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Ageing Management Program (AMP)
  
Remarks
Design
1
101
  
Main circulation loop/ pipingCracking due to stress corrosion crackingClass 1 piping, piping components and piping elementsCast austenitic stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection
No
PWR
2
101
  
Pump, valveLoss of fracture toughness due to thermal ageing embrittlementClass 1 pump casings, valve bodies and bonnetsCast austenitic stainless steelReactor coolant >250°C (>482°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP112 Thermal Ageing Embrittlement of Cast Austenitic Stainless Steel
Yes, if TLAA (TLAA110 Thermal Ageing of Cast Austenitic Stainless Steels)
PWR
3
101
  
Pump, valveCracking due to stress corrosion crackingClass 1 pump casings, valve bodiesSteel with stainless steel cladding, stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP138 Reactor Coolant Pump
No
PWR
4
101
  
Main circulation loop/ pipingCracking due to stress corrosion crackingClosure boltingHigh-strength, low alloy steel, stainless steelAir with reactor coolant leakage
AMP102 In-service Inspection/ Periodic Inspection, AMP115 Bolting Integrity
No
PWR
5
101
  
Main circulation loop/ pipingLoss of preload due to thermal effects, gasket creep, self-looseningClosure boltingNickel alloy, stainless steelAir with reactor coolant leakage
AMP115 Bolting Integrity
No
PWR
6
101
  
PressurizerCumulative fatigue damage due to fatiguePressurizer relief tank: tank shell and head, flange, nozzleSteel with stainless steel or nickel-alloy claddingTreated borated water
AMP101 Fatigue Monitoring
Yes, if TLAA (TLAA101 Low-Cycle Fatigue Usage, TLAA106 Environmentally Assisted Fatigue)
PWR
7
101
  
Main circulation loop/ pipingLoss of material due to boric acid corrosionExternal surfaceSteelAir with borated water leakage
AMP110 PWR Boric Acid Corrosion
No
PWR
8
101
  
Main circulation loop/ pipingCumulative fatigue damage due to fatiguePiping and component (external surface), boltingSteel, stainless steelSystem temperature up to 340°C (644°F)
AMP101 Fatigue Monitoring
Yes, if TLAA (TLAA101 Low-Cycle Fatigue Usage)
PWR
9
101
  
PressurizerCracking due to cyclic loadingPressurizer: integral supportSteel, stainless steelAir with metal temperature up to 288°C (550°F)
AMP102 In-service Inspection/ Periodic Inspection
No
PWR
10
101
  
PressurizerCracking due to stress corrosion crackingPressurizer heater sheath and sleeve, heater bundle diaphragm plateStainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
11
101
  
Main circulation loop/ pipingCumulative fatigue damage due to fatigueReactor coolant pressure boundary components: piping, piping components, piping element, flange, nozzle and safe end, pressurizer vessel shell head, weld, heater sheath and sleeve, penetration, thermal sleeveSteel with or without nickel-alloy or stainless steel cladding, stainless steel, nickel alloyReactor coolant
AMP101 Fatigue Monitoring
Yes, if TLAA (TLAA101 Low-Cycle Fatigue Usage, TLAA106 Environmentally Assisted Fatigue)
PWR
12
101
  
PressurizerCracking due to stress corrosion cracking, primary water stress corrosion crackingPressurizer componentsSteel with stainless steel or nickel-alloy cladding, stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
13
101
  
Main circulation loop/ pipingCracking due to stress corrosion crackingReactor coolant system piping and fittings: cold leg, hot leg, surge line, spray lineSteel with stainless steel cladding, stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
14
101
  
Main circulation loop/ pipingLoss of fracture toughness due to thermal ageing embrittlementClass 1 piping, piping components and piping elementsCast austenitic stainless steelReactor coolant >250°C (>482°F)
AMP112 Thermal Ageing Embrittlement of Cast Austenitic Stainless Steel
No
PWR
15
101
  
Main circulation loop/ pipingCracking due to cyclic loadingReactor coolant system piping and fittings: cold leg, hot leg, surge line, spray lineSteel with stainless steel cladding, stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection
No
PWR
16
101
  
PressurizerCracking due to cyclic loadingPressurizer componentsSteel with stainless steel or nickel-alloy cladding, stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
17
101
  
Main circulation loop/ pipingLoss of material due to selective leachingPiping, piping component, piping elementCopper alloy (>15% Zn or >8% Al)Closed cycle cooling water
AMP120 Selective Leaching
No
PWR
18
101
  
PressurizerCracking due to primary water stress corrosion crackingPressurizer surge and steam space nozzle, weldNickel alloyReactor coolant, steam
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
19
101
  
Main circulation loop/ pipingCracking due to primary water stress corrosion crackingPiping, piping component, piping elementNickel alloyReactor coolant, steam
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
20
101
  
Main circulation loop/ pipingLoss of material due to general, pitting, crevice corrosionClosure boltingSteelAir - indoor uncontrolled
AMP115 Bolting Integrity
No
PWR
21
101
  
Main circulation loop/ pipingLoss of material due to boric acid corrosionClosure boltingSteelAir with borated water leakage
AMP110 PWR Boric Acid Corrosion
No
PWR
22
101
  
Main circulation loop/ pipingLoss of material due to general, pitting, crevice corrosionPiping, piping component, piping elementSteelClosed cycle cooling water
AMP117 Closed Treated Water Systems
No
PWR
23
101
  
Main circulation loop/ pipingLoss of material due to pitting, crevice, galvanic corrosionPiping, piping component, piping elementCopper alloyClosed cycle cooling water
AMP117 Closed Treated Water Systems
No
PWR
24
101
  
Main circulation loop/ pipingLoss of material due to pitting, crevice corrosionPiping, piping component, piping element, flange, heater sheath and sleeve, penetration, thermal sleeve, vessel shell head, weldSteel with stainless steel or nickel-alloy cladding, stainless steel, nickel alloyReactor coolant
AMP103 Water Chemistry
No
PWR
25
101
  
PressurizerCracking due to stress corrosion crackingPressurizer relief tank: tank shell and head, flange, nozzleStainless steel, steel with stainless steel claddingTreated borated water >60°C (>140°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
26
101
  
Main circulation loop/ pipingCracking due to stress corrosion cracking, intergranular stress corrosion cracking (for stainless steel only), mechanical, thermal, vibratory loadingClass 1 piping, fittings and branch connections < 100mm (4 inch)Stainless steel, steel with stainless steel claddingTreated borated water >60°C (>140°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP121 One-Time Inspection of Class 1 Small-bore piping
No
PWR
27
101
  
Main circulation loop/ pipingCracking due to stress corrosion crackingClass 1 piping, piping components and piping elementsStainless steel, steel with stainless steel claddingTreated borated water >60°C (>140°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
28
101
  
PressurizerCracking due to primary water stress corrosion crackingPressurizer instrumentation penetration, heater sheath and sleeve, heater bundle diaphram plate, manway and flangeNickel alloy, nickel-alloy claddingTreated borated water >60°C (>140°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
29
101
  
Main circulation loop/ pipingLoss of material due to boric acid corrosionExternal surface: reactor coolant pressure boundary piping or components adjacent to dissimilar metal (alloy 82/ 182) weldSteelAir with borated water leakage
AMP110 PWR Boric Acid Corrosion, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
30
101
  
PressurizerCracking due to stress corrosion crackingPressurizer relief tank: tank shell and head, flange, nozzleStainless steel, steel with stainless steel claddingTreated borated water >60°C (>140°F)
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP119 One-Time Inspection
No
PWR
31
101
  
PressurizerCracking due to stress corrosion cracking, primary water stress corrosion crackingPressurizer: spray headNickel alloyTreated borated water >60°C (>140°F)
AMP103 Water Chemistry, AMP119 One-Time Inspection
No
PWR
32
101
  
PressurizerCracking due to stress corrosion crackingPressurizer: spray headStainless steelTreated borated water >60°C (>140°F)
AMP103 Water Chemistry, AMP119 One-Time Inspection
No
PWR
33
101
  
Reactor pressure vessel (PWR)Loss of material due to boric acid corrosionExternal surfaceSteelAir with borated water leakage
AMP110 PWR Boric Acid Corrosion
No
PWR
34
101
  
Reactor pressure vessel (PWR)Cumulative fatigue damage due to fatigueReactor pressure vessel components: flange, nozzle, penetration, pressure housing, safe end, thermal sleeve, vessel shell, head, weldSteel with or without nickel-alloy or stainless steel cladding, stainless steel, nickel alloyTreated borated water >60°C (>140°F)
AMP101 Fatigue Monitoring
Yes, if TLAA (TLAA101 Low-Cycle Fatigue Usage, TLAA106 Environmentally Assisted Fatigue)
PWR
35
101
  
Reactor pressure vessel (PWR)Cumulative fatigue damage due to fatiguePressure vessel support skirt and attachment weldSteelAir - indoor uncontrolled
AMP101 Fatigue Monitoring
Yes, if TLAA (TLAA101 Low-Cycle Fatigue Usage)
PWR
36
101
  
Reactor pressure vessel (PWR)Cracking due to stress corrosion crackingClosure head: vessel flange leak detection lineStainless steelAir with borated water leakage
AMP102 In-service Inspection/ Periodic Inspection, a plant-specific ageing management programme
Yes, if plant- specific AMP
A plant-specific ageing management programme to mitigate or detect cracking
PWR
37
101
  
Reactor pressure vessel (PWR)Loss of fracture toughness due to thermal ageing embrittlementControl rod drive head penetration: pressure housingCast austenitic stainless steelReactor coolant >250°C (>482°F)
AMP112 Thermal Ageing Embrittlement of Cast Austenitic Stainless Steel
No
PWR
38
101
  
Reactor pressure vessel (PWR)Cracking due to stress corrosion crackingControl rod drive head penetration: flange boltingStainless steelAir with reactor coolant leakage
AMP115 Bolting Integrity
No
PWR
39
101
  
Reactor pressure vessel (PWR)Loss of material due to wearControl rod drive head penetration: flange boltingStainless steelAir with reactor coolant leakage
AMP115 Bolting Integrity
No
PWR
40
101
  
Reactor pressure vessel (PWR)Loss of preload due to thermal effects, gasket creep, self-looseningControl rod drive head penetration: flange boltingStainless steelAir with reactor coolant leakage
AMP115 Bolting Integrity
No
PWR
41
101
  
Reactor pressure vessel (PWR)Loss of fracture toughness due to neutron irradiation embrittlementNozzle: inlet, outlet, safety injectionSteel with stainless steel, nickel-alloy cladding or without claddingReactor coolant and neutron flux
AMP118 Reactor Vessel Surveillance
Yes, if TLAA (TLAA102 RPV Neutron Embrittlement)
PWR
42
101
  
Reactor pressure vessel (PWR)Loss of fracture toughness due to neutron irradiation embrittlementVessel shell: upper shell, intermediate shell, lower shell (including beltline weld)Steel with stainless steel or nickel-alloy claddingReactor coolant and neutron flux
AMP118 Reactor Vessel Surveillance
Yes, if TLAA (TLAA102 RPV Neutron Embrittlement)
PWR
43
101
  
Reactor pressure vessel (PWR)Crack growth due to cyclic loadingVessel shell: upper shell, intermediate shell, lower shell (including beltline weld)Low alloy steel SA508-Cl 2 forgings clad (with stainless steel) using a high-heat-input welding processReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
Yes, if TLAA (TLAA115 Fatigue and Thermal Ageing Analysis of Manufacturing Flaws)
PWR
44
101
  
Reactor pressure vessel (PWR)Loss of material due to wearVessel shell: vessel flangeSteelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection
No
PWR
45
101
  
Reactor pressure vessel (PWR)Cracking due to primary water stress corrosion crackingPenetration: head vent piping (top head), instrument tube (top head)Nickel alloyReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
46
101
  
Reactor pressure vessel (PWR)Cracking due to stress corrosion crackingBottom-mounted instrument guide tube (external to bottom head)Stainless steelReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, a plant-specific ageing management programme
Yes, if plant- specific AMP
PWR
47
101
  
Reactor pressure vessel (PWR)Cracking due to primary water stress corrosion crackingControl rod drive head penetration: nozzle weldNickel alloyReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
50
101
  
Reactor pressure vessel (PWR)Cracking due to stress corrosion cracking, primary water stress corrosion crackingNozzle safe end and weld: inlet, outlet, safety injectionStainless steel, nickel alloy weld or butteringReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
51
101
  
Reactor pressure vessel (PWR)Loss of material due to pitting, crevice corrosionFlange, head weld, nozzle, penetration, pressure housing, safe end, vessel shellSteel with stainless steel or nickel-alloy cladding, stainless steel, nickel alloyReactor coolant
AMP102 In-service Inspection/ Periodic Inspection, AMP103 Water Chemistry
No
PWR
52
101
  
Reactor pressure vessel (PWR)Loss of material due to boric acid corrosionExternal surface: reactor pressure vessel top head and bottom headSteelAir with reactor coolant leakage
AMP110 PWR Boric Acid Corrosion, AMP111 PWR Cracking of Nickel-Alloy Reactor Coolant Pressure Boundary Components
No
PWR
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