ULNRC-06032, Enclosure 2 - Amendment 26, LRA Changes
| ML13242A292 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/29/2013 |
| From: | Ameren Missouri |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13242A308 | List: |
| References | |
| ULNRC-06032 | |
| Download: ML13242A292 (9) | |
Text
ULNRC-06032 August 29, 2013 Page 1 of 9 Amendment 26, LRA Changes Enclosure 2 Summary Table Affected LRA Section LRA Page Table 2.3.3-26 2.3-76 Table 3.3.2-4 3.3-94 and 3.3-97 Table 3.3.2-5 3.3-100 Table 3.3.2-20 3.3-204 and 3.3-216 Table 3.3.2-21 3.3-217 and 3.3-221 Table 3.3.2-26 3.3-258 and 3.3-262 Table 3.3.2-27 3.3-263 and 3.3-270 Table A4-1 A-49
ULNRC-06032 August 29, 2013 Page 2 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add a pressure boundary intended function for closure bolting.
Table 2.3.3-26 (Page 2.3-76) is revised as follows (new text underlined):
Table 2.3.3-26 Oily Waste System Component Type Intended Function Closure Bolting Leakage Boundary (spatial)
Pressure Boundary Piping Direct Flow Leakage Boundary (spatial)
Pressure Boundary Pump Leakage Boundary (spatial)
Pressure Boundary Tank Leakage Boundary (spatial)
Valve Leakage Boundary (spatial)
Pressure Boundary
ULNRC-06032 August 29, 2013 Page 3 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps and correct a typographical error associated with the internal spray nozzle environment.
Table 3.3.2-4 (Pages 3.3-94 and 3.3-97) is revised as follows (new text underlined and deleted text shown in strikethrough):
Table 3.3.2-4 Auxiliary Systems - Summary of Aging Management Evaluation - Essential Service Water System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Notes Type Function Requiring Program Item Item Management Closure PB Stainless Raw Water (Ext) Loss of material Open-Cycle Cooling VII.C1.A-54 3.3.1.040 C Bolting Steel Water System (B2.1.10)
Closure PB Stainless Raw Water (Ext) Loss of preload Bolting Integrity VII.I.AP-264 3.3.1.015 A Bolting Steel (B2.1.8)
Spray Nozzle PB Copper Raw Water (Ext) (Int) Loss of Material Open-Cycle Cooling VII.C1.AP-196 3.3.1.036 C Alloy Water System (B2.1.10)
ULNRC-06032 August 29, 2013 Page 4 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps.
Table 3.3.2-5 (Page 3.3-100) is revised as follows (new text underlined):
Table 3.3.2-5 Auxiliary Systems - Summary of Aging Management Evaluation - Service Water System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Closure Bolting PB Carbon Steel Raw Water Loss of material External Surfaces VII.C1.AP-194 3.3.1.037 E, 2 (Ext) Monitoring of Mechanical Components (B2.1.21)
Closure Bolting PB Carbon Steel Raw Water Loss of preload Bolting Integrity VII.I.AP-264 3.3.1.015 A (Ext) (B2.1.8)
ULNRC-06032 August 29, 2013 Page 5 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps.
Table 3.3.2-20 (Pages 3.3-204 and 3.3-216) is revised as follows (new text underlined):
Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Closure Bolting PB Carbon Steel Raw Water Loss of material External Surfaces VII.G.A-33 3.3.1.064 E, 3 (Ext) Monitoring of Mechanical Components (B2.1.21)
Closure Bolting PB Carbon Steel Raw Water Loss of preload Bolting Integrity VII.I.AP-264 3.3.1.015 A (Ext) (B2.1.8)
Notes for Table 3.3.2-20:
Plant Specific Notes:
1 The fire water storage tanks rest on a sand cushion surrounded by a reinforced concrete ring beam.
2 PVC in a wastewater environment is unaffected by water, concentrated alkalies, nonoxidizing acids, oils, ozone, or humidity changes.
PVC in a waste water environment is not exposed to direct sunlight or ionizing radiation. Therefore PVC in a wastewater environment has no aging effect.
3 The external surface of these pumps components will be managed by the External Surfaces Monitoring of Mechanical Components program (B2.1.21).
ULNRC-06032 August 29, 2013 Page 6 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps and underground bolting associated with the fuel oil storage tank.
Table 3.3.2-21 (Pages 3.3-217 and 3.3-221) is revised as follows (new text underlined):
Table 3.3.2-21 Auxiliary Systems - Summary of Aging Management Evaluation - Emergency Diesel Engine Fuel Oil Storage and Transfer System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Notes Type Function Requiring Program Item Item Management Closure Bolting PB Carbon Steel Underground Loss of material Buried and Underground VII.I.AP-284 3.3.1.109a C (Ext) Piping and Tanks (B2.1.25)
Closure Bolting PB Carbon Steel Underground Loss of preload Bolting Integrity None None G, 1 (Ext) (B2.1.8)
Closure Bolting PB Stainless Fuel Oil (Ext) Loss of material Fuel Oil Chemistry VII.H1.AP-136 3.3.1.071 C Steel (B2.1.16) and One-Time Inspection (B2.1.18)
Closure Bolting PB Stainless Fuel Oil (Ext) Loss of preload Bolting Integrity VII.I.AP-266 3.3.1.015 A Steel (B2.1.8)
Notes for Table 3.3.2-21:
Standard Notes:
A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.
B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.
C Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.
D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.
G Environment not in NUREG-1801 for this component and material.
Plant Specific Notes:
None
- 1. Loss of preload for underground bolting is managed by the Bolting Integrity program (B2.1.8).
ULNRC-06032 August 29, 2013 Page 7 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps.
Table 3.3.2-26 (Pages 3.3-258 and 3.3-262) is revised as follows (new text underlined):
Table 3.3.2-26 Auxiliary Systems - Summary of Aging Management Evaluation - Oily Waste System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Closure Bolting LBS, PB Carbon Steel Waste Water Loss of material External Surfaces VII.E5.AP-281 3.3.1.091 E, 1 (Ext) Monitoring of Mechanical Components (B2.1.21)
Closure Bolting LBS, PB Carbon Steel Waste Water Loss of preload Bolting Integrity None None G, 4 (Ext) (B2.1.8)
Closure Bolting LBS Stainless Waste Water Loss of material External Surfaces VII.E5.AP-278 3.3.1.095 E, 1 Steel (Ext) Monitoring of Mechanical Components (B2.1.21)
Closure Bolting LBS Stainless Waste Water Loss of preload Bolting Integrity None None G, 4 Steel (Ext) (B2.1.8)
Notes for Table 3.3.2-26:
Plant Specific Notes:
1 The External Surfaces Monitoring of Mechanical Components program (B2.1.21) is credited since the component's external surface is exposed to waste water.
2 Since the internal and external environments for this component are the same, the External Surfaces Monitoring of Mechanical Components program (B2.1.21) is credited to manage the aging of the internal surfaces of this component.
3 Gray Cast Iron SSCs with surfaces exposed to Waste Water are subject to loss of material due to selective leaching.
4 Loss of preload for submerged bolting associated with submerged pumps is managed by the Bolting Integrity program (B2.1.8).
ULNRC-06032 August 29, 2013 Page 8 of 9 Callaway Plant License Renewal Application Amendment 26 Changes made to add submerged bolting associated with submerged pumps.
Table 3.3.2-27 (Pages 3.3-263 and 3.3-270) is revised as follows (new text underlined):
Table 3.3.2-27 Auxiliary Systems - Summary of Aging Management Evaluation - Floor and Equipment Drain System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Closure Bolting LBS, SIA Stainless Waste Water Loss of material External Surfaces VII.E5.AP-278 3.3.1.095 E, 2 Steel (Ext) Monitoring of Mechanical Components (B2.1.21)
Closure Bolting LBS, SIA Stainless Waste Water Loss of preload Bolting Integrity None None G, 3 Steel (Ext) (B2.1.8)
Notes for Table 3.3.2-27:
Standard Notes:
A Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP is consistent with NUREG-1801 AMP.
B Consistent with NUREG-1801 item for component, material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.
D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. AMP takes some exceptions to NUREG-1801 AMP.
E Consistent with NUREG-1801 for material, environment, and aging effect, but a different aging management program is credited or NUREG-1801 identifies a plant-specific aging management program.
G Environment not in NUREG-1801 for this component and material.
Plant Specific Notes:
1 Components associated with the reactor coolant pump oil collection system do not normally contain lubricating oil. Any oil or water that is found during operator visual inspections is documented and reviewed. If there is an accumulation of liquid, it is removed and discarded during the outage inspection. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.23) inspects the piping, valves and tank for loss of material to maintain these components' intended function.
2 The External Surfaces Monitoring of Mechanical Components program (B2.1.21) is credited since the component's external surface is exposed to waste water.
3 Loss of preload for submerged bolting associated with submerged pumps is managed by the Bolting Integrity program (B2.1.8).
ULNRC-06032 August 29, 2013 Page 9 of 9 Appendix A Final Safety Analysis Report Supplement Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 41 To allow for monitoring of the condition of the threads on the RPV stud and flange hole B2.1.3 Completed no later threads, Callaway commits to remove RPV stud #18 through non-destructive or destructive than six months prior means. If RPV stud hole repair is required following removal of RPV stud #18, the repair plan to the PEO or the will include inspecting the RPV stud hole prior to the repair to assess the as-found condition refueling outage prior and an inspection after the repair is complete to assess the results of the repair. to the period of extended operation, whichever occurs later.
42 It is noted that Callaway experienced problems with the reactor vessel head closure studs and B2.1.3 Completed no later stud holes early in plant life (1986 - 1992), and that multiple RPV stud holes required ASME than six months prior Section XI repairs to remove damaged threads. To supplement the monitoring that is to the PEO or the accomplished through regular volumetric inspections and to confirm that additional thread refueling outage prior degradation is not occurring in the RPV stud holes, Callaway commits to perform a one-time to the period of inspection of select RPV stud holes using a method consistent with the Babcock and Wilcox extended operation, laser inspection that was applied following stud hole repair in 1989 and 1992. RPV stud hole whichever occurs locations 2, 4, 5, 7, 9, and 53 have had more than one thread removed and will be inspected. If later.
inspection of these RPV stud holes confirms that there was minimal or no additional degradation since the prior video inspection, then it is a reasonable conclusion that there will be minimal additional degradation in the period of extended operation. If additional degradation is observed in any of the repaired stud holes where more than one thread has been removed, the condition will be entered in the Corrective Action Program for evaluation and corrective action, and the remaining repaired RPV stud hole locations 13, 25, 39 and 54 will be inspected. The inspection is expected to confirm that further degradation is not occurring in the repaired stud holes, and will provide a basis for the conclusion that acceptance criteria for thread engagement will continue to be met through the period of extended operation.
Callaway Plant Unit 1 Page A-49 License Renewal Application Amendment 26