ML052000234
| ML052000234 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/06/2005 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Morgan M, NRR/NRC/DRIP/RLEP, 415-2232 | |
| Shared Package | |
| ML052000229 | List: |
| References | |
| Download: ML052000234 (48) | |
Text
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 1 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Alloy 600 Cladding Shelter /
Protection Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.D1.1-i 3.1.1-44 C
Water Chemistry Program IV.D1.1-i 3.1.1-44 C
Alloy 600 Safe Ends Fluid Pressure Boundary Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.C2.2-f 3.1.1-36 A, 123 IV.C2.5-h 3.1.1-36 A
Water Chemistry Program IV.C2.2-f 3.1.1-36 A, 123 IV.C2.5-h 3.1.1-36 A
Alloy 600 Thermal Sleeves Shelter /
Protection Alloy 600/690 Treated Water (Ext)
Cracking Alloy 600 Program IV.C2.5-k 3.1.1-14 C, 124 Water Chemistry Program IV.C2.5-k 3.1.1-14 C, 124 Bolting and Fasteners Fluid Pressure Boundary Low Alloy Steel Containment Air (Ext)
Loss of Preload Bolting Integrity Program IV.C2.4-g 3.1.1-27 101, A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 2 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Loss of Material Bolting Integrity Program F
V.E-4 2-25 A
Boric Acid Corrosion Program IV.C2.1-d 3.1.1-39 C
IV.C2.2-d 3.1.1-39 C
Plant Indoor Air (Ext)
Loss of Preload Bolting Integrity Program IV.C2.4-g 3.1.1-27 A
Loss of Material Bolting Integrity Program F
V.E-4 2-25 A
Boric Acid Corrosion Program IV.C2.1-d 3.1.1-39 C
IV.C2.2-d 3.1.1-39 C
Carbon Steel Nozzles Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.2-d 3.1.1-38 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 3 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Carbon Steel Pipe (30 and
- 42)
Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.1-d 3.1.1-38 A
Flow Element (PCP Controlled Bleed)
Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.2-f 3.1.1-36 C
Water Chemistry Program IV.C2.2-f 3.1.1-36 C
Non-CASS Valves in PCS and Connected Systems Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.2-f 3.1.1-36 C
Water Chemistry Program IV.C2.2-f 3.1.1-36 C
IV.C2.2-f 3.1.1-36 C
PCS Spray and Drain Nozzles Fluid Pressure Boundary Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.C2.5-k 3.1.1-14 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 4 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes IV.C2.5-s 3.1.1-14 C
Water Chemistry Program IV.C2.5-k 3.1.1-14 C
IV.C2.5-s 3.1.1-14 C
PORV Isolation, Quench Tank Spray Manual Valves Fluid Pressure Boundary Cast Austenitic SS Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.4-b 3.1.1-36 A
Water Chemistry Program IV.C2.4-b 3.1.1-36 A
PORV Isolation Valves Fluid Pressure Boundary Cast Austenitic SS Treated Water (Int)
Reduction of Fracture Toughness ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.4-c 3.1.1-23 A
Pressurizer Alloy 600 Instrument Penetrations Fluid Pressure Boundary Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.C2.5-k 3.1.1-14 A
Water Chemistry Program IV.C2.5-k 3.1.1-14 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 5 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Pressurizer Heater Sleeves Fluid Pressure Boundary Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.C2.5-s 3.1.1-14 A
Water Chemistry Program IV.C2.5-s 3.1.1-14 A
Pressurizer Heaters Fluid Pressure Boundary Alloy 600/690 Treated Water (Int)
Cracking Alloy 600 Program IV.C2.5-s 3.1.1-14 A
Water Chemistry Program IV.C2.5-s 3.1.1-14 A
Pressurizer Integral Support Weld Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.5-v 3.1.1-41 A
Loss of Material Boric Acid Corrosion Program IV.C2.5-u 3.1.1-38 A
Pressurizer Manway and Flange Bolting Fluid Pressure Boundary Low Alloy Steel Containment Air (Ext), Borated Water or Steam Leakage Loss of Material Boric Acid Corrosion Program IV.C2.5-o 3.1.1-38 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 6 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.5-o 3.1.1-38 A
Loss of Preload Bolting Integrity Program IV.C2.5-p 3.1.1-26 101, A Pressurizer Manway and Flanges Fluid Pressure Boundary Carbon Steel Containment Air (Ext), Borated Water or Steam Leakage Loss of Material Boric Acid Corrosion Program IV.C2.5-o 3.1.1-38 A
Pressurizer Quench Tank Fluid Pressure Boundary Epoxy Coated Carbon Steel Containment Air (Ext)
Loss of Material System Monitoring Program IV.C2.6-b 3.1.1-38 E
Treated Water (Int)
Loss of Material One-Time Inspection Program F
VII.A3-8 3-22 E
Pressurizer Quench Tank Shell and Heads Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.6-b 3.1.1-38 A
Pressurizer Spray Head Spray Pattern Alloy 600/690 Treated Water (Int)
Cracking One-Time Inspection Program IV.C2.5-j 3.1.1-12 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 7 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Water Chemistry Program IV.C2.5-j 3.1.1-12 A
Primary Coolant Pump Casing Fluid Pressure Boundary Cast Austenitic SS Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.3-b 3.1.1-36 A
Water Chemistry Program IV.C2.3-b 3.1.1-36 A
Reduction of Fracture Toughness ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.3-c 3.1.1-23 A
Primary Coolant Pump Closure Bolting Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Preload Bolting Integrity Program IV.C2.3-g 3.1.1-27 101, A Loss of Material Boric Acid Corrosion Program IV.C2.3-f 3.1.1-39 A
Primary Coolant Sample Heat Exchanger Shell Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.2-d 3.1.1-38 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 8 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes System Monitoring Program VII.I.1-b 3.1.1-05 A
Treated Water (Int)
Loss of Material Closed Cycle Cooling Water Program V.D1.5-a 3.1.1-13 C
Reactor Head Vent Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-g 3.1.1-07 C
Water Chemistry Program IV.C2.1-g 3.1.1-07 C
Reactor Head Vent Orifice Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-g 3.1.1-07 A
Water Chemistry Program IV.C2.1-g 3.1.1-07 A
Sample Point (Quench Tank Liquid, Loop 2 Hot Leg, Pressurizer Surge Line)
Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-g 3.1.1-07 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 9 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes IV.C2.2-h 3.1.1-07 C
Water Chemistry Program IV.C2.1-g 3.1.1-07 C
IV.C2.2-h 3.1.1-07 C
Small Bore Stainless Steel Pipe (PCS and Connected Systems)
Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-g 3.1.1-07 A
IV.C2.2-h 3.1.1-07 A
Water Chemistry Program IV.C2.1-g 3.1.1-07 A
IV.C2.2-h 3.1.1-07 A
SS Cladding Shelter/
Protection Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-c 3.1.1-36 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 10 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes IV.C2.5-c 3.1.1-36 A
IV.C2.5-g 3.1.1-36 A
IV.C2.5-h 3.1.1-36 A
IV.C2.5-m 3.1.1-36 A
Water Chemistry Program IV.C2.1-c 3.1.1-36 A
IV.C2.5-c 3.1.1-36 A
IV.C2.5-g 3.1.1-36 A
IV.C2.5-h 3.1.1-36 A
IV.C2.5-m 3.1.1-36 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 11 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes Stainless Steel Pipe (PCS and Connected Systems)
Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.1-c 3.1.1-36 A
IV.C2.2-f 3.1.1-36 A
Water Chemistry Program IV.C2.1-c 3.1.1-36 A
IV.C2.2-f 3.1.1-36 A
Stainless Steel Safe Ends (Pressurizer and Connected Systems)
Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.2-f 3.1.1-36 A
IV.C2.5-h 3.1.1-36 A
Water Chemistry Program IV.C2.2-f 3.1.1-36 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 12 of 48 6/6/2005 Table 3.1.2-1 Reactor Coolant System - Primary Coolant System - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 NUREG -
1801 Volume 1 Table Row (Table # -
Row #)
Rev 1 NUREG
- 1801 Notes IV.C2.5-h 3.1.1-36 A
Stainless Steel Thermal Sleeves Shelter /
Protection Stainless Steel Treated Water (Ext)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.5-h 3.1.1-36 C
Water Chemistry Program IV.C2.5-h 3.1.1-36 C
Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.5-h 3.1.1-36 C
Water Chemistry Program IV.C2.5-h 3.1.1-36 C
Stainless Steel Tubing Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.C2.2-f 3.1.1-36 A
Water Chemistry Program IV.C2.2-f 3.1.1-36 A
- Vessels, Pressure (Pressurizer)
Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.C2.5-b 3.1.1-38 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 13 of 48 6/6/2005
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 14 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes CRDM Upper Pressure Housing &
Flange Pressure Boundary/
Fission Product Retention Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.2-b 3.1.1-36 A
Water Chemistry Program IV.A2.2-b 3.1.1-36 A
CRDM/Incore Instrument Bolting Pressure Boundary/
Fission Product Retention Stainless Steel Containment Air (Ext)
Loss of Material Bolting Integrity Program IV.A2.2-f 3.1.1-26 A
Loss of Preload Bolting Integrity Program IV.A2.2-g 3.1.1-26 101, A Cracking Bolting Integrity Program IV.A2.2-e 3.1.1-26 A
Incore Instrument Closure Flanges Pressure Boundary/
Fission Product Retention Stainless Steel Containment Air (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.2-f 3.1.1-26 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 15 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.2-b 3.1.1-36 C
Water Chemistry Program IV.A2.2-b 3.1.1-36 C
Internal SS Cladding Pressure Boundary/
Fission Product Retention Stainless Steel Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.4-b 3.1.1-36 C
Water Chemistry Program IV.A2.4-b 3.1.1-36 C
Reactor Vessel Column Support Component Structural Support Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.8-b 3.1.1-38
- 119, 122, A Reactor Vessel Bottom Head Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 16 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel Closure Head Component Structural Support Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.5-f 3.1.1-40 C
Boric Acid Corrosion Program IV.A2.1-a 3.1.1-38 A
Reactor Vessel Closure Head Lifting Lugs Component Structural Support Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.1-a 3.1.1-38 C
Reactor Vessel Core Stabilizer Lugs Structure Functional Support Nickel-Based Alloys Treated Water (Ext)
Cracking Water Chemistry Program IV.A2.6-a 3.1.1-12 A
Reactor Vessel Internals Inspection Program IV.A2.6-a 3.1.1-12 A
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program 110, H IV.B3-22 1-52 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 17 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel CRDM Nozzles Structure Functional Support Pressure Boundary/
Fission Product Retention Nickel-Based Alloys Treated Water (Int)
Cracking Alloy 600 Program IV.A2.2-a 3.1.1-35 A
Water Chemistry Program IV.A2.2-a 3.1.1-35 A
Reactor Vessel Flow Skirt Reduce Flow Inequalities Nickel-Based Alloys Treated Water (Ext)
Cracking Water Chemistry Program IV.A2.6-a 3.1.1-12 E
Reactor Vessel Internals Inspection Program IV.A2.6-a 3.1.1-12 A
Reactor Vessel Head O-ring Leakage Monitoring Pressure Boundary/
Fission Product Retention Nickel-Based Alloys Treated Water (Int)
Cracking Alloy 600 Program IV.A2.1-f 3.1.1-12 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 18 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel Head Vent Nozzle Pressure Boundary/
Fission Product Retention Nickel-Based Alloys Treated Water (Int)
Cracking Alloy 600 Program IV.A2.7-b 3.1.1-35 A
Water Chemistry Program IV.A2.7-b 3.1.1-35 A
Reactor Vessel Incore Instrument Nozzles Pressure Boundary/
Fission Product Retention Nickel-Based Alloys Treated Water (Int)
Cracking Alloy 600 Program IV.A2.7-b 3.1.1-35 121, A Water Chemistry Program IV.A2.7-b 3.1.1-35 A
Reactor Vessel Intermediate Shell Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Reduction in Fracture Toughness Reactor Vessel Integrity Surveillance Program IV.A2.5-c 3.1.1-05 109, A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 19 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel Lower Shell Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Reduction in Fracture Toughness Reactor Vessel Integrity Surveillance Program IV.A2.5-c 3.1.1-05 109, A Reactor Vessel Nozzle Safe Ends Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Reactor Vessel Primary Coolant Nozzles Pressure Boundary/
Fission Product Retention Structure Functional Support Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 20 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel Seal Ledge Ring Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 C
Reactor Vessel Stop Lugs Prevent Core Displacement Nickel-Based Alloys Treated Water (Ext)
Cracking Water Chemistry Program IV.A2.6-a 3.1.1-12 A
Reactor Vessel Internals Inspection Program IV.A2.6-a 3.1.1-12 A
Reactor Vessel Studs, Nuts, Washers Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Crack Initiation and Growth ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.1-c 3.1.1-22 A
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.1-d 3.1.1-47 C
Boric Acid Corrosion Program IV.A2.1-a 3.1.1-38 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 21 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reactor Vessel Surveillance Capsule Holder Structure Functional Support Nickel-Based Alloys Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.A2.6-a 3.1.1-12 A
Water Chemistry Program IV.A2.6-a 3.1.1-12 C
Reactor Vessel Upper Shell Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.5-f 3.1.1-40 A
Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 A
Reactor Vessel Upper Shell Flange Pressure Boundary/
Fission Product Retention Carbon Steel Containment Air (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.5-f 3.1.1-40 A
Boric Acid Corrosion Program IV.A2.5-e 3.1.1-38 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 22 of 48 6/6/2005 Table 3.1.2-2 Reactor Coolant System - Reactor Vessel - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Under Head CRDM Support Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.A2.2-b 3.1.1-36 C
Water Chemistry Program IV.A2.2-b 3.1.1-36 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 23 of 48 6/6/2005
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 24 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Control Rod Shroud Assembly =
IV.B3.2 -
CEA Shroud Assemblies Control Rod Shroud Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.2-c 3.1.1-11 A, 113 Control Rod Shroud, Shroud Top Support, Shroud Support Lug Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.2-a 3.1.1-45 A
Water Chemistry Program IV.B3.2-a 3.1.1-45 A
Control Rod Support Lug, Fuel Guide Pin, Fuel Guide Pin Nuts Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.2-c 3.1.1-11 A, 113
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 25 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Fuel Guide Pin, Fuel Guide Pin Nuts Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.2-b 3.1.1-45 A
Water Chemistry Program IV.B3.2-b 3.1.1-45 A
Fuel Guide Pin, Fuel Guide Pin Nuts, Fuel Plate Cap Screw Structure Functional Support Stainless Steel Treated Water (Ext)
Loss of Preload ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program V.B3.2-g 3.1.1-48 101, A Core Shroud Assembly =
IV.B3.4 -
Core Shroud Assembly Anchor Block, Centering Plate, Core Shroud Plate Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.4-b 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.4-a 3.1.1-45 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 26 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Water Chemistry Program IV.B3.4-a 3.1.1-45 A
Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.4-c 3.1.1-43 A, 113 Anchor Screw &
Pin, Centering Screw & Pin, Positioning Screw, Shroud Bolt & Pin Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.4-e 3.1.1-45 A
Water Chemistry Program IV.B3.4-e 3.1.1-45 A
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.4-f 3.1.1-11 A, 113 Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.4-g 3.1.1-43 A, 113 Loss of Preload ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.4-h 3.1.1-48 101, A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 27 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Core Support Barrel Assembly =
IV.B3.3 -
Core Support Barrel Assembly Core Support Barrel Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.3-a 3.1.1-45 A
Water Chemistry Program IV.B3.3-a 3.1.1-45 A
Core Support Barrel Integral Upper Flange Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.3-a 3.1.1-45 A
Water Chemistry Program IV.B3.3-a 3.1.1-45 A, 113 Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.3-b 3.1.1-11 A, 113
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 28 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Incore Instrument Guide Tube (This group of components is not addressed in GALL IV.B3)
Guide Tube Plug Screw Structure Functional Support Stainless Steel Treated Water (Ext)
Loss of Preload ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.2-g 3.1.1-48 E, 103 Instrument Guide Tube, Guide Tube Bracket Structure Functional Support Stainless Steel Treated Water (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 29 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Instrument Guide Tube, Guide Tube Bracket, Guide Tube Plugs, Guide Tube Plug Screw, Guide Tube Support Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.1-b 3.1.1-11 C, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.1-a 3.1.1-45 C
Water Chemistry Program IV.B3.1-a 3.1.1-45 C
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 C
Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.3-a 3.1.1-45 C, 113
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 30 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Lower Internal Assembly (Integral with Core Barrel Assembly) =
IV.B3.5 -
Lower Internal Assembly Core Support Barrel Cap Screws Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.5-c 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.5-b 3.1.1-45 A
Water Chemistry Program IV.B3.5-b 3.1.1-45 A
Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.5-d 3.1.1-11 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 31 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Core Support Barrel Snubber Lug Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.5-c 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.5-a 3.1.1-45 A
Water Chemistry Program IV.B3.5-a 3.1.1-45 A
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.5-e 3.1.1-40 A
Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.5-d 3.1.1-11 A
Core Support Column Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.5-c 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.5-a 3.1.1-45 A
Water Chemistry Program IV.B3.5-a 3.1.1-45 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 32 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Core Support Column Support Beams and Tie Rods Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.5-c 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.5-a 3.1.1-45 A
Water Chemistry Program IV.B3.5-a 3.1.1-45 A
Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.5-d 3.1.1-11 A
Core Support Plate Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.5-c 3.1.1-11 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.5-a 3.1.1-45 A
Water Chemistry Program IV.B3.5-a 3.1.1-45 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 33 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.5-d 3.1.1-11 A
Upper Guide Structure -
Not in GALL Instrument Sleeve Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.1-b 3.1.1-11 C, 113 Reduction in Fracture Toughness Reactor Vessel Internals Inspection Program IV.B3.2-e 3.1.1-43 F
IV.B3-7 1-13 C
Spacer Shim, Instrument Sleeve Structure Functional Support Stainless Steel Treated Water (Ext)
Cracking Reactor Vessel Internals Inspection Program IV.B3.1-a 3.1.1-45 C
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 34 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Upper Internal Assembly =
GALL IV.B3.1 -
Upper Internal Assembly Brace Grid Beam, Cross Brace Screw, Shroud Grid Ring Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.1-b 3.1.1-45 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.1-a 3.1.1-45 A
Water Chemistry Program IV.B3.1-a 3.1.1-45 A
Fuel Alignment Plate Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.1-b 3.1.1-45 A, 113
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 35 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Cracking Reactor Vessel Internals Inspection Program IV.B3.1-a 3.1.1-45 A
Water Chemistry Program IV.B3.1-a 3.1.1-45 A
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 A
Fuel Plate Align Lug, Fuel Plate Cap Screw, Fuel Plate Guide Pin Structure Functional Support Stainless Steel Treated Water (Ext)
Changes in Dimensions Reactor Vessel Internals Inspection Program IV.B3.1-b 3.1.1-45 A, 113 Cracking Reactor Vessel Internals Inspection Program IV.B3.1-a 3.1.1-45 A
Water Chemistry Program IV.B3.1-a 3.1.1-45 A
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 36 of 48 6/6/2005 Table 3.1.2-3 Reactor Coolant System - Reactor Vessel Internals - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Holddown Ring
- Plunger, Holddown Ring Strap, Holddown Ring Structure Functional Support Stainless Steel Treated Water (Ext)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.B3.1-c 3.1.1-40 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 37 of 48 6/6/2005
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 38 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Alloy 690 Tube Plugs Fluid Pressure Boundary Alloy 600/690 Treated Water (Ext)
Cracking Steam Generator Tube Integrity Program IV.D1.2-i 3.1.1-18 A
Water Chemistry Program IV.D1.2-i 3.1.1-18 A
Treated Water (Int)
Cracking Steam Generator Tube Integrity Program IV.D1.2-i 3.1.1-18 A
Water Chemistry Program IV.D1.2-i 3.1.1-18 A
Handhole Cover Fluid Pressure Boundary Low-Alloy Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 39 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Water Chemistry Program IV.D1.1-c 3.1.1-02 C
Tube Bundle Support Assembly Structural Support for Safety Related Stainless Steel Treated Water (Ext)
Cracking Water Chemistry Program F
IV.D1-9 1-61 A
Steam Generator Tube Integrity Program 118, F IV.D1-9 1-61 A
Carbon Steel Treated Water (Ext)
Loss of Material Water Chemistry Program IV.D1.2-k 3.1.1-20 A
Steam Generator Tube Integrity Program IV.D1.2-k 3.1.1-20 118, A Tube Bundle Wrapper Direct Flow Low Alloy Steel Treated Water (Int)
Loss of Material Water Chemistry Program F
IV.D1-8 1-65 E
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 40 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Lower Head Fluid Pressure Boundary Carbon Steel w/SS cladding Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 A
Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-i 3.1.1-44 C
Water Chemistry Program IV.D1.1-i 3.1.1-44 C
Primary Manway Cover Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-k 3.1.1-38 A
Manway Cover Diaphragm Fluid Pressure Boundary Stainless Steel Treated Water (Int)
Cracking Water Chemistry Program IV.D1.1-i 3.1.1-44 E
Nozzle Safe Ends Fluid Pressure Boundary Carbon Steel w/ SS Cladding Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-i 3.1.1-44 A
Water Chemistry Program IV.D1.1-i 3.1.1-44 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 41 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Primary Divider Plate Fluid Pressure Boundary Stainless Steel Treated Water (Ext)
Cracking Water Chemistry Program IV.D1.1-i 3.1.1-44 C
Primary Inlet and Outlet Nozzles Fluid Pressure Boundary Carbon Steel w/SS cladding Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Treated Water (Int)
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-i 3.1.1-44 A
Water Chemistry Program IV.D1.1-i 3.1.1-44 A
Feedwater Inlet Nozzles and Thermal Sleeves Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 42 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 C
Water Chemistry Program IV.D1.1-c 3.1.1-02 C
Flow Accelerated Corrosion Program IV.D1.1-d 3.1.1-25 117, A Steam Outlet Nozzle and Flow Limiter, Blowdown Nozzle Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Treated Water (Int)
Loss of Material Water Chemistry Program IV.D1.1-c 3.1.1-02 E
Flow Accelerated Corrosion Program IV.D1.1-d 3.1.1-25 117, A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 43 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Secondary Side 2 Inspection Port Cover Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-k 3.1.1-38 C
Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 A
Water Chemistry Program IV.D1.1-c 3.1.1-02 A
Wide and Narrow Range Water level Nozzles, Sampling and Instrument Nozzles Fluid Pressure Boundary Low Alloy Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Treated Water (Int)
Loss of Material Water Chemistry Program IV.D1.1-c 3.1.1-02 C
Cracking ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 E
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 44 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Water Chemistry Program IV.D1.1-c 3.1.1-02 E
Shells (Lower, Upper, Transition)
Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 A
Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 A
Water Chemistry Program IV.D1.1-c 3.1.1-02 A
Steam Generator Tube Integrity Program IV.D1.1-c 3.1.1-02 B
Tubesheet Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 114, C Treated Water (Int) (Secondary)
Loss of Material Steam Generator Tube Integrity Program IV.D1.1-c 3.1.1-02 C
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 45 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Water Chemistry Program IV.D1.1-c 3.1.1-02 C
Nickel Based Alloy Treated Water (Int) (Primary)
Cracking Steam Generator Tube Integrity Program IV.D1.2-a 3.1.1-18 C
Water Chemistry Program IV.D1.2-a 3.1.1-18 C
Upper Head Fluid Pressure Boundary Carbon Steel Containment Air (Ext)
Loss of Material Boric Acid Corrosion Program IV.D1.1-g 3.1.1-38 C
Treated Water (Int)
Loss of Material ASME Section XI IWB, IWC, IWD, IWF Inservice Inspection Program IV.D1.1-c 3.1.1-02 A
Loss of Material Water Chemistry Program IV.D1.1-c 3.1.1-02 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 46 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes U-Tubes Fluid Pressure Boundary Heat Transfer Alloy 600/690 Treated Water (Ext)
Cracking Steam Generator Tube Integrity Program IV.D1.2-b 3.1.1-18 A
IV.D1.2-c 3.1.1-18 A
Water Chemistry Program IV.D1.2-b 3.1.1-18 A
IV.D1.2-c 3.1.1-18 A
Loss of Material Water Chemistry Program IV.D1.2-e 3.1.1-18 A
Steam Generator Tube Integrity Program IV.D1.2-e 3.1.1-18 A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 47 of 48 6/6/2005 Table 3.1.2-4 Reactor Coolant System - Replacement Steam Generators - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG -
1801 Volume 2 Line Item Table 1 Item Notes Rev 1 NUREG -
1801 Volume 2 Line Item Rev 1 Table 1 Item Rev 1 Notes Treated Water (Int)
Cracking Steam Generator Tube Integrity Program IV.D1.2-a 3.1.1-18 A
Water Chemistry Program IV.D1.2-a 3.1.1-18 A
Manway Fasteners Fluid Pressure Boundary Carbon Steel
/ Low Alloy Steel Containment Air (Ext)
Crack Initiation and Growth Bolting Integrity Program IV.D1.1-l 3.1.1-26 A
Loss of Material Boric Acid Corrosion Program IV.D1.1-k 3.1.1-38 A
Loss of Preload Bolting Integrity Program IV.D1.1-f 3.1.1-26 101, A
Application for Renewed Operating License - Palisades Nuclear Plant Precedent Tables for Section 3.1, Reactor Coolant System 48 of 48 6/6/2005