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