ML092400531

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PSEG Nuclear, Salem Nuclear Generating Station, Units 1 and 2, License Renewal Application, Volume 2 of 3
ML092400531
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/18/2009
From:
Public Service Enterprise Group
To:
Division of License Renewal
Robinson, J NRR/DLR/RPB1 415-2878
Shared Package
ml092430232 List:
References
TAC ME1834, TAC ME1836
Download: ML092400531 (792)
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Text

Section 3 - Aging Management Management Review Results Results 3.4 AGING MANAGEMENT MANAGEMENT OF THE STEAM AND AND POWER CONVERSION POWER CONVERSION SYSTEM 3.

4.1 INTRODUCTION

This section provides the results of the aging management management review for those those components identified in Section 2.3.4, Steam and Power Conversion components identified Conversion System, as being subject to aging management management review. The systems, or portions of systems, which are addressed addressed in this section section are described in in the the indicated sections.

System (2.3.4.1)

    • Main Turbine and Auxiliaries System (2.3.4.5) 3.4.2 RESULTS RESULTS The following tables summarizesummarize the results of the aging management management review review

Conversion System Table 3.4.2-1 Summary of Aging Management Evaluation - Auxiliary Management Evaluation Evaluation - Main Management Evaluation Main Condensate Table 3.4.2-3 Summary of Aging Management Management Evaluation Evaluation - Main Condenser and Air Removal System Table 3.4.2-4 Summary of Aging Management Management Evaluation - Main Steam Steam System Table 3.4.2-5 Summary of Aging Management Management Evaluation - Main Turbine and Auxiliaries Auxiliaries System

  • Salem Nuclear Nuclear Generating License Renewal Generating Station, Unit No.

Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.4-1

Section 33 - Aging Management Management Review Results 3.4.2.1 3.4.2.1.1 Materials, Environments.

Materials.

Aging Managements Environments, Aging Effects Managements Programs Auxiliary Feedwater Feedwater System Programs Requiring Management Effects Reguiring Management And And

  • Materials Materials materials of construction The materials construction for the Auxiliary Feedwater Feedwater System components components are:
  • " Carbon and Low Alloy Steel Bolting Bolting
    • Stainless Steel Environments Environments The Auxiliary Feedwater System components Auxiliary Feedwater components are exposed to the following following environments:
    • Air-- Indoor Air Indoor
    • Air - Outdoor Outdoor

Air with Borated Borated Water Leakage Air/Gas - Wetted Wetted Closed Cycle Cooling Water Lubricating Lubricating Oil Leakage Water> > 140 OF OF *

    • Soil
    • Steam
    • Treated WaterWater
  • " Treated WaterWater >140 OF OF Aging Effects/Mechanisms Effects/Mechanisms Requiring Management Management The following aging effects associated with the Auxiliary Feedwater effects associated Feedwater System components require management:

components

    • Cracking/Stress Corrosion Cracking/Stress Corrosion Cracking
    • Cumulative Cumulative Fatigue Damage/Fatigue Fatigue Damage/Fatigue
    • Material/Boric Acid Corrosion Loss of Material/Boric
    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced
  • "
  • Wall Thinning/Flow Aging Management Management Programs The following aging management Transfer/Fouling Reduction of Heat Transfer/Fouling Thinning/Flow Accelerated Accelerated Corrosion Programs management programs programs manage the aging effects effects for the the Auxiliary Feedwater System System components:

" Aboveground Non-Steel

  • Aboveground Non-Steel Tanks (B.2.2.3)

"* Bolting Integrity (B.2.1.9)

"* Boric Acid Corrosion (B.2.1.4)

    • Buried Piping Inspection Inspection (B.2.1.22)
    • Closed-Cycle Cooling Water Closed-Cycle Water System (B.2.1.12)
    • External Surfaces Monitoring (B.2.1.24)

Surfaces Monitoring (B.2.1.24)

    • Flow-Accelerated Corrosion (B.2.1.8)

Flow-Accelerated

  • " Inspection of Internal SurfacesSurfaces in in Miscellaneous Miscellaneous Piping and Ducting Ducting Components Components (B.2.1.26)
    • Lubricating Oil Analysis (B.2.1.27)

Lubricating

    • One-Time One-Time Inspection (B.2.1.20) (B.2.1.20)

" Water Chemistry (B.2.1.2)

Auxiliary Feedwater 3.4.2.1.2 3.4.2.1.2 Condensate and Feedwater Main Condensate Feedwater System Materials Materials The materials materials of construction for the Main Condensate Condensate and Feedwater System components are:

"* Carbon Carbon Steel

    • Carbon Carbon and Low Alloy Steel Bolting

"* Cast Austenitic Stainless Steel (CASS)

"* Stainless Stainless Steel

"* Stainless Stainless Steel BoltingBolting

Unit No.1 No.22 Page 3.4-3 3.4-3

Section 33 - Aging Management Management Review Results Environments Environments Condensate and Feedwater System The Main Condensate the following environments:

    • Air-Indoor Air - Indoor environments:

System components are exposed to *

    • Air with Borated Water Leakage Leakage
  • " Treated Water
  • " Treated Water >140 of °F Aging Effects/Mechanisms Effects/Mechanisms Requiring Requiring Management Management The following aging effects associated with the Main Condensate Condensate and Feedwater System components Feedwater components require management:
    • Cracking/Stress Corrosion Cracking Cracking/Stress Cracking
    • Damage/Fatigue Cumulative Fatigue Damage/Fatigue
  • Material/Boric Acid Corrosion Loss of Material/Boric
    • Material/General, Pitting, Crevice, and Galvanic Corrosion Loss of Material/General,

Preload/Thermal Effects, Loss of PreloadlThermal Wall Thinning/Flow Accelerated Aging Management Management Programs Effects, Gasket Creep, and Self-Loosening Accelerated Corrosion Programs Self-Loosening

  • The following aging management management programsprograms manage the aging effects effects for thethe Main Condensate Condensate and Feedwater Feedwater System System components:
    • Bolting Integrity (B.2.1.9)
    • External Surfaces Monitoring (B.2.1.24)

External

  • " Flow-Accelerated Flow-Accelerated Corrosion (B.2.1.8)
  • " One-Time Inspection Inspection (B.2.1.20)

(B.2.1.20)

    • Water Chemistry (B.2.1.2)

Salem Nuclear Nuclear Generating License Renewal No. 1 and Generating Station, Unit No.1 Renewal Application Application No. 2 and Unit No.2 Page 3.4-4 Page

  • 3.4.2.1.3 3.4.2-2, Summary Table 3.4.2-2, Condensate management Summary of Aging Management Condensate and Feedwater management review for Main Condenser Management Evaluation - Main Feedwater System summarizes for the Main Condensate Condenser and Air Removal System Condensate and Feedwater Main summarizes the results of the aging Feedwater System.

Materials Materials materials of construction The materials construction for the Main Main Condenser Condenser and Air Removal System components components are:

    • Copper Alloy with 15% 15% Zinc or More More
    • Stainless Steel Environments Environments Condenser and Air The Main Condenser Air Removal System components components are exposed to .

the following environments:

environments:

    • Air-Indoor Air - Indoor
    • Raw Raw Water Water
  • ** Treated Water Removal Water Aging EffectslMechanisms Effects/Mechanisms Requiring Removal System components Requiring Management Management The following aging effects associated with the Main Condenser components require management:

Condenser and Air Air

    • Loss of Material/General, Material/General, Pitting, Crevice, Microbiologically-Influenced Microbiologically-Influenced Corrosion, and FoulingFouling
    • Loss of Material/Selective Material/Selective Leaching Leaching Management Pro~rams Aging Management Programs The following aging management management programs manage the aging effects for the the Main Condenser Condenser and Air Removal ~emoval System components:
    • External External Surfaces Monitoring Mo~itoring (B.2.1.24)
    • One-Time Inspection Inspection (B.2.1.20)
    • Open-Cycle Cooling Water System (B.2.1.11) (B.2.1.11)
    • Selective Leaching Leaching of Materials Materials (B.2.1.21)

(B.2.1.21)

  • Salem Nuclear Nuclear Generating License Renewal Generating Station, Unit No.

Renewal Application Application No.11 and Unit No.2

.

No. 2 Page 3.4-5

Section 3 - Aging Management Review Results

    • Water Chemistry (B.2.1.2)

Table 3.4.2-3, Summary and Air Removal Summary of Aging Management Management Evaluation - Main Condenser Removal System summarizes the results of the aging management Condenser and Air Removal review for the Main Condenser Removal System.

Condenser management

  • 3.4.2.1.4 3.4.2.1.4 Main Steam System Materials Materials The materials construction for the Main materials of construction Main Steam System components components are:

"* Carbon Carbon and Low Alloy Steel Bolting Bolting

    • Stainless Steel Stainless Environments Environments The Main Steam System System components are exposed to the following following environments:
    • Air -Indoor

- Indoor

    • Air - Outdoor Outdoor

"* Air with Borated Water Leakage Water Leakage

  • " Steam
  • " Treated Treated Water
    • Treated Treated Water >140 of OF Aging Effects Requiring Management Requiring Management The following The following aging effects associated associated with the Main Steam System components require management:

components a* Cracking/Stress Cracking/Stress Corrosion Cracking a* Cumulative Damage/Fatigue Cumulative Fatigue Damage/Fatigue a* Material/Boric Acid Corrosion Loss of Material/Boric a* Loss of Loss of Material/General, Material/General, Pitting, and Crevice Crevice Corrosion Corrosion a* Preload/Thermal Effects, Gasket Loss of PreloadlThermal Gasket Creep, and Self-Loosening Self-Loosening a* Wall Thinning/Flow Accelerated Corrosion

  • Thinning/Flow Accelerated Salem Nuclear Nuclear Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page 3.4-6 License License Renewal Renewal Application Application

Section 3 - Aging Management Management Review Results

    • Bolting Integrity Programs management programs (B.2.1.9)

Integrity (8.2.1.9) manage the aging effects programs manage the effects for the

.4)

    • External Surfaces Surfaces Monitoring (B.2.1.24)

(8.2.1.24)

    • Flow-Accelerated Corrosion Flow-Accelerated Corrosion (B.2.1.8)
    • One-Time One-Time Inspection (B.2.1.20)
    • Periodic Inspection Inspection (B.2.2.2)

(B.2.2.2)

  • " Water Chemistry (B.2.1.2)

Table 3.4.2-4, Summary of Aging Management Management Evaluation Evaluation - Main Steam System summarizes summarizes the results of the aging managementmanagement review for the Main Main Steam System

  • 3.4.2.1.5 Main Turbine and Auxiliaries System Materials Materials The materials of construction construction for the Main Turbine and Auxiliaries Auxiliaries System components are: .
    • Aluminum Aluminum
    • Carbon and Low Alloy Steel Bolting Bolting
    • Stainless Steel Stainless Environments Environments The Main Main Turbine and Auxiliaries Auxiliaries System System components are exposed to the the following environments:
    • Air- Indoor Air - Indoor
    • Lubricating Oil Lubricating Aging Effects Requiring Management Management The following aging effects associated with the Main Turbine and Auxiliaries Auxiliaries System components components require management:
    • Loss of Loss of Material/General Material/General Corrosion, Pitting, Crevice, and Microbiologically-lnfluenced Corrosion Microbiologically-Influenced
  • Salem Salem Nuclear Generating Station, Unit Nuclear Generating Renewal Application License Renewal Application No. 1 and Unit No.

Unit No.1 No.22 Page 3.4-7

Section Section 3 - Aging Management Results Management Review Results

    • Loss of PreloadlThermal Aging Management Preload/Thermal Effects, Gasket Creep, and Self-Loosening Management Programs The following aging management Main Turbine and Auxiliaries Programs management programs Self-Loosening manage the aging effects for the programs manage Auxiliaries System components: .

the

    • Bolting Integrity 80lting Integrity (B.2.1.9)

(8.2.1.9)

    • Lubricating Oil Analysis (8.2.1.27)

Lubricating (B.2.1.27)

    • One-Time Inspection Inspection (B.2.1.20)

(8.2.1.20)

Table 3.4.2-5, Summary of Aging Management Evaluation - Main Management Evaluation Main Turbine Turbine and Auxiliaries Auxiliaries System summarizes the results of the aging aging management management review for the Main Turbine and Auxiliaries System.

3.4.2.2 3.4.2.2 AMR Results for Which Further Evaluation Evaluation is Recommended Recommended by the the GALL Report NUREG-1801 provides the basis for identifying those programs that warrant NUREG-1801 warrant further evaluation evaluation by the reviewer reviewer in in the license renewal renewal application.

application. For the the Steam and Power Power Conversion Conversion System, those programs programs are addressed addressed in in the the following subsections.

3.4.2.2.1 3.4.2.2.1 Cumulative Fatigue Damage Damage Fatigue is a TLAA as defined in 10 CFR 54.3. TLAAs are required to be accordance with 10 evaluated in accordance 10 CFR 54.21(c). The evaluation fatigue as a TLAA for the Auxiliary Feedwater System, Main Condensate and Feedwater is discussed in in Section 4.3.

evaluation of metal Feedwater System, Component Feedwater System, and Main Steam System be Cooling Component Cooling

  • Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.

Renewal Application License Renewal Application No.11 and Unit No.2 No. 2 Page 3.4-8

  • 3.4.2.2.2 Loss of MaterialMaterial due to General. General, Pitting.

Pitting, and Crevice Corrosion Corrosion 1.

1. Loss of material materialdue to general,general,pitting, pitting, and and crevice crevice corrosion corrosion could occur for steel piping, piping, piping components, piping piping components, piping elements, elements, tanks, tanks, andand heat exchanger components exposed to treated exchanger components treated water water and and for steel piping, piping, piping components, piping components, and and piping piping elements exposed to steam. steam. The existing aging aging management management program program relies relies on monitoring monitoring and and control control of water chemistry to manage chemistry manage the effects effects of loss of material material due to general, general,pitting, pitting, and crevice corrosion.

and corrosion.However, control of water However, control water chemistry chemistry does not preclude loss preclude loss of material materialdue due to general, general,pitting, pitting, and and crevice crevice corrosion corrosionat locations stagnantflow conditions.

locations of stagnant conditions. Therefore, Therefore, the effectiveness of the water chemistry water chemistry control controlprogram program should be verified verified to ensure ensure thatthat corrosion corrosion is not occurring.

occurring. The GALL GALL Report recommends recommends further further evaluation programsto verify the effectiveness of the water evaluation of programs water chemistry control program.AA one-time inspection control program. inspection of select components components and susceptible locations is an acceptable susceptible locations acceptable method to ensure that corrosion is that corrosion occurringand that not occurring that the component's component's intended function will be intended function be maintainedduring maintained during the period period of extended operation.

operation.

Salem will implement implement a One-Time Inspection program, B.2.1.20, for One-Time Inspection susceptible susceptible locations to verify verify the effectiveness effectiveness of the Water Chemistry program, B.2.1.2, to manage manage the loss of material due to general, pitting, and crevice crevice corrosion corrosion in steel piping, piping components, components, piping elements, heat exchanger exchanger components, tanks, turbine casings, and steel components components exposed to treated water or steam in the Auxiliary Feedwater

  • System, Component Cooling System, Demineralized Demineralized Water System, Main Main Condensate Condensate and Feedwater System, Main Condenser Condenser and Air Removal System, Main Main Steam System, Reactor Coolant Coolant System, Sampling Sampling System, and Steam Generators. The Water Chemistry and One-Time One-Time Inspection programs Inspection programs are described described in Appendix B. B.
2. Loss of material
2. materialdue due to to general, general, pitting, pitting, and crevice corrosion corrosioncould occur for steel piping, for piping, piping piping components, components, and and piping piping elements exposed to lubricating lubricating oil.oil. The existing existing aging aging management management programprogram relies relies on the the periodicsampling periodic sampling and and analysis analysis of lubricating lubricating oil to maintain maintain contaminants contaminants within acceptable within acceptable limits, limits, thereby preserving preserving an environment that is is not conducive to corrosion.

corrosion.However, control of However, control lube oil contaminantscontaminantsmay not always have been adequate preclude corrosion.

adequate to preclude corrosion. Therefore, Therefore, the the effectiveness of lubricating lubricating oil contaminant contaminantcontrol control should be verified to ensure that corrosion ensure that corrosion is not occurring.

occurring. The GALL Report Report recommends recommends further evaluation of further evaluation programs programsto manage corrosionto verify the manage corrosion the effectiveness of the lube oil chemistry control controlprogram.

program. A A one-time inspection inspection of selected selected components components at susceptible susceptible locations locations is an acceptable acceptable method to ensure ensure that corrosion corrosion is not occurring occurring and and that the component's intendedintended function function will be maintained maintainedduringduiing the period of period extended operation.

operation.

Salem will implement implement a One-Time Inspection Inspection program, B.2.1.20, to verify the effectiveness of the effectiveness the Lubricating of the Lubricating Oil Oil Analysis program, B.2.1.27, to manage loss of material manage material duedue to to general, general, pitting, and crevice corrosion in in steel piping, steel piping, piping piping components, components, and piping elements elements exposed exposed to

No.22 Page 3.4-9 3.4-9

Section 3 - Aging Management Management Review Results Results 3.4.2.2.3 lubricating oil in the Auxiliary Feedwater Analysis and One-Time B.

B.

Loss of Material Material due to General, Influenced Corrosion (MIC),

Influenced Feedwater System. The Lubricating Inspection programs One-Time Inspection programs are described Lubricating Oil described in General, Pitting, Crevice, and Microbiologicallv-(MIC), and FoulingFouling in Appendix Appendix Microbiolocqically-

  • Loss of material materialdue to general,general,pitting, pitting, crevice, crevice, and MIC, and fouling fouling could occur in steel piping, piping, piping components, components, and piping piping elements exposed to raw raw water. The GALL Report water. Report recommends recommends further evaluation of a plant-specific further evaluation plant-specific aging management program aging management program to ensure ensure thatthat these aging aging effects are are adequately managed.Acceptance criteria adequately managed. are described criteria are described in Branch Technical Branch Technical Position Position RLSB-1.

Item Number 3.4.1-8 3.4.1-8 is not applicable applicable to Salem. There There are no steel piping, piping, piping components, and piping elements elements exposedexposed to raw water in in the Steam and Power Conversion System.

3.4.2.2.4 3.4.2.2.4 Reduction of Heat Transfer Transfer due to Fouling Fouling 1.

1. Reduction of heat heat transfer transferdue to fouling fouling could occur occur for stainless stainless steel and copper al/oy and alloy heat exchanger exchangertubes exposed to treated treated water.

water. The The existing aging management program aging management program relies relies on control control of water water chemistry chemistry to manage manage reduction reduction of heat heat transfer transferdue to fouling.

fouling. However, However, control control of water chemistry water chemistry may not always always have been adequate adequate to preclude preclude fouling.

fouling.

  • Therefore, the GALL Therefore, GALL Report recommends recommends that that the effectiveness of the water chemistry control water chemistry control program program should should be verified to ensure ensure that reduction reduction of heat transfer transfer due to fouling fouling is not occurring. A occurring. A one-time inspection inspection is an acceptable acceptable method to ensure that reduction ensure that reduction of heat transfer transfer is not occurring occurringand and that that the component's component's intended intended function will maintainedduring be maintained during the period period of extended operation.operation.

Salem will implement implement a One-Time Inspection Inspection program, B.2.1.20, to verify effectiveness of the Water Chemistry program, B.2.1.2, to manage the effectiveness manage the the reduction of heat transfer due to fouling in in stainless steel heat exchanger exchanger components exposed to treated water in the Auxiliary Feedwater components Feedwater System and Component Component Cooling System. The Water Water Chemistry and One-Time One-Time programs are described Inspection programs described in in Appendix B. B.

2. Reduction of heat heat transfer transferdue to fouling fouling could occur occur for steel, stainless steel, stainless steel, steel, and copper copper al/oyalloy heat exchanger exchanger tubes exposed to lubricating lubricatingoil. oil.

The existing aging aging management management program programrelies relies on monitoring monitoringand control control of lube lube oil chemistry chemistry to mitigate mitigate reduction reduction of heat transfer transfer due to fouling.

fouling.

However, control of lube oil contaminants However, control contaminantsmay not always have been adequate to preclude adequate corrosion. Therefore, preclude corrosion. Therefore, the effectiveness of lubricating lubricating oil contaminant contaminantcontrol control should be verified verified to ensure ensure that that fouling is not occurring.

occurring. The GALL GALL Report recommends further further evaluation evaluation of programs to verify the effectiveness of lube oil chemistry chemistry control program.AA one-control program.

inspection of select components at time inspection at susceptible susceptible locations locations is an acceptable acceptable method to determine determine whetherwhether an an aging aging effect effect is not occurring occurring or an an aging aging effect effect isis progressing progressing very slowly such that that the component's Salem Nuclear Generating Salem Nuclear License License Renewal Generating Station, Station, Unit Application Renewal Application No. 1 and Unit No.1 and Unit Unit No.

No.2 2 Page 3.4-10 Page 3.4-10

  • intended function will be maintained intended function operation.

operation.

Salem will implement maintainedduring implement a One-Time the effectiveness effectiveness of the Lubricating manage the reduction during the period period of extended Inspection program, B.2.1.20, One-Time Inspection B.2.1.20, to verify Lubricating Oil Analysis program, B.2.1.27, to reduction of heat transfer due to fouling in stainless steel to steel heat exchanger exchanger tubes exposed to lubricating lubricating oil inin the Auxiliary Feedwater Auxiliary Feedwater System, Component Cooling System, and Service Water System. The The Lubricating Oil Analysis and One-Time Lubricating One-Time Inspection programs are described in described in Appendix B. B.

3.4.2.2.5 Loss of Material Material due to General, Pitting, Crevice.

General. Pitting. Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced 1.

1. Loss of material material due to general, general, pitting and crevice corrosion, pitting and corrosion,and MIC MIC could occur occur in steel (with or or without coating coating oror wrapping) wrapping) piping, piping, piping components, components, piping piping elements, elements, and and tanks exposed to soil. buriedpiping soil. The buried piping and tanks tanks inspection inspection program relies on industry program relies industry practice, frequency of pipe practice, frequency excavation, excavation, and and operating operatingexperience experience to manage manage the effects of loss loss of of material material from generalgeneralcorrosion, corrosion,pitting, pitting, and crevice corrosion, corrosion, and and MIC.

MIC.

The effectiveness The effectiveness of the buried piping and buried piping and tanks inspection program inspection program should be verified to evaluate evaluate an applicant's applicant'sinspection inspection frequency and operating operating experience experience with buried components, ensuring buried components, ensuring that loss of material material is not occurring.

occurring.

  • Salem Salem will implement implement a Buried Piping Inspection Inspection program, program, B.2.1.22, to manage the loss of material material due to general, general, pitting, crevice, and microbiologically-influenced corrosion microbiologically-influenced corrosion (MIG)

(MIC) in steel piping, piping piping, piping components, and piping elements elements exposed to soil in the Auxiliary Feedwater System and the Demineralized Feedwater Demineralized Water Water System. The Buried Piping Piping Inspection program is described described in in Appendix B. B.

2.

2. Loss of material material due to general, general,pitting pitting and crevice corrosion, corrosion, andand MIC MIC could occur occur in steel heat exchanger exchanger components exposed to lubricating oil.

lubricating oil.

The existing aging aging management management programprogram reliesrelies on the periodic periodic sampling and analysis analysis of lubricating lubricating oil to maintain contaminantswithin acceptable maintain contaminants acceptable limits, thereby preserving limits, thereby preservingan an environment environment that that is not conducive conducive to corrosion. However, control corrosion. However, control of lube oil contaminants contaminantsmay not always have been adequate preclude corrosion.

adequate to preclude corrosion. Therefore, Therefore, the effectiveness of lubricatingoil lubricating oil contaminant contaminantcontrol control should be verified to ensure ensure that corrosion corrosion is not occurring.

occurring. The GALL GALL Report recommends recommends further evaluation evaluation of programs programs to manage corrosionto verify the effectiveness of manage corrosion of the lube lube oil chemistry controlcontrolprogram. inspection of selected program. A one-time inspection selected components at at susceptible locations is susceptible locations is an acceptable acceptablemethod to ensure ensure that corrosion corrosion is not occurring occurringand that that the component's component's intended intended function function will be maintained maintainedduringduring the period period of extended operation.

operation.

Salem will implement One-Time Inspection implement a One-Time Inspection program, B.2.1.20, for susceptible locations to verify the effectiveness effectiveness of the Lubricating Oil Analysis program, program, B.2.1.27, to manage manage the loss of material due to general, pitting, general, pitting, crevice, crevice, and microbiologically-influenced corrosion and microbiologically-influenced corrosion (MIG)(MIC)

  • Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.1 Renewal Application License Renewal Application No. 1 and Unit No.

No.22 Page Page 3.4-11

Section Section 3 - Aging Management Management Review Results Review Results in steel piping, piping exchanger components exchanger Feedwater piping components, piping elements, .tanks, components exposed to lubricating Feedwater System and Reactor tanks, and heat lubricating oil in the Auxiliary Auxiliary Coolant System. The Lubricating Reactor Coolant Analysis and One-Time Inspection programs are described B.

B.

heat Lubricating Oil described in Appendix Appendix

Cracking see Cracking due to SCC could occur occur in in the stainless stainless steel piping, piping, piping piping components, piping components, piping elements, elements, tanks, tanks, andand heat heat exchanger exchangercomponents exposed to treated treated water greater than 600 C (>

water greater 0 e 140 0 F), and for stainless

(>140°F), steel stainless steel piping, piping components, piping, piping components, and andpiping elements exposed to steam. steam. The The existing aging existing aging management management program program relies relies on monitoring monitoringand controlcontrolof water chemistry to manage chemistry manage the effects of cracking see.

cracking due to SCC. However,However, high high concentrationsof impurities concentrations impurities at at crevices crevices and locations locations of stagnant stagnantflow conditions could conditions cause Sec.

could cause SCC. Therefore, Therefore, the GALL Report Report recommends recommends that that the effectiveness of the water water chemistry control controlprogram program should be verifiedverified to ensure that ensure see that SCC is is not occurring.

occurring.A one-time inspectioninspection of selected selected components at components at susceptible susceptible locations locations is an an acceptable acceptable method to ensure ensure that see SCC is not occurring occurringand that that the component's intended intended function function will be be maintainedduring maintained during the periodperiod of extended operation.

operation.

implement a One-Time Salem will implement Inspection program, B.2.1.20, One-Time Inspection B.2.1.20, for susceptible locations susceptible locations to verify the effectiveness effectiveness of the Water Chemistry program, B.2.1.2, to manage manage cracking cracking due to stress corrosion corrosion cracking in in

  • stainless steel piping, piping, piping components, piping elements, heat exchanger exchanger components, steam generator components, and tanks exposed to treated steam generator water > 60 deg C (>140 OF) water> OF) in the Auxiliary Feedwater Feedwater System, Demineralized Demineralized Water System, Main Condensate Condensate and Feedwater System, Main Steam Steam System, Sampling System, and Steam Generators. The Water Water Chemistry and One-Time One-Time Inspection programs programs are described described in Appendix B. B.

3.4.2.2.7 Loss of Material Material due to Pitting and Crevice Crevice Corrosion 1.

1. Loss of material materialdue to pitting pitting and crevice corrosion could occur corrosion could occur for stainless steel, aluminum, stainless steel, aluminum, and copper copperalloy piping, piping al/oy piping, piping components, components, and piping piping elements, elements, and for for stainless stainless steel tanks tanks and heat heat exchanger exchanger components exposed to treated treated water.

water. The existing aging aging management program relies program relies on monitoring monitoring and and control control of water water chemistry chemistry to manage manage the effects of loss loss of material materialdue to pitting and crevice corrosion.

pitting and corrosion.

However, control However, control of water water chemistry chemistry does not preclude preclude corrosion corrosion at locations locations of stagnant stagnantflow conditions.

conditions. Therefore, Therefore, the GALL Report Report recommends that the effectiveness of the water water chemistry chemistry program program should be verified verified to ensure ensure that corrosion corrosionis not occurring.

occurring.A A one-time inspection components at susceptible inspection of select components susceptible locations locations isis an acceptable acceptable method to ensureensure thatthat corrosion corrosionis not occurring and that occurring and that the component's component's intended intended function will be maintainedmaintainedduringduring the period period of extended operation.

operation.

Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.1 Application License Renewal Application No. 1 and Unit No.2 No. 2 Page 3.4-12 3.4-12

  • susceptible implement a One-Time Salem will implement susceptible locations crevice corrosion in piping components and piping components exposed One-Time Inspection Inspection program, B.2.1.20, for locations to verify the effectiveness 8.2.1.2, to manage program, B.2.1.2, effectiveness of the Water Chemistry manage the loss of material piping elements, material due to pitting and in aluminum, copper alloy, and stainless steel piping, elements, tanks, and heat exposed to treated water in in the Auxiliary heat exchanger exchanger Auxiliary Feedwater Feedwater System, Chemical Chemical and Volume Control System, Component Component Cooling System, Demineralized Water System, Main Demineralized Main Condensate and Feedwater Feedwater System, Main Condenser and Air Removal Removal System, Main Main Steam System, Reactor Coolant System, Sampling Coolant Sampling System, and Steam Generators. Generators. The Water Chemistry and One-TimeOne-Time Inspection programs programs are described described in Appendix Appendix B.

B.

2. Loss of material materialdue to pittingpitting and and crevice crevice corrosion occur for corrosion could occur stainless steel piping, stainless steel piping, piping piping components, components, and pipingpiping elements exposed to soil.

soil. The GALL GALL Report recommends further evaluation of a plant-further evaluation plant-specific aging aging management management to ensure ensure that that this this aging aging effect is adequately adequately managed. Acceptance criteria managed. criteria are are described Branch Technical described in Branch Technical Position Position RLSB-1.

Number .3.4.1-17 Item Number 3.4.1-17 is not applicable to Salem. The stainless steel piping, piping components, components, and piping elements external surfaces in the elements external the Steam and Power Conversion System are not exposed exposed to soil.

3. Loss of material
3. materialdue to pittingpitting and and crevice crevice corrosion occur for corrosion could occur
  • copper alloy piping, copper al/oy piping, piping piping components, components, and piping piping elements exposed to lubricating lubricating oil.oil. The existing agingaging management managementprogram programrelies relies on the the periodic sampling periodic sampling and analysis lubricatingoil to maintain analysis of lubricating maintain contaminants contaminants within acceptable within acceptablelimits,limits, thereby preserving preserving an environment that is is not conducive to corrosion.

corrosion.However, However, control control of lube oil contaminants contaminantsmay not always have been adequate adequate to preclude corrosion. Therefore, preclude corrosion. Therefore, thethe effectiveness of lubricating lubricating oil oil contaminant contaminantcontrol control should be verified to ensure that ensure that corrosion corrosion is is not occurring.

occurring. The GALL ReportReport recommends recommends further further evaluation evaluation of programs manage corrosion programs to manage corrosionto verify thethe effectiveness of the lube oil chemistry control controlprogram.

program.AA one-time inspection inspection of selected components components at susceptible susceptible locations locations is anan acceptable acceptable method to ensure that corrosion ensure that corrosion is is not occurring and that occurring and that the the component's intended component's intended function function will be maintained maintainedduring during the period period of of extended operation.

operation.

Item Number 3.4.1-183.4.1-18 is not applicable to Salem. There are no copper alloy piping, piping components, and piping elements elements exposed exposed to lubricating lubricating oil in the Steam and Power Power Conversion Conversion System.

3.4.2.2.8 Loss of Material Material due to Pitting,Pitting. Crevice, Crevice. and Microbiologically-Microbiologically-Influenced Corrosion Influenced Loss of material materialdue due to pitting, pitting, crevice, crevice, andand MIC could could occur in stainless steel stainless steel piping, piping components, piping, components, piping piping elements, elements, and heat exchanger exchanger components exposed to lubricating lubricatingoil. oil. The existing aging aging management management program program relies relies on the periodic sampling and analysis periodic sampling analysis of lubricating lubricating oil to maintain maintain contaminants contaminants

No.22 3.4-13 Page 3.4-13

Section 3 - Aging Management Results Management Review Results within acceptable conducive acceptablelimits, conducive to corrosion.

limits, thereby preserving corrosion. However, always have been adequate effectiveness of lubricating ensure that ensure evaluation of programs evaluation lubricatingoil that corrosion programs to manage preserving an environment However, control adequate to preclude oil contaminant contaminantcontrol corrosionis not occurring.

occurring. The GALL manage corrosion environment that control of lube oil contaminants preclude corrosion.

that is not contaminants may not corrosion. Therefore, Therefore, the the control should be verified verified to GALL Report recommends further corrosionto verify the effectiveness of the to further the

  • lube oil chemistry lube chemistry control control program.

program.AA one-time one-time inspection inspection of selected components at susceptible components susceptible locations locations is is an acceptable acceptable method to ensure ensure that that corrosion is corrosion is not occurring occurring and and that the component's component's intended intended function function will be be maintainedduring maintained during the period period of extended.

extended operation.

operation.

Salem will implement a One-Time Inspection program, B.2.1.20, One-Time InspeCtion B.2.1.20, forfor susceptible locations to verify the effectiveness susceptible effectiveness of the Lubricating Analysis Lubricating Oil Analysis program, B.2.1.27, to manage the loss of material due to pitting, crevice, and microbiologically-influenced corrosion (MIC) microbiologically-influenced (MIC) inin stainless steel heat exchangers, piping, and piping components exposed to lubricating lubricating oil in thethe Feedwater System and Main Turbine and Auxiliaries System. The Auxiliary Feedwater The Lubricating Oil Analysis and One-Time Inspection programs Lubricating programs are described described in in Appendix B. B.

3.4.2.2.9 Loss of Material due to General. General, Pitting.

Pitting, Crevice, Crevice. and Galvanic Galvanic Corrosion Loss of material materialdue to general, general,pitting, pitting, crevice, crevice, and andgalvanic corrosioncan galvanic corrosion occur for steel heat occur heat exchanger exchangercomponents components exposed to treated treated water.

water. TheThe

  • existing aging existing aging management managementprogram program relies relies on monitoring monitoring andand control control of water water chemistry to manage chemistry manage the effects of loss of material material due general,pitting, due* to general, pitting, and crevice and crevice corrosion.

corrosion.However, However, control control of water water chemistry does not preclude preclude loss of material loss materialdue to general, general, pitting, pitting, and crevice crevice corrosion corrosion at locations locations of of stagnantflow conditions.

stagnant conditions. Therefore, Therefore, the effectiveness of the water chemistry water chemistry controlprogram control program should be verified verified to ensure ensure that corrosion corrosion is not occurring.

occurring.

The GALL GALL Report recommends recommends furtherfurther evaluation programsto verify the evaluation of programs the effectiveness of the water water chemistry chemistry control control program.

program.AA one-time inspection inspection select components and of select and susceptible locations is an susceptible locations an acceptable acceptable method to ensure that ensure that corrosion corrosion is is not occurring occurring and and that the component's component's intended function will function will be maintained maintainedduringduring the period period of extended operation.

operation.

Salem will implement a One-Time One-Time Inspection program, B.2.1.20, for susceptible locations to verify the effectiveness effectiveness of the Water Chemistry program, B.2.1.2, to manage manage the loss of material due to general, pitting, crevice, and galvanic corrosion in steel heat exchanger exchanger components exposed to treated water in the Main Main Condensate and Feedwater System. The Water Feedwater Chemistry and One-Time Inspection programs programs are described in Appendix B. B.

3.4.2.2.10 Quality Assurance for Aging Aginq Management Non-Safety Related Management of Non-Safety Components Components QA provisions applicable License Renewal applicable to License Renewal are discussed in in Section B.1.3.

Salem Nuclear Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.2 No. 2 3.4-14 Page 3.4-14

Section 3 - Aging Aging Management Management Review Review Results Results

  • 3.4.2.3 Time-Limited Aging Analyses The time-limited Steam and Power
  • .

Analyses time-limited aging analysesanalyses identified below are associated with the Conversion System components:

Power Conversion Section 4.3, Metal Fatigue of Piping and Components Components the 3.

4.3 CONCLUSION

CONCLUSION The Steam and Power Conversion System piping, fittings, and components that are subject to aging management review have been identified in identified in accordance accordance with the requirements requirements of 10 CFR 54.4. The aging management management programs selected selected to manage aging effects for the Steam and Power Power Conversion System components components are identified in the summaries summaries in Section 3.4.2.1 above.

A description description of these aging management management programs provided in Appendix programs is provided Appendix B, S, along with the demonstration demonstration that the identified aging effects will be managed for the period of extended extended operation.

Therefore, Therefore, based on the conclusionsconclusions provided in Appendix S, B, the.

the effects of associated with the Steam and Power Conversion System components aging associated components will be adequately managed so that there is reasonable reasonable assurance that the the intended function(s) will be maintained intended maintained consistent consistent with the current licensing current licensing basis during the period of extended operation..

extended operation

  • Salem Nuclear Nuclear Generating License Renewal Generating Station, Unit No.

Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.4-15 3.4-15

Section 3 - Aging Management Management Review Review Results Results Table Table 3.4.1 Summary of Aging ManagementManagement Evaluations Conversion System Evaluations for the Steam and Power Conversion Item Component Component Effect/Mechanism Aging Effect/Mechanism Aging Further Further Evaluation Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-1 Steel piping, piping, piping Cumulative Cumulative fatigue evaluated TLAA, evaluated Yes, TLAA Fatigue is a TLAA; further evaluation is is components, and damage damage in accordance in accordance documented in documented Subsection 3.4.2.2.1.

in Subsection 3.4.2.2.1.

elements piping elements with 10 CFR exposed to steam or 54.21 (c)

(c) treated water 3.4.1-2 Steel piping, piping, piping Loss of material material due to Water Chemistry Yes, detection of Consistent with NUREG-1801.

Consistent NUREG-1801. The One-components, and general, general, pitting, and and One-Time aging effects effects is to Time Inspection program, B.2.1.20, will be be elements piping elements crevice crevice corrosion Inspection Inspection be evaluated effectiveness of the used to verify the effectiveness the exposed to steam Water Chemistry program, B.2.1.2, to to manage the manage loss of the loss material due of material due to to general, pitting, and crevice crevice corrosion in in steel turbine steel turbine casings, casings, piping, piping, piping piping components, and piping elements elements exposed to steam.

See Subsection Subsection 3.4.2.2.2.1.

3.4.2.2.2.1.

3.4.1-3 Steel heat heat exchanger exchanger Loss of material material due to Water Chemistry Chemistry Yes, detection of Consistent with NUREG-1 Consistent NUREG-1801. 801. The One-components general, general, pitting, and and One-Time aging effects effects is to Time Inspection program, B.2.1.20, 8.2.1.20, will bebe exposed to treated crevice crevice corrosion Inspection Inspection be evaluated used to verify the effectiveness effectiveness of the the water Water Chemistry program, B.2.1.2, to manage manage the the loss of material loss of material due due to to general, pitting, and crevice corrosion general, pitting, and crevice corrosion in in steel heat steel heat exchanger components exchanger components exposed to treated exposed treated water.

See Subsection Subsection 3.4.2.2.2.1.

3.4.2.2.2.1.

Salem Nuclear Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-16 3.4-16 Application License Renewal Application

  • 0
  • Results Review Results Table Table 3.4.1 Summary of Aging Management Summary Management Evaluations Evaluations for the Steam and Power Power Conversion System Item Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-4 Steel piping, piping piping Loss of material due to Water Chemistry Yes, detection of Consistent with NUREG~1801.

Consistent NUREG-1801. The One- One~

components, and general, pitting, and and One~

One-Time Time aging effects is to program, B.2.1.20, will be Time Inspection program, be piping elements piping elements crevice corrosion crevice corrosion Inspection Inspection be evaluated evaluated used to verify the effectiveness the effectiveness of the exposed to treated treated Water Chemistry program, B.2.1.2B.2.1.2 to water water manage the loss of material material due to general, pitting, and crevice corrosion in in steel piping, piping components, and piping elements exposed to treated water.

See Subsection Subsection 3.4.2.2.2.1.

3.4.2.2.2.1.

3.4.1-5 3.4.1~5 Steel Steel heat exchanger Loss of material material due due to Water Chemistry Yes, detection detection of Consistent with NUREG-1 NUREG~1801. 801. The One~

One-components components general, pitting, crevice, and One-Time On~Time aging effects effects is to Time Inspection Inspection program, B.2.1.20, will be be exposed exposed to treated and galvanic corrosion Inspection Inspection be evaluated evaluated used to verify the effectiveness effectiveness of the the water Water Chemistry program, program, B.2.1.2, to to manage the manage the loss loss of of material material due due to to general, pitting, crevice, and galvanic galvanic corrosion corrosion in steel heat exchanger components components exposed to treated water.

See Subsection 3.4.2.2.9.

Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-17 Page 3.4-17 Application License Renewal Application

Section 3 - Aging Aging Management Management Review Results Results Table 3.4.1 Summary Summary of Aging ManagementManagement Evaluations Evaluations for the Steam and Power Conversion System Power Conversion Item Component Component EffectlMechanism Aging Effect/Mechanism Aging Further Evaluation Evaluation Discussion Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-6 3.4.1-6 Steel and stainless material due to Loss of material Water Chemistry Chemistry Yes, detection of Consistent with NUREG-1 NUREG-1801. The One-801. The One-steel tanks exposed general (steel only) and One-Time One-Time aging effects effects is to Time Inspection program, B.2.1.20, will be be to treated treated water water pitting, and crevice Inspection Inspection be evaluated used to verify the effectiveness effectiveness of the the corrosion Water Chemistry Chemistry program, B.2.1.2, to manage the loss of material material due to pitting pitting and crevice and crevice corrosion corrosion in stainless steel in stainless steel tanks exposed tanks exposed to to treated treated water.

water.

See Subsection Subsection 3.4.2.2.7.1 Consistent with NUREG-1801.

Consistent NUREG-1 801. The One-Time Inspection program, B.2.1.20, will be be used to verify the effectiveness effectiveness of the the program, B.2.1.2, to Water Chemistry program, manage the manage the loss of material loss of material due due to to general, pitting, and crevice crevice corrosion in steel tanks exposed to treated water.

See Subsection 3.4.2.2.2.1.

SubsElction 3.4.2.2.2.1.

Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-18 3.4-18 License Application License Renewal Application

  • * *
  • Management Review Results Table 3.4.1 Summary Summary of of Aging Management Evaluations for Management Evaluations for the the Steam Steam and and Power Conversion System Power Conversion Item Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-7 Steel piping, piping, piping Loss of material material due to Lubricating Oil Yes, detection detection of Consistent with NUREG-1801 NUREG-1 801 with components, and general, pitting, and Analysis and aging aging effects effects is to One-Time Inspection exceptions. The One-Time piping elements elements crevice corrosion crevice corrosion One-Time One-Time be evaluated be evaluated program, B.2.1.20, program, B.2.1.20, will will be be used used to verify to verify exposed to Inspection effectiveness of the Lubricating the effectiveness Lubricating Oil lubricating lubricating oil Analysis program, program, B.2.1.27, to manage the the loss of material due to general, pitting, and crevice corrosion in crevice in steel piping, piping piping components, and piping elements elements exposed to lubricating oil.

exposed Exceptions Exceptions apply to the NUREG-1801 recommendations recommendations for Lubricating Oil Analysis program implementation.

program implementation.

See Subsection 3.4.2.2.2.2.

3.4.1-8 3.4.1-8 Steel piping, piping Steel Loss of material due of material due to Plant specific Plant specific Yes, plant specific specific Not Applicable.

Not Applicable.

components, and general, pitting, crevice, piping elements microbiologically-and microbiologically- See Subsection 3.4.2.2.3.

exposed to raw influenced corrosion, and influenced water water fouling fouling 3.4.1-9 3.4.1-9 Stainless steel and Reduction of heat transfer Reduction Water Chemistry Water Chemistry Yes, detection of NUREG-1801. The One-Consistent with NUREG-1801.

copper alloy heat copper alloy due to fouling and One-Time One-Time aging effects effects is is to to Time Inspection Inspection program, program, B.2.1.20, will be be exchanger exchanger tubes Inspection Inspection be evaluated evaluated used to verify the effectiveness effectiveness of thethe exposed to treated Water Water Chemistry program, B.2.1.2, to

-

water water manage the manage the reduction reduction of heat transfer due due to to fouling fouling inin stainless steel heat stainless steel heat exchanger exchanger tubes tubes exposed exposed to treated water.

to treated water.

Subsection 3.4.2.2.4.1.

See Subsection 3.4.2.2.4.1.

Salem Nuclear Generating Salem Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-19 Page 3.4-19 Renewal Application License Renewal Application

Section 3 - Aging Management Management Review Review Results Table 3.4.1 TabJe3.4.1 Summary of Aging Management Evaluations Aging Management Evaluations for the Steam Steam and Power Power Conversion System Item Item Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-10 3.4.1-10 Steel, stainless steel, Reduction of heat transfer Lubricating Lubricating Oil Yes, detection of NUREG-1 801 with Consistent with NUREG-1801 and copper copper alloy due to fouling Analysis and aging effects .is is to exceptions. The One-Time One-Time Inspection heat heat exchanger One-Time One-Time be evaluated evaluated program, B.2.1.20, will be used to verify tubes exposed to Inspection Inspection effectiveness of the Lubricating the effectiveness Lubricating Oil lubricating lubricating oiloil Analysis program, B.2.1.27, to manage the the reduction of reduction heat transfer due to fouling in of heattransfer in stainless steel stainless steel heat exchanger tubes heat exchanger tubes exposed to exposed to lubricating lubricating oil.

oil.

Exceptions Exceptions applyapply to to the NUREG-1 801 the NUREG-1801 recommendations for recommendations for Lubricating Lubricating OilOil Analysis program Analysis program implementation.

implementation.

Subsection 3.4.2.2.4.2.

See Subsection 3.4.1-11 3.4.1-11 Buried steel Buried piping, steel piping, Loss of material Loss material due due to Buried Piping and No Consistent with NUREG-1801.

NUREG-1801. The Buried Buried piping components, piping general, pitting, crevice, Tanks Piping Inspection program, program, B.2.1.22, B.2.1.22, will piping elements, and microbiologically-.

and microbiologically- Surveillance be used used to manage manage the loss of material tanks (with or without influenced corrosion influenced due to general, pitting, crevice, and coating or coating or wrapping) or microbiologically-influenced corrosion microbiologically-influenced corrosion exposed to exposed to soil Yes, detection of of (MIC) in in steel piping, piping components, Buried Piping and -aging effects effects and and piping elements exposed to soil.

Tanks Inspection Inspection operating experience are experience are to to See Subsection Subsection 3.4.2.2.5.1.

3.4.2.2.5.1.

be further be further evaluated evaluated Generating Station, Unit No.1 Salem Nuclear Generating No. 1 and Unit No.

No.22 Page Page 3.4-20 License Renewal Renewal Application Application

  • * *
  • Review Results Results Table 3.4.1 Summary of Aging ManagementManagement Evaluations for the Steam and Power Power Conversion System Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-12 3.4.1-12 Steel heat exchanger exchanger Loss of material due to Lubricating Oil Lubricating detection of Yes, detection Consistent Consistent with NUREG-1801 NUREG-1 801 with components components general, general, pitting, crevice, Analysis and aging effects effects is to exceptions. The One-Time exceptions-. One-Time Inspection exposed to and microbiologically-microbiologically- One-Time One-Time be evaluated program, program, B.2.1.20, will be used to verify lubricating lubricating oil influenced corrosion Inspection effectiveness of the Lubricating Oil the effectiveness Analysis program, B.2.1.27, to manage the the loss of material material due to general, general, pitting, microbiologically-influenced crevice, and microbiologically-influenced corrosion (MIG) (MIC) in steel piping, piping piping components, piping elements, tanks, and heat exchanger exchanger components components exposed exposed to lubricating oil.

Exceptions Exceptions apply to the NUREG-1801 NUREG-1 801 recommendations for Lubricating recommendations Lubricating Oil program implementation.

Analysis program See Subsection Subsection 3.4.2.2.5.2.

3.4.2.2.5.2.

3.4.1-13 3.4.1-13 BWR Only BWROnly Salem Nuclear Nuclear Generating Generating Station, No. 1 and Unit No.2 Station, Unit No.1 No. 2 Page 3.4-21 Page Renewal Application License Renewal

Section Section 3 - Aging Management Management Review Review Results Results Table 3.4.1 Summary Summary of Aging Management Management Evaluations for the Steam and Power Conversion Conversion System Item Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-14 Stainless steel Cracking due to stress Water Chemistry Yes, detection of Consistent with NUREG-1801.

NUREG-1801. The One-piping, piping corrosion cracking cracking and One-Time aging effects is to Time Inspection B.2.1.20, will be Inspection program, 8.2.1.20, be components, piping Inspection evaluated be evaluated used to verify the effectiveness effectiveness of the the elements, tanks, and Water Water Chemistry B.2.1.2, to Chemistry program, 8.2.1.2, heat exchanger exchanger manage cracking cracking due to stress corrosion corrosion components components cracking inin stainless steel piping, piping piping exposed to treated components, piping elements, heat 0C water >60

>60°C exchanger exchanger components, steam generatorgenerator

(>140'F)

(>140°F) components, and tanks exposed exposed to treated water water> > 60 deg C (>140 OF).OF).

Subsection 3.4.2.2.6.

See Subsection 3.4.1-15 3.4.1-15 Aluminum Aluminum and Loss of material material due to Water Water Chemistry Chemistry detection of Yes, detection Consistent with NUREG-1 NUREG-1801. 801. The One-copper alloy piping, pitting and crevice crevice and One-Time aging effects effects is to Time Inspection program, B.2.1.20, 8.2.1.20, will be be piping components, corrosion Inspection Inspection ~- be evaluated evaluated used to verify the effectiveness effectiveness of thethe and piping elements elements Water Water Chemistry program, 8.2.1.2,B.2.1.2, to exposed to to treated manage the loss of material pitting material due to pitting water water crevice corrosion in and crevice in copper alloy heat exchanger components exchanger components and aluminum and aluminum tanks exposed to tanks exposed treated water.

to treated water.

See Subsection 3.4.2.2.7.1.

Subsection 3.4.2.2.7.1.

Salem Nuclear Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-22 Renewal Application License Renewal Application

  • *
  • Review Results Results Table 3.4.1 Table 3.4.1 Summary Summary of of Aging Management Evaluations Aging Management Evaluations for the Steam for the Steam andand Power Power Conversion Conversion SystemSystem Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-16 Stainless steel Loss of material material due to Water Chemistry Yes, detection of Consistent with NUREG-1801.

NUREG-1801. The One-piping, piping pitting and crevice crevice and One-Time One-Time aging aging effects is to Time Inspection program, program, B.2.1.20, will bebe components, and corrosion Inspection Inspection be evaluated evaluated used to verify the effectiveness effectiveness of the the piping elements; Water Chemistry program, B.2.1.2, to Chemistry program, tanks, and heat manage the loss of material material due to stress stress exchanger exchanger corrosion corrosion cracking in in stainless steel piping, components components piping components, piping elements, heat exposed exposed to treated exchanger components, steam generator exchanger water components, and tanks exposed to treated water.

See Subsection Subsection 3.4.2.2.7.1.

3.4.2.2.7.1.

3.4.1-17 Stainless steel Loss of material due to Plant specific Yes, plant specific Not Applicable.

piping, piping pitting and crevice crevice components, and corrosion See Subsection Subsection 3.4.2.2.7.2.

elements piping elements exposed exposed to soil 3.4.1-18 Copper alloy piping, Copper Loss of material due to Lubricating Oil Yes, detection of Not Applicable.

piping components, piping pitting and crevice Analysis and aging aging effects is to and piping elements elements corrosion One-Time be evaluated evaluated See Subsection Subsection 3.4.2.2.7.3 exposed exposed to Inspection lubricating oil Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-23 Page 3.4-23 License Renewal Renewal Application Application

Section 3 - Aging Section Management Review Aging Management Review Results Results Table Table 3.4.1 3.4.1 Summary Summary of of Aging Aging Management Evaluations for the Steam Management Evaluations Steam and and Power Conversion System Power Conversion Item Item Component Component Aging EffectlMechanism Effect/Mechanism Aging Further Further Evaluation Evaluation Discussion Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-19 Stainless Stainless steel steel Loss ofof material material due due to Lubricating Oil Lubricating Oil detection of Yes, detection of Consistent with Consistent with NUREG-1 NUREG-1801 801 with with piping, piping, piping pitting, crevice, and Analysis and and aging effects aging effects is is to exceptions. The One-Time exceptions. One-Time Inspection Inspection components, piping components, piping microbiologically-microbiologically- One-Time One-Time be evaluated evaluated 8.2.1.20, will be used to verify program, B.2.1.20, elements, and heat elements, influenced corrosion influenced Inspection Inspection the effectiveness Lubricating Oil effectiveness of the Lubricating exchanger exchanger Analysis program, B.2.1.27, to manage Analysis manage the the components components loss of material due due to pitting, pitting, crevice, and exposed exposed to microbiologically-influenced corrosion microbiologically-influenced corrosion lubricating oil lubricating (MIC) in (MIC) in stainless steel piping, piping piping components, piping piping elements, and heat exchanger exchanger components exposed to components exposed to lubricating oil.

lubricating oil.

Exceptions apply Exceptions apply to the NUREG"1801 to the NUREG-1801 recommendations Lubricating Oil recommendations for Lubricating Oil Analysis program implementation.

Analysis program implementation.

See Subsection Subsection 3.4.2.2.8 3.4.2.2.8 3.4.1-20 Steel tanks exposed Loss of material/

material! general, Aboveground Aboveground No Not Applicable. There are no steel tanks tanks to air -- outdoor pitting, and crevice Steel Tanks exposed to air - outdoor (external) in exposed the in the (external) corrosion corrosion Conversion System.

Steam and Power Conversion

-

3.4.1-21 High-strength steel High-strength Cracking due to cyclic Bolting Integrity No Not Applicable. There are no high-closure bolting loading, stress corrosion corrosion strength steel closure bolting exposed to exposed to air with cracking air with steam or water leakage leakage in in the the steam or water Steam and Power Conversion System.

leakage leakage Nuclear Generating Station, Unit No.

Salem Nuclear No.11 and Unit Unit No.2 No. 2 Page 3.4-24 3.4-24 License Renewal License Renewal Application Application

  • * *
  • Management Review Results Results Table Table 3.4.1 Summary of Aging Management Evaluations for the Steam and Power Conversion Management Evaluations Conversion System Item Component Effect/Mechanism Aging Effect/Mechanism Aging Evaluation Further Evaluation Discussion Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-22 Steel Steel bolting and Loss of material material due to Integrity Bolting Integrity No Consistent with NUREG-1801 NUREG-1801 with closure closure bolting general, pitting, and exceptions. The Bolting Integrity Integrity program, program, exposed exposed to air with crevice corrosion; corrosion; loss of B.2.1.9, will be used to manage manage the loss of steam steam or water preload due to thermal preload material material due to general, general, pitting, and leakage, air -

leakage, air- effects, gasket creep, and crevice corrosion, and the loss of preload preload outdoor (external), or self-loosening due to thermal thermal effects, gasket creep, and air air-- indoor indoor self-loosening in steel bolting exposed self-loosening exposed to uncontrolled uncontrolled indoor and outdoor air in the Auxiliary (external);

(external) ; Feedwater Feedwater System, Main Condensate and Feedwater Feedwater System, Main Steam System, and Main and Turbine and Main Turbine and Auxiliaries System.

Auxiliaries System.

Exceptions Exceptions apply to the apply to the NUREG-1801 NUREG-1801 recommendations for Bolting Integrity recommendations program implementation.

implementation.

3.4.1-23 3.4.1-23 Stainless steel Cracking due to stress Closed-Cycle Closed-Cycle No Consistent with NUREG-1801 NUREG-1 801 withwith piping, piping corrosion cracking Cooling Water exceptions. The Closed-Cycle Closed-Cycle Cooling components, and System Water System System program, B.2.1.12, will be be piping elements used to manage manage the cracking cracking due to stress stress exposed to closed- corrosion cracking in stainless steel heat heat cycle cooling water water exchanger components exposed to to

>60 0 C (>140*F)

>60°C (> 140°F) closed-cycle cooling water >60°C closed-cycle >60 0 C (>140 0

(>140°F) F) in the Auxiliary Feedwater System in the Auxiliary Feedwater System and and Chemical and Chemical and Volume Volume Control Control System.

System.

Exceptions apply to the NUREG-1801 recommendations for Closed-Cycle recommendations Closed-Cycle Cooling Water System System program implementation.

Salem Salem Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.4-25 License Renewal Renewal Application Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table Table 3.4.1 3.4.1 Summary of Summary of Aging Aging Management Management Evaluations the Steam Evaluations for the Steam and and Power Power Conversion Conversion System Item Item Component Component Aging-EffectiMechanism Aging-Effect/Mechanism Aging Further Evaluation Further Evaluation Discussion Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-24 3.4.1-24 Steel Steel heat heat exchanger exchanger Loss of material due to material due to Closed-Cycle Closed-Cycle No No Not Applicable. There Not Applicable. There are no no steel steel heat heat components components general, general, pitting, crevice, Cooling Cooling Water exchanger components exposed to closed exchanger components exposed exposed to closed closed and galvanic galvanic corrosion corrosion System cycle cycle cooling cooling water water in in the Steam Steam and cycle cooling water cycle cooling Power Power Conversion System.

3.4.1-25 3.4.1-25 Stainless Stainless steel steel Loss Loss ofof material material due to Closed-Cycle Closed-Cycle No Consistent with NUREG-1 Consistent NUREG-1801 801 with with piping, piping, piping pitting and crevice Cooling Water exceptions. The Closed-Cycle Cooling Closed-Cycle Cooling components, piping corrosion System Water Water System program, B.2.1.12, will be System program, be elements, elements, and heat used manage loss of material used to manage material due due to exchanger exchanger pitting and crevice crevice corrosion in stainless corrosion in stainless components components steel steel piping, piping components, piping piping exposed exposed to closed closed elements, elements, and heat heat exchanger exchanger cycle cooling cycle cooling water components components exposed exposed to closed cycle cycle cooling cooling water in the Auxiliary Feedwater System.

System.

Exceptions Exceptions apply apply to the the NUREG-1801 recommendations recommendations for for Closed-Cycle Closed-Cycle Cooling Water System program implementation.

implementation.

3.4.1-26 Copper alloy piping, Loss of material material due to Closed-Cycle Closed-Cycle No Not Applicable. There are no copper alloy piping components, pitting, crevice, and Cooling Water piping, piping components, and piping piping and piping elements galvanic galvanic corrosion corrosion System elements exposed to closed cycle cooling cooling exposed to closed water water in the Steam and Power Power Conversion cycle cooling water System.

No. 1 and Unit No.2 Salem Nuclear Generating Station, Unit No.1 No. 2 Page 3.4-26 Page License Renewal License Renewal Application Application

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  • Review Results Results Table 3.4.1 Table 3.4.1 Summary of Summary of Aging Aging Management Management Evaluations Evaluations for for the the Steam Steam and and Power Power Conversion System Item Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Evaluation Further Evaluation Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-27 3.4.1-27 Steel, stainless Steel, stainless steel, steel, Reduction of Reduction heat transfer of heat transfer Closed-Cycle Closed-Cycle No No Not Applicable. There are no stainless Not stainless and copper and copper alloy alloy due to due fouling to fouling Cooling Water Water steel, steel or steel, or copper copper alloy heat exchanger exchanger heat exchanger heat exchanger System tubes exposed to closed cycle cooling tubes exposed tubes exposed to to water inin the Steam and Power Conversion closed cycle closed cycle cooling cooling System.

water 3.4.1-28 3.4.1-28 Steel external Steel external Loss of Loss of material material due to to External Surfaces No NUREG-1 801. The Consistent with NUREG-1801. The surfaces exposed surfaces exposed to to general general corrosion corrosion Monitoring Monitoring External Surfaces Surfaces Monitoring program, Monitoring program, air - indoor air- indoor B.2.1.24, will be used to manage 8.2.1.24, manage the loss loss uncontrolled uncontrolled of material material due to general general corrosion on thethe (external),,

(external) external external surfaces surfaces of steel piping, piping piping condensation condensation components, piping elements, heat (external), or air exchanger exchanger components, tanks, and steam outdoor (external) outdoor (external) generator generator and turbine casings exposedexposed to indoor air indoor air in in the the Auxiliary Auxiliary Feedwater Feedwater System, Main Condensate and Feedwater Feedwater System, Main Condenser Condenser and Air Removal System, Main Steam System, and Steam Generators.

Salem Salem Nuclear Nuclear Generating Generating Station, Station, Unit No. 1 and Unit No.1 and Unit No. 2 Unit No.2 Page 3.4-27 Page 3.4-27 License Renewal Application License Renewal Application

Section 3 - Aging Management Management Review Review Results Results Table 3.4.1 Summary of Aging Management Evaluations for the Steam and Power Management Evaluations Conversion System Power Conversion Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Discussion Number Management Management Recommended Programs Programs 3.4.1-29 Steel piping, piping, piping Wall thinning due to flow-f1ow- Flow-Accelerated Flow-Accelerated No Consistent with NUREG-1 Consistent NUREG-1801 801 with components, and accelerated accelerated corrosion corrosion Corrosion exceptions. The Flow-Accelerated Flow-Accelerated piping elements Corrosion program, Corrosion B.2.1.8, will be used to program, 8.2.1.8, exposed to steam or manage wall thinning due to f1ow-manage flow-treated water accelerated corrosion in accelerated in steel piping, piping components, piping elements, and exposed to steam or .

heat exchanger exposed treated water in in the Auxiliary Feedwater System, Main System, Main Condensate Condensate and and Feedwater Feedwater System, Main Steam System, and Steam Generators. ,

Exceptions apply to the NUREG-1801 Exceptions NUREG-1 801 recommendations for recommendations for Flow-Accelerated Flow-Accelerated Corrosion program Corrosion implementation.

program implementation.

3.4.1-30 3.4.1-30 Steel piping, piping Steel of material Loss of Loss material due to Inspection of No Consistent with NUREG-1801.

Consistent NUREG-1801. The The components, and general, pitting, and Internal Surfaces Internal Surfaces Inspection of Internal Surfaces in in piping elements crevice corrosion in Miscellaneous in Miscellaneous Miscellaneous Piping and Ducting Miscellaneous exposed to air exposed air Piping and Piping Components Components program, B.2.1.26, will program, B.2.1.26, will be be outdoor (internal) outdoor (internal) or*

or Ducting used to manage the loss of material material due to.

condensation condensation Components Components general, pitting, and crevice creviCe corrosion in in (internal) steel piping, piping components, piping elements, and turbine components components exposed to air/gas - wetted in exposed in the Auxiliary Feedwater System.

Salem Nuclear Generating Station, Unit No.

Nuclear Generating No.11 and Unit No.2 No. 2 Page 3.4-28 Renewal Application License Renewal

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  • 0
  • Section
  • S 3 - Aging Management Review Results Section 3 - Aging Management Review Results Table 3.4.1 Summary Summary of Aging ManagementManagement Evaluations Evaluations for the Steam and Power Conversion Conversion System Item Component Component Effect/Mechanism Aging Effect/Mechanism Aging Further Evaluation Evaluation Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-31 Steel Steel heat exchanger exchanger Loss of material material due to Open-Cycle Open-Cycle No Not Applicable.

Applicable. There are no steel heat components components general, pitting, crevice, Cooling Water exchanger exchanger components components exposed to raw exposed to raw galvanic, and System water inin the Steam and Power Conversion water microbiologically-microbiologically- System.

influenced corrosion, influenced corrosion, and and fouling fouling 3.4.1-32 Stainless steel and Loss of material material due to Open-Cycle No Not applicable. There are no stainless stainless copper alloy piping, pitting, crevice, and Cooling Water Water steel and copper alloy piping, piping piping components, microbiologically-microbiologically- System components, and piping elements elements and piping elements influenced corrosion influenced exposed to raw water in in the Steam and exposed to raw Power Conversion Conversion System.

water water Salem Nuclear Generating Generating Station, No. 1 and Unit No.2 Station, Unit No.1 No. 2 Page 3.4-29 License Renewal Renewal Application Application

Section 33 - Aging Management Management Review Results Results Table Table 3.4.1 3-4.1 Summary Summary of Aging Management Evaluations Aging Management Evaluations for the Steam Power Conversion System Steam and Power Item Component Component Effect/Mechanism Aging Effect/Mechanism Aging Further Evaluation Further Evaluation Discussion Discussion Number Management Management Recommended Recommended Programs Programs Consistent with NUREG-1801.

NUREG-1801. The Open-3.4.1-33 3.4.1-33 Stainless Stainless steel heat Loss of material due to Open-Cycle Open-Cycle No Cycle Cooling Water System program, program, exchanger exchanger pitting, pitting, crevice, and Cooling Water B.2.1.11, will be used 8.2.1.11, used to manage the loss loss components components microbiologically-microbiologically- System of material due to pitting, crevice, exposed exposed to raw influenced influenced corrosion, and microbiologically-influenced corrosion, microbiologically-influenced corrosion, and water water fouling fouling in stainless steel heat exchanger exchanger components, piping,piping, piping components, and piping elements elements exposed exposed to raw water in the Main Condensers and Air Removal System and Service Service Water Water System.

Components in the Fire Protection System Components have been aligned aligned to this item number number material, environment, based on material, environment, and aging aging effect. The Fire Water System program, B.2.1.16, will be substituted to manage 8.2.1.16, manage loss of material material due to pitting, crevice, and microbiologically-influenced corrosion microbiologically-influenced (MIC), and fouling of the stainless steel heat exchanger exchanger components exposed exposed to raw water for the Fire Protection System.

Components in the Radioactive Drain Drain System and Containment Structure have Containment Structure have been aligned to this item number number based on material, environment, and aging effect.

Inspection program 8.2.2.2 The Periodic Inspection B.2.2.2 will be substituted substituted to manage manage loss of material due to pitting, crevice, material crevice, and microbiologically-influenced corrosion microbiologically-influenced (MIC), and fouling of the stainless steelsteel piping, piping, piping components, components, sump screens, and piping elements elements exposed to raw waterwater for the Radioactive Radioactive Drain System and Containment Structure.

Containment Salem Nuclear Salem Generating Station, Nuclear Generating Station, Unit No.11 and Unit No. and Unit No.2 Unit No. 2 Page 3.4-30

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  • Management Review Results Table 3.4.1 Summary of Aging Management Evaluations for the Steam and Power Conversion Management Evaluations Conversion System Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Discussion Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-34 3.4.1-34 Steel, stainless steel, Reduction of heat transfer transfer Open-Cycle Open-Cycle No Not applicable. ThereThere are no steel, and copper copper alloy due to fouling .Cooling Water Water copper alloy heat stainless steel, and copper heat exchanger exchanger System exchanger tubes exposed to raw water tubes exposed to with a reduction reduction of heat heat transfer due to raw water water fouling aging effect/mechanism effect/mechanism in thethe Steam and Power Conversion System.

3.4.1-35 Copper alloy >15% Loss of material material due to Selective Selective No Consistent with NUREG-1801.

NUREG-1801. The The Zn piping, piping selective leaching leaching Leaching Leaching of Selective Leaching of Materials Materials program, components, and Materials Materials B.2.1.21, will be used to manage B.2.1.21, manage the lossloss piping elements of material due to selective selective leaching inin exposed to closed copper copper alloy with greater than 15% 15% Zn cycle cooling water, heat exchanger exchanger components components exposed to raw water, or treated raw or treated water in the MainMain water water Condenser and Air RemovalRemoval System.

3.4.1-36 Gray cast iron piping, Loss of material material due to Selective No No Not applicable. There are no gray cast piping components, selective selective leaching leaching Leaching of iron piping, piping components, and piping piping and piping elements Materials elements exposed to soil, treated water, or exposed exposed to soil, raw water in the Steam and Power treated water, or raw Conversion System.

Conversion water Salem Nuclear Generating No.1I and Unit No.2 Generating Station, Unit No. No. 2 Page Page 3.4-31 License Renewal Application Renewal Application

Section 3 - Aging Management Review Results Results Table 3.4.1 Summary Summary of Aging ManagementManagement Evaluations Evaluations for the Steam and Power Conversion System Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Discussion Number Management Management Recommended Recommended Programs Programs 3.4.1-37 3.4.1-37 Steel, stainless steel, Loss of material material due to Water Chemistry No NUREG-1801. The Water Consistent with NUREG-1801.

and nickel-based nickel-based pitting and crevice Chemistry program, B.2.1.2, will be used alloy piping, piping corrosion to manage manage the loss of material material due to components, and pitting and crevice corrosion stainless corrosion in stainless piping elements steel, piping, piping piping components, and exposed to steam piping elements exposed to steam in the the Auxiliary Feedwater Feedwater System and Main Main Steam System.

Consistent with NUREG-1801.

NUREG-1801. The Boric Boric 3.4.1-38 Steel bolting and Loss of material material due to Boric Acid No Acid Corrosion program, B.2.1.4, will be be external surfaces boric acid corrosion corrosion Corrosion Corrosion used to manage the loss of material due to exposed to air with boric acid corrosion on the external borated borated water water surfaces surfaces of steel bolting, heat exchanger exchanger leakage leakage components, piping, piping components, piping elements, steam generator generator components, tanks, and turbineturbine casings casings exposed exposed to air with borated borated water leakage water leakage in the in the Auxiliary Feedwater System, Auxiliary Feedwater System, Main Main Condensate Feedwater System, Main Condensate and Feedwater Main Steam System, and Steam Generators.

3.4.1-39 3.4.1-39 Stainless Stainless steel Cracking due to stress Cracking Water Chemistry No Consistent Consistent with NUREG-1801.

NUREG-1801. The Water Water piping, piping, piping corrosion cracking Chemistry program, program, B.2.1.2, will be used components, and to manage cracking cracking due to stress piping piping elements corrosion corrosion cracking in stainless stainless steel piping, exposed exposed to steam steam piping components, and piping elements exposed to steam in the Auxiliary Feedwater System and Main Steam Feedwater System.

Salem Nuclear Generating Salem Nuclear Generating Station, Station, Unit No.11 and Unit Unit No. Unit No.2 No. 2 Page 3.4-32 3.4-32 License Renewal License Renewal Application Application

  • * *
  • Management Review Results Table 3.4.1 Summary of Aging Management Conversion System Evaluations for the Steam and Power Conversion Management Evaluations Item Component EffectlMechanism Aging Effect/Mechanism Aging Further Evaluation Further Evaluation Discussion Discussion Number Number Management Management Recommended Recommended Programs Programs 3.4.1-40 3.4.1-40 Glass piping None None NA - NoAEM NA- No AEM or There are no glass piping Not applicable. There piping elements exposed to elements AMP exposed to air, lubricating elements exposed lubricating oil, air, lubricating air, lubricating oil, raw water, and treated water in raw the Steam in the Steam raw water, and and Power Conversion System.

treated treated water 3.4.1-41 Stainless steel, None None NA NA-- NoAEM No AEM or NUREG-1801.

Consistent with NUREG-1801.

copper alloy, and AMP AMP nickel alloy piping, piping components, and piping elements elements exposed to air --

indoor uncontrolled (external)

(external) 3.4.1-42 Steel piping, piping None None NA NA-- NoAEM No AEM or Not applicable. All indoor air components, and AMP environments environments at Salem are assumed to be be piping elements uncontrolled for license license renewal.

exposed to air -

indoor controlled (external) 3.4.1-43 Steel and stainless stainless None None NA NA-- NoAEM No AEM or Not applicable. There are no steel and steel piping, piping AMP stainless steel piping, piping components, components, and and piping elements in concrete in elements in in the the piping elements in in Steam and Power Conversion System.

concrete concrete Salem Nuclear Generating Salem Generating Station, Unit No.

No.11 and Unit No.

No.22 Page 3.4-33 3.4-33 License Renewal License Application Renewal Application

Section 3 - Aging Management Management Review Review Results Results Table 3.4.1 Summary of Aging Management Summary Evaluations for the Steam and Power Conversion System Management Evaluations Item Component Component Aging Effect/Mechanism Effect/Mechanism Aging Further Evaluation Evaluation Discussion Discussion Number Number Management Management Recommended Recommended Programs Programs Not applicable.

Not applicable. There There are no steel, are no steel, 3.4.1-44 3.4.1-44 Steel, stainless steel, None*

None None None NA - No NA- AEM or NoAEM stainless steel, aluminum, and copper aluminum, and aluminum, AMP alloy piping, piping components, and copper alloy piping, exposed to gas in piping elements exposed in the the piping components, Steam and Power Conversion Conversion System.

and piping elements piping elements exposed to gas gas Salem Nuclear Nuclear Generating Generating Station, Unit No. 11 and Unit No.2 No. 2 Page 3.4-34 License Renewal License Renewal Application Application

  • * *
  • Section33--Aging Section
  • ReviewResults ManagementReview Aging Management Results Table 3.4.2-1 Table 3.4.2-1 Auxiliary Feedwater System Auxiliary Feedwater System Summary of Summary Management Evaluation Aging Management of Aging Evaluation Table 3.4.2-1 Table 3.4.2-1 Feedwater System Auxiliary Feedwater Auxiliary System Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table I1Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Vol. Item Management Management Bird Screen Bird Screen Filter Filter Stainless Steel Stainless Steel Air -- Outdoor Air Outdoor Loss of Loss of Material/Pitting Material/Pitting Aboveground Non-Steel Aboveground Non-Steel l1l.B2-7 II I. B2-7 3.5.1-50 3.5.1-50 E,

E,1 1

_ _ _ _and Crevice Corrosion and Crevice Corrosion Tanks Tanks VIII.H-4 3.4.1-22 B Bolting Bolting Mechanical Closure Carbon MechanicalClosure Carbon and Air -- Indoor Low Air and Low Loss of (External) Loss Indoor(External) of Material/General, Material/General, Bolting Integrity Bolting Integrity VIII.H-4 3.4.1-22 B Alloy Alloy Steel Steel and Crevice Pitting, and Pitting, Crevice Bolting Bolting Corrosion Corrosion Bolting Bolting Mechanical Carbon and Closure Carbon Mechanical Closure Indoor (External)

Air -- Indoor Low Air and Low (External) Loss of Loss of Preload/Thermal PreloadfTherrnal Bolting Integrity Bolting Integrity VIII.H-5 VIII.H-5 3.4.1-22 3.4.1-22 BB Alloy Steel Alloy Steel Gasket Creep, Effects, Gasket Effects, Creep, Bolting Bolting_ and Self-Loosening and Self-Loosening Bolting Bolting Mechanical Closure Mechanical Carbon and Closure Carbon and Low Low Air Outdoor (External)

Air -- Outdoor of Material/General, Loss of (External) Loss Material/General, Bolting Integrity Bolting Integrity VIII.H-1 VII I. H-1 3.4.1-22 3.4.1-22 BB Alloy Steel Alloy Steel Pitting, and Pitting, and Crevice Crevice Bolting Bolting_ Corrosion Corrosion Bolting Bolting Carbon and Closure Carbon Mechanical Closure Mechanical and Low Low Air with Borated Air with Water Loss Borated Water Material/Boric Acid of Material/Boric Loss of Acid Acid Corrosion Boric Acid Boric Corrosion VIII.H-2 VII I. H-2 3.4.1-38 3.4.1-38 AA Alloy Steel Alloy Steel Leakage (External)

Leakage (External) Corrosion Corrosion Bolting Bolting Flow Element Flow Element Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel Indoor (External)

Air -- Indoor Air (External) None None None None Vlll.l-10 VIII.I-10 3.4.1-41 3.4.1-41 AA Flow Element Flow Element Pressure Boundary Pressure Boundary Steel Air Stainless Steel Stainless Air with Borated Water with Borated Water None None None None VII.J-16 VI\.J-16 3.3.1-99 3.3.1-99 AA Leakag_e (External)

Leakage (External)

Flow Element Flow Element Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel ITreated Water (Internal)

Treated Water (Internal) Loss of Loss of Material/Pitting Material/Pitting One-Time Inspection One-Time Inspection VIII.G-32 VII\.G-32 3.4.1-16 3.4.1-16 AA and Crevice Corrosion and Crevice Corrosion Flow Flow Element Element Pressure Boundary Pressure Boundary Stainless Steel Stainless Treated Water Steel Treated Loss of (Internal) Loss Water (Internal) of Material/Pitting Material/Pitting Water Chemistry Water Chemistry VIII.G-32 VIII.G-32 3.4.1-16 3.4.1-16 AA and Crevice Corrosion and Crevice Corrosion Heat Leakage Boundary Exchanger Leakage Heat Exchanger Boundary Stainless Steel Stainless Steel Indoor (External)

Air -- Indoor Air (External) None None None None VIII.l-10 VII 1.1-1 0 3.4.1-41 3.4.1-41 CC Components Components (Tubeside (Tubeside (Auxiliary (Auxiliary Components)

Components)

Feedwater Storage Feedwater Storage Tank)

Tank)

Salem Generating Station, Nuclear Generating Salem Nuclear Unit No.

No. 1 and Unit Station, Unit No.1 No.22 Page 3.4-35 Page 3.4-35 License Renewal Renewal Application

Section 33 -- Aging Section Aging Management Management Review Review Results Results Table 3.4.2-1 3.4.2-1 Auxiliary Feedwater Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Table Notes Notes Type Function Requiring Programs Vol. 2 Item Item Management Management Heat Exchanger Leakage Heat Exchanger Boundary Leakage Boundary Stainless Steel Stainless Air with Borated Water None None VII.J-16 3.3.1-99 C Components Components (Tubeside (External)

Leakage (External)

(Auxiliary Components)

Feedwater Storage Feedwater Storage Tank)

Heat Leakage Boundary Heat Exchanger Leakage Stainless Steel Closed Cycle Cooling Cracking/Stress Cracking/Stress Corrosion Closed-Cycle Cooling VIII.G-28 3.4.1-23 D Components Components (Tubeside ~ater Water (Internal)

(Intemal) > 140 140 F Cracking Cracking Water System (Auxiliary Components)

Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Leakage Boundary Exchanger Leakage Stainless Steel Closed Cycle Cooling Loss of Material/Pitting Material/Pitting Closed-Cycle Cooling VIII.G-2 3.4.1-25 B Components Components (Tubeside ~ater Water (Internal)

(Intemal) > 140 FF and Crevice Corrosion Corrosion Water Water System (Auxiliary Components)

Components)

Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Heat Pressure Boundary Exchanger Pressure Boundary Stainless Steel Air --Indoor Indoor (External)

(External) None None None - VIII.I-10 VII 1.1-1 0 3.4.1-41 3.4.1-41 C C

Components (Shellside (Shellside (Auxiliary Components)

Components)

Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Exchanger Pressure Pressure Boundary Stainless Steel Air with Borated Water None None None VII.J-16 3.3.1-99 3.3.1-99 C C

Components Components (Shellside Leakage (External)

Leakage (Auxiliary Components)

Components)

Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel r-reated Treated Water (Internal) Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection VIII.F-27 VIII.F-27 3.4.1-16 A Components Components (Shellside and Crevice Crevice Corrosion (Auxiliary Components)

Components)

Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel [Treated Loss of Material/Pitting Material/Pitting Water Chemistry VIII.F-27 3.4.1-16 3.4.1-16 A Components Components (Shellside and Crevice Crevice Corrosion Corrosion (Auxiliary Components)

Feedwater Storage Feedwater Storage Tank)

Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-36 License Renewal Renewal Application

  • Application
  • Section 3-Section 3- Aging

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1I Item Item Notes Notes Type Type Function Function Requiring Requiring Programs Vol. 22 Item Item Management Management Heat Exchanger Pressure Heat Exchanger Pressure Boundary Boundary Stainless Steel Closed Cycle Cooling Cracking/Stress Corrosion Closed-Cycle Cooling VIII.G-28 VIILG-28 3.4.1-23 D Components Components (Tubes) Water (Internal) > 140 FF Water Cracking Cracking Water System (Auxiliary Feedwater Storage Feedwater Storage Tank)

Tank)

Heat Exchanger Heat Exchanger Pressure Pressure Boundary Boundary Stainless Steel Stainless Steel Closed Closed Cycle Cycle Cooling Cooling Material/Pitting Loss of Material/Pitting Closed-Cycle Cooling Closed-Cycle VIII.G-2 VIILG-2 3.4.1-25 B Components (Tubes) Water (Internal)>

Water (Intemal) > 140 F F and Crevice Corrosion Water System (Auxiliary Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Heat Exchanger Pressure Pressure Boundary Boundary Stainless Steel Stainless Steel Treated Water Treated Water Loss of Material/Pitting Material/Pitting One-Time Inspection Inspection VIII.G-32 VIILG-32 3.4.1-16 C Components Components (Tubes) (External) and Crevice Corrosion (Auxiliary Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Heat Pressure Boundary Exchanger Pressure Boundary Stainless Steel Treated Water Loss of Material/Pitting Water Chemistry Chemistry VIII.G-32 VIILG-32 3.4.1-16 C Components Components (Tubes) (External)

(External) and Crevice Corrosion (Auxiliary Feedwater Storage Feedwater Storage Tank)

Heat Exchanger Heat Exchanger Pressure Pressure Boundary Boundary Stainless Stainless Steel Closed Cycle Steel Closed Cycle Cooling Cracking/Stress Corrosion Cooling Cracking/Stress Closed-Cycle Cooling Closed-Cycle VIII.G-28 VIILG-28 3.4.1-23 3.4.1-23 D D

Components Components (Tubesheet) ~ater Water (Internal)>

(Internal) > 140 F Cracking Water System (Auxiliary Feedwater Feedwater Storage Storage Tank)

Heat Exchanger Heat Exchanger Pressure Boundary . Stainless Pressure Boundary Stainless Steel Closed Cycle Steel Closed Cycle Cooling Cooling Loss of Loss of Material/Pitting Material/Pitting Closed-Cycle Closed-Cycle Cooling VIII.G-2 VIILG-2 3.4.1-25 3.4.1-25 B Components Components (Tubesheet) ~ater Water (Internal) > 140 F (Internal) > and Crevice Corrosion Water System (Auxiliary Feedwater Feedwater Storage Storage Tank)

Tank)

Heat Exchanger Heat Pressure Boundary Exchanger Pressure Boundary Stainless Stainless Steel Steel Treated Water Treated Water Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection VIII.F-27 VIILF-27 3.4.1-16 3.4.1-16 A Components Components (Tubesheet) (External)

(External) and Crevice Corrosion (Auxiliary (Auxiliary Feedwater Feedwater Storage Storage Tank)

Tank)

Salem Salem Nuclear Nuclear Generating Generating Station, Station, Unit No.

No.11 and and Unit No.

No.22 Page 3.4-37 Page License Renewal License Renewal Application Application

Section 3 -- Aging Management Management Review Revfiew Results Table 3.4.2-1 3.4.2-1 Feedwater System Auxiliary Feedwater (Continued)

Component Component Intended Intended Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Table Notes Notes Type Function Requiring Programs Programs Vol. 2 Item Item Management Management Heat Exchanger Exchanger Pressure Boundary Stainless Steel Treated Treated Water Loss loss of Material/Pitting Material/Pitting Chemistry Water Chemistry VIII.F-27 VII I. F-27 3.4.1-16 A Components Components (Tubesheet) (External) and Crevice Corrosion (Auxiliary Storage Feedwater Storage, Tank)

Heat Heat Exchanger Heat Transfer Stainless Steel Lubricating lubricating Oil Reduction of Heat Lubricating lubricating Oil Analysis VIII.G-12 VIII.G-12 3.4.1-10 B Components Components (Tubes) (External) Transfer/Fouling Transfer/Fouling (Turbine-Driven Pump Governor, Turbine Turbine Bearing)

BearinQ)

Heat Exchanger Heat Exchanger Heat Transfer Stainless Steel Stainless Lubricating lubricating Oil Reduction of Heat One-Time One-Time Inspection VIII.G-12 3.4.1-10 A A

Components (Tubes) (External) Transfer/Fouling Transfer/Fouling (Turbine-Driven (Turbine-Driven Pump Governor, Turbine Bearing)

Heat Exchanger Heat Heat Transfer Stainless Stainless Steel Treated Treated Water (Internal)

Water (Intemal) Reduction of Heat One-Time Inspection One-Time Inspection VIII.F-10 VII I. F-10 3.4.1-9 A A

Components (Tubes) Transfer/Fouling Transfer/Fouling (Turbine-Driven (Turbine-Driven Pump Governor, Turbine Bearing)

Heat Heat Exchanger Heat Transfer Stainless Stainless Steel Treated Treated Water (Internal) Reduction of Heat' Heat Water Chemistry Chemistry VIII.F-10 3.4.1-9 A Transfer/Fouling Components (Turbine-Driven (Turbine-Driven (Tubes) Transfer/Fouling

.,

Pump Governor, Turbine Bearing)

Heat Heat Exchanger Exchanger Pressure Boundary Carbon Carbon Steel Air-.Indoor Air -Indoor (Extemal)

(External) Loss loss of Material/General Material/General External Surfaces VIII.H-7 3.4.1-28 A Components Components (Shellside Corrosion Corrosion Monitoring Monitoring (Turbine-Driven '

(Turbine-Driven Components)

Pump Governor, Turbine Bearing)

Heat Exchanger Pressure Boundary Heat Exchanger Carbon Carbon Steel Air with Borated Water Lossloss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 3.4.1-38 A A

Components (Shellside Leakage (External) leakage Corrosion Corrosion (Turbine-Driven Components)

Pump Governor, Turbine Turbine Bearing)

Bearing}

Generating Station, Unit No.

Salem Nuclear Generating No.11 and Unit No.2 No. 2 Page 3.4-38 Page 3.4-38 License Renewal Renewal Application Application

  • License
  • *

Component Component Intended Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Table Notes Notes Type Function Function Requiring Programs Item Vol. 2 Item Management Management Exchanger Heat Exchanger Boundary Pressure Boundary Carbon Steel Lubricating Lubricating Oil (Internal) Loss of Material/General, Material/General, Lubricating Lubricating Oil Analysis VIII.G-6 VIILG~ 3.4.1-12 3.4.1-12 B B

Components Components (Shellside Pitting, Crevice, and (Turbine-Driven (Turbine-Driven Components) Microbiologically-Microbiologically-Pump Governor, Influenced Influenced Corrosion Turbine Bearing)

Heat Exchanger Heat Exchanger Pressure Boundary Pressure Boundary Carbon Steel Lubricating Lubricating Oil (Internal)

(Internal) Loss of Material/General, Material/General, One-Time Inspection VIII.G-6 VIILG~ 3.4.1-12 3.4.1-12 A A

Components Components (Shellside Pitting, Crevice, and (Turbine-Driven (Turbine-Driven Components)

Components) Microbiologically-Microbiologically-Pump Governor, Influenced Influenced Corrosion Turbine Bearing)

Heat Exchanger Heat Exchanger Pressure Boundary Boundary Stainless Stainless Steel Lubricating Lubricating Oil Loss of Material/Pitting, Material/Pitting, Lubricating Oil Analysis VIII.G-3 VIILG-3 3.4.1-19 3.4.1-19 B Components Components (Tubes)

(Tubes) (External) . Crevice, and (Turbine-Driven (Turbine-Driven Microbiologically-Microbiologically-Pump Governor, Influenced Influenced Corrosion Turbine Bearing)

Bearing)

Heat Heat Exchanger Pressure Boundary Pressure Boundary Stainless Stainless Steel Lubricating Lubricating Oil Loss of Material/Pitting, Material/Pitting, One-Time One-Time Inspection VIII.G-3 VIILG-3 3.4.1-19 3.4.1-19 A A

Components Components (Tubes) (External)

(External) Crevice, and (Turbine-Driven (Turbine-Driven Microbiologically-Microbiologically-Pump Governor, Influenced Corrosion Influenced Turbine Bearing)

Bearing)

Heat Exchanger Heat Exchanger Pressure Boundary Stainless Steel Treated Water (Internal)

Stainless (Internal) Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.F-27 VII LF-27 3.4.1-16 3.4.1-16 A A

Components Components (Tubes) and Crevice Corrosion (Turbine-Driven Pump Governor, Turbine Turbine Bearing)

Bearing)

Heat Exchanger Heat Exchanger Pressure Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Irreated (Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.F-27 VIILF-27 3.4.1-16 A A

Components Components (Tubes) and Crevice Crevice Corrosion Corrosion (Turbine-Driven Pump Governor, Turbine Bearing)

Turbine Bearing)

Piping Piping and and Fittings Leakage Leakage Boundary Carbon Carbon Steel Air - Indoor Indoor (External) Loss of Material/General Material/General External Surfaces External Surfaces VIII.H-7 VIILH-7 3.4.1-28 A A

Corrosion Monitoring Monitoring Piping Piping and Fittings Leakage Leakage Boundary Carbon Carbon Steel Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 VIILH-9 3.4.1-38 A A

Leakage Leakage (External) Corrosion Corrosion Generating Station, Unit No.

Salem Nuclear Generating No.11 and Unit No.

No.22 Page 3.4-39 License Renewal Renewal Application Application

Section 3 - Aging Management Management Review Review Results Table 3.4.2-1

,Table 3.4.2-1 Auxiliary Feedwater System Auxiliary Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Piping and Fittings Leakage Leakage Boundary Carbon Carbon Steel Steel Steam (Internal)

(Internal) Material/General, Loss of Material/General, One-Time One-Time Inspection VIII.A-16 VIII,A-16 3.4.1-2 3.4.1-2 A Pitting, and Crevice Crevice Corrosion Piping Piping and Fittings Leakage Leakage Boundary Carbon Carbon Steel Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, Water Chemistry VIII.A-16 VIII,A-16 3.4.1-2 3.4.1-2 A Pitting, and Crevice Crevice Corrosion Piping Piping and Fittings Leakage Leakage Boundary Carbon Carbon Steel Steel Treated Water (Internal) irreated (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.G-38 VIII,G-38 3.4.1-4 3.4.1-4 A Pitting, and Crevice Crevice Corrosion Piping and Fittings Leakage Boundary Leakage Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, Water Chemistry VIII.G-38 3.4.1-4 A A

Pitting, and Crevice Corrosion Piping and Fittings Pressure Boundary Carbon Carbon Steel Air - Indoor (External) Loss of Material/General Material/General External External Surfaces VIII.H-7 VIII,H-7 3.4.1-28 A A

Corrosion Monitoring Monitoring Piping Piping and Fittings Fittings Pressure Boundary Carbon Carbon Steel Steel Air - Outdoor (External) Loss of Material/General, Material/General, External Surfaces VII.H1-8 VII,H1-8 3.3.1-60 3,3.1-60 A Pitting, and Crevice Crevice Monitoring Monitoring Corrosion Corrosion Piping Piping and Fittings Pressure Boundary Fittings Pressure Boundary Carbon Carbon Steel Air with Borated Borated Water Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 VIII,H-9 3.4.1-38 A Leakage {External}

Leakage (External) Corrosion Corrosion Piping and Pressure Boundary and Fittings Pressure Carbon Carbon Steel Air/Gas - Wetted Wetted Loss of Material/General, Material/General, Inspection of Internal Inspection Internal VIII.G-34 VII I. G-34 3.4.1-30 A (Internal) Pitting, and Crevice Crevice Surfaces in in Miscellaneous Miscellaneous Corrosion Corrosion Piping and Ducting Ducting Components Components Piping and Fittings Piping Fittings Pressure Pressure Boundary Boundary Carbon Steel Carbon Steel Lubricating Oil (Internal) Loss of Material/General, Material/General, Lubricating Oil Analysis VIII.G-35 VIII,G-35 3.4.1-7 3.4.1-7 B Pitting, and Crevice Corrosion Corrosion Piping and Fittings Pressure Pressure Boundary Boundary Carbon Steel Lubricating Oil (Internal) Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.G-35 VIII,G-35 3.4.1-7 A A

Pitting, and Crevice Corrosion Corrosion Piping and and Fittings Pressure Boundary Carbon Steel Carbon Steel Soil (External) Loss of Material/General, Material/General, Buried Piping Inspection Inspection VIII.G-1 VIII,G-1 3.4.1-11 3.4.1-11 A A

Pitting, Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced Piping and Fittings Pressure Pressure Boundary Boundary Carbon Steel Steam (Internal) Cumulative Fatigue Fatigue TLAA VIII.B1-10 VIII,B1-10 3.4.1-1 3.4.1-1 A, 2 A,2 1___ _ 1Damage/Fatigue Damaae/Fatiaue I Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page 3.4-40 3.4-40 0

License Renewal Application

  • Application

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table Item Table I1*ltem Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Piping and Fittings Pressure Pressure Boundary Boundary Carbon Steel Carbon Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.A-16 VIILA-16 3.4.1-2 A A

Pitting, and Crevice Crevice Corrosion Corrosion Piping and Pressure Boundary Fittings Pressure andFittings Boundary Carbon Steel Carbon Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, Water Water Chemistry Chemistry VIII.A-16 VIILA-16 3.4.1-2 A Pitting, and and Crevice Crevice Corrosion Piping and Piping and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Steel Carbon Steel Steam (Internal)

(Internal) Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.B1-9 VIILB1-9 3.4.1-29 3.4.1-29 B Accelerated Corrosion Accelerated Corrosion Corrosion Corrosion Piping and Fittings Pressure Pressure Boundary Boundary Carbon Steel Carbon Treated Water Steel ITreated (Internal) Loss of Material/General, Water (Internal) Material/General, One-Time Inspection One-Time Inspection VIII.G-38 VIILG-38 3.4.1-4 A Pitting, and Crevice Crevice Corrosion Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Treated (Internal) Loss of Material/General, ITreated Water (Internal) Material/General, Chemistry Water Chemistry VIII.G-38 VIILG-38 3.4.1-4 A A

Pitting, and and Crevice Crevice Corrosion and Fittings Piping and Piping Fittings Pressure Boundary Boundary Stainless Steel Air - Indoor (External)

(External) None None None VIII.1-10 VIIU-10 3.4.1-41 3.4.1-41 A A

Piping and Piping and Fittings Fittings Pressure Boundary Boundary Stainless Stainless Steel Air with Borated Water Water None None None VII.J-16 VILJ-16 3.3.1-99 3.3.1-99 A A

._ __ Leakage (External)

Leakage (External)

Piping and Piping and Fittings Fittings Pressure Boundary Boundary Stainless Stainless Steel Steam (Internal)

(Internal) Cracking/Stress Corrosion Cracking/Stress Corrosion Water Chemistry VIII.A-10 VIILA-10 3.4.1-39 3.4.1-39 A A

Cracking Cracking Piping and Piping and Fittings Fittings Pressure Boundary Stainless Steel Steam (Internal)

Steam (Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.A-12 3.4.1-37 3.4.1-37 A A

_ and Crevice and Crevice Corrosion Corrosion Piping and Fittings Pressure Boundary Treated Water (Internal)

Stainless Steel Treated Stainless (Internal) Material/Pitting Loss of Material/Pitting One-Time One-Time Inspection VIII.G-32 VIILG-32 3.4.1-16 3.4.1-16 A A

and Crevice Crevice Corrosion Piping and Fittings Pressure Boundary Stainless Steel Treated Stainless (Internal)

Treated Water (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry VIII.G-32 VIII.G-32 3.4.1-16 3.4.1-16 A A

and Crevice Crevice Corrosion Pump Casing Pressure Pressure Boundary Stainless Steel Air - Indoor (External) None None None VIII.I-10 VIIU-10 3.4.1-41 A A

(AFST Circulator)

Pump Casing Pressure Boundary Boundary Stainless Steel Air with Borated Water Water None None None VII.J-16 VILJ-16 3.3.1-99 3.3.1-99 A A

(AFST Circulator) (External)

Leakage (External)

Pump Casing Pressure Boundary Pressure Boundary Stainless Stainless Steel Treated Water (Internal) Material/Pitting Loss of Material/Pitting One-Time One-Time Inspection VIII.G-32 VIILG-32 3.4.1-16 3.4.1-16 A A

(AFST Circulator)

Circulator) and Crevice Crevice Corrosion Pump Casing Pressure Boundary Stainless Steel Treated reated Water (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry VIII.G-32 VIILG-32 3.4.1-16 A A

(AFST Circulator) I I IT and Crevice Corrosion I III Salem Nuclear Generating Station, Station, Unit No.

No.11 and Unit Unit No.2 No. 2 Page 3.4-41 License Renewal Application License

Section 3 - Aging Management Management Review Results Table 3.4.2-1 Auxiliary Auxiliary Feedwater Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Table Notes Notes Type Type Function Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Pump Casing Pressure Pressure Boundary Carbon Steel Air-- Indoor Air Indoor (External)

(Extemal) Loss of Material/General Material/General External External Surfaces Surfaces VIII.H-7 VIII.H-? 3.4.1-28 3.4.1-28 A A

(Auxiliary (Auxiliary Corrosion Monitoring Monitoring Feedwater)

Pump Casing Pressure Boundary Pressure Boundary Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion VIII.H-9 3.4.1-38 3.4.1-38 A A

(Auxiliary (Auxiliary Leakage Leakage (External) Corrosion Feedwater)

Pump Casing Pressure Pressure Boundary Carbon Steel Treated Water (Intemal)

!Treated (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection Inspection . VIII.G-38 3.4.1-4 A A

(Auxiliary Pitting, and Crevice Crevice Feedwater) Corrosion Pump Casing Pressure Pressure Boundary Carbon Steel Treated Water (Intemal)

!Treated (Internal) Loss of Material/General, Material/General, Chemistry Water Chemistry VIII.G-38 3.4.1-4 A A

(Auxiliary (Auxiliary Pitting, and Crevice Feedwater) Corrosion Restricting Restricting Orifices Leakage Leakage Boundary Stainless Steel Air - Indoor Indoor (External)

(External) None None VIII.1-10 VIIU-10 3.4.1-41 3.4.1-41 A A

Restricting Restricting Orifices Leakage Boundary Leakage Boundary Stainless Steel Air with Borated Water None None VII.J-16 3.3.1-99 3.3.1-99 A A

LeakaQe (External)

Leakage (External)

Restricting Restricting Orifices Leakage Boundary Leakage Boundary Treated Water (Internal)

Stainless Steel Irreated (Internal) Cracking/Stress Cracking/Stress Corrosion One-Time One-Time Inspection Inspection VIII.G-33 VIII.G-33 3.4.1-14 3.4.1-14 A A

> 140 F Cracking Cracking Restricting Leakage Boundary Restricting Orifices Leakage Stainless Steel Irreated Treated Water (Internal) Cracking/Stress Cracking/Stress Corrosion .Water Chemistry VIII.G-33 VIII.G-33 3.4.1-14 3.4.1-14 A A

> 140 F Cracking Cracking Restricting Leakage Boundary Restricting Orifices Leakage Stainless Stainless Steel Treated Treated Water (Internal)

(Internal) Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.G-32 VIII.G-32 3.4.1-16 A A

> 140 F and Crevice Corrosion Crevice Corrosion Restricting Leakage Boundary Restricting Orifices Leakage Stainless Stainless Steel Treated Treated Water (Intemal)

(Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.G-32 VII I. G-32 3.4.1-16 A A

> 140 F and Crevice Crevice Corrosion Corrosion Restricting Restricting Orifices Pressure Pressure Boundary Stainless Steel - Indoor (External)

Air -Indoor (Extemal) None None None VIII.1-10 VIIU-10 3.4.1-41 3.4.1-41 A A

Restricting Restricting Orifices Pressure Pressure Boundary Boundary Stainless-Steel Stainless-Steel Air with Borated Water None None VII.J-16 3.3.1-99 3.3.1-99 A A

Leakage Leakage (External)

Restricting Restricting Orifices Pressure Pressure Boundary Stainless Steel iTreated Treated Water (Internal) Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.G-32 VIII.G-32 3.4.1-16 3.4.1-16 A A

and Crevice Crevice Corrosion Corrosion Restricting Restricting Orifices Pressure Pressure Boundary Stainless Steel Irreated Treated Water (Internal)

(Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.G-32 VII I. G-32 3.4.1-16 3.4.1-16 A A

and Crevice Corrosion Crevice Corrosion Restricting Restricting Orifices Throttle Stainless Steel Air - Indoor Indoor (External)

(Extemal) None None VIII.I-10 VIIU-10 3.4.1-41 3.4.1-41 A A

Restricting Orifices Throttle Stainless Steel Air with Borated Water None None VII.J-16 3.3.1-99 3.3.1-99 A A

I__ _ __ _ I__

__ Leakage (External) ,

Leakage (Extemal) I I I Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.

No.22 Page 3.4-42 9

License Renewal Renewal Application

  • *
  • License Application
  • *

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table Table 1 1 Item Item Notes Notes Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Restricting Restricting Orifices Throttle Treated Water (Internal)

Stainless Steel ITreated (Internal) Loss of Material/Pitting Material/Pitting One-Time Inspection Inspection VIII.G-32 3.4.1-16 A and Crevice Crevice Corrosion Restricting Restricting Orifices Throttle Stainless Steel Treated (Inte~mal)

Treated Water (Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.G-32 3.4.1-16 A and Crevice Crevice Corrosion Strainer Strainer Body Pressure Boundary Pressure Boundary Carbon Carbon Steel Air-- Indoor Air Indoor (External)

(External) Loss of Material/General Material/General External External Surfaces Surfaces VIII.H-7 3.4.1-28 A Corrosion Corrosion Monitoring Monitoring Strainer Strainer Body Pressure Pressure Boundary Carbon Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 3.4.1-38 A Leakage (External)

Leakage Corrosion Corrosion Strainer Strainer Body Body Pressure Pressure Boundary Carbon Steel Treated Water Treated (Internal) Loss of Material/General, Water (Internal) Material/General, One-Time Inspection One-Time Inspection VIII.G-38 VII I. G-38 3.4.1-4 A Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Strainer Body Body Pressure Pressure Boundary Carbon Steel Treated Water Treated Water (Internal) Loss of Material/General, Material/General, Water Water Chemistry VIII.G-38 VIII.G-38 3.4.1-4 A Pitting, and Crevice Crevice Corrosion Tanks (Auxiliary Pressure Pressure Boundary Stainless Steel Air - Outdoor Outdoor (External) Loss of Material/Pitting Aboveground Non-Steel Aboveground Non-Steel III.B2-7 III.B2-7 3.5.1-50 E, 1 Feedwater Feedwater Storage Storage and Crevice Corrosion Tanks Tanks Tank)

Tanks Tanks (Auxiliary Pressure Boundary Boundary Stainless Steel Soil (External)

(External) Loss of Material/Pitting, Material/Pitting, Aboveground Aboveground Non-Steel G, G,3 3 Feedwater Feedwater Storage Crevice, and Tanks Tanks Tank) Microbiologically-Microbiologically-Influenced Corrosion Tanks Tanks (Auxiliary Pressure Boundary Boundary Treated Water Stainless Steel ITreated Water (Internal) Loss of Material/Pitting Material/Pitting One-Time Inspection One-Time Inspection VIII.G-41 VIII.G-41 3.4.1-6 3.4.1-6 A A

Feedwater Feedwater Storage and Crevice Corrosion Tank)

Tanks Tanks (Auxiliary Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel ITreated (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.G-41 VIII.G-41 3.4.1-6 A A

Feedwater Storage Feedwater and Crevice Corrosion Corrosion Tank)

Thermowell Therrnowell Pressure Boundary Boundary Stainless Steel Air-- Indoor (External)

Air (External) None None VIII.I-10 VIIU-10 3.4.1-41 3.4.1-41 A A

Thermowell Therrnowell Pressure Boundary Pressure Boundary Stainless Steel Air with Borated Water None None VII.J-16 3.3.1-99 3.3.1-99 A A

Leakage Leakage (External)

(External)

Thermowell Therrnowell Pressure Boundary Boundary Treated Water Stainless Steel ITreated Water (Internal)

(Internal) Material/Pitting Loss of Material/Pitting One-Time Inspection One-Time Inspection VIII.G-32 3.4.1-16 3.4.1-16 A A

I__ I and Crevice Crevice Corrosion Corrosion Thermowell Therrnowell Pressure Boundary Boundary reated Water (Internal)

Stainless Steel ITreated (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.G-32 VII I. G-32 3.4.1-16 A A

and Crevice Corrosion Corrosion Nuclear Generating Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-43 License Renewal Application

Section 3 - Aging Management Review Results Aging Management Results Table 3.4.2-1 Table 3.4.2-1 Feedwater System Auxiliary Feedwater Auxiliary System (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Table Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Turbine Casing Turbine Casing Pressure Boundary Pressure Boundary Carbon Carbon Steel Air - Indoor (External)

(External) Loss of Material/General Material/General External External Surfaces Surfaces VIII.H-7 VIII,H-7 3.4.1-28 3.4.1-28 A A

(Turbine-driven (Turbine-driven Corrosion Corrosion Monitoring Monitoring Auxiliary Auxiliary Feedwater)

Feedwater)

Turbine Casing Turbine Casing Pressure Boundary Pressure Boundary Carbon Carbon Steel Borated Water Loss of Material/Boric Air with Borated Material/Boric Acid Boric Acid Corrosion Corrosion VIII.H-9 VIII,H-9 3.4.1-38 3.4.1-38 A A

(Turbine-driven (Turbine-driven Leakage Leakage (External)

(External) Corrosion Corrosion Auxiliary Feedwater)

Feedwater)

Casing Turbine Casing Pressure Boundary Pressure Boundary Carbon Carbon Steel Air/Gas Air/Gas - Wetted Wetted Loss of Material/General, Material/General, Inspection Inspection of Internal Internal VIII.G-34 VIILG-34 3.4.1-30 3.4.1-30 A A

(Turbine-driven (Turbine-driven (Internal)

(Internal) Pitting, and Crevice Crevice Surfaces Surfaces in Miscellaneous Miscellaneous Auxiliary Auxiliary Corrosion Corrosion Piping and Dueting Ducting Feedwater) Components Components Turbine Casing Casing Pressure Boundary Pressure Boundary Carbon Steel Carbon (Internal)

Steam (Internal) Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.A-16 VIILA-16 3.4.1-2 A A

(Turbine-driven (Turbine-driven Pitting, and Crevice Crevice Auxiliary Auxiliary Corrosion Feedwater)

Turbine Casing Casing Pressure Pressure Boundary Boundary Carbon Carbon Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, Water Chemistry Chemistry VIII.A-16 3.4.1-2 A A

(Turbine-driven (Turbine-driven Pitting, and and Crevice Crevice Auxiliary Auxiliary Corrosion Feedwater)

Valve Valve Body Body Leakage Boundary Leakage Boundary Carbon Steel Carbon Indoor (External)

Air - Indoor (External) Loss Loss of Material/General Material/General External Surfaces External VIII.H-7 VIILH-7 3.4.1-28 3.4.1-28 A A

Corrosion Monitoring Monitoring Valve Body Valve Body Leakage Boundary Leakage Boundary Carbon Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion VIII.H-9 VIILH-9 3.4.1-38 A A

LeakaQe Leakage (External) Corrosion Valve Valve Body Body Leakage Boundary Leakage Boundary Carbon Steel Carbon r-reated (Internal) Loss of Material/General, Treated Water (Internal) Material/General, One-Time Inspection One-Time Inspection VIII.G-38 VIILG-38 3.4.1-4 A A

Pitting, and Crevice Corrosion Valve Valve Body Leakage Boundary Leakage Boundary Carbon Steel r-reated Carbon (Internal) Loss of Material/General, Treated Water (Internal) Material/General, Water Chemistry Chemistry VIII.G-38 VIII.G-38 -3.4.1-4

-3.4.1-4 A A

Pitting, and Pitting, Crevice and Crevice Corrosion Corrosion Valve Valve Body Pressure Pressure Boundary Carbon Steel Carbon Air-- Indoor Air Indoor (External)

(External) Loss of Material/General Material/General External Surfaces .

External Surfaces VIII.H-7 3.4.1-28 A A

I Corrosion Monitoring Monitoring Valve Body Pressure Boundary Carbon Steel Air - Outdoor (External) Loss of Material/General, External External Surfaces VII.H1-8 VILH1-8 3.3.1-60 A A

Pitting, and Pitting, Crevice and Crevice Monitoring Monitoring Corrosion Salem Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.4-44

  • *
  • Section 33 -- Aging Section

Component Component Intended Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Requiring Programs Programs Vol. 2 Item Item Management Management Valve Body Pressure Boundary Carbon Steel Borated Water Air with Borated Material/Boric Acid Water Loss of Material/Boric Boric Acid Corrosion Corrosion VIII.H-9 3.4.1-38 A A

Leakage (External)

Leakage (External) Corrosion Corrosion Valve Body Pressure Boundary Pressure Boundary Carbon Carbon Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.A-16 3.4.1-2 A A

Pitting, and Crevice Crevice Corrosion Valve Body Pressure Boundary Boundary Carbon Carbon Steel Steam (Internal)

(Internal) Loss of Material/General, Material/General, Water Chemistry Chemistry VIII.A-16 3.4.1-2 A A

Pitting, and Crevice Crevice Corrosion Valve Body Pressure Boundary Pressure Boundary Carbon Carbon Steel Steam (Internal)

(Internal) Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.B1-9 3.4.1-29 3.4.1-29 B B

Accelerated Accelerated Corrosion Corrosion Valve Body Boundary Pressure Boundary Carbon Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, One-Time Inspection VIII.G-38 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Corrosion Valve Body Boundary Pressure Boundary Carbon Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, Water Chemistry Chemistry VIII.G-38 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Corrosion Valve Body Pressure Boundary Boundary Gray Cast Iron Air- Indoor (External)

Air -Indoor Loss of Material/General Material/General External Surfaces VIII.H-7 VII I. H-7 3.4.1-28 A A

Corrosion Corrosion Monitoring Monitoring Valve Body Pressure Boundary Boundary Gray Cast Iron Air with Borated Water Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion VIII.H-9 3.4.1-38 A A

Leakage (External)

Leakage (External) Corrosion

'Corrosion Valve Body Pressure Boundary Boundary Gray Cast Iron Air/Gas - Wetted Wetted Loss of Material/General, Material/General, Inspection of Internal Inspection VIII.G-34 3.4.1-30 A A

(Internal) Pitting, and Crevice Crevice Surfaces in Miscellaneous Miscellaneous Corrosion Ducting Piping and Ducting Components Components Valve Body Pressure Boundary Pressure Boundary Stainless Stainless Steel Air- (Extemal)

Air - Indoor (External) None None None VIII.I-10 3.4.1-41 3.4.1-41 A A

Valve Body Boundary Pressure Boundary Stainless Stainless Steel Air with Borated Water None None None VII.J-16 3.3.1-99 A A

(External)

Leakage (External)

Valve Body Pressure Boundary Stainless Steel Treated Stainless Treated Water (Internal) Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection VIII.G-32 VII I. G-32 3.4.1-16 3.4.1-16 A A

and Crevice Corrosion III Valve Body Boundary Pressure Boundary Stainless Steel Treated Stainless reated Water (Internal)

(Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.G-32 VIII.G-32 3.4.1-16 3.4.1-16 A A

IT__ _ _ I___

and Crevice Corrosion _ _I_ I Nuclear Generating Salem Nuclear Generating Station, No. 1 and Unit No.2 Station, Unit No.1 No. 2 Page 3.4-45 License License Renewal Application

Section Section 33 - Aging Aging Management Management Review Review Results Results Notes Notes Definition of Definition of Note Note A

A Consistent NUREG-1801 item Consistent with NUREG-1801 for component, material, environment, and item for NUREG-1801 AMP.

and aging effect. AMP is consistent with NUREG-1801 AMP.

B Consistent with NUREG-1 Consistent NUREG-1801 item for component, material, environment, and 801 item and aging takes some aging effect. AMP takes exceptions to NUREG-some exceptions NUREG-1801 1801 AMP.AMP.

C Component is Component is different, NUREG-1801 item consistent with NUREG-1801 different, but consistent environment, and aging effect; material, environment, item for material, AMP is effect AMP consistent with is consistent NUREG-1801 NUREG-1801 AMP.

D Component is Component NUREG-1801 item consistent with NUREG-1801 is different, but consistent material, environment, and aging effect. AMP item for material, AMP takes some exceptions exceptions NUREG-1801 AMP.

to NUREG-1801 AMP.

E Consistent with NUREG-1801 item for material, with NUREG-1801 environment, and aging material, environment, management program different aging management aging effect, but a different credited or program is credited NUREG-1 801 identifies NUREG-1801 plant-specific aging identifies a plant-specific management program.

aging management F Material not in Material NUREG-1 801 for this component.

in NUREG-1801 G Environment not in NUREG-1 Environment NUREG-1801 801 for this component and material.

material.

H H Aging effect Aging NUREG-1 801 for this component, material, effect not in NUREG-1801 environment combination.

material, and environment combination.

I Aging Aging effect effect in in NUREG-1 NUREG-1801 material, and environment 801 for this component, material, combination is not applicable.

environment combination applicable.

J component nor Neither the component Neither nor the material and environment combination material and evaluated in NUREG-1 combination is evaluated NUREG-1801.801.

Specific Notes:

Plant Specific

1. The Aboveground Non-Steel Tanks program Aboveground Non-Steel component type, material, and applicable to this component program is substituted to manage the aging effect(s) applicable environment combination.

environment combination.

2. The TLAA designation designation in Management Program column indicates in the Aging Management component is evaluated indicates fatigue of this component evaluated in Section 4.3.

Aboveground Non-Steel Tanks program

3. The Aboveground program is usedused to manage applicable to this component manage the aging effect(s) applicable environment component type, material, and environment combi nation.

combination.

Salem Nuclear Generating Station, Unit No.1 Station. Unit and Unit No.2 No. 1 and No. 2 Page 3.4-46 Page 3.4-46

  • *
  • Section 3 - Aging
  • Aging Management Management Review Review Results Results Table 3.4.2-2 Main Condensate Condensate and Feedwater System Summary of Aging Management Summary Management Evaluation Evaluation Table 3.4.2-2 Main Condensate and Feedwater Main Condensate Feedwater System Component Component Intended Intended Material Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Bolting Mechanical Closure Mechanical Closure Carbon and Low Air - Indoor Indoor (External) Loss of Material/General, Material/General, Bolting Integrity VIII.H-4 VIII,H-4 3.4.1-22 B Alloy Steel Pitting, and Crevice Crevice Bolting Corrosion Bolting Mechanical Closure Mechanical Closure Carbon and Low Air - Indoor Indoor (External) Loss of PreloadfThermal Preload/Thermal Bolting Integrity VIII.H-5 VIII,H-5 3.4.1-22 B Alloy Steel Effects, Gasket Creep, Bolting Self-Loosening and Self-Loosening Bolting Mechanical Closure Mechanical Closure Carbon and Low Low Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-2 VIII,H-2 3.4.1-38 A A

Alloy Steel Leakage (External)

Leakage (External) Corrosion Bolting Bolting Bolting Mechanical Closure Mechanical Closure Stainless Steel Air-Air - Indoor Indoor (External)

(External) Loss of PreloadfThermal Preload/Thermal Bolting Integrity IV.C2-8 3.1.1-52 B Bolting Effects, Gasket Creep, and Self-Loosening Self-Loosening

-

Bolting Mechanical Closure Mechanical Stainless Steel Airwith Air with Borated Water None None VII.J-16 VII,J-16 3.3.1-99 C Bolting Leakage Leakage (External)

Flow Device Pressure Pressure Boundary Boundary Stainless Steel Air - Indoor Indoor (External)

(External) None None VIII.1-10 VIIU-10 3.4.1-41 A A

Flow Flow Device Device Pressure Pressure Boundary Boundary Stainless Steel ITreated Treated Water Water (Internal) Loss of Material/Pitting Material/Pitting One-Time Inspection VIII.D1-4 VIII,D1-4 3.4.1-16 A and Crevice Corrosion Flow Device Device Pressure Boundary Pressure Boundary Treated Water (Internal)

Stainless Steel irreated Loss of Material/Pitting Material/Pitting Water Chemistry Chemistry VIII.DI-4 VIII.D1-4 3.4.1-16 A A

and Crevice and Crevice Corrosion Corrosion Flow Element Pressure Pressure Boundary Boundary Stainless Steel Air-- Indoor (External)

Air None None VIII.1-10 VIIU-10 3.4.1-41 A A

Element Flow Element Pressure Pressure Boundary Boundary Treated Water Stainless Steel ITreated Water (Internal) Loss of Material/Pitting of Material/Pitting One-Time Inspection One-Time VIII.D1-4 VIII,D1-4 3.4.1-16 A and Crevice Corrosion Flow Element Pressure Pressure Boundary Boundary Treated Water (Intemal)

Stainless Steel !Treated (Internal) Material/Pitting Loss of Material/Pitting Water Water Chemistry Chemistry VIII.D1-4 VIII,D1-4 3.4.1-16 A and Crevice Corrosion and Crevice Corrosion Exchanger Heat Exchanger Pressure Boundary Pressure Boundary Carbon Steel Air-- Indoor Air Indoor (External)

(External) Loss of Material/General Material/General External External Surfaces VIII.H-7 VIII,H-7 3.4.1-28 A Components Components (Shellside Corrosion Corrosion Monitoring Monitoring (Feedwater (Feedwater Components)

Components)

Heaters)

Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-47 3.4-47 License Renewal Renewal Application .

Section 3 - Aging Management Review Review Results Results Table 3.4.2-2 Main Condensate and Feedwater Main Condensate Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Fun~tion Requiring Requiring Programs Vol. 2 Item Item Management Management Heat Exchanger Exchanger Pressure Boundary Boundary Carbon Steel Treated Water (Internal)

Treated (Internal) Loss of Material/General, One-Time Inspection One-Time Inspection VIII.E-37 VIILE-37 3.4.1-3

-*3.4.1-3 A Components Components (Shellside Pitting, and Crevice Crevice (Feedwater (Feedwater Components) Corrosion Heaters)

Heaters)

Exchanger Heat Exchanger Pressure Boundary Carbon Steel Treated Water (Internal)

Treated (Internal) Loss of Material/General, Material/General, Water Chemistry Chemistry VIII.E-37 VIILE-37 3.4.1-3 A Components Components (Shellside Pitting, and Crevice Crevice (Feedwater (Feedwater Components)

Components) Corrosion Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Carbon Steel Carbon Treated Water Loss of Material/General, One-Time One-Time Inspection VIII.E-7 VIILE-7 3.4.1-5 A A

Components Components (Tube Sheet) (External) Pitting, Crevice, and (Feedwater (Feedwater Galvanic Corrosion Galvanic Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Carbon Steel Treated Treated Water Loss of Material/General, Chemistry Water Chemistry VIII.E-7 VIILE-7 3.4.1-5 A A

Components Components (Tube Sheet) (External) Pitting, Crevice, and (Feedwater (Feedwater Galvanic Corrosion Galvanic Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Carbon Steel Treated Water Wall Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.D1-9 VIILD1-9 3.4.1-29 D Components Components (Tube Sheet) (External) Accelerated Corrosion Accelerated Corrosion (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.E-7 VIILE-7 3.4.1-5 A Components Components (Tube Sheet) Pitting, Crevice, and (Feedwater (Feedwater Galvanic Galvanic Corrosion Heaters)

Heat Exchanger Heat Exchanger Pressure Boundary Pressure Boundary Carbon Steel Carbon Steel Treated Water Treated Water (Internal)

(Internal) Loss of Material/General, Material/General, Water Chemistry VIII.E-7 VIILE-7 3.4.1-5 3.4.1-5 A A

Components Components (Tube Sheet) Pitting, Crevice, and (Feedwater (Feedwater Corrosion Galvanic Corrosion Heaters)

Heat Exchanger Heat Exchanger Pressure Boundary Pressure Boundary Carbon Carbon Steel Treated Water Treated Water (Internal)

(Internal) Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.D1-9 VIILD1-9 3.4.1-29 D Components Components (Tube Sheet) Accelerated Corrosion Accelerated Corrosion (Feedwater (Feedwater Heaters)

Exchanger Heat Exchanger Pressure Boundary Carbon Steel Air - Indoor Indoor (External) Loss of Material/General Material/General External Surfaces VIII.H-7 VIILH-7 3.4.1-28 A Components Components (Tubeside Corrosion Monitoring Monitoring (Feedwater (Feedwater . Components)

Components)

Heaters)

Nuclear Generating Salem Nudear Generating Station, Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-48 3.4-48 0

License Renewal Application

  • * *0
  • 0
  • Section 3 - Aging Management Management Review Review Results Results Table 3.4.2-2 3.4.2-2 Main Condensate and Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Requiring Requiring Programs Vol.

Vol. 2 Item Item Management Management Exchanger Heat Exchanger Pressure Boundary Pressure Boundary Carbon Carbon Steel Treated Water (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.E-7 VIII.E-7 3.4.1-5 A A

Components (Tubeside , Pitting, Crevice, and (Feedwater (Feedwater Components) Galvanic Corrosion Galvanic Heaters)

Heat Heat Exchanger Pressure Boundary Carbon Steel Steel Treated Water ("Internal)

Treated (Internal) Loss of Material/General, Material/General, Water Chemistry VIII.E-7 3.4.1-5 3.4.1-5 A A

Components Components (Tubeside Pitting, Pitting, Crevice, and (Feedwater (Feedwater Components)

Components) Galvanic Corrosion Galvanic Heaters)

Heat Heat Exchanger Exchanger Pressure Pressure Boundary Carbon Carbon Steel Steel Treated Water (Internal)

(Internal) Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.D1-9 VIII.D1-9 3.4.1-29 D Components Components (Tubeside Accelerated Corrosion Corrosion Corrosion (Feedwater (Feedwater Components)

Components)

Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel Treated Treated Water Water Cracking/Stress Cracking/Stress Corrosion One-Time Inspection One-Time Inspection VIII.F-3 VII I. F-3 3.4.1-14 A Components Components (Tubes) (External) > 140 140 F Cracking Cracking (Feedwater (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel Treated Treated Water Water Cracking/Stress Cracking/Stress Corrosion Water Water Chemistry Chemistry VIII.F-3 VII I. F-3 3.4.1-14 A Components Components (Tubes) (External) > 140 F Cracking Cracking (Feedwater (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel Treated Treated Water Water Material/Pitting Loss of Material/Pitting Inspection One-Time Inspection VIII.E-4 VII I. E-4 3.4.1-16 A Components Components (Tubes) (External)

(External) > 140 F Corrosion and Crevice Corrosion (Feedwater (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel Treated Treated Water Water Material/Pitting Loss of Material/Pitting Water Water Chemistry Chemistry VIII.E-4 3.4.1-16 A Components Components (Tubes) (External) > 140 F and Crevice Corrosion (Feedwater (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Treated Water (Internal) Cracking/Stress Stainless Steel ITreated Cracking/Stress Corrosion One-Time Inspection One-Time Inspection VIII.F-3 3.4.1-14 A Components Components (Tubes) > 140 F Cracking Cracking (Feedwater Heaters)

Heaters)

Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel ITreated Treated Water (Internal) Cracking/Stress Cracking/Stress Corrosion Corrosion Water Water Chemistry Chemistry VIII.F-3 VII I. F-3 3.4.1-14 A Components Components (Tubes) > 140 F Cracking Cracking (Feedwater (Feedwater Heaters)

Heaters)

Salem Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.4-49 Page 3.449 Renewal Application License Renewal Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table Table 3.4.2-2 3.4.2-2 Main Main Condensate Condensate and and Feedwater Feedwater System System (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table Table I1 Item Item Notes Notes Type Type Function Function Requiring Requiring . Programs Programs Vol.

Vol. 22 Item Item Management Management Heat Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Steel Treated Water (Internal)

Stainless Steel Treated Water (Internal) Loss of Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.E-4 VIII.E-4 3.4.1-16 3.4.1-16 AA Components Components (Tubes)

(Tubes) >

> 140 140 FF and and Crevice Crevice Corrosion Corrosion (Feedwater (Feedwater Heaters)

Heaters)

Heat Heat Exchanger Exchanger Pressure Pressure Boundary Boundary Stainless Stainless Steel Steel Treated Treated WaterWater (Internal)

(Internal) Loss Loss ofof Material/Pitting Material/Pitting Water Water Chemistry Chemistry VIII.E-4 VIII,E-4 3.4.1-16 3.4.1-16 AA Components Components (Tubes)

(Tubes) >> 140 140 FF and and Crevice Crevice Corrosion Corrosion (Feedwater (Feedwater Heaters)

Heaters)

Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Air Air -- Indoor Indoor (External)

(External) Loss Loss ofof Material/General Material/General External External Surfaces Surfaces VIII.H-7 VIII,H-7 3.4.1-28 3.4.1-28 AA Corrosion Corrosion Monitoring Monitoring Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Air Air with with Borated Borated Water Water Loss Loss of of Material/Boric Material/Boric Acid Acid Boric Boric Acid Acid Corrosion Corrosion VIII.H-9 VIII,H-9 3.4.1-38 3.4.1-38 AA Leakage Leakage (External)

(External) Corrosion Corrosion Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Treated Treated WaterWater (Internal)

(Internal) Cumulative Cumulative Fatigue Fatigue TLAA TLAA VIII.D1-7 VIII.D1-7 3.4.1-1 3.4.1-1 A, A,11 Damage/Fatigue Damage/F atig ue Piping and Fittings Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, One-Time Inspection VIII.D1-8 3.4.1-4 A Piping and Fittings Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, One-Time Inspection VIII,D1-8 3.4.1-4 A Pitting, and Crevice Pitting, and Crevice Corrosion Corrosion Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Treated Irreated Water Water (Internal)

(Internal) Loss Loss of of Material/General, Material/General, Water Water Chemistry Chemistry VIII.D1-8 VIII,D1-8 -3.4.1-4

. 3.4.1-4 AA Pitting, Pitting, and and Crevice Crevice Corrosion Corrosion Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steel Treated Treated WaterWater (Internal)

(Internal) Wall Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.D1-9 VIII,D1-9 3.4.1-29 3.4.1-29 B Accelerated Accelerated Corrosion Corrosion Corrosion Corrosion

.Piping Piping and and Fittings FittinQS Pressure Pressure Boundary Boundary Stainless Stainless Steel Steel Air-Air - Indoor Indoor (External)

(External) None None None None VIII.I-10 VIILI-10 3.4.1-41 3.4.1-41 AA Piping and Fittings Pressure Boundary Stainless Steel Treated Water (Internal) Cracking/Stress Piping and Fittings Pressure Boundary Stainless Steel Treated Water (Internal) Cracking/Stress Corrosion Corrosion One-Time One-Time Inspection Inspection VIII.D1-5 VIII.D1-5 3.4.1-14 3.4.1-14 AA

>> 140 140 FF Cracking Cracking Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Stainless Stainless Steel Steel Treated Treated WaterWater (Internal)

(Internal) Cracking/Stress Cracking/Stress Corrosion Corrosion Water Water Chemistry Chemistry VIII.D1-5 VIII,D1-5 3.4.1-14 3.4.1-14 AA

>> 140 140 FF Cracking Cracking Piping Piping and and Fittings "Fittings Pressure Pressure Boundary Boundary Stainless Stainless Steel Steel Treated Treated WaterWater (Internal)

(Internal) Cumulative Cumulative Fatigue Fatigue TLAA TLAA IV.C2-10 IV.C2-10 3.1.1-7 3.1.1-7 A, A,11

>> 140 140 FF Damage/Fatigue DamaQe/F atig ue Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Stainless Stainless Steel Steel Treated Treated WaterWater (Internal)

(Internal) Loss Loss ofof Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.D1-4 VIII,D1-4 3.4.1-16 3.4.1-16 AA

>> 140 140 FF and and Crevice Crevice Corrosion Corrosion Piping Piping and and Fittings Fittings Pressure Pressure Boundary Boundary Stainless Stainless Steel reated Water Steel Treated Water (Internal)

(Internal) Loss Loss ofof Material/Pitting Material/Pitting Water Water Chemistry Chemistry . VIII.D1-4 VIII,D14 3.4.1-16 3.4.1-16 AA

>> 140 140 FF and and Crevice Crevice Corrosion Corrosion I I I I Salem Salem Nuclear Nuclear Generating Generating Station, Station, Unit Unit No.

No.11 and and Unit Unit No.

No.22 Page Page 3.4-50 3.4-50 License License Renewal Renewal Application

  • *
  • Application
  • *

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table 1I Item Table Notes Notes Type Type Function Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Pump Casing Pump Casing Pressure Boundary Pressure Boundary Carbon Steel Carbon Steel Air -- Indoor Air Indoor (External)

(External) Loss of Material/General Material/General External Surfaces VIII.H-7 VIILH-? 3.4.1-28 A A

(Condensate) Corrosion Monitoring Monitoring Pump Casing Pump Casing Pressure Boundary Pressure Boundary Carbon Steel Carbon Steel Treated Water (Intemal)

Treated (Internal) Loss of Material/General, Material/General, One-Time Inspection VIII.D1-8 VIILD1-8 3.4.1-4 A (Condensate) Pitting, and Crevice Corrosion Pump Casing Pump Casing Pressure Boundary Pressure Boundary Carbon Steel Treated Water (Intemal) iTreated (Internal) Loss of Material/General, Material/General, Water Chemistry VIII.D1-8 VIILD1-8 3.4.1-4 A A

(Condensate) Pitting, and Crevice Corrosion Pump Casing Pump Casing (SG (SG Pressure Pressure Boundary Cast Austenitic Air-- Indoor Air (External)

Indoor (External) None None None VIII.1-10 VIILI-10 3.4.1-41 A A

Feedwater)

Feedwater) Stainless Steel Stainless Steel (CASS)

Pump Pump Casing Casing (SG Pressure Boundary Pressure Boundary Cast Austenitic iTreated Treated Water (Intemal)

(Internal) Cracking/Stress Cracking/Stress Corrosion One-Time One-Time Inspection VIII.D1-5 VIILD1-5 3.4.1-14 3.4.1-14 A Feedwater) Stainless Steel > 140 F Cracking Cracking (CASS)

Pump Pump Casing Casing (SG (SG Pressure Boundary Pressure Boundary Cast Austenitic iTreated Treated Water (Internal) Cracking/Stress Corrosion Corrosion Water Chemistry VIII.D1-5 VIILD1-5 3.4.1-14 A A

Feedwater)

Feedwater) Stainless Steel > 140 F Cracking Cracking (CASS)

Pump Casing Pump Casing (SG (SG Pressure Boundary Pressure Boundary Cast Austenitic Cast Treated Water Austenitic Irreated (Internal)

Water (Internal) Loss of Material/Pitting One-Time Inspection One-Time Inspection VIII.D1-4 VIILD1-4 3.4.1-16 A Feedwater)

Feedwater) Stainless Steel Stainless Steel > 140 F

> and Crevice Corrosion (CASS)

Pump Pump Casing Casing (SG (SG Pressure Pressure Boundary Boundary Cast Austenitic Cast Treated Water Austenitic iTreated (Internal)

Water (Internal) Loss of Material/Pitting Material/Pitting Water Water Chemistry VIII.D1-4 VIILD1-4 3.4.1-16 3.4.1-16 A Feedwater) Stainless Steel Steel > 140 F Crevice Corrosion and Crevice (CASS)

(CASS)

Restricting Orifices Restricting Pressure Boundary Orifices Pressure Boundary Stainless Steel Air --Indoor Indoor (External)

(External) None None None VIIIl-l10 VIILI-10 3.4.1-41 3.4.1-41 A Restricting Orifices Restricting Pressure Boundary Orifices Pressure Boundary Stainless Steel Stainless Steel Treated iTreated Water (Internal)

Water (Internal) Loss of Material/Pitting Material/Pitting One-Time Inspection One-Time Inspection VIII.D1-4 VIILD1-4 3.4.1-16 A and and Crevice Crevice Corrosion Restricting Orifices Restricting Pressure Boundary Orifices Pressure Boundary Stainless Steel Stainless Steel Treated iTreated Water (Internal)

Water (Internal) Loss of Material/Pitting Material/Pitting Water Water Chemistry Chernistry VIII.D1-4 VIILD1-4 3.4.1-16 A and and Crevice Corrosion Spectacle Spectacle Blinds Blinds Pressure Boundary Pressure Boundary Carbon Steel Carbon Air - Indoor Indoor (External) Loss Loss of Material/General Material/General External Surfaces Surfaces VIII.H-7 VIILH-? 3.4.1-28 A I Corrosion Monitoring Monitoring Spectacle Spectacle Blinds Blinds Pressure Boundary Boundary Carbon Steel Steel Treated iTreated Water Water (Internal)

(Internal) Loss Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.D1-8 VIILD1-8 3.4.1-4 3.4.1-4 A Pitting, Pitting, and and Crevice Crevice Corrosion Corrosion Salem Nuclear Nuclear Generating Generating Station, Station, Unit Unit No.

No.11 and Unit No.

No.22 Page 3.4-51 Page License License Renewal Renewal Application Application

Section 3 - Aging Management Review Results Aging Management Results Table 3.4.2-2 Main Condensate Condensate and Feedwater System (Continued)

Component Component Intended Intended Material Material Environment Aging Effect Effect Aging -Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Function Requiring Programs Programs Vol. 2 Item Item Management Management Spectacle Spectacle Blinds Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, r-reated Material/General, Water Chemistry VIII.D1-8 VIILD1-8 3.4.1-4 3.4.1-4 A A

Pitting, and Pitting, and Crevice Crevice Corrosion Strainer Body Strainer Pressure Boundary Carbon Steel Air-- Indoor Air Indoor (External) Material/General Loss of Material/General External Surfaces External Surfaces VIII.H-7 VIII.H-7 3.4.1-28 A Corrosion MonitorinQ Monitoring Strainer Body Pressure Pressure Boundary Carbon Carbon Steel Treated Water (Internal) r-reated (Internal) Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.D1-8 VIILD1-8 3.4.1-4 A Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Strainer Body Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, r-reated Material/General, Water Chemistry VIII.D1-8 VIILD1-8 3.4.1-4 3.4.1-4 A A

Pitting, and Crevice Pitting, and Crevice Corrosion Corrosion Thermowell Therrnowell Pressure Boundary Carbon Steel Air - Indoor Indoor (External) Loss of Material/General Material/General External Surfaces Surfaces VIII.H-7 VIILH-7 3.4.1-28 A Corrosion Monitoring MonitorinQ Thermowell Therrnowell Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, r-reated Material/General, One-Time Inspection Inspection VIII.D1-8 VIILD1-8 3.4.1-4 3.4.1-4 A A

Pitting, and and Crevice Crevice Corrosion Thermowell Therrnowell Pressure Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, Water Water Chemistry VIII.D1-8 VIILD1-8 3.4.1-4 A A

Pitting, Pitting, and and Crevice Crevice Corrosion Corrosion Valve Body Valve Body Pressure Boundary Pressure Boundary Carbon Steel Carbon Steel Air- Indoor (External)

Air - Indoor (External) Loss of Loss of Material/General Material/General External Surfaces External Surfaces VIII.H-7 VIILH-7 3.4.1-28 3.4.1-28 A A

Corrosion Corrosion Monitoring Monitoring Valve Body Pressure Boundary Boundary Carbon Steel Air with Borated Material/Boric Acid Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion VIII.H-9 VIILH-9 3.4.1-38 A A

Leakage (External)

(External) Corrosion Corrosion Valve Body Valve Body Pressure Boundary Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, One-Time Inspection Inspection VIII.D1-8 VIILD1-8 3.4.1-4 A A

Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Valve Body Pressure Boundary Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Treated Material/General, Water Water Chemistry VIII.D1-8 VIILD1-8 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Valve Body Pressure Boundary Bbundary Carbon Steel Treated Water (Internal)

Treated Wall Thinning/Flow Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.D1-9 VIILD1-9 3.4.1-29 3.4.1-29 B Accelerated Corrosion Accelerated Corrosion Corrosion Corrosion Valve Body Pressure Boundary Boundary Stainless Steel Air- Indoor(External)

Air -Indoor (External) None None VIII.-l10 VII 1.1-1 0 3.4.1-41 3.4.1-41 A A

Valve Body Pressure Boundary Boundary Stainless Steel Treated Water.(Intemal)

Water (Internal) Loss of Material/Pitting Material/Pitting One-Time Inspection Inspection VIII.D1-4 VIII.D1-4 3.4.1-16 3.4.1-16 A A

and Crevice and Crevice Corrosion Corrosion Nuclear Generating Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-52 3.4-52 0

License Renewal Application

  • license
  • Section 33 -- Aging Section

Component Component Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Valve Valve Body Pressure Boundary Boundary Stainless Steel Treated Treated Water Water (Internal) Loss of Material/Pitting Water Water Chemistry VIII.D1-4 3.4.1-16 A and Crevice Corrosion Notes Definition of Note Definition Note A Consistent Consistent with NUREG-1801 NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 NUREG-1801 AMP.

B Consistent Consistent with NUREG-1801 NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG- NUREG-1801 AMP.

1801 C Component Component is different, but consistent with NUREG-1801 NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

NUREG-1801 D Component Component is different, but consistent with NUREG-1801 NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions exceptions to NUREG-1801 NUREG-1801 AMP.

E Consistent NUREG-1801 item for material, environment, and aging effect, but a different aging management Consistent with NUREG-1801 management program is credited or NUREG-1801 identifies a plant-specific NUREG-1801 plant-specific aging management management program.

F NUREG-1 801 for this component.

Material not in NUREG-1801 G Environment not in NUREG-1801 NUREG-1801 for this component and material. material.

H Aging effect not in in NUREG-1801 NUREG-1 801 for this component, material, and environment environment combination.

combination.

I Aging effect in NUREG-1 NUREG-1801 801 for this component, material, and environment environment combination is not applicable.

J Neither the component nor the material environment combination material and environment combination is evaluated NUREG-1801.

evaluated in NUREG-1801.

Plant Specific Notes:

1. The TLAA TLAA designation designation in the Aging Management Management Program column indicates indicates fatigue of this component is evaluated in Section 4.3.

evaluated in Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-53 3.4-53 License Renewal Renewal Application Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table 3.4.2-3 Table 3.4.2-3 Main Condenser and Main Condenser Removal System and Air Removal Summary of Summary Management Evaluation of Aging Management Evaluation Table 3.4.2-3 Main Condenser and Air Removal System Main Condenser Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Management Aging Management 'NUREG-1801

'NUREG-1801 Table I1 Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Vol. Item Management Management Heat Exchanger Pressure Boundary Exchanger Pressure Boundary Carbon Steel Air - Indoor Indoor (External)

(External) Loss of Material/General Material/General External External Surfaces Surfaces VIII.H-7 VIILH-7 3.4.1-28 3.4.1-28 A A

Components (Main Components (Shellside Corrosion Corrosion Monitoring Monitoring Condenser and Condenser components) components)

Hotwell)

Pressure Boundary Exchanger Pressure Heat Exchanger Boundary Carbon Carbon Steel ~reated Treated Water (Intemal) Loss of Material/General, Water (Internal) Material/General, One-Time Inspection Inspection VIII.E-37 VIILE-37 3.4.1-3 3.4.1-3 A A

Components (Main Components (Shellside (Shellside Pitting, and Crevice Pitting, Crevice Condenser Condenser and components) components) Corrosion Corrosion Hotwell)

Hotwell)

Pressure Boundary Exchanger Pressure Heat Exchanger Boundary Carbon Steel Carbon Treated Water rt"reated (Intemal) Loss of Material/General, Water (Internal) Material/General, Water Water Chemistry VIII.E-37 VIILE-37 3.4.1-3 3.4.1-3 A A

Components (Main Components (Shellside (Shellside Pitting, and Crevice Pitting, Crevice Condenser Condenser and components) components) Corrosion Corrosion Hotwell)

Heat Exchanger Pressure Boundary Exchanger Pressure Alloy with Raw Copper Alloy Boundary Copper RawWater (Extemal)

Water (Extemal) Material/Pitting, Open-Cycle Cooling Water Loss of Material/Pitting, VII.C1-9 VILC1-9 3.3.1-81 3.3.1-81 C Components (Main Components 15% Zinc or More 15% Zinc More Crevice, and System Condenser and (Tubesheet) Microbiologically-Microbiologically-Hotwell) Corrosion, and Influenced CorrOSion, Fouling Fouling Heat Exchanger Pressure Boundary Copper Alloy with Raw Exchanger Pressure RawWater Water (Extemal) Material/Selective (External) Loss of Material/Selective Selective Leaching of Selective Leaching VIII.E-20 VIILE-20 3.4.1-35 3.4.1-35 C Components (Main Components 15% Zinc or More 15% More Leaching Materials Materials Condenser Condenser and (Tubesheet)

Hotwell)

Hotwell)

Heat Exchanger Boundary Copper Alloy with Treated Pressure Boundary Exchanger Pressure (Internal)

Treated Water (Intemal) Material/Pitting Loss of Material/Pitting One-Time Inspection One-Time Inspection VIII.A-5 VIILA-5 3.4.1-15 C C

Components Components (Main 15% Zinc or More 15% and Crevice Corrosion Corrosion Condenser Condenser and (Tubesheet)

Hotwell)

Hotwell)

Exchanger Pressure Heat Exchanger Heat Boundary Copper Alloy with Treated Pressure Boundary (Internal)

Treated Water (Intemal) Loss of Material/Pitting Material/Pitting Chemistry Water Chemistry VIII.A-5 VIILA-5 3.4.1-15 CC Components (Main 15%

15% Zinc or More More Corrosion and Crevice Corrosion Condenser Condenser and (Tubesheet)

(Tubesheet)

Hotwell)

Hotwell)

Salem Nuclear Generating Station, Unit No.1 No. 1 and and Unit No.2 No. 2 II 3.4-54 Page 3.4-54

  • *
  • Section 3 - Aging

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG*1801 Table Table 1 I Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Heat Exchanger Pressure Heat Exchanger Pressure Boundary CopperCopper Alloy with ITreated Treated Water (Intemal)

(Internal) Loss of Material/Selective Material/Selective Selective Leaching Selective Leaching of VIII.E-21 3.4.1-35 3.4.1-35 C C

Components (Main 15%

15% Zinc or More Leaching Leaching Materials Materials Condenser Condenser and (Tubesheet)

Hotwell)

Heat Exchanger Pressure Heat Exchanger Pressure Boundary Boundary Stainless Stainless Steel Raw Water (Intemal)

(Internal) Loss of Material/Pitting, Open-Cycle Open-Cycle Cooling Wate Water VIII.E-3 3.4.1-33 A A

Components (Main Components (Main (Tubes)

(Tubes) Crevice, and System Condenser Condenser and Microbiologically-Microbiologically-Hotwell)

Hotwell) Influenced Corrosion, and Fouling Fouling Heat Heat Exchanger Exchanger Pressure Boundary Boundary Stainless Steel Treated Water Treated Water Loss of Material/Pitting Material/Pitting One-Time Inspection Inspection VIII.E-36 VIII.E-36 3.4.1-16 A A

Components Components (Main (Tubes) (External)

(External) Crevice Corrosion and Crevice Condenser Condenser and Hotwell)

Hotwell)

Heat Exchanger Heat Pressure Boundary Exchanger Pressure Boundary Stainless Steel Stainless Steel Treated Water Treated Water Material/Pitting Loss of Material/Pitting Water Chemistry VIII.E-36 VII I. E-36 3.4.1-16 A A

Components Components (Main (Tubes) (External)

(External) and Crevice Crevice Corrosion Condenser and Condenser Hotwell)

Hotwell)

No. I and Unit No.

Generating Station, Unit No.1 Salem Nuclear Generating No.22 Page 3.4-55 Page 3.4-55 License Renewal License Renewal Application Application

Section Section 33 - Aging Aging Management Management Review Review Results Results Notes Notes Definition of Definition of Note Note A NUREG-1801 item for component, material, Consistent with NUREG-1801 Consistent environment, and aging material, environment, aging effect. AMP consistent with NUREG-1801 AMP is consistent NUREG-1801 AMP.

BB NUREG-1801 item for component, material, Consistent with NUREG-1801 material, environment, and aging effect. AMP and aging AMP takes some exceptions to NUREG-some exceptions NUREG-1801 AMP.

1801 AMP.

C Component is different, but Component consistent with NUREG-1801 but consistent material, environment, NUREG-1801 item for material, aging effect.

environment, and aging effect. AMP consistent with AMP is consistent NUREG-1801 AMP.

NUREG-1801 AMP.

D Component Component is different, but but consistent consistent with NUREG-1 NUREG-1801801 item for material, material, environment, environment, and effect. AMP takes some and aging effect. some exceptions exceptions to NUREG-1801 AMP.

to NUREG-1801 EE Consistent with NUREG-1801 item with NUREG-1801 material, environment, and aging effect, item for material, aging management effect, but a different aging management program credited or program is credited or NUREG-1801 identifies NUREG-1801 plant-specific aging management identifies a plant-specific management program.

program.

FF Material Material not in NUREG-1 NUREG-1801 801 for this component.

component.

G Environment NUREG-1 801 for this component Environment not in NUREG-1801 component and material.

H Aging Aging effect NUREG-1801 for this component, material, and environment effect not in NUREG-1801 combination.

environment combination.

II Aging effect effect in NUREG-1 NUREG-1801 801 for this component, material, and environment environment combination is not applicable.

applicable.

JJ Neither the component Neither component nor material and nor the material combination is evaluated and environment combination NUREG-1 801.

evaluated in NUREG-1801.

Plant Sp*ecific Plant Specific Notes:

None None No. 1 and Unit No.2 Nuclear Generating Station, Unit No.1 Salem Nuclear No. 2 Page 3.4-56

  • Renewal Application
  • Section
  • Section 3 -- Aging Management Review Results Management Review Results Table 3.4.2-4 Main Steam System Summary of Aging Management Management Evaluation Evaluation Table 3.4.2-4 Main Steam System Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Vol. 2 Item Item Management Management Bolting Mechanical Closure Carbon and Low Air Air -- Indoor (External)

Indoor (External) Loss of Loss of Material/General, Material/General, Bolting Integrity Bolting Integrity VIII.H-4 VIILH-4 3.4.1-22 3.4.1-22 B B

Alloy Steel Alloy Steel Pitting, and Crevice Pitting, Crevice Bolting Corrosion Bolting Bolting Mechanical Closure Carbon Mechanical Closure Carbon and and Low Low Air Air -- Indoor (External)

Indoor (External) Loss of Loss of PreloadfThermal Preload/Thermal Bolting Integrity Bolting Integrity VIII.H-5 VIILH-5 3.4.1-22 3.4.1-22 B B

Alloy Steel Effects, Gasket Creep, Bolting Bolting and Self-Loosening and Self-Loosening Bolting Mechanical Mechanical Closure Closure Carbon and Low Air - Outdoor (External) Loss of Material/General, Material/General, Bolting Integrity VIII.H-1 VIILH-1 3.4.1-22 B B

Alloy Alloy Steel Steel Pitting, Pitting, and and Crevice Crevice Bolting BoltinQ Corrosion Bolting Bolting Mechanical Closure Mechanical Carbon and Closure Carbon and Low AirAir with with Borated Borated Water Water Loss Loss of of Material/Boric Material/Boric Acid Acid Boric Acid Corrosion Boric Corrosion VIII.H-2 VIILH-2 3.4.1-38 3.4.1-38 A A

Alloy Alloy Steel Steel Leakage (External)

Leakage (External) Corrosion Corrosion Bolting Bolting Condensing Condensing Pressure Boundary Pressure Boundary Stainless Steel Air - Indoor Indoor (External)

(External) None None None None VIII.1-10 VIIU-10 3.4.1-41 CC Chamber Chamber Condensing Pressure Boundary Boundary Stainless Steel Air with Borated Water Borated Water None None None VII.J-16 VILJ-16 3.3.1-99 3.3.1-99 C Chamber Chamber Leakage (External)

(External)

Condensing Condensing Pressure Boundary Boundary Stainless Steel Treated Treated Water Cracking/Stress Corrosion Water (Internal) Cracking/Stress One-Time Inspection One-Time Inspection VIII.E-38 VIILE-38 3.4.1-14 A A

Chamber Chamber > 140 F Cracking Condensing Condensing Pressure Boundary Boundary Stainless Steel Treated Water (Internal) Cracking/Stress Water (Internal) Cracking/Stress Corrosion Corrosion Water Water Chemistry VIII.E-38 VIILE-38 3.4.1-14 A A

Chamber Chamber > 140 FF

> Cracking Condensing Pressure Boundary Boundary Stainless Steel Treated Water Water (Internal) Loss of Material/Pitting Material/Pitting Inspection One-Time Inspection VIII.B1-4 VIILB1-4 3.4.1-16 C Chamber Chamber > 140 F and Crevice Corrosion Condensing Condensing Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel irreated Treated Water (Internal)

(Internal) Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.B1-4 VIILB1-4 3.4.1-16 C Chamber Chamber > 140 F and Crevice Corrosion Corrosion Flow Element Flow Element Pressure Boundary Pressure Boundary Carbon Steel Carbon Steel Air Air -- Indoor Indoor (External)

(Extemal) Loss Loss of Material/General of Material/General External Surfaces External Surfaces VIII.H-7 VIILH-? 3.4.1-28 3.4.1-28 A Corrosion Monitoring I Flow Element Element Pressure Boundary Boundary Stainless Steel Steam (Internal)

Steam (Internal) Cracking/Stress Corrosion Cracking/Stress Corrosion Water Water Chemistry Chemistry VIII.B1-2 VIILB1-2 3.4.1-39 3.4.1-39 A, A,11 I_ Cracking Cracking Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.4-57 License Renewal Application

Section 3 - Aging Management Section Management Review Results Review Results Table 3.4.2-4 .-Main Main Steam System (Continued)

Component Component Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Flow Element Pressure Boundary Pressure Boundary Stainless Stainless Steel Steam Steam (Internal)

(Internal) Material/Pitting Loss of Material/Pitting Water Chemistry VIII.B1-3 VIILB1-3 3.4.1-37 A, 1 A,1 and Crevice Corrosion Corrosion Flow Element Throttle Throttle Stainless Steel Steam (Internal)

(Internal) Cracking/Stress Corrosion Cracking/Stress Water Chemistry Chemistry VIII.B1-2 3.4.1-39 A, A,11 Cracking Cracking Flow Element Throttle Stainless Steel (Internal)

Steam (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.B1-3 VIILB1-3 3.4.1-37 A, A,11 and Crevice Crevice Corrosion Corrosion Piping and Fittings Piping and Fittings Leakage Leakage Boundary Boundary Carbon Carbon Steel Air -- Indoor Indoor (Extemal)

(External) Loss of Material/General Material/General External Surfaces VIII.H-7 VIILH-7 3.4.1-28 A A

Corrosion Corrosion Monitoring Monitoring Piping and and Fittings Leakage Boundary Fittings Leakage Boundary Carbon Carbon Steel Air with Borated Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 VIILH-9 3.4.1-38 A A

Leakage (External) Corrosion Corrosion Piping and Fittings Boundary .- Carbon Fittings Leakage Boundary Carbon Steel Treated Water (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.B1-1 VIILB1-111 3.4.1-4 A A

Pitting,

_

and Crevice

. Corrosion Corrosion Piping Piping and Fittings Leakage Boundary Boundary Carbon Carbon Steel Treated Water (Internal)

Treated (Intemal) Loss of Material/General, Material/General, Water Chemistry Chemistry VIII.B1-1 VIILB1-111 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Piping Piping and Fittings Fittings Leakage Leakage Boundary Boundary Carbon Carbon Steel Treated Water (Internal)

!Treated (Internal) Wall Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.B1-9 VIILB1-9 3.4.1-29 B B

Accelerated Corrosion Accelerated Corrosion Corrosion Corrosion Piping and Fittings Piping and Fittings Leakage Leakage Boundary Boundary Stainless Steel Stainless Steel Air -- Indoor Air Indoor (External)

(External) None None VIII.I-10 VIILI-10 3.4.1-41 3.4.1-41 A A

Piping Piping and Fittings Leakage Leakage Boundary Boundary Stainless Stainless Steel Air with Borated Water None None VII.J-16 3.3.1-99 A A

Leakage Leakage (External)

Piping Piping and Fittings Leakage and Fittings Leakage Boundary Boundary Stainless Steel iTreated Stainless Steel Treated Water (Intemal)

(Internal) Cracking/Stress Cracking/Stress Corrosion Inspection One-Time Inspection VIII.B1-5 VIILB1-S 3.4.1-14 A A

_ > 140 F Cracking

> 140 F Cracking Piping Piping and Fittings Leakage Leakage Boundary Boundary Stainless Steel Treated Treated Water (Internal)

(Intemal) Cracking/Stress Corrosion Water Chemistry Chemistry VIII.B1-5.

VIILB1-S. 3.4.1-14 A A

> 140 F F Crackin9.-

Cracking Piping Piping and Fittings Fittings Leakage Leakage Boundary Boundary Stainless Treated Water (Internal)

Stainless Steel Irreated Material/Pitting Loss of Material/Pitting Inspection One-Time Inspection VIII.B1-4 VIILB1-4 3.4.1-16 3.4.1-16 A A

>> 140 140 FF and Crevice Corrosion Corrosion Piping Leakage Boundary Piping and Fittings Leakage Boundary Stainless Steel Treated Treated Water (Internal)

(Intemal) Loss of Material/Pitting Material/Pitting Water Chemistry Chemistry VIII.B1-4 VIILB1-4 3.4.1-16 A A

> 140 F F and Crevice Crevice Corrosion Corrosion II_ I Piping Piping and Fittings Pressure and Fittings Boundary Pressure Boundary Carbon Carbon Steel Steel Air -- Indoor Air (Extemal)

Indoor (External) Loss of Material/General Material/General External Surfaces External VIII.H-7 VIII.H-7 3.4.1-28 3.4.1-28 A A

Corrosion Monitoring Monitoring Salem Nuclear Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.4-58 0

  • Section

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Piping and Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Air-- Outdoor (External)

Air (External) Loss of Material/General, Material/General, External External Surfaces VII.H1-8 3.3.1-60 3.3.1-60 A A

Pitting, and Crevice Crevice Monitoring Monitoring Corrosion Piping and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion VIII.H-9 VII I. H-9 3.4.1-38 3.4.1-38 A A

Leakage Leakage (External) Corrosion Corrosion Piping and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steam (Internal)

Steam (Internal) Cumulative Fatigue Cumulative Fatigue TLAA VIII.B1-10 VIII.B1-10 3.4.1-1 3.4.1-1 A, A,2 2 Damage/Fatigue Damage/F atig ue Piping and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steam (Internal)

Steam (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.A-16 3.4.1-2 3.4.1-2 A A

Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Piping and Fittings Fittings Pressure Pressure Boundary Boundary Carbon Carbon Steel Steam (Internal)

Steam (Internal) Loss of Material/General, Material/General, Water Chemistry VIII.A-16 3.4.1-2 3.4.1-2 A A

Crevice Pitting, and Crevice Corrosion Piping and Fittings Pressure Pressure Boundary Boundary Carbon Steel Steam Steam (Internal) Wall Thinning/Flow Flow-Accelerated Flow-Accelerated VIII.B1-9 3.4.1-29 B B

Accelerated Corrosion Accelerated Corrosion Corrosion Piping and Fittings Pressure Pressure Boundary Boundary Stainless Steel Stainless Air-- Indoor (External)

Air (External) None None None VIII.I-10 VIIU-10 3.4.1-41 A A

Piping and Fittings Pressure Pressure Boundary Boundary Stainless Steel Air - Outdoor Outdoor (External) Loss of Material/Pitting Material/Pitting Periodic Inspection 1I1.B2-7 III.B2-7 3.5.1-50 E, 3 and Crevice Crevice Corrosion Piping and Fittings Pressure Boundary Boundary Stainless Steel Air with Borated Borated Water None None VII.J-16 VII.J-16 3.3.1-99 A A

Leakage (External)

Leakage (Extemal)

Piping Piping and Fittings Pressure Pressure Boundary Boundary Stainless Steel Steam (Internal)

(Internal) Cracking/Stress Cracking/Stress Corrosion Water Water Chemistry Chemistry VIII.B1-2 VIII.B1-2 3.4.1-39 A A

Cracking Cracking Piping Piping and Fittings Pressure Pressure Boundary Boundary Stainless Steel Steam (Internal)

(Internal) Loss of Material/Pitting Material/Pitting Water Chemistry Chemistry VIII.B1-3 VIII.B1-3 3.4.1-37 A and Crevice Crevice Corrosion Piping Piping and Fittings Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Treated (Internal) Cracking/Stress Cracking/Stress Corrosion Corrosion One-Time Inspection One-Time Inspection VIII.B1-5 VIII.B1-5 3.4.1-14 A

> 140 140 F Cracking Cracking Piping Piping and Fittings Fittings Pressure Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Treated (Internal) Cracking/Stress Cracking/Stress Corrosion Corrosion Water Chemistry Chemistry VIII.B1-5 VIII.B1-5 3.4.1-14 A

> 140

> 140 FF Cracking Cracking Piping Piping and Fittings Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Treated (Internal) Material/Pitting Loss of Material/Pitting One-Time Inspection One-Time Inspection VIII.B1-4 VIII.B1-4 3.4.1-16 A

> 140

> 140 F and Crevice Corrosion and Crevice Piping and Fittings Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Treated (Internal) Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.B1-4 VIII.B1-4 3.4.1-16 3.4.1"16 A

> 140 140 FF and Crevice Corrosion and Crevice I Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page 3.4-59 Renewal Application License Renewal Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table 3.4.2-4 Table 3.4.2-4 Steam System Main Steam Main System (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table I1 Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Vol. Item Management Management Leakage Boundary Orifices Leakage Restricting Orifices Restricting Boundary Carbon Steel Indoor (External)

Air - Indoor Air- Loss of Material/General Loss Material/General External Surfaces External Surfaces VIII.H-7 VII I. H-7 3.4.1-28 3.4.1-28 A A

Corrosion Corrosion Monitoring Monitoring Restricting Onfices Restricting Orifices Leakage Leakage Boundary Boundary Carbon Steel Carbon with Borated Air with Borated Water Material/Boric Acid Loss of Material/Boric Water Loss Acid Corrosion Boric Acid Corrosion VIII.H-9 VII I. H-9 3.4.1-38 3.4.1-38 A A

Leakage (External)

Leakage (External) Corrosion Corrosion Leakage Boundary Orifices Leakage Restricting Orifices Restricting Boundary Treated Water Carbon Steel Treated (Internal) Loss of Water (Internal) of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.B1-111 VIII.B1-1 3.4.1-4 3.4.1-4 A Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Restricting Orifices Restricting Orifices Leakage Leakage Boundary Boundary Carbon Steel Treated Treated Water (Internal) Loss of Water (Internal) of Material/General, Material/General, Water Water Chemistry Chemistry VIII.B1-11 VIII.B1-11 3.4.1-4 3.4.1-4 A Pitting, Pitting, and and Crevice Crevice Corrosion Corrosion Restricting Orifices Pressure Boundary Restricting Boundary . Carbon Steel Air - Indoor Indoor (External) Loss of Material/General Material/General External External Surfaces Surfaces VIII.H-7 VII I. H-7 3.4.1-28 3.4.1-28 A A

Corrosion Corrosion Monitoring Monitoring Restricting Orifices Pressure Boundary Restricting Boundary Carbon Steel Air with Borated Material/Boric Acid Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion VIII.H-9 VII I. H-9 3.4.1-38 3.4.1-38 A A

Leakage (External)

Leakage (External) Corrosion Corrosion Restricting Orifices Pressure Restricting Pressure Boundary Boundary Carbon Steel Steam (Internal)

Steam (Internal) Loss of Material/General, Material/General, One-Time Inspection One-Time Inspection VIII.A-16 VIII.A-16 3.4.1-2 3.4.1-2 A and Crevice Pitting, and Crevice Corrosion _

Restricting Orifices Pressure Restricting Orifices Pressure Boundary Boundary Carbon Steel Carbon Steel Steam (Internal)

Steam (Internal) Material/General, Loss of Material/General, Water Chemistry Water Chemistry VIII.A-16 VIII.A-16 3.4.1-2 A Pitting, and Crevice Crevice Corrosion COrTosion Strainer Body Strainer Leakage Leakage Boundary Boundary Carbon Steel Indoor (External)

Air - Indoor (External) Loss of Material/General Material/General External External Surfaces VIII.H-7 VII I. H-7 3.4.1-28 A Corrosion Monitoring Monitoring Strainer Body Leakage Leakage Boundary Boundary Carbon Carbon Steel Material/Boric Acid Air with Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion VIII.H-9 VII I. H-9 3.4.1-38 A A

Leakage Leakage (External) Corrosion Strainer Body Leakage Leakage Boundary Boundary Carbon Steel Carbon Treated (Internal) Loss of Material/General, Treated Water (Internal) Material/General, One-Time One-Time Inspection VIII.B1-11 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Strainer Body Leakage Leakage Boundary Boundary Carbon Steel Carbon Treated (Internal) Loss of Material/General, Treated Water (Internal) Material/General, Water Chemistry Chemistry VIII.B1-1 1 VIII.B1-11 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Corrosion Strainer Body Pressure Pressure Boundary Carbon Steel Air - .Indoor (External)

Indoor (External) Loss of Material/General Material/General External External Surfaces VIII.H-7 VII I. H-7 3.4.1-28 AA I I Corrosion Monitoring' Monitoring' Strainer Body Pressure Pressure Boundary Carbon Carbon Steel Air with Borated Water Loss Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion VIII.H-9 VII I. H-9 3.4.1-38 AA Leakage Leakage (External) Corrosion Nuclear Generating Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-60 3.4-60 0

  • License
  • *0 Section 33 -- Aging Section

Component Component Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Requiring Requiring Programs Vol. 2 Item Item Management Management Strainer Strainer Body Boundary Pressure Boundary Carbon Steel Treated Water (Internal)

Treated (Internal) Loss of Material/General, Material/General, One-Time One-Time Inspection VIII.B1-1 1 VIII.B1-11 3.4.1-4 A Pitting, and Pitting, and Crevice Crevice Corrosion Corrosion Strainer Strainer Body Boundary Pressure Boundary Carbon Steel Treated Water (Internal)

(Internal) Loss of Material/General, Material/General, Water Chemistry Chemistry VIII.B1-1 1 VIII.B1-11 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Corrosion Thermowell Therrnowell Leakage Boundary LeakaoeBoundarv Stainless Stainless Steel Air - Indoor (External) None None VIII.I-10 VIILI-10 3.4.1-41 3.4.1-41 A A

Thermowell Therrnowell Leakage Boundary Boundary Stainless Stainless Steel Air - Outdoor (External)

(External) Loss of Material/Pitting Periodic Inspection Periodic Inspection III.B2-7 3.5.1-50 3.5.1-50 E, 3 E,3 and Crevice Corrosion Thermowell Therrnowell Leakage Boundary Boundary Stainless Stainless Steel Air with Borated Water None None None VII.J-16 3.3.1-99 3.3.1-99 A A

(External)

Leakage (External)

Thermowell Therrnowell Leakage Leakage Boundary Boundary Treated Water (Internal)

Stainless Steel Treated (Internal) Cracking/Stress Cracking/Stress Corrosion One-Time One-Time Inspection VIII.B1-5 3.4.1-14 3.4.1-14 A A

> 140 FF Cracking Cracking Thermowell Therrnowell Leakage Leakage Boundary Boundary Stainless Steel Treated Stainless Treated Water Water (Internal)

(Internal) Cracking/Stress Cracking/Stress Corrosion Water Chemistry VIII.B1-5 3.4.1-14 3.4.1-14 A A

> 140 140 F F Cracking Cracking Thermowell Therrnowell Leakage Leakage Boundary Boundary Treated Water (Internal)

Stainless Steel Treated Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection VIII.B1-4 3.4.1-16 3.4.1-16 A A

> 140 F

> 140 and Crevice and Crevice Corrosion Corrosion Thermowell Therrnowell Leakage Leakage Boundary Boundary Treated Water (Internal)

Stainless Steel Treated Loss of Material/Pitting Material/Pitting Water Chemistry VIII.B1-4 3.4.1-16 A A

> 140 F

> 140 F and Crevice and Crevice Corrosion Corrosion Thermowell Therrnowell Pressure Boundary Stainless Steel Air-Air - Indoor Indoor (External) None None None VIII.1-10 VIILI-10 3.4.1-41 3.4.1-41 A A

Thermowell Therrnowell Pressure Boundary Stainless Steel Air - Outdoor (External) Loss of Material/Pitting Material/Pitting Periodic Periodic Inspection IIII1.B2-7 I. B2-7 3.5.1-50 3.5.1-50 E, 3 E,3 and Crevice and Crevice Corrosion Thermowell Therrnowell Pressure Boundary Stainless Steel Stainless Air with Borated Water None None None VII.J-16 3.3.1-99 A A

Leakage (External)

(External)

Thermowell Therrnowell Pressure Pressure Boundary Stainless Steel Stainless Steam (Internal)

(Internal) Cracking/Stress Corrosion Water Chemistry VIII.B1-2 3.4.1-39 A A

Cracking Cracking Thermowell Therrnowell Pressure Pressure Boundary Boundary Stainless Steel Stainless Steel Steam (Internal)

Steam (Internal) Loss of Material/Pitting Material/Pitting Water Chemistry VIII.B1-3 3.4.1-37 A A

and Crevice Crevice Corrosion Corrosion Valve Body Valve Body Leakage Boundary Leakage Boundary Carbon Steel Air - Indoor Indoor (External)

(External) Loss of Material/General Material/General External Surfaces Surfaces VIII.H-7 3.4.1-28 A A

Corrosion Monitoring Monitoring Valve Body Valve Body Leakage Boundary Leakage Boundary Carbon Steel Material/Boric Acid Air with Borated Water Loss of Material/Boric Boric Acid Corrosion VIII.H-9 VII I. H-9 3.4.1-38 A A

Leakage (External)

Leakage Corrosion I I No. 1 and Unit No.

Salem Nuclear Generating Station, Unit No.1 No.22 Page Page 3.4-61 License Renewal Renewal Application Application

Section 3 - Aging Management Management Review Results Table Table 3.4.2-4 Main Steam System System (Continued)

Component Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Requiring Programs Vol. 2 Item Item Manaaement Management Valve Body Leakage Boundary Leakage Carbon Steel Treated Water (Internal) Loss of Material/General, Irreated Material/General, One-Time One-Time Inspection Inspection VIII.B1-1 1 VIII.B1-11 3.4.1-4 A A

Pitting, and Crevice Crevice Corrosion Valve Body Leakage Boundary Leakage Carbon Steel Treated Water (Internal) Loss of Material/General, Irreated Material/General, Water Chemistry VIII.B1-1 VIII.B1-111 3.4.1-4 A A

Pitting, Pitting, and Crevice and Crevice Corrosion Valve Body Leakage Boundary Leakaoe Stainless Steel Air - Indoor Indoor (External)

(External) None None VIII.1-10 VIIU-10 3.4.1-41 A Valve Body Leakage Boundary Leakage Stainless Steel Airwith Air with Borated Water None None None VII.J-16 3.3.1-99 A Leakaoe (External)

Leakage Valve Body Leakage Boundary Leakage Treated Water (Internal) Cracking/Stress Stainless Steel !Treated Cracking/Stress Corrosion One-Time One-Time Inspection Inspection VIII.B1-5 3.4.1-14 3.4.1-14 A A

> 140 F Crackino Cracking Valve Body Leakage Boundary Leakage Stainless Steel Irreated Cracking/Stress Corrosion Treated Water (Internal) Cracking/Stress Water Chemistry VIII.B1-5 3.4.1-14 A A

> 140 F Cracking Crackina Valve Body Leakage Boundary Leakage Treated Water (Internal)

Stainless Steel Irreated Loss of Material/Pitting Material/Pitting One-Time One-Time Inspection Inspection VIII.B1-4 3.4.1-16 A A

> 140 FF and Crevice Corrosion Corrosion Valve Body Leakage Boundary Leakage Treated Water (Internal) Loss of Material/Pitting Stainless Steel Irreated Material/Pitting Water Chemistry VIII.B1-4 3.4.1-16 3.4.1-16 A A

> 140 F

>140 F ..and and Crevice Corrosion Corrosion Valve Body Pressure Pressure Boundary Boundary Carbon Steel Air - Indoor Indoor (External)

(External) Loss of Material/General Material/General External Surfaces External Surfaces VIII.H-7 3.4.1-28 A A

Corrosion Monitoring Monitoring Valve Body Pressure Pressure Boundary Boundary Carbon Steel Material/General, Air - Outdoor (External) Loss of Material/General, External External Surfaces Surfaces VII.H1-8 3.3.1-60 A Pitting, and and Crevice Crevice Monitoring Monitoring Corrosion Valve Valve Body Pressure Pressure Boundary Boundary Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Acid Boric Acid Corrosion Corrosion VIII.H-9 VII I. H-9 3.4.1-38 A (External)

Leakage (External) Corrosion Valve Valve Body Pressure Boundary Pressure Boundary Carbon Steel Steam Steam (Internal) Material/General, Loss of Material/General, One-Time One-Time Inspection VIII.A-16 3.4.1-2 A Pitting, and Crevice Crevice Corrosion Valve Valve Body Pressure Pressure Boundary Boundary Carbon Steel Steam (Internal)

(Internal) Material/General, Loss of Material/General, Water Chemistry VIII.A-16 3.4.1-2 A Pitting, and Crevice Crevice Corrosion Corrosion*

Valve Body Pressure Boundary Stainless Steel Air-Air - Indoor Indoor (External) None None None VIII.I-10 VIIU-10 3.4.1-41 A Valve Body Valve Body Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel Air Air -- Outdoor Outdoor (External)

(External) Loss of Loss of Material/Pitting Material/Pitting Inspection Periodic Inspection Periodic IIIII.B2-7 I. B2-7 3.5.1-50 3.5.1-50 E, E,33 and Crevice Corrosion I I Salem Nuclear Nuclear Generating Generating Station, Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.4-62 3.4-62 0

  • Section 33 -- Aging Section

Component Component Intended Material Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 I Item Item Notes Notes Type Function Requiring Programs Programs Vol. 2 Item Item Management Management Valve Body Valve Body Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel Air with with Borated Borated Water Water None None VII.J-16 VII,J-16 3.3.1-99 A A

Leakage (External)

Leakage Valve Body Valve Body Pressure Boundary Pressure Boundary Stainless Steel Stainless Steel !Treated Treated Water Water (Internal)

(Internal) Cracking/Stress Corrosion One-Time Inspection One-Time Inspection VIII.B1-5 VIII,B1-5 3.4.1-14 A A

> 140 F Crackina Cracking Valve Body Valve Body Pressure Pressure Boundary Boundary Stainless Steel Stainless Steel Treated Treated Water Water (Internal)

(Internal) Cracking/Stress Cracking/Stress Corrosion Water Chemistry VIII.B1-5 VIII,B1-5 3.4.1-14 A A

> 140

> 140 F Cracking Crackina Valve Body Valve Body Pressure Pressure Boundary Boundary Stainless Steel Stainless Steel Treated Treated Water (Internal) Material/Pitting Loss of Material/Pitting One-Time Inspection One-Time Inspection VIII.B1-4 VIII,B1-4 3.4.1-16 A A

> 140 F and Crevice Corrosion Valve Body Valve Body Pressure Pressure Boundary Boundary Treated Water (Internal)

Stainless Steel Treated Material/Pitting Loss of Material/Pitting Water Chemistry Chemistry VIII.B1-4 VIII,B1-4 3.4.1-16 A A

>> 140 140 F F and Corrosion and Crevice Corrosion T 2 Page 3.4-63 Salem Nuclear Salem Salem Nuclear Generating Station, Nuclear Generating Generating Unit No.1I1 and Unit No.

Station, Unit No. and Unit No.

and Unit Unit No.

No.22 Page 3.4-63 Page License Renewal Application License Renewal Application

Section Section 3 - Aging Management Management Review Results Notes Definition of Note Definition Note A NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 Consistent with NUREG-1801 NUREG-1801 AMP.

B B NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-Consistent with NUREG-1801 NUREG-1801 1801 AMP.

C Component is different, but consistent with NUREG-1 801 item for material, environment, and aging effect. AMP is consistent NUREG-1801 consistent with NUREG-1801 NUREG-1801 AMP.

D Component is different, but consistent with NUREG-1801 Component NUREG-1801 item for material, environment, and aging effect. AMP takes someexceptioris some exceptions to NUREG-1801 NUREG-1801 AMP.

E Consistent with NUREG-1801 environment, and aging effect, but a different aging management NUREG-1801 item for material, environment, management programprogram is credited or NUREG-1 NUREG-1801 801 identifies a plant-specific management program.

plant-specific aging management F Material Material not in NUREG-1 NUREG-1801 801 for this component.

. ' . .

G Environment Environment not in component and material.

NUREG-1801 for this component in NUREG-1801 material.

H NUREG-1 801 for this component, material, and environment Aging effect not in NUREG-1801 combination.

environment combination.

I Aging effect in NUREG-1801 environment combination NUREG-1 801 for this component, material, and environment combination is not applicable.

J Neither the component nor the material evaluated in NUREG-1801.

environment combination is evaluated material and environment NUREG-1 801.

Plant Specific Specific Notes:

Stainless steel flow elements are inserted into a carbon steel pipe. Therefore, the flow element

1. Stainless
1. element does not have an external environment.
2. The TLAA designation designation in in the Aging Management indicates fatigue of this component is evaluated Management Program column indicates evaluated in Section 4.3.
3. The Periodic Periodic Inspection program applicable to this component type, material, and environment program is substituted to manage the aging effect(s) applicable environment combination. .

Salem Nuclear Generating Generating Station, Unit No. No. 2 No.11 and Unit No.2 Page 3.4-64

  • *
  • Section 3 - Aging Management Management Review Results Review Results Table Table 3.4.2-5 3.4.2-5 Main Main Turbine and Auxiliaries Auxiliaries System Summary of Aging Management Summary Management Evaluation Evaluation Table 3.4.2-5 Main Turbine and Auxiliaries System Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table I1 Item Table Notes Notes Type Type Function Function Requiring Programs Vol. 2 Item Vol. Item Management Management Bolting Mechanical Closure Carbon Mechanical Carbon and LowLow Air - Indoor Indoor (External) Loss of Material/General, Material/General, Bolting Integrity Integrity VIII.H-4 VIILH-4 3.4.1-22 3.4.1-22 B B

Alloy Steel Pitting, and Crevice Crevice Bolting Corrosion Bolting Mechanical Closure Carbon Mechanical Carbon and LowLow Air - Indoor Indoor (External) Loss of Preload/Thermal PreloadfTherrnal Bolting Integrity Integrity VIII.H-5 VIILH-5 3.4.1-22 3.4.1-22 B B

---

Alloy Steel Effects, Gasket Gasket Creep, Bolting and Self-Loosening Self-Loosening Piping and Fittings Pressure Pressure Boundary Stainless Steel Air - Indoor Indoor (External) None None None VIII.I-10 VII 1.1-1 0 3.4.1-41 3.4.1-41 A A

Piping and Fittings Pressure Pressure Boundary Lubricating Oil (Internal)

Stainless Steel Lubricating Material/Pitting, (Internal) Loss of Material/Pitting, Lubricating Oil Analysis Lubricating VIII.A-9 VIILA-9 3.4.1-19 3.4.1-19 B B

Crevice, and Microbiologically-Microbiologically-Influenced Influenced Corrosion Corrosion Piping and Fittings Pressure Pressure Boundary Stainless Steel Lubricating Lubricating Oil (Internal)

(Internal) Loss of Material/Pitting, Material/Pitting, One-Time One-Time Inspection VIII.A-9 VIILA-9 3.4.1-19 3.4.1-19 A A

Crevice, and Microbiologically-Microbiologically-Influenced Influenced Corrosion Valve Body Valve Body Pressure Pressure Boundary Boundary Aluminum Air - Indoor Indoor (External)

(Extemal) None None V.F-2 3.2.1-50 3.2.1-50 A A

Valve Body Pressure Pressure Boundary Boundary Aluminum Lubricating Oil (Internal) Loss of Material/Pitting, Material/Pitting, Lubricating Oil Analysis G Crevice, Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced Valve Body Pressure Boundary Pressure Boundary Aluminum Lubricating Oil (Internal) Loss of Material/Pitting, Material/Pitting, One-Time Inspection G Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced Valve Valve Body Pressure Boundary Boundary Stainless Steel Air-Air - Indoor (External)

(External) None None None VIII.1-10 VIIU-10 3.4.1-41 A A

Valve Valve Body Body Pressure Boundary Pressure Boundary Stainless Steel Lubricating Stainless Lubricating Oil (Internal) Loss of Loss of Material/Pitting, Material/Pitting, Lubricating Lubricating Oil Analysis VIII.A-9 VIILA-9 3.4.1-19 B Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced Corrosion Salem Nuclear Salem Generating Station, Unit No.

Nuclear Generating No.11 and Unit No.2 No. 2 Page 3.4-65 3.4-65 License Renewal Renewal Application Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table 3.4.2-5 Table 3.4.2-5 Main Auxiliaries System Main Turbine and Auxiliaries System (Continued)

Component Component Intended Intended Material Material . Environment Environment Aging Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Valve Body Pressure Boundary Pressure Boundary Stainless Steel Lubricating Stainless (Internal) Loss of Material/Pitting, Oil (Internal)

Lubricating Oil Material/Pitting, One-Time Inspection One-Time Inspection VIII.A-9 VIII.A-9 3.4.1-19 3.4.1-19 A A

Crevice, and Microbiologically-Microbiologically-Influenced Corrosion Influenced Notes Notes Definition of Note Definition Note A

A Consistent NUREG-1801 item for component, Consistent with NUREG-1801 component, material, environment, and aging effect. AMP is consistent with NUREG-1801 material, environment, NUREG-1801 AMP.

B NUREG-1801 item for component, material, environment, Consistent with NUREG-1801 environment, and aging effect. AMP takes some exceptions exceptions to NUREG-NUREG-1801 AMP.

C Component is different, but consistent Component NUREG-1801 item consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.

NUREG-1801 .

D Component is different, but consistent Component NUREG-1801 item for material, consistent with NUREG-1801 material, environment, and aging effect. AMP takes some exceptions exceptions NUREG-1801 AMP.

to NUREG-1801 E

E Consistent Consistent with NUREG-1 801 item with NUREG-1801 item for for material, environment, and material, environment, aging effect, and aging but aa different effect, but aging management different aging management program program is credited or is credited or NUREG-1801 plant-specific aging management NUREG-1801 identifies a plant-specific management program.

F NUREG-1 801 for this component.

Material not in NUREG-1801 G NUREG-1 801 for this component and material.

Environment not in NUREG-1801 H

H Aging effect not Aging effect not in in NUREG-1801 NUREG-1 801 for this component, for this component, material, material, and and environment environment combination.

combination. -

I Aging effect in NUREG-1 801 for this component, material, and environment in NUREG-1801 environment combination combination is not applicable.

J component nor the material Neither the component Neither material and environment evaluated in NUREG-1801.

combination is evaluated environment combination NUREG-1801.

Specific Notes:

Plant Specific None None Salem Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.4-66 Page

Section 33 -- Aging Management Section Management Review Review Results

INTRODUCTION INTRODUCTION CONTAINMENTS. STRUCTURES.

STRUCTURES, AND COMPONENT This section This section provides provides the the results results of the aging management management reviewreview for those components components identified in identified in Section 2.4, Scoping and Screening Screening Results: Structures and Component Component Supports, as being subject to aging aging management management review. The structuresstructures and component supports or portions of of structures, component component supports and commodities, which are addressed in in this section, are described in in the indicated sections.

  • " Auxiliary Building (2.4.1)

Auxiliary (2.4.1)

    • Component Supports Commodity Group (2.4.2)

Component

    • Containment Structure Structure (2.4.3)
  • " Fire Pump House (2.4.4)
  • " Handling Building (2.4.5)

Fuel Handling

  • " Office Buildings (2.4.6)
    • Penetration Areas (2.4.7)

Penetration

\.

    • Pipe Tunnel (2.4.8)
    • Piping and Component Insulation Commodity Piping Commodity Group Group (2.4.9)
    • SBO Compressor Compressor Building (2.4.10)
  • " Service Building (2.4.11)

(2.4.11)

"* Service Water Intake Intake (2.4.13)

    • Shoreline Protection and Dike (2.4.14)
    • Turbine Turbine Building (2.4.16)
    • Yard Yard Structures Structures (2.4.17) 3.5.2 3.5.2 RESULTS RESULTS The The following following tables summarize summarize the results of the aging management management review for Structures Structures and Component Supports:

and Component Table Table 3.5.2-1 Summary of 3.5.2-1 Summary of Aging Management Evaluation Management Evaluation - Auxiliary Building Building Table Table 3.5.2-2 Summary of 3.5.2-2 Summary of Aging Management Management Evaluation Evaluation - Component Component Supports Supports Commodity Commodity Group Group Table Table 3.5.2-3 3.5.2-3 Summary Summary of of Aging Aging Management Management Evaluation Evaluation - Containment Containment Structure Structure Table Table 3.5.2-4 3.5.2-4 Summary Summary of of Aging Aging Management Management Evaluation Evaluation - Fire Fire PumpPump House House

  • Salem Nuclear Generating Salem Nuclear License License Renewal Generating Station, Renewal Application Station, Unit Application No. 1 and Unit No.1 Unit No.

and Unit No.22 Page Page 3.5-1 3.5-1

Section 3 - Aging Management Review Results Section 3 - Aging Management Review Results Table Table3.5.2-5 Table 3.5.2.,5Summary 3.5.2-6 SummaryofofAging Summary of AgingManagement Aging ManagementEvaluation Management Evaluation - -Fuel Evaluation Table 3.5.2-6 Summary of Aging Management Evaluation - Office Buildings Table Table3.5.2-7 Table 3.5.2-7Summary Table3.5.2-8 SummaryofofAging 3.5.2-8Summary SummaryofofAging AgingManagement ManagementEvaluation AgingManagement ManagementEvaluation

-

FuelHandling Office Evaluation - -Pipe HandlingBuilding Buildings Evaluation - -Penetration PenetrationAreas PipeTunnel Tunnel Building Areas

  • Table 3.5.2-9 Summary of Aging Management Evaluation - Pipingand Table 3.5.2-9 Summary of Aging Management Evaluation - Piping andComponent Component Insulation Commodity Insulation Commodity Group Group Table Table3.5.2-10 3.5.2-10Summary SummaryofofAging AgingManagement ManagementEvaluation Evaluation - -SBOSBOCompressor CompressorBuilding Building Table 3.5.2-11 Summary of Aging Management Evaluation Table 3.5.2-11 Summary of Aging Management Evaluation - Service Building - Service Building Table Table3.5.2-12 3.5.2-12Summary SummaryofofAging AgingManagement ManagementEvaluation Evaluation - -Service ServiceWater Water Accumulator Enclosures Accumulator Enclosures Table Table3.5.2-13 3.5.2-13Summary SummaryofofAging AgingManagement ManagementEvaluation Evaluation - -Service ServiceWater WaterIntake Intake Table 3.5.2-14 Summary of Aging Management Evaluation -

Table 3.5.2-14 Summary of Aging Management Evaluation - Shoreline Protectionand Shoreline Protection and Dike Dike Table Table3.5.2-15 3.5.2-15Summary SummaryofofAging AgingManagement ManagementEvaluation Evaluation - -Switchyard Switchyard Table 3.5.2-16 Summary of Aging Management Evaluation Table 3.5.2-16 Summary of Aging Management Evaluation - TurbineBuilding - Turbine Building Table 3.5.2-17 Summary of Aging Management Evaluation Table 3.5.2-17 Summary of Aging Management Evaluation - Yard Structures - Yard Structures 3.5.2.1 Materials, Environments, Aging Effects Requiring Management and Aging 3.5.2.1 Materials. Environments. Aging Effects Requiring Management and Aging

  • ManagementPrograms Management Programs 3.5.2.1.1 3.5.2.1.1 Auxiliary AuxiliaryBuilding Building Materials Materials The Thematerials materialsofofconstruction constructionfor forthe theAuxiliary AuxiliaryBuilding Buildingcomponents componentsare: are:
  • Aluminum
  • Aluminum
  • Aluminum Bolting
  • Aluminum Bolting

"

  • Carbon Carbonand andLow LowAlloy AlloySteel SteelBolting Bolting
  • Concrete
  • Concrete
  • Concrete block
  • Concrete block
  • Elastomers
  • Elastomers

" Galvanized GalvanizedSteel

  • Steel

" Galvanized GalvanizedSteel SteelBolting

  • Bolting

" Reinforced concrete

  • Reinforced concrete Salem Nuclear Salem Renewal License Generating Station, Nuclear Generating Unit No. 1 and Unit No. 2 Application Station, Unit No.1 and Unit No.2 License Renewal Application Page Page3.5-2 3.5-2
  • **

Steel Stainless Steel Stainless Steel Stainless Environments Steel Bolting Bolting The Auxiliary Building components are are exposed to the to~he following environments:

    • Air- Indoor Air-Indoor
    • Air -- Outdoor
    • Air with Air with Borated Borated Water Leakage Leakage
  • " Concrete
  • " Encased Encased in in Steel
    • Groundwater/Soil
    • Raw Water Raw
  • " Water - Flowing Flowing Effects Requiring Management Aging Effects Management The following aging effects associated associated with the Auxiliary Building componentscomponents require management:

management:

    • Cracking, Loss Cracking, Loss ofof Bond, Bond, and and Loss Loss of of Material Material (Spalling, (Spalling, Scaling)/Corrosion Scaling)/Corrosion of of Embedded Embedded Steel
  • " Cracking/Restraint, Cracking/Restraint, Shrinkage, Creep, Creep, and and Aggressive Aggressive Environment Environment
  • .- Cracking/Shrinkage Cracking/Shrinkage
    • Cracks Cracks and Distortion/Increased Stress and Distortion/Increased Stress Levels Levels from Settlement Settlement
    • Increase Increase in in Porosity and Permeability, Porosity and Permeability, Cracking, Cracking, Loss Loss of Material (Spalling, Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Chemical Attack
    • Increase Increase in in Porosity and Permeability, Permeability, Loss of Strength Strength /Leaching

/Leaching of Calcium Calcium Hydroxide Hydroxide

    • Increased Hardness, Shrinkage Increased Hardness, Shrinkage and Loss Loss of StrengthlWeathering Strength/Weathering
    • Loss Loss ofof Material Material (Spalling, (Spalling, Scaling)

Scaling) and Cracking/Freeze-thaw and Cracking/Freeze-thaw

    • Loss Loss ofof Material/Boric Material/Boric Acid Corrosion Corrosion
    • Loss Loss ofof Material/General, Material/General, Pitting,Pitting, Crevice, Crevice, and Microbiologically Influenced and Microbiologically Influenced Corrosion
    • Loss Loss of Preload/Self-Loosening of Preload/Self-Loosening
    • Loss Loss ofof Sealing/Deterioration Sealing/Deterioration of of Seals, Gaskets, and Seals, Gaskets, Moisture Barriers and Moisture Barriers (caulking, flashing, and other sealants) sealants)
  • Salem Salem Nuclear Nuclear Generating License Renewal License Generating Station, Unit Renewal Application Application Unit No.

No.11 and Unit No.

No.22 Page 3.5-3 3.5-3

Section 3 - Aging Management Review Results Aging Management Results Management Programs Aging Management The following aging management Auxiliary Building components:

Programs management programs Boric Acid Corrosion (B.2.1.4) programs manage manage the aging effects for the the *

    • Monitoring Program (B.2.1.33)

Structures Monitoring Table 3.5.2-1, 3.5.2-1, Summary Summary of Aging Management Management Evaluation - Auxiliary Building Building summarizes the results of the aging aging management Auxiliary Building.

management review for the Auxiliary Building.

3.5.2.1.2 Component Supports Commodity Commodity Group Group Materials Materials materials of construction The materials construction for the Component Component Supports Commodity Commodity Group Group components are:

  • " Carbon Carbon and Low Alloy Steel Bolting Bolting
    • Elastomers Elastomers
    • Galvanized Galvanized Steel
    • Galvanized Galvanized Steel Bolting
  • 0
  • 0 Graph-Air Graph-Air Tool Steel High Strength Low Alloy Steel Bolting with Yield Strength Greater Lubrite Lubrite Greater than 150 ksi High Strength Stainless Steel Bolting with Yield Strength Greater than 150 ksi
    • Reinforced concrete; concrete; Grout Grout
  • a Stainless Stainless Steel
    • Stainless Steel Bolting Environments Environments The Component Supports Commodity Commodity Group components components are exposed to the the following environments:

environments:

    • Air Air -- Indoor Indoor
    • Air Air -- Outdoor Outdoor
    • Air with with Borated Borated WaterWater Leakage Leakage
    • Air with Steam or Water Leakage Leakage
    • Treated Borated Water Treated Borated Water Salem Nuclear Salem Nuclear Generating License Renewal License Station, Unit Generating Station, Renewal Application Application Unit No.1 No. 1 and Unit No.2 and Unit No. 2 Page Page 3.5-4
  • Aging Effects Requiring Group components

Management Requiring Management The following aging effects associated associated with the Component components require management:

Lock-up Lock-up due to wear Component Supports Commodity

    • Loss of Material/Boric Material/Boric Acid Corrosion
  • " Loss of Material/General, Material/General, Pitting and CreviceCrevice Corrosion
    • Loss of Mechanical Function/Corrosion, Distortion, Dirt, Overload, Mechanical Function/Corrosion, Overload, Fatigue due due to Vibratory Vibratory and Cyclic Thermal Loads Thermal Loads
    • Loss of Preload/Self-Loosening Preload/Self-Loosening
    • Reduction Reduction in Concrete anchor capacity due to local concrete concrete degradation/service-induced cracking or other degradation/service-induced other concrete concrete aging mechanisms mechanisms
    • Reduction Reduction or Loss of Isolation Function/Radiation Function/Radiation Hardening, Hardening, Temperature, Temperature, Humidity, Sustained Humidity, Sustained Vibratory Loading Aging Management Management Programs Programs The following aging management management programs manage the aging effects for the programs manage the Component Supports Commodity Group components:
    • ASME Section Section XI,Xl, Subsection Subsection IWF (B.2.1.30)
  • **

Boric Acid Corrosion (B.2.1.4)

Structures Monitoring Structures Monitoring Program (B.2.1.33)

Water Chemistry (B.2.1.2)

Table 3.5.2-2, Summary (B.2.1.2). .'

(B.2.1.33)

Management Evaluation Summary of Aging Management Evaluation - Component Component Supports Supports Commodity Commodity Group summarizes summarizes the results of the aging management management review for the the Component Component SupportsSupports Commodity Commodity Group.

3.5.2.1.3 3.5.2.1.3 Containment Containment Structure Structure Materials Materials The materials materials of construction for the Containment Structure Structure components components are:

    • Asbestos Asbestos
    • Carbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete
    • Elastomers Elastomers
    • Galvanized Steel Galvanized Steel
    • Galvanized Steel Bolting Bolting

Unit No.1 No.22 Page 3.5-5

Section Section 3 - Aging Management Management Review Review Results Results

Paint Paint Reinforced Reinforced concrete Stainless Steel concrete Stainless Steel Bolting Bolting

  • Environments Environments The Containment Containment Structure Structure components exposed to the following environments:

components are exposed

    • Air- Indoor Air - Indoor 0* Air - Outdoor
    • Air with Borated Borated Water LeakageLeakage
    • Air with Steam or Water Leakage Leakage
    • Concrete Concrete
    • Encased in Steel Encased
    • Groundwater/Soil 0* Raw Water Water
    • Treated Borated Water
  • 0 Water-Flowing Water - Flowing Aging Effects Requiring Management "

Requiring Management" The following aging effects associatedassociated with the Containment Structure Structure components components require require management: "

    • Cracking, Blistering, Flaking, Peeling, and Delamination
    • Cracking, Loss of Bond, and Loss of Material Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion" of Embedded Embedded Steel
    • Cracks and Distortion/lncreased Distortion/Increased Stress Levels from Settlement Settlement
    • Cumulative Fatigue Damage/Fatigue Damage/Fatigue.
    • Increase Increase in in Porosity Porosity and Permeability, Cracking, Loss of Material Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack
    • Increase Porosity and Permeability, Loss of Strength /Leaching Increase in Porosity /Leaching of Calcium Hydroxide Hydroxide
    • Increased Increased Hardness, ShrinkageShrinkage and Loss of Strength/Weathering StrengthlWeathering
    • Loss of Leaktightness/Mechanical Leaktightness/Mechanical Wear of Locks, Hinges and Closure Mechanisms Mechanisms
    • Loss of Material (Spalling, Scaling) and Cracking/Freeze-thaw and Cracking/Freeze-thaw
    • Material/Boric Acid Corrosion Loss of Material/Boric Salem Nuclear Generating Salem Nuclear Generating Station, Unit Renewal Application License Renewal No. 1 and Unit No.2 Unit No.1 No. 2 Page 3.5-6 3.5-6
  • **

Material/General, Pitting, Crevice, and Microbiologically Loss of Material/General, Corrosion, and Fouling Loss of Preload/Self-Loosening Preload/Self-Loosening Microbiologically Influenced Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Loss of Sealing/Deterioration Influenced Barriers (caulking, flashing, and other sealants)

(caulking, Aging Management Management Programs Programs The following aging management programs manage the aging effects for the The following aging management programs manage the aging effects for the Containment StructureStructure components:

    • Buried Non-Steel Piping InspectionInspection (B.2.2.4)
    • Protective Coating Monitoring Monitoring and Maintenance Maintenance Program Program (B.2.1.35)

(B.2.1.35)

    • Monitoring Program (B.2.1.33)

Structures Monitoring

(4.5)

    • Water Chemistry Chemistry (B.2.1.2)
    • Periodic Inspection Inspection (B.2.2.2)

Table 3.5.2-3, Summary of Aging Management Evaluation - Containment Structure Management Evaluation Structure summarizes the results of the aging management management review for the Containment Containment Structure.

3.5.2.1.4 Fire Pump HouseHouse Materials Materials The materials of construction construction for the Fire Pump House componentscomponents are:

    • Aluminum Aluminum
    • Aluminum Bolting Bolting
    • Carbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete
    • Concrete Concrete block
    • Elastomers Elastomers
    • Galvanized Galvanized Steel
  • Salem Nuclear Salem Nuclear Generating Generating Station, Unit No.

License Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.5-7 Page 3.5-7

Section 3 - Aging Management Management Review Results Results

Galvanized Steel Bolting Galvanized Grout Grout Reinforced concrete Reinforced concrete Bolting

    • Steel Stainless Steel
  • 0 Stainless Steel Bolting Bolting Environments Environments The Fire Pump House House components are exposed exposed to the following environments:
    • Air- Indoor Air - Indoor
    • Air - Outdoor
    • Concrete Concrete
    • Encased in Steel

"* Groundwater/Soil Aging Effects RequiringRequiring Management Management The following aging effects associated with the Fire Pump House components effects associated components require management:

    • Cracking, Cracking, Loss of Bond, and Loss of Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Embedded 0* Cracking/Restraint, Shrinkage, Creep, and Aggressive Cracking/Restraint, Aggressive Environment Environment.

0* Cracking/Shrinkage Cracking/Shrinkage

    • Increase in Porosity and Permeability, Cracking, Increase Cracking, Loss of Material (Spalling, (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack
    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Influenced Corrosion

"* Preload/Self-Loosening Loss of Preload/Self-Loosening

    • Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Moisture Barriers (caulking, flashing, flashing, and other sealants)

Management Programs Aging Management Programs The following aging management program manages the aging effects for the Fire The following aging management program manages the aging effects for the Fire Pump House components:

    • Structures Monitoring Structures Program (B.2.1.33)

Monitoring Program Table 3.5.2-4, Summary of Aging Management Evaluation - Fire Pump House Management Evaluation House summarizes summarizes the results of the aging management management review for the Fire Pump House.

Salem Nuclear Generating Salem Nuclear License Renewal Generating Station, Unit No.1 Renewal Application No. 1 and Unit No.2 No. 2 Page 3.5-8

  • 3.5.2.1.5 3.5.2.1.5 Handlinq Building Fuel Handling Buildinq Materials Materials The materials materials of construction for the Fuel Handling Handling Building components components are:
    • Aluminum Aluminum
    • Carbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete
    • Elastomers Elastomers
    • Galvanized Steel Galvanized
    • Galvanized Steel Bolting Galvanized Bolting
    • Reinforced Concrete Reinforced Concrete
    • Stainless Steel Environments Environments The Fuel Handling Building components components are exposed to the following environments:
  • **

Air-- Indoor Air Outdoor Air - Outdoor Air with Borated Concrete Concrete Borated Water LeakageLeakage

    • Groundwater/Soil
    • Borated Water Treated Borated
    • Water - Flowing Flowing Aging Effects Effects Requiring Management Management The following aging effects associatedassociated with the Fuel Handling Building components components require management:
    • Cracking, Cracking, Loss of Bond, and Loss of Material Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Embedded
    • Cracking/Shrinkage Cracking/Shrinkage
  • " Cracking/Stress Cracking/Stress Corrosion Corrosion Cracking Cracking
    • Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Settlement
    • Cumulative Damage/Fatigue Cumulative Fatigue Damage/Fatigue
  • Salem Nuclear Nuclear Generating License Renewal Generating Station, Unit No.

Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.5-9 3.5-9

Section 3 - Aging Aging Management Management Review Results Results

Increase in Porosity and Permeability, Cracking, Increase Scaling)/ Aggressive Scaling)/

Increase Hydroxide Hydroxide Aggressive Chemical Attack Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Permeability, Loss of Strength/

(Spalling, Strength/ Leaching of Calcium Calcium

    • Increased Hardness, Shrinkage and Loss of StrengthlWeathering Increased Strength/Weathering
    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Loss of Material/

Material/ Abrasion; Abrasion; Cavitation

    • Loss of Material/Boric Material/Boric Acid Corrosion
    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Influenced Corrosion
    • Loss of Preload/Self-Loosening Loss Preload/Self-Loosening
    • Sealing/Deterioration of Seals, Gaskets, and Moisture Loss of Sealing/Deterioration Barriers Moisture Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs The following aging management programs manage the aging effects for the Fuel The following aging management programs manage the aging effects for the Fuel Handling Building components:

    • Buried Non-Steel Piping InspectionInspection (B.2.2.4)
    • One-Time One-Time Inspection (B.2.1.20)
    • Periodic Inspection Inspection (B.2.2.2)
    • Structures Monitoring Program Program (B.2.1.33)

TLAA (4.5)

    • Water Chemistry (B.2.1.2)

Table Table 3.5.2-5, Summary of Aging Management Evaluation - Fuel Handling Management Evaluation Handling Building Building summarizes summarizes the results of the aging management management review for the Fuel Handling Handling Building.

3.5.2.1.6 Buildings Office Buildings Materials Materials The materials materials of construction construction for the Office Buildings components components are:

    • Carbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete
    • Concrete Concrete blockblock
    • Elastomers
  • Elastomers Nuclear Generating Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-10 3.5-10 Renewal Application License Renewal

Management Review Section 3 - Aging Management Section Results Review Results

  • **

Galvanized Steel Galvanized Galvanized Galvanized Steel Bolting Reinforced concrete Reinforced Bolting Environments Environments The Office Buildings components components are exposed to the following environments:

    • Air -Indoor

- Indoor

    • Air - Outdoor
    • Concrete Concrete
    • Encased in Steel Encased
    • Groundwater/Soil Aging Effects Requiring Requiring Management Management The following aging effects effects associated with the Office Buildings components components require management:
    • 'Cracking, Cracking, Loss of Bond, and Loss of Material Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Embedded Steel
    • Cracking/Restraint, Shrinkage, Creep, and Aggressive Environment
  • Cracking/Restraint, Aggressive Environment
    • Increase Increase in in Porosity and Permeability, Permeability, Cracking, Loss of Material Material (Spalling, Scaling)/

Scaling)/ Aggressive Aggressive Chemical Attack

    • Loss of Material Material (Spalling, Scaling)

Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw

    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Corrosion
    • Loss of Preload/Self-Loosening Preload/Self-Loosening
    • Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Moisture Barriers Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs The following aging management program manages the aging effects for the Office The following aging management program manages the aging effects for the Office Buildings Buildings components:

    • Structures Monitoring Monitoring Program (B.2.1.33)

Table 3.5.2-6, Summary Management Evaluation Summary of Aging Management Evaluation - Office Buildings Buildings summarizes the results of the aging management summarizes management review review for the Office Office Buildings.

  • Salem Nuclear Generating Salem Nuclear License License Renewal Generating Station, Station, Unit No.1 Application Renewal Application No. 1 and Unit No.

No.22 Page 3.5-11 3.5-11

Section 33 - Aging Management Management Review Results 3.5.2.1.7 Penetration Areas Penetration Materials Materials Areas The materials of construction for the Penetration Areas components components are:

    • Aluminum Aluminum
    • Aluminum Bolting Bolting
    • Carbon and Low Alloy Steel Bolting Bolting
    • Elastomers Elastomers
    • Galvanized Steel Galvanized
    • Galvanized Steel Bolting Galvanized Bolting
    • Reinforced Concrete Reinforced Concrete Environments Environments The Penetration Penetration Areas components components are exposed to the following environments:
    • Air--Indoor Air Indoor

..*.

Air - Outdoor Concrete Concrete Encased in Encased in Steel Groundwater/Soil Groundwater/Soil

    • Water-- Flowing Water Flowing Aging Effects Requiring Management Management The following aging effects associated with the Penetration Penetration Areas components Areas components require management:
    • Scaling)/Corrosion of Cracking, Loss of Bond, and Loss of Material (Spalling, Scaling)/Corrosion Cracking, Embedded Steel Embedded
    • Cracks and Distortionllncreased Distortion/Increased Stress Levels from Settlement Settlement
    • Increase in Porosity Porosity and Permeability, Cracking, Loss of Material Material (Spalling, Scaling)/ Aggressive Chemical Chemical Attack
    • Increase in Increase in Porosity Porosity andand Permeability, Permeability, Loss of Strength Loss of Strength /Leaching

/Leaching of Calcium of Calcium Hydroxide Hydroxide

    • Increased Hardness, Shrinkage Increased Shrinkage and Loss of Strength/Weathering StrengthlWeathering
    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Loss of Material/General, Material/General, Pitting and Crevice Corrosion Salem Nuclear Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.2 No. 2 3.5-12 Page 3.5-12 License Renewal License Renewal Application Application

Section 33 - Aging Management Review Results

  • **

Loss of Preload/Self-Loosening (caulking, Preload/Self-Loosening Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs Barriers The following aging management programs manage the aging effects for the The following aging management programs manage the aging effects for the Penetration Areas components:

Penetration

    • Structures Structures Monitoring Monitoring Program (B.2.1.33)

Table 3.5.2-7, Summary of Aging Management Management Evaluation Evaluation - Penetration Penetration Areas Areas summarizes the results of the aging management summarizes management review for the Penetration Penetration Areas.

3.5.2.1.8 Pipe Tunnel Materials Materials construction for the Pipe Tunnel components The materials of construction components are:

    • Carbon Carbon and Low Alloy Steel Bolting
    • Elastomers Elastomers
  • **

Galvanized Galvanized Steel Galvanized Galvanized Steel Bolting Grout Grout Reinforced Concrete Reinforced Concrete Bolting

    • Stainless Steel
    • Stainless Steel Bolting Bolting Environments Environments The Pipe Tunnel components are exposed to the following environments:
    • Air--Indoor Air Indoor
    • Outdoor Air - Outdoor
    • Air with Borated Borated Water Leakage Leakage
    • Concrete Concrete
  • " Groundwater/Soil Groundwater/Soil
  • " Water-- Flowing Water Flowing
  • Salem Nuclear Nuclear Generating Generating Station, Unit No.

Renewal Application License Renewal Application No.11 and Unit No.2 No. 2 Page 3.5-13 3.5-13

Section 3 - Aging Management Management Review Results Aging Effects Requiring Management Effects Requiring Management The following aging effects associated with the Pipe Tunnel components require components require

  • management:
    • Cracking, Loss of Bond, and Loss of Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel
    • Cracking/Shrinkage Cracking/Shrinkage
    • Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Settlement
    • Increase in Porosity

'Increase Porosity and Permeability, Cracking, Loss of Material Material (Spalling, Scaling)/ Aggressive Chemical Attack Scaling)/ Aggressive

    • Increase in Porosity Increase Permeability, Loss of Strength /Leaching Porosity and Permeability, /Leaching of Calcium Calcium Hydroxide Hydroxide
    • Loss of Material Material (Spalling, Scaling)

Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw

    • Loss of Material/Boric Material/Boric Acid Corrosion
    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Influenced Microbiologically Influenced Corrosion Corrosion
    • Loss of Preload/Self-Loosening Preload/Self-Loosening
  • Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs The following aging management programs manage the aging effects for the Pipe The following aging management programs manage the aging effects for the Pipe Tunnel components:

    • Monitoring Program (B.2.1.33)

Structures Monitoring (B.2.1.33)

Summary of Aging Management Table 3.5.2-8, Summary Management Evaluation - Pipe Tunnel summarizes the results of the aging management summarizes management review for the Pipe Tunnel.Tunnel.

3.5.2.1.9 3.5.2.1.9 Piping and Component Component Insulation Commodity Group Insulation Commoditv Group Materials Materials materials of construction The materials construction for the Piping and Component Insulation Commodity Component Insulation Group components Group components are:

    • Aluminum Aluminum
    • Silicate Calcium Silicate
    • Ceramic Fiber
    • Fiberglass
  • Fiberglass Salem Nuclear Generating Salem Nuclear No.1I and Unit No.2 Generating Station, Unit No. No. 2 Page 3.5-14 3.5-14 Application Renewal Application License Renewal

Section 3 - Aging Management Management Review Results Results

  • 0*

Fiberglass Blanket Min "K" Min NUKON NUKON "K"

Stainless Steel Environments Environments The Piping and Component Insulation Commodity components are exposed Commodity Group components to the following environments:

    • Air- Indoor Air - Indoor
    • Air - Outdoor
    • Air with Borated Water Leakage Leakage
    • Air with Steam Steam or Water Leakage Leakage Requiring Management Aging Effects Requiring Management The following aging effects effects associated with the Piping and Component Insulation Insulation Commodity Commodity Group Group components components require management:
    • Loss of Material/Boric Material/Boric Acid Corrosion Corrosion
    • Loss of Material/Pitting Material/Pitting and Crevice Corrosion
  • "*

Management Programs Aging Management Component Programs The following aging management and Component management programs Insulation Boric Acid Corrosion programs manage the aging effects for the Piping Commodity Group components:

Commodity Corrosion (B.2.1.4)

"* Periodic Inspection Inspection (B.2.2.2) 3.5.2-9, Summary Table 3.5'.2-9, Summary of Aging Management Management Evaluation Evaluation - Piping and Component Insulation Commodity Commodity Group summarizes summarizes the results of the aging management management review for the Piping and Component Insulation Insulation Commodity Group.

3.5.2.1.10 SBO Compressor Building Materials Materials materials of construction The materials construction for the SBO Compressor Compressor Building components components are:

    • Aluminum Aluminum
    • Aluminum Bolting Bolting
    • Carbon Carbon and Low Alloy Steel Bolting Bolting
  • " Concrete Concrete block
  • Salem Nuclear Generating Station, Unit No.1 License License Renewal Renewal Application Application No. 1 and Unit No.2 No. 2 Page 3.5-15 3.5-15

Section 3 - Aging Management Management Review Results

Galvanized Steel Galvanized Galvanized Galvanized Steel Bolting Reinforced concrete Reinforced concrete Bolting

  • Environments Environments The SBO Compressor Building components components are exposed to the followingfollowing environments:
    • Air-Air - Indoor Indoor
    • Air - Outdoor
    • Concrete Concrete
    • Groundwater/Soil Aging Effects Requiring Management Requiring Management The following aging effects associated associated with the SBO' Compressor Building Compressor Building components require management:

components

    • Cracking, Loss Cracking, Loss of of Bond, Bond, andand Loss Loss of Material (Spalling, of Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of of .

Embedded Steel Embedded

    • Cracking/Restraint, Cracking/Restraint, Shrinkage, Creep, and Aggressive Aggressive Environment Environment

Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Increase in Porosity and Permeability, Cracking, Increase Scaling)/ Aggressive Chemical Loss of Material Loss of Material/General, Chemical Attack Material (Spalling, Scaling)

Settlement Cracking, Loss of Material (Spalling, Cracking/Freeze-thaw Scaling) and Cracking/Freeze-thaw Material/General, Pitting and Crevice Corrosion

    • Loss of Preload/Self-Loosening Preload/Self-Loosening Management Programs Aging Management Programs The following aging managementmanagement programs manage the aging effects for the SBO Compressor Compressor Building components:
    • Structures Monitoring Structures Monitoring Program (B.2.1.33)

(B.2.1.33)

Table 3.5.2-10, Summary Management Evaluation Summary of Aging Management Evaluation - SBO Compressor Building summarizes the results of the aging management management review for the SBO Compressor Building.

Compressor Salem Nuclear Generating Station, License License Renewal Renewal Application Station, Unit No.1 Application No. 1 and Unit No.

No.2 2 Page 3.5-16 Page 3.5-16

  • 3.5.2.1.11 3.5.2.1.11 Service Service Building Building Materials Materials The materials materials of construction construction for the Service Building components are:
    • Aluminum Aluminum
    • Carbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete
    • Concrete block
    • Elastomers Elastomers
    • Galvanized Steel Galvanized
    • Galvanized Steel Bolting Galvanized
    • Reinforced Concrete Reinforced Concrete Environments Environments The Service Service Building components components are exposed to the following environments:
    • Air-- Indoor Air Indoor
  • *"
  • "

Air - Outdoor Outdoor Concrete Concrete Encased Encased in Steel Groundwater/Soil

    • Water - Flowing Flowing Aging Effects Requiring Management Requiring Management The following aging effects associated with the Service effects associated Service Building components require components require management:
    • Cracking, Loss of Bond, and Loss of Material Cracking, Material (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Embedded Steel
    • Cracking/Restraint, Shrinkage, Creep, and Aggressive Cracking/Restraint, Environment Aggressive Environment
  • 0 Increase Increase in in Porosity Porosity and Permeability, Cracking, Loss of Material Material (Spalling, Scaling)/

Scaling)/ Aggressive Chemical Chemical Attack

    • Increase Increase in in Porosity Porosity and and Permeability, Loss of Strength /Leaching

/Leaching of Calcium Calcium Hydroxide Hydroxide

  • Salem Nuclear Generating Salem Nuclear License Generating Station, Station, Unit Application License Renewal Application No. 1 and Unit No.

Unit No.1 No.22 Page 3.5-17 Page 3.5-17

Section Section 3 - Aging Management Review Results Management Review

Corrosion Corrosion Material (Spalling, Scaling)

Loss of Material Loss of Material/General, Cracking/Freeze-thaw Scaling) and Cracking/Freeze-thaw Material/General, Pitting, Crevice, and Microbiologically Loss of Preload/Self-Loosening Preload/Self-Loosening Microbiologically Influenced Influenced *

    • Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs The following aging management programs manage the aging effects for the Service The following aging management programs manage the aging effects for the Service Building components:

    • Monitoring Program (B.2.1.33)

Structures Monitoring 3.5.2-11, Summary of Aging Management Table 3.5.2-11, Evaluation - Service Building Management Evaluation summarizes the results of the aging management summarizes management review for the Service Building.

3.5.2.1.12 Service Water 3.5.2.1.12 Service Accumulator Enclosures Water Accumulator Enclosures Materials Materials materials of construction for the Service Water Accumulator The materials Accumulator Enclosures Enclosures components are:

components

Carbon and Low Alloy Steel Bolting Carbon Steel Elastomers Elastomers Galvanized Steel Steel Bolting

    • Galvanized Steel Bolting Bolting
    • Reinforced concrete Reinforced concrete Environments Environments The Service Service Water components are exposed Accumulator Enclosures components Water Accumulator exposed to the the following environments: .
  • " Air-Air - Indoor Indoor
    • Air Air -- Outdoor Outdoor
    • Concrete Concrete
    • Groundwater/soil Groundwater/soil Salem Salem Nuclear Generating Station, Unit No.

Nuclear Generating Renewal Application License Renewal Application No. 2 No.11 and Unit No.2 Page 3.5-18 3.5-18

  • Aging EffectsEffects Requiring Management Enclosures components require Enclosures Management The following aging effects associatedassociated with the Service require management:

Service Water Accumulator Water Accumulator

    • Cracking, Loss of Bond, and Loss of MaterialMaterial (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel
    • Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Settlement
    • Increase in Porosity and Permeability, Cracking, Increase Cracking, Loss of Material Material (Spalling, Scaling)/

Scaling)/ Aggressive Aggressive Chemical Attack

    • Loss of Material (Spalling, Scaling) Cracking/Freeze-thaw Scaling) and Cracking/Freeze-thaw
    • Loss of Material/General, Material/General, Pitting and Crevice Corrosion
    • Loss of Preload/Self-Loosening Preload/Self-Loosening
    • Sealing/Deterioration of Seals, Gaskets, and Moisture Loss of Sealing/Deterioration Moisture Barriers Barriers (caulking, flashing, and other sealants)

Management Programs Aging Management Programs The following folloY{ing aging management management programs manage the aging effects for the Service Service Water Accumulator Accumulator Enclosures Enclosures components: .

    • Structures Monitoring Program Structures Monitoring Program (B.2.1.33)

Table 3.5.2-12, Summary of Aging Management Management Evaluation Evaluation - Service Water Accumulator Enclosures summarizes the results of the aging management review for the Service Service Water Accumulator Accumulator Enclosures.

Enclosures.

Service Water Intake 3.5.2.1.13 Service Intake Materials Materials materials of construction The materials construction for the Service Water Water Intake components components are:

    • Aluminum Aluminum
    • Aluminum Bolting Bolting
    • Carbon Carbon and Low Alloy Steel Bolting Bolting
    • Elastomers Elastomers
    • Galvanized Galvanized Steel
    • Reinforced concrete Reinforced
    • Stainless Steel
    • Stainless Steel Bolting
  • Salem Nuclear Generating Station, Unit No.1 License License Renewal Renewal Application Application No. 1 and No. 2 and Unit No.2 Page 3.5-19 3.5-19

Section 3 - Aging Management Review Results Aging Management Results

    • Treated Wood Environments Environments The Service Water Intake components components are exposed to the following environments:
    • Air- Indoor Air - Indoor
    • Air - Outdoor Outdoor
    • Concrete Concrete
    • Groundwater/soil Groundwater/soil
    • Raw Water
    • Water- Flowing Water - Flowing Aging Effects Requiring Management Effects Requiring Management The following aging effects associated with the Service components Service Water Intake components require management:
    • Change Change in in Material Properties, Loss of Material/

Material/Insect Moisture Insect Damage, and Moisture Damage Damage

    • Cracking, Cracking, Loss of Bond, land and Loss of Material (Spalling, Scaling)/Corrosion of Embedded Steel

Cracking/Shrinkage Cracking/Shrinkage Cracks Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Hardening and Loss of Strength/Elastomer Hardening Scaling)/

Scaling)/ Aggressive Strength/Elastomer Degradation Settlement Increase in Porosity and Permeability, Cracking, Loss of Material Aggressive Chemical Attack' Attack Material (Spalling,

    • Increase in in Porosity Porosity and Permeability, Loss of Strength/

Strength/ Leaching of Calcium Calcium Hydroxide Hydroxide

    • Increased Hardness, Increased Hardness, Shrinkage Strength/Weathering Shrinkage and Loss of StrengthlWeathering
    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Loss of Material/

Material/ Abrasion; Abrasion; Cavitation

    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Influenced Corrosion Corrosion
    • Loss of Loss of Preload/Self-Loosening Preload/Self-Loosening
    • Loss of SealinglDeterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Barriers (caulking, flashing, and other sealants)

Aging Management Management Programs Programs The following aging managementmanagement programsprograms manage manage the aging effects for the Service Service Water IntakeIntake components:

Salem Nuclear Nuclear Generating License Renewal License No. 1 and Generating Station, Unit No.1 Renewal Application Application No. 2 and Unit No.2 Page Page 3.5-20

  • *

Table RG 1.127, Inspection Power Plants Inspection of Water-Control Plants (B.2.1.34)

Water-Control Structures Structures Monitoring Program (8.2.1.33)

Table 3.5.2-13, Summary of Aging Management 3.5.2-13, Summary Structures Associated with Nuclear (B.2.1.33)

Management Evaluation - Service Nuclear Intake Service Water Intake summarizes summarizes the results of the aging management management review review for the Service Service Water Water Intake.

3.5.2.1.14 3.5.2.1.14 Shoreline ProtectionProtection and Dike Dike Materials Materials The materials materials of construction for the Shoreline Protection and Dike components components are:

    • Reinforced Concrete Reinforced Concrete
    • Soil, Rip-Rap, Sand, Gravel Environments Environments The Shoreline Shoreline Protection Protection and Dike components components are exposed to the following following environments:

environments:

    • Air - Outdoor Outdoor
  • **

Groundwater/Soil Water-- Flowing Water Flowing Aging Effects Requiring Management The following aging Management associated with the Shoreline aging effects associated Shoreline Protection Protection and Dike Dike components components require management:

    • Cracking, Loss Cracking, Loss of of Bond, Bond, and and Loss Loss of of Material Material (Spalling, (Spalling, Scaling)/Corrosion Scaling)/Corrosion of of Embedded Embedded Steel
  • " Distortion/Increased Stress Cracks and Distortion/Increased Stress Levels from Settlement Settlement
    • Increase Increase in Porosity and Permeability, Cracking, Cracking, Loss of Material Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Chemical Attack
    • Increase Increase in Porosity and Permeability, Permeability, Loss of Strength/

Strength/ Leaching Leaching of Calcium Calcium Hydroxide Hydroxide

    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Loss of Material, Loss of Form/Erosion, Form/Erosion, Settlement, Sedimentation, Sedimentation, Frost Action, Waves, Currents, Surface Runoff, Seepage Seepage
  • " Loss of Material/

Material/ Abrasion; Cavitation Cavitation

    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Influenced Corrosion
  • Salem Salem Nuclear License Renewal license Generating Station, Unit Nuclear Generating Renewal Application Application No. I and Unit No.

Unit No.1 No.22 Page Page 3.5-21

Section 3 - Aging Management Review Results Aging Management Results Shoreline

Management Programs, Aging Management Programs.

management programs manage The following aging management Shoreline Protection and Dike components:

RG 1.127, Inspection manage the aging effects for the Inspection of Water-Control Structures Structures Associated the Nuclear Associated with Nuclear

  • Power Plants (B.2.1.34)
    • Structures Monitoring Monitoring Program (B.2.1.33)

(8.2.1.33)

Table 3.5.2-14, Summary of Aging Management Evaluation - Shoreline Management Evaluation Protection Shoreline Protection and Dike summarizes summarizes the results of the aging management management review for the Shoreline Shoreline Protection Protection and Dike.

3.5.2.1.15 Switchyard 3.5.2.1.15 Materials Materials construction for the Switchyard materials of construction The materials Switchyard components components are:

    • Aluminum Aluminum
    • Carbon C~rbon and Low Alloy Steel Bolting Bolting
    • Concrete Concrete

a*

Galvanized Galvanized Steel Galvanized Steel Bolting PVC Reinforced Concrete Reinforced Concrete

    • Bolting Stainless Steel Bolting Environments Environments The Switchyard Switchyard components are exposed exposed to the following environments:

environments:

    • Air - Outdoor
    • Concrete Concrete
    • Encased in Steel Encased
    • Groundwater/soil
    • Water-Water - Standing
    • Water-- Flowing Water Flowing Aging Effects Requiring Management Management The following aging effects associatedassociated with the Switchyard components require components require management:

Salem Nuclear Generating Salem Nudear Generating Station, Unit No.1 Renewal Application License Renewal Application No. 1 and Unit No.2 No. 2 Page 3.5-22 3.5-22

  • *

Cracking, Loss of Bond, and Loss of Material (Spalling, Scaling)/Corrosion of Cracking, Loss of Bond, and Loss of Material (Spalling, Scaling)/Corrosion of Embedded Embedded Steel Cracks and Distortion/Increased Distortionllncreased Stress Levels from Settlement Increase in Porosity and Permeability, Increase Settlement Permeability, Cracking, Loss of Material (Spalling, Scaling)/ Aggressive Chemical Scaling)/ Chemical Attack

    • Increase in Porosity and Permeability, Loss of Strength /Leaching Increase /Leaching of Calcium Calcium Hydroxide Hydroxide .
    • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw*

Cracking/Freeze-thaw

    • Loss of Material/General, Material/General, Pitting, Crevice, and Microbiologically Microbiologically Influenced Influenced Corrosion
    • Loss of Preload/Self-Loosening Preload/Self-Loosening Aging Management Management Programs Programs The following aging management management programs manage manage the aging effects for the the Switchyard components:
    • Structures Monitoring Monitoring Program (B.2.1.33)

Table 3.5.2-15, Summary Summary of Aging Management Management Evaluation Evaluation - Switchyard summarizes the results of the aging management management review for the Switchyard.

  • Building 3.5.2.1.16 Turbine Building Materials Materials The materials of construction for the Turbine Building
    • Aluminum Aluminum Building components are:
    • Aluminum Bolting Bolting
    • Carbon and Low Alloy Steel Bolting
    • Concrete Concrete
    • Concrete Concrete Block
    • Elastomers Elastomers
  • " Galvanized Galvanized Steel
  • " Galvanized Steel Bolting Galvanized Bolting
  • Salem Nuclear Nudear Generating License Renewal Generating Station, Unit No.

Renewal Application Application No.11 and Unit No.

No.22 Page 3.5-23 Page 3.5-23

Section 33 - Aging Management Review Results

  • "

Grout Grout Reinforced Concrete Reinforced Stainless Stainless Steel Concrete

  • Environments Environments The Turbine Building componentscom,ponents are exposed to the following environments:
  • " Air-- Indoor Air
  • " Air - Outdoor
  • " Concrete Concrete
    • Encased Encased in Steel
    • Groundwater/Soil Groundwater/Soil
    • Water-- Flowing Water Flowing Requiring! Management Aging Effects Requiring, Management The following aging effects associatedassociated with the Turbine components require Turbine Building components require management:
    • Cracking, Cracking, Loss of Bond, and Loss of Material Scaling)/Corrosion of Material (Spalling, Scaling)/Corrosion Embedded Steel Embedded
  • "
  • "

Cracking/Restraint, Cracking/Restraint, Shrinkage, Creep, and Aggressive Environment Cracking/Shrinkage Cracking/Shrinkage.

Increase Scaling)/

Porosity'and Increase in Porosity Scaling)/ Aggressive Chemical Attack Environment Cracking, Loss of Material (Spalling, and Permeability, Cracking, (Spalling,

  • " Increase Increase in in Porosity ,and and Permeability, Loss of Strength /Leaching

/Leaching of Calcium Calcium Hydroxide Hydroxide

  • Loss of Material Material (Spalling, Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw
    • Microbiologically Influenced Material/General, Pitting, Crevice, and Microbiologically Loss of Material/General, Influenced Corrosion
  • Preload/Self-Loosening Loss of Preload/Self-Loosening
    • Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Moisture Barriers flashing, and other sealants)

(caulking, flashing, Management Programs Aging Management Programs The following aging management programs manage the aging effects for the Turbine The following aging management programs manage the aging effects for the Turbine Building components:

  • Monitoring Program (B.2.1.33)

Structures Monitorin'g Table 3.5.2-16, Summary, Summary~of of Aging Management Management Evaluation Building Evaluation - Turbine Building summarizes the results of the aging management for the Turbine Building.

Turbine

  • summarizes management review Salem Nuclear Generating Station, Unit No.

Nuclear Generating No.11 and Unit No.2 No. 2 Page 3.5-24 3.5-24 License Renewal Renewal Application Application

Section Section 3 - Aging Management Management Review Results

  • Structures 3.5.2.1.17 Yard Structures Materials Materials The materials materials of construction construction for the Yard Structures Structures components components are:

"* Carbon and Low Alloy Steel Bolting Bolting

    • Concrete Concrete
    • Elastomers Elastomers
    • Galvanized Steel Galvanized
    • Galvanized Steel Bolting Bolting
    • Reinforced concrete Reinforced concrete Environments Environments The Yard Structures components are exposed to the following environments:
    • Air-- Indoor Air Indoor
    • Air -- Outdoor Air Outdoor
  • " Concrete Concrete
    • Encased Encased in in Steel

"* Groundwater/Soil

    • Water - Flowing Flowing Aging Effects RequiringRequiring Management Management The following aging effects associated with the Yard Structures components effects associated components require require management:
    • Cracking, Loss Cracking, Loss of of Bond, Bond, andand Loss Loss ofof Material (Spalling, Scaling)/Corrosion Materiai (Spalling, Scaling)/Corrosion of of Embedded Steel Embedded Steel
    • Cracks and Distortion/Increased Distortion/Increased Stress Levels from Settlement Settlement
    • Increase in Increase in Porosity and Permeability, Cracking, Loss of Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive ChemicalChemical Attack
    • Increase in Porosity and Permeability, Loss of Strength /Leaching Increase /Leaching of Calcium Calcium Hydroxide Hydroxide
    • Loss of Material Material (Spalling, Scaling)

Scaling) and Cracking/Freeze-thaw Cracking/Freeze-thaw

  • Salem Nuclear License Nuclear Generating Generating Station, Unit No.1 License Renewal Application Application No. 1 and Unit No.2 No. 2 Page 3.5-25 3.5-25

Section Section 3 - Aging Management Management Review Review Results

Loss of Material/General, Pitting, Crevice, and Microbiologically Influenced Loss of Material/General, Pitting, Crevice, and Microbiologically Influenced Corrosion Loss of Preload/Self-Loosening Preload/Self-Loosening Loss of Sealing/Deterioration Sealing/Deterioration of Seals, Gaskets, and Moisture Barriers Barriers

(caulking, flashing, and other sealants)

Aging Management Management ProgramsPrograms The following aging management programs manage the aging effects for the Yard The following aging management programs manage the aging effects for the Yard Structures components:

    • Structures Structures Monitoring ProgramProgram (B.2.1.33)

Table 3.5.2-17, SummarySummary of Aging Management Management Evaluation - Yard Structures Structures summarizes the results of the aging management management review for the Yard Structures.

3.5.2.2 AMR Results for Which 3.5.2.2 Which Further Recommended by the GALL Report Further Evaluation is Recommended NUREG-1801 provides the basis for identifying NUREG-1801 identifying those programs programs that warrant further evaluation evaluation by the reviewerreviewer in the LRA. For the Containments, Structures, and Component Component Supports, those programs programs are addressed addressed in the following subsections.

subsections .

3.5.2.2.1 PWR

. 3.5.2.2.1 PWR and and BWR BWR Containments Containments .

3.5.2.2.1.1 Aging of Inaccessible 3.5.2.2.1.1 Inaccessible Concrete Increases in porosity due to aggressive (spalling, aggressivechemical scaling)

(spalling, scaling) areas of PWR and areas due and BWR to Concrete Areas porosity and permeability, chemical attack, corrosion corrosion BWR concrete concrete and Areas permeability,cracking, of cracking, loss of material attack, and cracking, embedded steel and steel containments.

material(spalling, cracking, loss of bond, bond, and could occur (spa/ling, scaling) in scaling) and loss of material material inaccessible occur inaccessible containments. The existing program program

  • relies on ASME relies Subsection IWL to manage ASME Section XI, Subsection manage these these aging aging effects.

However, However, the GALL Report Report recommends recommends further further evaluation evaluation of plant plant - specific programsto manage programs manage the aging aging effects for inaccessible inaccessibleareas areasif the environment environment is aggressive.

aggressive. Acceptance criteria are described criteria are described in Branch Technical Technical Position in Position in RLSB-1.

At Salem, ASME Section Section XI,Xl, Subsection IWL program, B.2.1.29, is used to manage manage aging of accessible accessible Containment StructureStructure concrete concrete elements elements for increases in in permeability, cracking, loss of material (spalling, scaling) due to porosity and permeability, aggressive aggressive chemical chemical attack, and cracking, cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded embedded steel. The Structures Monitoring Monitoring Program, B.2.1.33, will be used to manage increases in manage increases in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive cracking, aggressive chemical chemical attack and cracking, loss of bond, and loss of material cracking, material (spalling, scaling) due to corrosion corrosion of embedded embedded steel for inaccessible inaccessible (below grade) areas areas of the containment.

Evaluation Evaluation of inaccessible inaccessible areas areas follows.

The Structures The Structures Monitoring Monitoring Program, Program, B.2.1.33, B.2.1.33, will be used used to to monitor below grade grade

  • portions of the Containment concrete.

Salem Nudear Salem Nuclear Generating No. 1 and Generating Station, Unit No.1 No. 2 and Unit No.2 Page 3.5-26 License Renewal License Reneyval Application Application

Section 3 -- Aging Management Management Review Results

  • Inaccessible, below-grade reinforced Inaccessible, subject to an aggressive considered considered a non-aggressive sulfates sulfates were variable reinforced concrete, for the Containment aggressive environment. Groundwater 2008 and 2009. Test results revealed Containment Structures, is Groundwater was sampledsampled and tested in revealed that pH values meet the limits to be non-aggressive environment, (i.e., (Le., pH >

be

> 5.5). The test results for variable across the site and between test periods, with test results in results indicating a non-aggressive non-aggressive environment due to sulfates, (i.e., (Le., sulfates level <1500 ppm). The test results for chlorides were variable variable across across the site, with some results results indicating an aggressive environment indicating environment due to chlorides (chloride test results between 7 to 4800 ppm), where limits consist of a chloride level < 500 ppm, indicating a non-aggressive aggressive environment. The ground water and river water are, therefore, considered aggressive environments considered aggressive environments due to chloride levels.

At Salem, the Containment Containment Structure is designed in accordance with ACI 318-63 in accordance and constructed in accordance accordance with ACI 301-66. The Portland Portland cementconforms cement'conforms to ASTM C 150, Type II II and flyash was also used. Concrete aggregates conform to the requirements requirements of ASTM C 33-66. Neither calcium chloride nor any admixtures admixtures containing calcium chloride or other chlorides, sulfides, ornitrates or nitrates were used.

Aggregates Aggregates were tested in accordanceaccordance with ASTM Specification Specification C 289-65 for potential reactivity reactivity and were also tested in accordance accordance with ASTM Specifications Specifications C 29-60, C 40-66, C 127-59, C 128-59, 128-59, and C 88-63. The coarse aggregate aggregate selected and used on the Salem Project was quarried stone, crushed and graded to meet the the detail specifications.

specifications. The stone, commonly commonly known as traprock, was a basic igneous basic igneous rock consisting rock consisting of diabase and basalt. The dry density density of the concrete concrete mixes used construction exceeded for construction exceeded 144 Ibsl lbs/ cu ft. For structural structural concrete, the maximummaximum

  • allowable slump for concrete placed was 4 inches. In allowable In areas with closely spaced reinforcing bars, the detail reinforcing specification allowed the use of a concrete detail specification concrete mix with a aggregate of 3/8 inch and a maximum coarse aggregate maximum slump of 5 inches.'inches., For the reactor containment wall, in the area adjacent to the equipment and personnel containment hatches personnel hatches where where additional reinforcing steel was specified, a more plastic mix was designed for adequate for adequate concrete concrete placement. In In this case, the slump was increased increased to bebe between 6 and 7 inches. The flyash contains no calcium chloride chloride to cause cause corrosion. The 1970 edition of "Concrete Industries Industries Year Book" states that concrete concrete made with flyash is more resistant to weak acids and sulfates, which cause corrosion. The type and size of aggregate, slump, cement and additives additives have been established established to produce durable concrete. Degradation Degradation of concrete concrete due to cracking, loss of bond, and loss of material (spalling, (spalling, scaling) due to corrosion of embedded steel has not been experienced at Salem.

Exposed portions of below grade concrete will be examined Exposed examined when excavated excavated for any reason and reason and groundwater groundwater chemistry will be monitored monitored periodically periodically in accordance accordance with the Structures Structures Monitoring Program, B.2.1.33. Also the enhanced enhanced periodic periodic inspections of the submerged inspections submerged portions of the Service Water Intake Structure will be be used as indicators indicators for the condition below-grade structures. Because condition of below-grade Because groundwater chemistry is bounded groundwater bounded by river water chemistry, the use of submerged structures as a leading indicator indicator for the potential degradation degradation of below-grade below-grade structures provides reasonable assurance that degradation inaccessible degradation of inaccessible structures will be detected before a loss of an intended intended function.

function. In In the event event inspection of inspection of submerged submerged structures identify identify significant concrete concrete degradations degradations at the the Service Water Water Intake structure, corrective corrective actions will be initiated to evaluate the evaluate the condition of inaccessible inaccessible portions of the Containment Containment Structure and determine determine if

No.22 3.5-27 Page 3.5-27

Section 3 - Aging Aging Management Review Results Results excavation of concrete for inspection is warranted.

excavation Operating experience warranted. Operating experience review has has

  • identified significant not identified significant signs of distress due to aggressive chemical attack or

. corrosion corrosion of embedded steel of submerged concrete components.

submerged concrete In summary, increase In increase in porosity and permeability, cracking, cracking, loss of material (spalling, scaling) due to aggressiveaggressive chemical chemical attack, and cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion corrosion of embedded steel could could occur in below-grade below-grade inaccessible inaccessible concrete. These aging effects will be monitored monitored for submerged submerged reinforced concrete concrete components components and used used as a leading indicator for the potential degradation degradation to below-grade below-grade structures. If If the aging effects are significant for submerged significant submerged structures, corrective actions will be initiated to evaluate inaccessible concrete and determine ifif excavation excavation to expose and inspect the the concrete is warranted.

concrete warranted. In In addition Salem Salem will inspect inaccessible inaccessible reinforced concrete concrete ififexcavated excavated for any reason, and monitor groundwater chemistry monitor groundwater periodically periodically as required required by the Structures Monitoring Structures Monitoring Program, B.2.1.33. The The enhanced program will require periodic sampling, testing, and analysis of ground enhanced water chemistry chemistry for pH, chlorides, and sulfates, and assessing assessing its impact on buried structures. The Structures Monitoring Monitoring Program and ASME Section XI, XI, Subsection IWL program are described in Appendix B. B.

3.5.2.2.1.2 Cracks and Distortion due to Increased 3.5.2.2.1.2 Increased Stress Levels from Settlement;Settlement:

Reduction of Foundation Reduction Strength, Cracking Foundation Strength. Cracking and Differential Differential Settlement Settlement due due to Erosion Erosion of Porous Concrete Concrete Subfoundations, Subfoundations. if Not Covered bv by Structures Structures Monitoring Program Cracks and Cracks PWR and strength, and distortion and BWR distortion due to increased BWR concrete strength, cracking, subfoundations subfoundations could existing program concrete and cracking, and program relies increasedstress stress levels from settlement could occur and steel containments.

and differential containments. Also, reduction settlement due to erosion differentia/settlement could occur in all relies on, all types of PWR and BWR on Structures Structures Monitoring effects. Some plants may rely on a de-watering erosion of porous BWR containments.

Monitoring Program containments. The Programto manage manage these de-watering system to lower the site ground occur in foundation reduction of foundation porous concrete concrete The these aging aging

  • waterlevel. If the plant's water: plant's CLB credits credits a de-watering de-watering system, the GALL Report Report recommends verification verification of the continued continued functionality functionality of the de-watering de-watering system during during the period period of extended operation.

operation. The GALL GALL Report recommends recommends no further evaluation if this evaluation this activity activity is within the scope of the applicant's Structures Monitoring applicant's Structures Monitoring Program.

Program.

At Salem, ASME Section Section XI,Xl, Subsection Subsection IWL program, B.2.1.29, is used to manage potential cracks and distortion due to increased stress levels from settlement, in accessible accessible areasareas of the Containment Structure. The Structures Structures Monitoring Monitoring Program, B.2.1.33, will be used to manage manage this aging effect/mechanism effect/mechanism in inaccessible areas of the Containment Containment Structure. Theaging effect/mechanism is The'aging effect/mechanism expected to be insignificant expected to be insignificant as as explained explained below.

below. ,

The foundation of the ContainmentContainment Structure Structure is established directly in the in the Paleocene silty sands of the Vincetown Formation or upon lean concrete Vincetown Formation concrete fill extending extending to this Formation.

Formation. The VincetownVincetown soils are preconsolidated preconsolidated and/or cemented cemented as a result of its depositional environment environment and subsequent erosion of younger sediments. Thus, this formation provides excellent foundation support for provides excellent Salem Salem structures. Measurements Measurements made throughout throughout plant construction and during Salem Nuclear Nuclear Generating License Renewal License Station, Unit No. 11 and Unit No.2 Generating Station.

Renewal Application Application No. 2 Page 3.5-28 3.5-28

  • initial operation operation indicated has not experienced indicated a maximum maximum settlement of approximately experienced cracks and distortion due to increased settlement of structures. ASME Section XI, Subsection IWL will be used to manage manage aging of accessible approximately 0.5 inch. Salem increased stress levels from IWL, , B.2.1.29, program accessible Containment Structure elements for cracks and distortion due to increased Structure concrete program concrete increased stress levels from settlement.

Inaccessible Inaccessible Containment concrete concrete surfaces surfaces which are below grade will be be examined using the Structures Monitoring Monitoring Program Program when excavated excavated for any reason.

Item Number Number 3.5.1-3 is not applicable applicable to Salem. Porous concrete concrete is not incorporated incorporated into the design and construction of the Containment Containment Structure Structure foundation foundation and a permanentpermanent de-watering de-watering system does not exist at Salem.

The Structures Monitoring Program Program and ASME Section XI, XI, Subsection Subsection IWL described in program are described in Appendix B.

B.

3.5.2.2.1.3 3.5.2.2.1.3 Reduction of Strenath Strength and Modulus Modulus of Concrete Concrete Structures Structures due to ElevatedElevated Temperature Temperature Reduction of strength strength and modulus of concrete concrete due to elevated elevated temperatures temperaturescould occur in occur in PWR and BWR BWR concrete and steel containments.

containments. The implementation implementation of CFR 50.55a 10 CFR 50.55a and and ASME ASME Section Section XI, X1, Subsection Subsection IWL would not be able able to identify the reduction identify reduction of strength strength and modulusmodulus of concrete concrete due to elevated temperature. Subsection temperature. Subsection CC-3400 CC-3400 of ASME ASME Section Il/, Division 2, III, Division 2, specifies the

  • concrete temperature concrete temperaturelimits limits for normal normal operation operation or any otherother long-term period.

period. TheThe GALL Report recommends further GALL evaluation of a plant-specific further evaluation plant-specific aging aging management management program program if any portion portion of the concrete containment containmentcomponents exceeds specified temperature temperature limits,limits, i.e., general general area temperaturegreater area temperature greater than 66°C (1500F) and 666C (150°F) local area temperaturegreater greaterthan than 93°C 0 0 93 C (200°F).

(200 F). Acceptance criteria local area temperature criteriaare are described in described in Branch Branch Technical Positionin RLSB-1.

Technical Position RLSB-1.

Item Item Number 3.5.1-4 is not applicable Number 3.5.1-4 applicable to Salem. The Containment Containment Structure Structure concrete is not exposed temperature greater than 150°F and local area exposed to general temperature area temperature greater than 200 0 F. Technical Specification temperature greater 200°F. 3 /4.6.1.5 limits the Technical Specification 3/4.6.1.5 the average air temperature average temperature inside the Containment during normal normal plant operation operation to 120°F.

120°F. The The bulk bulk air temperature temperature is maintained maintained within the Technical Specification Technical Specification limits limits byby recirculating recirculating air air through through cooling cooling coils. Process Process piping penetrations penetrations in the the Containment wall for high temperature temperature piping are insulated insulated and provided provided with a cooling system cooling system to limit concrete concrete temperature temperature to a maximum maximum of 150°F.1500 F. TheThe Penetration Penetration Air Cooling Cooling System, evaluated evaluated with the Compressed Compressed Air System, provides this provides this cooling cooling design feature. No portion of the concrete containment containment components exceeds components exceeds specified temperature temperature limits.

3.5.2.2.1.4 3.5.2.2.~.4 Loss of Material Material due to General.General, Pitting and Crevice Crevice Corrosion Corrosion Loss of Loss of material material due to general, pitting and general, pitting and crevice crevice corrosion corrosioncould occur occur in steel steel elements of accessible and inaccessible accessible and inaccessible areas areas for al/

all types of PWR and and BWR containments. The existing program containments. program relies relies on ASME ASME Section XI, Subsection Subsection IWE, and 10 and 10 CFR CFR PartPart50, 50, Appendix J, J, to manage manage thisthis aging aging effect. The GALL GALL Report recommends further evaluation of plant-specific programs recommends further evaluation of plant-specific programs to manage this to manage this aging aging

No.22 Page Page 3.5-29

Section 3 - Aging Management Review Results Aging Management Results effect for inaccessible areas if corrosionis significant.Acceptance criteriaare effect for inaccessible areas if corrosion is significant. Acceptance criteria are describedin described in Branch Branch Technical Position in RLSB-1.

Technical Position applicable to BWRs only and is not used for Salem.

Number 3.5.1-5 is applicable Item Number

  • The following discussion is applicable to Item Number 3.5.1-6.

At Salem, ASME ASME Section Xl, XI, Subsection IWE, B.2.1.28, and 10 Subsection IWE, 10 CFR Part 50, B.2.1.31, programs will be used to manage Appendix J, B.2.1.31, manage aging of accessible accessible and inaccessible areas of the Containment inaccessible Containment Structure steel elements due to general, crevice corrosion. Visual and ultrasonic testing (UT) pitting, and crevice (UT) examinations of the containment conducted in containment liner conducted accordance with ASME Section XI, in accordance Xl, Subsection have not identified IWE have identified significant loss of material material duedue to corrosion.

corrosion. Also, as discussed below, the conditions established discussed established in the GALL Report are met and thus GALL Report thus evaluation of plant-specific a further evaluation management programs is not required plant-specific aging management for managing loss of material material due corrosion in inaccessible inaccessible areasareas of the the Containment Structure Containment Structure steel elements.

Concrete in accessible interior interior areas of the Containment Structure monitored by Structure is monitored the Structures Monitoring Program, B.2.1.33, to ensure penetrating cracks that ensure penetrating could provide provide a path for water seepage to the surface surface of the containment liner, ifif corrective action process entered in the corrective identified, are entered process and accepted accepted by evaluation evaluation or repaired.

The lower portion of the Containment steel liner at Salem Salem is largely largely covered by thethe insulation and stainless steel lagging, causing liner insulation portions of the liner to be causing .portions be

  • considered considered inaccessible in accordance accordance with ASME ASME Section Section XI, Xl, Subsection IWE-Subsection IWE-1232. Thus only the portions of the steel liner that are accessible accessible are inspected by general general visual examination in accordance with ASME Section Xl, in accordance Subsection IWE.

XI, Subsection The inaccessible inaccessible steel liner areas areas are accepted accepted based adjacent based on the condition of adjacent accessible accessible areas.

In 2008, a sample of four (4) Unit 1 insulation panels In panels and lagging were removed to allow inspection of the steel liner plate and the moisture barrier. Inspection Inspection of the the accordance with ASME Section Xl, exposed steel liner in accordance XI, Subsection IWE, degradation of the moisture barrier or significant identified no degradation significant liner corrosion. The The examiner noted minor rust in two areas and a coating coating blister was noted and and determined to be due to an imperfectionimperfection in the application application process. The examinerexaminer removed the blister and found no loss of base metal in in the area beneath the blister.

The examiner identified no recordable indications of the liner and the moisture Because this area has been identified in the industry barrier. Because industry as potentially susceptible to corrosion, susceptible corrosion, Salem will remove the insulation insulation and lagging at samplesample locations, and inspect accordance with ASME Section Xl, inspect the liner in accordance XI, Subsection Subsection IWE. A sample of the Unit 2 insulation and lagging will be removed removed and inspected prior to entering period of extended entering the period extended operation.

operation. Thereafter, removal removal of the the sample insulation and lagging panels and the examination examination of the liner will be done done consistent with ASME Section XI, Xl, Subsection IWEIWE inspection frequency. Visual inspection of 100%

inspection 100% of the moisture moisture, barrier,st barrier, at the junction between the containment junction between containment containment liner, will be performed concrete floor and the containment concrete performed in accordance accordance with ASME Section XI, Xl, Subsection IWE program requirements, requirements, to the extent extent practical Salem Nuclear Generating Salem Nuclear Generating Station, Unit Renewal Application License Renewal License Application No. 1 and Unit No.2 Unit No.1 No. 2 Page 3.5-30 3.5-30

  • within the limitation of design, geometry geometry and materials components. The bottom edge of the stainless steel insulation materials of construction trimmed, if necessary, to perform the moisture barrier inspections.

inspections inspections are included as an enhancement B.2.1.28.

enhancement to ASME construction of the inspections. These ASME Section XI, These the lagging will be insulation lagging be Subsection IWE, XI, Subsection IWE, At Salem borated borated water leakage is monitored monitored in accordance accordance with the Boric Acid Acid Corrosion, B.2.1.4. Plant operating experience review did not identify identify degradation of the liner due to boratedborated water leakage.

There are only limited potential causes for linerdegradation.

liner degradation. Leaks inside the the containment are limited containment limited by Technical Technical Specifications Specifications to very small values.

Historically, Histori~ally, the majority majority of the leaks were from Service Service Water Water piping at el. 130',130',

which has been subsequently upgraded. The replacement of the Service subsequently upgraded. Service Water Water piping piping during during the 1990's 1990's with a material that is much' much more resistant to Service Service Water has significantly reduced leakage. There are multiple barriers to prevent water-induced corrosion water-induced corrosion of the liner. The lower portion of the liner is covered with insulation insulation that is sealed sealed against against moisture intrusion with plastic film covered covered by stainless steel lagging and sealed flashing. The liner was painted painted with an epoxy coating to prevent prevent corrosion even if ifwater did penetrate penetrate the insulation. There is a moisture barrier at the junction of the concrete floor and the liner. In moisture barrier In addition, floors are sloped away from the liner towards the drainage trench. A procedure procedure entitled "Service Water Spill Response Response in Containment" is implementedimplemented to appropriately address and clean up any service water leakage appropriately address leakage in the containment.

  • Any leakage leakage identified, identified, which could potentially reach the liner, has been investigated investigated for potential potential effect effect on the liner. Inspections Inspections since the early 1990's have have not identified significant significant liner corrosion corrosion due to service service water or borated water leakage.

As evaluated evaluated above, and based on plant operating operating experience, experience, loss of material due due to corrosion is not significant significant for inaccessible inaccessible areas of the Containment Containment Structure.

Therefore inspections Therefore conducted in accordance inspections conducted accordance with ASME Section XI, XI, Subsection IWE, B.2.1.28, IWE, B.2.1.28, program and testing in accordance accordance with 10 CFR Part 50, Appendix J, B.2.1, 31, provide B.2.1'.31, provide reasonable reasonable assurance assurance that loss of material due to corrosioncorrosion in in accessible and inaccessible accessible inaccessible areas of the Containment Structure will be detected prior to a loss of intended intended function.

The ASME ASME Section XI, XI, Subsection Subsection IWE program, Boric Acid Corrosion, 10 10 CFR Part 50, Appendix J, J, and and Structures Structures Monitoring Monitoring Programs are described in in Appendix B. B.

3.5.2.2.1.5 3.5.2.2.1.5 Loss of Prestress due to Relaxation. Relaxation, Shrinkage.

Shrinkage, Creep.

Creep, and Elevated Elevated Temperature Temperature Loss of prestress prestress forces due to relaxation, shrinkage, creep, relaxation, shrinkage, creep, and elevated temperature temperature for PWR prestressed prestressedconcrete concrete containmehts containments and BWR Mark /II/

prestressed prestressed concrete concrete containments containments is is a Time-Limited Aging Analysis (TLAA) (TLAA) as defined in 10 CFR CFR 54:3.54.3. TLAAs TLAAs are are required requiredto be evaluated evaluatedin accordance accordance with 10 CFR 54.21(c). The evaluation evaluation of this TLAA TLAA is addressed addressedseparately separatelyin in section section 4.5, 4.5, ""Concrete Containment Tendon Prestress Concrete Containment PrestressAnalysis.

Analysis."" of the SRP-LR.

SRP-LR.

Unit No.1 No.22 Page 3.5-31

Section 3 -~ Aging Section Aging Management Management Review Review Results Results Item Number 3.5.1-7 Structure 3.5.1-7 is not applicable Structure is not applicable prestressed concrete containment prestressed applicable to Salem. Loss of prestress forces due to relaxation, shrinkage, creep, and elevated temperature for the Salem Containment elevated temperature applicable since the Salem Containment Structure does not use a containment design.

Containment

  • 0 3.5.2.2.1.6 Cumulative Fatigue 3.5.2.2.1.6 Fatigue Damage Damage included in the current If included currentlicensing basis, fatigue licensing basis, fatigue analyses analyses of suppression suppression poolpool steel steel (including welded joints) shells (including andpenetrations joints) and penetrations (including (including penetration penetration sleeves, sleeves, dissimilarmetal dissimilar welds, and metal. welds, and penetration penetrationbellows) bellows) for all types of PWR and and BWR containments and containments and BWR header,vent line bellows, BWR vent header, bellows, and downcomers are are TLAAs TLAAs as defined in 10 CFR CFR 54.3.

54.3. TLAAsare TLAAs are required requiredto be evaluated evaluated in accordance accordancewith 10 CFR 54.21(c). The evaluation evaluation of this this TLAA TLAA isis addressed addressedseparately separately in Section 4.6, 4.6, "Containment "Containment Liner Plates, Plates, Metal Containments, Containments,andPenetrations and PenetrationsFatigue Fatigue Analysis.""

Analysis.

Item Number 3.5.1-8 is applicable to BWRs BWRs only and is not used used for Salem.

The following discussion is applicable applicable to Item Number Number 3.5.1-9.

A TLAA evaluation for the Transfer Transfer Tube bellows was performed. performed. The stainless stainless Transfer Tube bellows are not part of the containment penetration bellows and steel Transfer and are notnot part of the containment containment pressure boundary boundary but are a water retainingretaining boundary associated associated with the Reactor Reactor Cavity Cavity in the Containment Containment and the Transfer Transfer Pool in the Fuel Handling Building. The TLAA evaluation shows that the projected

  • number of cycles for 60 years is less than the design cycles. Thus, cracking number cracking of transfer tube bellows bellows due to cyclic loading loading is not expected expected to occur through the the period of extended operation. The TLAA is evaluated extended operation. evaluated in accordance accordance with 10 CFR 54.21(c).

54.21 (c). Evaluation Evaluation of this TLAA is discussed in Section 4.5, "Fuel Transfer Transfer TubeTube Bellows Design Cycles".

Cumulative Cumulative fatigue damage associated TLAA evaluations damage and associated evaluations are only applicable to the stainless steel Transfer Tube bellows. Salem is a PWR and the design design does not include a suppression pool. Fatigue analysis is not included included in the current licensing licensing basis for Containment penetrations penetrations (including (including penetration penetration sleeves and dissimilardissimilar metal welds).

Cracking of the Salem Containment Containment penetration penetration bellows, due to cyclic loading loading is not applicable applicable because because the Containment penetration bellows located outside of the the Containment are not in-scope for license license renewal and are not part of the the Containment leakage limiting boundary boundary per UFSAR section, 3.8.1.6.8.10, Piping 3.8.1.6.8.10, Piping Penetrations:

" ....

.... Containment penetrations designed for Salem are not required to be type Containment piping penetrations type "B"tested for 110CFR50 "B" OCFR50 Appendix Appendix J (Ref. Safety Evaluation S-C-R700-MSE-0253 Safety Evaluation S-C-R700-MSE-0253 Rev. 0). The type "B" "B" test is applicable Containment piping penetrations applicable to Containment penetrations that expansion bellows as the leakage limiting boundary. The piping penetrations utilize expansion penetrations at Salem rely on partiallfullpenetration partial/full penetration seal welds inside containment as the the Salem Nuclear Generating Station, Unit No.1 License Renewal License Renewal Application Application No. 1 and Unit No.

No.22 Page 3.5-32

  • S

Section 3 - Aging Management Management Review Results Review Results

  • 3.5.2.2.1.7 leakage limiting boundary, which are leak rate tested as part of the Appendix J type leakage "A" Containment Integrated "A" Integrated Leak Rate Test (ILRT).....".

3.5.2.2.1.7 Cracking due to Stress Corrosion Cracking (SCC)

(ILRT) ..... ".

(SCC) type Cracking due Cracking due to stress corrosioncracking stress corrosion cracking of stainless steel penetration stainless steel penetrationsleeves, sleeves, penetration penetration bellows, bellows, and and dissimilar dissimilarmetal welds could could occur in all types of PWR and containments. Cracking BWR containments. Cracking due to SCC could could also also occur occur in stainless stainless steel steel vent line bellows for BWR BWR containments.

containments. The existing program program relies relies on ASME Section Section X1, Subsection IWE and 10 CFR Part XI, Subsection Part50, 50, Appendix J to managemanage this aging effect.

aging effect.

The GALLGALL Report Report recommends recommends further further evaluation evaluation of additional appropriate additional appropriate examinations/evaluationsimplemented to detect examinations/evaluations detect these agingaging effects stainless effects for stainless steel penetration steel penetrationsleeves, penetrationbellows and sleeves, penetration and dissimilar dissimilarmetalmetal welds, welds, and stainless steel vent line bellows.

stainless bellows.

Item Number Number 3.5.1-11 is applicable to BWRs 8WRs only and is not used for Salem.

The following discussion is applicable Number 3.5.1-10.

applicable to Item Number 3.5.1-10.

corrosion cracking Stress corrosion cracking (SCC) is not an applicable aging mechanism mechanism for the the Containment Structure carbon steel penetration Containment penetration sleeves, stainless steel penetration bellows, and dissimilar dissimilar metal welds. The Salem Containment Containment liner and associated penetration penetration sleeves are carbon steel. High temperature piping systems temperature systems penetrating the containment containment are generally generally carbon carbon steel. Stress corrosion cracking cracking is only

  • applicable to stainless steel and is predicted only under under certain conditions. There There are stainless steel and dissimilar metal welds associated associated with stainless steel piping welded to penetration sleeve cap plates. Salem aging management management reviews reviews concluded SCC, of stainless steel at the penetration sleeves, is not considered considered credible because because stainless steel SCC requires a concentrationconcentration of chloride or sulfatesulfate contaminants, which are not normally contaminants, normally present present inin significant quantities, as well as, high stress, and temperatures temperatures greater greater than 140 degrees degrees F. Leakage of water in the the containment, which might contact the penetration sleeves, is event The event driven. The containment pressure boundary welds between containment between stainless stainless steel piping and penetration sleeves, with normal penetration normal operating temperatures temperatures above 140 140 degrees degrees F, are not highly not highly stressed. In In addition, addition, the Technical Technical Specification Specification limits the average air temperature temperature insideinside the the Containment Containment duringduring normal normal plant plant operation operation to 120 degrees to 120 degrees F. F.

Therefore cracking of these components Therefore components due to stress corrosion cracking is not applicable.

Cracking of the Containment stainless steel penetration bellows, due to stress stress corrosion cracking cracking is also not applicable because the containment containment penetration penetration bellows are not part of the containment leakage leakage limiting limiting boundary per UFSAR UFSAR section, 3.8.1.6.8.10, 3.8.1.6.8.10, Piping Piping Penetrations:

Penetrations:

" ....Containment

.... Containment piping penetrations penetrations designed for Salem are not required required to be type "B" tested for 10CFR50 "8" OCFR50 Appendix J (Ref. Safety Evaluation S-C-R700-MSE-0253 Safety Evaluation S-C-R700-MSE-0253 Rev. 0). The type "8" "B" test is applicable applicable to piping penetrations penetrations thatthat utilize expansion bellows as the leakage leakage limiting boundary. The piping penetrations penetrations at Salem rely on partial/full penetration seal welds inside containmentcontainment as the leakage limiting leakage limiting

  • Salem Nuclear Nuclear Generating Generating Station, Unit No.

License Renewal Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.5-33

Section Section 3 - Aging Management Management Review Review Results Results

boundary, which are leak rate tested as part of the Appendix J type "A" Containment Integrated Containment Integrated Leak Rate Test (ILRT)...".

are not subject to the combination (ILRT) ... "*

The stainless steel transfer tube bellows are located in the reactor cavity pool and combination of high temperature, high stress and the the and

  • concentration of contaminants required for stress corrosion cracking. The transfer corrosion cracking.

tube bellows bellows are evaluated evaluated for cumulative cumulative fatigue as addressed addressed in paragraph 3.5.2.2.1.6 above. A TLAA TLAA evaluation for the Transfer Transfer Tube bellows was was performed. The TLAA is evaluated performed. evaluated in accordance accordance with 10 CFR 54.21 54.21(c).

(c).

Evaluation of this TLAA is discussed Evaluation discussed in Section 4.5 "Fuel Transfer Tube Bellows Bellows Design Cycles".

3.5.2.2.1.8 Cracking due to Cyclic Loading 3.5.2.2.1.8 Cracking Loading Cracking due Cracking due to cyclic loading loadingof suppression suppressionpool steel and and stainless stainless steel shells (includingwelded joints)

(including andpenetrations joints) and penetrations (including penetrationsleeves, (including penetration dissimilar sleeves, dissimilar metal welds, metal welds, and penetration penetration bellows) could could occur occur for for all all types of PWR and BWR containmentsand BWR containments header, vent line bellows and BWR vent header, and downcomers.

downcomers. The The existing program existing relies on ASME program relies ASME Section X1, Subsection IWE and XI, Subsection and 10 CFR CFR PartPart50, 50, Appendix J to managemanage this aging However, VT-3 visual inspection aging effect. However, inspection may not detect fine cracks.

detect cracks. The GALL Report Report recommends recommends furtherfurther evaluation evaluation for detection detection of of this aging this aging effect.

Number 3.5.1-13 is applicable Item Number applicable to BWRs only and is not used at Salem. BWR

  • suppression pool, BWR vent header, vent line bellows and components including suppression downcomers downcomers do not exist at Salem.

Number 3.5.1-12 is not applicable Item Number applicable to Salem. Salem is a PWR and BWR components components including suppression pool, BWR vent header, vent line bellows and including suppression downcomers are not applicableapplicable to Salem. The containment penetration bellows are containment penetration not in-scope in-scope for license license renewal becausebecause they do not perform a Containment Containment structure pressure pressure boundary or any other other intended Containment intended function. The Containment penetration bellows located penetration located outside of the containment containment are not part of the the containment leakage limiting boundary boundary per UFSAR UFSAR section, 3.8.1.6.8.10.

"" .... Containment piping penetrations penetrations designed designed for Salem are not required to be type type "B" tested for 1 10CFR50 OCFR50 Appendix J (Ref. Safety Evaluation S-C-R700-MSE-0253 Safety Evaluation S-C-R700-MSE-0253 Rev. 0). The type "B" "B"test is applicable to piping penetrations penetrations that utilize expansion bellows as the leakage limiting boundary. The piping penetrations penetrations at Salem rely on partial/full penetration seal welds inside containment partial/full containment as the leakage limiting leakage limiting boundary, which are leak rate tested as part of the Appendix J type "A" containment containment Integrated Integrated Leak Rate Test (ILRT)....."

(ILRT) ..... "

The current current licensing basis does not address or include include any analysis of cyclic cyclic Containment liner or penetrations loading for the Containment penetrations (including (including sleeves dissimilar sleeves and dissimilar welds). Plant operating operating experience experience has not identified cracking of the bounding bounding penetrations (including piping, the containment liner or penetrations (including sleeves, dissimilar dissimilar metal welds, and penetrations bellows) as a concern. The*carbon The carbon steel containment containment liner forms a composite structure with the containment containment concrete concrete shell. The composite containment concrete concrete shell and carbon carbon steel liner, and penetrations penetrations (including (including Salem Nuclear Generating Salem Nuclear License License Renewal Generating Station, Unit No.1 Renewal Application Application No. 1 and Unit No.

No.22 Page 3.5-34 3.5-34

  • sleeves and dissimilar penetrations dissimilar metal welds) loads, is addressed welds} are not subject to cyclic loading induced cracking as analysis for the piping is bounding and enveloping addressed where applicable, as a TLAA section 4.3. Cracking Cracking is not predicted enveloping for stresses in the penetrations (including sleeves and dissimilar welds). Cracking, due to fatigue TLAA for the associated piping predicted in the associated fatigue in piping in associated piping due to the low design the loads and, therefore, is not expected expected in the Containment liner and penetrationspenetrations (including sleeves and dissimilar welds).

Thus, fine cracking of penetration penetration sleeves, dissimilar welds, and the containment containment carbon steel liner are not expected at Salem; and the use of ASME ASME Section XI, XI, Subsection IWE, Subsection IWE, and 10 CFR Part 50, Appendix J are adequate adequate to managemanage the the applicable aging effectseffects of these components without supplemental inspection inspection activities. ASME Section XI, Subsection IWE, IWE, and 10 CFR Part 50, Appendix J programs are described programs described in in Appendix B. B.

3.5.2.2.1.9 3.5.2.2.1.9 Loss of Material Material (Scaling. Cracking, Cracking. and Spalling) due to Freeze-Thaw Freeze-Thaw Loss of material (scaling, cracking, material (scaling, cracking, andand spalling) spalling) due to freeze-thaw could occur occur in in PWR and BWR concrete containments.

BWR concrete containments. The existing program programreliesrelies on ASME ASME Section X1, Subsection IWL to manage XI, Subsection manage this aging aging effect. The GALL Report Report recommends further recommends further evaluation evaluation of this aging this aging effect for plants plants located in moderate to located weathering conditions.

severe weathering conditions.

At Salem, ASME Section XI, XI, Subsection Subsection IWL program, B.2.1.29, will be used to

  • manage loss of material manage material (scaling, cracking, freeze-thaw of cracking, and spalling) due to freeze-thaw accessible Containment accessible Containment Structure Structure concrete elements. Evaluation Evaluation of inaccessible inaccessible areas follows.

areas follows.

The Salem The Salem Containment Containment Structure is located in a region where weathering located in weathering conditions are considered considered severe as shown in ASTM C 33-90, Fig. 1. 1. At Salem, the the Containment Structure Containment Structure is designed in accordance accordance with ACI 318-63 and constructed accordance with ACI 301-66. The Portland cement conforms to ASTM C 150, in accordance Type II II and flyash f1yash was also used. Concrete Concrete aggregates aggregates conform to the the requirements of ASTM C 33-66. The type and size of aggregate, slump, cement requirements additives have been established and additives established to produce produce durable durable concrete. Neither calcium calcium chloride nor any chloride any admixtures admixtures containing containing calcium chloride or other chlorides, sulfides, nitrates were used. Aggregates or nitrates Aggregates were tested in accordance accordance with ASTM Specification C Specification C 289-65 289-65 for for potential potential reactivity and were also tested in in accordance accordance with ASTM Specifications Specifications C 29-60, C 40-66, C 127-59, C 128-59, 128-59, and C 88-63. The The aggregate selected coarse aggregate selected and used on the Salem Project was quarried quarried stone, crushed and graded to meet the detail specifications. The stone, commonly commonly known as traprock, was a basic igneous igneous rock consisting of diabase diabase and basalt. The dry density of the concrete concrete mixes used for construction construction exceeded exceeded 144 Ibs/ lbs/ cu ft. The The flyash contains no calcium chloride to cause corrosion.

f1yash corrosion. The 1970 edition of Industries Year "Concrete Industries Year Book" states that concrete concrete made with f1yash flyash is more resistant to weak acids and sulfates, which cause corrosion. For structural concrete, the maximum allowable allowable slump for concreteconcrete placed placed was 4 inches. In In areas areas with reinforcing bars, the detail specification closely spaced reinforcing specification allowed the use of a concrete concrete mix with a coarse aggregate aggregate of 3/8 inch and a maximum maximum slump of 5 inches. For the reactor containment wall, in the area adjacent to the equipment and

  • Salem Nuclear Nuclear Generating Generating Station, Unit License Renewal Renewal Application Application No. 1 and Unit No.

Unit No.1 No.22 Page Page 3.5-35

Section Aging Management Section 33 - Aging Review Results Management Review Results personnel hatches personnel mix was increased to be increased cement cement and where additional hatches where designed for adequate was designed adequate concrete between 66 and be between additives have been and additives reinforcing steel additional reinforcing and 7 inches. The type been established steel was type andand size specified, aa more was specified, placement. In this case, the slump concrete placement.

more plastic slump was aggregate, slump, size of aggregate, durable concrete.

produce durable established to produce plastic was

  • At Salem, exceptexcept for the Service Water Intake the Service Intake structure, structures were also structure, structures also minimize exposure designed to minimize designed moisture to exposure to moisture minimize water absorption, to minimize absorption, minimizing the potential for damage minimizing freeze-thaw conditions. The damage from freeze-thaw The Service Service Water structure is also used Intake structure Water Intake used as as aa leading indicator for the condition leading indicator condition of inaccessible concrete for other inaccessible concrete other structures.

structures.

Exposed portions of Exposed of below below grade concrete will be examined grade concrete examined by the the Structures Structures Program when excavated Monitoring Program Monitoring excavated for any reason reason and groundwater chemistry will groundwater chemistry monitored periodically be monitored accordance with the Structures periodically in accordance Structures Monitoring Monitoring Program, B.2.1.33.

described above, the design and construction As described construction of the Containment Structure Containment Structure concrete is in concrete accordance with ACI standards in accordance significant loss of preclude significant standards that preclude spalling) due to freeze-thaw. Operating experience cracking, and spalling) material (scaling, cracking, material experience review review has not identified significant identified significant loss of material material (scaling, cracking, and spalling) of the accessible structure concrete. Inspections Containment structure accessible Containment conducted in Inspections conducted in accordance with accordance with ASME Section Xl, Subsection IWL identified isolated XI, Subsection isolated instances of minor local minor local spalling cracking of above grade spalling and cracking concrete and.grout.

grade concrete Evaluation of and .grout. Evaluation spalling and concluded they have cracking concluded and.cracking have no significant impact on structural significant impact

  • Containment structure.

integrity of the Containment integrity Therefore, loss of material (scaling, cracking and spalling) spalling) due to freeze-thaw of inaccessible insignificant and requires inaccessible concrete is insignificant requires no aging management. However, inaccessible concrete will be inspected if inaccessible if exposed for any reason, as required required by Salem Structures MonitoringMonitoring Program. ASME ASME Section Section XI, Subsection IWL, and Xl, Subsection Structures Monitoring Programs Structures described in Appendix B.

Programs are described B.

3.5.2.2.1.10 Cracking due to Expansion and Reaction 3.5.2.2.1.10 Reaction with Aggregate, Aggregate. and Increase Increase in Permeability due to Leaching of Calcium Porosity and Permeabilitv Porositv Hydroxide Calcium Hydroxide Crackingdue to expansion Cracking expansion and and reaction aggregate,and increase reaction with aggregate, increasein porosity in porosity and permeability due to leaching and permeability calcium hydroxide leaching of calcium hydroxide couldcould occur occur in in concrete concrete elements of PWR and concrete and and BWR concrete containments. The existing and steel containments. existing program program relies on ASME relies ASME Section X1, Subsection IWL to manage XI, Subsection manage these aging aging effects.

effects. TheThe Report recommends GALL Report recommends further evaluation if concrete further evaluation concrete was not not constructed constructedin. in.

recommendationsin accordancewith the recommendations accordance in ACl 201.2R-77.

ACI201.2R-77.

At Salem, the Containment Structure designed in accordance Structure is designed accordance with ACI 318-63 accordance with ACI 301-66. Aggregates and constructed in accordance Aggregates were tested in in accordance with ASTM Specification accordance Specification C 289-65 for potential reactivity to preclude preclude expansion and reaction expansion aggregate. The use of reaction with aggregate. of Type IIIIcement and fJyash flyash result in concrete resistant to leaching leaching..

.The type and size of aggregate, slump, cement and additives additives have been selected to produce durable concrete. Thus, cracking due to expansion and reaction reaction with Nuclear Generating Salem Nuclear Generating Station, Station, Unit No.1 Application Renewal Application License Renewal No. 2 No. 1 and Unit No.2 Page 3.5-36 Page

  • aggregate is not applicable and requires no aging management. Increase aggregate porosity and permeability permeability due to leaching of calcium the ASME Section XI, management.

Xl, Subsection Subsection IWL program will provide adequate Increase inin significant and calcium hydroxide is not significant adequate aging aging 3.5.2.2.2 Safety-Related and Other Structures 3.5.2.2.2 Safety-Related Structures and Component Supports 3.5.2.2.2.1 3.5.2.2.2.1 Aging of Structures Structures Not Covered Covered by Structures Monitoring Program Structures Monitoring The GALL ReportReport recommends recommends further further evaluation evaluation of certain certain structure/aging structure/agingeffect effect combinations if they are not covered by the Structures combinations StructuresMonitoring Program.This Monitoring Program.

includes (1) includes (1) cracking, cracking, loss of bond, bond, and loss of material (spalling,scaling) material (spalling, scaling) due to corrosionof embedded steel corrosion steel for for Groups Groups 1-5, 1-5, 7, 7, 9 structures; structures; (2)(2) increase increasein porosity porosity andpermeability, and permeability, cracking, cracking, loss of material material(spalling, (spalling,scaling) scaling)due to aggressive aggressive chemical attack for Groups chemical Groups 1-5, 7, 9 structures; structures;(3) (3) loss of material material due to corrosion corrosion Groups 1-5, for Groups 1-5, 7, 8 structures; structures;(4) loss of material (spalling,scaling) material (spalling, and cracking scaling) and cracking due to freeze-thaw freeze-thaw for for Groups Groups 1-3, 5, 5, 7-9 structures; structures;(5) cracking cracking due to expansion expansion and reaction and reaction with aggregates aggregatesfor Groups Groups 1-5, 1-5, 7-9 structures; structures; (6)(6) cracks cracks and distortion due to increased distortion increased stress stress levels from settlement settlement for Groups Groups 1-3, 5-9 structures;and structures; and (7)

(7) reduction reduction in foundation strength, cracking, foundation strength, cracking, differential differential settlement erosion of porous due to erosion concrete subfoundation porous concrete subfoundation for Groups Groups 1-3, 5-9 structures.

structures. TheThe GALL Report recommends further GALL evaluation only for structure/aging further evaluation structure/aging effect combinations that combinations that are are not within within the Structures Monitoring Program.

Structures Monitoring Program.

  • Lock up due to wear wear could occur occur for Lubrite Lubrite radial radial beam seatsseats in BWR BWR drywell, drywell, support shoes RPV support shoes for PWR with nozzle supports, generatorsupports, supports, steam generator supports, and other sliding other sliding support support bearings bearings and and sliding sliding support surfaces. The existing program support surfaces. program relies on the Structures relies Structures Monitoring Monitoring Program Programor ASME Section XI, Subsection Subsection IWF to manage this aging manage effect. The aging effect. The GALL GALL Report recommends recommends further further evaluation evaluation only for structure/agingeffect structure/aging combinationsthat effect combinations that are*not are not within the lSI ISI (IWF)

(IWF) or Structures Monitoring Program.

Monitoring Program.

At Salem, the Structures Monitoring Program, 8.2.1.33, B.2.1.33, is used to managemanage aging aging affects applicable affects applicable to to Groups Groups 1, 3, 4, and 5 structures and component component supports supports as as discussed below. The GALL structure Groups 2, 7, 8, and 9 do not exist at Salem.

Groups 2,7,8, Group 2 and Group 9 structures are BWR specific specific and are not applicable to the the Salem PWR design. Salem has no Group 7 concrete tanks. Concrete Concrete walls and structural steel with a missile barrier function function are associated with some buildings buildings and are addressed as an integral and are addressed as an integral part part of those parent structures. Salem Salem has no no separate Group 7 or 8 missile barrier structures. Steel Tanks are addressed addressed as a part of the mechanical systems and not as a Group 8 structure.

Salem aging management reviews concluded certain concrete aging effects or mechanisms identified mechanisms identified in NUREG-1801 are not applicable in NUREG-1801 applicable to some of Group 1, 3, 4, and 5 structures structures as explained below and require no aging management. However, .

Groups 1,3,4, 1, 3, 4, and 5 accessible accessible structures will be monitored monitored for loss of material, cracking, increase in porosity and permeability, cracking, permeability, and loss of bond through the the Structures Monitoring Structures Program regardless Monitoring Program regardless of the causal causal mechanism.

mechanism. The The Structures Monitoring Structures Program is described Monitoring Program described in Appendix B. B.

  • Salem Nuclear Salem Nuclear Generating Generating Station, Unit Renewal Application License Renewal Application No. 1 and Unit No.

Unit No.1 No.22 Page Page 3.5-37

Management Review Results Section 3 - Aging Management (1) Cracking,loss of bond, Cracking, At Salem, cracking, embedded embedded steel for Groups bond, and loss of material of embedded steel for Groups Groups 1-5, (spalling,scaling) material (spalling, 7, 9 structures.

1~5, 7, structures.

cracking, loss of bond, and loss of material scaling)due to corrosion corrosion material (spalling, scaling) due to Groups 1, 3, 4, and 5 structures are monitored monitored by the the

  • Structures Monitoring Monitoring Program, B.2.1.33, 8.2.1.33, and thus a further evaluation is not necessary. The Structures Monitoring Program is described described in Appendix B.

(2) Increase in porosity Increase porosity and andpermeability, cracking, loss of material permeability, cracking, material (spalling, (spalling, scaling) scaling) due to aggressive aggressive chemical chemical attack for Groups Groups 1-5, 7, 9 structures.

structures.

At Salem, increase in porosity and permeability, permeability, cracking, loss of material (spalling, scaling) due to aggressive aggressive chemical attack attack for Groups 1, 3, 4, and 5 structures structures are monitored through the Structures Monitoring Monitoring Program, B.2.1.33, and thus a further evaluation evaluation is not necessary. The Structures Monitoring Monitoring Program is described described in Appendix Appendix B. B.

Leakage of treated treated borated borated water, from the reactor cavity cavity liners, while while contained contained within the Containment Containment Structures, has come in contact with the the supporting concrete, during during refueling outages. The effects, on the the Containment Containment interior concrete, were evaluated evaluated and found to be bounded bounded by by the effects due to similar leaks in the Fuel Handling Handling Building, due to leaks from from the spent fuel pools. During the investigativeinvestigative phase phase of the spent fuel pool leakage in the Fuel Handling liner leakage Handling Buildings, Salem conductedconducted a plant specific specific concrete immersed in borated water for up to 39 months. Salem, in concrete test immersed in collaboration collaboration with EPRI, EPRI, also conducted additional tests on concrete concrete samples,

  • obtained obtained from another plant, with longer longer term exposure exposure to borated borated water. The The results of the tests were used to analyze analyze the impact continuous impact of potential continuous spent fuel pool concrete exposure to borated borated water leakage. The analyses analyses show that the effects of borated borated water on the reinforced concrete and structural structural margin margin is not significant significant and have no impact on structural structural integrity of the spent fuel pool or the Fuel Handing Handing Building through the period period of extended operation..

extended operation

. (3) Loss of material materialdue to corrosion corrosionfor Groups Groups 1-5, 7, 7, 8 structures.

structures.

At Salem, loss of material due to corrosion corrosion for Groups 1, 3, 4 and 5 structuresstructures and component component supports is monitored monitored through the Structures Monitoring Monitoring Program, B.2.1.33, and thus a further evaluation evaluation is not necessary. The The Structures Monitoring Monitoring Program is described described in Appendix B. B.

(4) Loss of material material(spalling, (spalling,scaling) and cracking scaling) and cracking due to freeze-thaw for for Groups 5, 7-9 structures.

1-3, 5, structures.

At Salem, loss of material (spalling,(spalling, scaling) and cracking due to freeze-thaw for Groups 1, 3 and 5 structures are monitored through the Structures Structures Monitoring Program Program and thus thus a further evaluation evaluation is not necessary. Salem Group 4 structures are inside the Containment Containment Structure and protected protected from repeated freeze-thaw; freeze-thaw; thus not subject to loss of material and cracking due to to freeze-thaw. The Structures Monitoring Monitoring Program is describeddescribed in Appendix B. B.

Salem Nuclear Nuclear Generating Generating Station, Unit No.

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  • (5)

(5) Crackingdue to expansion Cracking structures.

structures.

Item Number 3.5.1-27 expansion and and reaction reaction with aggregates aggregates for GroupsGroups 1-5, 7-9 3.5.1-27 is not applicable. At Salem, cracking due to reaction reaction with aggregates aggregates for Groups 1, 3, 4, and 5 structures is not applicable as as concrete concrete for Groups 1, 3, 4 and and 5 structures structures was constructed constructed in accordance accordance with ACI 301-66 and aggregatesaggregates were tested in accordance accordance with ASTM Specification Specification C 289-65 289-65 for potential reactivity. The type and size of aggregate, aggregate, slump, cement and additives have been selected to produce been selected produce durable durable concrete.

Thus, cracking due to expansion expansion and and reaction with aggregate is not applicable applicable and requires no aging management. Nevertheless, Nevertheless, concrete concrete cracking due to any mechanism mechanism is monitored monitored through Structures Structures Monitoring Program, B.2.1.33, and thus no further evaluation is necessary. The Structures Structures Monitoring Program is described described in Appendix B.

(6) Cracks and Cracks and distortion distortionduedue to increased stress levels from settlement increased stress settlement for Groups 1-3, 5-9 structures.

Groups structures.

structure Groups 1, 3, 4, and 5 are potentially subject At Salem, structure subject to cracks cracks and distortion due to increased increased stress levels from settlement. A de-watering de-watering system and porous concrete subfoundations are porous concrete are not used. Structures whose foundation is founded on soil or the Vincentown Vincentown Formation Formation are potentially subject to cracks cracks and distortion distortion due to increased increased stress levels from settlement.

  • The foundation of the Class 1 station structures are established established directly on the the Vincetown Formation Vincetown Formation or upon lean concrete concrete fill extending extending to this Formation.

Formation.

The Vincetown soils are preconsolidated preconsolidated and/or and/or cemented cemented as a result of its depositional environment depositional environment and subsequent erosion of younger younger sediments.

Thus, this formation provides excellent excellent foundation support support for Salem Measurements made throughout structures. Measurements throughout plant construction and during during initial operation indicated a maximum maximum settlement of approximately approximately 0.5 inch, which is insignificant. Salem has experienced cracks has not experienced cracks and distortion distortion due to increased increased stress levels from settlement of structures. Certain Group Group 3 structures are founded on concrete structures concrete piles, which are are encased encased in steel, and other Group 3 structures structures are founded on soil. For those structures structures founded on soil or the Vincentown formation formation cracks and distortion due to increasedincreased stress stress levels from settlement settlement are applicable and will be monitored under the the Structures MOflitoring Structures Monitoring Program. For those Group 3 structures structures founded founded on concrete concrete piles, encasedencased in steel, cracks and increased stress and distortion due to increased stress levels levels from settlement settlement is not applicable. The Groups 1, 3, 4, and 5 structures structures are monitored monitored under under the Structures Structures Monitoring Monitoring Program for cracks and .

distortion due to increased increased stress levels from settlement. The Structures Structures Monitoring Monitoring Program is described described in Appendix Appendix B.

(7) Reduction in foundation foundation strength, strength, cracking, differential settlement cracking, differential settlement due to erosion of erosion porous concrete porous subfoundation for Groups concrete subfoundation Groups 1-3, 5-9 structures structures Item Number 3.5.1-29 3.5.1-29 is not applicable to Salem structures structures as no porous porous concrete subfoundations concrete subfoundations were used at Salem.

No.22 Page Page 3.5-39

Section 3 - Aging Management Management Review Results Results At Salem, structures Groups 1, 3, 4, and 5 are not subject to reduction foundation strength, cracking, and differential settlement porous concrete subfoundation. The structures concrete subfoundation.

concrete reduction in settlement due to erosion of structures are not founded on a porous in porous

  • Lock up due to wear wear could could occur for Lubrite Lubriteradialradialbeam seats seats in BWR drywell, drywell, RPV support support shoes for PWR with nozzle supports, supports, steam generator generator supports, and other sliding support supports, and other sliding support bearings bearings and sliding support surfaces.

sliding support surfaces. The The existing program relies on the Structures program relies Structures Monitoring Monitoring Program Programor orASME ASME Section X1, Subsection IWF to manage XI, Subsection manage this this aging aging effect. The GALL GALL Report Report recommends further recommends evaluation only for structure/aging further evaluation structure/aging effect combinations that are that within the lSI are not within ISI (IWF)

(/WF) or or Structures Monitoring Program.

Structures Monitoring Program.

Item Item Number 3.5.1-303.5.1-30 and Item Number 3.5.1-56 3.5.1-56 were used at Salem for the the lubrite material associated with the steam material associated steam generator generator supports.

The applicable material for these item numbers numbers is lubrite. The steam generator supports include generator include pinned steel connections and lubrite plates.

Lockup due to wear in the indoor air environment environment is managed managed using the ASME ASME Section XI, Subsection IWF program, B.2.1.30, therefore XI, Subsection evaluation therefore no further evaluation is necessary.

Sliding surfaces for other supports are pinned steel connections connections or carbon surfaces for which lubrite is not used and Item Number 3.5.1-30 is steel sliding surfaces not applicable. At Salem, RPV support shoes for the PWR nozzle nozzle supports, piping supports, 'reactorreactor coolant pump supports and heat exchanger exchanger supports supports

  • include sliding steel surfaces. Item Numbers 3.5.1-52 3.5.1-52 and 3.5.1-54 3.5.1-54 areare applicable and address these items and the ASME Section XI, Xl, Subsection IWF program is used to manage manage for Loss of Mechanical Mechanical Function/Corrosion, Function/Corrosion, Distortion, Dirt, Overload, Fatigue due to Vibratory and Cyclic Thermal Loads Distortion, Loads for these sliding and pinned surfaces. The ASME Section XI, Subsection Subsection IWF program described in Appendix B.

program is described B.

3.5.2.2.2.2 Aging Management 3.5.2.2.2.2 Management of Inaccessible Inaccessible Areas Areas 1.

1. Loss of material (spalling,scaling) material (spalling, scaling) and and cracking cracking due to freeze-thaw could occur in below-grade occur below-grade inaccessible areasof concrete areas inaccessible concrete of Groups Groups 1-3, 5 and 7-9 structures. The GALL Report structures. Report recommends recommends further further evaluation evaluation of this this aging effect for inaccessible inaccessible areas areas of these these Groups structures for plants Groups of structures plants located located in moderate to severe weathering moderate to severe weathering conditions. conditions.

At Salem, structure Groups Groups 1, 3, and 5 structures structures are located in in a region where weathering conditions are considered severe severe as shown in ASTM C 33-90, Fig. 1. GALL structurestructure Groups 2, 7, 8, and 9 9dodo not exist at Salem. Group Group Containment internal 4 structures are Containment structures internal structures and are not exposed to freeze freeze thaw conditions. Concrete for Groups 1, 3, 3,' 4 and 5 structures designed in structures is designed accordance with ACI 318-63 and constructed in accordance accordance accordance with ACI 301-66.

Testing of concrete concrete materials is in accordance accordance with applicable ASTM standards as required by ACI. The Portland cement conforms to ASTM C 150, Type IIII and flyash was also used. Concrete aggregates conform Concrete aggregates conform to the the Salem Nuclear Generating Station, License Renewal License Renewal Application No. 1 and Unit No.2 Station, Unit No.1 Application No. 2 3.5-40 Page 3.5-40

  • requirements of ASTM C 33-66. The type and size of aggregate, slump, cement and additives cement selected additives have been established Neither calcium chloride-nor established to produce durable concrete.

chloride* nor any admixtures other chlorides, sulfides, or nitrates admixtures containing calcium chloride or nitrates were used. The aggregate The coarse aggregate selected and used on the Salem Project was quarried stone, crushed and graded to meet meet the detail specifications. The stone, commonly commonly known as as traprock, was a basic igneous rock consisting consisting of diabase diabase and basalt. The dry density density of the concrete concrete mixes used for construction construction exceeded exceeded 144 Ibsl lbs/ cu ft.

The flyash contains no calcium chloride to cause corrosion. corrosion. The 1970 edition edition Industries Year Book" states that concrete

. of "Concrete Industries concrete made with flyash is more resistant to weak acids and sulfates, which cause corrosion. corrosion. For structural structural concrete, the maximum maximum allowable concrete placed was 4 allowable slump for concrete inches. In In areas with closely spaced spaced reinforcing bars, the detail specification specification allowed allowed the use of a concrete concrete mix with a coarse aggregateaggregate of 3/8 inch and a maximum slump of 5 inches. For the reactor containment wall, in the area adjacent to the equipment adjacent equipment and personnel personnel hatches where additional reinforcing additional reinforcing steel was specified, a more plastic mix was designed for adequate concrete concrete placement. In In this case, the slump was increased to be between between 6 and 7 inches.

At Salem, except for the Service Service Water Intake Intake structure, structures structures were also designed deSigned to minimize minimize exposure to moisture moisture to minimize minimize water absorption, absorption,

. minimizing the potential for damage from freeze-thaw freeze-thaw conditions. The Service Service Water Water Intake structure structure is also used as a leading indicatorindicator for the condition of

  • inaccessible concrete for other inaccessible other structures. These measures measures provide concrete concrete with good freeze-thaw freeze-thaw resistance.

. As described described above, the design and constructionconstruction of the concrete concrete for Groups 1, 3, and 55 structures is in in accordance accordance with ACI Standards that preclude preclude significant loss of material (spallng, scaling) scaling) and cracking due to freeze-thaw.

The condition of exposedexposed above above grade concrete of Groups 1, 1, 3, and 5, structures are an indicator for inaccessible inaccessible concrete concrete and provides reasonable reasonable assurance that degradation of inaccessibleinaccessible structures structures will be detected detected before a loss of an intended intended function. Operating experience experience review has not identified significant loss of material and cracking of the accessible accessible Groups Groups 1, 3, and 5 structures concrete.

In the event inspection In inspection of above grade concrete concrete structures structures identify significant significant concrete degradation degradation due to freeze-thaw, correctivecorrective actions will be initiated initiated to evaluate the condition of inaccessible inaccessible portions of structures and determine determine if if excavation of concrete for inspection is warranted. warranted. Operating experience Operating experience significant signs of distress due to freeze-thaw review has not identified significant freeze-thaw of concrete components.

Therefore, loss of material (spalling, scaling), and cracking cracking due to freeze-thaw of inaccessible concrete are insignificant and require no aging management.

However, inaccessible inaccessible concrete concrete will be inspected if if excavated for any reason, as as. required by Salem Salem Structures Monitoring Monitoring Program, The B.2.,1.33. The Structures Monitoring Program is described Monitoring Program described in Appendix B. B.

  • Nuclear Generating Salem Nuclear License License Renewal Generating Station, Station, Unit No.1 Renewal Application Application No. 1 and No. 2 and Unit No.2 Page 3.5-41

Section Section 3 - Aging Management Review Results Management Review Results 2.

2. Cracking due to expansion Cracking expansion and and reaction aggregates could occur reaction with aggregates occur inin below-
  • grade inaccessible grade concrete areas inaccessibleconcrete areasfor Groups 1-5 and 7-9 structures.

for Groups structures.TheThe Report recommends GALL Report recommends further evaluation of inaccessible further evaluation areas of these inaccessible areas Groups of structures Groups concrete was not constructed structures if concrete accordancewith the constructed in accordance the recommendationsin ACI201.2R-77.

recommendations ACI 201.2R-77.

Number 3.5.1-27 is not applicable. At Salem, the concrete Item Number concrete portions portions of Groups 1, 3,4, 3, 4, and 5 Structures are designed in accordance accordance with ACI 318-63 and constructed accordance with ACI 301-66 using the same concrete constructed in accordance concrete specification and standards specification standards as the Containment Containment structure. Groups 2,7,8 2, 7, 8 and structures are not found at Salem. Aggregates 9 structures accordance Aggregates were tested in accordance Specification C 289-65 for potential reactivity. The Portland with ASTM Specification cement conforms to ASTM C 150, Type IIIIand fJyash flyash was also used The type type and size of aggregate, slump, cement and additives have been selected selected to produce durable durable concrete.

As described above, the concrete concrete for Groups 1, 3, 4 and 5 structures is designed and constructed to meet meet ACI and ASTM Standards. Thus, cracking cracking expansion and reaction due to expansion aggregates is not reaction with aggregates requires not. significant and requires no aging management. However, inaccessible concrete for Groups 1, 3, and inaccessible concrete 5 structures inspected for cracking due to any mechanism structures will be inspected mechanism if excavated if excavated for any reason, as requiredrequired by the Salem Structures Monitoring Program, Structures Monitoring Program, B.2.1.33. Group internal concrete Containment internal Group 4 Containment concrete structures structures are accessible accessible and inspected inspected by the Structures Monitoring Monitoring Program. The Structures Structures

  • Monitoring Program Monitoring described in Appendix B.

Program is described B.

3.

3. Cracks Cracks and and distortion increasedstress distortion due to increased settlement and stress levels from settlement reduction of foundation reduction foundation strength, cracking, and strength, cracking, differentialsettlement due to and differential porous concrete erosion of porous erosion concrete subfoundations subfoundationscould occur below-grade occur in below-grade inaccessibleconcrete inaccessible areasof Groups concrete areas Groups 1-3,1-3, 5 and structures. The existing and 7-9 structures.

program relies on Structures program relies Structures Monitoring Monitoring Program manage these aging Program to manage effects. Some plantsplants may rely on a de-watering de-watering system to lower the site ground water ground water level. If the plant's credits a de-watering plant's CLB credits de-watering system, the GALL GALL recommends verification Report recommends Report verification of the continued continued functionality functionality of the de-de-watering system during watering during the period operation. The GALL period of extended operation. GALL Report Report recommends no further recommends furtherevaluation evaluation if this activity is included this activity included in the scope of the applicant'sStructures applicant's Structures Monitoring Program.

Monitoring Program.

structure Groups 1, 3, 4, and 5 are potentially subject At Salem, structure subject to cracks and distortion due to increased settlement. However, the aging increased stress levels from settlement. aging effect/mechanism is not significant. Salem design does not employ a de-effect/mechanism watering system to control settlement settlement and does not include porous concrete concrete subfoundation. Structures subfoundation. foundation is founded on soil or the Structures whose foundation the Formation are.

Vincentown Formation are subject to cracks and distortion due to increased stress levels from settlement. The foundation of the Class 1 station structures structures established directly are established directly on the Vincetown Formation or upon lean concrete Vincetown Formation concrete fill extending to this Formation.

Formation. This This formation provides excellent foundation provides excellent support for Salem Generating Generating Station structures. MeasurementsMeasurements made made construction and during initial operation throughout plant construction maximum indicated a maximum operation indicated Salem Nuclear Generating Station, Unit No.1 Nuclear Generating License Renewal License Application Renewal Application No. 1 and and Unit Unit No.

No.22 Page 3.5-42

  • settlement of approximately settlement the accessible approximately 0.5 inch which is not significant. The condition of accessible and above grade concrete condition condition of the inaccessible reasonable assurance that degradation detected detected before concrete are used as an indicator for the inaccessible and below grade concrete concrete and provides inaccessible structures degradation of inaccessible before a loss of an intended function. In provides structures will be the be In the unlikely event of crackscracks and distortion distortion due to settlement occurring in below grade settlement occurring inaccessible grade or inaccessible concrete, they would propagatepropagate into the above grade or accessible concrete accessible concrete areas, and corrective corrective actions will be initiated to evaluate the condition of inaccessible portions of structures structures and determine determine if ifexcavation excavation of concrete for inspection is warranted. Salem has not experienced experienced crackscracks and distortion due distortion due to increased increased stress levels from settlement Inaccessible concrete settlement of structures. Inaccessible concrete for Groups Groups 1, 3 and 5 structures structures will be inspected for crackingcracking and distortion distortion due to settlement settlement if if excavated excavated for any reason, as required required by the Salem Monitoring Program, B.2.1.33.

Structures Monitoring Certain group 3 structures are founded on concrete concrete piles, which are encased in steel; other group 3 structures are founded on soil. For those structures in structures founded on soil or the Vincentown formation, cracks and distortion due to increased stress levels from settlement are are applicable applicable and will be monitored, monitored, as described described above, by the Structures Structures Monitoring Program. For those group 3 structures structures founded on concrete piles encased encased in steel, cracks and distortion due to increased increased stress levels from settlementsettlement are not applicable.

applicable.

Degradation of piles or foundation mats will manifest Degradation manifest in settlement distortion distortion or cracking, and accessible accessible concrete concrete examinations examinations will detectdetect cracks and and

  • distortion of Groups 1, 1, 3, 4 and 5 structures. Studies have shown that steel steel piles driven into undisturbed undisturbed natural natural soil are not appreciably appreciably affected by corrosion due to the oxygen deficiency in soil at a few feet below grade. Piles Piles driven into disturbed disturbed soil, have been shown to experience experience only minor to moderate corrosion.

moderate corrosion. In In either case the observed observed loss of material due to corrosion was not considered significant significant enough enough to impact the intended function of of the the piles, piles, which is consistent NUREG-1557.

consistent with NUREG-1557.

The Groups Groups 1, 1, 3, 3, 4, and and 5 structures are monitored monitored under the Structures Structures Monitoring Program Monitoring Program for cracks and distortion due to increased stress levels levels from settlement settlement and a de-watering de-watering system is not used, thus further evaluation is not necessary.

is necessary .

Item Number

. Item Number 3.5.1-29 3.5.1-29 is not applicable to Salem structures porous structures as porous concrete concrete subfoundations subfoundations were not used for any Salem structures structures and the the Salem design does not employ a de-watering de-watering system to control settlement.

The Structures The Structures Monitoring Monitoring Program Program is is described described in Appendix B.

in Appendix B.

4.

4. Increase in Increase in porosity porosity andandpermeability, permeability, cracking, loss of material cracking, loss material(spalling, (spalling, scaling)due to aggressive scaling) aggressive chemical attack; and cracking, chemical attack; cracking, loss loss of bond, bond, and loss loss of material(spalling, of material (spalling,scaling) scaling)due to corrosion corrosion of embedded steel could occur in below-grade occur below-grade inaccessible inaccessibleconcrete areas Groups 1-3, 5 and areas of Groups and 7-9 structures. The GALL structures. GALL Report recommends further evaluation of plant-specific further evaluation plant-specific programs programs to to manage manage these aging effects these aging effects in inaccessible inaccessible areas areas of these
  • Salem Salem Nuclear Nuclear Generating License Renewal Station, Unit Generating Station, Renewal Application Application Unit No.1 and Unit No. 1 and Unit No.2 No. 2 Page 3.5-43 3.5-43

Section Section 3 - Aging Management Management Review Review Results Groups of structures Groups structures if the environment is aggressive.

aggressive. The acceptance acceptancecriteria criteria

  • are described are describedin in Branch Branch Technical Technical Position Position RLSB-1.

The Structures Monitoring Monitoring Program, B.2.1.33, will be used to monitor monitor below grade portions of the Group 1, 3 and 5 structures.

For Group 1, 3 and 5 structures at Salem, inaccessible below-grade below-grade reinforced reinforced concrete concrete is subject to an aggressive Groundwater was sampled aggressive environment. Groundwater and tested in in 2008 and 2009. Test results revealed that pH values meet the the limits to be considered considered a non-aggressive non-aggressive environment, environment, (Le.,(i.e., pH > 5.5). The The test results for sulfates were variable across the site and between test periods, with test results indicating indicating a non-aggressive non-aggressive environment due to sulfates, (i.e., (Le.,

sulfates level <1500 ppm). The test results for chlorides were variable across across the site, with some results indicatingindicating an aggressive aggressive environment environment due to chlorides chlorides (chloride test results between between 7 to 4800 ppm), where limits consist of a chloride level < 500 ppm, indicating non-aggressive environment. The indicating a non-aggressive The ground water and river water are, therefore, considered aggressive therefore, considered aggressive environments environments due to chloride levels.

The leakage of the spent fuel pools in the Fuel Handling Handling Building has resulted in detectable detectable levels of borated water in the seismic gap between between the Auxiliary Auxiliary Building and the Containment Containment Structure. The effect effect of the borated water on inaccessible areas of concrete is bounded the inaccessible bounded by the effects effects of the borated water on the accessible areas of the Fuel Handling Handling Building. During the the investigative phase of the spent fuel pool liner leakage investigative leakage in the Fuel Handling Handling Buildings, Salem conducted a plant specific concrete concrete test immersed in borated

  • water for up to 39 months. Salem, in in-collaboration collaboration with EPRI, also conducted additional tests on concrete concrete samples, obtained from another plant, with longer term exposure exposure to borated water. The results of the tests were used to analyze analyze the impact of potential continuous spent fuel pool concrete exposure exposure to borated water leakage. The analyses show that the effects of borated water on the reinforced concrete concrete and structural margin margin is not significant significant and have no no impact on structural structural integrity integrity of the spent fuel pool or the Fuel Handing Handing Building through the period of extended extended operation.

At Salem, the Group 1, 3, and 5 structures are designed designed in accordance accordance with ACI 318-63 and constructed constructed in accordance accordance with ACI 301-66. The Portland Portland cement conforms conforms to ASTM C 150, Type IIIIand flyash was also used. Concrete Concrete aggregates conform conform to the requirements requirements of ASTM C 33-66. Neither calcium calcium chloride nor any admixtures containing containing calcium calcium chloride or other chlorides, sulfides, or nitrates were used. used. Aggregates Aggregates were tested in accordance accordance with ASTM Specification Specification C-289-65 C-289-65 for potential reactivity and were also tested in accordance with ASTM Specifications C 29-60, C 40-66, C 127-59, C 128-59, accordance 128-59, and C 88-63. The coarse aggregate aggregate selected selected and used on the Salem Project was quarried stone, crushed crushed and graded to meet the detail specifications.

specifications. The The stone, commonly known as traprock, was a basic igneous rock consisting consisting of diabase and basalt.

The dry density of the concrete mixes used for construction construction exceeded exceeded 144 lbs/

144 Ibsl cu ft. The flyash contains no calcium chloride chloride to cause corrosion. The 1970 Salem Nuclear Generating License No. 1 and Generating Station, Unit No.1 License Renewal Renewal Application Application No. 2 and Unit No.2 Page Page 3.5-44

  • edition of "Concrete Industries Year Book" states that concrete made with flyash is more resistant to weak acids and sulfates, which cause corrosion. For structural concrete, the maximum inches. In maximum allowable slump for concrete concrete placed was 4 In areas with closely spaced reinforcing bars, the detail specification allowed the use of a concrete concrete mix with a coarse coarse aggregate specification aggregate of 3/8 inch and a maximum slump of 5 inches. For the reaCtor maximum reactor containment containment wall, in the area adjacent to the equipment and personnel personnel hatches where additional reinforcingreinforcing steel was specified, a more plastic mix was designed for adequate adequate concrete concrete placement. In In this case, the slump was increased increased to be between between 6 and 7 inches. At Salem, except for the Service Water Intake structure, structures structures were also designed to minimize exposure exposure to moisture moisture to minimize water absorption. The type and size of aggregate, slump, cement and additives additives have been established established to produce produce durable durable concrete.

concrete. Degradation concrete Degradation of concrete due to cracking, cracking, loss of bond, and loss of material due to corrosion of embedded steel has not been experienced experienced at Salem.

Monitoring Program The Structures Monitoring includes inspection Program includes inspection of concrete to detect indications of increase indications increase in porosity porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack; attack; and cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion bond,and corrosion of embedded Exposed portions of below grade concrete will be examined by the steel. Exposed the Structures Monitoring Structures Monitoring Program when excavated for any reason, and groundwater chemistry will also be monitored periodically in accordance groundwater accordance with the Structures Monitoring Program. Also the enhanced Structures Monitoring periodic inspections enhanced periodic inspections of

  • the submerged submerged portions of the intake structure structure will be used as indicators indicators for the condition of below-grade below-grade structures. Due to ground ground water chemistry being bounded by river water chemistry, the use of submerged bounded submerged structures structures as a leading indicator indicator for the potential degradation degradation below-grade below-grade structures provides structures provides reasonable assurance that degradation reasonable assurance degradation of inaccessible inaccessible structures will be be detected before a loss of an intended detected intended function.

function. InIn the event inspection of submerged structures identify submerged identify significant concrete degradations degradations at the ServiceService Water Intake Structure, correctivecorrective actions actions will be initiated to evaluate evaluate thethe condition of inaccessible inaccessible portions of the Groups 1, 33 and 5 structures and

. determine if excavation of concrete for inspection is warranted. Operating if excavation Operating experience review has not identified significantsigns experience significant signs of distress due to chemical attack or corrosion aggressive chemical corrosion of embedded embedded steel of submerged submerged concrete components.

Due to the aggressive aggressive groundwater, increase increase in porosity porosity and permeability, permeability, cracking, loss of material material (spalling, scaling) due to aggressive aggressive chemical chemical attack; cracking, loss of bond, and loss of material and cracking, material (spalling, scaling) due to corrosion of embedded embedded steel could occur in in below-grade below-grade inaccessible inaccessible concrete. These aging effects will be monitored for submerged submerged reinforced reinforced concrete components and used used as a leading leading indicator indicator for the potential degradation to below-grade below-grade structures. If Ifthe aging effects effects are significant for submerged structures, corrective submerged corrective actions will be initiated to evaluate inaccessible concrete inaccessible concrete and determine determine ififexcavation excavation to expose and inspect the the concrete is warranted. In In addition addition Salem will inspect inaccessible reinforced inspect inaccessible reinforced concrete if if excavated excavated for any reason, and monitor groundwater groundwater chemistry periodically as required by the Structures Monitoring periodically Monitoring Program. The enhanced enhanced

  • Salem Nuclear License Nuclear Generating Generating Station, Unit No.1 Renewal Application License Renewal Application No. 1 and Unit No.2 No. 2 Page 3.5-45 3.5-45

Section 3 - Aging Management Management Review Results program will require periodic sampling, testing, and analysis of ground chemistry for pH, chlorides, and sulfates, and assessing its impact on inaccessible, inaccessible, below grade concrete Program Program is described concrete structures. The Structures described in Appendix B. B.

ground water Monitoring Structures Monitoring water

  • 5.
5. Increase in in porosity and permeability, porosity and permeability, and loss of strength strength due to leaching leaching of calcium calcium hydroxide could occur below-grade inaccessible occur in below-grade inaccessibleconcrete areas of concrete areas of Groups Groups 1-3, 5 and 7-9 structures.

structures. The GALLGALL Report recommends further evaluation of this evaluation aging effect for inaccessible this aging areas of these inaccessible areas Groups of these Groups structuresif concrete structures concrete was not constructed accordancewith the constructed in accordance recommendationsin ACI recommendations 201.2R-77.

ACI201.2R-77.

Leaching of calcium hydroxide is applicable Leaching applicable for a flowing water environment environment which may occur to a limited extent extent in accessible or inaccessible inaccessible portions of Groups 1, 3, 4, and 5 structures..

structures. . Operating experience at Salem has found Operating experience that increase increase in porosity and permeability, permeability, and loss of strength due to leaching leaching of calcium calcium hydroxide, is not significant significant and is adequately managed by the the Structures Monitoring Program, B.2.1.33. .

Inaccessible portions of the Group 5 structures may be subject to leaching Inaccessible leaching of calcium hydroxide hydroxide due to the known leakage leakage of the borated borated water from thethe spent fuel pools. Salem conducted plant specific concrete concrete test immersed in immersed borated water for up to 39 months. Salem, in collaboration with EPRI, EPRI, also

  • conducted additional tests on concrete conducted concrete samples, obtained from another plant,

. with longer term exposure to borated borated water. The results of the tests were used to analyze the impact of potential continuous spent fuel pool concrete concrete borated water leakage. The analyses exposure to borated analyses show that the effects of borated water on the reinforced reinforced concrete concrete and structural structural margin is not significant and have no impact impact on structural structural integrity of the spent fuel pool or the Fuel Handing Building through the period of extended operation.

In 2006, an inspection In inspection was conducted conducted in accordance accordance with ACI 349 to assess assess the structural structural condition of the spent fuel pool and the Fuel Handling Building.

inspections identified no Significant The inspections significant degradations degradations or areas of structural distress. A similar similar inspection was conducted conducted in 2009 to determine if if any changes have have occurred since the 2006 inspection with no significant significant changes changes noted.

During the investigative investigative phase of the spent fuel pool liner leakage, it was was determined that leakageleakage through small cracks. cracks, in the stainless steel liner seam and plug welds did not drain properly because because of clogged drains. As a result, water water pressure behind the liner increased increased and forced borated water through through small cracks in concrete concrete and in the small gap between between the liner and concrete.

Maintenance activities Maintenance activities were established to ensure the leak-chase leak-chase system drains are cleared cleared to allow drainage drainage of the leakage. These activities activities will continue through the period of extended continue extended operation. This reduces amount of concrete exposed to borated water and ensures that the analysis analysis performed to determine determine the impact of the borated water on the reinforced concrete concrete remains bounding.

bounding. The Structures Monitoring Program, B.2.1.33, includes includes the the Salem Nudear License Nuclear Generating Station, Unit No.1 License Renewal Application No. 1 and Unit No.

No.22 3.5-46 Page 3.5-46

  • reinforced concrete trench that collects the borated water drainage from the reinforced concrete spent fuel pool tell tale drains. This is addressed for the accessible accessible trench concrete. Monitoring reinforced concrete degradation in the Group 5 inaccessible degradation addressed with Item Number Number 3.5.1-37 Monitoring the structural condition of the concrete trench provides an indicationindication of the actual inaccessible areas, due to exposure concrete actual concrete exposure to borated the the water and provides reasonablereasonable assurance that degradation of inaccessible inaccessible structures structures will be detected detected before a loss of an intendedintended function. In In the event event inspection inspection of the concrete trench identifies identifies significant concrete degradation, degradation, corrective actions will be initiated to evaluate corrective evaluate the condition of inaccessible inaccessible portions of the Groups 5 structure exposed to borated structure potentially exposed borated water leakage and determine determine ifif excavation excavation of concrete for inspection warranted.

inspection is warranted.

At Salem, the Portland cement conforms to ASTM C 150, 150, Type II II and flyash flyash was also used. The use of Type IIII cement and flyash results in concrete concrete resistant leaching of calcium hydroxide. Concrete is designed designed in accordance accordance with ACI 318-63 and constructedconstructed in accordance accordance with ACI 301-66. Aggregates Aggregates were tested in accordance with ASTM Specification Specification C C 289-65 for potential reactivity. The type and size of aggregate, slump, cement and additives additives havehave been established established to produce produce durable concrete.

Salem will continue periodic periodic groundwater groundwater testing and will examine examine exposed portions of the below-grade below-grade concrete, when excavated excavated for any reason in in accordance accordance with the Structures Monitoring Monitoring Program. The Structures Structures Monitoring Program is described described in Appendix B. B.

  • 3.5.2.2.2.3 Reduction of Strength and Modulus of Concrete Structures 3.5.2.2.2.3 Reduction Temperature Temperature Reduction of strength occur occur in strength and in PWR and BWR that exceed specified and modulus of concrete BWR Group Group 1-5 concrete specified temperature temperaturelimits, concrete structures.

Structures due to Elevated concrete due to elevated elevated temperatures structures. For furtherevaluations limits, further temperaturescould For any concrete evaluations are concrete elements are recommended.

recommended.

Appendix A A of ACI 349-85 specifies AC1349-85 specifies the concrete concrete temperature temperature limits limits for normal normal operation operation or any other other long-term period.

period. The temperatures temperaturesshall not exceed 150°F 150°F except for for local areas, areas,which are are allowed allowed to have increased increasedtemperatures temperaturesnot to exceed 200 0 F. The GALL Report recommends further 200°F. The GALL evaluation of a plant-specific further evaluation plant-specific program program if any any portion portion of the safety-related safety-relatedand otherotherconcrete concrete structures structuresexceeds specified temperature specified temperaturelimits, limits, i.e., general area temperature general area temperaturegreatergreater than 66°C 66 0 C (150*F)

(150°F) and and local local area area temperature temperaturegreater greater than 93°C 93°C (200°F).

(200°F). The acceptance acceptance criteriaare criteria are described described in Branch Branch Technical Technical Position PositionRLSB-1.

RLSB-1.

Item Item Number 3.5.1-33 is not applicable Number 3.5.1-33 applicable to Salem. Group 2 structures structures are BWR specific. Group Group 1, 1, 3, 4, and 5 concrete concrete structures structures are not subject to general general area area temperature greater temperature greater than 150°F.1500F.

Group 1 structures (Control Room Area) and Group 3 structures, which include include areas within the Environmental Environmental Qualification Qualification program, are exposed to indoor conditioned air temperatures temperatures not greater than 120°F 120°F during normal operation.

operation.

Group 44 structures Group structures are exposed to air temperature temperature inside the Containment Containment Structure. The Technical Specification Technical Specification and UFSAR limit the bulk air temperature

Unit No.1 No.22 Page 3.5-47 Page 3.5-47

Section Management Review Section 3 - Aging Management Review Results Results inside the building during normal plant operation maintained within the Technical temperature is maintained temperature 120 0 F. The bulk air operation to 120°F.

Technical Specification air through cooling coils and by forced air through the reactor shield and reactor nozzle support areas.

air Specification limits by recirculating recirculating

  • Group 3 structures, which include Group include areas not within the Environmental Qualification Environmental Qualification program, and Group Group 5 structures (Fuel (Fuel Handling structures with Handling Building) are structures limited heat sources. Therefore, normal temperatures temperatures are less than 150°F. 1500 F.

Group 1, 3, 4 and 5 concreteconcrete structures are not subject to local temperature temperature greater greater 200 0 F. Penetration seal technology is designed to prevent surrounding concrete 200°F. technology designed surrounding concrete exceeding 200°F (Penetration from exceeding (Penetration Seal Specification).

Specification).

experience has not identified elevated local temperature Plant operating experience temperature as a concern concern for the Group 1, 3, 4 and 5 concrete concrete structures.

3.5.2.2.2.4 Aging Management 3.5.2.2.2.4 Inaccessible Areas for Group 6 Structures Management of Inaccessible Structures The GALL Report Report recommends recommends further further evaluation inaccessibleareas evaluation for inaccessible areas of certain certain Group 6 structure/aging Group structure/agingeffecteffect combinations identified below, combinations as identified below, whether or not they are inspections in accordance are covered by inspections accordancewith the GALL Report, Report, Chapter ChapterXl. S7, XI. S7, "RegulatoryGuide 1.127, "Regulatory 1.127, Inspection Water-ControlStructures Inspection of Water-Control Associated with Structures Associated Nuclear Power Nuclear Plants"or the FERC Power Plants" FERC / US Army Army Corp Engineers dam inspections Corp of Engineers inspections and maintenance.

maintenance.

1.

1. Increase Increase in porosity permeability,cracking, porosity and permeability, loss of material cracking, loss (spalling, material (spalling,
  • scaling)! aggressive scaling)/ chemical attack; aggressive chemical and cracking, attack; and loss of bond, cracking, loss and loss bond, and loss of (spalling,scaling)!

material(spalling, material corrosion of embedded steel could occur scaling)/ corrosion occur in below-inaccessibleconcrete grade inaccessible grade concrete areasareasof Group structures. The GALL Group 6 structures. GALL Report recommends further recommends plant-specific programs evaluation of plant-specific further evaluation programs to manage manage these inaccessibleareas aging effects in inaccessible aging areas if the environment environment is is aggressive.

aggressive. TheThe criteriaare acceptance criteria acceptance are described described in Branch Technical Position Branch Technical Position RLSB-1.

At Salem the RG 1.127, Inspections of Water-Control Water-Control Structures Associated Associated with Nuclear Power Plants, B.2.1.34, aging management management program is implemented through the Structures.

implemented Monitoring Program, B.2.1.33, which will Structures Monitoring manage cracking, loss of bond, and loss of material due to be used to manage embedded steel in corrosion of embedded accessible above grade and submerged in accessible submerged areasareas of water-control structures (Group 6 structures).

water-control structures inaccessible areas follows:

Evaluation of inaccessible Inaccessible areas Inaccessible areas of Group structures which are below-grade are monitored Group 6 structures using the Structures Monitoring Monitoring Program because groundwater water because the groundwater water environment environment is aggressive.

Underground, reinforced Underground, concrete structures and structures in contact with reinforced concrete river water (raw water) are subject to an aggressive aggressive environment.

Groundwater was sampled and tested in 2008 and 2009. Test results Groundwater results revealed that pH values values meet the limits to be considered a non-aggressive non-aggressive Salem Nuclear Nuclear Generating Renewal Application License Renewal Application No.11 and Unit No.2 Generating Station, Unit No. No. 2 Page 3.5-48

  • environment, (Le.,

environment (i.e., pH > 5.5). The test results for sulfates were variable the site and between test periods, with test results indicating a non-aggressive environment due to sulfates, (i.e.,

groundwater test results for chlorides groundwater (Le., sulfates sulfates level <1500 ppm). The chlorides were variable across variable across non-aggressive The across the site, with some results indicating an aggressive environment due to chlorides (chloride test some results between 7 to 4800 ppm), where limits consist of a chloride level level < 500 500 ppm, indicating indicating a non-aggressive non-aggressive environment. River water chloride content is also variable and ranges from 10000 10000 to 15000 15000 ppm. The ground water and river water are, therefore, considered aggressive aggressive environments environments due to chloride chloride levels. At Salem, the reinforced concrete concrete for Group 6 structures structures are designed in accordance in accordance with ACI 318-63 and constructed constructed in accordance accordance with ACI 301- 301-

66. The Portland cement conforms to ASTM C 150, Type IIII and flyash was was also used Concrete aggregates conform to the requirements Concrete aggregates requirements of ASTM C 33-
66. Neither calcium calcium chloride nor any admixtures admixtures containing calcium chloride chloride or other chlorides, sulfides, or nitrates nitrates were used. Aggregates Aggregates were tested in in accordance accordance with ASTM SpecificationSpecification C-289-65 C-289-65 for potential reactivity and and were also tested in accordance accordance with ASTM SpeCifications Specifications C 29-60, C 40-66, C 127-59, C 128-59, 128-59, and C 88-63. The coarse aggregate aggregate selected and used on the Salem Project was quarried quarried stone,crushed stone,crushed and gradedgraded to meet the detail specifications.

specifications. The stone, commonly commonly known as traprock, was a basic igneous igneous rock consisting of diabase diabase and basalt. The dry density of the concrete concrete mixes mixes used for construction exceededexceeded 144 Ibsl Ibs/ cu ft. The flyash contains no calcium calcium chloride chloride to cause corrosion. The 1970 1970 edition of "Concrete Industries Year Book" states that concrete concrete made with flyash is more resistant to weak acids acids

  • and sulfates, which cause cause corrosion. For structural concrete, the maximum maximum allowable allowable slump for concreteconcrete placed placed was 4 inches. In areas with closely In areas spaced reinforcing bars, the detail specification spaced reinforcing specification allowed allowed the use of a concrete concrete mix with a coarse coarse aggregate aggregate of 3/8 inch and a maximum slump of 5 inches.

The type and size of aggregate, slump, cement cement and additives additives have have been established established to produce durable concrete.

Exposed portions of below grade Exposed grade concrete will be examined by the StructuresStructures Monitoring Program Monitoring Program when excavatedexcavated for any reason and groundwater groundwater chemistry will be monitored periodically periodically in in accordance accordance with the Structures Structures Monitoring Program. Also the enhanced periodic periodic inspections of the the submerged portions of the intake structure will be used as indicators for the the condition of below-grade below-grade portion of the structures. Because Because ground water chemistry is bounded by river water chemistry, the use of submerged structures as a leading indicatorindicator for the potential degradation below-grade potential degradation below-grade structures provides provides reasonable reasonable assurance degradation of inaccessible assurance that degradation inaccessible structures will be detected before a loss of an intended function. In In the event event inspection of submerged submerged structures structures identify significant significant concrete concrete degradations degradations at the Service Service Water Intake Structure, corrective corrective actions will be initiated to evaluate the condition of inaccessible inaccessible below grade grade portions of the Group 6 structures and determine if excavation determine if excavation of concrete concrete for inspection inspection is warranted.

Operating experience experience review has not identified significant signs of distress due due aggressive chemical to aggressive chemical attack or corrosion of embeddedembedded steel of submerged concrete components.

  • Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.

Renewal Application License Renewal Application No.11 and Unit No.2 No. 2 Page 3.5-49 3.5-49

Section 3 - Aging Management Management Review Results Therefore, increase Therefore, (spalling, steel could occur in below-grade permeability, cracking, loss of material increase in porosity and permeability, (spalling, scaling) due to aggressive aggressive chemical bond, and loss of material (spailing, chemical attack; attack; and cracking, loss of (spalling, scaling) due to corrosion of embedded below-grade inaccessible concrete. These aging effects effects

  • monitored for submerged will be monitored submerged reinforced reinforced concrete concrete components and used as as a leading indicator for the potential degradation below-grade structures degradation to below-grade structures.... If If the aging effects are significant significant for submerged structures, corrective corrective actions actions will be initiated initiated to evaluate inaccessible concrete and determine evaluate inaccessible determine if excavation to expose and inspect inspect the concrete concrete is warranted.

warranted. In In addition Salem will inspect inspect inaccessible inaccessible reinforced concrete concrete ififexcavated excavated for any reason, and monitor monitor groundwater groundwater chemistry periodically periodically as required by the Structures Structures Monitoring Monitoring Program. The enhanced enhanced program will require periodic periodic sampling, testing, and analysis of ground water chemistry chemistry for pH,pH, chlorides, and sulfates, and-assessing and assessing its impact on buried structures. The RG 1.127, Inspections Inspections of Water-Control Structures Water-Control Structures Associatedwith Associated with Nuclear Nuclear Power Power Plants, and Structures Structures Monitoring Programs described in Appendix Programs are described Appendix B. 8.

2.

2. Loss of material (spalling,scaling) material (spalling, scaling) and and cracking cracking due to freeze-thaw could occur in below-grade occur below-grade inaccessible concrete areas inaccessible concrete areasof Group Group 6 structures.

structures. The GALL Report recommends GALL Report recommends further furtherevaluation evaluation of this this aging aging effect for inaccessibleareas inaccessible areasfor for plants located in moderate>

plants located moderate,to severe weathering weathering conditions.

conditions.

At Salem, the RG 1.127, Inspections with Nuclear Power Plants, B.2.1.34, Program, 8.2.1.33, Inspections of Water-Control B.2.1.33, will be used to manage cracking due to freeze-thaw and cracking structures (Group 6 structures).

structures Water-Control Structures Associated implemented by Structures Monitoring 8.2.1.34, as implemented Monitoring manage loss of material (spalling, scaling) freez~-thaw in accessible areas areas' of water-control

  • Evaluation Evaluation of inaccessible inaccessible areas areas follows:,

follows: .

Group 6 structures structures are located located in a region wherewhere weathering conditions are considered severe as shown inASTM considered in ASTM C 33-90, Fig. 1.

Operating Operating experience experience review has not identified significant loss of material and and cracking of reinforced concrete concrete in Group Group 6 structures. Concrete for Group 6 structures is designed in accordanceaccordance with ACI 318-63 and constructed in in accordance accordance with ACI 301-66. Testing of concrete concrete materials materials is in accordance accordance with applicable ASTM standards as required by ACI. ACL The Portland cement conforms to ASTM C 150, Type II II and flyash was also used Concrete Concrete aggregates conform to the requirements aggregates requirements of ASTM C 33-:66. 33-66. The type and size size of aggregate, slump, cement and additives have been established produce established to produce durable concrete. Neither calcium chloride nor any admixtures containing durable containing calcium chloride or other chlorides, sulfides, or nitrates nitrates were used. The The aggregate selected and used on the Salem Project was quarried stone, coarse aggregate crushed and graded to meet the detail detail specifications.

specifications. The stone, commonly known as traprock, was a basic igneous rock consisting of diabase and basalt.

The dry density of the concrete mixes used for construction exceeded 144 lbs/

construction exceeded Ibs/

Salem Nuclear License Nuclear Generating Station, License Renewal Renewal Application No. 1 and Unit No.2 Station, Unit No.1 Application No. 2 Page 3.5-50

  • cu ft. The flyash fJyash contains no calcium chloride structural concrete, the maximum inches. In chloride to cause corrosion. The 1970 edition of "Concrete Industries Year Book" states that concrete made flyash fJyash is more resistant to weak acids and sulfates, which cause corrosion. For maximum allowable slump for concrete In areas with closely spa~ed spaced reinforcing made with concrete placed 1970 placed was 4 reinforcing bars, the detail specification specification allowed the use of a concreteconcrete mix with a coarse coarse aggregate aggregate of 3/8 inch and a maximum slump of 5 inches. These measures measures provide provide concrete with good freeze-thaw freeze-thaw resistance.

The design and construction construction of the concrete concrete for Groups 6 structures is in in accordance with ACI Standards that preclude accordance preclude significant loss of material (spallng, scaling) and cracking due to freeze-thaw. The condition condition of exposed above grade and submerged concrete of Groups 6 structures are an indicator submerged concrete indicator for inaccessible inaccessible concrete concrete and provides reasonable reasonable assurance assurance thatthat degradation degradation of inaccessible structures will be detected before before a loss of an intended function. Operating experience experience review has not identified significant loss of material and cracking of the accessible concrete for Groups 6 structures.

accessible concrete In the event inspection In inspection of above grade concrete structures or submerged concrete structures significant concrete degradation structures identify significant degradation due to freeze-thaw, corrective actions will be initiated initiated to evaluate evaluate the condition inaccessible condition of inaccessible below grade portions of Group Group 6 structures and determine determine ififexcavation excavation of concrete for concrete inspection is for inspection is warranted.

warranted. Operating Operating experience experience review review has not identified significant significant signs of distress due to freeze-thaw freeze-thaw of Group 6 structure structure

  • concrete components.

Therefore, loss of material (spalling, scaling) and cracking cracking due to freeze-thaw freeze-thaw inaccessible concrete are insignificant and require of inaccessible require no aging management.

However, inaccessible inaccessible concrete concrete will be inspected if ifexcavated excavated for any reason, as required by Structures Structures Monitoring Program. The RG 1.127, 1.127, Inspections Inspections of Water-Control Structures Structures Associated Associated with Nuclear Power Power Plants and Monitoring Programs are described Structures Monitoring Appendix B.

described in Appendix B.

3. Cracking Cracking due to expansion expansion and and reaction aggregatesand reaction with aggregates and increase increasein porosity porosity and permeability, permeability, and and loss of strength strength due to leaching leaching of calcium calcium hydroxide could hydroxide could occur in below-grade below-grade inaccessible inaccessiblereinforced reinforced concrete concrete areas areas Group 6 structures.

of Group structures. The GALL GALL Report recommends recommends furtherfurther evaluation evaluation of inaccessibleareas inaccessible areas if concrete concrete was not constructed accordancewith the constructed in accordance recommendationsin ACI recommendations 201.2R-77.

ACI201.2R-77.

Item Number Number 3.5.1-36 is not applicableapplicable for both accessible and inaccessible inaccessible areas. Cracking due to expansion and reaction with aggregates aggregates has not been experienced at Salem. Concrete aggregates aggregates have been tested and the the

. concrete was designed to preclude expansion expansion and reaction with aggregates.

Aggregates were tested in accordance Specification C 289-65 for accordance with ASTM Specification potential reactivity.

Reinforced concrete Reinforced concrete for Group 6 structures is designed in accordance accordance with ACI 318-63 and constructed in accordance accordance with ACI 301-66. The Portland Portland

  • Nuclear Generating Station, Unit No.1 Salem Nudear License License Renewal Renewal Application Application No. 1 and No. 2 and Unit No.2 Page 3.5-51

Section Section 3 - Aging Management Management Review Review Results cement cement conforms conforms to ASTM C 150, Type IIII and flyash of Type IIII cement and f1yash flyash result in concrete and permeability, and loss of strength due to leaching Concrete Concrete aggregates aggregates also conform to the requirements f1yash was also used. The use concrete resistant increase in porosity resistant to increase leaching of calcium hydroxide.

requirements of ASTM C 33-66.

The type and size of aggregate, slump, cement and additives have have been

  • established established to produce produce durable concrete.

For Item Number Number 3.5.1-37 the RG 1.127, Inspections Inspections of Water-Control Structures Structures Associated Associated with NuclearNuclear Power Plants, B.2.1.34, as implemented implemented by the Structures Monitoring Program, Structures Monitoring Program, B.2.1.33, will be used to manage manage cracking and increase cracking increase in porosity porosity and permeability, and loss of strength due to to leaching leaching of calcium hydroxide of reinforced reinforced concrete concrete in accessible accessible and inaccessible water-control structures inaccessible areas of water-control structures (Group 6 structures) subject subject to a flowing water environment. The RG 1: 1:127, 127, Inspections Inspections of Water-Control Structures Associated with Nuclear Power Plants program, and Structural Monitoring Monitoring Program are described described in Appendix B. B.

Evaluation Evaluation of inaccessible inaccessible areas areas follows:

Reinforced concrete for Group 6 structures Reinforced concrete structures is designed designed in in accordance accordance with ACI 318-63 and constructed in accordance accordance with ACI 301-66. The Portland cement conforms to ASTM C 150, Type IIII and flyash was also used. The use andflyash

. of Type IIII cement cement and flyashf1yash result in concrete resistant to increaseincrease in porosity and permeability, permeability, and loss of strength due to leaching of calcium hydroxide.

aggregates conform to the requirements Concrete aggregates requirements of ASTM C 33-66. The The concrete specification specification used to construct construct Group 6 structures structures is the same same

  • concrete specification specification used to construct construct the Containment Containment Structure. Neither Neither calcium chloride nor any admixtures containing containing calcium chloride or other chlorides, sulfides, or nitrates were used. Aggregates were tested in in accordance with ASTM Specification accordance Specification C ?89-65 289-65 for potential potential reactivity reactivity and were also tested in accordance accordance with ASTM Specifications C 29-60, C 40-66, C 127-128-59, and C 88-63. The coarse 59, C 128-59, coarse aggregate aggregate selected selected and used on the the Salem Project Project was quarried stone, crushed and graded to meet the detail specifications. The stone, commonly known as traprock, was a basic igneous igneous rock consisting of diabase diabase and basalt.

The dry dry density of the concrete mixes used for construction construction exceeded exceeded 144 lbs/

144 Ibsl cu ft. The f1yash flyash contains no calcium chloridechloride to cause corrosion. The 1970 1970 edition of "Concrete Industries Industries YearYear Book" states that concrete made made with flyash is more resistant to weak acids and sulfates, which cause corrosion. For f1yash structural concrete, the maximum allowable allowable slump for concrete placed was 4 concrete placed inches. InIn areas areas with closely spaced spaced reinforcing bars, the detail specification specification allowed the use of a concrete concrete mix with a coarse aggregateaggregate of 3/8 inch and a maximum slump of 5 inches. The type and size of aggregate, slump, cement and additives have have been established established to produce durable concrete.concrete.

Leaching is a potential aging mechanism Leaching mechanism applicable to submerged portions of Group 6 structures structures exposed to flowing water. However, these areas are accessible for underwater underwater inspection inspection and for inspections inspections when dewatered.

dewatered.

The enhanced periodic inspections enhanced periodic inspections of the submerged submerged portions portions of the intake intake structure of the Structures Structures Monitoring Program, B.2.1.33, will be used to a

Salem Nuclear Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 License Renewal Renewal Application Application No. 2 Page Page 3.5-52

  • manage this aging effect and mechanism. Leaching is also applicable manage inaccessible concrete which is buried as itit may be subject to a flowing water environment environment through cracks.

Operating experience at Salem has not identified Operating experience applicable to identified increase in porosity and permeability, and loss of strength due to leaching permeability, leaching of calcium hydroxide hydroxide for inaccessible below grade portions of Group inaccessible Group 6 structures as significant significant and this aging effect is managed by the RG 1.127, Inspections Inspections of Water-Control Structures Associated Associated with Nuclear Power Power Plants, B.2.1.34, 8.2.1.34, as implemented by the Structures Monitoring Program, 8.2.1.33. B.2.1.33. Inaccessible concrete will be Inaccessible concrete be inspected if if excavated for any reason, as required by the Structures Structures Monitoring Program. The Structures Structures Monitoring Monitoring Program is describeddescribed in in Appendix 8. B.

3.5.2.2.2.5 Cracking due to Stress Corrosion Cracking 3.5.2.2.2.5 Cracking and Loss of Material Material due to Pitting and Crevice Corrosion Corrosion Crackingdue to stress Cracking corrosioncracking stress corrosion cracking andand loss loss of material materialdue to pittingpitting and crevice corrosion crevice corrosion could occur occur for Group Group 7 andand 8 stainless stainless steel tank linersliners exposed standing water.

to standing water. The GALL GALL Report recommends recommends further further evaluation evaluation of plant-plant-specific programs specific programsto manage manage thesethese aging aging effects. The acceptance criteriaare acceptance criteria are describedin Branch described Technical Position Branch Technical Position RLSB-1.

Item Number Number 3.5.1-38 is not applicable. Salem does not have Group 7 and 8

  • stainless steel tank liners.

3.5.2.2.2.6 Aging of Supports Not Covered 3.5.2.2.2.6 Covered by Structures Monitoring Program The GALL ReportReport recommends recommends further furtherevaluation evaluation of certain certain component supportlagingeffect support/aging combinations if they are effect combinations are not covered by the Structures Structures Monitoring Program.

Monitoring Program. This includes includes (1) reduction reduction in concrete concrete anchor anchorcapacity capacity due to

. degradation degradation of the surrounding surroundingconcrete, concrete, for Groups Groups B 1-B5 supports; B1-B5 supports; (2) (2) loss loss of of material material due to general general and and pitting pitting corrosion, corrosion, forfor Groups Groups B2-B5 supports; supports; and and (3)

(3) reduction/loss reductionlloss of isolation isolation function function due to degradation degradationof vibration vibration isolation isolation elements, elements, for Group Group B4 supports.

supports.Further evaluation is Further evaluation is necessary necessaryonly for structure/agingeffect structure/aging effect combinations combinations not covered covered by the Structures Structures Monitoring Monitoring Program.

Program.

At Salem, (1) (1) reduction reduction in concrete anchor capacity due to degradation degradation of the the surrounding surrounding concrete, for Groups B B1-B5 1-85 supports, (2) loss of material for Groups Groups B2-B5 supports; 82-85 supports; and (3) reduction/loss reduction/loss of of isolation function due to degradation degradation of vibration isolation elements for Group 84 B4 supports are covered under the Structures Structures Monitoring Program, 8.2.1.33.B.2.1.33. Therefore Therefore further evaluation evaluation is not necessary. The The Structures Monitoring Monitoring Program is describeddescribed in in Appendix B. 8.

3.5.2.2.2.7 Cumulative Fatigue Damage 3.5.2.2.2.7 Damaqe due to Cyclic Loading Loading Fatigueof component Fatigue component supportsupport members, members, anchor bolts, and anchor bolts, and welds for GroupsGroups B 1.1,1. 1, B 1.2, B1.2, andand B1.3 component supports supports is a TLAA TLAA as defined in CFR 54.3 only if a 10 CFR CLB fatigue fatigue analysis analysis exists.

exists. TLAAs TLAAs are are required required to be evaluated evaluated in accordance accordancewith

  • Salem Nuclear Generating Station, Unit No.

License License Renewal Renewal Application Application No.11 and Unit No.2 No. 2 Page 3.5-53 3.5-53

Section 3 - Aging Management Management Review Results 4.3, CFR 54.21(c).

10 CFR Item Number 54.21(c). The evaluation 4.3, "Meta/Fatigue "MetalFatigueAnalysis,"

evaluation of this TLAA Analysis, " of NUREG-1800, Number 3.5.1-42 is not applicable TLAA is addressed addressedseparately NUREG- 1800, revision revision 1, separatelyin 11 the SRP-LR.

applicable to Salem. The Salem current basis contains no fatigue analysis for component SRP-LR.

in Section Section current licensing component supports members, anchor bolts, licensing

  • and welds of Groups B1.1, B1.1, B1.2, and B1.3 component supports. Therefore Therefore a TLAA is not evaluated evaluated in accordance accordance with 10 CFR 54.21(c) 54.21 (c) for these components.

components.

3.5.2.2.3 3.5.2.2.3 Quality Assurance for Aging Management Nonsafety-Related Components Management of Nonsafety-Related Components QA provisions applicable applicable to license renewal renewal are discussed discussed in in Section 8.1.3.

B.1.3.

3.5.2.3 Time-Limited Aging Analyses Time-Limited AgingAnalyses The time-limited aging analyses analyses identified identified below are associated associated with the Containment Containment Handling Building Structures:

and Fuel Handling

.* Section Section 4.5, Fuel Transfer Tube Bellows Design Cycles Cycles 3.

5.3 CONCLUSION

Containments, Structures, and Component The Containments, Component Supports that are subject subject to aging management management review have been identified accordance with the requirements identified in accordance requirements of 10 CFR 54.4.54.4.* The aging management management programs selected to manage aging effects programs selected the effects for the

  • Containments, Containments, Structures, and Component Supports identified in the summaries Supports are identified summaries in in Section 3.5.2.1 above.

description of these aging management A description management programsprograms is provided provided in Appendix B, S, along with the demonstration demonstration that the identified identified aging effects will be managedmanaged for the period of extended operation.

Therefore, based on the conclusions provided provided inin Appendix B, the effects of aging aging associated with the Containments, associated Containments, Structures and Component Supports Supports will be be adequately managed adequately managed so that there is reasonable assurance that the intended intended function(s) maintained consistent with the current licensing basis during the period of will be maintained extended operation.

Salem Nuclear Generating License Generating Station, Unit No.1 Renewal Application License Renewal No. 1 and Unit No.

No.2 2 Page 3.5-54

  • Review Results Results Table Table 3.5.1 Summary of Aging Management Evaluations for Structures and Component Supports Management Evaluations Effect/

Aging Effect! Aging Aging Further Item Component Component Management Management Evaluation Evaluation Discussion Discussion Number Mechanism Mechanism Programs Recommended Programs Recommended

_.

3.5.1-1 3.5.1-1 Concrete Aging of ISI (lWL) lSI (IWL) and for Yes, plant-specific, Consistent NUREG-1801. The ASME Section XI, Consistent with NUREG-1B01. xA, elements: accessible accessible and inaccessible if if the environment environment Subsection Subsection IWL, B.2.1.29, aging managementmanagement program walls, dome, inaccessible concrete, an is aggressive will be used to manage manage corrosion corrosion of embedded embedped steel of basemat, ring concrete concrete areas examination examination of the Containment Structure reinforced reinforced concrete concrete in in girder, due to representative representative accessible areas. Aggressive Aggressive chemical attack is not buttresses, aggressive aggressive samples of below- accessible areas applicable to accessible areas of the containment containment containment containment chemical grade concrete, because the environment is not aggressive in because in those (as applicable) applicable) attack, and and periodic Groundwater testing conducted in areas. Groundwater in 2008 200B and 20092009 corrosion of corrosion of monitoring monitoring ofof show that chloride show chloride contents exceed exceed the the threshold threshold limit limit of of embedded embedded groundwater, ififthe groundwater, the 500 ppm.

500 ppm. Thus the environment environment in in inaccessible inaccessible below steel steel environment is environment is grade environment grade environment is is aggressive. The Structures Structures non-aggressive. A non-aggressive. A Monitoring Program, B.2.1.33, Monitoring B.2.1.33, will be added to manage manage plant specific plant Containment Structure Containment Structure concrete aging effects concrete aging effects due to program is to be program aggressive chemical attack attack and corrosion of embedded evaluated ifif steel in in below grade areas.

environment is environment is See Subsection See Subsection 3.5.2.2.1.1.

3.5.2.2.1.1.

aggressive.

3.5.1-2 Concrete Concrete Cracks and Structures Yes, if if not within Consistent with NUREG-1B01.

NUREG-1801. The Structures Monitoring Monitoring elements; elements; All distortion due distortion Monitoring Monitoring the scope of the Program, B.2.1.33, will be used to manage cracks and to increased to increased Program. IfIfaa de-de- applicant's applicant's distortion due distortion due to to increased increased stress levels from from settlement settlement stress levels stress levels watering system watering system is is Structures for for the the Containment Structure reinforced Containment Structure reinforced concrete concrete in in the the from settlement from settlement relied upon relied upon for for Monitoring Monitoring inaccessible areas.

inaccessible areas. A A de-watering de-watering system system doesdoes not exist not exist control of Program or a de- for control control. of settlement settlement at Salem.

settlement, then watering system is For accessible For areas of accessible areas of the the Containment Containment Structure Structure that that the licensee is to relied upon. are potentially susceptible to cracks and distortion are potentially susceptible to cracks and distortion due to due to ensure proper increased stress levels from settlement, increased stress levels from settlement, The ASME The ASME functioning of the functioning Section Xl, Section Subsection IWL, XI, Subsection IWL, B.2.1.29, B.2.1.29, will will be be added added to to de-watering system manage the aging effect/mechanism.

manage the aging effecUmechanism. Inspections Inspections through the period conducted in conducted in accordance accordance with with the program will the program will detect detect of extended extended cracking in accessible areas regardless cracking in accessible areas regardless of the of the Salem Nuclear Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-55 3.5-55 License Renewal License Renewal Application Application

Section 3 - Aging Management Review Aging Management Review Results Results Table 3.5.1 3.5.1 Summary Summary of Aging Management Management Evaluations for Structures Structures and Component Component SupportsSupports Effect/

Aging Effect! Aging Aging Further Further Item Number Component Component Management Management Evaluation Evaluation Discussion Discussion Number Mechanism Mechanism Programs Recommended Programs Recommended operation. mechanism.

mechanism.

See Subsection Subsection 3.5.2.2.1.2.

3.5.2.2.1.2.

3.5.1-3 Concrete Concrete Reduction Reduction in in Structures Yes, ififnot within Not Applicable. This aging effect/mechanism effect/mechanism does not elements: foundation Monitoring Monitoring the scope of the apply to to the Containment Containment Structure concrete foundation foundation, foundation, strength, Program applicant's applicant's concrete is not incorporated as porous concrete incorporated into the design sub-foundation sub-foundation cracking, If a de-watering If a de-watering Structures Structures construction of the foundation. A and construction de-watering system A de-watering differential differential system system is relied is relied Monitoring Monitoring does not exist at Salem.

settlement due settlement upon for upon control of for control of Program Program or a de-to erosion of erosion of cement erosion of cement watering system is is porous porous from porous relied upon.

relied upon. Subsection 3.5.2.2.1.2 See Subsection 3.5.2.2.1.2 from porous concrete concrete concrete subfoundation subfoundation subfoundations, subfoundations, then the licensee is is to ensure proper functioning functioning of thethe de-watering system de-watering through the period of extended operation.

3.5.1-4 Concrete Reduction of Reduction A plant-specific A plant-specific Yes, plant-specific plant-specific Not Applicable. The reduction of strength and modulus modulus elements:

elements: strength and aging management management if temperature limits if temperature of concrete of concrete due due to to elevated elevated temperature temperature does not apply dome, wall, modulus of program is to be are exceeded. to the Containment Containment Structure concrete.

basemat, ring concrete due to evaluated The Containment Structure The Containment concrete is Structure concrete is not not exposed exposed to to girder, girder, elevated elevated general temperature greater than 150 degrees general temperature greater than 150 degrees F and F and buttresses, temperature local area local area temperature temperature greater greater than 200 degrees than 200 degrees F.F.

containment, containment, Technical Specification 3 14.6.1.5 Technical Specification /4.6.1.5 limits the average average airair concrete concrete fill-in temperature temperature inside the Containment inside the Containment during during normal normal plant plant annulus annulus (as operation to 120 degrees F. The bulk air temperature is operation to 120 degrees F. The bulk air temperature is applicable) applicable) maintained within the Technical Specification limits by maintained within the Technical Specification limits by recirculating air recirculating through cooling air through coils. Process cooling coils. Process Salem Nudear Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-56 License Renewal Application License

  • * *
  • Management Review Results Table 3.5.1 Summary Summary of Aging Management Management Evaluations for Structures Structures and Component Component Supports Supports Aging Effect/

Effect! Aging Aging Further Further Item Component Mechanism Management Management Evaluation Evaluation Discussion Discussion Number Number Mechanism Programs Programs Recommended Recommended penetrations in penetrations the Containment in the Containment wall wall for for high high temperature temperature piping are piping are insulated insulated andand provided with aa cooling provided with system cooling system to limit to limit concrete temperature to concrete temperature to aa maximum maximum of of 150 150 degrees degrees F. F. The Penetration Air The Penetration Air Cooling System, Cooling System, evaluated evaluated with the Compressed Air System, provides this this cooling design feature.

See Subsection Subsection 3.5.2.2.1.3.

3.5.1-5 BWR BWROnlyOnly 3.5.1-6 Steel elements: Loss of ISI (lWE),

lSI (IWE), and 10 Yes, ififcorrosion is Consistent with NUREG-1801 Consistent NUREG-1801 . The ASME Section XI, XI, steel liner, liner material due to CFR Part 50, significant for significant Subsection IWE, B.2.1.28, Subsection B.2.1.28, and 10 10 CFR Part 50 Appendix anchors, anchors, general, pitting Appendix J. inaccessible inaccessible areas B.2.1.31, will be used to manage J, B.2.1.31, manage loss of material due due integral integral and crevice to general, pitting and crevice corrosion corrosion of thethe attachments attachments corrosion Containment Structure Containment Structure steel liner, liner anchors, and integral attachments. The ASME Section XI, Subsection Subsection IWE will also be used to manage manage loss of material material due to general, pitting and general, pitting and crevice crevice corrosion corrosion of of Containment Containment Structure Structure steel bolting (containment closure).

10 10 CFR CFR Part Part 50 Appendix J, 50 Appendix J, B.2.1.31, B.2.1.31, aging aging management program management program is is consistent consistent with with the NUREG-NUREG-1801 recommendations 1801 recommendations for for implementation.

implementation.

Loss of material due to corrosion is not significant for inaccessible areas inaccessible areas of the Containment of the Containment Structure Structure steel steel elements elements as discussed discussed in in further evaluation.

See Subsection 3.5.2.2.1.4 See Subsection 3.5.2.2.1.4 3.5.1-7 3.5.1-7 Prestressed Loss of TLAA, evaluated in evaluated in Yes, TLAA Not Applicable. The Containment Structure is not containment containment prestress due prestress accordance with 10 accordance with 10 prestressed concrete prestressed concrete andand prestressed containment prestressed containment tendons to relaxation, CFR 54.21 54.21(c)

(c) tendons tendons do not exist at Salem.

shrinkage, I I I Salem Salem Nuclear Nuclear Generating Generating Station, Station, Unit No.1 No. I and and Unit No.2 Unit No. 2 Page 3.5-57 3.5-57 License Renewal License Renewal Application Application

Section 3 - Aging Management Management Review Results Table 3.5.1 Summary Summary of Aging ManagementManagement Evaluations for Structures Structures and Component Component Supports Aging Effect/

Effect! Aging Aging Further Item Number Component Management Management Evaluation Evaluation Discussion Discussion Number Component Mechanism Mechanism Programs Recommended Programs Recommended creep, and elevated See Subsection 3.5.2.2.1.5 See Subsection 3.5.2.2.1.5 temperature temperature 3.5.1-8 3.5.1-8 BWR BWROnly Only 3.5.1-9 3.5.1-9 Steel, stainless Cumulative Cumulative TLAA, TlAA, evaluated in evaluated in Yes, TLAA TlAA Not Applicable Applicable for the containment pressure pressure boundary steel elements, steel elements, fatigue damage fatigue damage accordance with accordance with 10 10 components components listed for this item number. Salem is a PWR dissimilar metal (CLB fatigue 54.21(c)

CFR 54.21 (c) and the design does does not include a suppression pool.

welds: analysis exists) Cracking of the Salem Containment penetration penetration bellows, penetration penetration .due due to cyclic loading is not applicable the because the applicable because sleeves, penetration bellows, located outside of the Containment penetration the penetration penetration Containment, are not in-scope for license renewal and license renewal and bellows; Containment leakage are not part of the Containment leakage limiting boundary suppression pool shell, per per UFSAR UFSAR Fatigue section, section, analysis 3.8.1.6.8.10, 3.8.1.6.8.10, is not Piping included inPiping Penetrations.

Penetrations.

the current licensing suppression unbraced pool shell, basis for Containment penetrations (including licensing Fatigue analysis is not included in the current penetration unbrace.d basis for Containment penetrations (including penetration downcomers downcomers dissimilar metal sleeves and dissimilar metal welds).

The TLAA TlAA for fatigue of the Transfer Tube bellows was was aligned to this aligned this item number number based upon upon material, material, environment, and aging effect. The stainless steel Transfer Transfer Tube bellows are not part of the containment containment penetration bellows and are not part of the containment penetration containment pressure boundary pressure boundary butbut are are aa water retaining boundary water retaining boundary associated with associated with the the Reactor Cavity in Reactor Cavity in the the Containment Containment and the Transfer Transfer Pool in in the Fuel Handling Building.

Subsection 3.5.2.2.1.6.

See Subsection Salem Nuclear Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page Page 3.5-58 License Renewal License Renewal Application Application

  • * *
  • Management Review Results Table 3.5.1 3.5.1 Summary of Aging Management Summary Management Evaluations Evaluations for Structures and Component Supports Supports Item Aging Effect!

Aging Effect/ Aging Further Further Item Number Component Mechanism Management Management Evaluation Evaluation Discussion Number Mechanism Programs Recommended Recommended 3.5.1-10 Stainless steel Cracking due ISI (IWE) and 10 lSI Yes, detection of Not Applicable. Stress corrosion cracking will not occur penetration penetration to stress CFR Part 50, aging effects is to at these components, within the scope of license sleeves, sleeves, corrosion corrosion Appendix and Appendix J, and evaluated be evaluated renewal, because the normal stress and environmental penetration penetration cracking additional exposure conducive to the exposure conditions are not conducive the bellows, appropriate development development of stress corrosion cracking.

dissimilar metal examinations/evalu examinations/evalu See Subsection 3.5.2.2.1.7.

See Subsection 3.5.2.2.1.7.

welds ations for bellows bellows assemblies and

.- . . - ... -'" .- ...... _.

dissimnilar metal dissimilar welds.

3.5.1-11 BWR BWROnly Only 3.5.1-12 Steel, stainless Cracking due ISI (lWE) lSI (IWE) and 10 10 Yes, detection of Not applicable.

applicable. Salem is a PWR PWR and BWR componentscomponents steel elements, steel elements, to cyclic CFR Part 50, aging effects is to including including suppression suppression pool, BWR vent header, vent line line dissimilar metal loading Appendix Appendix J, and evaluated be evaluated bellows bellows and downcomers downcomers are not applicable applicable to Salem.

welds: supplemented supplemented to penetration bellows are not in-scope for The containment penetration penetration penetration detect fine cracks detect fine cracks License Renewal because they do not perform a License sleeves, Containment structure Containment structure pressure pressure boundary or any other penetration penetration intended function. The containment intended containment penetration bellows bellows bellows; bellows; located outside are located outside ofof the containment containment and are not part of suppression suppression the containment containment leakage limiting boundary boundary per UFSAR UFSAR pool shell, section, 3.8.1.6.8.10.

section, 3.8.1.6.8.10.

unbraced unbraced downcomers downcomers Plant Plant operating operating experience experience has has not not identified identified cracking cracking ofof bounding piping or of the containment the bounding containment liner or penetrations penetrations (including sleeves, dissimilar dissimilar metal metal welds, and penetrations penetrations bellows) as a concern. Cracking due due toto cyclic loading will not occur at the penetrations because penetrations because the normal stress and environmental environmental exposureexposure conditions conditions are not conducive development of cyclic conducive to the development cyclic cracking.

cracking.

Cracking Cracking is not not predicted predicted in in the associated associated piping, piping, due due toto Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.1 No. 1 and and Unit No.

No.22 3.5-59 Page 3.5-59 License Renewal License Renewal Application Application

Section Section 3 - Aging Management Management Review Review Results Results 3.5.1 Table 3.5.1 Summary Summary of Aging Management Evaluations for Structures and Component Aging Management Component SupportsSupports Effectl Aging Effect! Aging Aging Further Item Component Management Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Programs Recommended Recommended low design stresses, low design stresses, and, and, therefore, therefore, is is not expected in not expected in the Containment the Containment liner and and penetrations penetrations (including (including sleeves sleeves and dissimilar welds) since the piping is bounding bounding and enveloping for the enveloping for stresses in the stresses in the the penetration sleeves.

penetration sleeves.

See Subsection 3.5.2.2.1.8 See Subsection 3.5.2.2.1.8 3.5.1-13 BWR BWROnlyOnly 3.5.1-14 Concrete Concrete Loss of ISI (IWL).

lSI (IWL). Yes, for Consistent with NUREG-1801.

NUREG-1801. ASME Section XI, elements: material Evaluation is Evaluation inaccessible inaccessible areas Subsection Subsection IWL, B.2.1.29, will be used to manage loss of dome, wall, (Scaling, needed for plants located in of plants located in material (Scaling, cracking, and spalling) due to freeze-basemat ring cracking, and that are located in located in moderate moderate to severe thaw of concrete elements elements in accessible areas of the in accessible the girder, spalling) due to moderate to severe severe weathering Containment structures.

buttresses, freeze-thaw weathering weathering conditions conditions See subsection See 3.5.2.2.1.9 subsection 3.5.2.2.1.9 containment containment conditions conditions (as applicable) (weathering index

>100 day-inch/yr)

(NUREG-1 557).

(NUREG-1557).

3.5.1-15 Concrete Concrete Cracking due ISI (IWL) lSI (IWL) for Yes, ififconcrete concrete NUREG-1801. ASME Sedion Consistent with NUREG-1801. Section XI, Xl, elements:

elements: to expansion expansion accessible areas. was not Subsection IWL, B.2.1.29, will be used to manage manage walls, dome, and reaction None for constructed constructed as cracking and increase increase in porosity, permeability permeability due to basemat, ring with aggregate; aggregate; inaccessible areas inaccessible stated for leaching of calcium hydroxide in in accessible accessible areas of the girder, increase in in ifconcrete was if inaccessible inaccessible areas Containment structures.

buttresses, porosity, constructed inin At At Salem, Salem, cracking cracking duedue toto expansion expansion and and reaction reaction with with containment, permeability permeability accordance with accordance aggregate is not applicable. The aggregates aggregate is not applicable. The aggregates in in the the concrete concrete fill-in due to leaching the Containment structures Containment structures were were tested tested inin accordance accordance with with annulus annulus (as of calcium recommendations recommendations ASTM Specification C ASTM Specification C 289-65 289-65 for for potential potential reactivity reactivity and and applicable),

applicable). hydroxide hydroxide in ACI 201.2R.

in conform to the requirements of ASTM conform to the requirements of ASTM C 33-66. C 33-66.

Increase in Increase in porosity, porosity, permeability permeability due due leaching leaching of of calcium calcium hydroxide is hydroxide is potentially applicable. The potentially applicable. The Containment Containment Salem Nuclear Generating Generating Station, Unit No. 1I and Unit No.2 No. 2 Page Page 3.5-60 License Renewal Renewal Application Application

  • * *
  • Management Review Results Table Table 3.5.1 Summary of Aging Management Evaluations for Structures Management Evaluations Structures and Component Supports Supports Effect/

Aging Effect! Aging Aging Further Further Item Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Programs Recommended Recommended Structure concrete concrete could be exposed to a flowing water environment, which is the cause of this aging effect/mechanism. The Containment effect/mechanism. Containment structures structures are are constructed of durable concrete which is managed constructed managed for the the aging effects by the ASME Section XI, Xl, Subsection IWL Subsection IWL program.

Subsection 3.5.2.2.1.10.

See Subsection 3.5.1-16 3.5.1-16 Seals, gaskets, Loss of sealing ISI lSI (IWE)

(lWE) and 10 10 No No Consistent with NUREG-1801.

NUREG-1 801. The ASME Section Section X1, XI, and moisture and leakage CFR Part 50, Subsection IWE, B.2.1.28, Subsection 8.2.1.28, and 10 CFR Part 50 Appendix Appendix barriers through Appendix J B.2.1.31, will be used to manage J, 8.2.1.31, manage loss of sealing sealing and containment containment leakage through containment due to deterioration deterioration of joint due to due seals, gaskets, and moisture moisture barriers.

deterioration of deterioration ASME Section XI, ASME Section Xl, Subsection Subsection IWE IWE isis the the applicable applicable joint seals, aging management program for the aging management program for the containmentcontainment gaskets, and moisture barrier moisture component; 10 barrier component; CFR 50 10 CFR 50 Appendix Appendix JJ moisture testing is not testing is applicable to not applicable to this component based this component based onon barriers ASME Section XI, ASME Section Xl, 1998 1998 and later ASME and later Codes.

ASME Codes.

(caulking, flashing, and 10 10 CFR applicable aging CFR 50 Appendix J is the applicable other sealants) management program for the seals and gasket management program components; components; ASME Section XI, Xl, Subsection Subsection IWE is not applicable applicable based on the ASME Section Xl, 1998 and later XI, 1998 ASME Codes.

Codes.*

Salem Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.

No.22 Page 3.5-61 License License Renewal Application Renewal Application

Section Section 3 - Aging Management Review Aging Management Review Results Table 3.5.1 Summary of Aging Evaluations for Structures and Component Management Evaluations Aging Management ComponentSupports Supports Effect/

Aging Effect! Aging Aging Further Further Item Component Management Evaluation Evaluation . Discussion Number Number Mechanism Mechanism Management Programs Programs Recommended Recommended 3.5.1-17 3.5.1-17 Personnel Personnel Loss of leak 10 CFR Part 50, No NUREG-1801. 10 CFR Part 50 Appendix Consistent with NUREG-1801.

airlock, tightness inin Appendix Appendix J and J, B.2.1.31, Technical Specifications B.2.1.31, and Plant Technical Specifications equipment equipment closed position Plant Technical Technical surveillance testing requirements will be used to managemanage hatch hatch and CRD due to Specifications Specifications loss of leak tightness in in closed position due to hatch hatch locks, mechanical mechanical mechanical wear of locks, hinges and closure mechanical hinges, and wear ofof locks, mechanisms of the personnel airlocks and the equipment mechanisms equipment closure hinges and hatches.

mechanisms mechanisms closure mechanisms mechanisms ~

3.5.1-18 3.5.1-18 Steel Loss of ISI (IWE) and 10 lSI No NUREG-1801. The ASME Section XI, Consistent with NUREG-1801. XI, penetration penetration material due to material CFR Part 50, Subsection B.2.1.28, and 10 CFR Part 50 Appendix Subsection IWE, 8.2.1.28, Appendix sleeves sleeves and general, pitting, Appendix J. J, B.2.1.31, material due B.2.1.31, will be used to manage loss of material due dissimilar metal dissimilar and crevice crevice corrosion of Containment to general, pitting and crevice Containment welds; corrosion penetration sleeves, dissimilar metal Structure steel penetration personnel welds, personnel airlock, and equipment welds, personnel equipment hatch.

airlock, equipment equipment hatch and CRD hatch hatch 3.5.1-19 3.5.1-19 BWR Only BWROnly 3.5.1-20 3.5.1-20 BWR Only BWROnly 3.5.1-21 3.5.1-21 BWR Only BWROnly 3.5.1-22 3.5.1-22 Prestressed Prestressed Loss of ISI lSI (IWL) No Not Applicable. Salem design does not include include containment:

containment: material material due to prestressed containment tendons and anchorage prestressed anchorage tendons and corrosion components.

anchorage anchorage components components Salem Nuclear Generating Station, Salem Nuclear No. 1 and Unit No.2 Station, Unit No.1 No. 2 Page 3.5-62 3.5-62 License Renewal Application

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  • Review Results Table 3.5.1 Summary of of Aging Management Evaluations for Structures Structures and Component Supports Item Aging Effect!

Aging Effect/ Aging Further Item Number Component Mechanism Management Management Evaluation Evaluation Discussion Number Mechanism Programs Recommended 3.5.1-23 3.5.1-23 All Groups All Groups Cracking, loss Cracking, loss Structures Structures Yes, ififnot Yes, not within within Consistent with NUREG-1801.

Consistent NUREG-1 801. The Structures Monitoring Monitoring except Group except Group of bond, of bond, andand Monitoring Monitoring the scope the scope of of the the Program, B.2.1.33, Program, 8.2.1.33, will be used to manage cracking, loss loss 6: interior 6: interior and and loss of loss of material material Program Program applicant's applicant's of bond, and loss of material material (spalling, scaling) due to above grade above grade (spalling, (spalling, Structures corrosion of embedded embedded steel for interior and above grade exterior exterior scaling) due scaling) due to to Monitoring Monitoring exterior concrete for Groups 1, 1, 3,4 3, 4 and 5. Groups 2,7,2, 7, 8 concrete concrete corrosion of corrosion of Program.

Program. and 9 do not apply to Salem.

embedded embedded Interior and Interior exterior masonry and exterior masonry walls walls with with reinforcing reinforcing steel steel steel steel were also were also addressed addressed under under this item number this item number as as this this aging effect and mechanism mechanism was determined determined during aging management management reviews to be applicable applicable to reinforced reinforced masonry walls.

masonry Components in in the Fire Protection Protection System (Fire barrier barrier concrete and masonry masonry wall components) have been aligned to this item number based on material, environment and aging environment aging effect effect. The The Fire Protection Protection Program, B2.1.15, Program, will be added to manage cracking, 82.1.15, will loss of loss of bond, and loss bond, and loss of of material (spalling, scaling) material (spalling, scaling) due due to corrosion of embedded embedded steel for the concreteconcrete and masonry wall masonry wall components components for for these these systems systems andand /or lor structures.

structures.

See Subsection 3.5.2.2.2.1 See Subsection Salem Salem Nuclear Nuclear Generating Generating Station, Station, Unit Unit No.

No.11 and and Unit Unit No.

No.22 Page 3.5-63 Page 3.5-63 License License Renewal Renewal Application Application

Section Section 3 - Aging Management Review Aging Management Review Results Results Table Table 3.5.1 3.5.1 Summary Summary of Aging Management Management Evaluations Evaluations for Structures and Component Structures and Component SupportsSupports Aging Effect/

Aging Effect! Aging Aging Further Further Item Item Component Management Evaluation Evaluation Discussion Discussion Number Number Mechanism Mechanism Management Programs Programs Recommended Recommended 3.5.1-24 All Groups 3.5.1-24 Groups Increase Increase inin Structures Structures Yes, ififnot within within Consistent NUREG-1 801. The Structures Consistent with NUREG-1801. Monitoring Structures Monitoring except Group Group porosity and Monitoring Monitoring the scope of the Program, Program, B.2.1.33, will be manage increase be used to manage increase in in 6: interior and permeability, Program Program applicant's applicant's porosity and permeability, cracking, loss porosity loss of material above grade grade cracking, loss 16ss Structures Structures (spalling, scaling) scaling) due due to aggressive aggressive chemical attack for chemical attack exterior exterior of material material Monitoring Monitoring interior interior and and above grade concrete for Group grade exterior concrete Group 1, 3, concrete concrete (spalling, Program.

Program. 4 and 5 structures.

structures.

scaling) due to scaling) aggressive aggressive chemical attack attack See See Subsection Subsection 3.5.2.2.2.1.

3.5.2.2.2.1.

3.5.1-25 3.5.1-25 All Groups Groups Loss of Structures Structures Yes, ififnot within within Consistent NUREG-1801. The Structures Consistent with NUREG-1801. Structures except Group Group material due to material Monitoring Monitoring the scope of the Monitoring Program, B.2.1.33, Monitoring 8.2.1.33, will be used used to manage manage 6: steel corrosion Program. IfIf applicant's applicant's loss of material structural steel material due to corrosion of all structural components:

components: protective coatings Structures components.

all structural structural are are relied upon to Monitoring Monitoring Protective coatings are Protective coatings not credited are not credited for for managing managing thethe steel manage the effects manage Program aging effects of steel components.

aging effects of steel components.

of aging, aging, the Structures of the Coatings inside Coatings inside the the Containment Containment Structure Structure are are credited to Structures Monitoring Monitoring maintain adhesion to protect against failure of the coating Program is Program is to which may block the suction strainers. The ProtectiveProtective include provisions Coating Monitoring Maintenance Program, Monitoring and Maintenance Program, B.2.1.35, to address manage the aging of coatings inside the Containment will manage protective coating protective Structure.

monitoring and monitoring See Subsection 3.5.2.2.2.1.

See Subsection 3.5.2.2.2.1.

maintenance.

maintenance.

Nuclear Generating Salem Nuclear Unit No.1 Generating Station, Unit No. 2 No. 1 and Unit No.2 Page Page 3.5-64 Renewal Application License Renewal Application

  • * *
  • Review Results Results Table 3.5.1 3.5.1 Summary Summary of Aging Management Management Evaluations Evaluations for Structures Structures and Component Component SupportsSupports Effectl Aging Effect! Aging Aging Further Further Item Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Recommended Recommended 3.5.1-26 All Groups Loss of Structures Yes, ififnot within Consistent Consistent with NUREG-1 NUREG-1801. 801. The Structures Monitoring Structures Monitoring except Group material material Monitoring the scope of the Program, B.2.1.33, will be used to manage loss of Progra-m, 8.2.1.33, 6: accessible accessible (spalling, Program. applicant's applicant's material (spalling, scaling) and cracking due to freeze-material and scaling) and Evaluation is Structures Structures thaw for accessible exterior exterior concrete concrete structures and inaccessible inaccessible cracking due to needed for plants Monitoring concrete foundations.

concrete concrete:

concrete: freeze-thaw that are located inin for Program or for' Exterior masonry Exterior masonry walls with reinforcing walls with steel were reinforcing steel also were also foundation moderate to severe inaccessible inaccessible areas addressed under this item number as this aging addressed under this item number as this aging effect effect weathering weathering of plants located in in and mechanism was determined during aging and mechanism was determined during aging conditions conditions moderate severe moderate to severe management reviews to be applicable to reinforced management reviews to be applicable to reinforced (weathering index weathering masonry walls.

masonry walls.

>100 day-inch/yr) conditions conditions (NUREG-1 (NUREG-1557).557). Components Components in barrier in the Fire Protection System (fire barrier masonry wall masonry components) have wall components) have been aligned to been aligned this item to this item number based number based on material, environment on material, environment andand aging aging effect.

effect.

The Fire Protection The Fire Protection Program, Program, 82.1.15, B2.1.15, will will be added to be added to manage the loss of material (spalling, scaling) and cracking due to freeze-thaw freeze-thaw for the exterior masonry masonry wall components for the Fire Protection system.

See subsection 3.5.2.2.2.2.1 3.5.1-27 3.5.1-27 All Groups Groups Cracking due Cracking due Structures Yes, ififnot Yes, not within Not Applicable. At Salem, Not Salem, Groups Groups 1,1, 3, 4, and 3, 4, and 55 except Group except Group to expansion to expansion Monitoring Monitoring the scope of the structures structures are monitored monitored for concrete cracking cracking due to any 6: accessible due to reaction Program. applicant's mechanisms through the Structures Program, Structures Monitoring Program, and with None for None for Structures Structures B.2.1.33, and thus a further evaluation is not necessary.

8.2.1.33, inaccessible inaccessible aggregates aggregates inaccessible areas inaccessible areas Monitoring Monitoring See Subsection 3.5.2.2.2.1.

See Subsection 3.5.2.2.2.1.

interior/exterior interior/exterior ifconcrete was if concrete was Program or or concrete concrete constructed in concrete was concrete not was not portions of Groups 1,3,4 concrete portions At Salem, the concrete 1, 3, 4 and 5 constructed in with accordance with constructed as constructed Structures (Groups 2,7, Structures (Groups 2, 7, 8 and8 and 9 9 structures structures do not exist at accordance the the stated for Salem)

Salem) is designed in is designed accordance with ACI 318-63 and in accordance recommendations inaccessible areas inaccessible areas constructed constructed inin accordance accordance with ACI 301-66. Aggregates Aggregates recommendations recommendations were tested in accordance with ASTM Specification C-were tested in accordance with ASTM Specification C-in ACl in 201 .2R-77.

ACI 201.2R-77. 289-65 for potential reactivity. The type and size of 289-65 for potential reactivity. The type and size of Salem Nuclear Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-65 3.5-65 License License Renewal Application Application

Section Aging Management Section 33 - Aging Management Review Review Results Results Table Table 3.5.1 3.5.1 Summary Summary of of Aging Aging Management Evaluations for Structures Management Evaluations Structures andand Component Component Supports Supports Aging Effect/

Aging Effect! Aging Aging Further Further Item Component Management Evaluation Discussion Number Number Component Number Mechanism MechaniPrograms Mechanism Management Programs Evaluation Recommended Recommended aggregate, aggregate, slump, cement cement and additives additives have have been established established to produce produce durable concrete concrete and determined and determined to preclude cracking and expansion preclude cracking expansion duedue to reaction reaction with with aggregates.

aggregates.

cracking due to expansion Thus, cracking expansion and reaction reaction with with aggregates accessible and inaccessible aggregates in both accessible inaccessible areas of Groups 1, 3, 4, and 55 structures Groups structures is not not significant significant and requires requires no aging management.

See See subsection 3.5.2.2.2.2.2 3.5.2.2.2.2.2 Further evaluation inaccessible areas evaluation of inaccessible areas is provided provided inin Subsection Subsection 3.5.2.2.2.2.2.

3.5.2.2.2.2.2.

L J. 4. 4 4 3.5.1-28 3.5.1-28 Groups Groups 1-3, 5- Cracks Cracks and Structures Structures Yes, if not within within Consistent with NUREG-1801.

NUREG-1801. The Structures Monitoring Structures Monitoring 9: All distortion distortion due due Monitoring Monitoring the scope scope of the the Program, B.2.1.33, B.2.1.33, will be used used to manage manage cracks and to increased increased Program. IfIf a de- applicant's applicant's distortion due distortion due to increased increased stress levels from settlement stress levels stress levels watering system is Structures StruCtures structures founded on soil. Salem for structures Salem does does not utilize utilize a from settlement settlement relied upon for Monitoring Monitoring de-watering system to controlcontrol settlement.

control of Program or a de-Program Interior and exterior masonry walls were also addressed Interior settlement, then watering system is watering number as this aging effect under this item number effect and the licensee is to relied upon determined during aging mechanism was determined management aging management ensure proper reviews to be applicable applicable to masonry walls.

the functioning of the de-watering de-watering system Fire barrier Fire barrier concrete concrete andand masonry masonry wall components components have have through the period been aligned to this item number based based on material, of extended extended environment and aging effeCt. effect. The Fire Protection operation. Program, B2.1.15, will be added to manage cracks and manage cracks distortion due due to increased increased stress levels from settlement for the concrete fire barrier barrier and masonry masonry wall components.

Unit No.1 Salem Nuclear Generating Station, Unit No. 1 and Unit No.2 No. 2 3.5-66 Page 3.5-66 License Renewal Application

  • * *
  • Review Results Results Table 3.5.1 Summary of Aging Management Summary Management Evaluations Evaluations for Structures Structures and Component Component SupportsSupports Effect/

Aging Effect! Aging Aging Further Further Item Component Mechanism Management Management Evaluation Evaluation Discussion Number Number Mechanism Programs Recommended Recommended 3.5.2.2.2.1 and 3.5.2.2.2.2.3.

subsections 3.5.2.2.2.1 See sub~ections 3.5.1-29 Groups Groups 1-3, 5- 5- Reduction in Reduction in Structures ifnot within Yes, if Not Applicable.

Not Applicable. Salem Salem design design does does not not utilize utilize aa de-de-9: foundation foundation Monitoring the scope of the watering system to control settlement and does watering system to control settlement and does not not strength, Program. IfIf a de- applicant's include porous concrete include porous concrete subfoundation.

subfoundation.

cracking, cracking, watering system system is Structures Structures differential differential relied upon for Monitoring Monitoring settlement due control of Program or a de- subsections 3.5.2.2.2.1 and 3.5.2.2.2.2.3.

See subsections to erosion of to settlement, then watering system is is porous porous the licensee licensee is to to relied upon relied upon concrete concrete ensure proper ensure proper subfoundation subfoundation functioning functioning of the the de-watering de-watering system through the period of extended operation.

operation.

3.5.1-30 Group 4: Lock-up due to ISI (IWF) or lSI Yes, ififnot within Consistent with NUREG 1801. 1801. The ASME Section XI, Radial beam wear Structures Structures the scope of lSIISI or Subsection Subsection IWF program, B.2.1.30, manage B.2.1.30, is used to manage seats in BWR Monitoring Monitoring Structures lock-up due to wear for the sliding lubrite surfaces at the lock-up the drywell; RPV Program Monitoring Monitoring steam generator generator supports.

support shoes Program See Subsection 3.5.2.2.2.1.

See Subsection 3.5.2.2.2.1.

PVVR with for PWR nozzle nozzle supports; Steam generator generator supports supports Salem Nuclear Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-67 Application License Renewal Application

Section Section 3 - Aging Management Review Aging Management Review Results Results Table 3.5.1 Summary Summary of Aging Management Management Evaluations Evaluations for Structures Component Supports Structures and Component Effect/

Aging Effect! Aging Aging Further Further Item Number Number Component Component Management Management Evaluation Evaluation Discussion Discussion Mechanism Mechanism Programs Programs Recommended Recommended 3.5.1-31 Groups Groups 1-3, 5, 5, Increase Increase in in Structures Structures Yes, plant-specific, Consistent with NUREG-1801.

NUREG-1801. The Structures Structures 7-9: below- porosity and Monitoring Monitoring if if environment is Monitoring Program, 8.2.1.33, Monitoring B.2.1.33, will be used to manage manage grade concrete grade concrete permeability, Program; aggressive aggressive increase inin porosity and permeability, cracking, loss of components, cracking, loss Examination of scaling)/ aggressive material (spalling, scaling)! aggressive chemical attack; such as of material representative representative cracking, loss of bond, and loss of materialmaterial (spalling, exterior walls (spalling, samples of below- scaling)/corrosion scaling)!corrosion of embedded steel in in accessible accessible areas.

below grade grade scaling)/

scaling)! grade concrete, A representative A representative sample of below-grade below-grade concrete will be be foundation and foundation aggressive periodic and periodic inspected, if if excavated excavated for any reason, and periodic periodic chemical monitoring of groundwater groundwater monitoring will be done as required by the the-attack; groundwater, if if the Structures Structures Monitoring Monitoring Program.

Cracking, loss environment environment is is Components Components in in the Circulating Circulating Water System and of bond, and non-aggressive.

non-aggressive. A A Service Service Water System have been aligned to this item loss of loss of material material plant plant specific specific number based on material, environment and aging effect.

(spalling, (spalling, program program is is to to be be The Buried Non-Steel Piping Inspection, B.2.2.4, aging scaling)/

scaling)! evaluated evaluated if if management management programprogram will be substituted substituted to manage manage the the corrosion of environment is environment is Cracking, Cracking, loss of bond, and loss of material material (spalling, embedded embedded aggressive.

aggressive. scaling)/

scaling)! corrosion of embedded embedded steel of the (concrete) steel steel piping and fittings for these these systems.

See Subsection 3.5.2.2.2.2.4.

3.5.2.2.2.2.4.

3.5.1-32 Groups 1-3, 5, 5, Increase in Increase in Structures Yes, ififconcrete Consistent Consistent with NUREG-1801. Structures NUREG-1801. The Structures 7-9: exterior porosity and Monitoring was not Monitoring Program, B.2.1.33, will be used to manage manage above and above permeability, Program for constructed as constructed Increase in in porosity and permeability, and loss of below grade grade and loss of accessible accessible areas. stated for strength due to leaching leaching of calcium hydroxide hydroxide in in reinforced reinforced strength due strength due to to None for None for inaccessible areas inaccessible areas accessible areas. Salem accessible areas. Salem maymay have have aa flowing water concrete leaching of leaching inaccessible areas inaccessible environment environment in accessible or in in accessible in inaccessible inaccessible areas areas of foundations calcium ifconcrete was if exterior exterior below gradegrade reinforced reinforced concrete foundations for hydroxide hydroxide constructed in constructed in Groups Groups 1, 3, 44 and 1, 3, and 55 structures. Groups 2, structures. Groups 2, 7, 8 and and 99 accordance with accordance structures structures do not exist at Salem. At Salem, the Portland the cement cement conforms to ASTM C 150, Type IIIIand flyash was was recommendations recommendations also used. The use of Type IIIIcement and flyash result in in in ACI 201.2R-77.

in 201.2R-77. concrete resistant to increase concrete resistant increase in in porosity and porosity and Salem Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.

No.22 Page 3.5-68 3.5-68

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,i:

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  • Section 3 - Aging Management Review Results Results Table 3.5.1 Summary of Aging Management Management Evaluations Evaluations for Structures Structures and Component Component SupportsSupports Effect/

Aging Effect! Aging Aging Further Further Item Number Component Component Management Management Evaluation Evaluation Discussion Discussion Number Mechanism Mechanism Programs Recommended Programs Recommended permeability, and loss of strength due to leachingleaching of calcium hydroxide.

hydroxide. Concrete Concrete is designed designed in accordance in accordance with ACI with ACI 318-63 318-63 and and constructed constructed in accordance with in accordance with ACI ACI 301-66. The 301-66. The type type and size of and size of aggregate, slump, cement aggregate, slump, cement and additives have and have been been established established to produce durabledurable concrete.

See subsection 3.5.2.2.2.2.5.

3.5.1-33 Groups 1-5:

Groups Reduction Reduction of A plant-specific A plant-specific Yes, plant-specific plant-specific Not Applicable. Salem Group 1, 1, 3, 4 and 5 concrete concrete concrete concrete strength and strength and aging management aging management if temperature limits if temperature limits structures structures are are not not subject subject to to general general area temperature modulus of modulus program is to program is to be be are exceeded.

are exceeded. greater than greater 150 0 F. Groups than 150°F. Groups 2,7,8 2, 7, 8 and and 99 structures structures do do concrete due to evaluated evaluated notexist not exist at Salem.

elevated temperature See subsection 3.5.2.2.2.3.

See subsection 3.5.2.2.2.3.

3.5.1-34 3.5.1-34 Group 6: Increase Increase inin Inspection Inspection of Yes, plant-specific plant-specific Consistent Consistent with NUREG-1801.

NUREG-1801. The RG 1.127, Inspection Inspection Concrete; porosity and porosity and Water-Control Water-Control if ifenvironment is environment is of of Water Control Structures Associated with Nuclear Nuclear permeability, Structures or aggressive B.2.1.34, as implemented Power Plants program, 8.2.1.34, implemented by the the all cracking, loss cracking, loss FERC/US Army FERC/US Army Structures Structures Monitoring Program, B.2.1.33, Monitoring Program, .will be 8.2.1.33, .will be used used to to of material of material due Corps of Engineers Engineers manage cracking, manage cracking, loss of of bond, and lossloss of of material material duedue to aggressive aggressive inspections dam inspections to corrosion corrosion of embedded steel and increase in in porosity chemical chemical and maintenance and maintenance and permeability, cracking, and permeability, cracking, loss loss of material due of material due toto attack; programs and for aggressive aggressive chemical chemical attack for concrete in in accessible accessible cracking, loss inaccessible inaccessible above above grade and submerged concrete concrete surfaces. A A of bond, loss of concrete, an representative sample of below-grade representative below-grade concrete will be be material due to examination of examination ifexcavated inspected, if excavated for any reason, and periodic periodic corrosion of corrosion of representative representative groundwater groundwater monitoring monitoring will will be be done done asas required required by by the the embedded samples of below- Structures Structures Monitoring Program.

Monitoring Program.

steel steel grade concrete, ..

Nuclear Generating Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page 3.5-69 3.5-69 License Renewal License Renewal Application Application

Section Section 33 - Aging Aging Management Management Review Review Results Results Table 3.5.1 Table 3.5.1 Summary of Summary Evaluations for Structures Management Evaluations of Aging Management and Component Structures and Component Supports Supports Aging Effect/

Effect! Aging Aging Further Further Item Item Numer Component Component Mechanism Management Management Programs Evaluation Evaluation Recommended Discussion Discussion Number Number Mechanism Programs Recommended and and periodic periodic See See subsection subsection 3.5.2.2.2.4.1.

3.5.2.2.2.4.1.

monitoring of monitoring of Components in the Circulating Water System and ComponentsWaterinSystem the Circulating Water System anditem to this groundwater, groundwater, if ifthe Service have been aligned Service Water System haveenvironment been alignedand to this agingitem effect.

environment environment is is number based on material, number based on material, environment and aging effect.

non-aggressive. A A The Buried Non-Steel Piping Inspection Program, The Buried Non-Steel Piping Inspection Program, increase in specific plant specific B.2.2.4, will be substituted to manage B.2.2.4, will be substituted to manage increase in due program is program isto be porosity and permeability, cracking, loss of material porosity and permeability, cracking, loss of material due evaluated ifif evaluated to aggressive chemical attack for reinforced concrete to aggressive chemical attack for reinforced concrete environment is environment is piping and fittings for these systems.

piping and fittings for these systems.

aggressive.

3.5.1-35 3.5.1-35 Group Group 6: Loss of Inspection of Inspection Yes, for Yes,for NUREG-1801. The RG 1.127, Inspection Consistent with NUREG-1801.

Consistent Inspection exterior exterior above material material Water-Control Water-Control inaccessible areas inaccessible of Water Water Control Structures Associated Control Structures Associated withwith Nuclear Nuclear and below (spalling, Structures or Structures of plants located located in in Power Plants program, implemented by the program, B.2.1.34, as implemented the grade concrete grade concrete scaling) and FERC/US Army moderate moderate to severe severe Structures B.2.1.33, will be used to Monitoring Program, B.2.1.33, Structures Monitoring foundation cracking due to Corps of Engineers Engineers weathering manage loss of material manage material (spalling, scaling) and (spalling, scaling) cracking and cracking freeze-thaw freeze-thaw dam inspections conditions due to freeze-thaw due concrete in freeze-thaw of concrete accessible areas of in accessible and maintenance maintenance Group 6 structures.

programs.

Evaluation Evaluation is needed for plants needed See subsection 3.5.2.2.2.4.2.

that are located located inin moderate to severe moderate severe weathering weathering conditions conditions (weathering index

>100 day-inch/yr)

(NUREG-1 (NUREG-1557).557).

Salem Nuclear Nuclear Generating Station, Unit Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-70 Page 3.5-70 License Renewal Application

  • * *
  • Section 3 3 -Aging Management Review

- Aging Management

  • Review Results Table 3.5.1 Table Summary of Summary Management Evaluations for Structures and Component

'ofAging Management Component Supports Item Itm gigEfec/

Aging Effect! Aging Further Further Component Management Evaluation Discussion Number Number Cmoet Mechanism Mechanism Management Evaluation Programs Programs Recommended Recommended 3.5.1-36 3.5.1-36 Group 6:

Group 6: all all Cracki *ngdue Cracking Accessible areas:

Accessible areas: Yes, ifif concrete Yes, concrete Not applicable. Reinforced concrete for Group 6 accessible/

accessiblel to expansionl expansion/ Inspection of Inspection of was not structures structures isis designed designed in in accordance with ACI 318-63 31 8-63 inaccessible inaccessible reaction with reaction with Water-Control Water-Control constructed as constructed as and constructed constructed in in accordance with ACI 301-66.

reinforced reinforced aggregates aggregates Structures or Structures or stated for stated for Aggregates werewere tested in in accordance with ASTM concrete concrete FERC/US Army FERC/US Army inaccessible areas Specification C C 289-65 for potential reactivity. The type

- Corps of Corps of Engineers Engineers and size of aggregate, slump, cement and additives have dam inspections been established to produce durable concrete and and and maintenance and maintenance determined determined to preclude preclude cracking and expansion due to programs.

programs. reaction with aggregates.

aggregates. However, accessible and and None for inaccessible concrete inaccessible concrete for for Group Group 6 6 structures will be structures will be inaccessible areas inaccessible areas inspected for inspected cracking due for cracking due toto any any mechanism mechanism as as required required if concrete if was concrete was by RG 1.127, the RG by the 1.127, Inspection Inspection of of Water Water Control Control Structures Structures constructed in constructed in Associated Associated withwith Nuclear Nuclear Power Power Plants, Plants, B.2.1.34, B.2.1 .34, and and for for accordance with accordance with below below grade grade portions, portions, as as required required by by the the Structures Structures the Monitoring program, Monitoring Program, B.2.1B.2.1.33,

.33, ifif excavated excavated for for any any recommendations recommendations reason.

reason.

in in ACI 201 .2R-77.

201.2R-77.

See subsection 3.5.2.2.2.4.3.

3.5.1-37 3.5.1-37 Group Group 6: Increase Increase in in For accessible For Yes, ifif concrete Yes, Consistent with with NUREG-1 NUREG-1801. 801. TheThe RG RG 1.127, 1.127, Inspection Inspection exterior above exterior above porosity and porosity and areas, areas, inspection ofof was not of Water Water Control Control Structures Structures Associated with Nuclear Nuclear and below and permeability, permeability , Water-Control Water-Control constructed as Power Power Plants program, program, B.2.1.34, 8.2.1.34, as implemented by as implemented by the grade grade loss loss ofof strength strength Structures Structures oror stated stated for Structures Monitoring Program, Structures Monitoring Program, B.2.1 .33, will be used to B.2.1.33, reinforced reinforced due to due to leaching leaching FERC/US Army FERC/US Army inaccessible areas manage manage increase increase in in porosity and permeability, loss of concrete of calcium Corps Corps of Engineers strength due to leaching of calcium hydroxide for for foundation foundation hydroxide dam dam inspections -- reinforced concrete in in accessible areas of Group Group 6 interior slab interior slab and maintenance maintenance structures (( i.e.,

i.e., Service Water Water Intake and Shoreline Shoreline Dike programs.

programs. None for structures). Increase Increase in in porosity porosity and permeability, permeability, loss of inaccessible areas strength strength due to leaching of of calcium hydroxide hydroxide is is not not if concrete concrete was was significant significant in in the the inaccessible inaccessible belowbelow grade grade areas areas of these these constructed inin structures structures asas these these areas are are constructed with with durable durable accordance with accordance concrete.

concrete ...

Salem Salem Nuclear Nuclear Generating Station, Unit Generating Station, Unit No.

No.11 and and Unit Unit No.

No.22 Page 3.5-71 3.5-71 License Renewal Application License Renewal Application

Section 3 - Aging Management Management Review Results Results Table Table 3.5.1 3.5.1 Summary Summary of Aging Management Management Evaluations Evaluations for Structures Component Supports Structures and Component Supports Item Aging Effect/

Aging Effect! Aging Further Further Item Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Recommended Recommended the See subsection 3.5.2.2.2.4.3.

See subsection 3.5.2.2.2.4.3.

recommendations recommendations inACI 201.2R-77.

in 201.2R-77. Components Components in in the Circulating Water System and the the Service Service Water System have been aligned to this item item number number based on material, environment and aging effect.

material, environment The Open-Cycle Open-Cycle Cooling Cooling Water System Program, B.2.1.11, will be B.2.1.11, will be substituted substituted to to manage increase in manage increase in porosity and permeability, porosity and permeability, loss of of strength strength due toto leaching of calcium leaching of calcium hydroxide hydroxide for for reinforced reinforced concrete concrete piping and and fittings fittings for for these systems.

systems.

Components Components in in the Fuel Handling Handling Building have been aligned to this item based on material, environment environment and aging effect. The Structures Monitoring Monitoring Program will be be substituted manage the increase in substituted to manage in porosity and permeability, loss of strength due to leaching of calcium hydroxide hydroxide for the accessible accessible concrete trench, exposed to a flowing water environment, in in the Fuel Handling Handling Building.

3.5.1-38 3.5.1-38 Groups 7, Groups 8:

7,8: Cracking Cracking due A plant-specific A plant-specific Yes, plant specific specific Not Applicable. Salem does not have Group 7 and 8 Tank liners to stress aging management stainless stainless steel tank liners.

corrosion corrosion program is to bebe -

cracking; cracking; loss evaluated of material due due See subsection 3.2.2.2.5.

to pitting pitting and and crevice crevice corrosion Salem Nuclear Generating No. I and Unit No.

Generating Station, Unit No.1 No.22 Page Page 3.5-72 License Renewal License Renewal Application Application

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  • Management Review Results Results Table 3.5.1 3.5.1 Summary of Aging Management Management Evaluations Evaluations for Structures Structures and Component Component Supports Aging Effect/

Effect! Aging Aging Further Item Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Recommended Recommended 3.5.1-39 3.5.1-39 Support Loss of Structures Yes, ififnot within Consistent Consistent with NUREG-1801.

NUREG-1801. The StructuresStructures members; members; material due to material due Monitoring Monitoring the scope the scope of of the the Monitoring Program, 8.2.1.33, Monitoring Program, B.2.1.33, will will be be used used toto manage manage welds; bolted welds; bolted general and general and Program Program applicant's applicant's loss of material due of material due toto general, pitting, and crevice crevice connections; connections; pitting Structures Structures corrosion for steel support members; members; welds; bolted support corrosion Monitoring Monitoring connections; support anchorage anchorage to building structure.

anchorage to Program See See subsection 3.5.2.2.2.6 subsection 3.5.2.2.2.6 building building structure structure 3.5.1-40 Building Reduction in Reduction in Structures Structures Yes, if if not within Consistent with NUREG-1801.

NUREG-1 801. The Structures Structures concrete at concrete Monitoring Monitoring the scope of the Monitoring Program, Monitoring Program, B.2.1.33, will be used to manage manage locations of locations anchor Program Program applicant's reduction in reduction in concrete anchor anchor capacity due to local expansion and capacity due to Structures concrete degradation/ service-induced cracking or other degradation! service-induced grouted grouted local concrete local concrete Monitoring Monitoring concrete aging concrete mechanisms in aging mechanisms in building building concrete concrete atat anchors; grout degradation/

degradation! Program Program locations locations of expansion expansion and grouted grouted anchors; grout pads pads pads for service- for support base plates.

forsupport support base induced plates cracking or other concrete See subsection 3.5.2.2.2.6 3.5.2.2.2.6 aging mechanisms mechanisms 3.5.1-41 3.5.1-41 Vibration Reduction or Structures Structures Yes, if if not within Consistent with NUREG-1801.

NUREG-1801. The StructuresStructures isolation loss of isolation Monitoring Monitoring the scope of the the the Monitoring Program, B.2.1.33, Monitoring B.2.1.33, will be used used to manage manage elements function/

function! Program Program applicant's elastomers for reduction or loss of isolation function due due radiation radiation Structures Structures to exposure to to exposure to radiation radiation hardening, hardening, temperature, hardening, Monitoring Monitoring humidity, or sustained vibratory vibratory loading loading for vibration-temperature, Program isolation elements in in the Component Supports Supports humidity, humidity, Commodity Group.

Commodity Group.

sustained vibratory See subsection 3.5.2.2.2.6 loading See subsection 3.5.2.2.2.6 Salem Nuclear Nuclear Generating Generating Station, Unit No. 1 and Unit No.

Unit No.1 No.22 Page 3.5-73 License Renewal Renewal Application Application

Section 3 - Aging Management Management Review Review Results Results Table 3.5.1 Summary Summary of Aging Management Management Evaluations Evaluations for Structures Component Supports Structures and Component Supports Effect/

Aging Effect! Aging Aging Further Further Item Number Component Management Management Evaluation Discussion Discussion Number Component Mechanism Mechanism Programs Recommended Programs Recommended 3.5.1-42 3.5.1-42 Groups B1.1, Groups B1.1, Cumulative Cumulative TLAA, evaluated in evaluated in Yes, TLAA Yes, TLAA current licensing basis contains no Not Applicable. Salem current B13.2, B1.2, and B1.3: damage fatigue damage accordance accordance with 1100 analysis for fatigue analysis component supports for component supports members, members,..

support support (CLB fatigue 54.21(c)

CFR 54.21 (c) anchor bolts, and welds of Groups anchor Groups B13.1, B13.3 B1.1, B1.2, and B1.3 members:

members: analysis exists) Therefore a TLAA is not evaluated component supports. Therefore anchor bolts, anchor bolts, in accordance with 10 CFR 54.21 in accordance (c) for these 54.21(c) welds welds components.

See subsection See 3.5.2.2.2.7.

subsection 3.5.2.2.2.7.

3.5.1-43 Groups Groups 1-3, 5, 5, Cracking Cracking due Masonry Wall Masonry No Consistent with NUREG-1801.

NUREG-1801. The Masonry Masonry Wall masonry 6: all masonry to restraint Program B.2.1.32, as implemented Program, B.2.1.32, implemented by the Structures Structures block walls shrinkage, Monitoring Program, B.2.1.33, Monitoring 8.2.1.33, will be used to manage manage creep, and cracking due to restraint shrinkage, creep, and aggressive aggressive aggressive environment of all masonry block walls.

environment environment Components in Components in the the Fire Protection system Fire Protection have been system have been aligned to this item number based on material, environment and environment and aging effect.

effect. The The Fire Fire Protection Protection Program, B.2.1.15; Program, B.2.1.15, will will be be added added to manage cracking due due to restraint shrinkage, creep, and aggressive aggressive environment environment of fire barrier masonry block walls for this this system.

3.5.1-44 Group 6 Loss of sealing Structures No Consistent with NUREG-1801.

NUREG-1801. The StructuresStructures elastomer elastomer due to Monitoring Monitoring Program, B.2.1.33, 8.2.1.33, will be used to manage manage seals, gaskets, seals, gaskets, deterioration deterioration of of Program Program loss of loss of sealing due due toto deterioration deterioration ofof elastomer seals, elastomer seals, and moisture seals, gaskets, gaskets, and moisture barriers (caulking, flashing, and barriers barriers and moisture other sealants) of structures.

barriers barriers (caulking, flashing, and other sealants)

Salem Nuclear Nuclear Generating No. 1 and Unit No.2 Generating Station, Unit No.1 No. 2 Page 3.5-74 Page Renewal Application License Renewal Application

  • * *
  • Review Results Table 3.5.1 Summary of Aging ManagementManagement Evaluations Evaluations for Structures and Component Supports Item Effectl Aging EffectJ Aging Aging Further Number Component Component Management Management Evaluation Discussion Discussion Number Mechanism Mechanism Programs Recommended Programs Recommended 3.5.1-45 3.5.1-45 Group Group 6: 6: Loss of Loss of Inspection of Inspection of No Consistent with NUREG-1801.

NUREG-1801. The RG 1.127, Inspection exterior above exterior above material due to Water-Control Water-Control of Water Control Structures Associated with Nuclear Nuclear and below below abrasion, abrasion, Structures or Power Plants program, B.2.1.34, as implemented by the the grade concrete grade concrete cavitation cavitation FERC/US Army FERC/US Army Structures Monitoring Monitoring Program, B.2.1.33, will be used to foundation; foundation; Corps of Engineers Corps Engineers monitor loss of material material due to abrasion and cavitation in in interior slab interior slab dam inspections dam inspections water control structures (Group 6 structures).

water maintenance and maintenance Components Components in in the Service Service Water System have been aligned aligned to this item number based on material, environment environment and aging effect. The Open-Cycle Cooling Cooling Water System Program, Water System Program, B.2.1.11, B.2.1.11, will will be be substituted substituted to manage loss manage loss of material material duedue to to abrasion and cavitation abrasion and cavitation for reinforced concrete for reinforced concrete piping piping and fittings for and fittings for this system this system exposed to to (flowing) raw raw water.

water.

Components Components in in the Fuel Handling Handling Building have been aligned to this item number based on material, environment environment and aging effect. The Structures Monitoring Monitoring Program, B.2.1.33, will be substituted to manage manage the loss loss of material material due to abrasion and cavitation cavitation for the the accessible accessible concrete trench trench exposed to flowing water water in in the Fuel Handling Handling Building.

Salem Nuclear Nuclear Generating Station, Unit Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-75 License Renewal Application License Renewal Application

Section 3 -- Aging Management Management Review Results Results Table Table 3.5.1 3.5.1 Summary of Aging Management Evaluations for Structures Management Evaluations Structures and Component Component Supports Supports Item Aging Effect/

Aging Effect! Aging Further Further Item Component Mechanism Management Management Evaluation Evaluation Discussion Number Number Mechanism Programs Recommended Recommended 3.5.1-46 3.5.1-46 Group 5: Fuel Cracking due Water Chemistry No NUREG-1801. The Water Chemistry Consistent with NUREG-1801.

pool liners pool liners to stress to stress and monitoring of program, B.2.1.2, monitoring of spent fuel pool water program, corrosion spent fuel pool level per Technical Specification Specification requirements, and cracking; loss cracking; in water level in monitoring leakage from the leak chase channels in monitoring in of material due accordance accordance with accordance with Salem procedures, will be used to accordance to pitting to pitting and technical manage loss of material due to pitting and crevice manage crevice crevice crevice specifications specifications and corrosion of the Fuel Handling Building spent fuel pool corrosion leakage leakage from the liner and components.

leak chase chase channels.

3.5.1-47 3.5.1-47 Group 6: all Loss of Inspection of No NUREG-1801. The RG 1:127, Consistent with NUREG-1801. 11127, metal structural metal material due to material Water-Control Water-Control Inspection Inspection ofof Water Control Structures Structures Associated with members members general general (steel Structures Structures or Nuclear Nuclear Power Power Plants program, B.2.1.34, as only), pitting FERC/US Army implemented by the Structures implemented Structures Monitoring Monitoring Program, and crevice Corps of Engineers B.2.1.33, B.2: 1.33, will be used to monitor monitor loss of material due to corrosion corrosion dam inspections inspections general (steel only), pitting and crevice corrosion in crevice corrosion in water and maintenance.

maintenance, control structures (Group (Group 6 structures).

Ifprotective If protective Protective coatings are not credited for managing the Protective coatings are not credited for managing the coatings are relied effects of aging effects of aging of of steel components.

steel components.

manage upon to manage aging, protective protective Components Components in Group 33 Structures in Group Structures (Auxiliary (Auxiliary Building, Building, coating monitoring coating monitoring Penetration Areas, Turbine Building and Yard Structures)

Penetration and maintenance maintenance have been have been aligned aligned toto this item item number number based based onon material, material, provisions should provisions should environment, and aging effect. The StructuresStructures be included.

be included. substituted to Monitoring Program, B.2.1.33, will be substituted Monitoring manage manage the the loss loss of material due of material to general, pitting and due to and crevice corrosion of the copper flashing, and cast iron hatches hatches oror manhole manhole covers, covers, and steel (sump) and steel liner and (sump) liner and integral attachments in integral attachments these structures in these structures and and component component supports.

supports.

Salem Nuclear Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-76 Renewal Application License Renewal

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  • Review Results Results Table 3.5.1 Summary of Aging Management Evaluations Aging Management Evaluations for Structures Structures and Component Component SupportsSupports Effect/

Aging Effect! Aging Aging Further Further Item Number Number Component Component Management Management Evaluation Evaluation Discussion Discussion Mechanism Mechanism Programs Programs Recommended Recommended

-

3.5.1-48 Group 6: Loss of Inspection of No Consistent NUREG-1801. The RG 1.127, G.Qnsistent with NUREG-1801. Inspection 1.127, Inspection earthen water material, loss Water-Control Water-Control of Water Control Structures Structures Associated Nuclear Associated with Nuclear control of form due to Structures or Power Power Plants program, B.2.1.34, as implemented implemented by the the structures - erosion, FERC/US Army Structures Monitoring Program, 8.2.1.33, Structures Monitoring B.2.1.33, will be used used to dams, settlement, Engineers Corps of Engineers monitor loss of material, loss of form due to erosion, monitor embankments, sedimentation, sedimentation, dam inspections settlement, sedimentation, frost action, waves, currents, reservoirs, frost action, and maintenance maintenance surface runoff, seepage in in earthen earthen water control channels, waves, programs structures (Group 6 structures).

structures canals, and currents, ponds surface surface runoff, Seepage Seepage 3.5.1-49 3.5.1-49 Support Loss of Water Chemistry No No Not Applicable.

Applicable. This component, material, environment, members; material/

material! and ISI(IWF)

ISI(IWF) effect/mechanism does not apply. These and aging effect/mechanism These welds; bolted general, pitting, support members, welds, bolted connections, and connections; and crevice anchorages to building structure support anchorages structure are addressed support .' corrosion 3.3.1-91.

under Item Number 3.3.1-91.

anchorage to anchorage building building structure structure Salem Nuclear Generating Station, Unit No.1 Nuclear Generating No. 1 and Unit No.2 No. 2 Page Page 3.5-77 Renewal Application License Renewal Application

Section Section 33 - Aging Aging Management Management Review Results Results Table Table 3.5.1 3.5.1 Summary Summary of of Aging Management Evaluations Aging Management Evaluations for Structures Structures and and Component Component Supports Supports Item Aging Aging Effect/

Effect! Aging Further Further Item Component Management Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Programs Programs Recommended Recommended

,

3.5.1-50 Groups B2, 82, Loss of Structures Structures No No Consistent Consistent with NUREG-1801.

NUREG-1 801. The The Structures Structures and B4:

and 84: material material due due to Monitoring Monitoring Monitoring Program, B.2.1.33, Monitoring Program, 8.2.1.33, will be usedused to manage manage galvanized galvanized pitting pitting and Program Program loss of material material due to general, pitting, and crevice crevice steel, steel, crevice crevice corrosion corrosion in galvanized galvanized steel, steel, aluminum, aluminum, and stainless stainless aluminum, corrosion steel steel support members members exposed to outdoor air for Group Group stainless steel B2 82 and Group 84 B4 Component Component Supports.

support members; welds; bolted welds; Section Xl, The ASME Section XI, Subsection program, Subsection IWF program, connections; connections; 8.2.1.30, manage loss of material substituted to manage B.2.1.30, will be substituted support crevice corrosion for stainless steel due to pitting and crevice steel anchorage to anchorage supports for ASME Class 2 and supports piping and components anc;l 3 piping components building members; welds; (Support members; connections; and welds; bolted connections; and structure support anchorage support exposed to building structure) exposed anchorage to building to outdoor air.

air. .

The Periodic Inspection, B.2.2.2, program Inspection, 8.2.2.2, program will be be substituted substituted to manage manage the loss of materialmaterial due to pitting pitting and crevice corrosion corrosion for aluminum aluminum and and stainless steel Insulation jacketing Insulation jacketing (includes wire mesh, straps, clips) exposed exposed to outdoor outdoor air air for for the Piping Piping and and Component Component Insulation Commodity Commodity Group.

The The RGRG 1.127, 1.127, Inspection Inspection of of Water-Control Water-Control Structures Structures Associated with Nuclear Power Plants program, B.2.1.34, 8.2.1.34, will be substituted substituted to manage loss of material material due to general, pitting, pitting, and crevice corrosion corrosion of the stainless stainless steel and stainless steel and steel bolting stainless steel bolting exposed exposed to outdoor air to outdoor air at at the the Service Water Intake Service Water Intake Structure.

Structure.

Components in Components in the Auxiliary Auxiliary Systems, Systems, Engineered Engineered Safety Safety Features, Steam Features, Steam and and Power Power Conversion Conversion Systems, Systems, and and Electrical Components Electrical Components have have been been aligned aligned to to this this item item number based number based on on material, material, environment environment and and aging aging effect.

effect.

The Periodic The Periodic Inspection Inspection Program, Program, 8.2.2.2, B.2.2.2, Aboveground Aboveground Salem Nuclear Generating Generating Station, Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-78 Renewal Application License Renewal Application

  • * *
  • Review Results Results Table Table 3.5.1 Summary of Aging Management Summary Management Evaluations Evaluations for Structures Structures and Component Component SupportsSupports Item Effect]

Aging Effect! Aging Further Further Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Recommended Recommended Non-Steel Tanks Program, B.2.2.3, and Bolting Integrity Non-Steel Program, B.2.1.9, will be substituted to monitor loss of material due to general, material general, pitting, and crevice corrosion of galvanized steel, aluminum, galvanized aluminum, and stainless steel piping, tanks, birdscreens, and other miscellaneous components components for these systems in in the outdoor air environment.

Metal Enclosed Metal Enclosed BusBus components components in the Electrical in the Electrical Commodities System have been aligned to this item number based number on material, based on environment and material, environment and aging aging effect.

effect.

Consistent with NUREG-1801, NUREG-1801, the Structures Monitoring Monitoring Program, B.2.1.33, 8.2.1.33, will be used to manage manage loss of material due to general, pitting, and crevicecrevice corrosion corrosion in in Metal Enclosed Bus members exposed to the aluminum Metal the outdoor air environment.

3.5.1-51 Group B1.1: Cracking due Bolting Integrity Integrity No Components in Components the Component in the Component Supports Supports Commodity Commodity high strength to stress stress Group have have been aligned to this-item this"item number basedbased on low-alloy low-alloy bolts corrosion material, environment environment and aging effect. The ASME cracking; loss cracking; loss Section XI, Section XI, Subsection Subsection IWF IWF program, B.2.1.30, will program, B.2.1.30, will be be material due of material substituted substituted to manage loss of material material due to general to general general corrosion corrosion for high high strength low-alloy low-alloy steel bolts bolts used used for corrosion corrosion Groups B1.1 component Groups B1.1 supports for component supports for these these structures structures in in the air indoor environment.

Salem does have high strength low-alloy bolts associated with supports for ASME Class 1 piping and components.

- However, cracking However, due to cracking due to stress stress corrosion cracking corrosion cracking (SCC) is not applicable due to low preload stress stress levels.

Supports Supports for the Reactor Coolant Pumps and Unit 11 Steam Generators Generators have high strength maraging maraging steel steel bolts (Vascomax 200, 300) with actual yield strength greater than 150 ksi. The bolts are not preloaded (not torqued) and are not subject to high tensile stress or a Salem Nuclear Salem Generating Station, Nuclear Generating Station, Unit Unit No.1 and Unit No. 1 and Unit No.2 No. 2 Page 3.5-79 Renewal Application License Renewal Application

Section Section 3 - Aging Management Management Review Review Results Results Table 3.5.1 3.5.1 Summary of Aging Management Management Evaluations Evaluations for Structures and Component Component Supports Effect/

Aging Effect! Aging Aging Further Further Item Component Management Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Programs Programs Recommended Recommended corrosive environment. A A review of plant operating operating instances of see experience has not identified any instances SCC for the bolts. Therefore cracking due to stress corrosion cracking is not an aging effect requiring aging management. Loss management Loss of of material material is the only is the only aging aging effect effect requiring aging management.

management. Supports for the Unit 2 Generators are a different Steam Generators different material material (high strength stainless steel bolts) where this line item is not applicable applicable and stress corrosion applicable due to low corrosion cracking is not applicable preload stress preload stress levels and also levels and also loss loss of of material material due due to to in the indoor air environment corrosion in environment is not applicable applicable for stainless stainless steel.

Salem Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.

No.22 Page Page 3.5-80 License Renewal Renewal Application Application

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  • Section
  • Management Review Results Section 3 - Aging Management Results Table 3.5.1 Summary Summary of Aging Management Evaluations Aging Management Evaluations for Structures Structures and Component Component Supports Supports Item Aging Effect/

Aging Effect! Aging Further Further Item Component Management Evaluation Evaluation Discussion Number Number Mechanism Mechanism Management Programs Programs Recommended Recommended 3.5.1-52 Groups Groups B2, Loss of Structures Structures No Components Components in inthe Component Component Supports Commodity and B4: sliding mechanical mechanical Monitoring Monitoring Group Group have beenbeen aligned to this item number based based on support support function due to Program Program material, environment and aging effect. The ASME material, environment ASME bearings and corrosion, Section XI, Subsection IWF program,program, B.2.1.30, will bebe sliding support distortion, dirt, substituted substituted to manage loss of mechanical mechanical function due to surfaces surfaces overload, corrosion, distortion, distortion, dirt, overload, fatigue due to fatigue due to vibratory and cyclic thermal loads in in Group B1 sliding vibratory and support bearings bearings and sliding support surfaces surfaces that were cyclic thermal aligned to this item number based on material, material, loads environment, and aging effect.

There were There were no no Group Group B2 B2 or or B4 components associated B4 components associated with this item number.

3.5.1-53 Groups B1.1, B13.1, Loss of ISI (IWF) lSI No Consistent with NUREG-1801.

NUREG-1801. The ASME Section Section XI, XI, B1.2, and B1.3: material due to Subsection Subsection IWF program, B.2.1.30, will be used used to support support general general and manage loss of material due to general, pitting and manage members:

members: pitting crevice corrosion in in Groups B1.1, B1.1, B1.2, and B1.3 steel welds; bolted corrosion component component supports.

connections; support anchorage to anchorage building building structure structure Salem Nuclear Nuclear Generating Station, Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-81 Page 3.5-81 Renewal Application License Renewal Application

Section Section 3 - Aging Aging Management Review Results Management Review Results Table 3.5.1 Summary of Aging Summary Management Evaluations Aging Management Evaluations for Structures Structures and Component Component Supports Supports Item Aging Effect/

Aging Effect! Aging Further Further Item Component Mechanism Management Management Evaluation Evaluation Discussion Number Number Mechanism Programs Recommended Recommended 3.5.1-54 Groups B1.1, B1.1, Loss of ISI lSI (IWF) No Consistent with NUREG-1801.

NUREG-1801. The ASME Section Section Xl,XI, B1.2, and B1.3: mechanical mechanical Subsection IWF program, B.2.1.30, will be used to Constant and function due to manage loss of mechanical mechanical function due to corrosion, variable load variable load corrosion, corrosion, distortion, dirt, overload, fatigue due to vibratory and spring hangers; distortion, dirt, cyclic thermal loads in in Groups B1.1, B1.1, B1.2, and B1.3 steel steel guides; stops; overload, component supports.

fatigue due to to vibratory and cyclic thermal loads loads 3.5.1-55 Steel, Loss of Boric Acid No Consistent with NUREG-1801.

NUREG-1801. The Boric Acid Corrosion galvanized galvanized material due to Corrosion program, B.2.1.4, will be used to manage loss of material steel, and boric acid boric acid due to boric acid corrosion in in steel, galvanized steel, and aluminum aluminum corrosion aluminum support members, welds, bolted connections connections support anchorage to building structure.

and support anchorage members; welds; bolted connections; support anchorage to anchorage building building structure structure Salem Nuclear Salem Generating Station, Unit No.

Nuclear Generating No.11 and and Unit Unit No.2 No. 2 Page Page 3.5-82 License Renewal Application License Renewal Application

  • * *
  • Management Review Results Table 3.5.1 Summary Summary of Aging Management Management Evaluations for Structures Structures and Component Component Supports Aging Effect/

Effect! Aging Aging Further Item Component Management Management Evaluation Evaluation Discussion Number Number Component Mechanism Mechanism Programs Programs Recommended Recommended 3.5.1-56 Groups 81.1, B13.1, Loss of ISI (lWF) lSI (IWF) No Consistent Consistent with NUREG-1801.

NUREG-1801. The ASME Section XI, Xl, B1.2, 81.2, and B1.3:

81.3: mechanical mechanical Subsection Subsection IWF program, B.2.1.30,8.2.1.30, will be used to Sliding function due to manage manage loss of mechanical mechanical function due to corrosion, surfaces surfaces corrosion, distortion, dirt, overload, and fatigue due to vibratory and and distortion, dirt, cyclic thermal loads in in Group B13.2 81.2 sliding surfaces.

overload, fatigue due to vibratory and cyclic thermal loads loads 3.5.1-57 3.5.1-57 Groups 81.1, Reduction or Reduction ISI (IWF) lSI No Not Applicable. This component, material, material, environment, B13.2, 81.2, and 81.3:

B1.3: loss of isolation and aging effect/mechanism effect/mechanism does not apply. Salem Vibration Vibration function/

function! design does not include vibration isolation elements elements inin isolation radiation B1.1, 81.1, B1.2, 81.2, and B1.3 81.3 component component supports. Salem does does elements elements hardening, hardening, have vibration isolation elements which are not temperature, temperature, associated with ASME piping supports. These non ASME ASME humidity, vibration isolation isolation elements are addressed addressed under Item sustained Number Number 3.5.1-41 and managedmanaged using the Structures Structures vibratory Monitoring Program, Monitoring B.2.1.33.

Program, 8.2.1.33.

loading loading Nuclear Generating Station, Salem Nuclear Station, Unit No.

No.11 and Unit No.2 No. 2 Page Page 3.5-83 License Renewal Application License Renewal

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table 3.5.1 Table 3.5.1 Summary of Aging Summary Aging Management Management Evaluations Evaluations for Structures Structures and and Component Component Supports Supports Item Aging Effect/

Aging Effect! Aging Aging Further Further Item Component Management Management Evaluation Evaluation Discussion Discussion Number Number Mechanism Mechanism Programs Programs Recommended Recommended 3.5.1-58 3.5.1-58 Galvanized Galvanized None None None None NA NA-- No AEM or NoAEM Consistent with NUREG-1 Consistent NUREG-1801. galvanized steel 801. The galvanized steel and steel steel and AMP AMP aluminum support aluminum support members, welds, bolted bolted connections, connections, aluminum aluminum and support support anchorages anchorages to buildingbuilding structure exposed to structure exposed to support support indoor indoor air air for the material/environment material/environment combination combination has has members; no aging effect/mechanism effect/mechanism that requires requires aging aging welds; welds; bolted management.

connections; connections; Metal Metal Enclosed Enclosed Bus Bus components components in in the Electrical the Electrical

.. --

-support support - "_ .. -

Commodities System.have been Commodities System .have been .alignedto aligned this .item..

to this item. .

-andl0rage to .. number number based based on material, environment on material, environment and and aging effect.

aging effect.

building No No AMPs AMPs areare required required as as no no aging aging effects are applicable effects are applicable structure to the aluminum items exposed to indoor to the aluminum items exposed to indoor air for the air for the exposed to air - Electrical Electrical Commodities System associated with this Commodities System associated with item this item indoor number.

number.

uncontrolled uncontrolled 3.5.1-59 3.5:1-59 Stainless steel None None None NA NA-- NoAEM No AEM or Consistent Consistent with NUREG-1 NUREG-1801. 801. The stainless stainless steel support AMP material material exposed to the indoor indoor air and and indoor air with members; members; borated borated water leakage environment water leakage environment combination combination has no no welds; bolted aging effect/mechanism effect/mechanism that requires aging connections; connections; management.

management.

support Components Components in in Containment Containment Ventilation Ventilation andand Control Control AreaArea anchorage to anchorage Ventilation Systems have been aligned Ventilation Systems have been aligned to this item to this item building number based on number based on material, material, environment environment and aging effect.

and aging effect.

structure No AMPs No AMPs are required as are required as no no aging aging effects are applicable effects are applicable to the stainless stainless steel components for the systems systems associated associated with thisthis item number.

number.

Salem Nuclear Generating Generating Station, Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-84 License Renewal Application License

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  • *
  • Section 3 - Aging Management Review Review Results Results Table 3.5.2-1 Auxiliary Auxiliary Building Building Summary Summary of Aging Management Evaluation Aging Management Evaluation 3.5.2-1 Table 3.5.2-1 Building Auxiliary Building Component Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Blowout Panel Pressure Pressure Relief Aluminum Aluminum Air- Indoor Air-Indoor None None None I11.B5-2 III.B5-2 3.5.1-58 C Blowout Panel Pressure Pressure Relief Aluminum Aluminum Air - Outdoor Material/Pitting Loss of Material/Pitting Structures Monitoring Structures II1.B2-7 III.B2-7 3.5.1-50 C and Crevice Corrosion Program Program Blowout Panel Protection Shelter, Protection Aluminum Aluminum Air- Indoor Air-Indoor None None None I11.B5-2 III.B5-2 3.5.1-58 C Blowout Panel Shelter, Protection Protection Aluminum Aluminum Air-- Outdoor Air Loss of Material/Pitting Material/Pitting Structures Monitoring Structures II1.B2-7 III.B2-7 3.5.1-50 C and Crevice Corrosion Program Program Bolting (Structural) Structural Support Aluminum Aluminum Bolting Air - Indoor Air-Indoor Loss of Preload/Self- Structures Monitoring Structures H, 1 H,1 Loosening Loosening Program Program Bolting (Structural) Structural Support Aluminum Aluminum Bolting Air - Outdoor Material/Pitting Loss of Material/Pitting Structures Monitoring Structures II1.B2-7 III.B2-7 3.5.1-50 C and Crevice Corrosion Program ProQram Bolting (Structural) Structural Support Aluminum Aluminum Bolting Air - Outdoor Loss of Preload/Self- Structures Monitoring Structures H, 1 H,1 Loosening Loosening Program Program Bolting (Structural) Structural Support Aluminum Aluminum Bolting Air with Borated Material/BoricAcid Borated Water Loss of Material/Boric Acid Boric Acid Corrosion II1.B5-4 III.B5-4 3.5.1-55 A Leakage Leakage Corrosion Bolting (Structural) Structural Support Carbon Carbon and Low Air - Indoor Air-Indoor Loss of Material/General, Material/General, Structures Monitoring Structures II1.A3-12 III.A3-12 3.5.1-25 A A

Alloy Steel Pitting and Crevice Program Program Bolting Corrosion Bolting (Structural) Structural Support Carbon Carbon and Low Air - Indoor Air-Indoor Loss of Preload/Self- Structures Monitoring VII.I-5 VIU-5 3.3.1-45 E, 1 E,1 Alloy Steel Loosening Loosening Program Bolting Bolting Bolting (Structural) Structural Support Support Carbon Carbon and Low Air-Air - Outdoor Loss of Material/General, Material/General, Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 A A

Alloy Steel Pitting and and Crevice Program Bolting Corrosion Bolting Bolting (Structural) Structural Structural Support Support Carbon Carbon and Low Air - Outdoor Loss of Preload/Self- Structures Monitoring H, 1 H,1 Alloy Steel Loosening Loosening Program Bolting Salem Nuclear Generating Salem Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-85 License Renewal Application

Management Review Results Section 3 - Aging Management Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Building Building (Continued)

Component Component Intended Material Material Environment Environment Aging Effect Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Function Requiring Requiring Programs Vol. 2 ItemItem Management Management Bolting (Structural) Structural Support Borated Water Loss of Material/BoricAcid Carbon and Low Air with Borated Material/Boric Acid Boric Acid Corrosion Corrosion III11.B5-8 I. B5-8 3.5.1-55 A A

Alloy Steel Leakage Leakage Corrosion Corrosion Bolting Bolting Bolting (Structural) Structural Support Galvanized Steel Galvanized Air - Indoor Air-Indoor Loss of Preload/Self- Structures Structures Monitoring Monitoring VII.I-5 VIU-5 3.3.1-45 E, 1 E,1 Bolting Loosening Program Bolting (Structural) Structural Support Galvanized Steel Galvanized Air-- Outdoor Air Loss of Material/General, Material/General, Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A A

Bolting Pitting and Crevice Program Corrosion Bolting (Structural) Structural Support Galvanized Steel Galvanized Air -- Outdoor Loss of Preload/Self- Structures Structures Monitoring H, H,11 Bolting Loosening Program Bolting (Structural) Structural Support Galvanized Material/Boric Acid Galvanized Steel Air with Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion II1.B5-4 III.B5-4 3.5.1-55 A A

Bolting Leakage Leakage Corrosion Bolting (Structural) Structural Support Stainless Steel Air - Indoor Air-Indoor Loss of Preload/Self- Structures Structures Monitoring H, H,11 Bolting Loosening Program Bolting (Structural) Structural Support Stainless Steel Air - Outdoor Loss of Material/Pitting Material/Pitting Structures Structures Monitoring III.B2-7 III.B2-7 3.5.1-50 C Bolting and Crevice Crevice Corrosion Program Bolting (Structural) Structural Support Stainless Steel Air - Outdoor Loss of Preload/Self- Structures Structures Monitoring Monitoring H, H,11 Bolting Loosening Program Bolting (Structural) Structural Support Stainless Steel Air with Borated Borated Water None None II111.B5-6 I. B5-6 3.5.1-59 A A

Bolting Leakage Leakage Cable Trays Structural Support Aluminum Aluminum Air- Indoor Air-Indoor None None 111.B5-2 III.B5-2 3.5.1-58 C Cable Trays Structural Support Aluminum Aluminum Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion II1.B5-4 III.B5-4 3.5.1-55 C Leakage Leakage Corrosion Cable Trays Structural Support Structural Galvanized Steel Galvanized Air --Indoor Indoor None None II111.B5-3 I. B5-3 3.5.1-58 C Cable Trays Galvanized Steel Air with Borated Water Loss of Material/Boric Structural Support Galvanized Structural Material/Boric Acid Boric Acid Corrosion Corrosion IIIII.B5-4 I. B5-4 3.5.1-55 C Leakage Leakage Corrosion Compressible Compressible Expansion / Elastomers Elastomers Air- Indoor Air-Indoor Increased Increased Hardness, Structures Structures Monitoring VII.G-1 3.3.1-61 E,2 E,2 Joints and Seals Separation Shrinkage and Loss of Shrinkage Program (Seismic Gap) I StrengthlWeaihering I Strength/Weathering Compressible Compressible Expansion / Elastomers Elastomers Air-Air - Outdoor Outdoor Increased Increased Hardness, Structures Structures Monitoring VII.G-2 3.3.1-61 E, 2 E,2 Joints and Seals Separation Shrinkage Shrinkage and Loss of Program (Seismic Gap) StrengthlWeathering Strength/Weathering Salem Nuclear Salem Nuclear Generating Generating Station, Unit No.1 Station, Unit No. I and and Unit No.2 No. 2 Page Page 3.5-86 3.5-86 0

License License Renewal Renewal Application

  • Application
  • Section 33 -- Aging Section
  • Management Review Aging Management Review Results Results 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Intended Intended Material Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes

.Type Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Concrete Concrete Curbs Direct Flow Concrete Air --Indoor Indoor Cracking, Loss of Bond, Structures Monitoring Structures Monitoring III.A3-9 3.5.1-23 A and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Concrete Concrete Curbs Direct Flow Concrete Concrete Air- Indoor Air-Indoor Cracks and Structures Monitoring Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 A A

Distortion/Increased Distortion/Increased Program Stress Levels Levels from Settlement Settlement Concrete Concrete Curbs Direct Flow Concrete Air-Air - Outdoor Outdoor Cracking, Loss of Bond, Structures Monitoring Structures Monitoring III.A3-9 III.A3-9 3.5.1-23 A and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Steel Concrete Curbs Concrete Direct Flow Concrete Concrete Air-- Outdoor Air Outdoor Cracks and Structures Monitoring Structures III.A3-3 III.A3-3 3.5.1-28 3:5.1-28 A A-Distortion/Increased Distortion/Increased Program Stress Levels from from Settlement Settlement Concrete Curbs Direct Flow Concrete Concrete Air - Outdoor Loss of Material Material (Spalling, Structures Monitoring III.A3-6 III.A3-6 3.5.1-26 A A

Scaling) and Program Cracking/Freeze-thaw Cracking/Freeze-thaw Concrete anchors Concrete anchors Structural Support Structural Support Carbon and Low Air - Indoor Air-Indoor Material/General, Loss of Material/General, Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

Alloy Steel Pitting and and Crevice Program Bolting Bolting Corrosion Concrete anchors Concrete Support Structural Support Carbon and Low Air-Air - Outdoor Loss of Material/General, Material/General, Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

Alloy Steel Pitting and Crevice Program Bolting Corrosion Concrete anchors Concrete StructuralSupport StructuraL Support Carbon and Low Air with Borated Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion III.B5-8 II I. B5-8 3.5.1-55 C Alloy Steel Leakage Leakage Corrosion Bolting Bolting Concrete anchors Concrete Structural Support Support Carbon Carbon and Low Concrete Concrete None None VII.J-21 3.3.1-96 C Alloy Steel Bolting Bolting Concrete Concrete Structural Support Support Carbon Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 A A

embedments embedments I Corrosion Program I Salem Nuclear Generating Station, Unit No.1 Nuclear Generating No. 1 and Unit No.2 No. 2 Page 3.5-87 Page 3.5-87 Renewal Application License Renewal Application

Section 3 - Aging Aging Management Management Review Results Review Results 3.5.2-1 Table 3.5.2-1 Auxiliary Auxiliary Building (Continued)

Component Component Intended Intended Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Requiring Programs Programs Vol. 2 Item Item Management Management Concrete Concrete Structural Structural Support Carbon Carbon Steel Steel Air - Outdoor Loss of Material/General, Structures Monitoring I11.A3-12 III.A3-12 3.5.1-25 A embedments embedments Pitting and Crevice Program Program Corrosion Concrete Concrete Structural Structural Support Carbon Carbon Steel Steel Air with Borated Water Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion I13.B5-8 III.B5-8 3.5.1-55 C embedments embedments Leakage Leakage Corrosion Concrete Concrete Structural Structural Support Support Carbon Carbon Steel Steel Concrete None None VII.J-21 3.3.1-96 C embedments embedments Concrete:

Concrete: Above- Flood Barrier Barrier Reinforced Reinforced Air - Outdoor Cracking, Cracking, Loss of Bond, Structures Monitoring Structures II1.A3-9 III.A3-9 3.5.1-23 3.5.1-23 A grade exterior concrete concrete and Loss of Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Embedded Steel Concrete:

Concrete: Above- Flood Barrier Barrier Reinforced Reinforced Air-- Outdoor Air Cracks and and Monitoring Structures Monitoring III.A3-3 3.5.1-28 3.5.1-28 A grade grade exterior concrete concrete Distortion/Increased Distortion/I ncreased Program Stress Levels from Settlement Settlement Concrete: Above- Flood Barrier Barrier Reinforced Reinforced Air -- Outdoor Loss of Material (Spalling, Structures Monitoring Structures Monitoring II1.A3-6 III.A3-6 3.5.1-26 3.5.1-26 A grade grade exterior concrete concrete Scaling) and Program Cracking/F reeze-thaw Cracking/Freeze-thaw Concrete: Above- Missile Barrier Reinforced Reinforced Air -- Outdoor Cracking, Loss of Bond, Structures Monitoring Structures Monitoring III.A3-9 3.5.1-23 3.5.1-23 A grade exterior grade exterior concrete concrete and Loss of Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded SteelSteel Concrete: Above- Missile Barrier Missile Reinforced Reinforced Air -- Outdoor Cracks and Structures Monitoring Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A grade exterior grade exterior concrete concrete Distortion/Increased Distortion/Increased Program Program Stress Levels from Settlement Settlement Concrete: Above- Missile Missile Barrier Reinforced Reinforced Air -- Outdoor Loss of Material (Spalling, Monitoring Structures Monitoring II1.A3-6 III.A3-6 3.5.1-26 3.5.1-26 A grade grade exterior concrete Scaling) and Program Cracking/Freeze-thaw Cracking/Freeze-thaw Concrete: Above-Above- Shelter, Protection Reinforced Reinforced Air-- Outdoor Air Cracking, Cracking, Loss of Bond, Monitoring Structures Monitoring III.A3-9 3.5.1-23 3.5.1-23 A grade grade exterior concrete concrete and Loss of Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Embedded Steel Salem Nuclear Salem Nuclear Generating Generating Station, Unit No.

Station, Unit No.11 and and Unit Unit No.2 No. 2 Page 3.5-88 3.5-88 License Renewal Renewal Application Application 0

  • *
  • License
  • Section 3 - Aging
  • Aging Management Review Results Table 3.5.2-1 3.5.2-1 Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801. Table Table 1 Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Concrete:

Concrete: Above- Shelter, Protection Reinforced Reinforced Air-Air - Outdoor Outdoor Cracks Cracks and Structures Structures Monitoring Monitoring III.A3-3 3.5.1-28 A A

grade exterior concrete Distortion/Increased Distortion/I ncreased Program Program Stress Levels Levels from Settlement Settlement Concrete: Above-Concrete: Shelter, Protection Protection Reinforced Air - Outdoor Loss of Material Material (Spalling, Structures Monitoring Structures Monitoring II1.A3-6 III.A3-6 3.5.1-26 A grade exterior concrete Scaling) and Program Program Cracking/Freeze-thaw Cracking/Freeze-thaw Concrete: Above- Structural Structural Support Reinforced Air - Outdoor Cracking, Loss of Bond, Structures Monitoring Structures II1.A3-9 III.A3-9 3.5.1-23 A A

grade exterior concrete concrete and Loss of Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Embedded Steel Concrete: Above- Structural Support Reinforced Reinforced Air-- Outdoor Air Cracks and Structures Monitoring Structures II1.A3-3 III.A3-3 3.5.1-28 A A

grade grade exterior exterior concrete concrete Distortion/Increased Distortion/I ncreased Program Program Stress Levels from from Settlement Settlement Concrete: Above-Above- Structural Support Reinforced Reinforced Air - Outdoor Loss of Material Material (Spalling, Structures Monitoring Structures III.A3-6 III.A3-6 3.5.1-26 A A

grade grade exterior exterior concrete concrete Scaling) and Program Cracking/Freeze-thaw Cracking/Freeze-thaw Concrete: Below-Concrete: Flood Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking, Cracking, Loss of Bond, Structures Monitoring III.A3-4 III.A3-4 3.5.1-31 A A

grade grade exterior exterior concrete concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Concrete: Below-Concrete: Below- Flood Barrier Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks and Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 A A

grade exterior exterior concrete concrete Distortion/Increased Distortion/I ncreased Program Stress Levels from Settlement Settlement Concrete: Below- Flood Barrier Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Porosity and Increase Structures Monitoring II1.A3-5 III.A3-5 3.5.1-31 A A

grade exterior exterior concrete concrete Permeability, Cracking, Permeability, Program Loss of Loss of Material (Spalling, Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack Chemical Generating Station, Unit No.1 Salem Nuclear Generating No. 1 and Unit No.2 No. 2 Page 3.5-89 3.5-89 License Renewal Application license Application

Section 3 - Aging Management Management Review Results Results Table 3.5.2-1 3.5.2-1 Auxiliary Building (Continued)

Component Component Intended Material Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Requiring Requiring Programs Vol. 2 Item Item Management Management Concrete:

Concrete: Below- Flood Barrier Reinforced Water Water - Flowing Increase in Porosity and in Porosity Structures Structures Monitoring Monitoring III.A3-7 3.5.1-32 A A

grade exterior concrete Permeability, Loss of Program Strength/ Leaching Leaching of Calcium Hydroxide Hydroxide Concrete:

Concrete: Below- Missile Barrier Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking, Loss of Bond, Structures Structures Monitoring II1.A3-4 III.A3-4 3.5.1-31 A A

grade exterior concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of of Embedded Embedded Steel Concrete: Below- Missile Barrier Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks and Structures Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 A A

grade exterior concrete Distortion/Increased Distortion/I ncreased Program Stress Levels Levels from Settlement Settlement Concrete:

Concrete: Below- Missile Barrier Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Porosity Increase Porosity and Structures Structures Monitoring II1.A3-5 III.A3-5 3.5.1-31 A A

grade exterior concrete Permeability, Cracking, Cracking, Program Loss of Material Material (Spalling, (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack Concrete:

Concrete: Below- Missile Barrier Missile Barrier Reinforced Reinforced Water-- Flowing Water Increase Porosity and Increase in Porosity and Structures Structures Monitoring II1.A3-7 III.A3-7 3.5.1-32 A A

grade exterior concrete Permeability, Loss of Permeability, Program Strength/ Leaching of Strength/ of Calcium Hydroxide Hydroxide Concrete: Below- Shelter, Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking, Loss of Bond, Structures Structures Monitoring II1.A3-4 III.A3-4 3.5.1-31 A A

grade exterior concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Steel Concrete: Below- Shelter, Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks and Structures Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 A A

grade exterior concrete Distortion/Increased Distortion" ncreased Program Program Stress Levels Levels from Settlement Settlement Concrete:

Concrete: Below- Shelter, Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Porosity Increase Porosity and and Structures Structures Monitoring II1.A3-5 III.A3-5 3.5.1-31 A A

grade exterior concrete concrete Permeability, Cracking, Permeability, Program Loss of Material Material (Spalling, Scaling)/ Aggressive Aggressive Chemical Attack "

Salem Nudear Nuclear Generating Station, Unit No.1 Generating Station, No. 1 and Unit No.2 No. 2 Page 3.5-90 Page License Renewal Application

  • *
  • Section 3 - Aging
  • Aging Management Review Results 3.5.2-1 Table 3.5.2-1 Auxiliary Building Building (Continued) -"

Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Function Requiring Requiring Programs Vol. 2 Item Item Management Management Concrete: Below- Shelter, Protection Reinforced Water-Water - Flowing Increase Increase inin Porosity and and Structures Structures Monitoring II1.A3-7 III.A3-7 3.5.1-32 A grade exterior concrete Permeability, Loss of Program Strength/ Leaching of Strength/ Leaching Hydroxide Calcium Hydroxide Concrete:

Concrete: Below- Structural Support Reinforced Groundwater/soil Grou ndwater/soil Cracking, Loss of Bond, Structures Structures Monitoring III.A3-4 III.A3-4 3.5.1-31 3.5.1-31 A A

grade exterior concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded SteelSteel Concrete: Below- Structural Support Structural Support Reinforced Reinforced Groundwater/soil Grou ndwater/soil Cracks Cracks and Structures Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 A grade exterior concrete Distortion/Increased Distortion/Increased Program Stress Levels from Stress Levels from Settlement Settlement Concrete:

Concrete: Below- Structural Support Reinforced Groundwater/soil Groundwater/soil Increase Increase inin Porosity and and Structures Structures Monitoring III.A3-5 III.A3-5 3.5.1-31 A A

grade exterior concrete Permeability, Permeability, Cracking, Program Loss of Material (Spalling, Aggressive Scaling)/ Aggressive Scaling)/

Chemical Attack Concrete: Below-Concrete: Structural Support Structural Support Reinforced Reinforced Water - Flowing Increase in Increase in Porosity and Structures Structures Monitoring II1.A3-7 III.A3-7 3.5.1-32 3.5.1-32 A A

grade grade exterior exterior concrete concrete Permeability, Loss of Permeability, Program Program Strength/ Leaching of Strength/

Hydroxide Calcium Hvdroxide Concrete:

Concrete: Flood Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking-, Loss of Bond, Cracking, Structures Monitoring Structures Monitoring II1.A3-4 III.A3-4 3.5.1-31 3.5.1-31 A A

Foundation concrete concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete:

Concrete: Flood Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks and Structures Monitoring Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A A

Foundation concrete concrete Distortion/Increased Distortion/I ncreased Program Program Stress*

Stress Levels from Settlement Settlement Concrete:

Concrete: Flood Barrier Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Porosity and Increase Structures Monitoring Structures Monitoring II1.A3-5 III.A3-5 3.5.1-31 3.5.1-31 A A

Foundation Foundation concrete concrete Permeability, Cracking, Permeability, Program Program Loss of Material (Spalling, (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack Salem Nudear Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-91 License Renewal Application Application

Section Section 33 -- Aging Review Results Management Review Aging Management Results 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary BLiilding (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Table Item Notes Notes Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Concrete: Barrier Flood Barrier Reinforced Reinforced Water - Flowing Water- Flowing Increase in Increase in Porosity Porosity and Structures Monitoring Structures Monitoring II1.A3-7 III.A3-7 3.5.1-32 3.5.1-32 A Foundation Foundation concrete concrete Loss of Permeability, Loss Program Program Strength/ Leaching of Strength/ Leaching of Calcium Hydroxide Hydroxide Concrete: Shelter, Protection Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking, Loss of Cracking, of Bond, Bond, Structures Monitoring Structures Monitoring II1.A3-4 III.A3-4 3.5.1-31 3.5.1-31 A Foundation Foundation concrete concrete and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Shelter, Protection Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks andand Structures Monitoring Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A Foundation Foundation concrete Distortion/increased Distortion/I ncreased Program Program Stress Levels Levels from Settlement Settlement Concrete:

Concrete: Shelter, Protection Shelter, Protection Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Increase in Porosity and and Structures Structures Monitoring II1.A3-5 III.A3-5 3.5.1-31 3.5.1-31 A A

Foundation Foundation concrete concrete Permeability, Cracking, Program Material (Spaliing, Loss of Material (Spalling, Aggressive Scaling)/ Aggressive Chemical Attack Chemical Concrete:

Concrete: Shelter, Protection Protection Reinforced Reinforced Water - Flowing Water- Flowing Porosity and ncrease in Porosity IIncrease and Structures Monitoring Structures Monitoring II1.A3-7 III.A3-7 3.5.1-32 A A

Foundation Foundation concrete concrete Permeability, Loss of Permeability, of Program Strength/ Leaching Strength/ Leaching of Calcium Hydroxide Hydroxide Concrete: Structural Support Structural Reinforced Reinforced Groundwater/soil Groundwater/soil Cracking, Cracking, Loss of Bond, Structures Monitoring Structures III.A3-4 3.5.1-31 A A

Foundation concrete concrete and Loss of Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Concrete:

Concrete: Structural Support Structural Reinforced Reinforced Groundwater/soil Groundwater/soil Cracks Cracks and Structures Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 A A

Foundation concrete concrete Distortion/Increased Distortion/I ncreased Program Stress Stress Levels Levels from from Settlement Concrete:

Concrete: Structural Support Reinforced Reinforced Groundwater/soil Groundwater/soil Increase in Increase in Porosity Porosity and Monitoring Structures Monitoring III.A3-5 3.5.1-31 A A

Foundation concrete Permeability, Cracking, Program Loss of Material (Spalling, Scaling)/ Aggressive Scaling)/ Aggressive Chemical Attack Salem Nuclear Salem Generating Station, Unit No.1 Nuclear Generating No. 2 No. 1 and Unit No.2 3.5-92 Page 3.5-92

  • Section Section 3 - Aging
  • Aging Management Management Review Review Results Results Table Table 3.5.2-1 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Concrete:

Concrete: Structural Support Structural Support Reinforced Reinforced Water-Water - Flowing Increase in Porosity Increase Porosity and Structures Monitoring Structures Monitoring IIl.A3-7 IILA3-7 3.5.1-32 3.5.1-32 A Foundation Foundation concrete concrete Permeability, Loss of Permeability, .Loss Program Program Strength/

Strengthl Leaching Leaching ofof Calcium Hydroxide Calcium Hydroxide Concrete: Interior Concrete: Interior Flood Barrier Flood Barrier Reinforced Reinforced Air --Indoor Air Indoor Cracking, Loss of Cracking, of Bond, Bond, Structures Monitoring Structures Monitoring III.A3-9 IILA3-9 3.5.1-23 3.5.1-23 A concrete concrete and Loss of Material and Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Interior Concrete: Interior Flood Barrier Flood Barrier Reinforced Reinforced Air-Indoor Air - Indoor Cracks and Cracks and Structures Monitoring Structures Monitoring IILA3-3 III.A3-3 3.5.1-28 3.5.1-28 A concrete concrete Distortion/increased Distortion/l ncreased Program Program Stress Levels from Stress Levels from Settlement Settlement Concrete: Interior Concrete: Interior HELB/MELB HELB/MELB Reinforced Reinforced Air --Indoor Indoor Cracking, Loss of Cracking, of Bond, Structures Structures Monitoring III.A3-9 IILA3-9 3.5.1-23 3.5.1-23 A Shielding Shielding concrete concrete and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Interior Concrete: Interior HELB/MELB HELB/MELB Reinforced Reinforced Air --Indoor Indoor Cracks and Structures Structures Monitoring III.A3-3 IILA3-3 3.5.1-28 3.5.1-28 A Shielding Shielding concrete concrete Distortion/Increased Distortion/l ncreased Program Program Stress Levels from Stress Levels Settlement Settlement Concrete: Interior Concrete: Interior Missile Barrier Barrier Reinforced Reinforced Air --Indoor Indoor Cracking, Loss of Bond, Cracking, Structures Structures Monitoring III.A3-9 IILA3-9 3.5.1-23 A concrete concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Interior Concrete: Interior Barrier Missile Barrier Reinforced Reinforced Air --Indoor Indoor Cracks and Structures Structures Monitoring III.A3-3 IILA3-3 3.5.1-28 A concrete concrete Distortion/Increased Distortion/lncreased Program Stress Levels from from Settlement Settlement Concrete:

Concrete: Interior Interior Shelter, Protection Protection Reinforced Reinforced Air-Indoor Air - Indoor Cracking, Loss of Bond, Structures Structures Monitoring II1.A3-9 IILA3-9 3.5.1-23 A concrete concrete and Loss of Material Program (Spalling,.

(Spalling, Scaling)/Corrosion of Scaling)/Corrosionof Embedded Steel Embedded Salem Nuclear Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-93 License Renewal Application

Section Section 33 -- Aging Aging Management Management Review Review Results Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 22 Item Vol. Item ..

Management Management Concrete: Interior Concrete: Interior Shelter, Protection Shelter, Protection Reinforced Reinforced - Indoor Air-Indoor Air Cracks and Cracks Structures Monitoring Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A concrete concrete Distortion/Increased Distortion/Increased Program Program Stress Levels Levels from from Settlement Settlement Concrete: Interior Concrete: Interior Shielding Shielding Reinforced Reinforced Air --Indoor Air Indoor Cracking, Loss Cracking, Loss of Bond, Structures Monitoring Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 3.5.1-23 A concrete concrete Loss of and Loss of Material Material Program Program (Spalling, (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Interior Concrete: Interior Shielding Shielding Reinforced Reinforced Air-Indoor Air - Indoor Cracks and Cracks Structures Structures Monitoring Monitoring III.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A concrete Distortion/Increased Distortion/Increased Program Program Stress Levels from Settlement Settlement Concrete: Interior Concrete: Interior Structural Support Structural Support Reinforced Reinforced Air -Indoor

- Indoor Cracking, Loss of Bond, Cracking, Structures Monitoring Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 3.5.1-23 A concrete and Loss Loss of Material Material Program Program (Spalling, (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Concrete: Interior Concrete: Interior Structural Support Structural Support Reinforced Reinforced Air -Indoor

- Indoor Cracks and Cracks Structures Monitoring Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A concrete Distortion/Increased Distortion/Increased Program Program Stress Levels from

.Stress Settlement Settlement Conduit Galvanized Steel Shelter, Protection Galvanized Air - Indoor Air-Indoor None None None 111.B5-3 III.B5-3 3.5.1-58 3.5.1-58 C Conduit Shelter, Protection Galvanized Steel Air with Borated Galvanized Material/Boric Acid Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion I11.B5-4 III.B5-4 3.5.1-55 3.5.1-55 C Leakage Leakage Corrosion Conduit Structural Support Support Galvanized Galvanized Steel Air-Indoor Air- Indoor None None None IIIII.B5-3 I. B5-3 3.5.1-58 3.5.1-58 C Conduit Structural Support Structural Galvanized Steel Air with Borated Galvanized Material/Boric Acid Borated Water Loss of Material/Boric Corrosion -

Boric Acid Corrosion III.B5-4 I. B5-4 3.5.1-55 3.5.1-55 C Leakage Leakage Corrosion Doors Doors Flood Barrier Carbon Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring Structures Monitoring Ili.A3-12 III.A3-12 3.5.1-25 A Corrosion Program Doors Flood Barrier Carbon Carbon Steel Air-Air - Outdoor Outdoor Loss of Material/General, Material/General, Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 A A

Pitting and Crevice Program Corrosion Doors HELB/MELB HELB/MELB Carbon Steel Air - Indoor Air-Indoor Material/General Loss of Material/General Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 AA I Shielding I Corrosion Corrosion Program _

Salem Nuclear Salem Generating Station, Unit No.1 Nuclear Generating No. 2 No. 1 and Unit No.2 Page 3.5-94

  • 0
  • Section Section 3 - Aging
  • Aging Management Management Review Results Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Vol. Item Management Management Doors Doors Missile Missile Barrier Barrier Carbon Steel Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

Corrosion Corrosion Program Program Doors Doors Missile Barrier Missile Barrier Carbon Steel Steel Air - Outdoor Outdoor Loss of Material/General, Loss Material/General, Structures Structures Monitoring Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 AA Pitting and and Crevice Program Program Corrosion Doors Doors Shelter, Protection Protection Carbon Steel Carbon Steel Air Air --Indoor Indoor Loss of Loss of Material/General Material/General Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A Corrosion Corrosion Program Program Doors Doors Shelter, Protection Protection Carbon Steel Carbon Steel Air - Outdoor Outdoor Loss of Material/General, Loss Material/General, Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A Pitting and and Crevice Program Program Corrosion Equipment Structural Support Structural Support Reinforced Reinforced Air - Indoor Air-Indoor Cracking, Loss of Bond, Cracking, Structures Monitoring Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 3.5.1-23 A A

foundations foundations concrete concrete and Loss of Material Material Program (Spalling, (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Equipment Equipment Structural Support Structural Reinforced Reinforced Air- Indoor Air-Indoor Cracks and Cracks Structures Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 3.5.1-28 A A

foundations foundations concrete concrete Distortion/Increased Distortionllncreased Program Stress Levels Levels from from Settlement Settlement Hatches/Plugs Hatches/Plugs HELB/MELB HELB/MELB Reinforced Reinforced Air --Indoor Indoor Cracking, Loss of Bond, Structures Structures Monitoring Monitoring III.A3-9 3.5.1-23 3.5.1-23 A A

Shielding concrete concrete Loss of Material and Loss Material Program Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Hatches/Plugs Hatches/Plugs Missile Barrier Barrier Carbon Steel Carbon Air- Indoor Air-Indoor Loss of Material/General Material/General Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

Corrosion Program Hatches/Plugs Hatches/Plugs Missile Barrier Missile Barrier Carbon Steel Carbon Outdoor Air - Outdoor Loss of Material/General, Material/General, Structures Monitoring Structures III.A3-12 III.A3-12 3.5.1-25 A A

Pitting and Crevice Crevice Program Corrosion Corrosion Hatches/Plugs Hatches/Plugs Missile Barrier Barrier Carbon Steel Carbon Concrete None None VII.J-21 3.3.1-96 3.3.1-96 C Hatches/Plugs Hatches/Plugs Missile Barrier Barrier Reinforced Reinforced Air - Indoor Air-Indoor Cracking, Loss of Bond, Structures Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 3.5.1-23 A A

concrete and Loss of Material Material . Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Embedded Salem Salem Nuclear Nuclear Generating Station, Unit No.1 No. I and Unit No.2 No. 2 Page 3.5-95 license License Renewal Renewal Application

Section 3 -- Aging Management Management Review Results Results Table 3.5.2-1 3.5.2-1 Auxiliary Building Building (Continued)

Component Component Intended Material Material Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Function Requiring Requiring Programs Item Vol. 2 Item Management Management Hatches/Plugs Hatches/Plugs Missile Missile Barrier Reinforced Air - Outdoor Cracking, Loss of Bond, Bond, Structures Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 A A

concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Embedded Hatches/Plugs Hatches/Plugs Missile Missile Barrier Reinforced Reinforced Outdoor Air - Outdoor Loss of Material Material (Spalling, (Spalling, Structures Structures Monitoring III.A3-6 III.A3-6 3.5.1-26 A concrete Scaling) and Program Cracking/Freeze-thaw Cracking/Freeze-thaw Hatches/Plugs Hatches/Plugs Missile Missile Barrier Reinforced Reinforced Encased in Steel None None G, G,33 concrete Hatches/Plugs Hatches/Plugs Shelter, Protection Protection Carbon Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A Corrosion Program Hatches/Plugs Hatches/Plugs Shelter, Protection Protection Carbon Carbon Steel Air - Outdoor Outdoor Loss of Material/General, Material/General, Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 A Pitting and Pitting Crevice and Crevice Program Program Corrosion Hatches/Plugs Hatches/Plugs Shelter, Protection Protection Carbon Steel Concrete None None VII.J-21 3.3.1-96 C Hatches/Plugs Hatches/Plugs Shelter, Protection Protection Reinforced Reinforced Air - Indoor Air-Indoor Cracking, Cracking, Loss of Bond, Structures Monitoring Structures Monitoring II1.A3-9 III.A3-9 3.5.1-23 A A

concrete concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Steel Hatches/Plugs Hatches/Plugs Shelter, Protection Reinforced Reinforced Air - Outdoor Outdoor Cracking, Loss of Bond, Structures Monitoring III.A3-9 III.A3-9 3.5.1-23 A concrete and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Hatches/Plugs Hatches/Plugs Shelter, Protection Reinforced Reinforced. Air - Outdoor Loss of Material (Spalling, Structures Monitoring Monitoring III.A3-6 III.A3-6 3.5.1-26 A A

concrete concrete Scaling) and Scaling) Program Program Cracking/Freeze-thaw Cracking/Freeze-thaw Hatches/Plugs Hatches/Plugs Shelter, Protection Protection Reinforced Reinforced Encased in Steel Encased None None None G, 3 G,3 1 concrete concrete I II_ I _ I Salem Nuclear Salem Generating Station, Nuclear Generating Station, Unit No. 1 and Unit No.1 Unit No.2 and Unit No. 2 Page 3.5-96 3.5-96 9

License Renewal Renewal Application Application

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  • License
  • *
  • Section 3 - Aging Management Management Review Review Results 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Hatches/Plugs Hatches/Plugs Shielding Reinforced Air- Indoor Air-Indoor Cracking, Loss of Bond, Bond, Structures Monitoring Structures Monitoring III.A3-9 IILA3-9 3.5.1-23 A concrete and Loss of Material Program Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Embedded Steel Hatches/Plugs Hatches/Plugs Structural Support Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Monitoring Structures Monitoring III.A3-12 IILA3-12 3.5.1-25 A A

Corrosion Program Program Hatches/Plugs Hatches/Plugs Structural Support Carbon Steel Air - Outdoor Loss of Material/General, Material/General, Monitoring Structures Monitoring II1.A3-12 IILA3-12 3.5.1-25 A Crevice Pitting and Crevice Program Program Corrosion Hatches/Plugs Hatches/Plugs Structural Support Carbon Steel Concrete None None None VII.J-21 VILJ-21 3.3.1-96 C Hatches/Plugs Hatches/Plugs Structural Support Reinforced Air - Indoor Air-Indoor Cracking, Loss of Bond, Monitoring Structures Monitoring II1.A3-9 IILA3-9 3.5.1-23 A concrete and Loss of Material Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Embedded Steel Hatches/Plugs Hatches/Plugs Structural Support Reinforced Air - Outdoor Cracking, Loss of Bond, Monitoring Structures Monitoring III.A3-9 IILA3-9 3.5.1-23 A concrete and Loss of Material Material Program (Spalling, Scaling)/Corrosion Scaling)/Corrosion of Embedded Steel Hatches/Plugs Hatches/Plugs Structural Support Reinforced Air - Outdoor Loss of Material Material (Spalling, Structures Monitoring Monitoring II1.A3-6 IILA3-6 3.5.1-26 A concrete Scaling) and . Program Program Crackina/Freeze-thaw Cracking/Freeze-thaw Hatches/Plugs Hatches/Plugs Structural Support Reinforced Encased in in Steel None None None G, 3 G,3 concrete Masonry Masonry walls: Shelter, Protection Concrete block Air - Indoor Air-Indoor Cracking, Loss of Bond, Monitoring Structures Monitoring II1.A3-9 IILA3-9 3.5.1-23 C Interior and Loss of Material Material Program Program (Spalling, Scaling)/Corrosion of Scaling)/Corrosion Embedded Steel Masonry walls:

Masonry Shelter, Protection Concrete Concrete block Air -Indoor

- Indoor Cracking/Restraint, Monitoring Structures Monitoring II1.A3-11 IILA3-11 3.5.1-43 A, 4 A,4 Interior Shrinkage, Creep, andand Program Aggressive Environment Environment Salem Salem Nuclear Generating Generating Station, Unit No.

No.11 and Unit No.

No.22 Page 3.5-97 Renewal Application License Renewal Application

Section 3 - Aging Aging Management Review Results Management Review Results Table Table 3.5.2-1 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table Table I1 Item Item Notes Notes Type Function Function Requiring Requiring Programs Programs Vol.

Vol. 22 Item Item Management Management Masonry walls:

Masonry walls: Shelter, Protection Protection Concrete block Concrete block Air- Indoor Air-Indoor Cracks and Cracks and Structures Monitoring Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 3.5.1-28 C Interior Interior Distortion/Increased Distortion/I ncreased Program Stress Levels Levels from Settlement Settlement Masonry walls:

Masonry Shielding Shielding Concrete Concrete block block Air - Indoor Air-Indoor Cracking, Loss Cracking, Loss ofof Bond, Structures Monitoring Structures Monitoring III.A3-9 III.A3-9 3.5.1-23 3.5.1-23 C Interior and Loss of Material Loss of Material Program (Spalling, (Spalling, Scalingj/Corrosion of Scaling)/Corrosion of Embedded Embedded Steel Masonry walls:

Masonry walls: Shielding Shielding Concrete block Concrete block Air - Indoor Air-Indoor Cracking/Restraint, Structures Monitoring Structures Monitoring III.A3-1 1 III.A3-11 3.5.1-43 3.5.1-43 A, A,44 Interior Interior Shrinkage, Creep, and Program Environment Aggressive Environment Aggressive Masonry Masonry walls:

walls: Shielding Shielding Concrete block Concrete block Air- Indoor Air-Indoor Cracks and Cracks Structures Monitoring Structures Monitoring II1.A3-3 III.A3-3 3.5.1-28 3.5.1-28 C Interior Interior Distortion/Increased Distortion/Increased Program Stress Levels Levels from Settlement Settlement Masonry walls:

Masonry Structural Support Concrete block Concrete block Air-Indoor Air - Indoor Cracking, Loss of Bond, Structures Monitoring Structures Monitoring III.A3-9 III.A3-9 3.5.1-23 3.5.1-23 C Interior and Loss Loss of Material Material Program (Spalling, (Spalling, Scalingj/Corrosion of Scaling)/Corrosion of Embedded Steel Embedded Steel Masonry walls: Structural Support Concrete block Concrete Air - Indoor Air-Indoor Cracking/Restraint, Cracking/Restraint, Structures Monitoring Structures II1.A3-11 III.A3-11 3.5.1-43 A, A,44 Interior Shrinkage, Creep, and Shrinkage,Creep, Program Environment Aggressive Environment AQQressive Masonry walls: Structural Structural Support Concrete block Concrete Air- Indoor Air-Indoor Cracks and and Structures Structures Monitoring III.A3-3 III.A3-3 3.5.1-28 C C

Interior Distortion/Increased Distortion/Increased Program Stress Levels from Settlement Settlement Miscellaneous steel Shelter, Protection Miscellaneous Protection Aluminum Air- Indoor Air-Indoor None None None I11.B5-2 III.B5-2 3.5.1-58 C (catwalks, stairs, handrails, ladders, vents and louvers, platforms, etc.

etc.)j No. 1 and Unit No.2 Nuclear Generating Station, Unit No.1 Salem Nuclear No. 2 Page 3.5-98 Page 3.5-98

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  • Section
  • Section 3 - Aging Management Management Review Review Results Results Table 3.5.2-1 3.5.2-1 Auxiliary Auxiliary Building (Continued)

Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG*1801 Table I1 Item Notes Notes Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Item Management Management Miscellaneous Miscellaneous steel Shelter, Protection Aluminum Aluminum Air-Air - Outdoor Loss of Material/Pitting Monitoring Structures Monitoring III.B2-7 II I. B2-7 3.5.1-50 3.5.1-50 C (catwalks, stairs, and Crevice Corrosion Program handrails, handrails, ladders, vents and louvers, platforms, etc.)

Miscellaneous Miscellaneous steel Structural Support Aluminum Aluminum Air- Indoor Air-Indoor None None I1.B5-2 III.B5-2 3.5.1-58 3.5.1-58 C (catwalks, stairs, handrails, handrails, ladders, vents and louvers, platforms, etc.)

Miscellaneous steel Structural Support Miscellaneous Aluminum Air - Outdoor Outdoor Loss of Material/Pitting Structures Monitoring Structures Monitoring II1.B2-7 III.B2-7 3.5.1-50 3.5.1-50 C (catwalks, stairs, and Crevice Corrosion Program handrails, handrails, ladders, vents and louvers, platforms, etc.)

Miscellaneous steel Structural Miscellaneous Structural Support Support Carbon Steel Air-- Indoor

'Air Material/General Loss of Material/General Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

(catwalks, stairs, Corrosion Corrosion Program handrails, ladders, vents and louvers, platforms, etc.)

Miscellaneous steel Miscellaneous steel Structural Structural Support Carbon Steel Air-Air - Outdoor Outdoor Loss of Material/General, Material/General, Structures Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

(catwalks, stairs, Pitting and Crevice Program handrails, ladders, Corrosion Corrosion vents and louvers, platforms, etc.)

Miscellaneous steel Miscellaneous stee Structural Structural Support Support Carbon Steel Air with Borated Water Material/Boric Acid Water Loss of Material/Boric Boric Acid Corrosion 111.B5-8 II I. B5-8 3.5.1-55 3.5.1-55 C (catwalks, stairs, Leakage Corrosion Corrosion handrails, handrails, ladders, vents and louvers, platforms, etc.)

Miscellaneous steel Structural Miscellaneous Structural Support Support Galvanized Galvanized Steel Steel Air --Indoor Indoor None None I11.B5-3 II I. B5-3 3.5.1-58 3.5.1-58 C (catwalks, stairs, handrails, handrails, ladders, vents and louvers, platforms, etc.)

Salem Nuclear Generating Station, Unit No.1 Nuclear Generating No. 1 and Unit No.2 No. 2 Page 3.5-99 Renewal Application License Renewal

Section 3 - Aging Management Management Review Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Auxiliary Building (Continued)

Component Intended Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1I Item Notes Notes Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Management Manaaement Miscellaneous steel Structural Support Miscellaneous Support Galvanized Steel Galvanized Air - Outdoor Loss of Material/General, Structures Monitoring Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A (catwalks, stairs, Pitting and Crevice Program Program handrails, ladders, Corrosion vents and louvers, platforms, etc.)

etc.)

Structural Support Miscellaneous steel Structural Miscellaneous Support Galvanized Steel Air with Borated Galvanized Material/Boric Acid Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion II111.B5-4 I. B5-4 3.5.1-55 3.5.1-55 C (catwalks, stairs, Leakage Leakage Corrosion handrails, ladders, vents and louvers, platforms; platforms, etc.)

Panels, Racks, Structural Support Structural Carbon Carbon Steel Air --Indoor Indoor Loss of Material/General Material/General Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A A

Cabinets, and Corrosion Program Other Other Enclosures Enclosures Panels, Racks, Structural Structural Support Carbon Carbon Steel Material/Boric Acid Air with Borated Water Loss of Material/Boric Boric Acid Corrosion Corrosion 111.B5-8 II I. B5-8 3.5.1-55 C C

Cabinets, and Leakage Corrosion Other Enclosures Other Enclosures Panels, Racks, Galvanized Steel Structural Support Galvanized Structural Air - Indoor Air-Indoor None None 111.B5-3 III.B5-3 3.5.1-58 C Cabinets, and and Enclosures Other Enclosures Other Panels, Racks, Structural Material/Boric Acid Galvanized Steel Air with Borated Water Loss of Material/Boric Structural Support Galvanized Boric Acid Corrosion Corrosion I11.B5-4 III.B5-4 3.5.1-55 C Cabinets, and Leakage

,Leakage Corrosion Other Enclosures Other Enclosures Penetration seals Flood Barrier Elastomers Elastomers Air- Indoor Air-Indoor Loss of Structures Structures Monitoring II1.A6-12 III.A6-12 3.5.1-44 A A

Sealing/Deterioration Sealing/Deterioration of Program Seals, Gaskets, and Moisture Barriers Moisture Barriers (caulking, flashing, and (caulking, flashing, and other other sealants)

Penetration seals Penetration Flood Barrier Elastomers Elastomers Air-Air - Outdoor Outdoor Loss of Structures Structures Monitoring II1.A6-12 III.A6-12 3.5.1-44 A A

Sealing/Deterioration of Sealing/Deterioration Program Seals, Gaskets, and Moisture Barriers Barriers (caulking, flashing, and and other sealants) other Penetration seals Flood Barrier Grout Air - Indoor Air-Indoor Cracking/Shrinkage Cracking/Shrinkage Structures Structures Monitoring F, 5 Program Salem Nuclear Salem Nuclear Generating Generating Station, Station, Unit No.1 No. 1 and and Unit Unit No.

No.22 Page 3.5-100 Renewal Application

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  • Section 3 - Aging Management Management Review Review Results Results 3.5.2-1 Table 3.5.2-1 Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Type Function Requiring Requiring Programs Item Vol. 2 Item Management Management Penetration ~eals Penetration seals Flood Barrier Barrier Grout Air - Outdoor Outdoor Cracking/Shrinkage Cracking/Shrinkage Structures Structures Monitoring Monitoring F, 5 F,5 Program Penetration seals Penetration Barrier Flood Barrier Grout Air - Outdoor Outdoor Loss of Material Material (Spalling, Monitoring Structures Monitoring F, 6 F,6 Scaling) and Program -

/

Cracking/Freeze-thaw Cracking/Freeze-thaw Penetration seals Penetration seals Flood Barrier Barrier Grout Groundwater/soil Groundwater/soil Cracking/Shrinkage Cracking/Shrinkage Monitoring Structures Monitoring F, 5 F,5 Program Penetration seals Penetration Flood Barrier Grout Groundwater/soil Groundwater/soil Increase in Porosity and Increase Structures Monitoring Monitoring F, 6 F,6 Permeability, Cracking, Program Loss of Material Material (Spalling, Scaling)/ Aggressive.

Aggressive.

Chemical Attack Chemical Attack Penetration seals HELB/MELB HELB/MELB Elastomers Elastomers Air - Indoor Air-Indoor Loss of Structures Monitoring Monitoring II1.A6-12 IILA6-12 3.5.1-44 A A

Shielding Shielding Sealing/Deterioration of Sealing/Deterioration Program Seals, Gaskets, and Moisture Barriers Barriers (caulking, flashing, and other sealants)

Penetration seals Penetration seals HELB/MELB HELB/MELB Grout Air - Indoor Air-Indoor Cracking/Shrinkage Cracking/Shrinkage Monitoring Structures Monitoring F, 5 F,5 Shielding Shielding Program Program Penetration seals seals Shelter, Protection Protection Elastomers Elastomers Air- Indoor Air-Indoor Loss of Monitoring Structures Monitoring III.A6-12 IILA6-12 3.5.1-44 A A

Sealing/Deterioration of Sealing/Deterioration Program Seals, Gaskets, and Moisture Barriers Barriers (caulking, flashing, and other sealants)

Penetration seals Penetration seals Shelter, Protection Protection Elastomers Elastomers Air-Air - Outdoor Loss of Monitoring Structures Monitoring II1.A6-12 IILA6-12 3.5.1-44 A Sealing/Deterioration of Sealing/Deterioration of Program Program Seals, Gaskets, and Barriers Moisture Barriers (caulking, flashing, and

. other sealants)

Penetration seals Shelter, Protection Protection Grout Air - Indoor Air-Indoor Cracking/Shrinkage Cracking/Shrinkage Structures Monitoring F, 5 Program ProQram Penetration Penetration seals Shelter, Protection Protection Grout Air - Outdoor Cracking/Shrinkage Cracking/Shrinkage Monitoring Structures Monitoring F, 5 F,5 Program Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-101 License Renewal Application

Section Section 3-3- Aging Aging Management Management Review Review Results Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Auxiliary Building Building (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Aging Management NUREG-1801 NUREG-1801 Table I1 Item Table Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 2 Item Vol. Item

_ Management

_Management Penetration seals Penetration Shelter, Protection Protection Grout Outdoor Air - Outdoor Loss of Material (Spalling, Material (Spalling, Structures Monitoring Structures Monitoring F, F,66 Scaling) and Scaling) and Program Program Cracking/Freeze-thaw Cracking/Freeze-thaw Penetration seals Penetration Protection Shelter, Protection Grout . Groundwater/soil Groundwater/soil Cracking/Shrinkage Cracking/Shrinkage Structures Structures Monitoring Monitoring F, 5 Program Program Penetration Penetration seals Shelter, Protection Protection Grout Groundwater/soil Groundwater/soil Increase Increase in Porosity 1 and Porosity\ and Structures Monitoring Structures Monitoring F, F,66 Permeability, Permeability, Cracking, Cracking, Program Program Loss of Material Material (Spalling, (Spalling, Scaling)/

Scaling)/ Aggressive Aggressive Chemical Chemical Attack Penetration seals Penetration seals Shielding Elastomers Elastomers Air - Indoor Air-Indoor Loss Loss of Structures Monitoring Structures Monitoring III.A6-12 III.A6-12 3.5.1-44 3.5.1-44 A A

- Sealing/Deterioration Sealing/Deterioration of Program Program Seals, Gaskets, and Moisture Barriers Moisture Barriers (caulking, (caulking, flashing, and and other sealants) sealants)

Penetration Penetration seals Shielding Grout Air - Indoor Air-Indoor Cracking/Shrinkage Cracking/Shrinkage Structures Structures Monitoring Monitoring F, 5 F,5 Program Program Penetration Penetration Flood Barrier Carbon Carbon Steel Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring Structures Monitoring III.A3-12 III.A3-12 3.5.1-25 3.5.1-25 A A

sleeves Corrosion Corrosion Program Program Penetration Penetration Flood Barrier Carbon Steel Air - Outdoor Loss of Material/General, Material/General, Monitoring Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A A

sleeves Pitting and Crevice Program Program Corrosion Penetration Flood Barrier Carbon Steel Steel Air with Borated Water Loss of Material/Boric Acid Boric Acid Corrosion I11.B5-8 III.B5-8 3.5.1-55 3.5.1-55 C sleeves Leakage Leakage Corrosion Penetration Flood Barrier Carbon Steel Steel Concrete None None VII.J-21 3.3.1-96 3.3.1-96 C sleeves sleeves

.-

Penetration Penetration Flood Barrier Carbon Steel Carbon Groundwater/soil Groundwater/soil Material/General, Loss of Material/General, Structures Structures Monitoring Monitoring VII.C1-18 3.3.1-19 3.3.1-19 E, 2 E,2 sleeves Pitting, Crevice, and Program Microbiologically Microbiologically Influenced Corrosion Influenced Corrosion Penetration HELB/MELB HELB/MELB Carbon Steel Air- Indoor Air-Indoor Material/General Loss of Material/General Monitoring Structures Monitoring *II1.A3-12 III.A3-12 3.5.1-25 A A

sleeves Shielding Corrosion Program Penetration Penetration HELB/MELB Carbon Steel Air with Borated Water Loss of Material/Boric Acid Boric Acid Corrosion III.B5-8 III.B5-8 3.5.1-55 CC sleeves Shielding Leakage Corrosion Nuclear Generating Station, Unit No.

Salem Nuclear No.11 and Unit No.2 No. 2 Page 3.5-102 3.5-102 0

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  • Section 3 -- Aging Management Management Review Results 3.5.2-1 Table 3.5.2-1 Auxiliary Auxiliary Building (Continued)

Component Component Intended Intended Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Programs Item Vol. 2 Item Management Management Penetration Penetration HELB/MELB HELB/MELB Carbon Steel Concrete Concrete None None None VII.J-21 VII.J-21 3.3.1-96 C C

sleeves Shielding Shielding Penetration Penetration Structural Structural Support Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring Monitoring III.A3-12 3.5.1-25 A A

sleeves Corrosion Program Program Penetration Penetration Structural Structural Support Carbon Steel Air - Outdoor Material/General, Loss of Material/General, Structures Monitoring Monitoring III.A3-12 3.5.1-25 A A

sleeves Pitting and Crevice Program Corrosion Penetration Penetration Structural Structural Support Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion Corrosion 111.B5-8 III.B5-8 3.5.1-55 C sleeves Leakage Leakage Corrosion Penetration Penetration Structural Structural Support Carbon Steel Concrete Concrete None None None VII.J-21 VII.J-21 3.3.1-96 C sleeves Penetration Penetration Structural Structural Support Carbon Steel Groundwater/soil Groundwater/soil Material/General, Loss of Material/General, Monitoring Structures Monitoring VII.C1-18 3.3.1-19 E, 2 E,2 sleeves Pitting, Crevice, and Program Microbiologically Microbiologically Influenced Corrosion Influenced Corrosion Pipe Whip HELB/MELB Carbon Steel Air - Indoor Air-Indoor Material/General Loss of Material/General Monitoring Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A Restraints and Jet Restraints Shielding Corrosion Program Impingement Impingement (including Shields (including Pipe Encapsulation and Spray Shields)

Pipe Whip HELB/MELB HELB/MELB Carbon Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion III.B5-8 II I. B5-8 3.5.1-55 3.5.1-55 C Restraints and Jet Shielding Shielding Leakage Leakage Corrosion Impingement Impingement Shields (including Shields (including .

Pipe Encapsulation Encapsulation and Spray Shields)

Pipe Whip Pipe Whip Restraint Carbon Steel Air - Indoor Air-Indoor Material/General Loss of Material/General Monitoring Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A Restraints and Jet Restraints Corrosion Corrosion Program Impingement Impingement (including Shields (including Encapsulation Pipe Encapsulation and Spray Shields)

Salem Nudear Generating Station, Unit No.1 Nuclear Generating No. 1 and Unit No.2 No. 2 Page 3.5-103 Page 3.5-103 License Renewal Renewal Application Application

Section 33 - Aging Section Aging Management Review Results Management Review Results 3.5.2-1 Table 3.5.2-1 Auxiliary Building Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Item Notes Notes Type Function Requiring Requiring Programs Programs Vol. 22 Item Item Management Management Pipe Whip Pipe Whip Restraint Pipe Restraint Carbon Steel Carbon Steel Air with Borated Material/Boric Acid Loss of Material/Boric Borated Water Loss Acid Boric Acid Corrosion Boric Corrosion 1.B5-8 III.B5-8 3.5.1-55 3.5.1-55 C Restraints and Restraints and Jet Jet Leakage Leakage Corrosion Impingement Impingement Shields (including Shields (including Pipe Encapsulation Encapsulation and Spray Shields' and Shields)

Roofing membrane Roofing membrane Shelter, Protection Protection Elastomers Elastomers Air - Outdoor Outdoor Loss of.

of Structures Monitoring Structures Monitoring II1.A6-12 III.A6-12 3.5.1-44 3.5.1-44 A Sealing/Deterioration of Sealing/Deterioration of Program Seals, Gaskets, Gaskets, and and Moisture Barriers Moisture Barriers flashing, and (caulking, flashing, and other sealants)

Seals, gaskets, and and Flood Barrier Flood Elastomers Elastomers Air --Indoor Indoor Loss of Structures Structures Monitoring II1.A6-12 III.A6-12 3.5.1-44 A moisture barriers moisture SealinglDeterioration of Sealing/Deterioration of Program Program (caulking, flashing (caulking, flashing Seals, Gaskets, andand and other sealants) Moisture Barriers Moisture Barriers (caulking, (caulking, flashing, and other sealants) other sealants)

Seals, gaskets, and Flood Barrier Flood Barrier Elastomers Elastomers Air - Outdoor Air- Loss of Monitoring Structures Monitoring I1I.A6-12 III.A6-12 3.5.1-44 A A

moisture barriers Sealing/Deterioration SealinglDeterioration of Program Program (caulking, flashing (caulking, Seals, Gaskets, and and and other sealants) and Moisture Barriers Moisture Barriers (caulking, flashing, and other sealants) other Seals, gaskets, and Shelter, Protection Copper Air -- Outdoor Loss of Material/Pitting Material/Pitting Structures Monitoring III.A6-11 3.5.1-47 A, 7 A,7 moisture barriers and Crevice Corrosion Corrosion Program (caulking, flashing and other sealants sealants)

Seals, eals, gaskets, and Shelter, Protection Elastomers Air-Indoor Air- Indoor Loss of Structures Monitoring II1.A6-12 III.A6-12 3.5.1-44 A A

moisture barriers Sealing/Deterioration of Sealing/Deterioration Program (caulking, flashing Seals, Gaskets, and and other sealants) Barriers Moisture Barriers (caulking, flashing, and I_ other sealants)

Salem Salem Nuclear Generating Station, Unit Nuclear Generating Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-104 Page 3.5-104

  • *
  • Section 3 - Aging Management Review Review Results Table 3.5.2-1 3.5.2-1 Auxiliary Building (Continued)

Component Intended Intended Material Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Vol. 2 Item Item Management Management Seals, gaskets, and Seals, and Shelter, Protection Elastomers Air-Air - Outdoor Outdoor Loss of Structures Monitoring Structures Monitoring III.A6-12 3.5.1-44 AA moisture barriers moisture barriers Sealing/Deterioration of Sealing/Deterioration Program Program (caulking, (caulking, flashing Seals, Gaskets, and and other sealants) Barriers Moisture Barriers (caulking, flashing, and other sealants) sealants)

Steel components: Barrier Missile Barrier Carbon Steel Air - Outdoor Loss of Material/General, Material/General, Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A All structural structural steel Pitting and Crevice Program Program Corrosion Corrosion Steel components: Structural Structural Support Carbon Steel Air --Indoor Indoor Loss of Material/General Material/General Structures Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A All structural structural steel Corrosion Corrosion Program Program Steel components: Structural Structural Support Carbon Steel Air-- Outdoor Air Loss of Material/General, Material/General, Structures Monitoring Structures Monitoring II1.A3-12 III.A3-12 3.5.1-25 A All structural structural steel Pitting and Crevice Program Program Corrosion Corrosion Steel components:

Steel components: Structural Support Structural Support Carbon Steel Carbon Steel Air with Air with.Borated Water Loss

-Borated Water Loss of of Material/Boric Material/Boric Acid Acid BoricAcid Boric Corrosion Acid Corrosion I11.B5-8 III.B5-8 3.5.1-55 3.5.1-55 CC All structural structural steel Leakage Leakage Corrosion Corrosion Steel components: Structural Structural Support Stainless Steel Air- Indoor Air-Indoor None None VII.J-15 VII.J-15 3.3.1-94 C Sump Screen Trench Trench Cover Cover Steel components: Structural Structural Support - Stainless Steel Air with Borated Water None None None I11.B5-6 III.B5-6 3.5.1-59 C Sump Screen Leakage Leakage Trench Cover Trench Cover Steel Steel components:

components: Structural Support Structural Stainless Steel Raw Water Water Loss of Material/Pitting, Material/Pitting, Structures Monitoring Structures VII.H2-18 3.3.1-80 E, E,11 Sump Screen Crevice, and Program Program Trench Cover Microbiologically Microbiologically Influenced Corrosion Influenced Corrosion Steel Steel elements: Water retaining Carbon Steel Air - Indoor Air-Indoor Loss of Material/General Material/General Structures Monitoring Structures III.A3-12 III.A3-12 3.5.1-25 A A

Liner; Liner Liner' boundary boundary Corrosion Corrosion .' Program anchors; Integral attachments attachments Steel elements: Water retaining Carbon Steel Air with Borated Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion III.B5-8 III.B5-8' 3.5.1-55 C Liner; Liner boundary boundary Leakage Leakage Corrosion anchors; Integral attachments attachments Salem Nuclear Generating Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page Page 3.5-105 License Application License Renewal Application

Section 3 -- Aging Management Management Review Results Results Table 3.5.2-1 Table 3.5.2-1 Auxiliary Building (Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Management Aging Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Type Function Function Requiring Requiring Programs Programs Vol. 2 ItemItem Management Management Steel elements:

Steel elements: Water retaining Water retaining Carbon Steel Carbon Steel Raw Water Raw Material/General, Loss of Material/General, Monitoring Structures Monitoring ILI.A6-1 1 III.A6-11 3.5.1-47 3,5,1-47 A, 7 A,7 Liner; Liner Liner; Liner boundary boundary Pitting and Crevice Program Program anchors; Integral anchors; Corrosion Corrosion attachments attachments Tube Track Tube Track Structural Support Structural Support Galvanized Steel Galvanized Steel Air- Indoor Air-Indoor None None II1.B5-3 III.B5-3 3.5.1-58 3,5,1-58 C Tube Track Tube Track Structural Support Galvanized Structural Support Galvanized Steel Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion IIIII.B5-4 I. B5-4 3.5.1-55 3,5,1-55 C Leakage Leakage Corrosion CorroSion Tube Track Tube Track Structural Support Structural Support Stainless Steel Stainless Steel Air-- fndoor Air Indoor None None VII.J-15 VII.J-15 3.3.1-94 3,3,1-94 C C

Tube Track Tube Track Structural Support Structural Support Stainless Steel Stainless Steel Air with Air Borated Water with Borated Water None None IIII1.B5-6 I. B5-6 3.5.1-59 3,5,1-59 C C

Leakage Leakage __

Salem Nuclear Salem Nuclear Generating Generating Station, Station, Unit No.

No, 1 and and Unit No.

No, 2 Page 3.5-106 Page 3,5-106 0

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  • Section
  • Section 33 - Aging Management Management Review Review Results Results Notes Notes Definition of Note Definition Note A NUREG-1801 item for component, material, environment, Consistent with NUREG-1801 Consistent environment, andand aging effect. AMP is consistent consistent with with NUREG-1801 NUREG-1801 AMP.

B Consistent NUREG-1801 item for component, material, Consistent with NUREG-1801 environment, and material, environment, and aging effect. AMP takes some exceptions to NUREG-some exceptions NUREG-1801 1801 AMP.AMP.

C Component is different, Component NUREG-1801 item different, but consistent with NUREG-1801 environment, and aging effect. AMP item for material, environment, consistent with AMP is consistent NUREG-1801 NUREG-1801 AMP.

Do Component different, but consistent with NUREG-1801 Component is different, NUREG-1801 item material, environment, and aging effect. AMP item for material, AMP takes some exceptions exceptions to NUREG-1801 NUREG-1801 AMP. AMP.

EE Consistent NUREG-1801 item Consistent with NUREG-1801 material, environment item for material, environment and and aging effect, but different aging but aa different management program is aging management is credited or or NUREG-1801 identifies a plant-specific NUREG-1801 plant-specific aging management management program.

F Material NUREG-1 801 for this component.

Material not in NUREG-1801 G Environment not in NUREG-1 Environment NUREG-1801 801 for this component material.

component and material.

H Aging effect not in NUREG-1801 for this component, material in NUREG-1801 material and environment combination.

and environment combination.

I Aging effect in NUREG-1 NUREG-1801 801 for this component, material and environment component, material combination is not environment combination not applicable.

applicable.

J Neither the Neither component nor the component nor the material material and environment combination is evaluated environment combination evaluated in in NUREG-1801.

NUREG-1801.

Plant Specific Specific Notes:

industry standards and operating experience

1. Based on industry preload/self-loosening of structural bolting could be caused by vibration, experience age related loss of preload/self-loosening flexing of the joint or cyclic shearshear loads that could occur in any environment. However, these causes considered in causes are considered in the design of structural connections and eliminated by the initial preload preload bolt torquing. preload/self-loosening of structural bolting is not significant and will not torquing. Thus, loss of preload/self-loosening preload/self-loosening will be monitored through the Structures structural intended functions. Nevertheless, loss of preload/self-loosening impact structural Monitoring Program.

Structures Monitoring

2. Structures Monitoring Program is the applicable aging management Structures Monitoring management program for this component.
3. Concrete encased in steel is protected from environments thatpromote Concrete encased that promote age related degradations.
4. Masonry walls are inspected as a part of the Structures Monitoring Program, which includes the ten attributes of NUREG-1801 Structures Monitoring NUREG-1 801 Masonry Masonry Wall Program Program (XI.S5)
5. Based on industry standards and guidelines, grout is susceptible to cracking due to shrinkage susceptible t() shrinkage in this environment. However, shrinkage cracking shrinkage cracking occurs early in plant life and is not expected to be significant significant for the extended period of operation. Nevertheless, the aging effect will be monitored Monitoring Program.

through the Structures Monitoring Salem Nuclear Nuclear Generating Generating Station, Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-107 License Renewal Application

Section 33 - Aging Management Section Management Review Review Results Results

6. The aging effects and aging managementmanagement program identifed identifed for this material/environments material/environments combination combination are consistent with industl)'

industry guidance.

7. The Structures Structures Monitoring attributes of NUREG Monitoring Program includes the ten attributes NUREG 1801 1801 Regulatol)'

Regulatory Guide 1.127, Inspection Inspection of Water-Control Structures Water-Control Structures Associated With Nuclear Nuclear Power Plants (XI.S7)

Salem Nuclear Generating Station, Unit No.1 No. 1 and Unit No.2 No. 2 Page 3.5-108 3.5-108 is License Renewal Application License Renewal

  • Application
  • 0
  • Section 3 - Aging Management Review Results Table Table 3.5.2-2 3.5.2-2 Component Supports Component Supports Commodity Group Group Summary of Aging Management Summary Management Evaluation Evaluation 3.5.2-2 Table 3.5.2-2 Component Supports Supports Commodity Commodity GroupGroup Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Programs Programs Vol. 2 Item Item Management Management Supports forASME Structural Support for ASME Structural Reinforced Reinforced Air- Indoor Air-Indoor Reduction in Reduction in Concrete Concrete Structures Monitoring Monitoring 111.B1.1-1 III.B1.1-1 3.5.1-40 A A

Class 1 piping and concrete; Grout anchor capacity due to Program components components local concrete concrete (Building (Building concrete degradation/service-degradation/service-at locations of induced induced cracking cracking or other expansion and concrete aging grouted grouted anchors; mechanisms mechanisms grout pads for support base plates) forASME Supports for ASME Structural Support Carbon Steel Air- Indoor Air-Indoor Loss of Mechanical Mechanical ASME Section Xl,XI, 111.B1.1-2 III.B1.1-2 3.5.1-54 A A

Class 1 piping and Function/Corrosion, Function/Corrosion, Subsection IWF Subsection components components Distortion, Dirt, Overload, (Constant and Fatigue due to Vibratory Vibratory variable load spring and Cyclic Thermal Loads Loads hangers; guides; stops)

Supports for ASME Structural Structural Support High Strength Strength Air- Indoor Air-Indoor Loss of Material/General Material/General ASME Section Xl,Section XI, 111.B1.1-4 III.B1.1-4 3.5.1-51 3.5.1-51 E, 1, 5, 6 1,5,6 Class 1 piping and Low Alloy Steel Corrosion Corrosion Subsection IWF IWF components components (High (High Bolting Bolting with Yield strength strength bolting for Strength Greater Greater component NSSS component ksi 150 ksi supports)

Supports for ASME Structural Structural Support High Strength Strength Air with Borated Water Loss of Material/Boric Material/Boric Acid Boric Acid Corrosion 1I1.B1.1-14 III.B1.1-14 3.5.1-55 3.5.1-55 A Class 1 piping and Low Alloy Steel Low Alloy Steel Leakage Leakage Corrosion Corrosion components (High components (High Bolting Bolting with Yield strength strength bolting for Strength Greater Greater NSSS NSSS component ksi 150 ksi supports)

Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.

No.22 Page Page 3.5-109 3.5-109 License License Renewal Renewal Application Application

Section 3 - Aging Aging Management Management Review Review Results Results Table 3.5.2-2 3.5.2-2 Component Supports Commodity Commodity GroupGroup (Continued)

Component Component Intended Material Environment Environment Aging Effect Aging Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Notes Notes Type Function Requiring Requiring Programs Vol. 22 Item Item Management Manaaement Supports for ASME ASME Structural Support Support High High Strength Strength Air - Indoor Air-Indoor None None None G, 6, 7 Class 1 piping and Stainless Steel Stainless components (High components(High Bolting with Yield Yield strength bolting bolting for Strength Greater Strength Greater component NSSS component 150 150 ksi supports) for ASME Structural Support Supports forASME Support High Air with Borated Water Strength Airwith High Strength None None None I1.1B1.1-10 III.B1.1-10 3.5.1-59 A Class 1 piping and Stainless Steel Stainless Leakage Leakage components (High components Bolting with Yield Yield strength bolting for Strength Greater Strength Greater component NSSS component 150 ksi 150 supports)

ASME Structural Support Supports for ASME Support Graph-Air Graph-Air tool Air - Indoor Air-Indoor Loss of Mechanical Mechanical ASME ASME Section Section Xl, XI, II1.B2-2 III.B2-2 3.5.1-52 E, 1 Class 1 piping and steel Function/Corrosion, Function/Corrosion, IWF Subsection IWF components components Distortion, Dirt, Overload, (Sliding Surfaces Surfaces - Fatigue due Fatigue due to Vibratory component NSSS component and Cyclic Thermal Thermal Loads Loads supports)

Supports-for Supports-for ASME ASME Structural Support Lubrite Air- Indoor Air-Indoor Lock-up due to wear Lock-up ASME Section Xl,Section XI, II1.A4-6 1I1.A4-6 3.5.1-30 A Class 1 piping and Subsection IWF components components Surfaces -

(Sliding Surfaces component NSSS component supports)

Supports for ASME Structural Supports Structural Support Lubrite Air --Indoor Indoor Loss of Mechanical Mechanical Xl, ASME Section XI, II1.B1.1-5 III.B1.1-5 3.5.1-56 A Class 1 piping and Function/Corrosion, Function/Corrosion, Subsection IWF Subsection IWF components components Distortion, Dirt, Overload, (Sliding Surfaces - Fatigue due to Vibratory Fatigue NSSS component NSSS component and Cyclic Thermal Loads Loads supports)

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  • Section 3 - Aging Management Management Review Review Results Results 3.5.2-2 Table 3.5.2-2 Component Supports Commodity Component Commodity Group Group (Continued)

Component Component Intended Intended Material Environment Environment Aging Effect Aging Management Management NUREG-1801 NUREG-1801 Table 1 Item Notes Notes Type Function Requiring Requiring Programs Item Vol. 2 Item Management Management Supports forASME for ASME Structural Support Carbon Carbon Steel Air --Indoor Indoor Material/General, Loss of Material/General, ASME ASME Section XI, XI, III.B1.1-13 III.B1.1-13 3.5.1-53 A A

Class 1 piping and Pitting and and Crevice IWF Subsection IWF components components Corrosion (Support members; welds; bolted connections; anchorage support anchorage to building building structure) structure)

Supports forASME for ASME Structural Structural Support Carbon Steel Air with Borated Water Loss of Material/Boric Acid Corrosion Boric Acid Corrosion 1111.1.1-14 III.B1.1-14 3.5.1-55 A A

Class 1 piping and Leakage Leakage Corrosion components components (Support members; welds; bolted connections; support anchorage anchorage to building building structure) structure)

Supports for ASME ASME Structural Structural Support Carbon Steel Air with Steam or Water Water Loss of Material/General, Material/General, ASME Section Xl, XI, G, 3 G,3 Class 1 piping and Leakage Leakage Pitting and Crevice Subsection IWF Subsection IWF components components Corrosion (Support members; welds; bolted connections; support support anchorage anchorage to building building structure) structure)

Supports for ASME Structural Structural Support Carbon Carbon and Low Air- Indoor Air-Indoor Loss of Material/General, ASME Section XI, 111.B1.1-13 III.B1.1-13 3.5.1-53 A A

Class 1 piping and Alloy Steel Pitting and Crevice Subsection IWF Subsection IWF components components Bolting Corrosion Corrosion (Support members; welds; bolted connections; support support anchorage anchorage building to building structure) structure) I Salem Nuclear Generating Generating Station, Unit No.1 No. 1 and Unit No.

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Section - Aging Management Review Results Section 33 - Aging Management Review Results Table 3.5.2-2 Table 3.5.2-2 Component Supports Component Commodity Group Supports Commodity Group (Continued)

(Continued)

Component Component Intended Intended Material Material Environment Environment Aging Effect Effect Aging Management Management NUREG-1801 NUREG-1801 Table I1 Item Item Notes Notes Type Function Function Requiring Requiring Programs Vol. 22 Item Item Management Management Supports for ASME ASME Structural Structural Support Carbon and Low Air-Indoor Air- Indoor Loss of Preload/Self- Section Xl, ASME Section XI, VII.l-5 VIU-5 3.3.1-45 E, E, 1, 1,2 2 Class 1 piping andand Alloy Steel Alloy Loosening Loosening Subsection IWF Subsection IWF components components Bolting Bolting (Support members; bolted welds; bolted connections; support anchorage support anchorage to building building structure) structure)

Supports for Supports for ASME ASME Structural Structural Support Support Carbon and Carbon and Low Air with Low Air with Borated Borated Water Loss of Water Loss of Material/Boric Material/Boric Acid Acid Boric Acid Corrosion Corrosion III.B1.1-14 III.B1.1-14 3.5.1-55 3.5.1-55 A A

Class 1 piping andand Alloy Steel Alloy Leakage Leakage Corrosion Corrosion components components Bolting Bolting (Support members; bolted welds; bolted connections; support anchorage anchorage to building building structure) structurej Supports Structural Support Supports for ASME Structural Water Loss of Material/General, Low Air with Steam or Water and Low Carbon and Material/General, ASME Section XI, XI, G, 3 G,3 Class 1 piping and Alloy Steel Leakage Leakage Pitting and Crevice Pitting Crevice Subsection IWVF Subsection IWF components components Bolting Corrosion Corrosion (Support members; welds; bolted connections; anchorage support anchorage building to building structurej structure)

Supports forASME for ASME Structural Support Structural Support Stainless Steel Stainless Air--Indoor Air Indoor None None None I11.B1.1-9 III.B1.1-9 3.5.1-59 A A

Class 1 piping and components components (Support members; ,

welds; bolted bolted connections; support anchorage anchorage to building structurel structure)

Salem Nuclear Generating Station, Unit No.

No.11 and Unit No.2 No. 2 Page 3.5-112 3.5-112 Application Renewal Application 0

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  • Section 3 - Aging Management Management Review Results 3.5.2-2 Table 3.5.2-2 Component Supports Component Supports Commodity Group Group (Continued)

Component Intended Material Material Environment

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