistry (132.1.2) ýVIILiA-5 3.4.1.15 fA 1(Zinc >15%) (Int) Sand One-Time Inspection __ _(B2.1.16) Valve LBS ýCopper Alloy Secondary Water Loss of material Selective Leaching of VIII.E-21 3.4.1.35 1B
- s. ........
*L (Zinc
........... >15%)
e.
....
.. s ...
-.._..(Int) 'Materials (B2.1.17)
LBS Stainless Borated Water None None V.F-13 13.2.1.57 A Steel Leakage (E ).. LBS, SIA Stainless PDemineralized Loss of material Water Chemistry (B2.1.2) VIII.E-291. 3.41.16 Steel Water (Int) and One-Time Inspection Valve (132.1.16) AK LBS, SIA Stainless . Pianitindoor Air None None VII.J-15 3.3.1.94 Valve Steel LBS Stainless Plant Indoor Air None None VIII.I1-10 ,3.4.1.41 Steel (Ext) ..... .................. Palo Verde Nuclear Generating Station Page 3.3-243 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Table 3.3.2-30 Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Auxiliary Systems In-Scope ONLY based Component Intended Material iagement Type Function: ram Valve LBS Stainless Internal \'j 15.15.1 . f ýj Steel SSurfaces In Miscellaneous
.Piping And Ducting iComponents (2.1.22 Valve LBS Stainless Raw Water (Int) Loss of material Inspection Of Internal VII.C1-15 3.3.1.79 JE, 2 Steel ,Surfaces In Miscellaneous Piping And Ducting
;Components (B2.1.22)
Valve SIA Stainless Raw Water (Int) Loss of material ,Inspection Of Internal VII.C1-15 3.3.1.79 E, 2 Steel Surfaces In Miscellaneous
,Piping And Ducting
.Components (B2.1.22)
Valve LBS Stainless Secondary Water Loss of material ,Water Chemistry (B2.1.2) VIII.F-23 3.4.1.16 Steel (Int) ,and One-Time Inspection A~7 (B2.1.16) V-alve iLBS 1Stainless Secondary Water Cracking lWater Chemistry (B2.1 .2) VIII.F-24 23.4.1.14 Steel (Int) and One-Time Inspection Treatd Borted Lss of(§2.1.16 _ __ LBS Stainless Treated Borated Loss of material Water Chemistry (B2.1 .2) V.A-27 3.2.1.49 _7A Steel W ater (Int) __........... Palo Verde Nuclear Generating Station Page 3.3-244 License Renewal Application
Section 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS Notes for Table 3.3.2-30: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. F Material not in NUREG-1801 for this component. G Environment not in NUREG-1 801 for this component and material. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.22) is credited instead of Open-Cycle Cooling Water System program (B2.1.9) for aging management of the components of solid radwaste system, sanitary drains and treatment, chemical waste, oily waste systems. Palo Verde Nuclear Generating Station Page 3.3-245 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM 3.4.1 Introduction Section 3.4 provides the results of the aging management reviews for those component types identified in Section 2.3.4, Steam and Power Conversion System, subject to aging management review. These systems are described in the following sections:
- Main steam (Section 2.3.4.1)
Condensate storage and transfer (Section 2.3.4.2)
- Auxiliary feedwater (Section 2.3.4.3)
Table 3.4.1, Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion System, provides the summary of the programs evaluated in NUREG-1801 that are applicable to the component types in this section. Table 3.4.1 uses the format of Table 3.x.1 (Table 1) described in Section 3.0. 3.4.2 Results The following tables summarize the results of the aging management review for the systems in the Steam and Power Conversion System area: Table 3.4.2-1, Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System Table 3.4.2-2, Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and Transfer System Table 3.4.2-3, Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary Feedwater System These tables use the format of Table 2 discussed in Section 3.0. 3.4.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs The materials from which the component types are fabricated, the environments to which they are exposed, the potential aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above systems in the following subsections. Palo Verde Nuclear Generating Station Page 3.4-1 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM 3.4.2.1.1 Main Steam System Materials The materials of construction for the main steam system component types are:
- Aluminum
- Carbon Steel
- Copper Alloy
- Copper Alloy (Zinc >15%)
- Insulation Calcium Silicate 0 Nickel Alloys
- Stainless Steel Environment The main steam system component types are exposed to the following environments:
- Dry Gas
- Plant Indoor Air
- Secondary Water
- Wetted Gas Aging Effects Requiring Management The following main steam system aging effects require management:
0 Cracking
- Loss of material 0 Loss of preload 0 Wall thinning Aging Management Programs The following aging management programs manage the aging effects for the main steam system component types:
- Bolting Integrity (B2.1.7)
- Extemal Surfaces Monitoring Program (B2.1.20)
- Flow-Accelerated Corrosion (B2.1.6)
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Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Inspection Of Internal Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22)
- One-Time Inspection (B2.1.16)
- Water Chemistry (B2.1.2) 3.4.2.1.2 Condensate Storage and Transfer System Materials The materials of construction for the condensate storage and transfer system component types are:
- Carbon Steel
- Stainless Steel
- Stainless Steel Cast Austenitic Environment The condensate storage and transfer system components are exposed to the following environments:
- Atmosphere/ Weather
- Dry Gas
- Encased in Concrete
- Plant Indoor Air
- Secondary Water
- Wetted Gas Aging Effects Requiring Management The following condensate storage and transfer system aging effects require management:
- Loss of material
- Loss of preload Aging Management Programs The following aging management programs manage the aging effects for the condensate storage and transfer system component types:
- Bolting Integrity (B2.1.7)
- External Surfaces Monitoring Program (B2.1.20)
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Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Inspection Of Internal Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22)
- One-Time Inspection (B2.1.16)
- Water Chemistry (B2.1.2) 3.4.2.1.3 Auxiliary Feedwater System Materials The materials of construction for the auxiliary feedwater system component types are:
- Aluminum 0 Carbon Steel
- Cast Iron
- Glass
- Insulation Calcium Silicate
- Nickel Alloys
- Stainless Steel
- Stainless Steel Cast Austenitic Environment The auxiliary feedwater system components are exposed to the following environments:
- Lubricating Oil
- Plant Indoor Air
- Secondary Water Aging Effects Requiring Management The following auxiliary feedwater system aging effects require management:
- Loss of material
- Loss of preload
- Reduction of heat transfer
- Wall thinning Aging Management Programs The following aging management programs manage the aging effects for the auxiliary feedwater system component types:
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Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM
- Bolting Integrity (B2.1.7)
- External Surfaces Monitoring Program (B2.1.20)
- Flow-Accelerated Corrosion (B2.1.6)
- Lubricating Oil Analysis (B2.1.23)
- One-Time Inspection (B2.1.16)
- Water Chemistry (B2.1.2) 3.4.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 NUREG-1801 provides the basis for identifying those programs that warrant further evaluation. For the Steam and Power Conversion System, those evaluations are addressed in the following subsections.
3.4.2.2.1 Cumulative Fatigue Damage Evaluation of fatigue is a time-limited aging analysis (TLAA) as defined in 10 CFR 54.3. TLAAs are evaluated in accordance with 10 CFR 54.21(c)(1). PVNGS piping designed to ASME III Class 2, Class 3, and ANSI B31.1 assumes a reduction in the allowable secondary stress range if more than 7,000 full-range thermal cycles are expected in a design lifetime. Section 4.3.5 describes the evaluation of these cyclic design TLAAs. The main steam safety valves are ASME III Class 2 components designed with a Class 1 fatigue analysis. Section 4.3.2.12 describes the evaluation of this TLAA. 3.4.2.2.2 Loss of Material due to General, Pitting, and Crevice Corrosion 3.4.2,2.2.1 Steel piping and components, tanks, and heat exchangers exposed to treated water and steel piping and components exposed to steam The Water Chemistry plrogram (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage loss of material due to general, pitting, and crevice corrosion for carbon steel and gray cast iron components exposed to secondary water and demineralized water. The one-time inspection will include selected components at susceptible locations where contaminants could accumulate (e.g. stagnant flow locations). 3.4.2,2.2.2 Steel piping and components exposed to lubricating oil The Lubricating Oil Analysis program (B2.1.23) and the One-Time Inspection program (B2.1.16) will manage loss of material due to general, pitting, and crevice corrosion for carbon steel components exposed to lubricating oil. The one-time inspection will include selected components at susceptible locations where contaminants such as water could accumulate. Palo Verde Nuclear Generating Station Page 3.4-5 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM 3.4.2.2.3 Loss of Material due to General, Pitting, Crevice, and Microbiologically-Influenced Corrosion (MIC), and Fouling Not applicable. PVNGS has no in-scope components exposed to raw water in the auxiliary feedwater system, so the applicable NUREG-1 801 line was not used. 3.4.2.2.4 Reduction of Heat Transfer due to Fouling 3.4.2.2.4.1 Stainless steel and copper alloy heat exchanger tubes exposed to treated water Not applicable. PVNGS has no in-scope heat exchangers in the condensate or blowdown systems, and no in-scope heat exchangers with a heat transfer intended function in the auxiliary feedwater system, so the applicable NUREG-1801 lines were not used. 3.4.2.2.4.2 Stainless steel and copper alloy heat exchanger tubes exposed to lubricating oil The Lubricating Oil Analysis program (B2.1.23) and the One-Time Inspection program (B2.1.16) will manage reduction of heat transfer due to fouling for carbon steel and copper alloy components exposed to lubricating oil. The one-time inspection will include selected components at susceptible locations where contaminants such as water could accumulate. 3.4.2.2.5 Loss of Material due to General, Pitting, Crevice, and Microbiologically-Influenced Corrosion 3.4.2.2.5.1 Steel piping and components and tanks exposed to soil Not applicable. PVNGS has no in-scope buried steel components or tanks exposed to soil in the condensate or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.2.2.5.2 Steel heat exchanger components exposed to lubricating oil The Lubricating Oil Analysis program (B2.1.23) and the One-Time Inspection program (B2.1.16) will manage loss of material due to general, pitting, crevice and microbiologically influenced corrosion for carbon steel components exposed to lubricating oil. The one-time inspection will include selected components at susceptible locations where contaminants such as water could accumulate. 3.4.2.2.6 Cracking due to Stress Corrosion Cracking The Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage cracking due to stress corrosion cracking for stainless steel components exposed to secondary water. The one-time inspection will include selected components at susceptible locations where contaminants could accumulate (e.g. stagnant flow locations). Palo Verde Nuclear Generating Station Page 3.4-6 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM 3.4.2.2.7 Loss of Material due to Pitting and Crevice Corrosion 3.4.2.2.7.1 Stainless steel and copper alloy piping and components and stainless steel tanks and heat exchangers exposed to treated water The Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage loss of material due to pitting and crevice corrosion for stainless steel and copper alloy components exposed to secondary water and demineralized water. The one-time inspection will include selected components at susceptible locations where contaminants could accumulate (e.g. stagnant flow locations and tank bottoms). 3.4.2.2.7.2 Stainless steel piping and components exposed to soil Not applicable. PVNGS has no in-scope stainless steel components exposed to soil in the condensate or auxiliary feedwater system, so the applicable NUREG-1801 lines were not used. 3.4.2.2.7.3 Copper alloy piping and components exposed to lubricating oil Not applicable. PVNGS has no in-scope copper alloy components exposed to lube oil in the steam turbine, feedwater, condensate, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.2.2.8 Loss of Material due to Pitting, Crevice, and Microbiologically-Influenced Corrosion Not applicable. PVNGS has no in-scope stainless steel components exposed to lube oil in the steam turbine, feedwater, condensate, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.2.2.9 Loss of Material due to General, Pitting, Crevice, and Galvanic Corrosion Not applicable to PVNGS, applicable to BWR only. 3.4.2.2.10 Quality Assurance for Aging Management of Nonsafety-Related Components Quality Assurance Program and Administrative Controls are discussed in Section B13.3. 3.4.2.3 Time-Limited Aging Analysis The time-limited aging analyses identified below are associated with the Steam and Power Conversion System component types. The section within Chapter 4, Time-Limited Aging Analyses, is indicated in parenthesis. Palo Verde Nuclear Generating Station Page 3.4-7 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Cumulative fatigue damage (Section 4.3, Metal Fatigue Analysis) 3.4.3 Conclusions The Steam and Power Conversion System component types that are subject to aging management review have been evaluated. The aging management programs selected to manage the aging effects for the Steam and Power Conversion System component types are identified in the summary Tables and in Section 3.4.2.1. A description of these aging management programs is provided in Appendix B, along with a demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstration provided in Appendix B, the effects of aging associated with the Steam and Power Conversion System component types will be adequately managed so that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. Palo Verde Nuclear Generating Station Page 3.4-8 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion 6.4.1.U I teei piping, piping iuumuiative Taugue aamage I LA-, evaiuaea in Fatigue of metal components is components, and accordance with 10 CFR a TLAA. piping elements 54.21(c) See further evaluation in exposed to steam or subsection 3.4.2.2.1. _treated water 3.4.1.02Steel piping, piping Loss of material due to Water Chemistry (B2.1.2 V Yes Not applicable. PVNGS has no components, and ;general, pitting and crevice and One-Time Inspection in-scope steel components piping elements corrosion (B2.1.16) exposed to steam in the steam exposed to steam turbine or extraction steam systems, so the applicable NUREG-1801 lines were not used. 3.4.1.03 Steel heat exchanger ILoss of material due to Water Chemistry (B2.1.2) Yes Consistent with NUREG-1801.
'components exposed igeneral, pitting and crevice and One-Time Inspection See further evaluation in Ito treated water corrosion (B2.1.16L ......... subsection 3.4.2.2.2.1.
3.4.1.04 'Steel piping, piping ILoss of material due to iWater Chemistry (B2.1.2) Yes Consistent with NUREG-1801. components, and general, pitting and crevice and One-Time Inspection See further evaluation in piping elements corrosion (B2.1.16) subsection 3.4.2.2.2.1. exposed to treated Iwater _ __ 3.4.1.05 1 t Notapplable - BWR only Palo Verde Nuclear Generating Station Page 3.4-9 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion
.q(tuctam 1('ntinlItcH}
Steel and stainless ILoss of material due to generzil IWater Chemistry (B2.1.2) Consistent with NUREG-1 801. steel tanks exposed to (steel only) pitting and crevice !and One-Time Inspection See further evaluation in treated water 1corrosion subsection 3.4.2.2.7.1. 3.4.1.07 Steel piping, piping ,Loss of material due to Lubricating Oil Analysis Yes Consistent with NUREG-1 801 components, and ,general, pitting and crevice i(B2.1.23) and One-Time with aging management piping elements !corrosion Inspection (B.2.1.16) program exceptions. exposed to lubricating The aging management oil program(s) with exceptions to NUREG-1801 include: Lubricating Oil Analysis (B2.11.23). See further evaluation in subsection 3.4.2.2.2.2. 3.4.1.08 Steel piping, piping ILoss of material due to !A plant-specific aging Yes Not applicable. PVNGS has no components, and .igeneral, pitting, crevice, and management program is to in-scope steel components piping elements ,microbiologically-influenced be evaluated. exposed to raw water in the exposed to raw water icorrosion, and fouling I auxiliary feedwater system, so the applicable NUREG-1801 line was not used. Palo Verde Nuclear Generating Station Page 3.4-10 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion itainiess steei ana -eauction oT neat transter cue vvater unemistry (8z.L1.z) Not applicable. PVNGS has no copper alloy heat to fouling and One-Time Inspection in-scope stainless steel or exchanger tubes (B2.1.16) copper alloy heat exchangers exposed to treated exposed to treated water in the water condensate, steam generator blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.1.10 Steel, stainless steel, Reduction of heat transfer due Lubricating Oil Analysis ý_Yes Consistent with NUREG-1801 - and copper alloy heat to fouling (B2.1.23) and One-Time with aging management exchanger tubes Inspection (B.2.1.16) program exceptions. exposed to lubricating The aging management oil program(s) with exceptions to NUREG-1801 include: Lubricating Oil Analysis (B2.11.23). See further evaluation in subsection 3.4.2.2.4.2. 3.4.1.11 Buried steel piping, Loss of material due to Piping and Tanks
'Buried Yes Not applicable. PVNGS has no piping components, general, pitting, crevice, and Inspection (B2 .1.18) in-scope buried steel piping elements, and 1microbiologically-influenced components or tanks exposed tanks (with or without corrosion to soil in the condensate or coating or wrapping) auxiliary feedwater systems, so exposed to soil the applicable NUREG-1801
... ................
....... lines were not used.
Palo Verde Nuclear Generating Station Page 3.4-11 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion Svstem (Continued) Steel heat exchanger Loss of material due to Lubricating Oil Analysis Consistent with NUREG-1801 components exposed !general, pitting, crevice, and (B2.1.23) and One-Time with aging management to lubricating oil microbiologically-influenced Inspection (B.2.1.16) program exceptions. corrosion The aging management program(s) with exceptions to NUREG-1801 include: Lubricating Oil Analysis ((B2.1.23). See further evaluation in subsection 3.4.2.2.5.2. 3.4.1.13-3 ,Not applicable - BWR only 13.4.1.14 Stainless steel piping, Cracking due to stress Water Chemistry(B2.1.2) Yes !Consistent with NUREG-11 801. piping components, corrosion cracking and One-Time Inspection See further evaluation in piping elements, tanks, (B2.1.16) subsection 3.4.2.2.6. and heat exchanger components exposed to treated water >60'C (>140-F) 3.4.1.151 Aluminum and copper Loss of material due to pitting Water Chemistry (B2.1.2) Yes 7Consistent with NUREG-1801. alloy piping, piping .and crevice corrosion and One-Time Inspection See further evaluation in components, and (B2.1.16) subsection 3.4.2.2.7.1. piping elements exposed to treated
!water Palo Verde Nuclear Generating Station Page 3.4-12 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion
.(:Z/_Qfrnm I.r~nfinitinril e~r Discussion Jlon mded Stainless steel piping, Water Chemistry (B2.1.2) Consistent with NUREG-1801.
piping components, and One-Time Inspection See further evaluation in and piping elements; (B2.1.16) subsection 3.4.2.2.7.1. tanks, and heat exchanger components exposed to treated water 3.4.1.17 Stainless steel piping, Loss of material due to pitting A plant-specific aging Yes Not applicable. PVNGS has no6-piping components, land crevice corrosion management program is to in-scope stainless steel
,and piping elements be evaluated. components exposed to soil in.
exposed to soil the condensate or auxiliary feedwater system, so the applicable NUREG-1801 lines were not used. ý3.4.1.18 Copper alloy piping, Loss of material due to pitting 'Lubricating Oil Analysis Yes Not applicable. PVNGS has no piping components, and crevice corrosion (B2.1.23) and OneTime in-scope copper alloy and piping elements Inspection (B.2.1.16) components exposed to lube exposed to lubricating oil in the steam turbine, oil feedwater, condensate, or auxiliary feedwater systems, so the applicable NUREG-1801 nes were not used. Palo Verde Nuclear Generating Station Page 3.4-13 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIfI of NUREG-1801 for Steam and Power Conversion i.4.1 .1i Itainiess steei piping, LOSS Or matenai aue to piting, LuDricating u1I /Anaiysis Noi appncaoie. r-vruo nas no piping components, crevice, and microbiologically- (B2.1.23) and One-Time in-scope stainless steel 1piping elements, and Influenced corrosion Inspection (B.2.1.16) components exposed-to lube Sheat exchanger oil in the steam turbine, components exposed feedwater, condensate, or to lubricating oil auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. See further evaluation in subsection 3.4.2.2.8. 3.4.1.20 Steel tanks exposed to Loss of material/ general, Aboveground Steel Tanks No Not applicable. PVNGS has no air - outdoor (external) pitting, and crevice corrosion in-scope steel tanks exposed to outdoor air in the condensate or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.1.21 High-strength steel ;Cracking due to cyclic loading, iBolting Integrity (B2.1.7) Not applicable. PVNGS has no closure bolting Istress corrosion cracking in-scope high strength bolting exposed to air with in the steam and power steam or water conversion systems, so the leakage applicable NUREG-1801 line was not used. Palo Verde Nuclear Generating Station Page 3.4-14 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter V1II of NUREG-1801 for Steam and Power Conversion Svstem (Continued) .j.4.1i.zz iz.)eei DOaing ana j LOSS OT materlai aue to DI l[iFig iniyerity tkD/. i.1) l,.,UII ILVIIL b WILII IlL rl'- - IOU I
!closure bolting general, pitting and crevice with aging management exposed to air with scorrosion; loss of preload due program exceptions.
steam or water to thermal effects, gasket The aging management leakage, air - outdoor creep, and self-loosening program(s) with exceptions to (external), or air - NUREG-1801 include: Bolting. indoor uncontrolled Integrity (B2.1.7) (external); 3.4.1.23 Stainless steel piping, 'Cracking due to stress Closed-Cycle Cooling No Not applicable. PVNGS has no piping components, corrosion cracking Water System (B2. 1.10) in-scope stainless steel and piping elements components exposed to closed exposed to closed- cycle cooling water >140'F in cycle cooling water the condensate, blowdown, or
>60'C (>140 0 F) auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used.
3.4.1.24 Steel heat exchanger Loss of material due to Closed-Cycle Cooling No Consistent with NUREG-1 801 components exposed general, pitting, crevice, and Water System (B2.1.10) with aging management to closed cycle cooling galvanic corrosion program exceptions. water The aging management program(s) with exceptions to NUREG-1801 include: Closed-Cycle Cooling Water System (B2.1.10) Palo Verde Nuclear Generating Station Page 3.4-15 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion System (Continued) Stainless steel piping, Loss ot material due to pitting %,UII IOLUIILLWILII II F' - VlU- I piping components, and crevice corrosion ;Water System (B2. 1.10) with aging management piping elements, and program exceptions. Sheat exchanger The aging management IcomDonents exDosed program(s) with exceptions to i to closed cycle cooling NUREG-1801 include: Closed-water Cycle Cooling Water System (g2. 1.10) 3.4.1.26 tCopper alloy piping, Loss of material due to pitting, Closed-Cycle Cooling No Not applicable. PVNGS has no piping components, Icrevice, and galvanic corrosion Water System (B2.1.10) in-scope copper alloy and piping elements components exposed to closed exposed to closed cycle cooling water in the cycle cooling water condensate, blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.1.27 Steel, stainless steel, Reduction of heat transfer due :Closed-Cycle Cooling No Not applicable. PVNGS has no and copper alloy heat ito fouling Water System (B2.1.10) in-scope copper alloy exchanger tubes components exposed to closed exposed to closed cycle cooling water in the cycle cooling water condensate, blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. Palo Verde Nuclear Generating Station Page 3.4-16 License Renewal Application
.Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion
.v.Oi-m (flnntintio.d)
Steel external surfaces j Loss of material due to gen External Surfaces *JUIIOIOLVI IIL WIL.II IN.rFr-*- I OV I exposed to air- indoor Icorrosion Monitoring (B2.1.20) with aging management uncontrolled (external), program exceptions. condensation The aging management (external), or air program(s) with exceptions to Ioutdoor (external) NUREG-1801 include: External Surfaces Monitoring Program (B2.1*20). 3.4.1.29 Steel piping, piping Wall thinning due to flow- Flow-Accelerated No Consistent with NUREG-1801 components, and accelerated corrosion Corrosion (B2.1.6) with aging management piping elements program exceptions. exposed to steam or The aging management treated water program(s) with exceptions to NUREG-1801 include: Flow-Accelerated Corrosion (B2.1 .6) 3.4.1.30 Steel piping, piping !Loss of material due to Inspection of Internal No Consistent with NUREG-1801 components, and ,general, pitting, and crevice Surfaces in Miscellaneous with aging management piping elements 1corrosion Piping and Ducting program exceptions. exposed to air outdoor Components (B2.11.22) The aging management I(internal) or program(s) with exceptions to condensation (internal) NUREG-1801 include: External Surfaces Monitoring Program (B2.1.20 . Palo Verde Nuclear Generating Station Page 3.4-17 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion System (Continued) Steel heat exchanger ,Loss of material due to Open-Cycle Cooling Water IIU Not applicable. PVNGS has no components exposed ,general, pitting, crevice, System (B.2.1.9) in-scope steel heat exchanger to raw water Igalvanic, and microbiologically- components exposed to raw
!influenced corrosion, and water in the condensate, ifouling blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines of material due to pitting, .Loss Open-Cycle Cooling Water were not used.
3.4.1.32 1Stainless steel and No Not applicable. PVNGS has no copper alloy piping, .crevice, and microbiologically- System (B.2.1.9) in-scope stainless steel or i piping components, influenced corrosion copper alloy components and piping elements exposed to raw water in the exposed to raw water steam turbine, condensate, blowdown, or auxiliary - feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.1.33lStainless steel heat Loss of material due to pitting, Open-Cycle Cooling Water No Not applicable. PVNGS has no
!exchanger ,crevice, and microbiologically- System (B.2.1.9) in-scope stainless steel heat components exposed influenced corrosion, and exchanger components to raw water fouling exposed to raw water in the condensate, blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used.
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Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion Svstem (Continued) Steel, stainless steel, Reduction of heat transfer due Open-Cycle Cooling Water I0UL dPPilUduI,. r"VlN%.4 h]dZ5 Flu and copper alloy heat .to fouling ;System (B.2.1.9) in-scope heat exchanger exchanger tubes components exposed to raw exposed to raw water water in the condensate, blowdown, or auxiliary feedwater systems, so the applicable NUREG-1801 lines were not used. 3.4.1.35 Copper alloy >15% Zn !Loss of material due to Selective Leaching of No Consistent with NUREG-1 801 piping, piping Iselective leaching Materials (B2.1.17) with aging management components, and program exceptions. piping elements The aging management exposed to closed program(s) with exceptions to cycle cooling water, NUREG-1801 include: raw water, or treated Selective Leaching of Materials water (B2.1 .17) 3.4.1.3( 6 Gray cast iron piping, Loss of material due to Selective Leaching of No Consistent with NUREG-1801 piping components, selective leaching Materials (B2.1.17) with aging management and piping elements program exceptions. exposed to soil, treated! The aging management water, or raw water program(s) with exceptions to NUREG-1801 include: Selective Leaching of Materials (132.1.17 _ _ _ _ Palo Verde Nuclear Generating Station Page 3.4-19 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion 3.4.1.31 steel, stainless steel, Loss of material due to 11O and nickel-based alloy land crevice corrosion piping, piping
!components, and
,piping elements exposed to steam 3...8Steel bolting and Loss of material due to boric Boric Acid Corrosion No Not applicable. PVNGS has no external surfaces acid corrosion ;(B2.1.4) in-scope steel components exposed to air with exposed to borated water borated water leakage leakage in the steam and power conversion systems, so the applicable NUREG-1801 lines were not used.
No Consistent with NUREG-1801. 3.4.1.39 Stainless steel piping, !Cracking due to stress IWater Chemistry (B.2.1.2) piping components, corrosion cracking and piping elements exposed to steam 3.4.1.40 Glass piping elements 1None None No Consistent with NUREG-1801. exposed to air, lubricating oil, raw water, and treated water Palo Verde Nuclear Generating Station Page 3.4-20 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.1 Summary of Aging Management Evaluations in Chapter VIII of NUREG-1801 for Steam and Power Conversion Svstem (Continued) i.4..i bziainiess steel, copper i'one alloy, and nickel alloy piping, piping components, and piping elements exposed to air- indoor uncontrolled (external) 3ý.4^.1.42 Stee piping, piping None None Not applicable. PVNGS has no components, and in-scope steel components piping elements exposed to indoor controlled air exposed to air - indoor in the steam and power controlled (external) conversion systems, so the applicable NUREG-1801 line was not used.
+
3.4.1.43 Steel and stainless None None No Consistent with NUREG-1801. steel piping, piping components, and piping elements in i concrete _ i -F 3:4.1.44 Steel, stainless steel, None None No Consistent with NUREG-1801. aluminum, and copper alloy piping, piping components, and piping elements exposed to gas Palo Verde Nuclear Generating Station Page 3.4-21 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM fury Uas ý lilt I________ Plant Indoor Air jLoss of material External Surfaces VIII.H-7 :3.4.1.28 (Ext) Monitoring Program (B2.1.20) _ Closure Bolting LBS, PB, Carbon Steel Plant Indoor Air ILoss of material Bolting Integrity (B2.1.7) VIII.H-4 13.4.1.22 B SIA Closure Bolting LBS, PB, Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) [VIII.H-5 13.4.1.22 SIA (Ext) "_" Closure Bolting LBS, PB, Stainless Plant indoorAir Loss of preload Bolting Integrity (B2.1.7) None 'None IG,1 SIA Steel (Ext) ofmtra LBS, SIA Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 13.4.1.28 B (Ext) Monitoring Program (B2.1.20) Fiter LBS, SIA Carbon Steel Secondary Water I Loss of material Water Chemistry VIII.B1-11 3.4.1.04 A (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Flexible Hoses PB ;Nicke Alloys DDy Gas (Int) None None None None G Flexible Hoses PB INickel Alloys Plant Indoor Air None None V.F-11 3.2.1.53 A (Ext) Flexible Hoses Nickel Alloys Secondary Water Loss of material Water Chemistry VIII.B1-1 !3.4.1.37 (Int) _ (B2.1.2)
* & , I iNone IV.F-2 13.2.1.50
- Insulation INS Plant Indoor Air None C Aluminum (Ext) _
....I
...........
...
..
.....
Palo Verde Nuclear Generating Station Page 3.4-22 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAMAND POWER CONVERSION SYSTEM Table 3.4.2-1 Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System I11Cac IOUICILIUI I None Calcium (Ext) _________ jSilicate Orifice PB, TH Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 B (Ext) Monitoring Program (B2.1.20) . ____. Orifice PB, TH ICarbon Steel Secondary Water Loss of material Water Chemistry VIII.B1-1 1 3.4.1.04 [A (Int) (B2.1.2) and One-Time Inspection (B2.1.16) LBS, PB, Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 13.4.1.28 B SIA (Ext) I Monitoring Program (B2.1.20) Piping LBS, PB, Carbon Steel Secondary Water Loss of material Water Chemistry VIII.1B1-8 13.4.1.37 A SIA _ (Int) (B2.1.2) Piping LBS, PB, _Carbon Steel Secondary Water Wall thinning Flow-Accelerated VIII.B1-9 i3.4.1.29 B SIA Co!rrosion (132.1.6) Piping PB Carbon Steel Secondary Water Cumulative Time-Limited Aging VIII.B1-10 3.4.1.01 (Int) fatigue damage Analysis evaluated for the period of extended A operation Piping LBS, PB, iCarbon Steel Secondary Water Loss of material VIII.B31-1 1 13.4.1.04 Water Chemistry SIA (Int) (B2.1.2) and One-Time InspectionB2-.1.16) Palo Verde Nuclear Generating Station Page 3.4-23 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-1 Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System (Continued) LIt5, [spe5UL U1 IILrrldi nIU1 VII.D 1-1 1.'-. 0.oU SIA Surfaces In Miscellaneous Piping And Ducting Components (32.1.22) Piping SIA Copper Alloy Dry Gas (lnt) :None None VlII1.I-3 3.4.1.44 A Piping SIA Copper Alloy Plant Indoor Air None None VII1-2 13.4.1.41 A (Ext) Stainless Dry Gas (Int) None None VIII -12 i3.4.1.44 A Piping PB, Steel Piping LBS, PB, Stainless Plant Indoor Air None None 1V11.-10 13.4.1.41 A i' ! ______ SIA Steel (LEXt)_____, Piping SIA PB, ILBS, Stainless Secondary Water Cracking Water Chemistry VillI B1-2 3.4.1.39 A SIA Steel (Int) LB2.1.2)?) Loss of material Piping LBS, PB, Stainless Secondary Water Water Chemistry ;VIII.B1-3 3.4.1.37 A SIA Steel (Int) Loss of material (B2.1.2) ........... Piping LBS, PB, Stainless Secondary Water Water Chemistry VIII.B1-4 13.4.1.16 A SIA Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.16) -A P'i p ing LBS, PB, Stainless Secondary Water Cracking Water Chemistry VIII.B1 -5 13.4.1.14 A SIA Steel (Int) (B2.1.2) and One-Time i Inspection (B2.1.116) 1 Piping [SIA Stainless Wetted Gas (Int) Loss of material Inspection Of Internal iV.D1-29 3.2.1 .08 E Steel Surfaces In I Miscellaneous Piping And Ducting Components (B2.1.22) _ _....... __ Palo Verde Nuclear Generating Station Page 3.4-24 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-1 Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System (I.nntintip.il Steel (Ext t Pump LBS, SIA Stainless Secondary Water Loss of material Water Chemistry TVIII.B1-4 13.4.1.16 A Steel (Int) (B2.1.2) and One-Time Inspection B12.1.16)J____ Tubing PB Copper Alloy D_ Gas Int) .... None None IVIII.I-3 13.4.1.44 A Tubing PB Copper Alloy Plant Indoor Air None None IVIII.I-2 3.4.1.41 A (Ext) Tubing PB Stainless Dry Gas (Int) - None None V i1i.-1.-2 3.4.1.44 A Steel Tubing PB Stainless Plant Indoor Air -None None V,,,.1-10 3.4.1.41 A Steel (Ext). . ..... _ Tubing PB Stainless Secondary Water ILoss of material Water Chemistry VI.B1-4 t.31.16 A Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.16) _ Tubing Stainless Secondary Water Cracking Water Chemistry TVIII.B1-5 3.4.1.14 A Steel (Int) (B2.1.2) and One-Time i Inspection (B2.1.16) LBS, PB, Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 B SIA (Ext) Monitoring Program i .Valve I ~ ~W~bn Stee Secondary Water Loss of material Water Chemistry -VIII.1B1-8 13.4.1.37 A (Int) (B2.1.2) 1 _ Valve IPB 7 Carbon Steel Secondary Water (Int) Wall thinning _________ Flow-Accelerated Corrosion (B2.1.6) J VIII.B1-9 _ 3.4.1.29 Palo Verde Nuclear Generating Station Page 3.4-25 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-1 Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System (('ontintied) beconcaary cumulative Time-Limited Aging :VIII.B13-10 (Int) 1fatigue damage Analysis evaluated for the period of extended operation _ Water Valve LBS, PB, Carbon Steel Secondary Secondary Water i Loss of material Water Chemistry IVIII.B1-11 3.4.1.04 TA SIA (Int) (B2.1.2) and One-Time
-Inspection (B2.1.16)______
Valve LBS, PB, Carbon Steel Wetted Gas (Int) Loss of material Inspection Of Internal VIII.B1-7 13.4.1.30 1B SIA Surfaces In Miscellaneous Piping And Ducting Components (B2.1.22) _ Valve PB Copper Alloy Dry Gas (Int) None None VIII.v1-3 3.4.1.44 TA (Zinc >15%) I Valve PB [Copper Alloy Plant Indoor Air . None None vII11.-2 :3.4.1.41 FA (Zinc >15%[ Valve PB Stainless Dry Gas (Int) ~None None Vlll.l-12 3.4.1.44 A
, _ _ Steel Valve 1PB, SIA Stainless Plant Indoor Air None None VIIlI.-10 13.4.1.41 A Steel (Ext)
'PB Stainless Secondary Water !Cracking- Wate r Chemistry :VIII.B1-2 3.4.1.39 A Steel .(B2.1 I r2) . . ..... iVIII.B1-3 13.4.1.37 A Valve IBPB Stainless Secondary Water !Loss of material Wate,r Chemistry Steel (Int) i (B2.1 .2)
Valve PB Stainless Secondary Water Loss of material Water Chemistry VIII.B1-4 13.4.1.16 A Steel (Int) (B2.1.2) and One-Time Ins.pection _B2.1.16 Palo Verde Nuclear Generating Station Page 3.4-26 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-1 Steam and Power Conversion System - Summary of Aging Management Evaluation - Main Steam System (Continued) Component Intended Material, ~Efironment ,Aging Effect ~Aging Management NUREG-~ Table 1 Item Notes Type Function Req~uiring, Programw. 1801 Vol. '~ Management 2 Item Valve PB Stainless Secondary Water Cracking Water Chemistry VIII.B1-5 3.4.1.14 A Steel (Int) (B2.1.2) and One-Time Ve~Atiesn o fInspection (1B2.1.16)_____ V-alv SIA Stainless Wetted Gas (Int) loss of material Inspection Of Internal V.D1- 29 3.2.1.08 -E Steel Surfaces In Miscellaneous Piping I And Ducting
, 1Components B2.1.22)
Notes for Table 3.4.2-1: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1 801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect; but a different aging management program is credited or NUREG-1 801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 NUREG-1801 does not consider mechanical insulation. The thermal insulation in-scope for license renewal is located in areas with non-aggressive environments (the insulation is not exposed to contaminants). Based on the review of the SERs of recent license renewal applications (Millstone, Dresden and Quad Cities, Cook, ANO-2, and Robinson) and review of the site operating experience, stainless steel insulation, closed cell foam, quilted fiberglass insulation, calcium silicate and insulation jacketing in non-aggressive environments have no aging effects requiring management. Palo Verde Nuclear Generating Station Page 3.4-27 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-2 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and Trmn efr .Qiefcrm
%.,dIUUI I .)LUCI /-LI I IU*II I*l*/ I LUL UI IUILII* 5IllUI I* I1UIVI.
Weather (Ext) preload Integrity
--1
_______ ____ __ ____ _ (132.1.7)_ _ _ _ _ Closure Boltingi LBS, SIA Carbon Steel !Atmosphere/ Loss of 'Bolting VI i.H-1 3.4.1.22 ýB Weather (Ext) material Integrity Closure Bolting LBS, PB, SIA Carbon Steel Plant Indoor Air (Ext) Loss of material I
!Bolting Integrity
'VIII.H-4 3.4.1.22
"(B2.1.7) 1B I
_ _ _ _ __ __ (B2.1.7) _ _ Closure Bolting6LBS, PB, SIA Closure Bolting1LBS, PB, SIA Carbon Steel Plant Indoor Air (Ext) Stainless Steel Plant Indoor Air (Ext) _ ____ _ _ _ Loss of preload Loss of preload Bolting Integrity (B2.1.7) Bolting Integrity 1VIII.H-5 1None 3.4.1.22 None 1B G,1 __I I _____(B2.1.7) _ _ _ Flow Element PB Stainless Steel Plant Indoor None None !VIII.J-10 3.4.1.41 IA e Air
........
..........................................
I.....staii ~e (Ext)....
....... .......
cia......... w ater............................ Flow Element PB Steel Secondary Wless Loss of VllI.E-29 3.4.1.16 :A Water (Int) material Chemistry (B2.1.2) and One-Time Inspection
.(B2.1.16) . .
Palo Verde Nuclear Generating Station Page 3.4-28 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-2 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and TransferSvstem (Continued)
)rifice Lainiess oieei -'riant inaoor SINlrle vii.I- IU 4.1.41 M
__________Air (Ext) Orifice iPB tainless Steel Secondary iWater IVIII.E-29 3.4.1.16 A Water (Int) Imaterial Chemistry (B2.1.2) and One-Time Inspection (B2.1.16) Piping i Carbon Steel Plant Indoor Loss of External 3.4.1.28 B Air (Ext) material Surfaces Monitoring Program (B2.1.20) Ppng LBS, SIA Water VIII. E-34 3.4.1.04 A material Chemistry (B2.1.2) and One-Time Inspection (B2.1.16) Pip9ig PB, SIA Stainless Steel Atmosphere/ None None 1None None 4G
,sS Weather (Ext)-I Piping 1PB Stainless Steel Encased in None None VI11.1-11 3.4.1.43 A B PConcrete (Ext)
Piping LBS, PB, SIA Stainless Steel Plant Indoor iNone None !Vll.l1-10 3.4.1.41 1A
...
............
j ..... . . . ..* . . . . . . .. Air (Ext)_ _ _ Palo Verde Nuclear Generating Station Page 3.4-29 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-2 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and "Iron efr .(ucfrnm 1('nnfint ijH) IoLUI lIUCi y VY VLVI 3.4.1.16 Water (Int) Chemistry (B2.1.2) and One-Time Inspection (B2.1.16) Ppng PB, SIA Stainless Steel Wetted Gas Loss of Inspection Of IV.Dl-29 3.2.1.08 E (Int) material Internal Surfaces In Miscellaneous Piping And Ducting Components 4 4 (B2.1.22) Pump iPB Stainless Steel Plant Indoor None None VI11. 1-1 0 13.4.1.41- IA P
.......... Cast Austenitic Air (Ext)
Pump iPB Stainless Steel Secondary Water iVIII.E-29 A Loss of 3.4.1.16 Cast Austenitic Water (Int) material Chemistry (B2.1.2) and One-Time Inspection Tank Liner + + (B2.1.16) ---
---
PB Stainless Steel Dry Gas (Int) None None VIII.1-12 3.4.1.44 iA Tank Liner IPB Stainless Steel Encased in None None 3.4.1.43 IC Concrete (Ext) Tank Liner ýPB Stainless Steel Plant Indoor None None VII1.1-10 3.4.1.41 C Air(Ext Palo Verde Nuclear Generating Station Page 3.4-30 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-2 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and Tranc, fnr C-/ot"t r //inn4nn,-lf LUbb UI VVdLul I V III.---'tU Water (IUl oWtUU (Int)y material Chemistry (B2.1.2) and One-Time I Inspection (B2.1.16) Tubing - LBS Stinl-ess Steel Plant Indoor 'None None IVIII.1-10 3.4.1.41 - A (E x) ANiir _ Ti IVIII.E-29 Tubing LBS Stainless Steel Secondary Loss of Water 3.4.1.16 A Water (Int) material Chemistry (B2.1.2) and One-Time Inspection (1B2.1.16) Valve LBS, PB Carbon Steel Plant Indoor Loss of External VIII.H-7 3.4.1.28 1B Air (Ext) material Surfaces Monitoring Program _(B2.1.20) Val1ve -LBS, PB Carbon Steel Secondary Loss of Water VIII.E-34 3.4.1.04 IA Water (Int) material Chemistry (B2.1.2) and One-Time Inspection N3 No2.1.16) Valve LBS, PB, SIA iStainless Steel 'Plant Indoor None VIII.1-10 3.4.1.41 ;A Air (Ext) Palo Verde Nuclear Generating Station Page 3.4-31 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-2 Steam and Power Conversion System - Summaty of Aging Management Evaluation - Condensate Storage and Transfer Svstem (Continued)
*econaary LOSS OT vvater Water (Int) material Chemistry (B2.1.2) and One-Time Inspection (B2.1.16)
Valve ,SIA Stainless Steel Atmosphere/ None None jNone None A Cast Austenitic Weather (Ext) 3.4.1.41A Val-ve Stainless Steel Plant Indoor None None VIlll.1-10 Cast Austenitic Air (Ext) 4 Valve PB Stainless Steel Secondary Loss of Water VIII.E-29 3.4.1.16 A Cast Austenitic Water (Int) Imaterial Chemistry (B2.1.2) and One-Time Inspection (B2.1.16) ______ Valve SIA Stainless Steel Wetted Gas !,Lossof Inspection Of V.D1-29 3.2.1.08 E Cast Austenitic (Int) material Internal Surfaces In Miscellaneous Piping And Ducting Components (B2-1 22*_._ Palo Verde Nuclear Generating Station Page 3.4-32 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Notes for Table 3.4.2-2: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Note: 1 Loss of Preload is considered to be applicable for all closure bolting. Palo Verde Nuclear Generating Station Page 3.4-33 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging ManagementEvaluation - Auxiliary Feedwater Svstem uiosure bolting LbI , 'Ib, Carbon Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.7) iVIII.H-4 3.4.1.22 D _SIA Carbon Steel Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) VIII.H-5 -r3-.4.1.22 B Closure Bolting LBS, PB, _SIA (Ext) _ Closure Bolting LBS, PB, Stainless Plant Indoor Air Loss of preload Bolting Integrity (B2.1.7) None None G, 1 SIA ...........................................
............................................ ...........................................
............................................
l~ iit r....................
...................
1 ..
.........................
Filter PB Aluminum Lubricating Oil Loss of material Lubricating Oil Analysis None None G (Int) (B2.1.23) and One-Time IInspection (B2.1.16) Aluminum Plant Indoor ir None None IV.F-2 3.2.1.50 A _ ~(Ext)___......____ __ _ __ __ __ _ Filter PB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis iVIII.G-3, 5 13.4.1.07 B (Int) (B2.1.23) and One-Time I _____ _____________ ____ _____________ Inspection (132.1.16) _ _ _ Filter IPB Carbon Steel PlantIndoor Air Loss of material External Surfaces VIII.H-7 13.4.1.28 B (Ext) Monitoring Program I l(nB2.1.20) F Flexible Hoses IPB Nickel Alloys Plant Indoor Air None None 'V.F-11 3.2.1.53 (Ext) 4 Flexible Hoses 1PB Nickel Alloys Secondary Water Loss of material Water Chemistry V2.1.1-11 13.4.1.37 A (Int) I(B2.11.2) Flow Element PBTH Stainless Plant Indoor Air None None 'VIII.I-10 '3.4.1.41 A Steel _ _ Ext) .. . , Palo Verde Nuclear Generating Station Page 3.4-34 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem (Continued)
,iiainiess oeconaary vvaier vvaier unemistry VIIILA.-,L .1.. 1 Steel (Int) (B2.1.2) and One-Time I Heat Exchanger (AF HT, PB Carbon Steel Lubricating Oil (Ext)
Loss of material Inspection (B2.1.16) _ Lubricating Oil Analysis VIII.G-6 (B2.1.23) and One-Time 3.4.1.12 I Turbine Oil Inspection (B2.1.16) Cooler) Hea.t HT, PB CarbonnStee Lubricating Oil Reduction of heat Lubricating Oil Analysis VIII.G-15 3.4.1.10 Exchanger (AF (Ext) transfer (B2.1.23) and One-Time Turbine Oil Inspection (B2.1.16) Cooler) Heat JPB Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis IVIII.G-6 3.4.1.12 TB Exchanger (AF (Int) (B2.1.23) and One-Time Turbine Oil Inspection (B2.1.16) Heat. Carbon SteeltPlant Indoor Air Loss of material External Surfaces IVIII.H-7 3.4.1.28 Exchanger (AF (Ext) Monitoring Program Turbine Oil (B2.1.20) Cooler) Heat HT, PB Carbon Steel Secondary Water Reduction of heat Water Chemistry None None Exchanger (AF (Int) transfer (B2.1.2) and One-Time Turbine Oil Inspection (B2.1.16) Cqooer)__ Heat HT, PB Carbon Steel Secondary Water Loss of material Water Chemistry IVIII.G-38 13.4.1.04 Exchanger (AF (Int) (B2.11.2) and One-Time Turbine Oil Inspection (B2.11.16) Cooler) Palo Verde Nuclear Generating Station Page 3.4-35 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem 1('.rmfini i*.f) Insulation INS I Insulation Plant Indoor Air None None None i None Calcium (Ext) [Silicate Orifice PB, THH Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis ýVIII.G-35 3.4.1.07 B (Int) (B2.1.23) and One-Time Inspection (B2.1.16) Orifice PB, TH Carbon Steel Plant indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 (Ext) Monitoring Program (B2.1_.20) . .. . Orifice PB, TH Carbon Steel Secondary Water Loss of material Water Chemistry lVIII.B1-8 3.4.1.37 (Int) S§B2.1. 2)_ __ Orifice PB, TH Carbon Steel Secondary Water Loss of material Water Chemistry VIII.G-38 '3.4.1.04 A (Int) (B2.1.2) and One-Time Inspection (32.1.16). Orifice ]-PB, TH [Stainless Plant Indoor Air i None None VIII.I-10 3.4.1.41 A _ ISteel ,(Extj __ Orifice PB, TH Stainless Secondary Water Loss of material Water Chemistry IVIII.G-32 13.4.1.16 Steel (Int) (B2.1.2) and One-Time i...........
.................
........
... Inspection (B2.1.16)
Orifice PB, TH Stainless Plant Indoor Air None None IVIII1-lO 3.4.1.41 A Steel Cast (Ext)
, _ Austenitic Orifice PB, TH Stainless Secondary Water Loss of material Water Chemistry VIII.G-32 13.4.1.16 A Steel Cast (Int) (B2.1.2) and One-Time
.Austenitic Inspection (B2.1. 16)
Palo Verde Nuclear Generating Station Page 3.4-36 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem (Int) B2.1.23) and One-Time nspection (B2.1.16) _ Piping LBS, PB, Carbon Steel Plant Indoor Air Loss of material xternal Surfaces VIII.H-7 3.4.1.28 B SIA I(Ext) Aonitoring Program 32.1.20 A Piping ]PB Carbon Steel Secondary Water Loss of material Vater Chemistry VIII.B1-8 3.4.1.37 (Int). B2.1.2) Piping PB Carbon Steel Secondary Water Wall thinning low-Accelerated VIII.B1-9 13.4.1.29 B (Int) :orrosion (B2.1.6) ___ Piping PB Carbon Steel Secondary Water Cumulative ime-Limited Aging IVIII.G-37 3.4. 1.01 (Int) fatigue damage nalysis evaluated for he period of extended peration Pi~ping LBS, SIA jCarbon Steel Secondary Water Loss of material /ater Chemistry ýVIII.G-38 3.4.1.04 A (Int) B2.1.2) and One-Time nspection (B2.1.16 Piping LBS, PB, Stainless Plant Indoor Air None lone VIII.l-10 13.4.1.41 SIA Steel (Ext) Piping LBS, PB, Stainless Secondary Water i Loss of mnaterial Water Chemistry VIII.G-32 13 4 1.16 A SIA Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.16) _ Pump PB I Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis IVIII.G-35 3.4.1.07 B (Int) (B2.11.23) and One-Time InsDection (B2.1.16) I
+ . . ______ ________ +
Pump 1PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H-7 3.4.1.28 B (Ext) Monitoring Program (B2.1.20) _ Palo Verde Nuclear Generating Station Page 3.4-37 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem tPB !Stainless Plant Indoor Air None 3.4.1.41 Steel Cast (Ext) I Austenitic Pump *PB Stainless Secondary Water Loss cif material Water Chermistry VIII.G-32 3.4.1.16 Steel Cast (Int) (B2.1.2) and One-Time lAustenitic Inspecti( ILBS Sight Gauge LBS IGlass Plant Indoor Air None None VIII.l-5 13.4.1.40 A SExt)condar WtrN - VIII_I-4_"A ! ,,1 An Secondary Water [None INcnn* Sight Gauge Glass A Strainer LBS, SIA [Carbon Stee Plant Indoor Air Loss of material External Surfaces VTIII.H-7 3.4.1.28 B (Ext) Monitoring Program TB2.1.20)L LBS, SIA ICarbon Steel Secondary Water Loss of material Water Chemistry IVIII.G-38 13.4.1.04 A (Int) (B2.1.2) and One-Time STrbing Inspection (B2.1.16) . . ... __ .. TLoss of material Lubricating Oil Analysis VIII.G-35 3.4.1.07 B Carbon Steel Lubricating Oil (Int) (B2.1.23) and One-Time I Inspection (B2.1.16) ....... Tubing PB Carbon Steel Plant Indoor Air ILoss of material External Surfaces VIII.H-7 3.4.1.28 (Ext) Monitoring Program B2.1__20 _ _ _ _ _ _ _ _ Tubing Stainless Plant Indoor Air INone None jVIII.I-10 13.4.1.41
.(Exo) _ _ _
Steel Tubing Stainless Secondary Water Loss of material Water Chemistry TVIII.G-32 13.4.1.16 Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.16 Palo Verde Nuclear Generating Station Page 3.4-38 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem (C..nfintipri) Plant Indoor LOSS Ot ma External Surfaces (Ext) Monitoring Program (B2. 1.2 0)ý Turbi~ne Carbon Steel [Secondary Water ]Loss of material Water Chemistry VIII.B1-8 13.4.1.37 (Int) IVIII. B1-9 B Turbine PB Carbon Stee Secondary Water Wall thinning Flow-Accelerated 13.4.1.29 (Int _________ Corrosion (B2.1.6) Valve Carbon Steel Lubricating Oil Loss of material Lubricating Oil Analysis IVIII.G-35 13.4.1.07 B (Int) (B2.1.23) and One-Time I Inspection B2.1.16) __ Valve LBS, PB, iCarbon Steel Plant Indoor Air !Loss of material External Surfaces VIII .H-7 13.4.1.28 B6 SIA (Ext) Monitoring Program (B2.1.20) _ __ _ Valve LBS, PB, Carbon Steel Secondary Water rLoss of material Water Chemistry 1VIII.B1-8 13.4.1.37 A SIA (Int). __ _ _ _ _ _ _ (B2.1.2) I Valve PB Carbon Steel Secondary Water IWall thinning Flow-Accelerated IVIII.B1-9 3.4.1.29 (Int) Corrosion (B2.1.6) I Valve LBS, PB, Carbon Steel Secondary Water Loss of material Water Chemistry IVIII.G-38 3.4.1.04 A SIA (Int) (B2.1.2) and One-Time Inspection (B2.1.16) Valve PB Cast Iron Lubricating Oil 'Loss of material Lubricating Oil Analysis iVIII.G-35 13.4.1.07 (Int) (B2.1.23) and One-Time I! Inspection (B2.1.16) I Valve PB Cast Iron Plant Indoor Air ,Loss of material External Surfaces IVIII.H-7 3.4.1.28 B (Ext) Monitoring Program Valve LBS, PB, Stainless Plant Indoor Air !None None 1VIII.I-10 3.4.1.41 A SIA SStee.l (Ext) ___ Palo Verde Nuclear Generating Station Page 3.4-39 License Renewal Application
Section 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Table 3.4.2-3 Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary FeedwaterSystem (Continued) Component Intended ~liMaterial* K Environment 7 Aging Effect Aging Ma*nagement NUREG- Table 1 Iteml Notes Tp FucinRequiring Program 1801 Vo9l. LValve LBS, PB, Stainless Secondary Water Loss of material Water Chemistry VIII.G-32 3.4.1.16 A ISIA Steel (Int) i ((B2.1.2) and One-Time _______ ___ __ Inspection (B2.1.16) Notes for Table 3.4.2-3: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1 801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. G Environment not in NUREG-1801 for this component and material. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 Loss of Preload is considered to be applicable for all closure bolting. 2 NUREG-1801 does not consider mechanical insulation. The thermal insulation in-scope for license renewal is located in areas with non-aggressive environments (meaning the insulation is not exposed to contaminants). Based on the review of the SERs of recent license renewal applications (Millstone, Dresden and Quad Cities, Cook, ANO-2, and Robinson) and review of the site operating experience, stainless steel insulation, closed cell foam, quilted fiberglass insulation, calcium silicate and insulation jacketing in non-aggressive environments have no aging effects requiring management. Palo Verde Nuclear Generating Station Page 3.4-40 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.1 Introduction Section 3.5 provides the results of the aging, management reviews for those component types identified in Section 2.4, Scoping and Screening Results - Structures, subject to aging management review. The structures are described in the following sections:
- Containment building (Section 2.4.1)
- Control building (Section 2.4.2)
- Diesel generator building (Section 2.4.3)
- Turbine building (Section 2.4.4)
- Auxiliary building (Section 2.4.5)
" Radwaste building (Section 2.4.6)
- Main steam support structure (Section 2.4.7)
- Station blackout generator structures (Section 2.4.8)
- Fuel building (Section 2.4.9)
" Spray pond and associated water control structures (Section 2.4.10)
" Tank foundations and shells (Section 2.4.11)
" Transformer foundations and electrical structures (Section 2.4.12)
" Yard structures (in-scope) (Section 2.4.13) 1 Supports (Section 2.4.14)
Table 3.5.1, Summary of Aging Management Evaluations in Chapter Ii and III of NUREG-1801 for Containments, Structures, and Component Supports, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component types in this Section. Table 3.5.1 uses the format of Table 1 described in Section 3.0. 3.5.2 Results The following tables summarize the results of the aging management review for the systems in the containments, structures and component supports area:
- Table 3.5.2-1 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Containment Building Palo Verde Nuclear Generating Station Page 3.5-1 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
" Table 3.5.2-2 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Control Building
" Table 3.5.2-3 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Diesel Generator Building
- Table 3.5.2-4 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Turbine Building
- Table 3.5.2-5 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Auxiliary Building
" Table 3.5.2-6 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Radwaste Building
- Table 3.5.2-7 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Main Steam Support Structure
- Table 3.5.2-8 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Station Blackout Generator Structures
- Table 3.5.2-9 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Fuel Building
- Table 3.5.2-10 Containments, Structures, and Component Supports -
Summary of Aging Management Evaluation - Spray Pond and Associated Water Control Structures Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank Foundations and Shells Table 3.5.2-12 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Transformer Foundations and Electrical Structures Table 3.5.2-13 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures (in-scope) Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports These tables use the format of Table 2 discussed in Section 3.0. 3.5.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs The materials from which the component types are fabricated, the environments to which they are exposed, the potential aging effects requiring management, and the aging Palo Verde Nuclear Generating Station Page 3.5-2 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS management programs used to manage these aging effects are provided for each of the above structures and commodities in the following subsections. 3.5.2.1.1 Containment Building Materials The materials of construction for the containment building component types are:
" Carbon Steel
- Concrete
- Elastomer
- Glass
- Stainless Steel
" Thermo-Lag Environment The containment building component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
- Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
- Submerged (Structural)
Aging Effects Requiring Management The following containment building aging effects require management:
" Concrete cracking and spalling
- Cracking
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Increase in porosity, permeability
- Increased hardness, shrinkage and loss of strength Palo Verde Nuclear Generating Station Page 3.5-3 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
" Loss of leak tightness
" Loss of material
" Loss of material (spalling, scaling) and cracking
- Loss of material, cracking
- Loss of sealing; leakage through containment Aging Management Programs The following aging management programs manage the aging effects for the containment building component types:
- 10 CFR 50, Appendix J (B2.1.30)
- ASME Section Xl, Subsection IWE (B2.1.27)
- ASME Section Xl, Subsection IWL (B2.1.28) 0 Fire Protection (B2.1.12)
- Structures Monitoring Program (B2.1.32)
- Water Chemistry (B2.1.2) 3.5.2.1.2 Control Building Materials The materials of construction for the control building component types are:
- Aluminum
" Carbon Steel
- Concrete
- Concrete Block (Masonry Walls)
- Elastomer
- Fire Barrier (Cementitious Coating)
" Fire Barrier (Ceramic Fiber)
" Gypsum/ Plaster Environment The control building component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
Palo Verde Nuclear Generating Station Page 3.5-4 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following control building aging effects require management:
" Concrete cracking and spalling
" Cracking
- Cracking due to expansion
" Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Increased hardness, shrinkage and loss of strength
- Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of material, cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the control building component types:
" Fire Protection (B2.1.12)
" Masonry Wall Program (B2.1.31)
" Structures Monitoring Program (B2.1.32) 3.5.2.1.3 Diesel Generator Building Materials The materials of construction for the diesel generator building component types are:
- Carbon Steel
" Concrete
" Elastomer Palo Verde Nuclear Generating Station Page 3.5-5 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Environment The diesel generator building component types are exposed to the following environments:
" Atmosphere/ Weather (Structural)
" Buried (Structural)
" Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following diesel generator building aging effects require management:
- Concrete cracking and spalling
" Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
" Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Increased hardness, shrinkage and loss of strength
- Loss of material
- Loss of material (spalling, scaling) and cracking
" Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the diesel generator building component types:
- Fire Protection (B2.1.12)
- Structures Monitoring Program (B2.1.32) 3.5.2.1.4 Turbine Building Materials The materials of construction for the turbine building component types are:
- Carbon Steel
- Concrete Palo Verde Nuclear Generating Station Page 3.5-6 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Concrete Block (Masonry Walls)
- Elastomer
- Fire Barrier (Cementitious Coating)
Environment The turbine building component types are exposed to the following environments:
" Atmosphere/ Weather (Structural)
" Buried (Structural)
" Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following turbine building aging effects require management:
" Cracking
" Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
" Cracks and distortion
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
" Increased hardness, shrinkage and loss of strength
" Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of material, cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the turbine building component types:
- Fire Protection (B2.1.12)
- Masonry Wall Program (B2.1.31)
- Structures Monitoring Program (B2.1.32)
Palo Verde Nuclear Generating Station Page 3.5-7 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.1.5 Auxiliary Building Materials The materials of construction for the auxiliary building component types are:
- Carbon Steel
- Concrete
- Concrete Block (Masonry Walls)
- Elastomer
" Fire Barrier (Cementitious Coating)
- Gypsum/ Plaster
- Stainless Steel Environment The auxiliary building component types are exposed to the following environments:
" Atmosphere/ Weather (Structural)
- Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following auxiliary building aging effects require management:
- Concrete cracking and spalling
- Cracking
- Cracking due to expansion
" Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
" Increased hardness, shrinkage and loss of strength
" Loss of material
" Loss of material (spalling, scaling) and cracking
- Loss of material, cracking Palo Verde Nuclear Generating Station Page 3.5-8 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the auxiliary building component types:
- Fire Protection (B2.1.12)
- Masonry Wall Program (B2.1.31)
- Structures Monitoring Program (B2.1.32) 3.5.2.1.6 Radwaste Building Materials The materials of construction for the radwaste building component types are:
- Aluminum
- Carbon Steel
" Concrete
" Elastomer Environment The radwaste building component types are exposed to the following environments:
" Atmosphere/ Weather (Structural)
" Buried (Structural)
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following radwaste building aging effects require management:
- Concrete cracking and spalling
- Cracking due to expansion
" Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Increased hardness, shrinkage and loss of strength Palo Verde Nuclear Generating Station Page 3.5-9 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the radwaste building component types:
" Fire Protection (B2.1.12)
- Structures Monitoring Program (B2.1.32) 3.5.2.1.7 Main Steam Support Structure Materials The materials of construction for the main steam support structure component types are:
" Carbon Steel
" Concrete
- Elastomer Environment The main steam support structure component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
" Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following main steam support structure aging effects require management:
- Concrete cracking and spalling
" Cracking due to expansion
" Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion Palo Verde Nuclear Generating Station Page 3.5-10 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
" Increased hardness, shrinkage and loss of strength
" Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the main steam support structure component types:
- Fire Protection (B2.1.12)
" Structures Monitoring Program (B2.1.32) 3.5.2.1.8 Station Blackout Generator Structures Materials The materials of construction for the station blackout generator structures component types are:
" Carbon Steel
- Concrete Environment The station blackout generator structures component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
" Buried (Structural)
" Encased in Concrete
" Plant Indoor Air (Structural)
Aging Effects Requiring Management The following station blackout generator structures aging effects require management:
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling) 0 Cracks and distortion
- Palo Verde Nuclear Generating Station Page 3.5-11 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Loss of material
- Loss of material (spalling, scaling) and cracking Aging Management Programs The following aging management program manages the aging effects for the station blackout generator structures component types:
- Structures Monitoring Program (B2.1.32) 3.5.2.1.9 Fuel Building Materials The materials of construction for the fuel building component types are:
- Carbon Steel
- Concrete
- Elastomer
- Stainless Steel Environment The fuel building component types are exposed to the following environments:
" Atmosphere/ Weather (Structural)
" Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
- Treated Borated Water Aging Effects Requiring Management The following fuel building aging effects require management:
- Concrete cracking and spalling
" Cracking
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
Palo Verde Nuclear Generating Station Page 3.5-12 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
" Cracks and distortion
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
" Increased hardness, shrinkage and loss of strength
- Loss of material
" Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the fuel building component types:
- Fire Protection (B2.1.12)
- Structures Monitoring Program (B2.1.32)
- Water Chemistry (B2.11.2) 3.5.2.1.10 Spray Pond and Associated Water Control Structures Materials The materials of construction for the spray pond and associated water control structures component types are:
- Carbon Steel
" Concrete
- Copper Alloy
" Elastomer
" Stainless Steel Environment The spray pond and associated water control structures component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
" Buried (Structural)
" Plant Indoor Air (Structural)
- Raw Water Palo Verde Nuclear Generating Station Page 3.5-13 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Submerged (Structural) Aging Effects Requiring Management The following spray pond and associated water control structures aging effects require management:
- Concrete cracking and spalling
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
" Increase in porosity and permeability, loss of strength
" Loss of material
" Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the spray pond and associated water control structures component types:
- Fire Protection (B2.1.12)
- Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (B2.11.33)
" Structures Monitoring Program (B2.1.32) 3.5.2.1.11 Tank Foundations and Shells Materials The materials of construction for tank foundations and shells component types are:
- Carbon Steel
- Concrete
" Elastomer Palo Verde Nuclear Generating Station Page 3.5-14 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Environment The tank foundations and shells component types are exposed to the following environments: 0 Atmosphere/ Weather (Structural)
- Buried (Structural)
- Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following tank foundations and shells aging effects require management:
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management program manages the aging effects for the tank foundations and shells component types:
- Structures Monitoring Program (B2.1.32) 3.5.2.1.12 Transformer Foundations and Electrical Structures Materials The materials of construction for the transformer foundations and electrical structures component types are:
" Carbon Steel
- Concrete
- Elastomer Palo Verde Nuclear Generating Station Page 3.5-15 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Environment The transformer foundations and electrical structures component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
- Buried (Structural)
- Encased in Concrete Aging Effects Requiring Management The following transformer foundations and electrical structures aging effects require management:
- Concrete cracking and spalling
- Cracking due to expansion
- Cracking, loss of bond, and loss of material (spalling, scaling)
- Cracks and distortion
- Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Increased hardness, shrinkage and loss of strength
- Loss of material
- Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the transformer foundations and electrical structures component types:
" Fire Protection (B2.1.12)
- Structures Monitoring Program (B2.1.32) 3.5.2.1.13 Yard Structures (In-Scope)
Materials The materials of construction for the yard structures (in-scope) component types are:
" Carbon Steel
- Concrete Palo Verde Nuclear Generating Station Page 3.5-16 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Concrete Block (Masonry Walls)
- Elastomer
- Gypsum/ Plaster Environment The yard structures (in-scope) component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
" Buried (Structural)
" Encased in Concrete
- Plant Indoor Air (Structural)
Aging Effects Requiring Management The following yard structures (in-scope) aging effects require management:
" Concrete cracking and spalling
- Cracking
- Cracking due to expansion
" Cracking, loss of bond, and loss of material (spalling, scaling)
" Increase in porosity and permeability, cracking, loss of material (spalling, scaling)
- Loss of material
" Loss of material (spalling, scaling) and cracking
- Loss of sealing Aging Management Programs The following aging management programs manage the aging effects for the yard structures (in-scope) component types:
- Fire Protection (B2.1.12)
- Masonry Wall Program (B2.1.31)
- Structures Monitoring Program (B2.1.32)
Palo Verde Nuclear Generating Station Page 3.5-17 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.1.14 Supports Materials The materials of construction for the supports component types are:
- Aluminum
- Carbon Steel
- Concrete
- High Strength Low Alloy Steel (Bolting)
- Lubrite
- Stainless Steel Environment The supports component types are exposed to the following environments:
- Atmosphere/ Weather (Structural)
- Borated Water Leakage 0 Fuel Oil
- Plant Indoor Air (Structural)
- Raw Water Aging Effects Requiring Management The following supports aging effects require management:
- Cracking
- Loss of material
" Loss of mechanical function
- Reduction in concrete anchor capacity Aging Management Programs The following aging management programs manage the aging effects for the supports component types:
- ASME Section XI, Subsection IWF (B2.1.29)
- Bolting Integrity (B2.1.7)
- Boric Acid Corrosion (B2.1.4)
- Palo Verde Nuclear Generating Station Page 3.5-18 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
. Structures Monitoring Program (B2.1.32) 3.5.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 NUREG-1801 provides the basis for identifying those programs that warrant further evaluation. For the containments, structures and component supports areas, those evaluations are addressed in the following subsections.
3.5.2.2.1 PWR and BWR Containments 3.5.2.2.1.1 Aging of Inaccessible Concrete Areas Aggressive Chemical Attack: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of aggressive chemical attack is not required. Corrosionof Embedded Steel: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of corrosion of embedded steel is not required. Palo Verde Nuclear Generating Station Page 3.5-19 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.2.1.2 Cracks and Distortion due to Increased Stress Levels from Settlement; Reduction of Foundation Strength, Cracking, and Differential Settlement due to Erosion of Porous Concrete Subfoundations, if not Covered by the Structures Monitoring Program Settlement: Further evaluation for the effects of settlement is not required because the concrete components are evaluated under the Structures Monitoring Program, and no permanent de-watering system has been constructed at PVNGS. UFSAR Section 2.5.4.13 describes PVNGS settlement monitoring, which is part of the Structures Monitoring Program. Porous Concrete Subfoundations: PVNGS does not have porous concrete subfoundations. Therefore, further evaluation for this effect is not required. 3.5.2.2.1.3 Reduction of Strength and Modulus of Concrete Structures due to Elevated Temperature Elevated Temperatures: At PVNGS, the reactor cavity cooling subsystem operates in conjunction with the containment normal cooling units and provides cooling of the primary shield and reactor cavity to limit the concrete temperature to less than the specified maximum of 150F. The system functions continuously during normal plant operation. The reactor cavity temperature is monitored with four cavity high temperature alarm channels that are annunciated in the control room (UFSAR Section 9.4.6.2.2.E). To ensure that temperatures remain below the specified limit, PVNGS Technical Specifications (LCO 3.6.5) require that the containment average air temperature shall not exceed 1170 F. PVNGS Design Basis Manual HC, Containment Building HVAC System, Table 5-1, specifies instrumentation to provide control room indication of the reactor cavity temperature, and a control alarm on high temperature with a set point of 115 +/- 50 F. For high temperature pipe at PVNGS, penetrations have been designed to limit the local concrete temperature to 2000 F. (Ref. UFSAR Appendix 14A, Response 14A.34). Process piping penetrations were designed with a special flued head and the pipe is insulated to prevent excessive concrete temperatures (UFSAR Section 3.8.1.1.3.3). Therefore, reduction of strength and modulus of concrete structures due to elevated temperature is not an aging effect that requires further evaluation. Accessible concrete components are monitored by the Structures Monitoring Program to confirm the absence of aging effects that could impact the structural integrity./ intended function of the component. Palo Verde Nuclear Generating Station Page 3.5-20 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.2.1.4 Loss of Material due to General, Pitting, and Crevice Corrosion Corrosionin inaccessible areasof steel containment liner: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Concrete mixes were designed in accordance with ACI 211.1-74. The ASME Section XI, Subsection IWL Program will identify and manage any cracks in the concrete that could potentially provide a pathway for water to reach inaccessible portions of the steel containment liner. Procedural controls ensure that borated water spills are not common, and when detected are cleaned up in a timely manner. Therefore, further evaluation for corrosion in inaccessible areas of the steel containment liner is not required 3.5.2.2.1.5 Loss of Prestress due to Relaxation, Shrinkage, Creep, and Elevated Temperature Loss of prestress forces due to relaxation, shrinkage, creep, and elevated temperature for PWR prestressed concrete containments and BWR Mark II prestressed concrete containments is a TLAA as defined in 10 CFR 54.3. TLAAs are evaluated in accordance with 10 CFR 54.21(c). The PVNGS containment is a prestressed concrete pressure vessel with ungrouted tendons. Section 4.5 describes the evaluation of this TLAA. 3.5.2.2.1.6 Cumulative Fatigue Damage Analysis of fatigue in containment penetrations are TLAAs as defined in 10 CFR 54.3 only if a CLB fatigue analysis exists. TLAAs are evaluated in accordance with 10 CFR 54.21(c). PVNGS containment penetrations for the main steam, main feedwater, and recirculation sump suction penetrations are supported by TLAAs. There are no penetration bellows within the scope of license renewal at PVNGS. Section 4.6.2 describes the evaluation of the main steam and feedwater penetrations. Section 4.6.3 describes the evaluation of the recirculation sump suction penetrations. 3.5.2.2.1.7 Cracking due to Stress Corrosion Cracking (SCC) Not applicable. PVNGS has no in-scope stainless steel penetration sleeves, penetration bellows, or dissimilar metal welds subject to stress corrosion cracking, so the applicable NUREG-1 801 lines were not used. 3.5.2.2.1.8 Cracking due to Cyclic Loading Not applicable. Fatigue of metal components is a TLAA, evaluated in accordance with 10 CFR 54.21(c), so the applicable NUREG-1 801 lines were not used. Palo Verde Nuclear Generating Station Page 3.5-21 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.2.1.9 Loss of Material (Scaling, Cracking. and Spalling) due to Freeze Thaw Freeze-Thaw: PVNGS is located in a weathering region classified as Negligible according to Figure 1 of ASTM C33-03. Therefore, further evaluation for the effects of freeze-thaw is not required. 3.5.2.2.1.10 Cracking due to Expansion, and Reaction with Aggregate, and Increase in Porosity and Permeability due to Leaching of Calcium Hydroxide Reaction with Aggregates: As noted in UFSAR Section 3.8.1.6.1.B, source acceptance of aggregates was based, in part, on petrographic examination in accordance with ASTM C295. 13-CN-101, Technical Specification for Furnishing and Delivering Concrete for APS PVNGS Quality Class Q, Section 7.2.2.c, specifies that aggregate reactivity be determined by ASTM C289 and C227. The concrete aggregates were found to be non-reactive. Therefore, further evaluation for the effects of reaction with aggregates is not required. Leaching of Calcium Hydroxide: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Concrete mixes were designed in accordance with ACI 211.1-74. Concrete structures in groups 1-3, 5, 7-9 at PVNGS are not subjected to flowing water for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of leaching of calcium hydroxide is not required. 3.5.2.2.2 Safety-Related and Other Structures and Component Supports 3.5.2.2.2.1 Aging of Structures Not Covered by Structures Monitoring Program The following aging effects do not require further evaluation because the components are evaluated under the Structures Monitoring Program.
- Corrosion of embedded steel
- Aggressive chemical attack
- Loss of material due to corrosion Palo Verde Nuclear Generating Station Page 3.5-22 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Freeze-thaw
- Reaction with aggregates
- Settlement Further evaluation for the effects of erosion of porous concrete subfoundations is not required because PVNGS does not have porous concrete subfoundations.
Further evaluation for lock up due to wear of sliding surfaces is not required because all in-scope sliding surfaces are evaluated under the Structures Monitoring Program (B2.1.32) or under ASME Section X1, Subsection IWF (B2.1.29). 3.5.2.2.2.2 Aging Management of Inaccessible Areas 3.5.2.2.2.2.1 Freeze-Thaw Freeze-Thaw: PVNGS is located in a weathering region classified as Negligible according to Figure 1 of ASTM C33-03. Therefore, further evaluation for the effects of freeze-thaw is not required. 3.5.2.2.2.2.2 Reaction with Aggregates Reaction with Aggregates: As noted in UFSAR Section 3.8.1.6.1.B, source acceptance of aggregates was based, in part, on petrographic examination in accordance with ASTM C295. 13-CN-101, Technical Specification for Furnishing and Delivering Concrete for APS PVNGS Quality Class Q, Section 7.2.2.c, specifies that aggregate reactivity be determined by ASTM C289 and C227. The concrete aggregates were found to be non-reactive. Therefore, further evaluation for the effects of reaction with aggregates is not required 3.5.2.2.2.2.3 Settlement and settlement due to erosion of porous concrete subfoundations Settlement: Competent foundation materials were found to be present at PVNGS for establishing conservative design and construction criteria for support of the facilities. Major structures are founded either on engineered backfill or undeformed basin sediments with a minimum thickness in the power block areas of about 200 feet. These sediments are firm, consolidated, continuous, and show no, evidence of shears, faults, joints, folds or other tectonic features. No permanent de-watering system has been constructed at PVNGS. As discussed in UFSAR Section 2.5.4, settlement of all major structures has been monitored since construction. Table 2.5-19 specifies a frequency for settlement monitoring of every five years, following more frequent intervals during the first three years post-construction. The most recent data were collected in December 2003. The total post-construction Palo Verde Nuclear Generating Station Page 3.5-23 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS settlements recorded have been well below the 1.5 inch maximum specified in UFSAR Section 2.5.4.11. Therefore, further evaluation for the effects of settlement is not required. Porous Concrete Subfoundations: PVNGS does not have porous concrete subfoundations. Therefore, further evaluation for this effect is not required. 3.5.2.2.2.2.4 Aggressive chemical attack and corrosion of embedded steel Aggressive Chemical Attack: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of aggressive chemical attack is not required. Corrosionof Embedded Steel: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of corrosion of embedded steel is not required. 3.5.2.2.2.2.5 Leaching of Calcium Hydroxide Leaching of Calcium Hydroxide: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Concrete mixes were designed in accordance with ACI 211.1-74. Concrete structures in Groups 1-3, 5, 7-9 at PVNGS are not subjected to Palo Verde Nuclear Generating Station Page 3.5-24 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS flowing water for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of leaching of calcium hydroxide is not required. 3.5.2.2.2.3 Reduction of Strength and Modulus of Concrete Structures due to Elevated Temperature Containment: At PVNGS, the reactor cavity cooling subsystem operates in conjunction with the containment normal cooling units and provides cooling of the primary shield and reactor cavity to limit the concrete temperature to less than the specified maximum of 150F. The system functions continuously during normal plant operation. The reactor cavity temperature is monitored with four cavity high temperature alarm channels that are annunciated in the control room (Ref. UFSAR Section 9.4.6.2.2.E). To ensure that temperatures remain below the specified limit, PVNGS Technical Specifications (LCO 3.6.5) require that the containment average air temperature shall not exceed 117 0 F. PVNGS Design Basis Manual HC, Containment Building HVAC System, Table 5-1, specifies instrumentation to provide control room indication of the reactor cavity temperature, and a control alarm on high temperature with a set point of 115 +/- 5 0 F. For high temperature pipe at PVNGS, penetrations have been designed to limit the local concrete temperature to 200'F. (Ref. UFSAR Appendix 14A, Response 14A.34). Process piping penetrations were designed with a special flued head and the pipe is insulated to prevent excessive concrete temperatures (Ref. UFSAR Section 3.8.1.1.3.3). Therefore, reduction of strength and modulus of concrete structures due to elevated temperature is not an aging effect that requires further evaluation. Accessible concrete components will be monitored by the Structures Monitoring Program to confirm the absence of aging that could impact the structural integrity / intended function of the component. Main Steam Support Structure: For high temperature pipe at PVNGS, penetrations have been designed to limit the local concrete temperature to 200'F. Process piping penetrations were designed with a 5-way whip restraint and air flowing around the pipe to prevent excessive concrete temperatures under normal operation. In the event of a loss in air flow the exhaust fans that provide air flow will be restored to service within a seven day period. During that time the local concrete temperature, of the affected penetrations shall be monitored on a daily basis to ensure that the maximum concrete temperature does not exceed 300'F. Therefore, reduction of strength and modulus of concrete structures due to elevated temperature is not an aging effect that requires further evaluation. Accessible concrete components are monitored by the Structures Monitoring Program to confirm the absence of aging that could impact the structural integrity / intended function of the component. UFSAR Table 3.6 "High Energy Lines Outside Containment" identifies the lines outside of containment that have operating temperatures over 200 OF. Palo Verde Nuclear Generating Station Page 3.5-25 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Turbine Building: There are no high energy lines in the turbine building that penetrate concrete barriers, therefore no further evaluation for the effects of Elevated Temperatures are required. (Ref. USFAR Figures 3.6-28 and -30) Auxiliary Building: Safety injection and shutdown cooling system operates at high temperature/pressure less than 2% of the time, therefore it is not considered a high energy line. (UFSAR Table 3.6-2, See note E) The high energy lines in the auxiliary building that penetrate concrete barriers are not subjected to high temperatures and therefore no further evaluation for the effects of Elevated Temperatures are required. Other Structures: Further evaluation for the effects of Elevated Temperatures is not required because high energy lines (Operating Pressure > 275 0 F and/or Operating Temperature > 200 0 F) outside Containment are only found in the MSSS, Turbine Building, and Auxiliary Building. (UFSAR Table 3.6-2) 3.5.2.2.2.4 Aging Management of Inaccessible Areas for Group 6 Structures 3.5.2.2.2.4.1 Aggressive chemical attack and corrosion of embedded steel Aggressive ChemicalAttack: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of aggressive chemical attack is not required. Corrosionof Embedded Steel: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design Palo Verde Nuclear Generating Station Page 3.5-26 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS requirements for each major structure. Crack control was achieved through proper sizing, spacing, and distribution of reinforcing steel in accordance with ACI 318-71. Concrete structures at PVNGS are not subjected to groundwater for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of corrosion of embedded steel is not required. 3.5.2.2.2.4.2 Freeze-Thaw Freeze-Thaw: PVNGS is located in a weathering region classified as Negligible according to Figure 1 of ASTM C33-03. Therefore, further evaluation for the effects of freeze-thaw is not required. 3.5.2.2.2.4.3 Reaction with Aggregates and Leaching of Calcium Hydroxide Reaction with Aggregates: As noted in UFSAR Section 3.8.1.6.1.B, source acceptance of aggregates was based, in part, on petrographic examination in accordance with ASTM C295. 13-CN-101, Technical Specification for Furnishing and Delivering Concrete for APS PVNGS Quality Class Q, Section 7.2.2.c, specifies that aggregate reactivity be determined by ASTM C289 and C227. The concrete aggregates were found to be non-reactive. Therefore, further evaluation for the effects of reaction with aggregates is not required. Leaching of Calcium Hydroxide: Reinforced concrete structures at PVNGS were designed, constructed, and inspected in accordance with ACI and ASTM standards, which provide for a good quality, dense, well-cured, and low permeability concrete. Procedural controls ensured quality throughout the batching, mixing, and placement processes. UFSAR Section 3.8 discusses the design requirements for each major structure. Concrete mixes were designed in accordance with ACI 211.1-74. Concrete structures in groups 1-3, 5, 7-9 at PVNGS are not subjected to flowing water for any sustained periods. An engineering study was performed to confirm that groundwater elevations are below the lowest structures. Therefore, further evaluation for the effects of leaching of calcium hydroxide is not required. 3.5.2.2.2.5 Cracking due to Stress Corrosion Cracking and Loss of Material due to Pitting and Crevice Corrosion The in-scope tank liners at PVNGS were evaluated in the condensate and CVCS systems and assigned NUREG-1801 lines from chapters VII and VIII. Therefore, further evaluation for the effects of cracking due to stress corrosion cracking and loss of material due to pitting and crevice corrosion is not required. Palo Verde Nuclear Generating Station Page 3.5-27 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS 3.5.2.2.2.6 Aging of Supports Not Covered by the Structures Monitoring Program Further evaluation of the following components is not required because they will be inspected per the Structures Monitoring Program.
- Building concrete around support anchorages
" HVAC duct supports
- Instrument supports
" Non-ASME mechanical equipment supports
" Non-ASME supports
- Electrical panels and enclosures 3.5.2.2.2.7 Cumulative Fatigue Damage due to Cyclic Loading Analyses of fatigue in component support members, anchor bolts, and welds for Group B1.1, B1.2, and B1.3 component supports (for ASME III Class 1, 2, and 3 piping and components, and for Class MC BWR containment supports) are TLAAs as defined in 10 CFR 54.3 only if a CLB fatigue analysis exists. The review identified no TLAAs supporting design of these components at PVNGS.
PVNGS ASME Class 1 piping is designed to code editions and addenda before 1986, which therefore precede cycle limits for allowable stress in supports. Section 4.3.2.7 describes the absence of a cycle-based stress limit for ASME Class 1 supports. PVNGS ASME Class 2 and 3 piping and components require no fatigue or cycle design analysis for their supports, and no other similar analysis exist for supports for those components at PVNGS. PVNGS is a PWR and does not have Class MC BWR containment supports. 3.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components Quality Assurance Program and Administrative Controls are discussed in Section B1.3. 3.5.2.3 Time-Limited Aging Analysis The time-limited aging analyses identified below are associated with the containments, structures, and component supports component types. The section within Chapter 4, Time-Limited Aging Analyses, is indicated in parenthesis.
- Loss of prestress (Section 4.5, Concrete Containment Tendon Prestress)
Palo Verde Nuclear Generating Station Page 3.5-28 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
- Cumulative fatigue damage (Section 4.6, Containment Liner Plate, Equipment Hatch And Personnel Air Locks, Penetrations, And Polar Crane Brackets) 3.5.3 Conclusions The Containments, Structures and Component Supports component types that are subject to aging management review have been evaluated. The aging management programs selected to manage the aging effects for the Containment, Structures and Component Supports component types are identified in the summary Tables and in Section 3.5.2.1.
A description of these aging management programs is provided in Appendix B, along with a demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstration provided in Appendix B, the effects of aging associated with the Containments, Structures and Component Supports component types will be adequately managed so that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. Palo Verde Nuclear Generating Station Page 3.5-29 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in ChaptersII and Ill of NUREG-1801 for Containments, Structures, and Component Supports Concrete elements: !Aging of accessible and i 101 kIVVL) k /-. I .Z-- ) al U HUH I co I..UI I*l*Itl IL VYILI I I1 I walls, dome, basemat, !inaccessible concrete areas inaccessible concrete, an 1801. ring girder, buttresses, ,due to aggressive chemical !examination of representativei See further evaluati on in containment (as iattack, and corrosion of samples of below-grade subsection 3.5.2.2.11.1. applicable) embedded steel concrete, and periodic monitoring of groundwater, if 1the environment is non-aggressive. A plant specific program is to be evaluated if environment is aggressive. Palo Verde Nuclear Generating Station Page 3.5-30 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluationsin Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) All Cracks and distortion due to Structures Monitoring iYes, it not within Consistent with NUREG-S1801. increased stress levels from Program (B2.1.32). If a de- 1the scope of the
,settlement watering system is relied applicant's See further evaluation in upon for control of structures subsection 3.5.2.2.1.2.
settlement, then the licensee monitoring is to ensure proper program or a de-functioning of the de-watering watering system system through the period of is relied upon _extended operation. , 3.5.1 .03 Concrete elements: Reduction in foundation Structures Monitoring fYes, if not within INot applicable. PVNGS has foundation, sub- strength, cracking, differential Program (B2.1.32). If a de- 'the scope of the no porous concrete foundation settlement due to erosion of watering system is relied !applicant's foundations, so the porous concrete subfoundation upon for control of erosion of structures applicable NUREG-1801 cement from porous concrete monitoring lines were not used. subfoundations, then the program or a de- ,See further evaluation in licensee is to ensure'proper 1watering system isubsection 3.5.2.2.1.2. functioning of the de-watering Iis relied upon. system through the period of extended operation. Palo Verde Nuclear Generating Station Page 3.5-31 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) iltem, Co9mponent Type Aging Effect / Mechanism Aging Manageament Fgurthert Dsussio NubrProgr~am Evaluation ____ ___ _ __ __ ____ ___ ____ ___ __ _ ___ ____ ___ __ Recommended r 3.5.1.04 Concrete elements: IReduction of strength and A plant-specific aging Yes Not applicable. PVNGS has dome, wall, basemat, ,modulus of concrete due to management program is to no dome, wall, basemat, ring ring girder, buttresses, :elevated temperature be evaluated girder, buttresses, containment, concrete 'containment, or annulus fill-in annulus (as concrete exposed to
, applicable) ,elevated temperatures, so the applicable NUREG-1801 Ilines were not used.
ISee further evaluation in
!,subsection 3.5.2.2.1.3.
3.5.1.05 INot applicable - BWR only 3.5.1.06 7§Steel elements: steel ILoss of material due to ilSI (IWE) (B2.1.27), and 10 Yes, if corrosion Consistent with NUREG-liner, liner anchors, general, pitting and crevice CFR 50, Appendix J is significant for 11801 with aging integral attachments ,corrosion (B2.1.30). inaccessible !management program areas !exceptions. The aging management iprogram(s) with exceptions
'to NUREG-1801 include:
IASME Section XI,
!Subsection IWE (B2.1.27).
!See further evaluation in isubsection 3.5.2.2.1.4.
Palo Verde Nuclear Generating Station Page 3.5-32 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) ii ~ V ,3.o. .u' l-'restresseu LOSS OT presiress due to I LA-v--, evaluatea in Tes, I L.AA LOSS 01 presiress oT containment tendons Irelaxation, shrinkage, creep, accordance with 10 CFR containment tendons is a and elevated temperature 54.21(c) *TLAA.
,See further evaluation in 3.5.1.081 ______ [_________ Ssubsection 3.5.2.2.1.5.
_Not applicable - BWR only 3.5.1.09 !Steel, stainless steel Cumulative fatigue damage ITLAA, evaluated in Yes, TLAA !Fatigue of metal components elements, dissimilar (CLB fatigue analysis exists) ;,accordance with 10 CFR is a TLAA. However, only metal welds: 54.21(c) !design of penetration penetration sleeves, ,sleeves is supported by a penetration bellows; TLAA. suppression pool shell, See further evaluation in unbraced downcomers isubsection 3.5.2.2.1.6. 3.5.1.10 Stainless steel Cracking due to stress ISI (IWE) (B2.1.27), and 10 Yes Not applicable. PVNGS has penetration sleeves, corrosion cracking CFR 50, Appendix J ,no in-scope stainless steel penetration bellows, i(B2.1.30), and additional ;penetration sleeves, dissimilar metal welds appropriate " ,penetration bellows, or examinations/evaluations for dissimilar metal welds bellows assemblies and ,subject to stress corrosion 1dissimilar metal welds. cracking, so the applicable NUREG-1801 lines were not used.
',See further evaluation in subsection 3.5.2.2.1.7.
3.5.1.11 _ _ _ _ _ _ _ _ _I_ _ _ _ _ _ _ --- _ INot applicable - BWR only Palo Verde Nuclear Generating Station Page 3.5-33 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in ChaptersII and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) Item : KComponent Type Aging Effect/ Mechanism Aging Management FEurther % Discussion Number Program
- Evaluation
- RecommendedjY~
3.5.1.12 Steel, stainless stee lCracking due to cyclic loading ISI (IWE) (B2.11.27), and 10 ;Yes !Not applicable. Fatigue of
!elements, dissimilar CFR 50i Appendix J !metal components is a metal welds: ((B2.1.30), and supplemented ITLAA, evaluated in
,penetration sleeves, to detect fine cracks accordance with 10 CFR penetration bellows; 54.21(c), so the applicable suppression pool shell, NUREG-1801 lines were not unbraced downcomers used.
See further evaluation in subsection 3.5.2.2.1.8. 3.5.1.13 Not applicable - BWR only 3.5.1.14 Concrete elements: I Loss of material (Scaling, ISI (IWL) (B2.1.28). 1Yes Consistent with NUREG-dome, wall, basemat !cracking, and spalling) due to Evaluation is needed for 1801 ring girder, buttresses, jfreeze-thaw plants that are located in See further evaluation in containment (as moderate to severe !subsection 3.5.2.2.1.9. applicable) weathering conditions (weathering index >100 day-Iinch/yr) (NUREG-1557). 3.5.1.15 Concrete elements: Cracking due to expansion and IISI (IWL) (B2.1.28) for Yes, if concrete Consistent with NUREG-walls, dome, basemat, reaction with aggregate; accessible areas. None for was not 1801. ring girder, buttresses, increase in porosity, inaccessible areas if concrete i constructed as See further evaluation in containment, concrete permeability due to leaching of was constructed in Istated for ]subsection 3.5.2.2.1.10. fill-in annulus (as calcium hydroxide accordance with the inaccessible applicable). !recommendations in ACI areas __ I I1201.2R. Palo Verde Nuclear Generating Station Page 3.5-34 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) Oeals, gasKeLS, anIu ILO55 UI b ~l~llrl drIU ldKdYtj 1hb 10 kIVYr- k_)D/. dI.) IU IVU ý*UlIbIbILUI IL WILI I INurMr"-7 moisture barriers !through containment due to 1CFR 50, Appendix J 1801 with aging
!deterioration of joint seals, 1(B2.1.30). management program gaskets, and moisture barriers exceptions.
(caulking, flashing, and other The aging management sealants) program(s) with exceptions to NUREG-1801 include: jASME Section Xl, Subsection IWE (B2.1.27) 3.5.1.17 Personnel airlock, Loss of leak tightness in closed 10 CFR 50, Appendix J No Consistent with NUREG-equipment hatch and !position due to mechanical (B2.1.30) and Plant Technical! 1801. CRD hatch locks, wear of locks, hinges and Specifications hinges, and closure closure mechanisms mechanism s .....
.........
....
....
....
....
3Y5.1.1 8 Steel penetration Loss of material due to IlSI (IWE) (B2.1.27), and 10 ýNo IConsistent with NUREG-sleeves and dissimilar Igeneral, pitting, and crevice CFR 50, Appendix J 1801 with aging metal welds; personnel corrosion (B2.1.30). management program airlock, equipment exceptions. hatch and CRD hatch The aging management jprogram(s) with exceptions to NUREG,1801 include: ASME Section Xl, Subsection IWE (B2.1.27) 3.5.1.19 Not applicable - BWR only 3.5.1.20 i Not applicable - BWR only_ 3.5.1.21 !Not applicable - BWR only Palo Verde Nuclear Generating Station Page 3.5-35 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters I/ and /// of NUREG-1801 for Containments, Structures, and Component Supports (Continued) 3.5.1.22 Prestressed Loss of material due to ISI (IWL) (B2.1.28) 140 1k.onslsieni wim i'Ju containment: tendons 1corrosion 11801. and anchorage _components ___ 3.5.1.23 All Groups except Cracking, loss of bond, and !Structures Monitoring Yes, if not within 'Consistent with NUREG-Group 6: interior and loss of material (spalling, 'Program (B2.1.32) the scope of the 1801. above grade exterior 'scaling) due to corrosion of applicant's See further evaluation in concrete embedded steel structures subsection 3.5.2.2.2.1. monitoring programCose Yes, if not within with NUREG-3.5.1.24 All Groups except IIncrease in porosity and Structures Monitoring Group 6: interior and !,permeability, cracking, loss of Program (B2.1.32) the scope of the 1801. above grade exterior imaterial (spalling, scaling) due applicant's See further evaluation in concrete ito aggressive chemical attack I structures subsection 3.5.2.2.2.1. monitoring program 3.5.1.25 All Groups except Loss of material due to Structures Monitoring Yes, if not within lConsistent with NUREG-Group 6: steel Icorrosion Program (B2.1.32). If the scope of the 1801. components: all protective coatings are relied applicant's See further evaluation in structural steel upon to manage the effects structures subsection 3.5.2.2.2.1. Iof aging, the structures monitoring monitoring program is to program include provisions to address I Iprotective coating monitoring . ... . . .. . .. . .and maintenance. Palo Verde Nuclear Generating Station Page 3.5-36 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in ChaptersII and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) I 9: ~IV 7~<~< ~Recomm~endediL 3.5.1.26 All Groups except Loss of material (spalling, IStructures Monitoring iYes, if not within Consistent with NUREG-Group 6: accessible scaling) and cracking due to IProgram (B2.1.32). the scope of the 11801. and inaccessible 1freeze-thaw Evaluation is needed for applicant's See further evaluation in concrete: foundation !plants that are located in Istructures subsection 3.5.2.2.2.1. moderate to severe monitoring
'weathering conditions program or for (weathering index >100 day- inaccessible inch/yr) (NUREG-1 557). areas of plants located in moderate to severe weathering jconditions 3.5.1.27 All Groups except Cracking due to expansion due Structures Monitoring Yes, if not within Consistent with NUREG-Group 6: accessible to reaction with aggregates Program (B2.1.32) the scope of the 1801.
and inaccessible applicant's See further evaluation in interior/exterior structures subsection 3.5.2.2.2.1. concrete monitoring program or concrete was not constructed as stated for inaccessible areas Palo Verde Nuclear Generating Station Page 3.5-37 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluationsin Chapters// and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued)
.roups i-,, 0-U: Al iuracKs ana austortion due to :Structures Monitoring IYes, if not within Uonsistent with NUK-<L-increased stre ss levels from !Program (B2.1.32). If a de- the scope of the 1801.
settlement .watering system is relied applicant's See further evaluation in upon for control of structures subsection 3.5.2.2.2.1.
,settlement, then the licensee monitoring is to ensure proper program or a de-functioning of the de-watering watering system Isystem through the period of is relied upon oundation extended operation.
[Structures _ Monitoring Yes, if not within: Not applicable. PVNGS has 3.5.1.29 Groups 1-3, 5-9: Reduction in f foundation strength, craciking, differential Program (B2.1.32). If a de- the scope of the ;no porous concrete settlement duee to erosion of watering system is relied iapplicant's foundations, so the porous concre te subfoundation upon for control of structures applicable NUREG-1801
!settlement, then the licensee monitoring lines were not used.
'is to ensure proper program or a de-
!functioning of the de-watering watering system
!system through the period of is relied upon
!extended operation. - _
3.5.1.30 Group 4: Radial beam Lock-up due tco wear !Structures Monitoring Yes,if not within ýNot applicable. PVNGS did seats in BWR drywell; Program (B2.1.32) the scope of ISI not use Lubrite on the RPV RPV support shoes for or structures isupport shoes or steam PWR with nozzle monitoring Igenerator supports, so the supports; Steam program ,applicable NUREG-1801 line
.generator supports- ____was not used.
Palo Verde Nuclear Generating Station Page 3.5-38 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) 3.5.1.31 uroups l-ij, o3, t-ýj: Increase in porosity and Structures Monitoring Consistent with NUREG-below-grade concrete permeability, cracking, loss of Program (B2.1.32); 1801. components, such as material (spalling, scaling)/ Examination of !See further evaluation in exterior walls below aggressive chemical attack; 'representative samples of subsection 3.5.2.2.2.2.4. grade and foundation below-grade concrete, and periodic monitoring of groundwater, if the Ienvironment is non-aggressive. A plant specific program is to be evaluated if environment is aggressive. 3.5.1.32 Groups 1-3, 5, 7-9: Increase in porosity and Structures Monitoring Yes, if concrete Not applicable. Concrete exterior above and permeability, and loss of Program (B2.1.32) for was not structures in groups 1-3, 5, below grade reinforced strength due to leaching of accessible areas. None for constructed as 7-9 at PVNGS are not concrete foundations calcium hydroxide inaccessible areas if concrete stated for .subjected to flowing water for was constructed in inaccessible iany sustained periods, so 1accordance with the areas ithe applicable NUREG-1801 recommendations in ACI lines were not used. See 201.2R-77. ifurther evaluation in
ýsubsection 3.5.2.2.2.2.5.
Palo Verde Nuclear Generating Station Page 3.5-39 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters I/ and I/ of NUREG- 1801 for Containments, Structures, and Component Supports (Continued) Groups 1-5: concrete Reduction of strength and A plant-specific aging Yes Not applicable. PVNGS has modulus of concrete due to !management program is to Ino concrete exposed to elevated temperature 'be evaluated !elevated temperatures, so
!the applicable NUREG-1801 lines were not used.
See further evaluation in subsection 3.5.2.2.2.3. 3.5.1.34 Group 6: Increase in porosity and IInspection of Water-Control Yes Consistent with NUREG-Concrete; !permeability, cracking, loss of Structures (B2.1.33) 11801. all material due to aggressive i See further evaluation in chemical attack; cracking, loss subsection 3.5.2.2.2.4.1. of bond, loss of material due to I _corrosion of embedded steel __ 3.5.1.35 Group 6: exterior Loss of material (spalling, Inspection of Water-Control Yes, for Consistent with NUREG-above and below ,scaling) and cracking due to Structures (B2.1.33) inac cessible 1801. grade concrete freeze-thaw area s of plants See further evaluation in foundation loca ted in subsection 3.5.2.2.2.4.2.
'mod erate to sevE*re wealthering conclitions Palo Verde Nuclear Generating Station Page 3.5-40 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging ManagementEvaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) uroup t: aii it.racKing aue to expansion/ inspection or vvater-,ontrol I res, ia concrete it, onsistent witn 4r¶umt-- accessible/ reaction with aggregates Structures (B2.1.33) was not 11801. inaccessible reinforced I constructed as ISee further evaluation in concrete istated for subsection 3.5.2.2.2.4.3. inaccessible areas 3.5.1.37 Group 6: exterior Increase in porosity and 'Inspection of Water-Control Yes, if concrete Consistent with NUREG-above and below permeability, loss of strength Structures (B2.1.33) was not 1801. grade reinforced due to leaching of calcium constructed as See further evaluation in concrete foundation hydroxide stated for subsection 3.5.2.2.2.4.3. t3.5.1.38 interior slab J linaccessible areas Groups 7, 8: Tank Cracking due to stress iA plant-specific aging Yes Not applicable. The in-scope liners corrosion cracking; loss of management program is to tank liners at PVNGS were material due to pitting and be evaluated evaluated in the condensate crevice corrosion !and CVCS systems and assigned NUREG-1801 lines from Chapters VII and VIII. Therefore, the NUREG-1801
!lines from Chapter III were
!not used.
Palo Verde Nuclear Generating Station Page 3.5-41 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters // and H/ of NUREG-1801 for Containments, Structures, and Component Supports (Continued) I I 13.5.1.39 Support members; !Loss of material due to general Structures Monitoring Yes, if not within 'Consistent with NUREG-welds; bolted and pitting corrosion Program (B2.1.32) 'the scope of the 1801. connections; support ýapplicant's See further evaluation in anchorage to building 1 ,structures Fsubsection 3.5.2.2.2.6. 1structure - imonitoring
.program 3.5.1.40 Building concrete at Reduction in concrete anchor ;Structures Monitoring . Yes, if not within IConsistent with NUREG-locations of expansion capacity due to local concrete Program (B2.1.32) the scope of the 1801.
and grouted anchors; !degradation/ service-induced applicant's See further evaluation in grout pads for support cracking or other concrete structures !subsection 3.5.2.2.2.6. base plates aging mechanisms Imonitoring 1program 3.5.1.41 Vibration isolation !Reduction or loss of isolation Structures Monitoring Yes, if not within !Not applicable. PVNGS has elements Jfunction/ radiation hardening, Program (B2.1.32) !the scope of the Ino in-scope vibration temperature, humidity, lapplicant's isolation elements, so the sustained vibratory loading structures lapplicable NUREG-1801 monitoring !lines were not used. pro qram 3.5.1.42 1Groups B 1.1, B1.2, !Cumulative fatigue damage TLAA, evaluated in !Yes, TLAA Fatigue of support members Iand B1.3: support I(CLB fatigue analysis exists) accordance with .10 CFR is not a TLAA as defined in members: anchor 54.21(c) 10 CFR 54.3. bolts, wel ds 'See further evaluation in ____subsection 3.5.2.2.2.7. Palo Verde Nuclear Generating Station Page 3.5-42 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) Recommpnndq~o I Groups 1-3, 5, 6: all !%lIC lly UUV LU I LI:dIIIL i lVIdbUIIl1 ! No IConsistent with NUREG masonry block walls !shrinkage, creep, and (B2.1.31) 11801 for inspections
;aggressive environment performed under the Masonry Wall Program
,(B2.1.31). NUREG 1801 idoes not provide a line in which concrete masonry is inspected per the Fire
,Protection program.
Therefore, for CMU walls that provide a fire barrier function, the Fire Protection program (B2.1.12) has been iadded. 3.5.1.44 Group 6 elastomer 'Loss of sealing due to Structures Monitoring No iConsistent with NUREG-seals, gaskets, and deterioration of seals, gaskets, Program (B2.1.32) 1801. moisture barriers and moisture barriers (caulKing, flashing, and other sealants) _d.-5.1.45 Group 6: exterior Loss of material due to Inspection of Water-Control No lConsistent with NUREG-above and below abrasion, cavitation !Structures (B2.1.33) 11801. grade concrete foundation; interior slab _ Palo Verde Nuclear Generating Station Page 3.5-43 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluations in Chapters /I and I/ of NUREG-1801 for Containments, Structures, and Component Supports (Continued) uroup SCracking due to stress Water Chemistry (B2.1.2) liners corrosion cracking; loss of and monitoring of spent fuel 1801. material due to pitting and Ipool water level in
,crevice corrosion ,accordance with technical i specifications and leakaae from the leak chase
_ __I channels. 3.5.1.47 Group 6: all metal Loss of material due to general Inspection of Water-Control No Consistent with NUREG-structural members (steel only), pitting and crevice !Structures (B2.1.33) 1801 for material, Icorrosion ienvironment, and aging effect, but a different aging Imanagement program, IStructures Monitoring Program (B2.1.32) is credited. 3.5.1.48 Group 6: earthen Loss of material, loss of form !Inspection of Water-Control No Not applicable. PVNGS has water control due to erosion, settlement, (B2.1.33) no earthen dams, structures - dams, sedimentation, frost action, !embankments, reservoirs, embankments, waves, currents, surface Schannels, canals, or ponds reservoirs, channels, runoff, Seepage in-scope for license renewal, canals, and ponds iso the applicable NUREG-11801 lines were not used.
,The spray ponds are Iconcrete structures.
+
3.5.1.49 INot applicable - BWR only Palo Verde Nuclear Generating Station Page 3.5-44 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluationsin Chapters II and Ill of NUREG- 1801 for Containments, Structures, and Component Supports (Continued) uroups D/, arnu D'+. LOSS 1rmiatirial uUe to piunIry 0iruutures IVIUon1LU[rln IConsistent with NUREG-galvanized steel, *and crevice corrosion Program (B2.1.32) 1801, except for the Class 2 aluminum, stainless land 3 components. For steel support 'these, consistent for members; welds; }material, environment and bolted connections; aging effect, but a different support anchorage to 1aging management program building structure 'was used. Class 2 and 3 icomponents are evaluated Iunder ASME Section XI, Subsection IWF (B2.1.29). For other components, Structures Monitoring SProgram (B2.1.32) is Icredited, which is consistent with NUREG-1801. 3.5.1.51 Group Bl.: high -Cracking due to stress Bolting Integrity (B2.1.7) jNo Consistent with NUREG-strength low-alloy bolts 1corrosion cracking; loss of 1801 with aging
,material due to general Imanagement program corrosion exceptions.
The aging management
,program(s) with exceptions
!to NUREG-1801 include:
!Boltina InteQritv (B2.1.7)
Palo Verde Nuclear Generating Station Page 3.5-45 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluationsin Chapters // and I/ of NUREG-1801 for Containments, Structures, and Component Supports (Continued)
. Lroupsbz, ana b4: LOSS OT mecnanicai tunction titructures Monitonr uonsistent v sliding support due to corrosion, distortion, Program (B2.1.32) 1801.
bearings and sliding 'dirt, overload, fatigue due to support surfaces vibratory and cyclic thermal loads 3.5.1.53 Groups B1.1, B1.2, Loss of material due to general', IS[ (IWF) (B2.1.29) No lConsistent with NUREG-
- and pitting corrosion 11801.
and B1.3: support members: welds; bolted connections; support anchorage to building structure 3.5.1.54 Groups B-1.1, B1.2, Loss of mechanical function 1lSl (IWF) (B2.1.29) No Consistent with NUREG-
,due to corrosion, distortion, and B1.3: Constant 11801.
*nnf Inr
%inrinhialr 1irfirf rworlnor fn÷i "m* rhl*n spring hangers; vibratory and cyclic thermal guides; stops; Iloads 3.5.1.55 Steel, galvanized steel, Loss of material due to boric Boric Acid Corrosion (B2.1.4) No !Consistent with NUREG-and aluminum support acid corrosion 11801.
members; welds; bolted connections; support anchorage to building structure Palo Verde Nuclear Generating Station Page 3.5-46 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.1 Summary of Aging Management Evaluationsin Chapters II and Ill of NUREG-1801 for Containments, Structures, and Component Supports (Continued) p ...... n4 4 n,4 q croups o i. I, t3 i./L, L0SS U1 .I.U iuriuFI
.d1iiLdI ý.U[flSIUWIIt WiuLF NUMC.U-and B1.3: Sliding due to corrosion, distortion, ,1801.
surfaces dirt, overload, fatigue due to vibratory and cyclic thermal loads 3.5.1.57 Groups BB1.1, B 1.2, Reduction or loss of isolation ISI (IWF) (B2.1.29) !Not applicable. PVNGS has and B1.3: Vibration function/ radiation hardening, no in-scope vibration isolation elements temperature, humidity, !isolation elements, so the sustained vibratory loading ,applicable NUREG-1801 lines were not used. 3.5.1.58 Galvanized steel and None None No Consistent with NUREG-aluminum support 11801. 1 members; welds; bolted connections; support anchorage to building structure exposed to air - indoor uncontrolled
+
3.5.1.59 Stainless steel support None None No lConsistent with NUREG-members; welds; 1801. bolted connections; support anchorage to buildiong structure _____________ Palo Verde Nuclear Generating Station Page 3.5-47 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Buildina uompresslDI tiastomer riant inaoor /ir LOSS O seawing; /-'.lVll" OecGIon Al, 3.1.0. I.1I0 Joints/Seals (Structural) (Ext) Leakage through Subsection IWE containment (B2.1.27) and 10 CFR 50, Appendix J (1B2.1.30) ___ Concrete FB, MB, Concrete Atmosphere/ Cracking due to ASME Section Xl, I1l.A1-3 3.5.1.15 Elements SH, SLD, Weather !expansion Subsection IWL
,(B2. 1.28) .... . . .. .....
SPB, SS (Structural) (Ext) Concrete FB, MB, SH, SLD, Concrete SAt mosphere/ Weather Cracks and distortion Structures Monitoring II.A1-5 3.5.1.02 Elements (Structural) (Ext) d Program (B2.1.32) SPB, SS Concrete FB, MB, Concrete Atmosphere/ Increase in ASME Section XI, i All -6 3.5.1.15 Weather porosity, Subsection IWL { Elements SH, SLD, SPB, SS (Structural) (Ext) Ipermeability (B2.1.28) Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of ASME Section XI, ill.A1-7 3.5.1.01 SElements SH, SLD, Weather !bond, and loss of Subsection IWL
ýSPB, SS (Structural) (Ext) material (spalling, (B2.1.28) scaling)
Palo Verde Nuclear Generating Station Page 3.5-48 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Concrete FB, MB, Atmosphere/ Concrete cracking Fire Protection (B2.1 3.3.1. Elements SH, SLD, Weather and spalling and Structures SPB, SS (Structural) (Ext) Monitoring Program (B2.1.32) Concrete [FB, MB, Concrete Atmosphere/ Loss of material Fire Protection (B2.1.12)!VII.G-31 13.31.67 B Elements ISH, SLD, Weather and Structures SPB, SS (Structural) (Ext) Monitoring Program (B2.1.32) i Concrete FLB, SH, Concrete Buried (Structural) Loss of material ASME Section XI, ill.A1-2 13.5.1.14 Elements SLD, (Ext) (spalling, scaling) Subsection IWL SPB, SS and cracking (B2.1.28) Concrete FLB, SH, Concrete Buried (Structural) Cracking due to ASME Section Xl, II.A1-3 3.5.1.15 1A Elements SLD, (Ext) expansion Subsection IWL SPB, SS (B2.1.28) Concrete FLB, SH, Concrete Buried (Structural) Increase in ASME Section Xl, I1I.A1-4 3.5.1.01 A Elements SLD, (Ext) porosity and Subsection IWL SPB, SS permeability, (B2.1.28) cracking, Ioiss of material (sppalling,
!scaling Concrete FLB, SH, Concrete Buried (Structural) Cracks and Structures Monitoring ill .A1-5 13.5.1.02 A Elements SLD, (Ext) distortion Program (B32.1.32)
SPB, SS Palo Verde Nuclear Generating Station Page 3.5-49 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment %.,UI1L;(Ui. r-LD, On, k,UIlLRA LU DUI IUU kOLI UULUIdII) 1 1lL~l1 :IU Ill t-OlVlr ;IUI- Al, II.I' I-U .J.,J. I. I Elements SLD, (Ext) porosity, Subsection IWL SPB, SS Ipermeability (B2.1.28)_ _ , Concrete FB, MB, Concrete Plant Indoor Air !Cracking due to ASME Section XI, 1l.A1-3 13.5.1.15 A Elements SH, SLD, (Structural) (Ext) expansion Subsection IWL SPB, SS Concrete FB, MB, Concrete Plant Indoor Air Increase in ASME Section XI, 1II.A1-4 3.5.1.01 A Elements SH, SLD, (Structural) (Ext) !porosity and Subsection IWL SPB, SS permeability, (B2.1.28) cracking, loss of
,material (spalling, iscalinci) 4 4 4 4 4 Concrete FB, Concrete Plant Indoor Air Cracks and Structures Monitoring 'll.A1-5 3.5.1.02 A Elements HLBS, (Structural) (Ext) distortion Program (B2.1.32)
MB, SH, SLD, SPB, SS Concrete FB, MB, Concrete P. lant Indoor Air Cracking, loss of ASME Section XI, 1I.A1-7 '3.5.1.01 Elements SH, SLD, 3tructural) (Ext) Ibond, and loss of Subsection IWL SPB, SS (5 !material (spalling, (B2.1.28) S.caling) Concrete FB, Concrete ant Indoor Air Cracking due to Structures Monitoring IIl.A4-2 -3.5.1.27 Elements HLBS, 3tructural) (Ext) expansion Program (B2.1.32) MB, SLD, _________________ I LSS Palo Verde Nuclear Generating Station Page 3.5-50 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Buildina (Continued) uoncrete L'racKing, loss OT caruciures ivonnoning ýml./-v+-,o !0.0. 1./-0, Ir'ani inooor Air Elements HLBS, (Structural) (Ext) bond, and loss of Program (B2.1.32) MB, SLD, material (spalling, SS tscaling) Concrete FB, Concrete Plant Indoor Air Concrete cracking Fire Protection (B2.1.12) VII.G-28 3.3.1.65 I Elements HLBS, (Structural) (Ext) and spalling and Structures MB, SH, Monitoring Program SLD, (B2.1.32) SPB, SS Concrete FB, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12)IVII.G-29 i3.3.1.67 B Elements HLBS, (Structural) (Ext) and Structures MB, SH, Monitoring Program SLD, (B2.1.32) 6 SPB, SS 1Non Fire Barrier FFB Thermo-Lag Plant Indoor Air Loss of material, Fire Protection (B2.1.12)1, None J, 1 Coatings/ (Structural) (Ext) cracking Wraps Fire Barrier ES, FB, Elastomer Atmosphere/ Increased Fire Protection (B2.1.12)IVII.G-2 3.31.61 Seals SH Weather hardness, (Structural) (Ext) shrinkage and loss of strength Fire Barrier Elastomer Plant Indoor Air Increased Fire Protection (B2.1.12)iVII.G-1 3.3.1.61 Seals (Structural) (Ext) hardness,
!shrinkage and jkloss of strength Palo Verde Nuclear Generating Station Page 3.5-51 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Hatch - %'dILUF1 att MU-I IUb*lJl I{1 [*/ ILUbb U1 IMdI' IU -,r-r1 ;U II 3.... 1I. I Emergency tSPB, SS Weather tightness (B2.1.30) Airlock (Structural) (Ext), Hatch-- "- MB, SLID, Carbon Steel .Atmosphere/ "Lssof material ASME Section XI, I1A3-6 i3.5.1.18 B Emergency SPB, SS Weather Subsection IWE Airlock (Structural) (Ext) (B2.1.27) and 10 CFR 50, Appendix J Loss of leak (B2.*1-30) ......... Hatch - MB, SLD, Carbon Steel Plant Indoor Air 10 CFR 50, Appendix J 1I.A3-5 3.5.1.17 A Emergency ISPB, SS (Structural) (Ext) tightness (B2.1.30) Airlock Hatch - SMB, SLD, Carbon Steel Plant Indoor Air Loss of material ASME Section Xl, 11.A3-6 3.5.1.18 B Emergency SPB, SS (Structural) (Ext) Subsection IWE I Airlock (B2.1.27) and 10 CFR 50, Appendix J I (B2.1.30) + Hatch - ISPB Glass Plant Indoor Air None None iV.F-6 13.2.1.52 C Emergency (Structural) (Ext) [Airlock Hatch - ISPB, SS Carbon Steel Atmosphere/ Loss of leak 10 CFR 50, Appendix J II.A3-5 13.5.1.17 Equipment Weather __(Structural) (Ext) {i tightness
-___.....
(B2.1.30) _ __ _ _ _ _ _ _ _ j _ _ _ _ Palo Verde Nuclear Generating Station Page 3.5-52 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment R~ilidinry ((';.tntinii*.f) Hatch - Atmosphlere/ AML cSection Al, Equipment Weather Subsection IWE (Structural) (Ext) (B2.1.27) and 10 CFR 50, Appendix J (132.1 .30) _ ___ Hatch - SPB, SS Carbon Steel Plant Indoor Air Loss of leak 10 CFR 50, Appendix J I1.A3-5 3.5.1.17 A Equipment (Structural) (Ext) ,tightness (B2.1.30) -_ Hatch - i SPB, SS Carbon Steel Plant Indoor Air Loss of material ASME Section X, II1.A3-6 3.5.1.18 Equipment (Structural) (Ext) Subsection IWE (B2.1.27) and 10 CFR 50, Appendix J (*B2.1.30)_ Hatch - MB, SLD Concrete Atmosphere/ Cracking due to Structures Monitoring IIl.A7-1 3.5.1.27 A Equipment Weather expansion Program (B2.1.32) (Structural J(Ext) Hatch - MB, SLD Concrete Atmosphere/ Loss of material Structures Monitoring IlI1.A7-5 3.5.1.26 A Equipment Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext) and cracking Hatch - MB, SLD Concrete Atmosphere/ Cracking, loss of Structures Monitoring II .A7-8 3.5.1.23 A Equipment Weather 'bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling)___ Palo Verde Nuclear Generating Station Page 3.5-53 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Buildina (Continued) ia-aicn - I' mtmuspnere/ inurease in Structures Monitoring Equipment Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, Indoor Ai Jsccling) a----
--------.... II.A3-5 -
Hatch - FB, MB, Carbon Steel Plant Indoor Air Loss of leak 10 CFR 50, Appendix J '3.5.1.17 A Personnel SLD, (Structural) (Ext) tightness (B2.11.30) Airlock SPB, SS Hatch - FB, MB, Carbon Steel Plant Indoor(Ext) (Structural) Air Loss of material ASME Section XI, II.A3-6 3.5-1.18 B Personnel SLD, Subsection IWE Airlock SPB, SS (B2.1.27) and 10 CFR 50, Appendix J Plant Indoor Air None N(o2.1.30)-'- _ Hatch - S-P B Glass Nýo -ne !V.F-6 3.2.1.52 C Personnel (Structural) (Ext) i Airlock Liner SHSPB Carbon Steel Encased in ('r.nn -rafo (PYt)
'None 1
None VII.J-21 :3.3.1.96 *1 C Containment Liner SH, SPB Carbon Steel Plant Indoor Air ILoss of material ASME Section Xl, I11.A1-11 '3.5.1.06 Containment (Structural) (Ext) Subsection IWE (B2.1.27) and 10 CFR 50, Appendix J ((B2.1.30) _ Liner Refueling ISH Stainless Encased in None None iVlI.J-17 :3.3.1.96 Steel Con crete (Ex4 ________ Palo Verde Nuclear Generating Station Page 3.5-54 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment BuildinQ (Continued) OtdllI lli fId~lFL IIIUUUI M1 O.O. I, CaIkUI Ing Steel (Structural) Liner Refueling SH Stainless Submerged SCracking Water Chemistry II1.A5-13 3.5.1.46 A Steel (Structural) (Ext) (B2.1.2) and Monitoring of the Spent Fuel Pool Water Level Penetration ISLD, Carbon Steel Plant Indoor Air jLoss of material ASME Section Xl, I1.A3-1 3.5.1.18 SPB, SS (Structural) (Ext) Subsection IWE (B2.1.27) and 10 CFR 50, Appendix J (B2.1.30) Penetration SLD, Carbon Steel Plant Indoor Air 1Cumulative Time-Limited Aging 11.A3-4 3.5.1.09 A SPB, SS (Structural) (Ext) fatigue damage Analysis evaluated for the period of extended operation Penetration SLD, Stainless Plant Indoor Air I None VII.J-15 3.3.1.94 C SPB, SS Steel (Structural) (Ext) Pipe Whip MB, SS Carbon Steel Plant Indoor Air !Loss of material Structures Monitoring III.A4-5 3.5.1.25 A Restraints & (Structural) (Ext) Program (B2.1.32) Jet Shields _ Stainless Pipe Whip MB, SS Plant Indoor Air None None VII.J-15 3.3.1.94 Restraints & Steel (Structural) (Ext) Jet Shields Stairs/ NSRS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring IIl.A4-5 i3.5.1.25 A Platforms/ (Structural) (Ext) Program (B2.1.32) Grates Palo Verde Nuclear Generating Station Page 3.5-55 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Containment Ruildinn f((.. ntinli-d) Encased in None Concrete (Ext). __ Structural Steel SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring 1ll.A4-5 3.5.1.25 ýA (Structural) (Ext)____ P~rog~am .*B1_32) Tendons SS Carbon Steel Atmosphere/ Loss of prestres*S Time-Limited Aging Hll.A1-9 3.5.1.07 A Weather Analysis evaluated for (Structural) (Ext) the period of extended operation Tfendon-s ss -c-arbon Stee Atmosphere/ iLoss of material ASME Section Xl, 'I.Al-O 13.5.1.22 A Weather Subsection IWL (Structural) (Ext) (B2.1.28) Notes for Table 3.5.2-1: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 NUREG-1801 does not address aging of Thermo-Lag materials. Palo Verde Nuclear Generating Station Page 3.5-56 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Buildina mimospnere/ LOSS O materiai lotructures ivionitoring Weather ,Program (B2.1.32) (Structura(Ext) Caulking/. HLBS, Elastomer Atmosphere/ Loss of sealing Structures Monitoring lII.A6-12 135.1.44 Sealant SH, SPB Weather Program (B2.1.32) (Structural) (Ext) Caulking! HLBS, Elastomer Plant Indoor Air ILoss of sealing !Structures Monitoring 111.A6-12 '3.5.1.44 A Sealant SH, SPB (Structural) (Ext) !Program (B2.1.32) Compressible SH Elastomer Atmosphere/ Loss of sealing ' Structures Monitoring 111I.A6-12 13.5.1.44 Joints/Seals Weather Program (B2.1.32) (Structural) (ExtL_____.... .. ..... Compressible SH Elastomer Buried (Structural) Loss of sealing Structures Monitoring III.A6-12 13.5.1.44 Joints/Seals (Ext) Program (B2.1.32) Compressible SH Elastomer Plant Indoor Air ILoss of sealing Structures Monitoring III.A6-12 13.5.1.44 A Joints/Seals (Structural) (Ext) Program (B2.1.32) i i Concrete Block FB, SH, Concrete Plant Indoor Air Cracking Fire Protection (B2.1.12) II1.A1-1 1 53.5.1.43 (Masonry SS Block (Structural) (Ext) and Masonry Wall Walls) (Masonry Program (B2.1.31) Walls) Concrete FB, MB, Concrete Atmosphere/ Cracýki-n-gdu-e -to- Structures Monitoring III.A1-2 13.5.1.27 A Elements SH, SS Weather !expansion Program (B2.1.32) t (Structural) (Ext) Palo Verde Nuclear Generating Station Page 3.5-57 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building [t*.nnfin11j*h) Concrete Concrete 'Atmosphere/ Loss of material Structures Monitoring III.A1-6 Elements 11H 8SS ISH, SIlSMu lWeather (spalling, scaling) Program (B2.1'32) (Structural _ _ (Ext) land cracking _ Concrete FB, MB, Concrete ýAtmosphere/ ICracking, loss of Structures Monitoring Ill.A1-9 3.5.1.23 A Elements SH, SS iWeather Ibond and loss of Program (B2.1.32) I(Structural) (Ext) imaterial (spalling, i ~iscaling.i Concrete 7FB, MB, Concrete IAtmosphere/ Increase in Structures Monitoring III.A1-10 3.5.1.24 A Elements SH, SS Weather iporosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, S'Atmoshe/ lscalng) Fir Concrete iAtmosphere/ !Concrete cracking !Fire Protection (B2.1.12) VII.G-30 B Concrete FB, MB, 3.3.1.66 Elements SH, SS IWeather land spalling and Structures (Structural) (Ext) I Monitonng Program S(B2.1.32) _ Concrete FB, MB, Concrete Atmosphere! TLoss of material IFire Protection (B2.1.12) VI I.G-31 13.3.1.67 Elements SH, SS Weather and Structures (Structural) (Ext) IMonitoring Program (B2.1.32) Concrete SH, SS nc-rete Cracking due to
'Buried IStructures Monitoring . 1-2 3.5127 Elements (Structural) (Ext) expansion iProgram (B2.1.32)
A Concrete SH,SS 1Concrete Buried !Cracks and 'Structures Monitoring lll.A1-3 i3.5.1.28 Elements (Structural) (Ext) distortion 1Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-58 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building L;oncrete buriea uracKing, ioss or z*tructures ionioring i1ii./-'1-4 15.0. i.15 Elements (Structural) (Ext) bond, and loss of IProgram' (B2.1.32) material (spalling, s__scaling) Concrete SH, SS IConcrete Buried Increase in Structures Monitoring III.A1-5 3.5.1.31 A Elements (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling,
'scaling) i Concrete FB, FLB, Concrete Plant Indoor Air Cracking due to Structures Monitoring ill.A1-2 3.5.1.27 A Elements SH, SPB, I(Structural) (Ext) expansion Program (B2.1.32)
SS Concrete Concrete FB, FLB, Plant Indoor Air Cracking, loss of Structures Monitoring 1lll.A1-9 3.5.1.23 KA Elements SH, SPB, !(Structural) (Ext) bond, and loss of Program (B2.1.32) SS material (spalling, Concrete _______ scaling) Concrete FB, FLB, !Plant Indoor Air !Increase in Structures Monitoring II1.A1-10 3.5.1.24 Elements SH, SPB, i(Structural) (Ext) porosity and Program (B2.1.32) SS permeability,
'cracking, loss of
?material (spalling,
_ s c a lin g ._
.......................
Concrete FB, FLB, Concrete Plant Indoor Air Concrete cracking Fire Protection (B2.1.12)iVII.G-28 3.3.1.65 B Elements SH, SPB, (Structural) (Ext) and spalling land Structures SS Monitoring Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-59 License Renewal Application g
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building uoncrete juoncrete Pl-ant indoor Air LOSS ot material I-ire Irotection (1i2.1.12) b Elements iSH, SPB (Structural) (Ext) I and Structures SS Monitoring Program ((B2.1.32) Doors SH Carbon Steel Atmosphere/ 1Loss of material Structures Monitoring II1.A1-12 3.5.1.25
'Weather *Program (B2.1.32)
I(Structural) (Ext) I _ - Doors MB, SH, Carbon Steel Plant Indoor Air Loss of material 'Structures Monitoring IIl.A1-12 3.5.1.25 A SPB (Structural) (Ext) Program (B2.1.32) FýireBgarier jFB Fire Barrier OPlant Indoor Air 1Loss of material, Fire Protection (B2.1.12): None None J, 2 Coatings/ (Cementitious (Structural) (Ext) cracking Wraps _ Coating ___ .. ...... . . _ _ _ Fire Barrier FB, HLBS, Carbon Steel Plant Indoor Air Loss of material IStructures Monitoring l11.A1-12 3.5.1.25 A Doors MB, SH, i(Structural) (Ext) Program (B2.1.32) SPB Fire Barrier FB, HLBS, Carbon Steel Plant Indoor Air Loss of material Fire Protection (B2.1.12) VIlI.G-3 3.3.1.63 Doors MB, SH, (Structural) (Ext) SPB Fire Barrier FB Elastomer Plant Indoor Air Increased !Fire Protection (B2.1.12) VII.G-1 3.3.1.61 B Seals ;(Structural) (Ext) hardness, I shrinkage and
.... !loss of strength Fire Barrier FB Fire Barrier iPlant Indoor Air Loss of material, Fire Protection (B2.1.12) None None J, 2 Seals (Ceramic (Structural) (Ext) icracking Fiber) _
Palo Verde Nuclear Generating Station Page 3.5-60 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building Uypsum/ I-r, uypsum/ mianT inaoor /ir i\4one Plaster Barrier NSRS, Plaster (Structural) (Ext) SH, SPB Hatch FL**, MB, [&da rb-on St e f ,Atmosphere/ Loss of material 'Structures Monitoring III.A1-12 A SH Weather Program (B2.1.32)
,(Structural) (Ext)
Hatch SH, SPB Carbon Steel Plant Indoor Air Loss of material !Structures Monitoring II1.A1-12 3.5.1.25 A I(Structural) (Ext) Program (B2.1.32) Hatches/Plugs SH Concrete ,Atmosphere/ Cracking due to 1Structures Monitoring III.A1-2 13.5.1.27 A iWeather expansion Program (B2.1.32) (IStructural)(E*) Hatches/Plugs ISH Concrete Atmosphere/ Loss of material 'Structures Monitoring III.A1-6 3.5.1.26 A Weather (spalling, scaling) Program (B2.1.32) 1(Structural) (Ext) and cracking) Hatches/Plugs SH Concrete6 Atmosphere/ Cracking, loss of Structures Monitoring III.A1-9 3.5.1.23 A Weather bond, and loss of Program (B2.1.32)
'(Structural) (Ext) material (spalling, sca ing_..._
Hatches/Plugs SH Concrete Atmosphere/ Increase in Structures Monitoring ýII1.A1-10 3.5.1.24 A iWeather porosity and !Program (B2.1.32) I(Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Hatches/Plugs TSH Concrete T Plant Indoor Air Cracking due to 'Structures Monitoring ILI.A1-2 13.5.1.27 A i(Structural) (Ext) expansion !Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-61 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building (Continued) Concrete Plant Indoor Air Cracking, loss of !Structures Monitoring (Structural) (Ext) bond, and loss of !,Program (B2.1.32) material (spalling, [scaling) Hatches/Plugs fSH Concrete Plant Indoor Air Increase in Structures Monitoring IllI.A1-10 3.5.1.24 ,A (Structural) (Ext) porosity and Program (B2.1.32)
'permeability,
[cracking, loss of material (spalling,
..............
.................... sc aling ) ............
....................................
Metal Siding SH Carbon Steel Atmosphere/ Loss of material .Structures Monitoring .... A.1..."2 ..............
.......
25' A Weather Program (B2.1.32)
,(Structural) (Ext) _ __
Metal Siding tSH 1Carbon Steel Plant Indoor Air Loss of material Structures Monitoring IllI.A1-12 3.5.1.25 (Structural) (Ext) ,Program (B2.1.32) Penetrations SS Carbon Steel Atmosphere/ .Loss of material ,Structures Monitoring 111.A1-12 3.5.1.25 A Weather iProgram (B2.1.32) Electrical _ (Structural (Ext) _ Penetrations Carbon Steel Encased in lNone None 1VII.J-21 3.3.1.96 C Electrical Concrete (Ext) Penetrations Carbon Steel IPlant Indoor Air Loss of material 'Structures Monitoring I .llA- 12 3.5.1.25 Electrical (Structural) (Ext) ,Program (B2.1.32) t ructures onit-oring Penetrations SS Carbon Steel Atmosphere/ -Loss of material Illl.A11-12 3.5.1.25 Mechanical 'Weather Program (B2.1.32) _, (Stru ctural,) (Ext)j-Palo Verde Nuclear Generating Station Page 3.5-62 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building t((-nntintiprt) Penetrations uarbon ,steei ilncased in None oNone Mechanical !Concrete (Ext) Penetrations Carbon Steel Plant Indoor Air Loss of material !Structures Monitoring III.A1-12 :3.5.1.25 A Mechanical (Structural) (Ext) i Program (B2.1.32) Ro6ofin'g- --- ' Elastomer . Atmosphere/ !Loss of sealing Structures Monitoring II1.A6-12 3.5.1.44 A Membrane IWeather Program (B2.1.32) ________(Structurl(xtI(2..2 Stairs/ NSRS Carbon Steel I Plant Indoor Air !Loss of material IStructures Monitoring I111.A1-12 3.5.1.25 A Platforms/ (Structural) (Ext) Program (B2.1.32) Grates Structural Steel MB, SS Cda-rbonS-teel Atmosphere/ 'Loss of material Structures Monitoring j111.A1-12 T3.5.1.25
!Weather !!Program (B2.1.32) 1(Structural)_(Ext)' _
StfructuralSteel SS Carbon Steel jEncased in None 'None VVII.J-21 3.3.1.96 Concrete (Ext) Carbon Steel IPlant Indoor Air Loss of material !Structures Monitoring Structural Steel ISH, SS IIII.A1-12 13.5.1.25 A (Structural) (Ext) Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-63 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Notes for Table 3.5.2-2: Standard Note Text A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 The NUREG-1 801 does not provide a line in which Concrete Masonry is inspected per the Fire Protection program. 2 NUREG-1801 does not provide a line in which Fire Barriers (Ceramic Fiber or Cementitious Coating) are inspected per the Fire Protection program. Palo Verde Nuclear Generating Station Page 3.5-64 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel r.ns.r*ftr Riuildinn Caulking/ Atmosphlere/ LOSS Ot sealing 1structures monitoring Sealant Weather 'Program (B2.1.32) (Structural) (Ext) Caulking! FLB, SH Elastomer iStru6ctures Monitoring II1.A6-12 3.5.1.44 DUIIU kI.IUULUIdl .LOSS 01 sealingI Sealant (Ext) Program (B2.1.32) Caulking/ FLB, SH Elastomer Plant Indoor Air !Loss of sealing 'Structures Monitoring I111.A6-12 3.5.1.44 A Sealant (Structural) (Ext) !Program-(B2.1.32) Compressible ES, SH Elastomer Atmosphere/ 'Loss of sealing Structures Monitoring I111.A6-12 3.5.1.44 A Joints/Seals Weather Program (B2.1.32) Structural) (Ext) Compressible ES, SH Elastomer Plant Indoor Air Loss of sealing Structures Monitoring Illl.A6-12 3.5.1.44 A Joints/Seals (Structural) (Ext) Program (B2.1.32) Concrete FB, MB, Concrete Atmosphere/ SCracking due to Structures Monitoring II.A3-2 3.5.1.27 A Elements SH, SS Weather expansion Program (B2.1.32) Structural (Ext) Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III1.A3-6 3.5.1.26 Elements SH, SS Weather (spalling, scaling) Program (B2.1.32) (Struct ural)_(Ext) and cracking) Palo Verde Nuclear Generating Station Page 3.5-65 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator
,,I rllr1;1rs"Itf fin, ,corIi LUI ILAIM I-D, IVID, Atmosphere/ Cracking, loss of Structures Monitoring Elements SH, SS Weather bond, and loss of Program (B2.1.32)
(Structural) (Ext) material (spalling,,I i scaling) _ _ _ Concrete FB, MB, Concrete Atmosphere/ Increase in 'Structures Monitoring III.A3-1O0 3.5.1.24 A Elements SH, SS Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, scaling _Fr Concrete FB, MB, Concrete Atmosphere/ Concrete cracking Fire Protection (B2.1.12) VII.G-30 13.3.1.66 B Elements ISH, SS Weather and spalling and Structures (Structural) (Ext) Monitoring Program Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection (B2.1.12) VII.G-31 13.3.1.67 B Elements SH, SS Weather land Structures (Structural) (Ext) !Monitoring Program
- _ ___ *L(B2.1.32) -
Concrete SH, SS Concrete Buried (Structural) Cracking due to jStructures Monitoring III1.A3-2 3.5.1.27 A Elements (Ext) expansion Program (B2.1.32) Concrete SH, SS Concrete Buried (Structural) !Cracks and' IStructures Monitoring II1.A3-3 3.5.1.28 A Elements (Ext) distortion Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-66 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator uoncrete uoncrete bunea(. L;racKing, loss OT ;structures Moniton v.v. ,. Elements (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) Concrete SH, SS Concrete Buried (Structural) IIncrease in Structures Monitoring III1.A3-5 3.5.1.31 A Elements (Ext) 1porosity and IProgram (B2.1.32)
,permeability,
!cracking, loss of material (spalling,
,scaling) !
13.5.1.27 Concrete FB, FLB, Concrete Plant Indoor Air Cracking due to.Structures Monitoring II.A3-2 A Elements SH, SS (Structural) (Ext) expansion Program (B2.1.32) C ............Pia................
.oncrete t in o o ..
.......... .... rai.n.....o-.tr..u rs....orin................iA.............
.....
Concrete FB, FLB, Plant Indoor Air !Cracking, loss of IStructures Monitoring IlII.A3-9 13.5.1.23 A Elements SH, SS (Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, Concrete Iscaling) Concrete FB, FLB, Plant Indoor Air -Increase in iStructures Monitoring III.A3-10 3.5.1.24 Elements SH, SS (Structural) (Ext) porosity and !Program (B2.1.32) permeability, i cracking, loss of I
!material (spalling, f Concrete scaling 9) __
Concrete FB, FLB, Plant Indoor Air Concrete cracking Fire Protection (B2.1.12) VlI.G-28 3.3.1.65 B Elements SH, SS (Structural) (Ext) land spalling and Structures Monitonng Program _ _ _ __ _ _ (B2.1.32) _ Palo Verde Nuclear Generating Station Page 3.5-67 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Buildinq (Continued) Component Inedd Material~t~ Environment~ Aging Effect Aging Manfagement INUREG-. Table 1 Item Notes Type Function '3/4 ~ ' <~ Requiring Pr~ogram. 1801 Vol. _______ ____ _____ ________ Managemenpt 2 I~tem\ ____ Concrete FB, FLB, Concrete Plant Indoor Air Loss of material lFire Protection (B2.1.12) VII.G-29 i3.3.1.67 B Elements SH, SS (Structural) (Ext) land Structures
,Monitonng Program 1(B2.1.32) i Doors - MB, SHf !Carbon Steel Atmosphere/ Loss of material IStructures Monitoring 11.A3-12 3.5.1.25 A Weather Program (B2.1.32)
(Structural) (Ext) Doors MB, SH Carbon Steel Plant Indoor Air Loss of material IStructures Monitoring I1I.A3-12 13.5.1.25 (Structural) (Ext) Program (B2.1.32) FB, MB, Loss of material IStructures Monitoring III.A3-12 3.5.1.25 A Fire Barrier Carbon Steel Atmosphere/ Doors SH Weather !Program (B2.1.32) (Structural) (Ext) Fire Barrier rFB, MB, Carbon Steel Atmosphere/ iLoss of material iFire Protection (B2.1.12) VII.G-4 13.3.1.63 B Doors SH Weather (Structural) (Ext) Fire Barrier FB, FLB, Carbon Steel Plant Indoor Air
,Loss of material
'Structures Monitoring i Prnnrrnm (R2 1 .39 ItII.A3-12 3.5.1.25 KA Doors MB, SH FB, B Fire Barrier FLB, Carbon Stee Plant Indoor Air ILoss of material Fire Protection (B2.1.12)I VILlG-3 13.3.1.63 Doors MB, SH (Structural) (Ext)
Elastomer B Fire Barrier WtAtmosphere/ Increased Fire Protection (B2.1.12) VIG-2 3.3.1.61 Seals Weather hardness, (Structural) (Ext) Ishrinkage and _ _ loss of strength I Palo Verde Nuclear Generating Station Page 3.5-68 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Buildina (Continued) i-ire earner r-iant. inaoor /-kir iincreasea Seals (Structural) (Ext) hardness, shrinkage and iloss of strength Hatch IMB, SH ICarbon Steel Atmosphere/ !Loss of material Structures Monitoring II.A3-12 3.5.1.25 A Weather !Program (B2.1.32) (Structural) (Ext) Hatch Carbon Steel Plant Indoor Air Loss of material iStructures Monitoring 111.A3-12 3.5.1.25 A (Structural) (Ext) !Program (B2.1.32) Hatches/Plugs MB, SH Concrete Atmosphere/ Cracking due to 'Structures Monitoring 1II.A3-2 13.5.1.27 A Weather expansion Program (B2.1.32) (Structural) (Ext) Hatches/Plugs MB, SH Concrete Atmosphere! Loss% of material IStructures Monitoring IIl .A3-6 3.5.1.26 A Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext) land cracking_____ Hatches/Plugs MB, SH Concrete Atmosphere/ eCracking, loss of IStructures Monitoring 111.A3-9 i3.5.1.23 A Weather ibond, and loss of !Program (B2.1.32) (Structural) (Ext) material (spalling, scaling) Atmosphere/ IIncrease in 'Structures Monitoring llI.A3-10 Hatches/Plugs MB, SH Concrete 3.5.1.24 A Weather 'porosity and !Program (B2.1.32) (Structural) (Ext) permeability, Icracking, loss of material (spalling,
.scaling
. . . ... ..._._.. . .
Palo Verde Nuclear Generating Station Page 3.5-69 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Buildina (Continued) Plant Indoor Air Cracking due to Structures Monitoring (Structural) (Ext) expansion !Program (B2.1.32) Hatches/Plugs MB, SH Concrete Plant Indoor Air - TCracking, loss of !Structures Monitoring I11.A3-9 3.5.1.23 A (Structural) (Ext) lbond, and loss of Program (B2.1.32) material (spalling,
;scaling)
Hatches/Plugs MB, SH Concrete Plant Indoor Air IIncrease in 'Structures Monitoring IILlA3-1O0 3.5.1.24 A (Structural) (Ext) porosity and !Program (B2.1.32) Penetrations Electrical SS Carbon Steel Atmosphere/ Weather permeability, cracking, loss of material (spalling,
,scaling Loss of material i
StructuresMonitoring Program (B2.1.32) I111.A3-12 3.5.1.25 il...... A i Structural) (Ext) _ Penetrations SS Carbon Steel Encased in None None f3.3.1.96 VII.J-21 C Electrical Concrete (Ext) Penetrations Electrical SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II1.A3-12 3.5.1.25 A (Structural) (Ext) Program (B2.1.32) Penetrations SS Carbon Steel Atmosphere/ Loss of material Structures Monitoring I1.A3-12 i3.5.1.25 Mechanical Weather Program (B2.1.32) (Structural) (Ext) P C Encased in jNone None Penetrations SS Carbon Steel VII.J-21 3.3.1.96 Mechanical Concrete (Ext) Palo Verde Nuclear Generating Station Page 3.5-70 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-3 Containments,Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Buildinc (Continued) rwinutratuons Carbon Steel Plant Indoor Air LOSS ot material btructures Monitoring ii.Ai-12 I3b. 1.2b A Mechanical (Structural) (Ext) Program (B2.1.32) Roofing SH Elastomer Atmosphere/ Loss of sealing Structures Monitoring I11.A6-12 3.5.1.44 A Membrane Weather Program (B2.1.32) _(Structural) (Ext__a Stairs/Platform NSRS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring 111.A3-12 3.5.1.25 A s/Grates (Structural) (Ext) Program (B2.1.32) Structural Steel SS Carbon Steel Atmosphere/ Loss of material Structures Monitoring I111.A3-12 3.5.1.25 A Weather Program (B2.1.32) _ Str_ al Ext _ _ Structural Stee ISS Carbon Steel Encased in !None None VII.J-21 3.3.1.96 C Concrete (Ext) Structural Steel SH, SS Carbon Steel 5Plant Indoor Air Loss of material Structures Monitoring I111.A3-12 3.5.1.25 A (Structural) (Ext) ........ .. ... . Program (B2.1.32)
.........
Palo Verde Nuclear Generating Station Page 3.5-71 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Notes for Table 3.5.2-3: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-72 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine iuoncrete FB, SH, Concrete Atmospnere/ Fire Protection (B2.1.12) (Masonry SSS Block Weather land Masonry Wall Walls) (Masonry (Structural) (Ext) I!Program (B2.1.31) _Walls) Concrete Block FB, SH, Concrete Plant Indoor Air Cracking 'Fire Protection (B2.1.12) III.A3-1 1 3.5.1.43 E, 1 (Masonry SS Block (Structural) (Ext) and Masonry Wall Walls) (Masonry ,Program (B2.1.31)
*W a*.!s) ......
Concrete SS Concrete Atmosphere/ Cracking due to ,Structures Monitoring III.A3-2 3.5.1.27 A Elements Weather 1expansion Program (B2.1.32) (Structural) (Ext) dConcrete SS . . Concrete Atmosphere/ ILoss of material---- Structures Monitoring II .A3-6 3.5.1.26 A Elements fWeather i(spalling, scaling) Program (B2.1.32) ________ ___ (Structural)(Ext) land crackinh9 3.5.1.23 iA Concrete S concrete6 Atmosphere/ Cracking, loss of !Structures Monitoring 7i ll.A3-9 Elements Weather lbond, and loss of ,Program (B2.1.32) (Structural) (Ext) material (spalling, iscaling) llI.A3-10 q3.5.1.24 6C0ncrete- 1:Cncrete'
.... - *Atmosphere/ dIncrease in Structures Monitoring A Elements Weather porosity and !Program (B2.1.32)
(Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Palo Verde Nuclear Generating Station Page 3.5-73 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building tUllruu rl ( 1 lt ,exllp UUi !Structures Monitoring 13.5.1 Elements i(Structural) (Ext) !expansion Program (B2.1.32)
-tl-Concrete SS Concrete Buried . Cracks and IStructures Monitoring IIII.A3-3 13.5.1.28 A Elements (Structural) (Ext) distortion IProgramn (132.1.32)
Concrete CoBncrete turied Cracking, loss of Structures Monitoring 'IlA3-4135.1.31 A Elements (Structural) (Ext) bond, and loss of ,Program (B2.1.32) material (spalling,
......
.......
..... . ..................... scaling) .. ........... Structures Monitoring
................. IIII.A3-4 13.5.1.31 A Concrete SS Concrete Buried i Increase in Elements (Structural) (Ext) Iporosity and Program (B2.1.32)
Ipermeability, cracking, loss of i material (spalling, iscaling) ii.s ~...................... n i..n.c.o
.. ..... .1 c.ac
.......... 111-1111.1 1.T ...t..
........
... °.............. A Co~ncrete SH, SS Concrete ;Plant Indoor Air lCracking due to St...ructures M-onitoring 11Il.A3-2 3.5.1.27 Elements
- (Structural) (Ext) expansion Program (B2.1.32) A Concrete Concrete Plant Indoor Air lCracking, loss of !Structures Monitoring 11I.A3-9 3.5.1.23 Elements (Structural) (Ext) bond, and loss of 1Program (B2.1.32)
,material (spalling,
_scali Palo Verde Nuclear Generating Station Page 3.5-74 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (Continued) %,UE lemenUL ,Plant Indoor Air Increase in jOLrULALUIrb IVIOiuILUIlr1y 11j-.ma- 1U Elements (Structural) (Ext) porosity and !Program (B2.1.32) permeability, cracking, loss of Imaterial (spalling, _ _scaling) Doors SH Carbon Steel !Atmosphere/ Loss of material !Structures Monitoring I111.A3-12 3.5.1.25 A
ýWeather Program (B2.1.32)
I(Structural) (Ext) I_______ Doors SH Carbon Steel IPlant Indoor Air !Loss of material !Structures Monitoring III1.A3-12 3.5.1.25 A (Structural).(Ext) i Program (B2.1.32) .. .25 4 4 Fire Barrier FB Fire Barrier IPlant Indoor Air ILoss of material, Y Fire Protection (B2.1.12) None None J, 2 Coatings/ (Cementitious (Structural) (E xt) cracking Wraps .Coating)
+ 4 4 Fire Barrier FB, SH Carbon Steel !Atmosphere/ Loss of material Structures Monitoring II1.A3-12 3.5.1.25 A Doors lWeather i 'Program (B2.1.32) i i(Structural)(Ext) _ __ __ __ __ __ _ _ _ _ I _ _ _ _ _ _ _ _ _ _ _ _ - ____
Fire Barrier FB, SH Carbon Steel ,Atmosphere/ Loss of material Fire Protection (B2.1.12) VII.G-4 3.3.1.63 Doors Weather (Structural (Ext) 1351.25 Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II.A3-12 3.5.1.25 A Doors (Structural) (Ext)I IProgram (B2.1.32) Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Fire Protection (B2.1.12) 3.3.1.63 B Doors (Structural) (Ext) c B i Palo Verde Nuclear Generating Station Page 3.5-75 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (Inntintio-d) I Ianagement Fire Barrier Elastomer Atmosphere! Increased Seals iWeather hardness, (Structural) (Ext) shrinkage and loss of strength F~ire Barrier FB Elastomer -Rant Indoor Air IIncreased Fire Protection (B2.1.12)iVII.G-1 3.3.1.61 B Seals (Structural) (Ext) hardness,
- shrinkage and
. . .. ..... . loss of streqgth Hatch - Carbon Steel 'Atmosphere/ Loss of material TStructures Monitoring jI1.A3-12 3.5.1.25 A
'Weather Program (B2.1.32)
_ (Structural) (Ext) _ Hatch SH Carbon Steel Plant Indoor Air 1Loss of material Structures Monitoring II.A3-1 2 3.5.1.25 A
.(Structural) (Ext) i Program (B2.1.32)
Metal Siding SH Carbon Steel 'Atmosphere/! Loss of material Structures Monitoring 11I.A3-12 3.5.1.25 A iWeather Program (B2.1.32) _(Structural) (Ext) I Metal Siding jSH Carbon Steel Plant Indoor Air 1Loss of material Structures Monitoring I111.A3-12 .3.5.1.25
+
A (Structural) (Ext) Program (B2.1.32) i + Penetrations SS Carbon Steel lEncased in 1None None 1VII.J-21 3.3.1.96 C Electrical Concrete (Ext) Penetrations Carbon Steel - Plant Indoor Air Loss of material Structures Monitoring I111.A3-12 '3.5.1.25 A Electrical iiStructural) (Ext) i Program (B2.1.32) C Penetrations Carbon Steel Encased in None None IVII.J-21 3.3.1.96 Mechanical Concrete (Ext) Palo Verde Nuclear Generating Station Page 3.5-76 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (Continued) reneuraiions uarvuri oieei rilani inuooor Mlr LOSS U1 Mat~erial zructures ivionitaring III ./-'3-I 13.5. I.L4 A Mechanical (Structural) (Ext) Program (B23.1.32) Roofing Elastomer lAtmosphere/ Loss of sealing Structures Monitoring III.A6-12 i3.5.1.44 IA Membrane Weather Program (B2.1.32)
!(Structural (Ext) _
Structural Steel SH, SS ICarbon Steel ýAtmosphere/ Loss of material Structures Monitoring II1.A3-12 13.5.1.25 A Weather Program (B2.1.32) _ StructuralL)(Ext) ......
.....
Structural Steel SS Carbon Steel lEncased in None None VII.J-21 13.3.1.96 C Concrete (Ext) Structural Steel SH, SS Carbon Steel Plant Indoor Air Loss of material "Structures Monitoring II .A3-12 13.5.1.25 A (Structural) (Ext)j Program (B2.1.32) Notes for Table 3.5.2-4: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E' Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Palo Verde Nuclear Generating Station Page 3.5-77 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Plant Specific Notes: 1 NUREG-1801 does not provide a line in which Concrete Masonry is inspected per the Fire Protection program. 2 NUREG-1801 does not provide a line in which Fire Barriers (Ceramic Fiber or Cementitious Coating) are inspected per the Fire Protection program. Palo Verde Nuclear Generating Station Page 3.5-78 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building tended Material Environm En* ing Effect Aging Management NUREG- Table 1Iitem Notes inction Requiring Program 1801 Vol. M ahLagsment 2 Item U%.,: I:U IIIIr I Elastomer JAtmosphere! Loss of sealing Structures Monitoring IlI.A6-12 i3.5.1.44 A Sealant lWeather i IProgram (B2.1.32) __(Structural) Ext) ______ C Plant Indoor Air Loss of sealing Structures Monitoring II1.A6-12 3.5.1.44 A Sealant Structu Proram (B2.3)
-ompressible ES, SH Elastomer Atmosphere Joints/Seas Weatmher/ Loss of sealing Structures rotra Monitoring II1.A6-12 3.5.1.44 Joints/Seals IWeather 5 Program (132.11.32)
(Structural) (Ext) ___ Elastmer ,uned(Structural) dCompressible ES, SH 'Loss of sealing Structures Monitoring I11.A6-12 3.5.1.44 A SJoints/Seals program, B2.1.32) Compressible iS, SH *Eiatone r Plant Indoor Air !Loss of sealing Structures Monitoring I11.A6-12 13.5.1.44 A Joints/Seals _ (Structural )_IEiL Fire Protection (B2.1.12) Concrete Block FB, SH, Concrete Plant Indoor Air Cracking I11.A3-11 3.5.1.43 E 1 (Masonry SS Block (Structural) (Ext) and Masonry Wall Walls) (Masonry Program (B2.1.31) Walls) Concrete
-Concrete 'A fFB, FLB, 'AAtmosphere/ !Cracking due to Structures Monitoring II1.A3-2 3.5.1.27 Elements MB, SH, iWeather jexpansion Program (B2.1.32)
JSPB, SS ,t(Structural)*( Ext)* Concrete Concrete FB, FLB, Atmosphere! Loss of material Structures Monitoring IIl.A3-6 3.5.1.26 IA Elements MB,. SH, Weather (spalling, scaling) Program (B2.1.32) SPB, SS S,(Struct ural!).,(Ex.), Palo Verde Nuclear Generating Station Page 3.5-79 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building 11,nnfinlinril F-D, F-L0, 1'Atmosphere/ ICracking, loss of Structures Monitoring E-Ul 1m eLts iElements MB, SH, IWeather bond, and loss of Program (B2.1.32) SPB, SS '(Structural) (Ext)l material (spalling, _____ scaling)_ SConcrete FB, FLB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3-10 13.5.1.24 Elements MB, SH, Weather porosity and Program (B2.1.32) SPB, SS (Structural) (Ext) 1permeability,
- cracking, loss of material (spalling, i
jscaling -~ 4 i Concrete FB, FLB, Concrete Atmosphere/ Concrete cracking Fire Protection (B2.1.12)!VII.G-30 3.3.1.66 B Elements MB, SH, Weather !and spalling and Structures I SPB, SS !(Structural) (Ext) Monitoring Program Concrete FB, FLB, Concrete lAtmosphere/ of material
-Loss Fire Protection (B2.1.12)iVII.G-31 33.1.67 Elements MB, SH, Weather and Structures SPB, SS (Structural) (Ext),I Monitoring Program (132.1 .32) _ _ _ _ _ _ _ _ _ _ _ _
Concrete FLB, SH, Concrete Buried Cracking due to Structures Monitoring Il.A3-2 3.5.1.27 Elements SS (Structural) (Ext) expansion Program (B2.1.32) Concrete FLB, SH, Concrete Buried Cracks and Structures Monitoring ill1.A3-3 i3.5.1.28 A Elements SS (Structural) (Ext) istortion Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-80 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging ManagementEvaluation.- Auxiliary Building (Continued) uoncreie Concrete Buried Cracking, loss of Elements (Structural) (Ext) bond, and loss of Imaterial (spalling, _ _scaling) FConcrete FLB, SH, Concrete Buried Increase in Structures Monitoring IllI.A3-5 13.5.1.31 A Elements SS (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling,
.. .sc.ling)
Concrete FB, FLB, Concrete iPlant Indoor Air }Crackingdueto Structures Monitoring ;lll.A3-2 13.5.1.27 A Elements HLBS, 1(Structural) (Ext) 1expansion Program (B2.1.32) SH, SLD, SPB, SS Concrete FB, FLB, Concrete Plant IndoorAir Cracking, loss of Structures Monitoring lll1.A3-9 13.5.1.23 Elements HLBS, (Structural) (Ext) !bond, and loss of Program (B2.1.32) SH, SLD, material (spalling, SPB, SS _ _____ sscaling.
-4.
Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring IF.A3-1O0 3.5.1.24 A Elements HLBS, (Structural) (Ext) porosity and Program (B2.1 .32) SH, SLD, Ipermeability, SPB, SS cracking, loss of material (spalling, _Iscaling) Palo Verde Nuclear Generating Station Page 3.5-81 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building (Continued) loncrele r-5, rLID, Plani inaoor i-~r Concrete cracKing u-ire r-rotecuion itiL. I. IL) VII1. k-l -0 ,. 0..1. I.Do Elements HLBS, (Structural) (Ext) and spalling and Structures SH, SLD, Monitoring Program SPB, SS ___(B2.1.32) _ _ B Concrete FB, FLB, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12) tVll G-29 [3.3.1.67 Elements HLBS, i(Structural) (Ext) and Structures SH, SLD, IMonitoring Program SPB, SS __ ____(B2J.32) III.A3-12 '3.5.1.25 Doors FLBSH Carbon Siteel Plant Indoor Air iLoss of material Structures Monitoring A SPB (Structural) (Ext) I Proqram (B2.1.32) Doors SH, SPB Stainless Steel ntIndoorAjr None None VII.J-15 13.3.1.94 C ructural) (Ext) Fire Barrier FB Fire Barrier nt Indoor Air Loss of material, IFire Protection (B2.1.12) None INone Coatings/l (Cementitious ructural) (Ext) cracking Wraps _ Coating) Fire Barrier FB, Carbon Steel nosphere/ Loss of material Structures Monitoring III.A3*12 13.5.1.25 A Doors HLBS, ather Program (B2.1.32) i _________SH, SPB rutrl Ext) ________
-I +
Fire Barrier FB, Carbon Steel nosphere/ !Loss of material Fire Protection (B2.1.12)1VII.G-4 3.3.1.63 B Doors HLBS, ather _SH, SPB ructural)(Ext) i_ Fire Barder FB, Carbon Steel nt Indoor Air !Loss of material Structures Monitoring III.A3-12 3.5.1.25 A Doors HLBS, ructural) (Ext) I Program (B2.1.32) i 1MB, SH, [SPB Palo Verde Nuclear Generating Station Page 3.5-82 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments,Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building (Continued) Doors HLBS, (Structural) (Ext) MB, SH, SPB IFB Atmosphere/ Increased Fire Protection (B2.1.12) VII.G-2 3.3.1.61 B Fire Barrier Elastomer Seals Weather hardness, (Structural) (Ext) shrinkage and loss of strength Fire Barrier FB Elastomer 17Plant Indoor Air Increased Fire Protection (B2.1.1 2)fVll.G-1 3.3.1.61 B Seals (Structural) (Ext) hardness, shrinkage and loss of strenqth Gypsum/ FB, SH Gypsum/Plaste Plant Indoor Air Cracking Fire Protection (B2.1.12) None None J, 2 Plaster Barrier r (Structural EExt Hatch SH, SPB Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II1.A3-12 3.5.1.25 A
-I- Structural)(Ext) Program B2.1.3 Hatches/Plugs FLB, MB, Concrete Atmosphere/ Cracking due to Structures Monit III.A3-2 3.5.1.27 A SH Weather 'expansion IProgram (B2.1.32)
(Structural) (Ext) Hatches/Plugs FLB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3-6 3.5.1.26 A SH Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext)'4 and crackinQ I. I. ____________ ,. - Hatches/Plugs FLB, MB, Concrete Atmosphere/ Cracking, loss of Structures Monitoring II1.A3-9 13.5.1.23 1A SH Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling,
.scaling)
Palo Verde Nuclear Generating Station Page 3.5-83 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments, Structures,and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building IrnnfintiorH) 1FLB, MB, Atmosphere/ Increase in Structures Monitoring 3.5.1.24 SH lWeather i porosity and Program (B2.1.32)
!,(Structural) (Ext) permeability, cracking, loss of material (spalling, scaling Hatches/Plugs FLB, MB, Concrete Plant Indoor Air Cracking due to Structures Monitoring II .A3-2 A SH (Structural) (Ext) expansion Prog}ram (B2.1.32) ..
Structures Monitoring II .A3-9 13.5.1.23 A Hatches/Plugs FLB, MB, Concrete Plant Indoor Air Cracking, loss of i SH ,(Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) Concrete ',Plant Indoor Air 4 4 Hatches/Plugs FLB, MB, Increase in Structures Monitoring II .A3-1O0 3.5.1.24 A SH I(Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, Structures Monitoring Penetrations Ss Carbon Steel Atmosphere! Loss of material I.A3-l 2 I:I 3.5.1.25 A Electrical Weather Program (B2.1.32) ( Structural) (Ext)I Penetrations Carbon Steel lEncased in None None 1VII.J-212 3.3.1.96 C Electrical Concrete (Ext)_- Penetrations Ss Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II .A3-12 3.5.1.25 Electrical (Structural) (Ext) Program (B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-84 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-5 Containments,Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building Penetrations iAtmosphere/! Loss of material Structures Monitoring II1.A3-12 3.b. 1.25 Mechanical Weather Program (B2.1.32) 2 (Structural) (Ext)1 Penetrations {SS Carbon Steel Encased in iNone None 1VII.J-21 13.3.1.96 C Mechanical Concrete _Ext) _ Penetrations Ss Carbon Steel Plant Indoor Air i Loss of material Structures Monitoring III .A3-12 3.5.1.25 A Mechanical (Structural) (Ext) _ Program (B2.1.32) _ Roofing SH Elastomer -Amosphere! ILoss of sealing Structures Monitoring III1.A6-12 .1.44 Membrane Weather Program (B2.1.32) 2 I(Structural) (Ext) I Stairs/ NSRS Carbon Steel Atmosphere/ Loss of material Structures Monitoring lll1.A3-12 3.5.1.25 K Platforms/ Weather Program (B2.1.32) Grates (Structural) (Ext) Stairs/ NSRS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring i11.A3-12 3.5.1.25 A Platforms/ (Structural) (Ext) Program (B2.1.32) Grates Structural Steel Carbon Steel lAtmosphere/ ILoss of material Structures Monitoring 111.A3-12 i3.5.1.25 k Weather Program (B2.1.32) (Strctural) (x) Structural Steel ISS Carbon Steel Encased in None None VII.J-21 3.3.1.96 C Concrete (Ext) + i Structural Steel I-SH I, SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring illI.A3-12 3.5.1.25 A Ectua[LE(ExI Etr ProgErm 82.1.32 _..... Palo Verde Nuclear Generating Station Page 3.5-85 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Notes for Table 3.5.2-5: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 The NUREG-1801 does not provide a line in which Concrete Masonry is inspected per the Fire Protection program. 2 NUREG-1801 does not provide a line in which Gypsum/Plaster Barriers are inspected per the Fire Protection program. Palo Verde Nuclear Generating Station Page 3.5-86 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-6 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Riuildinn Concrete Atmosphere/ Cracking due to Structures Monitoring Elements Weather Iexpansion Program (B2.1.32) (Structural) (Ext _________ Concrete SH, SS IConcrete Atmosphere! -Loss of material Structures Monitoring lII.A3-6 13.5.1.26 A Elements Weather (spalling, scaling) Program (B2.1.32) I..................
..........
I I _(Structural) (Ext) Iand cracking +/- Concrete iSH, SS Concrete Atmosphere/ lCracking, loss of Structures Monitoring II1.A3-9 3.5.1.23 M Elements Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling,
+ +
IscalinQ) -. _______________ Concrete SH, SS Concrete Atmosphere/ Increase in Structures Monitoring III.A3-10 [3.5.1.24 A Elements Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Concrete SH, SS Concrete Buried (Structural) Cracking due to Structures Monitoring III.A3-2 [3.5.1.27 A Elements (Ext) expansion Proqram (B2.1.32) Concrete SH, SS IConcrete Buried (Structural) Cracks and Structures Monitoring III.A3-3 13.5.1.28 A Elements (E
.............
x) ..distortion _Program .L..32 Palo Verde Nuclear Generating Station Page 3.5-87 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-6 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste PI;1il nrY Ifnr'fntir m M',l Buried (Structural) Cracking, loss of Structures Monitoring IIl .A3-4 3.5.1.31 A Elements (Ext) bond, and loss of Program (B2.1.32) Imaterial (spalling, Iscaling) Concrete SH, SS Concrete Buried (Structural) IIncrease in Structures Monitoring III.A3-5 .3.5.1.31 Elements (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, _ scaling) Concrete FB, SH, Concrete Plant Indoor Air Cracking due to Structures Monitoring II1.A3-2 3.5.1.27 A Elements SS (Structural) (Ext) expansion Program (B2.1.32) _ Concrete FB, SH, Concrete Plant Indoor Air Cracking, loss of Structures Monitoring II1.A3-9 3.5.1.23 A Elements SS (Structural) (Ext) Ibond, and loss of Program (B2.1.32) imaterial (spalling, scaling) Concrete FB, SH, Concrete Plant Indoor Air Increase in Structures Monitoring II1.A3-1O0 3.5.1.24 A Elements SS (Structural) (Ext) porosity and Program (B2.1.32) 1permeability, cracking, loss of material (spalling, Iscaling) Palo Verde Nuclear Generating Station Page 3.5-88 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-6 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste uoncrete 1-lanT inaoor Air uoncreie crac t-ire rrotecuon tbLz.i.iLz) iVii.u-zts .i..i.I.o Elements SS (Structural) (Ext) land spalling and Structures Monitoring Program (B2.1.32) Concrete fB, SH, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12)iVII.G-29 3.3.1.67 Elements SS (Structural) (Ext) and Structures Monitoring Program (B2.1.32)_______ Doors Carbon Steel Atmosphere/ Loss of material Structures Monitoring IIII.A3-12 3.5.1.25 A Weather Program (B2.1.32) (Structural) (Ext) Doors SH Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II1.A3-12 13.5.1.25 (Structural) (Ext) Loss of material Program (2.1.32) __ Fire Barrier FB, SH Carbon Steel Plant Indoor Air Structures Monitoring II1.A3-12 13.5.1.25 A Doors (Structural) (Ext) Loss of material Proqram_(1B2.1.32) ..... ! Fire Barrier FB, SH jCarbon Steel Plant Indoor Air Fire Protection (B2.1.12)2VII.G-3 13.3.1.63 B Doors (Structural) (Ext) Fire Barrier FB
.... ...
....
....
Elastomer ....... Plant Indoor Air t Increased Fire Protection (B2.1.12) VII.G-1 3.3.1.61 B Seals (Structural) (Ext) hardness, shrinkage and loss of strength ... Hatch Aluminum Plant Indoor Air None None III.B5-2 3.5.1.58 SH Structural (Ext) Hatch Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 3.5.1.25 K Weather L Program (B2.1.32) (trctur1!.raig(Ex t Palo Verde Nuclear Generating Station Page 3.5-89 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-6 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Riuilrlinn (CnntintiPfd) Hatch SH Plant Indoor Air Loss of material zStructures Monitoring (Structural) (Ext_ Program (B2.1.32) [Hatches/Plugs SH Concrete Atmosphere/ !Cracking due to Structures Monitoring I11.A3-2 3.5.1.27 A it Weather expansion Program (B2.1.32) (Structural)_(E x Concrete 1Loss of material Structures Monitoring III.A3-6 3.5.1.26 A Hatches/Plugs ISH Atmosphere/ Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext) ,and cracking Hatches/Plugs ISH tConcrete Atmosphere/ fr~r rL'inn 1-; ^f Structures Monitoring I111.A3-9 3.5.1.23 A Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling) Hatches/Plugs SH Concrete Atmosphere/ Increase in Structures Monitoring 11lI.A3-10 j3.5.1.24 A Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, Iscaling i i i Hatches/Plugs SH Concrete Plant Indoor Air !Cracking due to Structures Mon itoring lll.A3-2 13.5.1.27 A (tctural) (Ext) expansion Program (B2.1. Hatches/Plugs SH Concrete Plant Indoor Air Cracking, loss of Structures Mon itoring lIII.A3-9 13.5.1.23 (Structural) (Ext) bond, and loss of Program (B2.1. 32) material (spalling, 1scaling) Palo Verde Nuclear Generating Station Page 3.5-90 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-6 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Rtuilinn (f.hrntintipr) IF Plant Indoor Air Increase in Structures Monitoring III.A3-1U 3.5.1.Z4 (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, _,scaling) III1.A6-12 3.5.1.44
§SH Elastomer r Atmosphere/ Loss of sealing Structures Monitoring A Membrane Weather Program (B2.1.32)
(Structural) (Ext) Structural Steel ISH, SS Carbon St eel Atmosphere/ Loss of material Structures Monitoring II .A3-12 3.5.1.25 A Weather Program (B2.1.32) (Structural)(Ext) i i Structural Steel SH, SS Carbon St eel Plant Indoor Air Loss of material Structures Monitoring IILA3-12 13.5.1.25 A (Structural) (Ext) Procram (B2.1.32) Notes for Table 3.5.2-6: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1 801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-91 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam Caulking/ Atmospnere/ LOSS OT seaiing Structures Monitoring Sealant Weather Program (B2.1.32) ( struct uraj)j( Et),,___ Caulking! SH Elastomer Buried (Structural) Loss of sealing Structures Monitoring IIILIA6-12 3.5.1.44 A Sealant Program (B2.1.32)* Caulking/ FLB, SHElsoe Plant Indoor Air Loss of sealing Structures Monitoring IIII.A6-12 13.5.1.44 Sealant (Structural) (Ext) Program (B2.1.32) Compressible ES, SH Elastomer Atmosphere/ Loss of sealing Structures Monitoring :111.A6-12 13.5.1.44 A Joints/Seals Weather Program (B2.1.32) (Structural) (Ext)__ Compressible ES, SH Elastomer Buried (Structural) iLoss of sealing Structures Monitoring Ill.A6-12 3.5.1.44 A Joints/Seals Programj(B2.1.32) i Compressible ES, SH Elastomer Plant Indoor Air Loss of sealing Structures Monitoring Il .A6-12 13.5.1.44 Joints/Seals (Structural) (Ext) Proqram (B2.1.32)
+ +
Concrete FB, Concrete Atmosphere/ Cracking due to Structures Monitoring IILA3-2 3.5.1.27 A Elements HLBS, Weather expansion Program (B2.1.32) MB, SH, (Structural) (Ext) I SS
+ +
Concrete FB, Concrete Atmosphere/ 1Loss of material Structures Monitoring I111.A3-6 13.5.1.26 A-Elements HLBS, Weather (spalling, scaling) Program (B2.1.32) MB, SH, (Structural) (Ext) Iand cracking) SS_- Palo Verde Nuclear Generating Station Page 3.5-92 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam
.i inrnrf .'Zfn mh ir*tt lrntint
- Ho Concrete I WI, Atmosphere/ ICracking, loss ot Structures Monitori IIl.A3-9 Elements HLBS, Weather bond, and loss of Program (B2.1.32)
MB, SH, (Structural) (Ext) imaterial (spalling, Sscaling*_ SS Concrete FB, Concrete Atmosphere/ 1Increase in Structures Monitoring III.A3-1O 3.5.1.24 1A Elements HLBS, Weather porosity and Program (B2.1.32) MB, SH, (Structural) (Ext) permeability, Ss cracking, loss of material (spalling,
+
scalinl) I v.. * + Concrete FB, Concrete Atmosphere/ Concrete cracking Fire Protection (B2.1.12)vilLG- 13.3.1.66 B Elements HLBS, Weather and spalling and Structures MB, SH, (Structural) (Ext) Monitoring Program SS (82.1.32) _ _ Concrete FB, Concrete Atmosphere! Loss of material Fire Protection (B2.1,12)zVll.G- 3.3.1.67 Elements HLBS, Weather and Structures MB, SH, (Structural) (Ext) Monitoring Program SS (B2.1.32) Concrete SH, SS Concrete Buried (Structural) Cracking due to Structures Monitoring Hi11.A3-2 13.5.1.27 A Elements (Ext) Iexpansion Proqram (B2.1.32) Concrete SH, SS Concrete Buried (Structural) !Cracks and Structures Monitoring I111.A3-3 3.5.1.28 A Elements (Ext...) _ .. idistortion .Program B2.1.-32__ Palo Verde Nuclear Generating Station Page 3.5-93 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam SuDoort Structure (Continued) uoncrete jorl, Z* uoncreie uruneo koiruciurai) 1%-racKIng,losS OT oiruciures ivioniioriny Elements (Ext) bond, and loss of Program (B2.1.32) material (spalling, _scaling) C-oncrete SS ~nrt Buried (Structural) Increase in Structures Monitoring III.A3-5 3.5.1.31 A Elements (Ext) porosity and Program (B2.1.32)
!permeability,
,cracking, loss of tmaterial (spalling, i scaling)
..............
..........
,. A LI II.A3-2
. 3 . ...........
2 3.5.1.27 Concrete FEB, FLB, Concrete Plant Indoor Air Cracking due to Structures Monitoring A Elements HILBS, (Structural) (Ext) expansion Program (B2.1.32) SIH, SLD, PB, SS ii Concrete 3, FLB, FIE Concrete Plant Indoor Air Cracking, loss of Structures Monitoring A Elements HILBS, (Structural) (Ext) bond, and loss of Program (B2.1.32) iS H, SLD, material (spalling, PB, SS scaling_) B, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring IllI.A3-10 3.5.1.24 A isiLBS, (Structural) (Ext) porosity and Program (B2.1.32) H, SLD, permeability, isIPB, SSJ !cracking, loss of 1material (spalling,
... .
iscaling) Palo Verde Nuclear Generating Station Page 3.5-94 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam Support Structure (Continued) Lk iUI1rLUt irD, rLD, rI"I IL IIIUUUI /-lI Fire Protection (B2.1 .12)!VII.G-28 i3.3.1.65 Elements HLBS, (Structural) (Ext) and spalling and Structures SH, SLD, Monitoring Program SPB, SS (B2.1.32) ___ Concrete FB, FLB, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12)IVII.G-29 3.3.1.67 B Elements HLBS, (Structural) (Ext) and Structures SH, SLD, Monitoring Program i SPB, SS (1B 2.1.3_2) ........... . ... Doors MB, SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 t3.5.1.25 Weather Program (B2.1.32) (Structural) (Ext) Doors FLB, Carbon Steel Plant Indoor Air Loss of material Structures Monitoring I!1;A3-12 '3.5.1.25 A HLBS, (Structural) (Ext) Program (B2.1.32) iMB, SH, _SPB Fire Barrier FB, SH Carbon Steel -Plant Indoor Air Loss of material Structures Monitoring IIl.A3-12 13.5.1.25 A Doors S(Structural(Et Program (B2.1.32) Fire Barrier 17FB, SH Carbon Steel Plant Indoor Air Loss of material Fire Protection (B2.1v.12)VIl.G-3 13.3.1.63 Doors . . . .. _ (Structural) (Ext) Fire Barrier FB Elastomer Atmosphere! Increased Fire Protection (B2.1.12)iVlI.G-2 13.3.1.61 Seals Weather hardness, (Structural) (Ext) shrinkage and ....... .....!.
............
..............
....
loss of strength Palo Verde Nuclear Generating Station Page 3.5-95 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam Fire Barrier Fi-ant indoor Air increasea Seals (Structural) (Ext) hardness, shrinkage and
-~ 4 4 +
loss of strength ............ =
?
Hatch FLB, iCarbon Steel Plant Indoor Air 1Loss of material Structures Monitoring Ill.A3-12 3.5.1.25 A HLBS, I (Structural) (Ext) Program (B2.1.32) SH, SPB Hatches/Plugs MB, SH fC o-nc-re-t e Atmosphere/ ICracking due to Structures Monitoring III.A3-2 3.5.1.27 Weather 1expansion Program (B2.1.32) (Structural (Ext) Hatches/Plugs T MB, SH -concrete Atmosphere/ I Loss of material Structures Monitoring II1.A3-6 3.5.1.26 A Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext) land cracking ______ -,~ 4 Hatches/Plugs IMB, SH IConcrete Atmosphere/ !Cracking, loss of Structures Monitoring III.A3-9 3.5.1.23 A Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling,
........... __. scalin~L Hatches/Plugs MB, SH I Concrete Atmosphere/ Increase in Structures Monitoring III.A3-10 13.5.1.24 A Weather porosity and Program (B2.1.32)
(Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Hatches/Plugs fMB, SH Concrete Plant Indoor Air Cracking due to Structures Monitoring III.A3-2 :3.5.1.27 (Structural) (Ext) expansion Program (B2.1.32) _ Palo Verde Nuclear Generating Station Page 3.5-96 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam
.innnnrt .tnhJrfirP (tnntintied)
Plant Indoor Air uracKing, loss OT Structures Monitoring 3.5.1.23 (Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) Hatches/Plugs 1MB, SH 1Concrete Plant Indoor Air Increase in Structures Monitoring Illl.A3-10 3.5.1.24 [A (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, n....... . ..........
.............
Penetrations SS ICarbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 3.5.1.25 A Electrical Weather Program (B2.1.32) (Structural) (Ext) Penetrations SS Carbon Steel Encased in None None VII.J-21 3.3.1.96 C Electrical Concrete ýE I Penetrations Ss Carbon Steel Plant Indoor Air iLoss of material Structures Monitoring III.A3-12 13.5.1.25 Electrical (Structural) {_t- Program (132.11.32) Penetrations Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 i3.5.1.25 A Mechanical Weather Program (B2.1.32) (Structural) (Ext)I Penetrations Carbon Steel Encased in 'None None IVII.J-21 3.3.1.96 C Mechanical Concrete (Ext) i Penetrations SS !Carbon Steel Plant Indoor Air Loss of material Structures Monitoring III.A3-12 3.5.1.25 1A Mechanical 1-- (Structu~ral) (E~xt) ___ Program (B2.1.32)_ Palo Verde Nuclear Generating Station Page 3.5-97 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-7 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Main Steam Support Structure (Continued) Component Intended Material Environment Aging Effect Aging Maagement NUREG- Table 1 Item Notes
- Type . Function Requiring Program: . 1801 Vol.
Roofing SH Elastomer Atmosphere/ iLoss of sealing Structures Monitoring lIII.A6-12 3.5.1.44 A Membrane Weather Program (B2.1.32) (Structural) (Ext) Stairs/ NSRS Carbon Steel Plant Indoor Air 'Loss of material lStructures Monitoring III.A3-12 53.5.1.25 AK Platforms/ (Structural) (Ext) Program (B2.1.32) Grates Structural Steel S Carbon Steel Atmosphere/ Loss of material Structures Monitoring 1Il.A3-12 3.5.1.25 Weather Program (B2.1.32) I (Structural)(x_ _ _ ___ _ Structural Steel SH, SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring III.A3-12 3.5.1.25 (Structural)a ExtProram (13..32) _ __ Notes for Table 3.5.2-7: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1.801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-98 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-8 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Station Blackout GeneratorStructures Elements k-Ul 1L;1ULU Weather 1expansion Program (B2.1.32) III3 (Structural) (ýExt) il.A3-6 13.5.1.26 A Concrete SS Concrete Atmosphere/ Loss of material Structures Monitoring i--lemenLS Weather (spalling, scaling) Program (B2.1.32) (Structural) (Ext and cracking Concrete SS Concrete Atmosphere/ Cracking, loss of Structures Monitoring II1.A3-9 13.5.1.23 !A Elements Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling)_ Concrete SS Concrete Atmosphere/ Increase in Structures Monitoring III.A3-10 13.5.1.24 1A Elements Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Concrete SS IConcrete Buried (Structural) Cracking due to Structures Monitoring I111.A3-2 '3.5.1.27 A Elements (Ext) expansion Program (B2.1.32 _ _ Concrete SS IConcrete Buried (Structural) Cracks and Structures Monitoring il1.A3-3 3.5.1.28 Elements distortion Program B2.1.32ý _, _ I___I Palo Verde Nuclear Generating Station Page 3.5-99 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-8 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Station Blackout 1--nmrfn~r Qfn ifh irm (t'*nnfiindl ,H D. .. ;-A LUI V~ k%: ULAUIC1Il) '-A~ Q...RII , IUj, uI Structures Monitoring A Elements (Ext) !bond, and loss of Program (B2.1.32) imaterial (spalling, _____________ Iscaling) Concrete SS Concrete Buried (Structural) Increase in Structures Monitoring 1111.A3-5 3.5.1.31 A Elements (Ext) i porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, scaling) Concrete SS Concrete Plant Indoor Air ' Cracking due to Structures Monitoring III.A3-2 13.5.1.27 A Elements (Structural) (Ext) expansion Program (B2.1.32) Concrete SS Concrete Plant Indoor Air iCracking, loss of Structures Monitoring TII.A3-9 43.5.1.23 Elements (Structural) (Ext) bond, and loss of Program (B2.1.32)
!material (spalling,
____________ scaling[) Concrete SS Concrete Plant Indoor Air IIncrease in Structures Monitoring III.A3-10 3.5.1.24 K Elements (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of Imaterial (spalling, scaling) Doors SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring lI1.A3-12 3.5.1.25 Weather Program (B2.1.32)
-(St§ructural,)AU,_
Palo Verde Nuclear Generating Station Page 3.5-100 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-8 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Station Blackout GeneratorStructures (Continued) riani inooor /ir (Structural) (Ext Metal Siding ISH !Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 13.5.1.25 A Weather Program (B2.1.32) (Structural) (Ext) i i Structural Steel [SH, SS Carbon Steel Atmosphere/ Loss of material Structures Monitoring I1.A3-12 13.5.1.25 A Weather Program (B2.1.32) (Structural (Extý Structural Steel SH, SS Carbon Steel Encased in None None VII.J-21 3.3.1.9 C Concrete {Ext)__ Structural Steel SH, SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring tIl .A3-12 3.5.1.25 A Sjrctural* )(ExtL Program_(B2.1.32) _ Notes for Table 3.5.2-8: Standard Note Text A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-101 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Atmospnere/ LOSS OT seaing structures Monitoring Sealant Weather Program (B2.1.32) (Structural) (Ext) 1 Caulking/ FLB, SH Elastomer Buried (Structural) ýLoss of sealing Structures Monitoring III.A6-12 13.5.1.44 A Sealant Program (B2.1.32) Caulking/ FLB, SH Elastomer Plant Indoor Air :Loss of sealing Structures Monitoring III.A6-12 3.5.1.44 Sealant (Structural)(Ext) Program (B2.1.32) + 4 Compressible SH, SPB !Elastomer Treated Borated Loss of sealing Structures Monitoring III.A6-12 13.5.1.44 A Joints/Seals Water (Ext) Program (B2.1.32) Concrete MB, SH, Concrete Atmosphere/T Cracking due to Structures Monitoring I11.A5-2 13.5.1.27 A Elements SS Weather expansion Program (B2.1.32) (Structural) (Ext) I Concrete MB, SH, Concrete Atmosphere/ Loss of material Structures Monitoring IIl.A5-6 13.5.1.26 A Elements SS Weather 1(spalling, scaling) Program (B2.1.32) (Structural) (Extý and cracking Concrete MB, SH, Concrete Atmosphere/ Cracking, loss of Structures Monitoring III.A5-9 13.5.1.23 A Elements SS Weather !bond, and loss of Program (B2.1.32) (Structural) (Ext) :material (spalling, [... L...' .............................
........... ..................]scaling)
.......................................... ....... ii I{ ...............
..... . .....................
.... .. .......... i ~ ......
1 24...
........
.......
....
Concrete MB, SH, Concrete Atmosphere/ !Increase in Structures Monitoring Ill A5-i 0 13.5.1.24 A Elements SS Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of imaterial (spalling,
.. ................ ss.....i....
c a ing ) 1 Concrete SH,"SS concrete Buried (Structural) ':Cracking due to Siruciures Monitoring .......... III .A5-2 3.5.1.27 A Elements j(Ext) _ _ expansion ]Program (B2.1 _ Palo Verde Nuclear Generating Station Page 3.5-102 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging ManagementEvaluation - Fuel Building (Continued) ýunr.iuie DUIIUU O [ ULAUI di) t-1dLIKb dII1U POrogULram IVIU(BlLU1.32Y Elements ___I distortion Program (132.1.32) Concrete SH, SS Concrete Buried (Strructural) !Cracking, loss of Structures Monitoring III.A5-4 13.5.1.31 A Elements (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) Concrete Sss Concrete Buried (Structural) 'Increase in IStructures Monitoring IIIL.A5-5 3.5.1.31 A Elements (Ext) porosity and !Program (B2.1.32) permeability, cracking, loss of material (spalling, scaling) 4- 4 Concrete FB, FLB, Concrete Plant Indoor Air Cracking due to !Structures Monitoring 3.5.1.27 A Elements jexpansion i II A5-2 SH, SS (Structural) (Ext) SCracking, loss of IProgram (B2.1.32) -~ + Concrete FB, FLB, Concrete Plant Indoor Air Structures Monitoring ll1.A5-9 3.5.1.23 A Elements SH, SS (Structural) (Ext) ibond, and loss of !Program (B2.1.32) material (spalling, scaling) 4 4- 4- 1 Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring II1.A5-10 3.5.1.24 A Elements SH, SS (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, Sscaling) Palo Verde Nuclear Generating Station Page 3.5-103 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building (t.nnftintiiari) Concrete FB, FLB, Concrete Plant Indoor Air Elements SH, SS (Structural) (Ext) ,and spalling and Structures
,,Monitoring Program (12.1.32) .
Concrete FB, FLB, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12) VII.G-29 13.3.1.67 B Elements .SH, SS (Structural) (Ext) and Structures iMonitoring Program ((B2.1.32) Doors. SH Carbon Steel Atmosphere/ Loss of material §stucturesMonitoring .I.... I.A5-12 .3.5.1.25 A Weather Program (B2.1.32) (Structural (Ext)_ Doors V13, I Carbon Steel Plant Indoor Air Loss of material
'*(Struct ural) .(Ext) ........ ................
iStructures Monitoring IIlI.A5-12 3.5.1.25 A Program (B2.1.32) Fire Barrier IFB, HLBS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring 11I.A5-12 3.5.1.25 A
.Doors . (Structural) (Ext) _ Program (3B2.1.32) .
Fire Barrier SH_]4H-LBS, Carbon Steel Plant Indoor Air FB, Loss of material ,Fire Protection (B2.1.12) V*I .G-3 3.3.1.63 B [Doors SH LStructural) (Ext) " Fire Barrier Elastomer Atmosphere/ Increased Fire Protection (B2.1 .112) VII.G-2 3.3.1.61 B Seals Weather Ihardness, 1FB (Structural) (Ext) shrinkage and loss of strength Fire Barrier IEliastomer Plant Indoor Air Increased .Fire Protection (B2.1.1i-2)VII:.G-1 *3.3.1.6Y Seals (Structural) (Ext) hardness, Ishrinkage and
'loss of strength Palo Verde Nuclear Generating Station Page 3.5-104 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building (Continued) Component Intended Material Environment, Aging Effect* fAging Management NUREG- Table 1 Item Notes Type SFunction Requiring Prami 1801 Vol. ________ _____ _ __ _ __ _________ Management _ _________ 2 Item _____ ____ IGate 1SPB3 Stainless fTreated Borated Cracking Water Chemistry IlIl.A5-13 '3.5.1.46 A ISteel IWater (Ext) (B2.1.2) and Monitoring of the Spent Fuel Pool Water Level , Hatch IMB, M SH Carbon Steel Atmosphere/ SHWeather of matriaFi
- Loss Structures Monitoring III.A5-12 3.5.1.25 A Program (B2.1.32)
_(Structural)(Ext) Hatch FB, FLB,. Carbon Steel Plant Indoor Air Loss of material 2 3.5.1.25 A MB, SH (Structural) (Ext) Program (B2.1.32) Hatch FIIFIB, FLB3, Carbon Steel Plant Indoor Air 'Loss of material Fire Protection (132.1 .12) VI I.G-3 Hatches/Plu gs 1MB, SH (§Iructua),x!. IM ..B",' -SH...Concrete Atmosphere/ Cracking due to Structures Monitoring IILI.A5-2 3.5.1.27 Weather expansion Program (B2.1.32) (Structural) (Ext) Hatches/Plugs MMB, SH Concrete Atmosphere! Loss of material Structures Monitoring IILA5-6 S3.5.1.26 A Weather 1(spalling, scaling) Program (B2.1.32) (Structural) (Ext) !and cracking Hatches/Plugs MB, SH Concrete Atmosphere/ !Cracking, loss of Structures Monitoring IlIlLA5-9 f3.5.1.23 A Weather ',bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, Hatches/Plugs IMB, SH Concrete Atmosphere/
!scaling)
Increase in Structures Monitoring Weather' porosity and Program (132.1.32) I(Structural) (Ext) 1permeability, Icracking, loss of material (spalling, scaling),. Palo Verde Nuclear Generating Station Page 3.5-105 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building (Continued) riani inaoor Flr k*rac ng ue to otructures vlonlioring St ructural) (Ext ex.pansion Program 2.1.32 Hatches/Plugs IMB, SHSHVIb,Concrete ri uoncreie Plant Indoor Air (Structural) (Ext) Cracking, loss of ibond, and loss of Structures Monitoring Program (B2.1.32) 111.A5-9 3.5.1.23 A Imaterial (spalling, Iscaling Hatches/Plugs -MB, SH Concrete Plant Indoor Air Increase in Structures Monitoring (Structural) (Ext) porosity and Program (132.1.32) permeability,
!cracking, loss of material (spalling, scaling)
Liner Spent SPB Stainlessel Encased in None None VII.J-17 3.3.1.96 Fuel Pool ISteel Concrete Ext.. i Liner Spent SPB Stainless Plant Indoor Air None None VII.J-15 3.3.1.94 Fuel Pool (Structural) (Et)_ Steel Liner Spent SPB Stainless Treated Borated Cracking IWater Chemistry III1.A5-13 3.5.1.46 A Fuel Pool Steel Water (Ext) l(B2.1.2) and Monitoring
!of the Spent Fuel Pool 1Water Level Penetrations SS Carbon SteEI1Atmosphere/ i Loss of material Structures Monitoring l1l.A5-12 13.5.1.25 A Electrical Weather Program (B2.1.32)
(Structural) Ext________ _ Penetrations ~SS Carbon SteEeI Encased in !None INone TVII.J-21 13.3.1.96 Electrical Concrete (Ext) __ _ Penetrations SS 1I1I.A5-12 3.5.1.25 Carbon Stee,1 Plant Indoor Air Loss of material 'Structures Monitoring Electrical j Structural)AExt]Q __.Prooram (1B2.1.32) Palo Verde Nuclear Generating Station Page 3.5-106 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building Fenetrations Atmospnere/ LOSS OT maieriai structures monitoring Mechanical Weather Program (B2.1.32) (Structural Ext _ Penetrations Iss Carbon Steel Encased in None None IVII.J-21 13.3.1.96 C Mechanical Concrete (Ext) Penetrations SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II1.A5-12 3.5.1.25 A Mechanical (Structural) (Ext) Program (B2.1.32) Roofing iSH Elastomer Atmosphere Loss of sealing Structures Monitoring I111.A6-12 13.5.1.44 A Membrane Weather IProgram (B2.1.32) (Structural )(Ext _ _ _ " _ Sairs/ Carbon Steel Plant Indoor Air
'NSRS Loss of material Structures Monitoring I:II.A5-12 13.5.1.25 Platforms/ (Structural) (Ext) Program (B2.1.32)
Grates Structural Steel SS Carbon Steel Atmosphere/ Loss of material Structures Monitoring II1.A5-12 13.5.1.25 Weather Program (B2.1.32) (Structural) (Ext ) __ _ _ _ _ Structural Steel ES Carbon Steel Buried (Structural) Loss of material !Structures Monitoring None None J (Ext ______________ Program (132.1.32). _ ___ _ _ _ _ Structural Steel SS Carbon Steel Encased in !None None IVII.J-21 13.3.1.96 Concrete (Ext) _ " _ Structural Steel SH, SS Carbon Steel Plant Indoor Air ILoss of material Structures Monitoring II1.A5-12 13.5.1.25 A (§Structural5Ext) ........ Program (1B2.1.32) _ Palo Verde Nuclear Generating Station Page 3.5-107 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Notes for Table 3.5.2-9: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-108 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Spray Pond uauIKInc Atmospnere/ !LOSS or seaiing tiructures monioring Sealant Weather Program (B2.1.32) (Structural)_ExtL)_________ HS, SPB Buried (Structural) !Loss of sealing Structures Monitoring II1.A6-12 13.5.1.44 Caulking/ Elastomer Sealant Proaram (B2.1.32) + i t Caulking/ HS, SPB Elastomer Submerged Loss of sealing Structures Monitoring III.A6-12 3.5.1.44 A Sealant (Structural) (Ext) Program (B2.1.32) __________ + Concrete HS, MB, Concrete Atmosphere/ Cracking, loss of Regulatory Guide 1.127, II1.A6-1 3.5.1.34 A Elements SH, SS Weather ibond, and loss of Inspection of Water-(Structural) (Ext) material (spalling, Control Structures scaling) Associated with Nuclear Power Plants (B2.1.33) Concrete HS, MB, Concrete Atmosphere/ SCracking due to Regulatory Guide 1.127, 1II.A6-2 13.5.1.36 A Elements SH, SS Weather texpansion Inspection of Water-(Structural) (Ex t) i Control Structures Associated with Nuclear Power Plants (B2.1.33) 1 Concrete HS, MB, Concrete Atmosphere/ Loss of material Regulatory Guide 1.127, III.A6-5 3.5.1.35 A Elements SH, SS Weather (spalling, scaling) Inspection of Water-(Structural) (Ex t) land cracking Control Structures Associated with Nuclear Power Plants 2.1.33L Palo Verde Nuclear Generating Station Page 3.5-109 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Spray Pond and Associated Water Control Structures (Continued) 1uoncreie uuncrete Buried (Structural) Cracking due to rUYUdlU1y %.ýUIUIU 1. 1/l, III1./A-ZD/ 13.0. I.Ou - Elements (Ext) expansion Inspection of Water-
;Control Structures :
!Associated with Nuclear I Power Plants (B2.1.33) _
Concrete HS, SS Concrete Buried (Structural) Ilncrease in Regulatory Guide 1.127,: III.A6-3 3.5.1.34 A Elements (Ext) porosity and Inspection of Water-permeability, Control Structures cracking, loss of Associated with Nuclear material (spalling, Power Plants (B2.1.33) __________ scaling) Concrete HS, SS Concrete Buried (Structural) TCrcks and Structures Monitoring II1.A6-4 3.5.1.28 A Elements (Ext) distortion ProEgram (B2.1.32) _ Con-cret e FB, HS, Concrete Plant Indoor Air !Cracking, loss of Regulatory Guide 1.127, III.A6-1 13.5.1.34 A Elements SH, SS (Structural) (Ext) ibond, and loss of Inspection of Water-Imaterial (spalling, Control Structures Iscaling) Associated with Nuclear Power Plants B2.1.33)___ Concrete FB, HS, Concrete Plant Indoor Air Cracking due to Regulatory Guide 1.127, III.A6-2 13.5.1.36 A Elements SH, SS (Structural) (Ext) expansion Inspection of Water-Control Structures I Associated with Nuclear I Power Plants (B2.1.33) i ------------- Palo Verde Nuclear Generating Station Page 3.5-110 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Spray Pond uoncrete L;oncrete v'iant maoor Air uoncrete cra( i-ire I-'rotection (bz.l .gz)1 vii.u-zoj Elements SH, SS (Structural) (Ext) and spalling and Structures Monitoring Program I
+
(B2.1.32) i
÷+
Concrete FB, HS, Concrete Plant Indoor Air Loss of material Fire Protection (B2.1.12)TVII.G-29 3.3:1.67 B Elements SH, SS (Structural) (Ext) and Structures Monitoring Program _ _ Concrete Concrete Submerged Cracking due to Regulatory Guide 1.127,11l.A6-2 3.5.1.36 A Elements (Structural) (Ext) expansion Inspection of Water-HS, SS Control Structures Associated with Nuclear Power Plants (B2.1.33) __ Concrete HSSS Concrete Submerged Increase in Regulatory Guide 1.127, 111.A6-6 3.5.1.37 A Elements (Structural) (Ext) porosity and Inspection of Water-tHS, SS permeability, loss Control Structures of strength Associated with Nuclear Poler Pants g2.1 .33 -~ Concrete Concrete Submerged Loss of material Regulatory Guide 1.127, III.A6-7 3.5.1.45 A Elements (Structural) (Ext) Inspection of Water-Control Structures Associated with Nuclear Power Plants (B2.1.33) Hatch SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring IIlI.A6-1 1 3.5.1.47 E, 1 Weather Program (B2.1.32) (Structural)_(Ext)I Palo Verde Nuclear Generating Station Page 3.5-111 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Spray Pond and Associated Water Control Structures (Continued) 61- luaroon zieei *iani inaoor /Air LOSS OT materiai 01ructures iviorlitrigiy II./AKo- I io.u.I1.41 (Structural) (Ext) _ Program (B2.1.32) ___ Hatches/Plugs SH Concrete Atmosphere/ Cracking, loss of Regulatory Guide 1.127, 1lII.A6-1 3.5.1.34 A Weather bond, and loss of Inspection of Water-(Structural) (Ext) Imaterial (spalling, Control Structures scaling) Associated with Nuclear Power Plants (B2.1.33) S 6.nConcrete ........,Atmosphere/ Cracking due to 3.5.1.36 Hýf6h-6ijlýil-66i' Regulatory Guide 1.127, 111.A6-2 Weather expansion Inspection of Water-(Structural) (Ext) Control Structures Associated with Nuclear IPower Plants (B2.1.33) Hatches/Plugs SH Concrete Atmosphere/ ,Loss of material Regulatory Guide 1.127, 111 .A6-5 13.5.1.35 A Weather 1(spalling, scaling) Inspection of Water-(Structural) (Ext) and cracking Control Structures Associated with Nuclear Power Plants (B2.1.33) Hatches/Plugs 1MB, SH, iConcrete Plant Indoor Air Cracking, loss of Regulatory Guide 1.127, 11II.A6-1 13.5.1.34 A (Structural) (Ext) bond, and loss of Inspection of.Water-material (spalling, Control Structures scaling) Associated with Nuclear Power Plants B2.1.33) _ Hatches/Plugs MB, SH, Concrete Plant Indoor Air Cracking due to Regulatory Guide 1.127, II1.A6-2 13.5.1.36 (Structural) (Ext) expansion Inspection of Water-Control Structures Associated with Nuclear Power Plants (B2.1.33) 1 Palo Verde Nuclear Generating Station Page 3.5-112 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Spray Pond
.nH A_.nninti Wnti r (t, nr nt l t.qr,
,ttrr,-_. (Ulnntintior)
Copper, Ii Loss of material Structures Monitoring 1None Program (B2.1.32) Structural Steel MB, SH, ICarbon Steel Atmosphere/ Loss of material Structures Monitoring IlI1.A6-11 13.5.1.47 E, 1 SS Weather Program (B2.1.32) (Structural) (Ext) Structural Steel ISH, SS tCarbon Steel Plant Indoor Air Loss of material Structures Monitoring IIl.A6-1 13.5.1.47 E, 1 (Structural) (Ext) Program (B32.1.82) Structural Steel NSRS Carbon Steel Submerged Loss of material Structures Monitoring I 1 13.5.1.47 (Structural) (Ext) Program (12.1.32)______ Structural Steel DF Stainless Atmosphere/ None None None None G Steel Weather (Structural)A(ExtL Notes for Table 3.5.2-10: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 NUREG 1801, line III.A6-11 specifies Reg Guide 1.127 as the program for metal components in water-control structures. Reg Guide 1.127 does not address metal components, so the Structures Monitoring Program is used. 2 NUREG-1801 does not provide a line in which copper alloy screens are inspected per the Structures Monitoring Program. Palo Verde Nuclear Generating Station Page 3.5-113 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank Foundationsand Shells 4 ItU1 Concrete n/1 uoncr, Atmospnere/ LracKing aue to Structures Monitoring iIII.A7-1 3.5.1.27 (Condensate Weather
- t:AIJdIl I;*IUI I Program (B2.1.32)
Storae T ank) _(Structural)_(Ext) Concrete Atmosphere/ !Loss of material Structures Monitoring IlII.A7-5 - 3.5.1.26 A (Condensate Weather (spalling, scaling) Program (B2.1.32) Storage TankL (Structural)(Ext) land cracking Concrete MB, SS Atmosphere/ Cracking, loss of Structures Monitoring II.A7-8 3.5.1.23 Ak (Condensate Weather !bond, and loss of Program (B2.1.32) Storage Tank) (Structural) (Ext) material (spalling, [scaling Concrete MB, SS Atmosphere/ lIncrease in Structures Monitoring III.A7-9 3.5.1.24 A (Condensate Weather porosity and Program (B2.1.32) Storage Tank) (Structural) (Ext) permeability, cracking, loss of material (spalling, Iscalinq) Concrete Buried (Structural) [Cracking due to Structures Monitoring II1.A7-1 ,3.5.1.27 A (Condensate (Ext) expansion Program (B2.1.32) Concrete Buried (Structural) Cracks and Structures Monitoring .lI.A7-2 3.5.1.28 A (Condensate (Ext) distortion Program (B2.1.32) Storage Tank) Palo Verde Nuclear Generating Station Page 3.5-114 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank
*rw Inr~nfrnn o *nnH Q1hMll0 Ir"*nifint#intH aUI IAI 0 Lt; L.Ul IOU Cracking, loss of Structures Monitori (Condensate (Ext) bond, and loss of Program (B2.1.32)
Storage Tank) material (spalling, scalingi) Concrete SS lConcrete Buried (Structural) Increase in Structures Monitoring III.A7-4 3.5.1.31 A (Condensate (Ext) porosity and Program (B2.1.32) Storage Tank) permeability, cracking, loss of material (spalling, scaling) Concrete SS Concrete Atmosphere/ Cracking due to Structures Monitoring III.A8-1 3.5.1.27 A (Reactor Weather expansion Program (B2.1.32) Makeup Water (Structural) (Ext) Tank)_ Concrete SS Concrete Atmosphere/ Loss of material Structures Monitoring ll.A8-5 i3.5.1.26 A (Reactor Weather (spalling, scaling) Program (B2.1,32) Makeup Water (Structural) (Ext) and cracking Tank) II - ---------------------
-
Concrete SS Concrete Buried (Structural) Cracking due to Structures Monitoring III.A8-1 '3.5.1.27 A (Reactor (Ext) expansion Program (B2.1.32) Makeup Water Tank) Palo Verde Nuclear Generating Station Page 3.5-115 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank Foundationsand Shells (Continued) Concrete DUIIIUu Structures Monitoring (Reactor (Ext) distortion Program (132.1.32) Makeup Water Tank) Concrete SS !Concrete Buried (Structural) TCracking, loss of Structures Monitoring III.A8-3 3.5.1.31 A (Reactor (Ext) bond, and loss of Program (B2.1.32) Makeup Water material (spalling, Tank) - - Concrete Concrete Buried (Structural) Increase in Structures Monitoring I/I.A8-4 3.5.1.31 (Reactor (Ext) porosity and Program (B2.1.32) Makeup Water permeability, Tank) cracking, loss of
,material (spalling, Concrete MB, SS Concrete Atmosphere/
scaling) ICracking due to Structures Monitoring J11.A7-1 13.5.1.27 A (Refueling Weather expansion Program (B2.1.32) Water Tank) (Structural) (Ext) Concrete MB, SS Concrete Atmosphere! Loss of material Structures Monitoring IlI .A7-5 3.5.1.26 (Refueling Weather 1(spalling, scaling) Program (B2.1.32) Water Tank) (Structural) (Ext) land +crackin-a 4 Concrete MB, SS Concrete Atmosphere/ lCracking, loss of Structures Monitoring I1II.A7-8 3.5.1.23 A (Refueling Weather bond, and loss of Program (B2.1.32) Water Tank) (Structural) (Ext) material (spalling, iscaling) Palo Verde Nuclear Generating Station Page 3.5-116 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank t Fndinriqtinn.s *nd £hRI.lhnl.* (.nninti-.d) Concrete Atmosphere/ increase in ,structures Monitonl (Refueling Weather porosity and Program (B2.1.32) Water Tank) (Structural) (Ext) permeability, cracking, loss of material (spalling, scaling) Concrete SS Concrete Buried (Structural) Cracking due to Structures Monitoring III.A7-1 3.5.1.27 (Refueling (Ext) expansion Program (B2.1.32) Water Tank Concrete SS Concrete Buried (Structural) Cracks and Structures Monitoring III.A7-2 3.5.1.28 K (Refueling (Ext) distortion Program (B2.1.32) Water Tank) .. Concrete SS Concrete Buried (Structural) Cracking, loss of Structures Monitoring III.A7-3 3.5.1.31 A (Refueling (Ext) bond, and loss of Program (B2.1.32) Water Tank) material (spalling, scaling) _ Concrete SS Concrete Buried (Structural) Increase in Structures Monitoring II1.A7-4 3.5.1.31 A (Refueling (Ext) porosity and Program (B2.1.32) Water Tank) permeability, cracking, loss of material (spalling, scaling) Titcihi7 rSH 7 Carbon Steel Atmosphere/ Loss of material Structures Monitoring 1II.A8-8 3.5.1.25 A Weather Program (B2.1.32) (Structural) (Ext) Palo Verde Nuclear Generating Station Page 3.5-117 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Tank Foundationsand Shells (Continued) rmooing Atmosphere/ Loss of sealing Structures Monitoring II1I.A6-12 3.5.1.44 Membrane Weather Program (B2.1.32) _(Structural) .(Ext) _ _ _ _ Structural Steel MB, SS Carbon SteelI Atmosphere! i-Loss of material Structures Monitoring III.A7-10 3.5.1.25 A Weather Program (B2.1.32) Structural) (Ext) _ Structural Steel 1SS [Carbon Steel Encased in None None VII.J-21 '3.3.1.96 AC { Structural Steel SSS Concrete (Et) Carbon Steel Plant Indoor Air (Structural) (Ext) __ Loss of material __ Structures Monitoring Program (B2.1.32) _ Ill A7-10 _ _ 3.5.1.25 _ Notes for Table 3.5.2-11: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-118 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-12 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Transformer Foundationsand ElectricalStructures Caulking/ *1"r Aimospnere/ baruciures z ivionitoring ,.'i.D. °1.44 Sealant Weather Program (B2.1.32) (Structural)_(Ext) Caulking/ SH Elastomer Buried Loss of sealing Structures Monitoring II1.A6-12 13.5.1.44 Sealant (Structural) (Ext) .... Proaram (B2.1.32)
............- I Concrete FB, Concrete Atmosphere/ Cracking due to Structures Monitoring II1.A3-2 3.5.1.27 A Elements NSRS, SS Weather expansion Program (B2.1.32)
'Structural) (Ext Concrete Concrete Atmosphere/ Loss of material Structures Monitoring II1.A3-6 3.5.1.26 A Elements NSRS, SS Weather (spalling, scaling) Program (B2.1.32)
(Structural) (Ext) and cracking Concrete FB, Concrete Atmosphere/ Cracking, loss of Structures Monitoring II1.A3-9 3.5.1.23 A Elements NSRS, SS Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling) Concrete FB, Concrete Atmosphere/ Increase in porosity Structures Monitoring Ill.A3-10 13.5.1.24 A Elements INSRS, SS Weather and permeability, Program (B2.1.32) (Structural) (Ext) cracking, loss of material (spalling, 1scaling) Palo Verde Nuclear Generating Station Page 3.5-119 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-12Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Transformer Foundationsand ElectricalStructures (Continued) Componen~t Intended 1Envi Material~~ onrnent Aging Effect ~ Aging Management NUREG- Table I Item Notes
~Type~ Function Requiring ~ Program ~ 1801 Vol. ~
_______ _____ I________ Management >2 Item Concrete Atmosphere/ Concrete cracking Fire Protection (B2.1.12):VII.G-30 3.3.1.66 B FB, SS IConcrete Elements Weather and spalling and Structures (Structural) (Ext) Monitoring Program _(B*2.1.2 __ _ _ _ ___ Concrete iFB, SS Concrete Atmosphere/ Loss of material Fire Protection (B2.1.12)'VII.G-31 13.3.1.67 Elements Weather and Structures (Structural) (Ext) Monitoring Program (B21.32) _ _ _ Concrete NSRS, SSConcrete Buried Cracking due to Structures Monitoring III.A3-2 i3.5.1.27 A Elements (Structural) (Ext) expansion Program (B2.1.32) _ _,__ Concrete ISS Concrete Buried Cracks and Structures Monitoring I111.A3-3 3.5.1.28 A Elements _ (Structural xt) distortion Program (B2.1.32)_ _ Concrete N, , SS Concrete Buried Cracking, loss of Structures Monitoring III.A3-4 3.5.1.31 Elements (Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling,) _ , _ Concrete SS Concrete
!NSRS, Buried Increase in porosity Structures Monitoring Tfll.A3-5 3.5.1.31 Elements (Structural) (Ext) and permeability, Program (B2.1.32) cracking, loss of material (spalling,
!scaling)
Duct Banks SH Concrete Atmosphere/ Cracking due to Structures Monitoring II1.A3-2 3.5.1.27 and Manholes I Weather expansion Program (B2.1.32) Structura!) (E!x) Palo Verde Nuclear Generating Station Page 3.5-120 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-12Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Transformer Foundationsand Electrical Structures (Continued) uoncrete and Manholes ' Weather (spalling, scaling) Program (B2.1.32) (StructuraL(Ext)_ and cracking_ Duct Banks IsH Concrete Atmosphere/ Cracking, loss of Structures Monitoring I111.A3-9 3.5.1.23 and Manholes Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling) Duct Banks [SH Concrete Atmosphere/ Increase in porosity Structures Monitoring II1.A3-10 3.5.1.24 A and Manholes Weather and permeability, Program (B2.1.32) (Structural) (Ext) cracking, loss of material (spalling, scaling Duct Banks 1SH Concrete Buried Cracking due to Structures Monitoring I11.A3-2 3.5.1.27 A and Manholes (Structural) (Ext) expansion Program (B2.1.32) Duct Banks FSH IConcrete Buried Cracks and Structures Monitoring II1.A3-3 3.5.1.28 A and Manholes Structural) (Ext) distortion Program (B2.1.32) Duct Banks SH Concrete Buried Cracking, loss of Structures Monitoring IIl.A3-4 3.5.1.31 and Manholes (Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) . Duct Banks SH Concrete Buried /Increase in porosity Structures Monitoring II1.A3-5 3.5.1.31 and Manholes (Structural) (Ext) and permeability, Program (B2.1.32) cracking, loss of material (spalling,
. .. __. _ .. ,scaling) ......
Palo Verde Nuclear Generating Station Page 3.5-121 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-12Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Transformer Foundationsand Electrical Structures (Continued) i-ire b, Aimospnere/ increaseu Seals Weather hardness, (Structural) (Ext) shrinkage and loss of strength Structural Steel NSRS, Carbon Steel Atmosphere/ Loss of material tStructures Monitoring jCI1.A3-12 3.5-1.25 A SH Weather iProgram (B2.1.32) (Structural) (Ext) Structural Steel NSRS, Carbon Steel Encased in None None IVIIJ-21 3.3.1.96 SH __ Concrete (Ext Transmission INSRS Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3-12 13.5.1.25 A Tower Weather Program (B2.1.32) (Structural) (Ext) Notes for Table 3.5.2-12: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. Plant Specific Notes: None Palo Verde Nuclear Generating Station Page 3.5-122 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures (In-Scone) L;aunKtg/ P-LB, Atmospnere/ LOSS OT seaiing Structures Monitoring A Sealant SPB Weather Program (B2.1.32) (Strctual Ext)I _____ Caulking/ IFLb, -SH Elstome-r Buried (Structural) FLoss of sealing S§tructures Monitoring lll.A6-12 13.5.1.44 A Sealantt (Ext) Program (B2.1.32_.) Caulking!/ Ca-ulking! FB SH,
-FLB,,
Elastomer
-. 4' . ___________________________
Structures Monitoring 11I.A6-12 13.5.1.44 A Plant Indoor Air !Loss of sealing Sealant SPB (Structural) (Ext) Program (B2.1.32) Compressible ES, SH Elastomer Atmosphere/ Loss of sealing Structures Monitoring Ill.A6-12 13.5.1.44 A Joints/Seals Weather Program (B2.1.32) (Structural) (Ext)__ _ I Compressible ES, SH Elastomer -Buried (Structural) !Loss of sealing Structures Monitoring flllA6-12 3.5.1.44 Joints/Seals (fx-t) _____ Program (B2.1.32) Compressible ES, SH Elastomer Plant Indoor Air t-ossofsealing .Structures Monitoring lll.A6-12 13.5.1.44 Joints/Seals _ (Structural) (Ext) _ _ _ Program (B2.1.32) Concrete Block §SH, SS Concrete Atmosphere/ Cracking Masonry Wall Program III.A3-1 1 3.5.1.43 A (Masonry Block Weather (B2.1.31) Walls) (Masonry (Structural) (Ext) Walls) Concrete Block FB, SH, Concrete Plant Indoor Air Cracking Fire Protection (B2.1.12) III.A3-11 3.5.1.43 E, 1 (Masonry ISS Block (Structural) (Ext) and Masonry Wall Walls) (Masonry .Program (B2.1.31) Walls,) Palo Verde Nuclear Generating Station Page 3.5-123 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures ý%A.J Elements iAtmosphere/ j Loss ot material OIrucLures Ivionitoring A Elements SH, SPB, Weather (spalling, scaling) Program (B2.1.32) SS (Structural))_.(Ext and cracking Concrete FB, MB, 6Concrete Atmosphere/ Cracking, loss of Structures Monitoring II1.A3-9 3.5.1.23 A Elements SH, SPB, Weather ,bond, and loss of Program (B2.1.32) SS (Structural) (Ext) material (spalling, scaling) Concrete FB, MB, !Concrete Atmosphere/ Increase in 'D C I 'A A J. I U .. I
ý.LA
- IVIUI IILT "III III.t'.,J " IU '.J . I
- Elements SH, SPB, Weather porosity and Program (B2.1.32)
SS (Structural) (Ext) 1permeability, 1cracking, loss of I material (spalling,
!scaling)
Concrete FB, MB, Concrete Atmosphere/ !Concrete cracking Fire Protection (B2.1.12)IVII.G-30 3.3.1.66 Elements SH, SPB, Weather and spalling and Structures SS (Structural) (Ext) Monitoring Program (B2.1.32) _I - } Concrete FB, MB, ICon crete Atmosphere/ Loss of material Fire Protection (B2. 1.12) VI.-31 13.3.1.67 Elements SH, SPB, Weather and Structures SS (Structural) (Ext) Monitoring Program Concrete Co6n-cre-te6 Buried (Structural) Cracking due to Structures Monitoring IIII.A3-2 '3.5.1.27 A Elements SS (_Erxt) expansion Pr B2.1.32)_____ _ _ Palo Verde Nuclear Generating Station Page 3.5-124 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13Containments,Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures (In-ScoDe) (Continued) uoncrete i-Ltb, 01-i, 1k n ri turiea koiruciurai) ikracKmng, loss or otruciures ivioniioring III1.'A,.5 -14 Elements 55SLocrS (Ext) .bond, and loss of Program (B2.1.32) material (spalling, _scaling) Concrete FLB, SH, Concrete Buried (Structural) Increase in Structures Monitoring IIIi.A3-5 3.5.1.31 A Elements SS (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling,
.scaling)
Concrete FLB, SH, Concrete Plant Indoor Air ICracking dueto Structures Monitoring IiiI 3-2 3.5.1.27 A Elements SPB. SS t (Structural) (Ext) Iexoansion Program (B2.1.32) Concrete FLB, SH, Concrete Plant Indoor Air lCracking, loss of Structures Monitoring II.A3-9 3.5.1.23 A Elements SPB, SS (Structural) (Ext) bond, and loss of Program (B2.1.32) material (spalling, scaling) Concrete FLB, SH, Concrete Plant Indoor Air Increase in Structures Monitoring I1.A3-10 3.5.1.24 A Elements SPB, SS (Structural) (Ext) porosity and Program (B2.1.32) permeability, cracking, loss of material (spalling, scaling) ~~1-~ Doors SH Carbon Steel Atmosphere! 1Loss of material Structures Monitoring II1.A3-12 3.5.1.25 Weather Program (B2.1.32) (Structural) _(Ext)___ Palo Verde Nuclear Generating Station Page 3.5-125 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures uoors 6H, *H* iant inaoor Air (Structural) (Ext) Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material -Structures Monitoring II1.A3-12 3.5.1.25 A Doors (Structural) (Ext) Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Prog Protection Fire (B2.1.12)iVII.G-3 i_ 3.3.1.63 ram (132.1.32) B (Structural) (Ext) Doors Gypsum/ FB, SH Gypsum/ Plant Indoor Air Cracking Fire Protection (B2.1.12)VNone None Plaster Barrier Plaster (Structural) (Ext) Hatch lMB, SH, Carbon Steel Atmosphere/ Loss of material Structures Monitoring I II.A3-12 3.5.1.25 SPB .Weather Program (B2.1.32)
.....
B. .
.................................
.F.i.-M ............... ..... ...........................
. ......
........
Hatch FLB, MB, Carbon Steel 'Plant Indoor Air Loss of material Structures Monitoring II .A3-12 13.5.1.25 A _SH, SPB 1Structural) (Ext) Program (B2.1.32) H -atches/Plugs IFLB, MB, Concrete Atmosphere/ ICracking due to Structures Monitoring III.A3-2 3.5.1.27 SH. SPB Weather expansion Program (B2.1.32)
.(Structural) (Ext)
Hatches/Plugs IFLB, MB, Concrete Atmosphere/ Cracking, loss of Structures Monitoring III.A3-9 13.5.1.23 SH, SPB Weather bond, and loss of Program (B2.1.32) (Structural) (Ext) material (spalling, scaling) Hatches/Plugs FLB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3-10 13.5.1.24 A SH, SPB Weather porosity and Program (B2.1.32) (Structural) (Ext) permeability, cracking, loss of
!material (spalling, iscaling Palo Verde Nuclear Generating Station Page 3.5-126 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13Containments,Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures (In-ScoDe) (Continued) imaicnes/ItIugs i-Lb, IVMb, t'iant inaoor /-lr i.,racKmng cue 1U 01ructures ivonoriilrng IO.O. I, SH, SPB (Structural) (Ext) i expansion Program (B2.1.32) Hatches/Plugs FLB, MB, Concrete Plant Indoor Air 'Cracking, loss of Structures Monitoring II .A3-9 13.5.1.23 A (Structural) (Ext) ,bond, and loss of Program (B2.1.32) i SH, SPB imaterial (spalling, Iscaling) Hatches/Plugs FLB, MB, Concrete Plant Indoor Air lIncrease in Structures Monitoring 3.5.1.24 _Il.A3-1O0 JA SH, SPB (Structural) (Ext) porosity and Program (B2.1.32) permeability,
!cracking, loss of
,material (spalling, scalinq_
Penetrations 1SS Carbon Steel Atmosphere/ Loss of material 'Structures Monitoring II1.A3-12 3.5.1.25 IA Electrical Weather Program (B2.1.32) (Structural) (Ext) Carbon Steel Encased in None None VII.J-21 13.3.1.96 C Penetrations ISS Concrete (Ext) Electrical _ i Structures Monitoring I1I1.A3-12 3.5.1.25 A Penetrations SS Carbon Steel Plant Indoor Air jLoss of material E lec tric a l I._.._.. (Structural) (Ext) _...._............... Program (B2.1.32) Penetrations SS Carbon Steel Atmosphere/ I Loss of material Structures Monitoring II.A3-12 3.5.1.25 Mechanical Weather Program (B2.1.32) (Structural) (Ext Penetrations SS Carbon Steel Encased in None None 1VII.J-21 3.3.1.96 C Concrete (Ext) _ Mechanical Carbon Steel Plant Indoor Air (Structural)_(ExtL. Loss of material _________ Structures Monitoring 111.A3-12 13.5.1.25 Program (12.1.32) Palo Verde Nuclear Generating Station Page 3.5-127 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-13Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Yard Structures fln-Scotoe) (Continued) Roofing SH Elastomer Atmosphere/ Loss of sealing Structures Monitoring 1II.A6-12 13.5.1.44 A Membrane Weather I Program (B2.1.32)
,,(,
S(Structural)(Ext)__ ____. .. ...... . . Structural Steel SS Carbon Steel Atmosphere/! Loss of material Structures Monitoring il1l.A3-12 3.5.1.25 A Weather Program (B2.1.32) _____ _____ ________ Strctural) (Ext) _________ _______ ___ _____ _____ ____ Structural Steel SS Carbon Steel Encased in 'None None VII.J-21 3.3.1.96 C Concrete (Ext __ Structural Steel SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring II1.A3-12 3.5.1.25 A (Structural) (Ext) _ Program (B2.1.32) __..._ ___ Notes for Table 3.5.2-13: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Note: 1 The NUREG-1801 does not provide a line in which Concrete Masonry is inspected per the Fire Protection program. Palo Verde Nuclear Generating Station Page 3.5-1: 28 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS
.c~rt nfitrimc~ ~,1fcmnin ~IrAt ,m~i Cable Tre Carbon Steel Atmosphere/ ILoss of material Structures Monitoring Supports Weather Program (B2.1.32)
(Structural (Ex)
ýCable Trays & NSRS, SS Carbon Steel ant Indoor Air SLoss of material Structures Monitoring 111.B2-10 13.5.1.39 A Supports j(Structural il'xt) Program (B2.1.32)
Cable Trays & SS 1Concrete Atmosphere/ Reduction in Structures Monitoring 1llI.B2-1 3.5.1.40 1A Supports Weather concrete anchor Program (B2.1.32) Structural)Ext) _ _ 1capacity Cable Trays & NSRS, SS Concrete Plant Indoor Air Reduction in Structures Monitoring IllI.B2-1 13.5.1.40 [A Supports (Structural) (Ext) concrete anchor Program (12.1.32) capacity Conduit And SS Carbon Steel Atmosphere/ SLoss of material Structures Monitoring 111.B2-10 3.5.1.39 Supports Weather Program (B2.1.32) (Structural) (Ext) Conduit And NSRS, Carbon Steel Plant Indoor Air Loss of material Structures Monitoring 11182-10 3.5.1.39 A Supports SH, SS (Structural) (Ext) Program (B2.1.32) Conduit And SS Concrete Atmosphere/ IReduction in Structures Monitoring II1I.B2-1 13.5.1.40 A Supports Weather Iconcrete anchor Program (12.1.32) (Structural) (Ext) capacity Conduit And NSRS, SSIConcrete Plant Indoor Air IReduction in Structures Monitoring ITB-2-1 3.5.1.40 A Supports (Structural) (Ext) iconcrete anchor Program (B2.1.32) ____ capacity Palo Verde Nuclear Generating Station Page 3.5-129 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports Electrical Carbon Steel Atmosphere/ Structures Monitoring Panels & Weather Program (B2.1.32) Enclosures (Sructural) (Ext) NSRS, Carbon Steel Plant Indoor Air Loss of material Structures Monitoring 111.B3-7 13.5.1.39 A Panels & iSH, SS (Structural) (Ext) Program (B2.1.32) Enclosures ----
-t . ...
------.............
Electrical iss Concrete 'Atmosphere/ Reduction in Structures Monitoring illI.B3-1 13.5.1.40 A Panels & Weather concrete anchor Program (B2.1.32) Enclosures _ (Structu'ral) (Ext) capacity NSRSSS Concrete IPlant Indoor Air Reduction in Structures Monitoring Jll.B33-1 3.5.1.40 (Structural) (Ext) concrete anchor Program (B2.1.32) Enclosures t --- capacity-High Strength ýSs High Plant Indoor Air Bolting Integrity (B2.1.7) I11B1.1-3 13.5.1.51 B Bolting Strength Low (Structural) (Ext) Alloy Steel
!(Bolting).....
High Strength ] High iPant fIn J-or-Ai.r Loss of material 1.7) 111. B1. 1-4 13.5.1.51 Bolting Strength Low (Structural) (Ext) Alloy Steel Instrument RS, Carbon Steel Plant Indoor Air ,Loss of material Structures Monitoring 111.B3-7 13.5.1.39 A Panels & SH; SS (Structural) (Ext) Program (B2.1.32) Racks Palo Verde Nuclear Generating Station Page 3.5-130 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports (Continued) Management
'rogramn Structures Monitoring Panels & (Structural) (Ext) concrete anchor Program (B2.1.32)
Racks 1.capacit.!,,, . . Supports ES, SS Carbon Steel Plant Indoor Air Loss of ASME Section Xl, 111.B1.1-2 3.5.1.54 A (Structural) (Ext) mechanical Subsection IWF
,_(B2.1.29),.... ...... .
function ASME Section -Xl, Supports ES, SS Carbon Steel Plant Indoor Air Loss of Il11.B1.2-2 3.5.1.54 A (Structural) (Ext) mechanical Subsection IWF ifunction (B2.1.29) ES, SS Lubrite Plant Indoor Air i Loss of ASME Section Xl, III.B1.1-5 3.5.1.56 A (Structural) (Ext) Imechanical Subsection IWF
!function (1B2.1.29)
Supports -ES, SS Lubrite Plant Indoor Air Loss of material, ASME Section Xl, 111..B1.2-3 3.5.1.56 1A (Structural) (Ext) cracking Subsection IWF (B2.1.29) Supports ES, SS Lubrite Plant Indoor Air Loss of Structures Monitoring 111.B2-2 3.5.1.52 A (Structural) (Ext) mechanical Program (B2.1:32)
!function Carbon Steel Borated Water Loss of material Boric Acid Corrosion II1.B1.1-14 3.5.1.55 A ASME 1 Leakage (Ext) (B2.1.4)
ASME 1 Supports ISS Plant Indoor Air Loss ofmaterial iASME Section XI, 11.B1.1-*13 3.5.1.53 A 1(Structural) (Ext) Subsection IWF Supports (132.1...29).... . . ..... ASME 1 SS !Concrete tPi~a nt IndorAir6 Reduction in Structures Monitoring Ill.B1. 1-1 3.5.1.40 A iconcrete anchor
,(Structural) (Ext) Program (B2.1.32) capacity Palo Verde Nuclear Generating Station Page 3.5-131 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports (tnntini iiorl z~ item Il Supports Stainless Borated Water 111.1B1.1-110 3.5.1.59 ASME 1 Steel Leakage (Ext) Supports Stainless Plant Indoor Air 1None None 1II.B1.1-9 13.5.1.59 ASME 1 Steel (Structural) (Ext) Supports SS Carbon Steel Atmosphere/ !Loss of material ASME Section XI, 111.B1.2-10 3.5.1.53 A ASME 2 & 3 Weather Subsection IWF (Structural) (Ext) (B2.1.29) Supports Carbon Steel Borated Water ,Loss of material Boric Acid Corrosion .I. III.B1.2-11 3.5.1.55 A ASME 2 & 3 (B2.1.4) _.. . Supports Carbon Steel Plant Indoor Air Loss of material ASME Section XI, I111.B1.2-10 3.5.1.53 A ASME 2 & 3 (Structural) (Ext) Subsection IWF (B2.1.29) Supports SS Carbon Ste el Raw Water (Ext) Loss of material ASME Section Xl, None None G ASME 2 & 3 Subsection IWF (B2.1.29). Supports Concrete Plant Indoor Air Reduction in Structures Monitoring S11. B1.2-1 '3.5.1.40 ASME 2 & 3 (Structural) (Ext) concrete anchor Program (B2.1.32) capacity 4 4 Supports SS Stainless Atmosphere/ Loss of material ASME Section XI, I111.B4-7 13.5.1.50 E, 1 ASME 2 & 3 Steel Weather Subsection IWF 4 (Structural) (Ext) (B2.1.29) 4 Supports SS Stainless Borated Water INone None III.B1.2-8 13.5.1.59 A ASME 2 & 3 Steel Leaka e(Ext) Supports SS Stainless Plant IndoorAir None None III.B1.2-7 3.5.1.59 ASME 2 & 3 Steel Structural) (Ext Palo Verde Nuclear Generating Station Page 3.5-132 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports supports 6sainless :t) 1LOSS OT mate A-5M_ zsection Ai, ASME 2 &3 Steel Subsection IWF
-SS (B2.1.29)
Supports Carbon Steel Atmosphere/ Loss of material Structures Monitoring 111.132-10 3.5.1.39 HVAC Duct Weather Program (B2.1.32) Structuraý)(Ext)
+
Supports NSRS, SS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring llI.B2-10 13.5.1.39 A HVAC Duct (Structural (Ext Program (B2.1.32) + Supports NSRS, SStConcrete Plant Indoor Air Reduction in Structures Monitoring 111.B2-1 3.5.1.40 A HVAC Duct (Structural) (Ext) concrete anchor Program (B2.1.32) t capacity ........... i Supports SS Stainless Plant Indoor Air !None None 111.B2-8 3.5.1.59 A HVAC Duct Steel (Structural) (Ext)
-4 Supports SS {Carbon Steel Atmosphere/ Loss of material Structures Monitoring I1.B2-10 13.5.1.39 A Instrument Weather Program (B2.1.32)
(Structural) (Ext) Supports SS Carbon Steel Borated Water Loss of material Boric Acid Corrosion II.B2-11 3.5.1.55 A Instrument Leakage (Ext) (B2.1.4)
-4 +
Supports NSRS, SS[Carbon Steel Plant Indoor Air !Loss of material Structures Monitoring 1,11.B2-10 13.5.1.39 A i Instrument 4. (Structural) (Ext) Program (B2.1.32) 4 Supports NSRS, SSlConcrete Plant Indoor Air Reduction in Structures Monitoring illI.B2-1 3.5.1.40 A Instrumeht (Structural) (Ext) concrete anchor Program (B2.1.32) capacity Supports SS Stainless Atmosphere/ Loss of material Structures Monitoring II1.B2-7 3.5.1.50 A Instrument Steel Weather Program (B2.1..32) (Structural) (Ext) Palo Verde Nuclear Generating Station Page 3.5-133 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports Supports SS Stainless 'Borated Water None None IlI.B2-9 3.5.1.59 A Instrument 1 Steel Leakage,(Ext) _... ............. "__ Supports... NSRS, SS !Stainless Plntd ndoor Air 'None None II1.B2-8 3.5.1.59 A Instrument _ _Steel Structural) (Ext. ____ ___ Supports ISS Aluminum Plant Indoor Air None None I111.B1.1-6 3.5 1.58 A Insulation(Structural) (Ext) Supports Mech iSS Carbon SteeliBorated Water . Loss of material Boric Acid Corrosion J11.B1.1-14 3.5.1.55 A Equip Class 1 1 Leakage (Ext) "(B2.1.4)
§Sup6ports Mech SS- C.on-crete Plant Indoor Air P "Reducti-non in IStructures Monitoring .. l.1B1.1-1-' 3.5.1.40 . A Equip Class 1 (Structural) (Ext) concrete anchor IProgram (B2.1.32)
..icapacity a n ....................
.... ....................
Supports Mech SS Stainless Borated Water None None I~lBI.-103.5.1.59 A Equip Class 11 Steel tLeakage Ext) 'Supports Mech SS I arbon Steeli Borated Water Loss of material Boric Acid Corrosion l.11.11.2-11 3.5.1.55 A Equip Class 2 Leakage (Ext) (B2.1.4)
&3 Supports Mech SS Carbon Steel Fuelil (Ext. Loss of material 1ASME Section XI, None None G Equip Class 2 1Subsection IWF 1(B2.1.29)
,Supports Mech ~SS Carbon Steel Pant Indoor Air Loss of material ASME Section Xl, I1B1.2-1 0 '3.5.1.53 A Equip Class 2 I(Structural) (Ext) Subsection IWF Supports Mech SS LB2.1.29 .. .. . IConcrete 'Plant Indoor Air Reduction in Structures Monitoring 111.BI:2-1 3.5.1.40 k Equip Class 2 (Structural) (Ext) concrete anchor Program (B2.1.32)
& 3. . icapacit Palo Verde Nuclear Generating Station Page 3.5-134 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports (Continued) Com~ponient Intended <Material Environment Aging Effect Aging Management NUREG~- Table 1 Item Notes~ Type Fuinction Requiring Program181Vl _____I I ___________ Management 2tem 2 I Supports Mech SS Stainless Borated Water None None 111.B1.2-8 3.5.1.59 A
&Equip 3l Class 2 Steel Leakage (Ext)
Supports Mech SS Stainless Fuel Oil (Ext) Loss of material ASME Section Xl, None None G Equip Class 2 1 Steel Subsection IWF upports Mech SS tainless Plant IndoHor Air No1ne MB1.2-7 3.5.1.59 A ainesss ancIndorr ~None Nn Equip Class 2 Steel (Structural) (Ext) i&3 Supports Mech NSRS Carbon Steel Atmosphere! Loss of material Structures Monitoring III.B4-10 3.5.1.39 A Equip Non Weather Program (B2.1.32) 'ASME ....... (Structural) (Ext) _ Supports Mech NSRS Carbon Steel Borated Water ILoss of material Boric Acid Corrosion "111.B4-11 3.5,1.55. Equip Non Leakage (Ext) (B2.1.4) ASME - Supports Mech NSRS Carbon Steel Plant Indoor Air Loss of material Structures Monitoring IllI.B4-10 3.5.1.39 A Equip Non ,(Structural) (Ext) Program (B2.1.32) 1ASME (tutrl Et ISupports Mech NSRS Concrete Plant Indoor Air Reduction in Structures Monitoring llI.B4-1 3.5.1.40 A ISEquip Non tb (Structural) (Ext) ;concrete anchor Program (B2.1.32) MechENISSails capacity ___ 1147 3 S-upports -ch -NSRS .. S ainiess Atm0h-ere Loss of material Structures Monitoring 111.4 Equip Non Steel Weather. Program (B2.1.32) [ASME (Structural) (Ext) I Palo Verde Nuclear Generating Station Page 3.5-135 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports (Continued) supports Mecn N*RK* zjtainiess boratea vvater rNone 3,.0.1.5t9 1ii.B4-Equip Non Steel Leakage (Ext) ASME Supports Mech NSRS Stainless Plant Indoor Air None None II11.B14-8 3519 Equip Non Steel (Structural) (Ext) ASME Supports Non NSRS ICarbon Steel Atmosphere/ Loss of material Structures Monitoring IllI.B2-10 3.5.1.39 A ASME Weather Program (B2.1.32) (Structural.)(Ex) Supports Non tNSRS tCarbon Steel Borated Water Loss of material Boric Acid Corrosion ,111.B2-11 3.5.1.55 A ASME Leakage (Ext) (B2.1.4) Supports Non NSRS ICarbon Steel Plant Indoor Air Loss of material Structures Monitoring 111.B2-10 3.5.1.39 A ASME (Structural) (Ext) Program (B2.1.32) Supports Non NSRS Carbon Steel Raw Water (Ext) Loss -ofmaterial Structures Monitoring None None G tASME Proram (B2.1.32)___ NSRS Plant Indoor Air Reduction in Structures Monitoring 1111.2-1 13.5.1.40 A Supports Non Concrete ASME (Structural) (Ext) concrete anchor Program (B2.1.32) I capacity Supot Non NSRS Stainless Atmosphere! Loss of material Structures Monitoring I111.B2-7 '3.5.1.50 A ASME Steel Weather Program (B2.1.32) (Structural) (Ext Supports Non NSRS Stainless Borated Water None None I111.B2-9 13.5.1.59 A ASME Steel Leakage (Ext) Supports Non FNSRS Stainless Plant Indoor Air None None I11.1B2-8 3.5.1.59 A ASME Steel (Structural) (_xt)_ Palo Verde Nuclear Generating Station Page 3.5-136 License Renewal Application
Section 3.5 AGING MANAGEMENT OF CONTAINMENTS, STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-14 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Supports (trln tint Irl) Supports Non NSKS Stainless :1 Raw Water (Ext) Loss ot material Structures Monitoring None Noni ASME IISteel IProgram (B2.1.32) Notes for Table 3.5.2-14: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP. E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. G Environment not in NUREG-1801 for this component and material. Plant Specific Notes: 1 NUREG-1801 does not provide a line to'evaluate stainless steel components outdoors under ASME Section X1, Subsection IWF. Palo Verde Nuclear Generating Station Page 3.5-137 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.1 Introduction Section 3.6 provides the results of the aging management reviews for those component types identified in Section 2.5, Scoping and Screening Results - Electrical and Instrument and Control Systems, subject to aging management review. The electrical component types subject to aging management review are discussed in the following sections:
- Connections (metallic parts) (Section 2.5.1.1)
" Connector (Section 2.5.1.2)
" High Voltage Insulators (Section 2.5.1.4)
" Insulated Cable and Connections (Section 2.5.1.5) (includes the following):
o Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements o Electrical cables and connections used in instrumentation circuits not subject to 10 CFR 50.49 EQ requirements that are sensitive to reduction in conductor insulation resistance o Inaccessible Medium-Voltage Electrical Cables not subject to 10 CFR 50.49 EQ requirements
- Metal Enclosed Bus (Section 2.5.1.6) (includes the following):
o Bus bar and connections o Bus enclosure o Bus Insulation and insulators
- Penetrations Electrical (Section 2.5.1.7)
" Switchyard Bus and Connections (Section 2.5.1.8)
- Terminal Block (Section 2.5.1.9)
- Transmission Conductors and Connections (Section 2.5.1.10)
Table 3.6.1, Summary of Aging Management Evaluations in Chapter VI of NUREG-1801 for Electrical Components, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component types in this Section. Table 3.6.1 uses the format of Table 1 described in Section 3.0. Palo Verde Nuclear Generating Station Page 3.6-1 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.2 Results The following table summarizes the results of the aging management review for the component types in the Electrical and Instrumentation and Controls area.
- Table 3.6.2-1 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components This table uses the format of Table 2 discussed in Section 3.0.
3.6.2.1 Materials, Environment, Aging Effects Requiring Management and Aging Management Programs The materials from which the component types are fabricated, the environments to which they are exposed, the potential aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above electrical component commodities in the following subsections. 3.6.2.1.1 Cable Connections (Metallic Parts) Materials The materials of construction for the cable connections (metallic parts) are:
- Various Metals Used For Electrical Contacts Environment The cable connections (metallic parts) are exposed to the following environment:
- Plant Indoor Air
- Atmosphere/Weather (Ext)
Aging Effects Requiring Management The following cable connections (metallic parts) aging effect requires management:
- Loosening of bolted connections Aging Management Programs The following aging management program manages the aging effects for the cable connections (metallic parts):
- Electrical Connections Not Subject to 10 CFR 50.49 EQ Requirements (B2.1.35)
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Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.2.1.2 Connectors Materials The materials of construction for the connectors are:
- Various Metals Used For Electrical Contacts Environment The connectors are exposed to the following environment:
- Borated Water Leakage Aging Effects Requiring Management The following connectors aging effect requires management:
- Corrosion Of Connector Contact Surfaces Aging Management Programs The following aging management program manages the aging effects for the connectors:
- Boric Acid Corrosion (B2.1.4) 3.6.2.1.3 High Voltage Insulator Materials The materials of construction for the high voltage insulators are:
- Carbon Steel (Galvanized)
- Cement (Electrical Insulators)
- Porcelain Environment The high voltage insulators are exposed to the following environment:
- Atmosphere/ Weather (Ext)
Aging Effects Requiring Management The following high voltage insulator aging effects require management:
- None Palo Verde Nuclear Generating Station Page 3.6-3 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Aging Management Programs The following aging management program manages the aging effects for the high voltage insulators: 0 None Technical justification for no aging effects requiring management The PVNGS is located in an area where the outdoor environment is not subject to industry air pollution or salt spray. Contamination buildup on the high-voltage insulators is not a problem due to sufficient rainfall periodically washing the insulators. Additionally there is no salt spray at the plant since the plant is not located near the ocean. Degradation of insulator quality in the absence of salt deposits and surface contamination is not an aging effect requiring management. Industry experience has shown that transmission conductors are designed and installed not to swing significantly and cause wear, due to wind induced abrasion and fatigue. The PVNGS transmission conductors are designed and installed not to swing significantly and cause wear due to wind induced abrasion and fatigue. Therefore, loss of material due to wind induced abrasion and fatigue is not an applicable aging effect requiring management. 3.6.2.1.4 Insulated Cables and Connections 3.6.2.1.4.1 Electrical cables and connections not subject to 10 CFR 50.49 EQ requirements Materials The materials of construction for the electrical cable and connections not subject to 10 CFR 50.49 EQ requirements are: 0 Various Organic Polymers Environment The electrical cable and connections not subject to 10 CFR 50.49 EQ requirements are exposed to the following environment:
& Adverse Localized Environment Aging Effects Requiring Management The following electrical cable and connections not subject to 10 CFR 50.49 EQ requirements aging effects require management:
- Embrittlement, cracking, melting, discoloration, swelling, or loss of dielectric strength leading to reduced insulation resistance (IR); electrical failure Palo Verde Nuclear Generating Station Page 3.6-4 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Aging Management Programs The following aging management program manages the aging effects for the cable and connections not subject to 10 CFR 50.49 EQ requirements:
- Electrical Cables and Connections Not Subject to 10 CFR 50.49 EQ Requirements (B2.1.24) 3.6.2.1.4.2 Electrical cables and connections used in instrumentation circuits not subject to 10 CFR 50.49 EQ requirements that are sensitive to reduction in conductor insulation resistance Materials The materials of construction for the electrical cables and connections used in sensitive instrumentation circuits not subject to 10 CFR 50.49 EQ requirements are:
- Various Organic Polymers Environment The electrical cables and connections used in sensitive instrumentation circuits not subject to -10 CFR 50.49 EQ requirements are exposed to the following environment:
- Adverse Localized Environment Aging Effects Requiring Management The following electrical cables and connections used in sensitive instrumentation circuits not subject to 10 CFR 50.49 EQ requirements aging effects require management:
- Embrittlement, cracking, melting, discoloration, swelling, or loss of dielectric strength leading to reduced insulation resistance (IR); electrical failure Aging Management Programs The following aging management program manages the aging effects for the cable and connections used in sensitive instrumentation circuits not subject to 10 CFR 50.49 EQ requirements:
- Electrical Cables and Connections Not Subject to 10 CFR 50.49 EQ Requirements Used in Instrumentation Circuits (B2.1.25)
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Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.2.1.4.3 Inaccessible Medium Voltage Electrical Cables not subject to 10 CFR 50.49 EQ requirements Materials The materials of construction for the inaccessible medium voltage electrical cables not subject to 10 CFR 50.49 EQ requirements are:
- Various Organic Polymers Environment The inaccessible medium voltage electrical cables not subject to 10 CFR50.49 EQ requirements are exposed to the following environment:
- Adverse Localized Environment Aging Effects Requiring Management The following inaccessible medium voltage electrical cables not subject to 10 CFR 50.49 EQ requirements aging effects require management:
- Localized damage and breakdown of insulation leading to electrical failure Aging Management Programs The following aging management program manages the inaccessible medium voltage electrical cables not subject to 10 CFR 50.49 EQ requirements:
- Inaccessible Medium Voltage Cables Not Subject to 10CFR50.49 EQ Requirements (B2.1.26) 3.6.2.1.5 Metal Enclosed Bus Materials The materials of construction for metal enclosed bus are:
- Aluminum
- Carbon Steel
- Stainless Steel
- Various Metals Used for Electrical Contacts
" Elastomer
- Various Insulation Material (Electrical)
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Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Environment Metal enclosed bus is exposed to the following environment:
- Atmosphere/ Weather (Ext)
Aging Effects Requiring Management The following metal enclosed bus aging effects require management:
- Loosening of bolted connections
- Loss of material
- Hardening and loss of strength
" Embrittlement, cracking, melting, discoloration, swelling, or loss of dielectric strength leading to reduced insulation resistance (IR); electrical failure Aging Management Programs The following aging management program manages the metal enclosed bus:
- Metal Enclosed Bus (B2.1.36) 3.6.2.1.6 Penetrations Electrical Materials The materials of construction for the penetrations electrical are:
- Various Organic Polymers Environment The penetrations electrical are exposed to the following environment:
- Adverse Localized Environment (Ext)
Aging Effects Requiring Management The following penetrations electrical aging effects require management:
- Embrittlement, cracking, melting, discoloration, swelling, or loss of dielectric strength leading to reduced insulation resistance (IR); electrical failure Aging Management Programs The following aging management program manages the penetrations electrical:
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Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS
- Electrical Cables and Connections Not Subject to 10 CFR 50.49 EQ Requirements (B2.1.24) 3.6.2.1.7 Switchyard Bus and Connections Materials The materials of construction for the switchyard bus and connections are:
" Aluminum
- Stainless Steel Environment The switchyard bus and connections are exposed to the following environment:
- Atmosphere/ Weather (Ext)
Aging Effects Requiring Management The following switchyard bus and connections aging effect require management:
- None Aging Management Programs
- None Technical justification for no aging effects requiring management The PVNGS outdoor environment is not subject to industry air pollution or saline environment. Aluminum bus material does not experience any appreciable aging effects in this environment.
Switchyard bus connections employ good bolting practices consistent with the recommendations of EPRI 1003471, "Electrical Connector Application Guidelines". The connections are treated with corrosion inhibitors to avoid connection oxidation and torqued to avoid loss of pre-load, at the time of installation. The switchyard bus bolted connections are designed and installed using lock washers that prevent loss of preload. The stainless steel connection material does not experience any appreciable aging effects in this environment. 3.6.2.1.8 Terminal Blocks Materials The materials of construction for the terminal blocks are: Palo Verde Nuclear Generating Station Page 3.6-8 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS
- Various Insulation Materials (Electrical)
Environment The terminal blocks are exposed to the following environment:
- Adverse Localized Environment (Ext)
Aging Effects Requiring Management The following terminal blocks aging effects require management:
- Embrittlement, cracking, melting, discoloration, swelling, or loss of dielectric strength leading to reduced insulation resistance (IR); electrical failure Aging Management Programs The following aging management program manages the aging effects for the terminal blocks:
- Electrical Cables and Connections Not Subject to 10 CFR 50.49 EQ Requirements (B2.1.24) 3.6.2.1.9 Transmission Conductors and Connections Materials The materials of construction for the transmission conductors and connections are:
- Aluminum Conductor Steel Reinforced Environment The transmission conductors and connections are exposed to the following environment:
- Atmosphere/ Weather (Ext)
Aging Effects Requiring Management The following transmission conductors and connections aging effect require management:
- None Aging Management Programs
- None Palo Verde Nuclear Generating Station Page 3.6-9 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Technical justification for no aging effects requiring management The most prevalent mechanism contributing to loss of conductor strength of an Aluminum Conductor Steel Reinforced (ACSR) transmission conductor is corrosion, which includes corrosion of the steel core and aluminum strand pitting. ACSR conductor degradation begins as a loss of zinc from the galvanized steel core wires. Corrosion rates depend largely on air quality, which involves suspended particles in the air, SO 2 concentration, rain, fog chemistry, and other weather conditions. The PVNGS outdoor environment is not subject to industry air pollution or saline environment that would cause significant corrosion of the transmission conductors. The National Electrical Safety Code (NESC) requires that tension on installed conductors be a maximum of 60% of the ultimate conductor strength. The NESC also sets the maximum tension a conductor must be designed to withstand under medium load requirements, which includes consideration of ice, wind, and temperature. At PVNGS, the ACSR transmission conductors are 2-2156 KCMIL per phase with a core of 19 steel strands having an ultimate conductor strength of 60,300 lbs. The PVNGS ACSR transmission conductors within the scope of license renewal are installed so that conductor tension does not exceed 18,000 lbs at the NESC medium loading condition (30% of the ultimate conductor strength). Tests performed by Ontario Hydroelectric on ACSR transmission conductors with a core of 7 steel strands averaging 70 to 80 years old showed a 30% loss of ultimate conductor strength due to corrosion. Assuming a 30% loss of ultimate conductor strength (18,090 Ibs) due to corrosion over 60 years the PVNGS ACSR transmission conductors have adequate design margin to offset the loss of strength due to corrosion and still meet the NESC requirement of not exceeding 60% of the ultimate conductor strength ((60,300-18,090)* 60% =25,326 Ibs). Therefore, corrosion is not a credible aging effect that requires management for the period of extended operation. Transmission conductor and switchyard bus connections at the time of installation are treated with corrosion inhibitors to avoid connection oxidation and torqued to avoid loss of pre-load. Based on temperature data in the UFSAR Chapter 2.3, the transmission connections and switchyard bus does not experience thermal cycling. The transmission connections and switchyard bus are subject to average monthly temperatures ranging from 105 OF in July and August to 38 OF in January with minimal ohmic heating. Therefore, increased resistance of connections due to oxidation or loss of pre-load is not an aging effect requiring management for the period of extended operation. These connections are periodically evaluated via thermography as part of the preventive maintenance activities. The periodic thermography will continue into the period of extended operation. Palo Verde Nuclear Generating Station Page 3.6-10 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS 3.6.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 NUREG-1801 provides the basis for identifying those programs that warrant further evaluation. For the electrical and control systems, those evaluations are addressed in the following subsections. 3.6.2.2.1 Electrical Equipment Subject to Environmental Qualification Environmental qualification (EQ) is a TLAA as defined in 10 CFR 54.3. Equipment qualification for degradation due to various aging mechanisms to which electrical equipment is subject is evaluated in accordance with 10 CFR 54.21(c)(1). The PVNGS EQ program meets requirements of 10 CFR 50.49. Section 4.4 describes the TLAA evaluation of electrical equipment subject to 10 CFR 50.49 environmental qualification. 3.6.2.2.2 Degradation of Insulator Quality due to Presence of Any Salt Deposits and Surface Contamination, and Loss of Material due to Mechanical Wear The PVNGS is located in an area where the outdoor environment is not subject to industry air pollution or salt spray. Contamination buildup on the high-voltage insulators is not a problem due to sufficient rainfall in the spring and summer washing the insulators. Additionally there is no salt spray at the plant since the plant is not located near the ocean. Degradation of insulator quality in the absence of salt deposits and surface contamination is not an aging effect requiring management. Industry experience has shown that transmission conductors are designed and installed not to swing significantly and cause wear, due to wind induced abrasion and fatigue. The PVNGS transmission conductors are designed and installed not to swing significantly and cause wear due to wind induced abrasion and fatigue. Therefore, loss of material due to wind induced abrasion and fatigue is not an applicable aging effect requiring management. 3.6.2.2.3 Loss of Material due to Wind Induced Abrasion and Fatigue, Loss of Conductor Strength due to Corrosion, and Increased Resistance of Connection due to Oxidation or Loss of Pre-load Industry experience has shown that transmission conductors are designed and installed not to swing significantly and cause wear due to wind induced abrasion and fatigue. Therefore, loss of material due to wind induced abrasion and fatigue is not an applicable aging effect requiring management for the period of extended operation. The most prevalent mechanism contributing to loss of conductor strength of an Aluminum Conductor Steel Reinforced (ACSR) transmission conductor is corrosion, which includes Palo Verde Nuclear Generating Station Page 3.6-11 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS corrosion of the steel core and aluminum strand pitting. ACSR conductor degradation begins as a loss of zinc from the galvanized steel core wires. Corrosion rates depend largely on air quality, which involves suspended particles in the air, S02 concentration, rain, fog chemistry, and other weather conditions. The PVNGS outdoor environment is not subject to industry air pollution or saline environment that would cause significant corrosion of the transmission conductors. The National Electrical Safety Code (NESC) requires that tension on installed conductors be a maximum of 60% of the ultimate conductor strength. The NESC also sets the maximum tension a conductor must be designed to withstand under medium load requirements, which includes consideration of ice, wind, and temperature. At PVNGS, the ACSR transmission conductors are 2-2156 KCMIL per phase with a core of 19 steel strands having an ultimate conductor strength of 60,300 lbs. The PVNGS ACSR transmission conductors within the scope of license renewal are installed so that conductor tension does not exceed 18,000 lbs at the NESC medium loading condition (30% of the ultimate conductor strength). Tests performed by Ontario Hydroelectric on ACSR transmission conductors with a core of 7 steel strands averaging 70 to 80 years old showed a 30% loss of ultimate conductor strength due to corrosion. Assuming a 30% loss of ultimate conductor strength (18,090 Ibs) due to corrosion over 60 years the PVNGS ACSR transmission conductors have adequate design margin to offset the loss of strength due to corrosion and still meet the NESC requirement of not exceeding 60% of the ultimate conductor strength ((60,300-18,090)(0.60) = 25,326 Ibs). Therefore, corrosion is not a credible aging effect that requires management for the period of extended operation. Transmission conductor and switchyard bus connections at the time of installation are treated with corrosion inhibitors to avoid connection oxidation and torqued to avoid loss of pre-load. Based on temperature data in the UFSAR Chapter 2.3, the transmission connections and switchyard bus does not experience thermal cycling. The transmission connections and switchyard bus are subject to average monthly temperatures ranging from 105 OF in July and August to 38 OF in January with minimal ohmic heating. Therefore, increased resistance of connections due to oxidation or loss of pre-load is not an aging effect requiring management for the period of extended operation. These connections are periodically evaluated via thermography as part of the preventive maintenance activities. The periodic thermography will continue into the period of extended operation. The PVNGS outdoor environment is not subject to industry air pollution or saline environment. Aluminum bus material, galvanized steel support hardware and aluminum connection material do not experience any appreciable aging effects in this environment. Switchyard bus connections employ good bolting practices consistent with the recommendations of EPRI 1003471, "Electrical Connector Application Guidelines". The connections are treated with corrosion inhibitors to avoid connection oxidation and torqued to avoid loss of pre-load, at the time of installation. The switchyard bus bolted connections Palo Verde Nuclear Generating Station Page 3.6-12 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS are designed and installed to prevent loss of preload. The aluminum connection material does not experience any appreciable aging effects in this environment. 3.6.2.2.4 Quality Assurance for Aging Management of Nonsafety-Related Components Quality Assurance Program and Administrative Controls are discussed in Section B1.3. 3.6.2.3 Time-Limited Aging Analysis The time-limited aging analyses identified below are associated with the electrical and instrument and controls component types. The section within Chapter 4, Time-Limited Aging Analyses, is indicated in parenthesis.
- Environmental Qualification of Electrical and Instrumentation and Control Equipment (Section 4.4, Environmental Qualification (EQ) of Electric Equipment) 3.6.3 Conclusions The Electrical and Instrument and Controls component types that are subject to aging management review have been evaluated. The aging management programs selected to manage the aging effects for the Electrical and Instrument and Controls component types are identified in the summary Table 3.6.1 and in Section 3.6.2.1.
A description of these aging management programs is provided in Appendix B, along with a demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstration provided in Appendix B, the effects of aging associated with the Electrical and Instrument and Controls component types will be adequately managed so that there is reasonable assurance that the intended functions will be maintained consistent with the current licensing basis during the period of extended operation. Palo Verde Nuclear Generating Station Page 3.6-13 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.1 Summary of Aging Management Evaluationsin Chapter VI of NUREG-1801 for ElectricalComponents Ite-m Component Type Ag'ing Effect I Mechanism.n ~ Agi ng Managemeint ~Fu~rther < Discufssion Number Prgram Evaluation* N, >~JRecommended 3.6.1.01 Electrical equipment Degradation due to various Environmental Qualification Yes, TLAA Environmental qualification subject to 10 CFR aging mechanisms Of Electric Components of electric components is a 50.49 environmental (B3.2) TLAA. qualification (EQ) !See further evaluation in requirements Section 3.6.2.2.1. 3.6.1.02 Electrical cables, Reduced insulation resistance Ectrical Cables and .. No Consistent with NUREG-connections and fuse and electrical failure due to Connections Not Subject To 1801. holders (insulation) not 'various physical, thermal, 10 CFR 50.49 EQ subject to 10 CFR iradiolytic, photolytic, and Requirements (B2.1.24) 50.49 EQ requirements chemical mechanisms _ 3.6.1.03 Conductor insulation !Reduced insulation resistance Electrical Cables And No Consistent UREG-for electrical cables and electrical failure due to Connections Used In 1801. and connections used various physical, thermal, Instrumentation Circuits Not in instrumentation radiolytic, photolytic, and I Subject To 10 CFR 50.49 EQ circuits not subject to chemical mechanisms Requirements (B2.1.25) 10 CFR 50.49 EQ requirements that are sensitive to reduction
,in conductor insulation resistance (IR) _
Palo Verde Nuclear Generating Station Page 3.6-14 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.1 Summary of Aging ManagementEvaluations in Chapter VI of NUREG-1801 for ElectricalComponents (Continued) Conductor insulation Localized damage and Inaccessible Medium Voltage No CCnsisieni wnn Ir for inaccessible breakdown of insulation !Cables Not Subject To 10 18.01. medium voltage (2 kV leading to electrical failure due CFR 50.49 EQ Requirements to 35 kV) cables (e.g., Ito moisture intrusion, water (B2.1.26) installed in conduit or trees
!direct buried) not Isubject to 10 CFR 150.49 EQ requirements' 3.6.1.05 Connector contacts for Corrosion of connector contact Boric Acid Corrosion (B2.1.4) No C( )nsistent with NUREG-electrical connectors surfaces due to intrusion of 118 .01.
exposed to borated borated water water leakage_- 3.6.1.06 Fuse Holders (Not Part-Fatigue due to ohmic heating, Fuse Holders No Nc)t applicable. All fuse of a Larger Assembly): thermal cycling, electrical he Iders including the fuses Fuse holders - metallic transients, frequent in.stalled for electrical clamp manipulation, vibration, pe netration protection are chemical contamination, pairt of larger assemblies, so corrosion, and oxidation th*e applicable NUREG-1801 I____in es were not used. 3.6.1.07 Metal enclosed bus - Loosening of bolted - Metal Enclosed Bus C()nsistent with NUREG-INo Bus/connections connections due to thermal (B2.1.36) 18*01. c cling and ohmic heating _ Palo Verde Nuclear Generating Station Page 3.6-15 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.1 Summaty of Aging Management Evaluations in Chapter VI of NUREG-1801 for Electrical Components (Continued) I.UO IVW..), WIl t::IIUIUb* U UUb - 1r-%UUU~tU IIIbUI:ILIUII It:bIbLd1IILU IVILdI I-IILt, lUI 801 Insulation/insulators land electrical failure due to (B2.1.36) 1801. various physical, thermal, Iradiolytic, photolytic, and' Ichemical mechanisms 3.6.1.09 1,Metal enclosed bus - Loss of material due to general Structures Monitoring No !Consistent with NUREG-Enclosure assemblies corrosion Program B2.1.32) 1801 for material, lenvironment, and aging
!effect, but a different aging management program.
jAging Management Program Ifor Metal Enclosed Bus
,(B2.1.36) is credited.
3.6.1.10 Metal enclosed bus- Hardening and loss of strerngth Structures Monitoring No lConsistent with NUREG-Enclosure assemblies due to elastomers degrada tion Program (B2.1.32) 11801 for material, jenvironment, and aging
!effect, but a different aging 1management program.
!Aging Management Program Ifor Metal Enclosed Bus I(B2.1.36) is credited.
3.6.1.11 High voltage insulators !Degradation of insulation JA plant-specific aging Yes iException to NUREG-1801.
ýquality due to presence of any imanagement program is to !Aging effect in NUREG-1801 Isalt deposits and surface J be evaluated. for this material and icontamination, Loss of material environment combination-is 1caused by mechanical wear not applicable.
1due to wind blowing on ISee further evaluation in _ ___ *... .............. . transmission conductors __ _ _ _ _ Section 3.6.2.2.2. Palo Verde Nuclear Generating Station Page 3.6-16 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.1 Summary of Aging Management Evaluations in ChapterV1 of NUREG-1801 for Electrical Components (Continued) iTransmission LUOS UI IlI::dlt~d UUd LU WIIIU A- pIlIILm- *L.III.* ayiiiy Exception to NUREG-1 801. iconductors and induced abrasion and fatigue, ;management program is to 2Aging effect in NUREG-1801 connections, Loss of conductor strength due be evaluated. Ifor this material and lenvironment combination is iOWILIlyadIU UUs dllU LU U UI IU IUI I, II l atd bU connections resistance of connection due to not applicable. ioxidation or loss of preload See further evaluation in "Section 3.6.2.2.3. 3.6.1.13 Cable Connections- iLoosening of bolted Electrical Cable Connections 'No Consistent with NUREG-Metallic parts connections due to thermal Not Subject To 10 CFR 50.49i 1801.
,cycling, ohmic heating, Environmental Qualification I
.electrical transients, vibration, Requirements (B2.1.35) ichemical contamination, corrosion, and oxidation -
3.6.1.14 Fuse Holders (Not Part None None NA - No AEM or Not applicable. All fuse of a Larger Assemt ly) AMP iholders including the fuses Insulation material installed for electrical ipenetration protection are
,part of larger assemblies, so
!the applicable NUREG-1801
- lines were not used.
Palo Verde Nuclear Generating Station Page 3.6-17 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electricaland Instrument and Controls - Summary of Aging Management Evaluation - ElectricalComponents Adverse Localized V dl IUUI> II1II1 -LII- I IILLU /-yll ly Electrical Organic Environment (Ext) degradation Analysis evaluated for Equipment Polymers the period of extended and Metallic operation. Materials Cable EC Various Atmosphere/ Loosening of Electrical Connections WA-T--T3-.6.1 1-3 Connections Metals Used Weather (Ext) bolted Not Subject to 10 CFR (Metallic Parts) for Electrical connections 50.49 Environmental Contacts Qualification Requirements (B2.1.35) Cable EC Various Plant Indoor Air Loosening of Electrical Connections VI.A-1 3.6.1.13 A Connections Metals Used (Ext) bolted Not Subject to 10 CFR (Metallic Parts) for Electrical connections 50.49 Environmental Contacts Qualification Requirements (2.1.35) Connector EC C Various Borated Water Corrosion of Boric Acid Corrosion Vl .A-5 3.6.1.05 A Metals Used Leakage (Ext) connector contact (B2.1.4)
'for Electrical surfaces 1Contacts 4 High Voltage NSRS Carbon Steel Atmosphere/ None None VI.A-9 3.6.1.11 1,1 Insulator (Galvanized) Weather (Ext) I+
High Voltage NSRS lCarbon Steel Atmosphere/ None None VI.A-10 3.6.1.11 I1, Insulator (Galvanized) Weather (Ext) Palo Verde Nuclear Generating Station Page 3.6-18 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components (Continued) High Voltage l I It-l IL MLI I IUOJJI iH1 U1 IVI.A-9 Insulator (Electrical Weather (Ext) Insulators) High Voltage IN Cement Atmosphere/ None rNone 1VI.A-10 3.6.1.11 1,1 Insulator (Electrical Weather (Ext) Insulators) 4 4 High Voltage 1IN Porcelain Atmosphere/ None None VI.A-9 3.6.1.11 Insulator Weather (Ext High Voltage IN Porcelain Atmosphere/ None None 1VI.A-10 '3.6.1.11 AI Insulator Weather (Ext) Insulated EC, IN Various Adverse Localize( d Embrittlement, Electrical Cables and 1VI.A-2 13.6.1.02 Cable and Organic Environment (Ext) cracking, melting, Connections Not Connections Polymers discoloration, Subject to 10 CFR swelling, or loss 50.49 EQ Requirements
- of dielectric (B2.1.24) strength leading to reduced
'insulation resistance (IR);
jelectrical failure Palo Verde Nuclear Generating Station Page 3.6-19 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components (Continued) Insulated UEC, IN Various Adverse Localized Embrittlement, Electrical Cables and .A-3J 3.. Cable and Organic Environment (Ext) cracking, melting, Connections Not Connections Polymers discoloration, Subject to 10 CFR swelling, or loss 50.49 EQ Requirements of dielectric Used in Instrumentation strength leading Circuits (B2.1.25) to reduced insulation resistance (IR); electrical failure Insulated EC, IN Various Adverse Localized Localized Inaccessible Medium VI.A-4 3.6.1.04 Cable and Organic. Environment (Ext) damage and Voltage Cables Not Connections Polymers breakdown of Subject to 10 CFR insulation leading 50.49 EQ Requirements 4 to electrical failure (B2.1.266_ Metal Enclosed EC Aluminum Atmosphere/ Loosening of Metal Enclosed Bus VI.A-I1 13.6.1.07 Bus Weather (Ext) bolted (B2.1.36) (Bus/Connectio connections nss) _ Metal Enclosed [Carbon Steel Atmosphere/ Loosening of Metal Enclosed Bus VIA-11 3.6.1.07 Bus (Bus/ Weather (Ext) bolted (B2.1.36) Connections) connections Metal Enclosed EC Stainless Atmosphere/ Loosening of Metal Enclosed Bus VI.A-11 i3.6.1.07 Bus (Bus/ Steel Weather (Ext) bolted (B2.1.36) Connections)- connections Palo Verde Nuclear Generating Station Page 3.6-20 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components (Continued) IUldli:l I-[1IU;1b:; r'-%., Vd::IIUUb Bus (Bus! Metals Used Weather (Ext) bolted (B2.1.36) Connections) for Electrical connections Contacts Metal Enclosed NSRS Aluminum Atmosphere/ iLoss of material Metal Enclosed Bus None None J Bus Weather (Ext) (B2.1.36) (Enclosure) ._________.._ Metal Enclosed NSRS Carbon Steel Atmosphere/ Loss of material Metal Enclosed Bus 'VI.A-13 :3.6.1.09 E, 3 Bus Weather (Ext) (B2.1.36) (Enclosure) / Metal Enclosed ES j Elastomer Atmosphere/ Hardening and Metal Enclosed Bus VI.A-12 3.6.1.10 Bus Weather (Ext) loss of strength (B2.1.36) Enclosure)_ 3 Metal Enclosed IN Various Atmosphere/ Embrittlement, Metal Enclosed Bus 1VI.A-14 13.6-1.08 A Bus (Insulation/ Insulation Weather (Ext) 1cracking, melting, (B2.1.36) Insulators) Material Idiscoloration, (Electrical) Iswelling, or loss of dielectric
,strength leading Ito reduced Iinsulation Iresistance (IR);
electrical failure Palo Verde Nuclear Generating Station Page 3.6-21 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components (Continued) t-enetratuons Itt, IN 1 various /averse LOcaiizea i .murlutemerni, rile(crlual lalets anlu IVI./A-Z 13.0. I.U/- Electrical Organic Environment (Ext) 1cracking, melting, Connections Not IPolymers discoloration, Subject to 10 CFR swelling, or loss 50.49 EQ Requirements of dielectric (B2.1.24) strength leading Ito reduced insulation Iresistance (IR); electrical failure Switchyard Bus EC Aluminum Atmosphere None None ý.61.lf 1,2 and Weather (Ext) Connections 3.6. 1.12 1,2 Switchyard BuslEC Stainless Atmosphere/ None None 'VI.A-15 and Steel Weather (Ext) Connections I........ Terminal Block IN Various Electrical Cables and 1VI.A-6 13.6.1.02 iC Adverse Localized iEmbrittlement, Insulation Environment (Ext) cracking, melting, Connections Not Material discoloration, Subject to 10 CFR (Electrical) swelling, or loss 50.49 EQ Requirements of dielectric (B2.1.24) strength leading to reduced insulation resistance (IR); electrical failure Palo Verde Nuclear Generating Station Page 3.6-22 License Renewal Application
Section 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS Table 3.6.2 Electrical and Instrument and Controls - Summary of Aging Management Evaluation - Electrical Components (Continued) Transmission EC Aluminum Atmosphere I None oniIA1 3.6.1.12 1,2 Conductors Conductor Weather (E: xt) and Steel Connections-- Reinforced Notes for Table 3.6.2-1: Standard Notes: A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP. E Consistent with NUREG-1 801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program. I Aging effect in NUREG-1801 for this component, material and environment combination is not applicable. J Neither the component nor the material and environment combination is evaluated in NUREG-1801. Plant Specific Notes: 1 See further evaluation 3.6.2.2.2 2 See further evaluation 3.6.2.2.3 3 PVNGS will use the Metal Enclosed Bus program (B2.1.36) to manage the aging effects for all metal enclosed bus components. Palo Verde Nuclear Generating Station Page 3.6-23 License Renewal Application
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