ULNRC-06080, Amendment 31 to License Renewal Application Change Regarding Fire Protection

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Amendment 31 to License Renewal Application Change Regarding Fire Protection
ML14045A285
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/14/2014
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML14045A283 List:
References
ULNRC-06080
Download: ML14045A285 (100)
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Text

ULNRC-06080 February 14, 2014 Page 1 of 100 Amendment 31, LRA Changes Enclosure 1 Summary Table Affected LRA Section LRA As-Submitted Page Number(s)

Section 2.1.2.3.1 2.1-9 Table 2.2-1 2.2-2 and 2.2-4 Section 2.3.2.4 and Table 2.3.2-4 2.3-19 and 2.3-20 Section 2.3.3 2.3-26 and 2.3-27 Section 2.3.3.5 and Table 2.3.3-5 2.3-34 through 2.3-36 Section 2.3.3.16 2.3-57 Section 2.3.3.17 and Table 2.3.3-17 2.3-58 and 2.3-59 Table 2.3.3-20 2.3-64 and 2.3-65 Section 2.3.3.26 2.3-75 and 2.3-76 Section 2.3.3.29 and Table 2.3.3-29 2.3-87 Section 2.3.4.6 and Table 2.3.4-6 2.3-97 and 2.3-98 Table 2.4-1 2.4-6 and 2.4-7 Section 2.4.4 and Table 2.4-4 2.4-12 through 2.4-14 Section 2.4.5 2.4-14 and 2.4-15 Section 2.4.6 2.4-17 and 2.4-18 Section 2.4.7 2.4-19 Section 2.4.8 2.4-21 and 2.4-22 Section 2.4.9 and Table 2.4-9 2.4-23 and 2.4-24 Section 2.4.10 and Table 2.4-10 2.4-24 through 2.4-26 Section 3.2.2.1.4 3.2-5 Table 3.2.2-4 3.2-45 Section 3.3.1 and Section 3.3.2 3.3-1 through 3.3-4 Section 3.3.2.1.17 3.3-21 and 3.3-22 Section 3.3.2.1.29 3.3-35 Table 3.3.2-5 3.3-100 Table 3.3.2-13 3.3-164 Table 3.3.2-17 3.3-193 and 3.3-194 Table 3.3.2-18 3.3-195 Table 3.3.2-20 3.3-204, 3.3-206, 3.3-207, and 3.3-209 through 3.3-216 Table 3.3.2-29 3.3-283 Table 3.4.2-6 3.4-61 through 3.4-64 Section 3.5.2.1.4 3.5-7 and 3.5-8 Section 3.5.2.1.9 3.5-13 and 3.5-14

ULNRC-06080 February 14, 2014 Page 2 of 100 Section 3.5.2.1.11 3.5-16 and 3.5-17 Table 3.5.2-1 3.5-55, 3.5-56, and 3.5-59 Table 3.5.2-2 3.5-67, 3.5-68, and 3.5-70 Table 3.5.2-3 3.5-74, 3.5-75, 3.5-77 through 3.5-80 Table 3.5.2-4 3.5-84 through 3.5-92 Table 3.5.2-5 3.5-93, 3.5-94, and 3.5-97 Table 3.5.2-9 3.5-123 through 3.5-128 Table 3.5.2-10 3.5-129, 3.5-130, and 3.5-133 Table 3.5.2-11 3.5-138, 3.5-139, and 3.5-143 Section A1.23 A-13 Section A1.25 A-13 and A-14 Section A1.32 A-16 and A-17 Table A4-1, item 34 A-48 Table A4-1, item 35 A-48 and A-49 Table A4-1, item 39 A-49 Table A4-1, item 43 A-49 Table A4-1, item 45 A-49 Section B2.1.23 B-81 through B-83 Section B2.1.25 B-87 through B-90 Section B2.1.32 B-108 and B-109

ULNRC-06080 February 14, 2014 Page 3 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.1.2.3.1 to note that Callaway is transitioning to a fire protection program based on 10 CFR 50.48(c).

Section 2.1.2.3.1 (Page 2.1-9) is revised as follows (new text underlined):

2.1.2.3.1 Fire Protection Criterion 10 CFR 54.4(a)(3) requires that plant SSCs within the scope of license renewal include all SSCs relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the regulations for fire protection (10 CFR 50.48).

10 CFR 50.48 requires each operating nuclear power plant to have a fire protection plan that satisfies the requirement of Criterion 3 of 10 CFR 50 Appendix A.

The CLB for fire protection for Callaway consists of General Design Criterion 3 to 10 CFR 50 Appendix A, Appendix A of BTP APCSB 9.5-1, 10 CFR 50, Appendix R, FSAR Section 9.5.1 SP and Operating License Condition 2.C(5). These documents identify features required for Callaway to demonstrate compliance with 10 CFR 50.48.

10 CFR 50.48(a) requires that operating nuclear power plants have a fire protection plan that satisfies Criterion 3 of 10 CFR 50 Appendix A. 10 CFR 50.48(a) does not provide specific criteria for the content of the required fire protection plan, however, the required contents of the fire protection plan are derived from 10 CFR 50.48(b).

10 CFR 50.48(b) states that Appendix R establishes fire protection features required to satisfy Criterion 3 of Appendix A. 10 CFR 50.48(b), however, allows the use of provisions of Appendix A to BTP APCSB 9.5-1 as an alternative to the requirements of Appendix R provided those provisions have been accepted by the NRC. In addition to the provisions of Appendix A to BTP APCSB 9.5-1, 10 CFR 50.48(b) imposes the provisions of Appendix R Sections III.G, J and O on plants licensed to operate prior to January 1, 1979.

Callaway is transitioning to a risk-informed, performance-based fire protection program based on 10 CFR 50.48(c), which incorporates, by reference, NFPA 805, with exceptions.

The NRC has issued license amendment number 206, which approves the use of NFPA 805. The license amendment requires Union Electric to implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request and supplements, and as approved in the safety evaluation report.

SSCs classified as satisfying criterion 10 CFR 54.4(a)(3) related to fire protection are identified as within the scope of license renewal.

ULNRC-06080 February 14, 2014 Page 4 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 2.2-1 to add the circulating water system to the scope of license renewal due to NFPA-805 changes.

Table 2.2-1 (Pages 2.2-2 and 2.2-4) is revised as follows (new text underlined and deleted text shown in strikethrough):

Table 2.2-1 Callaway Plant Scoping Results System/Structure In-Scope Section 2 Scoping and Screening Results Auxiliary Systems Circulating Water Yes 2.3.3.29 Radwaste Building HVAC System Yes No 2.3.3.17 Circulating Water Cooling Tower Makeup and Blowdown System No N/A also includes:

Cooling Water Chemical Control System Cooling Tower Makeup and Blowdown System Intake Structure and Water Treatment System

ULNRC-06080 February 14, 2014 Page 5 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.2.4 to add a fire barrier function for dampers as a result of NFPA-805 changes.

Section 2.3.2.4 (Pages 2.3-19 and 2.3-20) is revised as follows (new text underlined):

2.3.2.4 Containment Purge System

System Description

The purpose of the containment purge system is to provide ventilation of the containment building for habitability when required and provide a vent path for equalization of containment pressure with the atmosphere. The containment minipurge system is typically used during power operation to reduce the concentration of noble gases within containment prior to and during personnel access to the containment or to equalize containment internal pressure with the external pressure. The containment shutdown purge system supplies outside air into the containment for ventilation and cooling or heating needed for prolonged containment access during a reactor outage. It may also be used when the reactor is in the cold shutdown mode to reduce the concentration of noble gases within the containment prior to and during personnel access.

The containment purge system consists of the common HVAC intake, common unit vent, nonessential filtering unit, supply fans, exhaust fans, containment isolation valves, radiation monitors, dampers, and associated ventilation ducts.

System Intended Functions The containment purge system provides containment isolation valves that are capable of rapid closure, following a design basis event, to limit the escape of fission products from the containment, and radiation monitors that provide radiation level input to the engineered safety feature actuation signal for the containment purge system. Therefore, the containment purge system is within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(1).

Portions of the containment purge system are within the scope of license renewal as nonsafety-related affecting safety-related components based on the criterion of 10 CFR 54.4(a)(2) for spatial interaction and structural integrity.

Portions of the containment purge system are within the scope of license renewal to support fire protection and environmental qualification requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the containment purge system are included in FSAR Sections 7.3.2 SP and 9.4.6 SP.

ULNRC-06080 February 14, 2014 Page 6 of 100 License Renewal Boundary Drawings The license renewal boundary drawing for the containment purge system is listed below:

LR-CW-GT-M-22GT01 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.3.2 Containment Purge System.

Table 2.3.2-4 Containment Purge System Component Type Intended Function Closure Bolting Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Damper Fire Barrier Pressure Boundary Ductwork Pressure Boundary Filter Filter, Pressure Boundary Flex Connectors Pressure Boundary Flow Orifice Structural Integrity (attached)

Heat Exchanger (Containment Purge) Leakage Boundary (spatial)

Piping Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Pump Pressure Boundary Screen Structural Integrity (attached)

Solenoid Valve Pressure Boundary Valve Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

The AMR results for these component types are provided in Table 3.2.2-4, Engineered Safety Features - Summary of Aging Management Evaluation - Containment Purge System.

ULNRC-06080 February 14, 2014 Page 7 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.3 to add Section 2.3.3.29 for the circulating water system as a result of NFPA-805 changes.

Section 2.3.3 (Pages 2.3-26 and 2.3-27) is revised as follows (new text underlined):

2.3.3 Auxiliary Systems This section addresses scoping and screening results for the following systems:

  • Fuel Storage and Handling System (Section 2.3.3.1)
  • Cranes, Hoists, and Elevators (Section 2.3.3.3)
  • Reactor Makeup Water System (Section 2.3.3.6)
  • Component Cooling Water System (Section 2.3.3.7)
  • Compressed Air System (Section 2.3.3.8)
  • Nuclear Sampling System (Section 2.3.3.9)
  • Chemical and Volume Control System (Section 2.3.3.10)
  • Control Building HVAC System (Section 2.3.3.11)
  • Auxiliary Building HVAC System (Section 2.3.3.13)
  • Fuel Building HVAC System (Section 2.3.3.14)
  • Miscellaneous Buildings HVAC System (Section 2.3.3.15)
  • Diesel Generator Building HVAC System (Section 2.3.3.16)
  • Radwaste Building HVAC System (Section 2.3.3.17)
  • Turbine Building HVAC System (Section 2.3.3.18)
  • Containment Cooling System (Section 2.3.3.19)
  • Fire Protection System (Section 2.3.3.20)
  • Emergency Diesel Engine Fuel Oil Storage and Transfer System (Section 2.3.3.21)
  • Standby Diesel Generator Engine System (Section 2.3.3.22)
  • EOF and TSC Diesels, Security Building System (Section 2.3.3.23)

ULNRC-06080 February 14, 2014 Page 8 of 100

  • Liquid Radwaste System (Section 2.3.3.24)
  • Decontamination System (Section 2.3.3.25)
  • Oily Waste System (Section 2.3.3.26)
  • Floor and Equipment Drainage System (Section 2.3.3.27)
  • Miscellaneous systems in-scope ONLY for Criterion (a)(2) (Section 2.3.3.28)

Includes:

Boron Recycle System Central Chilled Water System Chemical and Detergent Waste System Condensate and Feedwater Chemical Addition System Condensate System Demineralized Water Makeup System Domestic Water System Gaseous Radwaste Plant Heating System Sanitary Drainage System Secondary Liquid Waste System Solid Radwaste System Roof Drains System

ULNRC-06080 February 14, 2014 Page 9 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.3.5 FSAR references and added a flow orifice as a result of NFPA-805 changes.

Section 2.3.3.5 (Pages 2.3-34 through 2.3-36) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.3.3.5 Service Water System

System Description

The purpose of the service water system is to supply cooling water to the non-essential plant auxiliary equipment and components served by the essential service water system (ESWS) during normal plant operation and normal plant shutdown. The service water system also normally supplies fire water to two hose stations within the ESW pumphouse via ESWS piping. The service water system takes suction from the cooling tower basin, and the heated return water is discharged into the circulating water system. The service water system is nonsafety-related and performs no safety-related functions.

The service water system consists of three pumps, piping, valves, strainers, heat exchangers, and chillers.

System Intended Functions Portions of the service water system are within the scope of license renewal as nonsafety-related affecting safety-related components based on the criterion of 10 CFR 54.4(a)(2) for spatial interaction and structural integrity.

Portions of the service water system are within the scope of license renewal to support fire protection requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the service water system are included in FSAR Sections 9.2.1.1 SA, 9.2.1.1 SP, 9.5.1.2.2 SA and 9.5.1.2.2.SP and Appendix 9.5B SA.

License Renewal Boundary Drawings The license renewal boundary drawings for the service water system are listed below:

LR-CW-EA-M-22EA01 LR-CW-EA-M-22EA02 LR-CW-EA-X-89610 LR-CW-EA-X-89611 LR-CW-EA-X-89612 LR-CW-EA-X-89613 LR-CW-EA-X-89614 LR-CW-EA-X-89615

ULNRC-06080 February 14, 2014 Page 10 of 100 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.3.3 Service Water System.

Table 2.3.3-5 Service Water System Component Type Intended Function Closure Bolting Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Flow Orifice Pressure Boundary Piping Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Strainer Pressure Boundary Thermowell Pressure Boundary Tubing Pressure Boundary Valve Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

ULNRC-06080 February 14, 2014 Page 11 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.3.16 FSAR references as a result of NFPA-805 changes.

Section 2.3.3.16 (Page 2.3-57) is revised as follows (deleted text shown in strikethrough):

2.3.3.16 Diesel Generator Building HVAC System

System Description

The purpose of the diesel generator building HVAC system is to provide combustion air and cooling for the diesel generators, using outside air as the medium. Outside air is supplied to the building, circulated, and is returned outside through exhaust louvers. In the event of a fire, heat and smoke venting for each diesel generator room is provided utilizing the exhaust flow path. In an emergency, the exhaust air flow path is a backup source for combustion air. Each diesel generator room is provided with a separate ventilation system.

Nonsafety-related electric unit heaters are provided in each room for space heating.

The diesel generator building HVAC system consists of safety-related supply fans, dampers, and connecting ductwork. Nonsafety-related electric unit heaters are provided in each room for space heating.

The ventilation air supply and exhaust louvers for the diesel generator building HVAC system are evaluated as structural components in Section 2.4.5, Diesel Generator Building.

System Intended Functions The diesel generator building HVAC system provides combustion air and a suitable environment for operation of the diesel generators during design basis events. Therefore, the diesel generator building HVAC system is within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(1).

Portions of the diesel generator building HVAC system are within the scope of license renewal to support fire protection requirements based on the criterion of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the diesel generator building HVAC system are included in FSAR Section 9.4.7 SP and Appendix 9.5B SP.

ULNRC-06080 February 14, 2014 Page 12 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.3.17 to delete the radwaste building HVAC system from the scope of license renewal to be consistent with NFPA-805 changes.

Section 2.3.3-17 (Pages 2.3-58 and 2.3-59) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.3.3.17 Radwaste Building HVAC System The radwaste building HVAC system is not within the scope of license renewal.

System Description

The purpose of the radwaste building HVAC system is to provide a suitable environment for equipment and for personnel occupation. The radwaste building ventilation system is nonsafety-related and performs no safety-related functions.

The portion of the radwaste building HVAC system within the scope of license renewal consists of the exhaust filter adsorber, unit charcoal filter, fire suppression piping and fusible-link actuated fire dampers in various locations in the system.

System Intended Functions The radwaste building HVAC system performs no safety-related function. Failure of any radwaste building ventilation system component will not prevent the satisfactory accomplishment of any safety-related functions.

Portions of the radwaste building HVAC system are within the scope of license renewal to support fire protection requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the radwaste HVAC system are included in FSAR Sections 9.4.5 SP, 9.5.1 SP, and Appendix 9.5A SP.

License Renewal Boundary Drawings The license renewal drawings for the radwaste HVAC system are listed below:

LR-CW-GH-M-22GH01 LR-CW-GH-M-22GH02 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.3.3 Radwaste Building HVAC System.

ULNRC-06080 February 14, 2014 Page 13 of 100 Table 2.3.3-17 Radwaste Building HVAC System Component Type Intended Function Damper Fire Barrier Piping Pressure Boundary The AMR results for these component types are provided in Table 3.3.2-17, Auxiliary Systems - Summary of Aging Management Evaluation - Radwaste Building HVAC System.

ULNRC-06080 February 14, 2014 Page 14 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 2.3.3-20 to add the add a leakage boundary (spatial) function to components that no longer had a fire barrier function as a result of NFPA-805 changes.

Table 2.3.3-20 (Pages 2.3-64 and 2.3-65) is revised as follows (new text underlined):

Table 2.3.3-20 Fire Protection System Component Type Intended Function Closure Bolting Pressure Boundary Expansion Joint Pressure Boundary Filter Pressure Boundary Filter (Halon) Pressure Boundary Flame Arrestor Pressure Boundary Flexible Hoses Pressure Boundary Flow Element Pressure Boundary Flow Orifice Leakage Boundary (spatial)

Pressure Boundary Heat Exchanger (DFP Jacket Water) Pressure Boundary Hose Station Pressure Boundary Hydrant Pressure Boundary Piping Pressure Boundary Structural Integrity (attached)

Piping (Halon) Pressure Boundary Pump Pressure Boundary Silencer Pressure Boundary Solenoid Valve Leakage Boundary (spatial)

Pressure Boundary Solenoid Valve (Halon) Pressure Boundary Spray Nozzle Spray Spray Nozzle (Halon) Spray Strainer Leakage Boundary (spatial)

Pressure Boundary

ULNRC-06080 February 14, 2014 Page 15 of 100 Table 2.3.3-20 Fire Protection System (Continued)

Component Type Intended Function Tank Leakage Boundary (spatial)

Pressure Boundary Tank (Halon) Pressure Boundary Tubing Pressure Boundary Valve Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Valve (Halon) Pressure Boundary

ULNRC-06080 February 14, 2014 Page 16 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.3.26 FSAR references as a result of NFPA-805 changes.

Section 2.3.3.26 (Pages 2.3-75 and 2.3-76) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.3.3.26 Oily Waste System

System Description

The purpose of the oily waste system is to collect nonradioactive waste water from areas where oil may be present for processing and disposal and collect waste water that may contain oil and/or trace amounts of radioactive contaminants for processing and recycling.

The mechanical portions of the oily waste system are nonsafety and perform no safety-related functions.

The portions of the oily waste system within the scope of license renewal consist of sumps, sump pumps, piping, valves, and control and instrumentation equipment located in the diesel generator building, auxiliary building, control building and the tendon access gallery.

The safety-related portion of the oily waste system for leak detection in the diesel generator rooms is evaluated as part of the electrical and instrumentation and control evaluation in Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Control Systems.

System Intended Functions Portions of the oily waste system are within the scope of license renewal as nonsafety-related affecting safety-related components based on the criterion of 10 CFR 54.4(a)(2) for spatial interaction and flood control.

Portions of the oily waste system are within the scope of license renewal to support fire protection requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the oily waste system are included in FSAR Sections 3B.4.2.3 SP, 9.3.3 SP, and 9.5.1 SP, and Appendices 9.5A SP and 9.5B SP.

ULNRC-06080 February 14, 2014 Page 17 of 100 Callaway Plant License Renewal Application Amendment 31 Added Section 2.3.3.29 for the circulating water system as a new system within the scope of license renewal. The circulating water system provides a return path to the cooling tower for the service water system consistent with NFPA-805 changes.

Section 2.3.3.29 (Page 2.3-87) is added as a new system within the scope of license renewal.

2.3.3.29 Circulating Water System

System Description

The purpose of the circulating water system is to supply cooling water from the plant's cooling water source to the main condenser to condense the steam that discharges from the exhaust of the turbine or the turbine bypass system. The Callaway site utilizes a large natural draft cooling tower for its source of cooling. The circulating water system is nonsafety and performs no safety-related functions.

The circulating water system consists of pumps, piping and valves, and the large hyperbolic natural draft cooling tower.

System Intended Functions Portions of the circulating water system are within the scope of license renewal to support fire protection requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the circulating water system are included in FSAR Section 10.4.5 SA.

License Renewal Boundary Drawings The license renewal boundary drawings for the circulating water system are listed below:

LR-CW-DA-M-22DA01 LR-CW-DA-M-22DA02 LR-CW-DA-X-89615 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.3.3 Circulating Water System.

ULNRC-06080 February 14, 2014 Page 18 of 100 Table 2.3.3-29 Circulating Water System Component Type Intended Function Closure Bolting Pressure Boundary Expansion Joint Pressure Boundary Piping Pressure Boundary Valve Pressure Boundary The AMR results for these component types are provided in Table 3.3.2-29, Auxiliary Systems - Summary of Aging Management Evaluation - Circulating Water System.

ULNRC-06080 February 14, 2014 Page 19 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.3.4.6 to add the nonsafety auxiliary feedwater pump and associated piping components to incorporate NFPA-805 changes.

Section 2.3.4.6 (Pages 2.3-97 and 2.3-98) is revised as follows (deleted text shown in strikethrough and new text underlined):

2.3.4.6 Condensate Storage and Transfer System

System Description

The purpose of the condensate storage and transfer system is to supply or receive condensate to compensate for changes in plant systems inventory as required by the condenser hotwell level control system. It is also a nonseismically designed source of water to the auxiliary feedwater system and is not credited for accident mitigation. The condensate storage and transfer system is nonsafety-related and performs no safety-related functions.

The condensate storage and transfer system consists of one 450,000 gallon condensate storage tank, nonsafety auxiliary feedwater pump, and associated valves and piping.

Valves ADV0204 and ADV0389 were realigned from the condensate system to this system because they form part of the boundary for the nonsafety auxiliary feedwater pump.

System Intended Functions Portions of the condensate storage and transfer system are in scope as nonsafety-related affecting safety-related components based on the criterion of 10 CFR 54.4(a)(2) for spatial interaction.

Portions of the condensate storage and transfer system are within the scope of license renewal to support fire protection, environmental qualification, and station blackout requirements based upon the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the condensate storage and transfer system are included in FSAR Section 9.2.6 SP.

License Renewal Boundary Drawings The license renewal boundary drawings for the condensate storage and transfer system are listed below:

LR-CW-AL-M-22AL01 LR-CW-AP-M-22AP01 LR-CW-AD-M-22AD01

ULNRC-06080 February 14, 2014 Page 20 of 100 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.3.4 Condensate Storage and Transfer System.

Table 2.3.4-6 Condensate Storage and Transfer System Component Type Intended Function Closure Bolting Pressure Boundary Flow Orifice Pressure Boundary Insulation Insulate (Mechanical)

Piping Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

Pump Pressure Boundary Tank Pressure Boundary Tubing Pressure Boundary Valve Leakage Boundary (spatial)

Pressure Boundary Structural Integrity (attached)

The AMR results for these component types are provided in Table 3.4.2-6, Steam and Power Conversion Systems - Summary of Aging Management Evaluation - Condensate Storage and Transfer System.

ULNRC-06080 February 14, 2014 Page 21 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 2.4-1 to delete the fire barrier doors and the fire barrier function from the hatch emergency airlock to incorporate NFPA-805 changes. The tendon gallery fire barrier door is now evaluated with the auxiliary building fire area.

Table 2.4-1 (Pages 2.4-6 and 2.4-7) is revised as follows (deleted text shown in strikethrough):

Table 2.4-1 Reactor Building Component Type Intended Function Barrier Missile Barrier Shelter, Protection Bolting (Pressure-retaining) Structural Pressure Boundary Structural Support Bolting (Structural) Structural Support Coatings Maintain Coating Integrity Compressible Joints and Seals Expansion/Separation Shelter, Protection Structural Pressure Boundary Concrete Elements Fire Barrier Flood Barrier Missile Barrier Shelter, Protection Shielding Structural Pressure Boundary Structural Support Debris Barrier Filter Shelter, Protection Fire Barrier Coatings/Wraps Fire Barrier Fire Barrier Doors Fire Barrier Missile Barrier Shelter, Protection Gate Shelter, Protection Structural Pressure Boundary Hatch Emergency Airlock Fire Barrier Shelter, Protection Shielding Structural Pressure Boundary Structural Support Hatch Equipment Shelter, Protection Shielding Structural Pressure Boundary Structural Support

ULNRC-06080 February 14, 2014 Page 22 of 100 Table 2.4-1 Reactor Building (Continued)

Component Type Intended Function Hatch Personnel Airlock Fire Barrier Shelter, Protection Shielding Structural Pressure Boundary Structural Support Hatches and Plugs Missile Barrier Shelter, Protection High Strength Bolting Structural Support Liner Containment Shelter, Protection Structural Pressure Boundary Liner Refueling Shelter, Protection Liner Sumps Shelter, Protection Structural Pressure Boundary Penetration Shelter, Protection Shielding Structural Pressure Boundary Structural Support Penetration - Electrical Shelter, Protection Structural Pressure Boundary Structural Support Penetrations Mechanical Shelter, Protection Shielding Structural Pressure Boundary Structural Support Pipe Whip Restraints and Jet Shields HELB Shielding Missile Barrier Pipe Whip Restraint Structural Support Stairs, Platforms and Grates Structural Support Structural Steel Shelter, Protection Structural Support Tendons Structural Support

ULNRC-06080 February 14, 2014 Page 23 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.4 to delete the fire barrier structural intended functions from the turbine building consistent with NFPA-805 changes. Also added a structural pressure boundary function for a portion of the turbine building that provides a NFPA-805 return path for the circulating water system.

Section 2.4.4 (Pages 2.4-12 through 2.4-14) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.4.4 Turbine Building Structure Description The purpose of the turbine building is to support and shelter and protect the turbine generator, condensers, main feed pumps, and other power-conversion equipment. The non-Category I turbine building is a three level steel structure supported on both mat and spread footing foundations. The auxiliary boiler room, which houses the auxiliary boiler, is also evaluated with the turbine building in this section.

The turbine building is located north of the auxiliary building and east of the communications corridor, which are evaluated separately. Non-Category I structures located near seismic Category I SSCs have been designed to preclude gross collapse upon safety-related structures or components under loads imposed by the design basis tornado.

Structure Intended Functions Portions of the turbine building provide structural support and shelter and protection for nonsafety-related SSCs whose failure could prevent performance of a safety-related function. Therefore, the turbine building is within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2).

Portions of the turbine building provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection and ATWS requirements based upon criteria of 10 CFR 54.4(a)(3). The wall and associated structural components that separate the turbine building fire area from the auxiliary boiler room fire area support fire protection requirements based on NFPA 805. Therefore the turbine building is within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional design requirements applicable to the turbine building are included in FSAR Sections 2.5.4.10.2.1 SA, and 3.3.2.3 SP, and Appendix 9.5B SP.

ULNRC-06080 February 14, 2014 Page 24 of 100 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.4 Turbine Building.

Table 2.4-4 Turbine Building Component Type Intended Function Bolting (Structural) Structural Support Caulking and Sealant Flood Barrier Shelter, Protection Compressible Joints and Seals Expansion/Separation Shelter, Protection Concrete Block (Masonry Walls) Fire Barrier Flood Barrier Shelter, Protection Structural Support Concrete Elements Fire Barrier Flood Barrier Missile Barrier Shelter, Protection Structural Pressure Boundary Structural Support Door Shelter, Protection Fire Barrier Coatings/Wraps Fire Barrier Fire Barrier Doors Fire Barrier Shelter, Protection Fire Barrier Seals Fire Barrier Hatch Missile Barrier Shelter, Protection Hatches and Plugs Fire Barrier Missile Barrier Shelter, Protection Structural Support High Strength Bolting Structural Support Metal Siding Fire Barrier Shelter, Protection Penetrations Electrical Shelter, Protection Structural Support Penetrations Mechanical Shelter, Protection Structural Support Roofing Membrane Flood Barrier Shelter, Protection Stairs, Platforms and Grates Structural Support Structural Steel Shelter, Protection Structural Support

ULNRC-06080 February 14, 2014 Page 25 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.5 references section to be consistent with NFPA-805 changes.

Section 2.4.5 (Pages 2.4-14 and 2.4-15) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.4.5 Diesel Generator Building Structure Intended Function The diesel generator building provides structural support and shelter and protection for safety-related SSCs providing the capability to shutdown the reactor and maintains it in a safe shutdown condition. Therefore, the diesel generator building is within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(1).

Portions of the diesel generator building provide structural support and shelter and protection for nonsafety-related SSCs whose failure could prevent performance of a safety-related function. Therefore, the diesel generator building is within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2).

Portions of the diesel generator building provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection and station blackout requirements based upon criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the diesel generator building are included in FSAR Sections 3.7(B).1.4 SP, 3.8.4.1.4 SP, and 3.8.4.1.6 SP, and Appendix 9.5B SP.

ULNRC-06080 February 14, 2014 Page 26 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.6 references section to be consistent with NFPA-805 changes.

Section 2.4.6 (Pages 2.4-17 and 2.4-18) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.4.6 Miscellaneous In-Scope Structures Structure Intended Function Portions of the miscellaneous in-scope structures provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection and station blackout requirements based upon criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the Miscellaneous In-Scope Structures are included in FSAR Sections 8.3A.4.a SP, and 9.2.5.3 SA and 9.5.1.3 SA.

ULNRC-06080 February 14, 2014 Page 27 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.7 references section to be consistent with NFPA-805 changes.

Section 2.4.7 (Page 2.4-19) is revised as follows (deleted text shown in strikethrough):

2.4.7 In-Scope Tank Foundations and Structures Structure Intended Function The in-scope tank foundations and structures provide structural support and shelter and protection for safety-related SSCs providing the capability to shutdown the reactor and maintain it in a safe shutdown condition. Therefore, the in-scope tank foundations and structures are within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(1).

Portions of the in-scope tank foundations and structures provide structural support and shelter and protection for nonsafety-related SSCs whose failure could prevent performance of a safety-related function. Therefore, the in-scope tank foundations and structures are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2).

Portions of the in-scope tank foundations and structures provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection and station blackout requirements based upon criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the in-scope tank foundations and structures are included in FSAR Sections 1.2.2 SP, 3.8.4.1.5 SP, 3.8.5.1.5 SP, 8.3A.5.1 SP, 9.5.1 SA, and 10.4.9.1.2 SP.

ULNRC-06080 February 14, 2014 Page 28 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.8 references section to be consistent with NFPA-805 changes.

Section 2.4.8 (Pages 2.4-21 and 2.4-22) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.4.8 Electrical Foundations and Structures Structure Intended Function The electrical foundations and structures provide structural support and shelter and protection for safety-related SSCs providing the capability to shutdown the reactor and maintain it in a safe shutdown condition and SSCs required to mitigate the consequences of accidents that could result in potential offsite exposure. Therefore, the electrical foundations and structures are within the scope of license renewal based on the criteria of 10 CFR 54.4(a)(1).

Portions of the electrical foundations and structures provide structural support and shelter and protection for nonsafety-related SSCs whose failure could prevent performance of a safety-related function. Therefore, the electrical foundations and structures are within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2).

Portions of the electrical foundations and structures provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection and station blackout requirements based upon criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the electrical foundations and structures are included in FSAR Section 3.8.4.1.3 SA, and Appendices 9.5B SP and 9.5B SA.

ULNRC-06080 February 14, 2014 Page 29 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.9 to delete the fire barrier structural intended functions from the radwaste building consistent with NFPA-805 changes.

Section 2.4.9 (Pages 2.4-23 and 2.4-24) is revised as follows (new text underlined and deleted text shown in strikethrough):

2.4.9 Radwaste Building Structure Description The purpose of the radwaste building is to provide support and shelter and protection for radioactive waste treatment facilities, tanks, filters, and other miscellaneous equipment.

The radwaste pipe tunnel provides access and carries electrical cable trays and piping between the auxiliary building and the radwaste building.

The radwaste building is a rectangular, multistory, structural steel and reinforced concrete structure. The building is supported on a reinforced concrete mat foundation constructed on structural backfill. The building has a built-up roof supported by structural steel beams and girders and the roof and intermediate floor framing are supported by structural steel columns and reinforced concrete bearing walls. The radwaste pipe tunnel is a below grade, reinforced concrete, two-cell box structure connecting the auxiliary building and the radwaste building. It is separated from both buildings by isolation joints.

With the exception of the radwaste tunnel, the radwaste building is physically separated from the rest of the plant by approximately 100 ft. The radwaste tunnel is separated from the connected auxiliary building by a fire barrier wall which is included in the scope of the auxiliary building.

Structure Intended Function Portions of the radwaste building provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection requirements based on the criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the radwaste building are included in FSAR Section 3.8.6 SP and Appendices 9.5A SP and 9.5B SP.

Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.4 Radwaste Building.

ULNRC-06080 February 14, 2014 Page 30 of 100 Table 2.4 Radwaste Building Component Type Intended Function Bolting (Structural) Structural Support Caulking and Sealant Flood Barrier Shelter, Protection Compressible Joints and Seals Expansion/Separation Shelter, Protection Concrete Block (Masonry Walls) Flood Barrier Shelter, Protection Structural Support Concrete Elements Fire Barrier Flood Barrier Missile Barrier Shelter, Protection Structural Support Door Flood Barrier Shelter, Protection Fire Barrier Coatings/Wraps Fire Barrier Fire Barrier Doors Fire Barrier Shelter, Protection Fire Barrier Seals Fire Barrier High Strength Bolting Structural Support Penetrations Electrical Structural Support Penetrations Mechanical Structural Support Roofing Membrane Flood Barrier Shelter, Protection Stairs, Platforms and Grates Structural Support Structural Steel Shelter, Protection Structural Support The AMR results for these component types are provided in Table 3.5.2-9, Containments, Structures, and Component Supports - Summary of Aging Management Evaluation -

Radwaste Building.

ULNRC-06080 February 14, 2014 Page 31 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 2.4.10 to delete the fire barrier door structural intended functions from the fuel building consistent with NFPA-805 changes. Also provided an editorial correction in the structure intended function section.

Section 2.4.10 (Pages 2.4-24 through 2.4-26) is revised as follows (deleted text shown in strikethrough):

2.4.10 Fuel Building Structure Description The purpose of the fuel building is to provide support and shelter and protection for the spent fuel pool, transfer canal, cask loading pool and cask washdown pit, spent fuel pool bridge crane, cask handling crane, and other miscellaneous equipment. The spent fuel pool receives spent fuel from the containment through the fuel transfer tube. The spent fuel pool, including the transfer canal, cask loading pool, and cask washdown pit consist of reinforced concrete walls and floors lined with stainless steel plates. A leak chase system is provided to check the leaktightness of the liners. The concrete dividing walls and the spent fuel pool gates permit de-watering of the spent fuel pool without dewatering the entire pool.

The fuel building is a multistory, structural steel and reinforced concrete seismic Category I structure, supported by a two-way reinforced concrete basemat founded on structural backfill. The exterior walls have integral reinforced concrete pilasters. The elevated floors and roof are reinforced concrete slabs supported by steel beams and girders. The floor and roof framing are supported by reinforced concrete bearing walls.

Structure Intended Function The fuel building provides structural support and shelter and protection for safety-related SSCs required to mitigate the consequences of accidents that could result in potential offsite exposure. Therefore, the fuel building is within the scope of license renewal based on the criteria of 10 CFR 54(a)(1).

Portions of the fuel building provide structural support and shelter and protection for nonsafety-related SSCs whose failure could prevent performance of a safety-related function. Therefore, the auxiliary building fuel building is within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2).

Portions of the fuel building provide structural support and shelter and protection for SSCs that are within the scope of license renewal to support fire protection requirements based upon criteria of 10 CFR 54.4(a)(3).

Callaway FSAR References Additional details of the fuel building are included in FSAR Section 3.8.4.1.2 SP.

ULNRC-06080 February 14, 2014 Page 32 of 100 Component-Function Relationship Table The component types subject to aging management review are indicated in Table 2.4 Fuel Building.

Table 2.4 Fuel Building Component Type Intended Function Bolting (Structural) Structural Support Caulking and Sealant Flood Barrier Shelter, Protection Compressible Joints and Seals Expansion/Separation Shelter, Protection Concrete Elements Fire Barrier Flood Barrier Missile Barrier Shelter, Protection Structural Support Door Shelter, Protection Fire Barrier Coatings/Wraps Fire Barrier Fire Barrier Doors Fire Barrier Shelter, Protection Fire Barrier Seals Fire Barrier Hatch Shelter, Protection High Strength Bolting Structural Support Liner Spent Fuel Pool Shelter, Protection Structural Pressure Boundary Penetrations Electrical Structural Support Penetrations Mechanical Structural Support Roofing Membrane Flood Barrier Shelter, Protection Stairs, Platforms and Grates Structural Support Structural Metals Shelter, Protection Structural Steel Missile Barrier Shelter, Protection Structural Support

ULNRC-06080 February 14, 2014 Page 33 of 100 Callaway Plant License Renewal Application Amendment 31 Revised the environments portion of Section 3.2.2.1.4 to reflect addition of a new environment for dampers with a fire barrier function as a result of NFPA-805 changes.

Section 3.2.2.1.4 (Page 3.2-5) is revised as follows (new text underlined):

3.2.2.1.4 Containment Purge System Environment The containment purge system component types are exposed to the following environments:

  • Borated Water Leakage
  • Closed Cycle Cooling Water
  • Concrete
  • Condensation
  • Plant Indoor Air
  • Ventilation Atmosphere
  • Waste Water

ULNRC-06080 February 14, 2014 Page 34 of 100 Callaway Plant License Renewal Application Amendment 31 Added aging evaluation lines for a damper with a fire barrier function for NFPA-805 changes.

Table 3.2.2-4 (Page 3.2-45) is revised as follows (new text underlined):

Table 3.2.2-4 Engineered Safety Features - Summary of Aging Management Evaluation - Containment Purge System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Damper FB, PB Carbon Steel Concrete (Ext) None None VII.J.AP-282 3.3.1.112 C (Galvanized)

Damper FB, PB Carbon Steel Ventilation Loss of material Inspection of Internal VII.F3.A-08 3.3.1.090 B (Galvanized) Atmosphere (Int) Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

ULNRC-06080 February 14, 2014 Page 35 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 3.3.1 to reference Section 2.3.3.29 for the circulating water system as a result of NFPA-805 changes. Also revised Section 3.3.2 to add Table 3.3.2-29 for the circulating water system as a result of NFPA-805 changes.

Section 3.3.1 and Section 3.3.2 (Pages 3.3-1 through 3.3-4) are revised as follows (new text underlined):

3.3.1 Introduction Section 3.3 provides the results of the aging management reviews (AMRs) for those component types identified in Section 2.3.3, Auxiliary Systems, subject to AMR. These systems are described in the following sections:

  • Fuel Storage and Handling System (Section 2.3.3.1)
  • Cranes, Hoists, and Elevators (Section 2.3.3.3)
  • Reactor Makeup Water System (Section 2.3.3.6)
  • Component Cooling Water System (Section 2.3.3.7)
  • Compressed Air System (Section 2.3.3.8)
  • Nuclear Sampling System (Section 2.3.3.9)
  • Chemical and Volume Control System (Section 2.3.3.10)
  • Control Building HVAC System (Section 2.3.3.11)
  • Auxiliary Building HVAC System (Section 2.3.3.13)
  • Fuel Building HVAC System (Section 2.3.3.14)
  • Miscellaneous Buildings HVAC System (Section 2.3.3.15)
  • Diesel Generator Building HVAC System (Section 2.3.3.16)
  • Radwaste Building HVAC System (Section 2.3.3.17)
  • Turbine Building HVAC System (Section 2.3.3.18)
  • Containment Cooling System (Section 2.3.3.19)
  • Fire Protection System (Section 2.3.3.20)
  • Emergency Diesel Engine Fuel Oil Storage and Transfer System (Section 2.3.3.21)

ULNRC-06080 February 14, 2014 Page 36 of 100

  • Standby Diesel Generator Engine System (Section 2.3.3.22)
  • EOF and TSC Diesels, Security Building System (Section 2.3.3.23)
  • Liquid Radwaste System (Section 2.3.3.24)
  • Decontamination System (Section 2.3.3.25)
  • Oily Waste System (Section 2.3.3.26)
  • Floor and Equipment Drainage System (Section 2.3.3.27)

(Section 2.3.3.28) includes:

Boron Recycle Central Chilled Water Chemical and Detergent Waste Condensate Condensate and Feedwater Chemical Addition Demineralized Water Makeup Domestic Water Gaseous Radwaste Plant Heating Roof Drains Sanitary Drainage Secondary Liquid Waste Solid Radwaste

Table 3.3-1, Summary of Aging Management Programs in Chapter VII of NUREG-1801 for Auxiliary Systems, provides the summary of the programs evaluated in NUREG-1801 that are applicable to the component types in this section. Table 3.3-1 uses the format of Table 1 described in Section 3.0, Aging Management Review.

3.3.2 Results The following tables summarize the results of the AMR for the systems in the Auxiliary Systems area:

  • Table 3.3.2-1, Auxiliary Systems - Summary of Aging Management Evaluation - Fuel Storage and Handling System
  • Table 3.3.2-2, Auxiliary Systems - Summary of Aging Management Evaluation -Fuel Pool Cooling and Cleanup System
  • Table 3.3.2-3, Auxiliary Systems - Summary of Aging Management Evaluation - Cranes, Hoists, and Elevators

ULNRC-06080 February 14, 2014 Page 37 of 100

  • Table 3.3.2-6, Auxiliary Systems - Summary of Aging Management Evaluation - Reactor Makeup Water System
  • Table 3.3.2-7, Auxiliary Systems - Summary of Aging Management Evaluation - Component Cooling Water System
  • Table 3.3.2-8, Auxiliary Systems - Summary of Aging Management Evaluation - Compressed Air System
  • Table 3.3.2-9, Auxiliary Systems - Summary of Aging Management Evaluation - Nuclear Sampling System
  • Table 3.3.2-10, Auxiliary Systems - Summary of Aging Management Evaluation - Chemical and Volume Control System
  • Table 3.3.2-11, Auxiliary Systems - Summary of Aging Management Evaluation - Control Building HVAC System
  • Table 3.3.2-13, Auxiliary Systems - Summary of Aging Management Evaluation - Auxiliary Building HVAC System
  • Table 3.3.2-14, Auxiliary Systems - Summary of Aging Management Evaluation - Fuel Building HVAC System
  • Table 3.3.2-15, Auxiliary Systems - Summary of Aging Management Evaluation - Miscellaneous Buildings HVAC System
  • Table 3.3.2-16, Auxiliary Systems - Summary of Aging Management Evaluation - Diesel Generator Building HVAC System
  • Table 3.3.2-17, Auxiliary Systems - Summary of Aging Management Evaluation - Radwaste Building HVAC System
  • Table 3.3.2-18, Auxiliary Systems - Summary of Aging Management Evaluation - Turbine Building HVAC System
  • Table 3.3.2-19, Auxiliary Systems - Summary of Aging Management Evaluation - Containment Cooling System
  • Table 3.3.2-20, Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System
  • Table 3.3.2-21, Auxiliary Systems - Summary of Aging Management Evaluation - Emergency Diesel Engine Fuel Oil Storage and Transfer System
  • Table 3.3.2-22, Auxiliary Systems - Summary of Aging Management Evaluation - Standby Diesel Generator Engine System
  • Table 3.3.2-23, Auxiliary Systems - Summary of Aging Management Evaluation - EOF and TSC Diesels, Security Building System
  • Table 3.3.2-24, Auxiliary Systems - Summary of Aging Management Evaluation - Liquid Radwaste System

ULNRC-06080 February 14, 2014 Page 38 of 100

  • Table 3.3.2-25, Auxiliary Systems - Summary of Aging Management Evaluation - Decontamination System
  • Table 3.3.2-26, Auxiliary Systems - Summary of Aging Management Evaluation - Oily Waste System
  • Table 3.3.2-27, Auxiliary Systems - Summary of Aging Management Evaluation - Floor and Equipment Drainage System

ULNRC-06080 February 14, 2014 Page 39 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Section 3.3.2.1.17 to delete the radwaste building HVAC system from the scope of license renewal to be consistent with NFPA-805 changes.

Section 3.3.2.1.17 (Pages 3.3-21 and 3.3-22) is revised as follows (new text underlined and deleted text shown in strikethrough):

3.3.2.1.17 Radwaste Building HVAC System The radwaste building HVAC system is not within the scope of license renewal.

Materials The materials of construction for the radwaste building HVAC system component types are:

  • Stainless Steel Environment The radwaste building HVAC system component types are exposed to the following environments:
  • Plant Indoor Air
  • Ventilation Atmosphere Aging Effects Requiring Management The following radwaste building HVAC system aging effect requires management:
  • External Surfaces Monitoring of Mechanical Components (B2.1.21)
  • Fire Protection (B2.1.13)
  • Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

ULNRC-06080 February 14, 2014 Page 40 of 100 Callaway Plant License Renewal Application Amendment 31 Added Section 3.3.2.1.29 for the circulating water system as a new system within the scope of license renewal. The circulating water system provides a return path to the cooling tower for the service water system consistent with NFPA-805 changes.

Section 3.3.2.1.29 (Page 3.3-35) is added as a new system within the scope of license renewal.

3.3.2.1.29 Circulating Water System Materials The materials of construction for the circulating water system component types are:

  • Carbon Steel (with coating or lining)
  • Concrete
  • Atmosphere/Weather
  • Buried
  • Plant Indoor Air
  • Changes in Material Properties
  • Cracking
  • Cracking and Changes in Material Properties
  • Cracking, Spalling, Corrosion of Rebar
  • Hardening and Loss of Strength
  • Loss of material
  • Loss of preload

ULNRC-06080 February 14, 2014 Page 41 of 100 Aging Management Programs The following aging management programs manage the aging effects for the circulating water system component types:

  • Bolting Integrity (B2.1.8)
  • Selective Leaching (B2.1.19)
  • External Surfaces Monitoring of Mechanical Components (B2.1.21)
  • Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)
  • Buried and Underground Piping and Tanks (B2.1.25)

ULNRC-06080 February 14, 2014 Page 42 of 100 Callaway Plant License Renewal Application Amendment 31 Changes made to add a flow orifice and internally coated carbon steel piping in the service water return path to the cooling tower for NFPA-805 changes.

Table 3.3.2-5 (Pages 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 Flow Orifice PB Stainless Plant Indoor Air None None VII.J.AP-17 3.3.1.120 A Steel (Ext)

Flow Orifice PB Stainless Raw Water (Int) Loss of material Inspection of Internal VII.C1.A-409a 3.3.1.134 B Steel Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB, SIA Carbon Steel Buried (Ext) Loss of material Buried and Underground VII.C1.AP-198 3.3.1.106 A (with coating Piping and Tanks or lining) (B2.1.25)

Piping PB, SIA Carbon Steel Raw Water (Int) Loss of material Inspection of Internal VII.C1.AP-194 3.3.1.037 E, 1 (with coating Surfaces in or lining) Miscellaneous Piping and Ducting Components (B2.1.23)

ULNRC-06080 February 14, 2014 Page 43 of 100 Callaway Plant License Renewal Application Amendment 31 Changes made to delete galvanized steel dampers in a plant indoor air environment due to removal of fire barrier functions for NFPA-805 changes.

Table 3.3.2-13 (Pages 3.3-164) is revised as follows (deleted text shown in strikethrough):

Table 3.3.2-13 Auxiliary Systems - Summary of Aging Management Evaluation - Auxiliary Building HVAC System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Damper FB, PB Carbon Steel Plant Indoor Air None None VII.J.AP-13 3.3.1.116 C (Galvanized) (Ext)

ULNRC-06080 February 14, 2014 Page 44 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.3.2-17 to delete the radwaste building HVAC system from the scope of license renewal to be consistent with NFPA-805 changes.

Table 3.3.2-17 (Pages 3.3-193 and 3.3-194) is revised as follows (new text underlined and deleted text shown in strikethrough):

Table 3.3.2-17 Auxiliary Systems - Summary of Aging Management Evaluation - Radwaste Building HVAC System The radwaste building HVAC system is not within the scope of license renewal.

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Damper FB Carbon Steel Plant Indoor Air None None VII.J.AP-13 3.3.1.116 C (Galvanized) (Ext)

Damper FB Carbon Steel Ventilation Loss of material Fire Protection VII.F2.A-08 3.3.1.090 E, 2 (Galvanized) Atmosphere (B2.1.13)

(Int)

Piping PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Ext) Monitoring of Mechanical Components (B2.1.21)

Piping PB Carbon Steel Ventilation Loss of material Inspection of Internal VII.I.A-81 3.3.1.078 E, 1 Atmosphere Surfaces in (Ext) Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Carbon Steel Ventilation Loss of material Inspection of Internal VII.F2.A-08 3.3.1.090 B Atmosphere Surfaces in (Int) Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A (Ext)

ULNRC-06080 February 14, 2014 Page 45 of 100 Table 3.3.2-17 Auxiliary Systems - Summary of Aging Management Evaluation - Radwaste Building HVAC System (Continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Piping PB Copper Alloy Ventilation Loss of material Inspection of Internal VII.G.AP-143 3.3.1.089 B Atmosphere Surfaces in (Int) Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Stainless Plant Indoor Air None None VII.J.AP-17 3.3.1.120 A Steel (Ext)

Piping PB Stainless Ventilation Loss of material Inspection of Internal VII.F2.AP-99 3.3.1.094 D Steel Atmosphere Surfaces in (Int) Miscellaneous Piping and Ducting Components (B2.1.23)

  • Notes for Table 3.3.2-17:
  • 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.

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.

Plant Specific Notes:

1 The subject component is enclosed within another component. Loss of material on the external surface of the subject component is managed by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.23).

2. Fire Protection (B2.1.13) manages the aging effects associated with this fire damper material and environment combination.

ULNRC-06080 February 14, 2014 Page 46 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.3.2-18 to reflect deletion of the fire barrier function from dampers as a result of NFPA-805 changes.

Table 3.3.2-18 (Page 3.3-195) is revised as follows (deleted text shown in strikethrough):

Table 3.3.2-18 Auxiliary Systems - Summary of Aging Management Evaluation - Turbine Building HVAC System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Damper FB, PB Carbon Steel Ventilation Loss of material Fire Protection (B2.1.13) VII.F2.A-08 3.3.1.090 E, 3 (Galvanized) Atmosphere (Int)

Damper FB, PB Carbon Steel Plant Indoor Air None None VII.J.AP-13 3.3.1.116 C (Galvanized) (Ext)

Damper FB, PB Carbon Steel Ventilation Loss of material Inspection of Internal VII.F2.A-08 3.3.1.090 B (Galvanized) Atmosphere Surfaces in (Int) Miscellaneous Piping and Ducting Components (B2.1.23)

ULNRC-06080 February 14, 2014 Page 47 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.3.2-20 to incorporate the following as a result of NFPA-805 changes:

  • deleted the fire water storage tank sump pump and the fire protection pumphouse valve pit pumps,
  • added a leakage boundary (spatial) function to components that no longer had a fire barrier function as a result of NFPA-805 changes,
  • Added copper alloy (>15% zinc) hose stations
  • Added loss of material and flow blockage aging effect to hydrants, gray cast iron piping, solenoid valves, strainers, tanks (retard chambers), gray cast iron valves, and copper alloy (>15% zinc) valves Table 3.3.2-20 (Pages 3.3-204, 3.3-206, 3.3-207, and 3.3-209 through 3.3-216) is revised as follows (new text underlined and deleted text shown in strikethrough):

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 (Ext) Loss of preload Bolting Integrity (B2.1.8) VII.I.AP-264 3.3.1.015 A Closure Bolting PB Carbon Steel Raw Water (Ext) Loss of material Bolting Integrity (B2.1.8) VIII.G.SP-136 3.4.1.038 E, 5 Flow Orifice LBS, PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Ext) Monitoring of Mechanical Components (B2.1.21)

Flow Orifice LBS, PB Carbon Steel Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 B and flow blockage (B2.1.14)

Hose Station PB Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A

(> 15% Zinc) (Ext)

ULNRC-06080 February 14, 2014 Page 48 of 100 Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Hose Station PB Copper Alloy Raw Water (Int) Loss of material Selective Leaching VII.G.A-47 3.3.1.072 D

(> 15% Zinc) (B2.1.19)

Hose Station PB Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G.AP-197 3.3.1.064 D

(> 15% Zinc) and flow blockage (B2.1.14)

Hydrant PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 B (Gray Cast and flow blockage (B2.1.14)

Iron)

Piping PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 B (Gray Cast and flow blockage (B2.1.14)

Iron)

Pump PB Cast Iron Raw Water (Ext) Loss of material External Surfaces VII.G.A-33 3.3.1.064 E, 3 (Gray Cast and flow blockage Monitoring of Iron) Mechanical Components (B2.1.21)

Pump PB Cast Iron Raw Water (Ext) Loss of material Selective Leaching VII.G.A-51 3.3.1.072 B (Gray Cast (B2.1.19)

Iron)

Solenoid Valve LBS, PB Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A

(> 15% Zinc) (Ext)

Solenoid Valve LBS, PB Copper Alloy Raw Water (Int) Loss of material Selective Leaching VII.G.A-47 3.3.1.072 B

(> 15% Zinc) (B2.1.19)

Solenoid Valve LBS, PB Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G.AP-197 3.3.1.064 B

(> 15% Zinc) and flow blockage (B2.1.14)

Strainer LBS, PB Cast Iron Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Gray Cast (Ext) Monitoring of Iron) Mechanical Components (B2.1.21)

Strainer LBS, PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 B (Gray Cast and flow blockage (B2.1.14)

Iron)

ULNRC-06080 February 14, 2014 Page 49 of 100 Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Strainer LBS, PB Cast Iron Raw Water (Int) Loss of material Selective Leaching VII.G.A-51 3.3.1.072 B (Gray Cast (B2.1.19)

Iron)

Strainer LBS, PB Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A

(> 15% Zinc) (Ext)

Strainer LBS, PB Copper Alloy Raw Water (Int) Loss of material Selective Leaching VII.G.A-47 3.3.1.072 B

(> 15% Zinc) (B2.1.19)

Strainer LBS, PB Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G.AP-197 3.3.1.064 B

(> 15% Zinc) and flow blockage (B2.1.14)

Tank PB Carbon Steel Raw Water (Int) Loss of material Fire Water System VII.H2.AP-194 3.3.1.037 E, 4 (with coating (B2.1.14) E, 3 or lining)

Tank LBS, PB Cast Iron Borated Water Loss of material Boric Acid Corrosion VII.I.A-79 3.3.1.009 A (Gray Cast Leakage (Ext) (B2.1.4)

Iron)

Tank LBS, PB Cast Iron Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Gray Cast (Ext) Monitoring of Iron) Mechanical Components (B2.1.21)

Tank LBS, PB Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 D (Gray Cast and flow blockage (B2.1.14)

Iron)

Tank LBS, PB Cast Iron Raw Water (Int) Loss of material Selective Leaching VII.G.A-51 3.3.1.072 D (Gray Cast (B2.1.19)

Iron)

Valve LBS, PB, Cast Iron Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A SIA (Gray Cast (Ext) Monitoring of Iron) Mechanical Components (B2.1.21)

Valve LBS, PB, Cast Iron Raw Water (Int) Loss of material Fire Water System VII.G.A-33 3.3.1.064 B SIA (Gray Cast and flow blockage (B2.1.14)

Iron)

ULNRC-06080 February 14, 2014 Page 50 of 100 Table 3.3.2-20 Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Valve LBS, PB, Cast Iron Raw Water (Int) Loss of material Selective Leaching VII.G.A-51 3.3.1.072 B SIA (Gray Cast (B2.1.19)

Iron)

Valve LBS, PB, Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A SIA (Ext)

Valve LBS, PB, Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G.AP-197 3.3.1.064 B SIA and flow blockage (B2.1.14)

Valve LBS, PB Copper Alloy Plant Indoor Air None None VII.J.AP-144 3.3.1.114 A

(> 15% Zinc) (Ext)

Valve LBS, PB Copper Alloy Raw Water (Int) Loss of material Selective Leaching VII.G.A-47 3.3.1.072 B

(> 15% Zinc) (B2.1.19)

Valve LBS, PB Copper Alloy Raw Water (Int) Loss of material Fire Water System VII.G.AP-197 3.3.1.064 B

(> 15% Zinc) and flow blockage (B2.1.14)

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 components will be managed by the External Surfaces Monitoring of Mechanical Components program (B2.1.21).

34 The Fire Water System (B2.1.14) program is used to manage components in the fire water system.

5. The Bolting Integrity program (B2.1.8) is used instead of the Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.23) to manage loss of material in submerged closure bolting.

ULNRC-06080 February 14, 2014 Page 51 of 100 Callaway Plant License Renewal Application Amendment 31 Added Table 3.3.2-29 for the circulating water system as a new system within the scope of license renewal. The circulating water system provides a return path to the cooling tower for the service water system consistent with NFPA-805 changes.

Table 3.3.2-29 (Page 3.3-283) is added as a new system within the scope of license renewal.

Table 3.3.2-29 Auxiliary Systems - Summary of Aging Management Evaluation - Circulating 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 Plant Indoor Air Loss of preload Bolting Integrity (B2.1.8) VII.I.AP-124 3.3.1.015 A (Ext)

Closure Bolting PB Carbon Steel Plant Indoor Air Loss of material Bolting Integrity (B2.1.8) VII.I.AP-125 3.3.1.012 A (Ext)

Expansion PB Elastomer Plant Indoor Air Hardening and External Surfaces VII.F4.AP-102 3.3.1.076 A Joint (Ext) loss of strength Monitoring of Mechanical Components (B2.1.21)

Expansion PB Elastomer Plant Indoor Air Loss of material External Surfaces VII.F4.AP-113 3.3.1.082 A Joint (Ext) Monitoring of Mechanical Components (B2.1.21)

Expansion PB Elastomer Raw Water (Int) Hardening and Inspection of Internal VII.C1.AP-75 3.3.1.032a E, 1 Joint loss of strength Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

ULNRC-06080 February 14, 2014 Page 52 of 100 Table 3.3.2-29 Auxiliary Systems - Summary of Aging Management Evaluation - Circulating Water System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Expansion PB Elastomer Raw Water (Int) Loss of material Inspection of Internal VII.C1.AP-76 3.3.1.032a E, 1 Joint Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Ext) Monitoring of Mechanical Components (B2.1.21)

Piping PB Carbon Steel Raw Water (Int) Loss of material Inspection of Internal VII.C1.A-408a 3.3.1.134 B Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Carbon Steel Buried (Ext) Loss of material Buried and Underground VII.C1.AP-198 3.3.1.106 A (with coating Piping and Tanks or lining) (B2.1.25)

Piping PB Carbon Steel Raw Water (Int) Loss of material Inspection of Internal VII.C1.AP-194 3.3.1.037 E, 1 (with coating Surfaces in or lining) Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Concrete Atmosphere/ Cracking External Surfaces VII.C1.AP-251 3.3.1.074 A Weather (Ext) Monitoring of Mechanical Components (B2.1.21)

Piping PB Concrete Atmosphere/ Loss of material External Surfaces VII.C1.AP-252 3.3.1.077 A Weather (Ext) Monitoring of Mechanical Components (B2.1.21)

ULNRC-06080 February 14, 2014 Page 53 of 100 Table 3.3.2-29 Auxiliary Systems - Summary of Aging Management Evaluation - Circulating Water System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Piping PB Concrete Atmosphere/ Changes in External Surfaces VII.C1.AP-253 3.3.1.073 A Weather (Ext) material Monitoring of properties Mechanical Components (B2.1.21)

Piping PB Concrete Buried (Ext) Cracking and Buried and Underground VII.C1.AP-157 3.3.1.103 A Changes in Piping and Tanks material (B2.1.25) properties Piping PB Concrete Buried (Ext) Cracking, spalling, Buried and Underground VII.C1.AP-178 3.3.1.105 A corrosion of rebar Piping and Tanks (B2.1.25)

Piping PB Concrete Raw Water (Int) Cracking Inspection of Internal VII.C1.AP-248 3.3.1.031 E, 1 Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Concrete Raw Water (Int) Loss of material Inspection of Internal VII.C1.AP-249 3.3.1.033 E, 1 Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Piping PB Concrete Raw Water (Int) Changes in Inspection of Internal VII.C1.AP-250 3.3.1.030 E, 1 material Surfaces in properties Miscellaneous Piping and Ducting Components (B2.1.23)

Valve PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Ext) Monitoring of Mechanical Components (B2.1.21)

ULNRC-06080 February 14, 2014 Page 54 of 100 Table 3.3.2-29 Auxiliary Systems - Summary of Aging Management Evaluation - Circulating Water System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Valve PB Carbon Steel Raw Water (Int) Loss of material Inspection of Internal VII.C1.A-408a 3.3.1.134 B Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23)

Valve PB Cast Iron Atmosphere/ Loss of material External Surfaces VII.I.A-78 3.3.1.078 A (Gray Cast Weather (Ext) Monitoring of Iron) Mechanical Components (B2.1.21)

Valve PB Cast Iron Plant Indoor Air Loss of material External Surfaces VII.I.A-77 3.3.1.078 A (Gray Cast (Ext) Monitoring of Iron) Mechanical Components (B2.1.21)

Valve PB Cast Iron Raw Water (Int) Loss of material Selective Leaching VII.C1.A-51 3.3.1.072 B (Gray Cast (B2.1.19)

Iron)

Valve PB Cast Iron Raw Water (Int) Loss of material Inspection of Internal VII.C1.A-408a 3.3.1.134 B (Gray Cast Surfaces in Iron) Miscellaneous Piping and Ducting Components (B2.1.23)

Notes for Table 3.3.2-29:

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.

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.

Plant Specific Notes:

1 NUREG-1801,Section XI.M20, Open-Cycle Cooling Water System, is for water which cools safety-related components and rejects heat to the ultimate heat sink. Since the circulating water system rejects heat to the cooling tower and is nonsafety-related, the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program (B2.1.23) is credited.

ULNRC-06080 February 14, 2014 Page 55 of 100 Callaway Plant License Renewal Application Amendment 31 Revised aging evaluations to add the nonsafety auxiliary feedwater pump and associated piping components to incorporate NFPA-805 changes.

Table 3.4.2-6 (Pages 3.4-61 through 3.4-64) is revised as follows (new text underlined and deleted text shown in strikethrough):

Table 3.4.2-6 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and Transfer System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Flow Orifice PB Stainless Plant Indoor Air None None VIII.I.SP-12 3.4.1.058 A Steel (Ext)

Flow Orifice PB Stainless Secondary Water Loss of material Water Chemistry VIII.E.SP-87 3.4.1.016 A Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

Piping LBS, SIA Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H.S-29 3.4.1.034 A (Ext) Monitoring of Mechanical Components (B2.1.21)

Piping LBS, SIA Carbon Steel Secondary Water Loss of material Water Chemistry VIII.G.SP-74 3.4.1.013 A (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

Piping PB, LBS, Carbon Steel Borated Water Loss of material Boric Acid Corrosion VIII.H.S-30 3.4.1.004 A SIA Leakage (Ext) (B2.1.4)

Piping PB, LBS, Carbon Steel Secondary Water Loss of material Water Chemistry VIII.G.SP-74 3.4.1.013 A SIA (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

ULNRC-06080 February 14, 2014 Page 56 of 100 Table 3.4.2-6 Steam and Power Conversion System - Summary of Aging Management Evaluation - Condensate Storage and Transfer System (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Pump PB Carbon Steel Plant Indoor Air Loss of material External Surfaces VIII.H.S-29 3.4.1.034 A (Ext) Monitoring of Mechanical Components (B2.1.21)

Pump PB Carbon Steel Secondary Water Loss of material Water Chemistry VIII.G.SP-74 3.4.1.013 A (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

Tubing PB Stainless Plant Indoor Air None None VIII.I.SP-12 3.4.1.058 A Steel (Ext)

Tubing PB Stainless Secondary Water Loss of material Water Chemistry VIII.G.SP-87 3.4.1.016 A Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

Valve PB Stainless Plant Indoor Air None None VIII.I.SP-12 3.4.1.058 A Steel (Ext)

Valve PB Stainless Secondary Water Loss of material Water Chemistry VIII.G.SP-87 3.4.1.016 A Steel (Int) (B2.1.2) and One-Time Inspection (B2.1.18)

ULNRC-06080 February 14, 2014 Page 57 of 100 Callaway Plant License Renewal Application Amendment 31 The following changes were made to delete fire barrier materials and aging effects associated with NFPA-805 changes. Also added a portion of the turbine building that provides a NFPA-805 return path for the circulating water system.

Section 3.5.2.1.4 (Page 3.5-7 and 3.5-8) is revised as follows (deleted text shown in strikethrough):

3.5.2.1.4 Turbine Building Materials The materials of construction for the turbine building component types are:

  • Concrete
  • Concrete Block (Masonry Walls)
  • Elastomer
  • High Strength Low Alloy Steel (Bolting)

Environment The turbine building component types are exposed to the following environments:

  • Atmosphere/ Weather (Structural)
  • Buried (Structural)
  • Concrete (Structural)
  • Plant Indoor Air (Structural)
  • Submerged (Structural)

Aging Effects Requiring Management The following turbine building aging effects require management:

  • Concrete cracking and spalling
  • Cracking
  • Cracking and distortion
  • Cracking, loss of material

ULNRC-06080 February 14, 2014 Page 58 of 100

  • Cracking; loss of bond; and loss of material (spalling, scaling)
  • Increase in porosity and permeability; cracking; loss of material (spalling, scaling)
  • Increase in porosity and permeability; loss of strength
  • Increased hardness; shrinkage; loss of strength
  • Loss of material
  • Loss of material (spalling, scaling) and cracking
  • Loss of preload
  • Fire Protection (B2.1.13)
  • Masonry Walls (B2.1.30)
  • RG 1.127, Inspection of Water-Control Structures Assocaited with Nuclear Power Plants (B2.1.31)
  • Structures Monitoring (B2.1.31)

ULNRC-06080 February 14, 2014 Page 59 of 100 Callaway Plant License Renewal Application Amendment 31 The following change was made to delete fire barrier materials, aging effects, and aging management programs associated with NFPA-805 changes.

Section 3.5.2.1.9 (Page 3.5-13 and 3.5-14) is revised as follows (deleted text shown in strikethrough):

3.5.2.1.9 Radwaste Building Materials The materials of construction for the radwaste building component types are:

  • Concrete
  • Concrete Block (Masonry Walls)
  • Elastomer
  • High Strength Low Alloy Steel (Bolting)

Environment The radwaste building component types are exposed to the following environments:

  • Atmosphere/ Weather (Structural)
  • Buried (Structural)
  • Concrete (Structural)
  • Plant Indoor Air (Structural)

Aging Effects Requiring Management The following radwaste building aging effects require management:

  • Concrete cracking and spalling
  • Cracking
  • Cracking and distortion
  • Cracking, loss of material
  • Cracking; loss of bond; and loss of material (spalling, scaling)
  • Increase in porosity and permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 60 of 100

  • Increase in porosity and permeability; loss of strength
  • Increased hardness; shrinkage; loss of strength
  • Loss of material
  • Loss of material (spalling, scaling) and cracking
  • Loss of preload
  • Fire Protection (B2.1.13)
  • Masonry Walls (B2.1.30)
  • Structures Monitoring (B2.1.31)

ULNRC-06080 February 14, 2014 Page 61 of 100 Callaway Plant License Renewal Application Amendment 31 The following change was made to delete aging effects associated with NFPA-805 changes.

Section 3.5.2.1.11 (Page 3.5-16 and 3.5-17) is revised as follows (deleted text shown in strikethrough):

3.5.2.1.11 Essential Service Water Structures Aging Effects Requiring Management The following essential service water structures aging effects require management:

  • Concrete cracking and spalling
  • Cracking
  • Cracking and distortion
  • Cracking, blistering, change in color
  • Cracking, loss of material
  • Cracking; loss of bond; and loss of material (spalling, scaling)
  • Increase in porosity and permeability; cracking; loss of material (spalling, scaling)
  • Increase in porosity and permeability; loss of strength
  • Increased hardness; shrinkage; loss of strength
  • Loss of material
  • Loss of material (spalling, scaling) and cracking
  • Loss of material; loss of form
  • Loss of preload
  • Loss of sealing

ULNRC-06080 February 14, 2014 Page 62 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-1 to delete the fire barrier doors and the fire barrier structural intended function from selected reactor building components consistent with NFPA-805 changes.

Table 3.5.2-1 (Pages 3.5-55, 3.5-56, and 3.5-59) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Reactor Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material ASME Section XI, II.A1.CP-31 3.5.1.018 A Elements SH, SLD, Weather (spalling, scaling) Subsection IWL SS (Structural) and cracking (B2.1.27)

(Ext)

Concrete FB, MB, Concrete Atmosphere/ Increase in ASME Section XI, II.A1.CP-32 3.5.1.020 A Elements SH, SLD, Weather porosity and Subsection IWL SS (Structural) permeability; loss (B2.1.27)

(Ext) of strength Concrete FB, MB, Concrete Atmosphere/ Cracking ASME Section XI, II.A1.CP-33 3.5.1.019 A Elements SH, SLD, Weather Subsection IWL SS (Structural) (B2.1.27)

(Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of ASME Section XI, II.A1.CP-68 3.5.1.021 A Elements SH, SLD, Weather bond; and loss of Subsection IWL SS (Structural) material (spalling, (B2.1.27)

(Ext) scaling)

Concrete FB, MB, Concrete Atmosphere/ Increase in ASME Section XI, II.A1.CP-87 3.5.1.017 A Elements SH, SLD, Weather porosity and Subsection IWL SS (Structural) permeability; (B2.1.27)

(Ext) cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 63 of 100 Table 3.5.2-1 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Reactor Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring II.A1.CP-97 3.5.1.025 A Elements SH, SLD, Weather bond; and loss of (B2.1.31)

SS (Structural) material (spalling, (Ext) scaling)

Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SLD, Weather material (B2.1.13) and SS (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SLD, Weather (B2.1.13) and SS (Structural) Structures Monitoring (Ext) (B2.1.31)

Fire Barrier FB, MB, Carbon Steel Plant Indoor Loss of material Structures Monitoring III.A1.TP-302 3.5.1.077 A Doors SH Air (Structural) (B2.1.31)

(Ext)

Fire Barrier FB, MB, Carbon Steel Plant Indoor Loss of material Fire Protection VII.G.A-21 3.3.1.059 A Doors SH Air (Structural) (B2.1.13)

(Ext)

Hatch FB, SH, Carbon Steel Plant Indoor Loss of material ASME Section XI, II.A3.C-16 3.5.1.028 A Emergency SLD, Air (Structural) Subsection IWE Airlock SPB, SS (Ext) (B2.1.26) and 10 CFR Part 50, Appendix J (B2.1.29)

Hatch FB, SH, Carbon Steel Plant Indoor Loss of material Fire Protection VII.G.A-21 3.3.1.059 A Emergency SLD, Air (Structural) (B2.1.13)

Airlock SPB, SS (Ext)

Hatch FB, SH, Carbon Steel Plant Indoor Loss of leak ASME Section XI, II.A3.CP-39 3.5.1.029 A Emergency SLD, Air (Structural) tightness Subsection IWE Airlock SPB, SS (Ext) (B2.1.26) and 10 CFR Part 50, Appendix J (B2.1.29)

ULNRC-06080 February 14, 2014 Page 64 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-2 to delete fire barrier seals and the fire barrier structural intended function from selected control building components consistent with NFPA-805 changes.

Table 3.5.2-2 (Pages 3.5-67, 3.5-68, and 3.5-70) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A1.TP-23 3.5.1.064 A Elements SH, SS Weather (spalling, scaling) (B2.1.31)

(Structural) and cracking (Ext)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A1.TP-24 3.5.1.063 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; loss (Ext) of strength Concrete FB, MB, Concrete Atmosphere/ Cracking Structures Monitoring III.A1.TP-25 3.5.1.054 A Elements SH, SS Weather (B2.1.31)

(Structural)

(Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A1.TP-26 3.5.1.066 A Elements SH, SS Weather bond; and loss of (B2.1.31)

(Structural) material (spalling, (Ext) scaling)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A1.TP-28 3.5.1.067 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; (Ext) cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 65 of 100 Table 3.5.2-2 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Control Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural)

(Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) shrinkage; loss of (Ext) strength

ULNRC-06080 February 14, 2014 Page 66 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-3 to delete the fire barrier structural intended functions from the auxiliary building components consistent with NFPA-805 changes.

Table 3.5.2-3 (Pages 3.5-74, 3.5-75, 3.5-77 through 3.5-80) is revised as follows (new text underlined and deleted text shown in strikethrough):

Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, FLB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3.TP-23 3.5.1.064 A Elements MB, SH, Weather (spalling, scaling) (B2.1.31)

SS (Structural) (Ext) and cracking Concrete FB, FLB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements MB, SH, Weather porosity and (B2.1.31)

SS (Structural) (Ext) permeability; loss of strength Concrete FB, FLB, Concrete Atmosphere/ Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements MB, SH, Weather (B2.1.31)

SS (Structural) (Ext)

Concrete FB, FLB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements MB, SH, Weather bond; and loss of (B2.1.31)

SS (Structural) (Ext) material (spalling, scaling)

Concrete FB, FLB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements MB, SH, Weather porosity and (B2.1.31)

SS (Structural) (Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 67 of 100 Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, FLB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements MB, SH, Weather material (B2.1.13) and SS (Structural) (Ext) Structures Monitoring (B2.1.31)

Concrete FB, FLB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements MB, SH, Weather (B2.1.13) and SS (Structural) (Ext) Structures Monitoring (B2.1.31)

Fire Barrier FB, FLB, Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 A Doors HLBS, Weather (B2.1.13)

MB, SH, (Structural) (Ext)

SPB Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural) (Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) (Ext) shrinkage; loss of strength Hatch FB, Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3.TP-302 3.5.1.077 A HLBS, Weather (B2.1.31)

MB, SH (Structural) (Ext)

Hatch FB, Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 C HLBS, Weather (B2.1.13)

MB, SH (Structural) (Ext)

Hatches and FB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3.TP-23 3.5.1.064 A Plugs HLBS, Weather (spalling, scaling) (B2.1.31)

MB, SH (Structural) (Ext) and cracking

ULNRC-06080 February 14, 2014 Page 68 of 100 Table 3.5.2-3 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Auxiliary Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Hatches and FB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Plugs HLBS, Weather porosity and (B2.1.31)

MB, SH (Structural) (Ext) permeability; loss of strength Hatches and FB, Concrete Atmosphere/ Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Plugs HLBS, Weather (B2.1.31)

MB, SH (Structural) (Ext)

Hatches and FB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Plugs HLBS, Weather bond; and loss of (B2.1.31)

MB, SH (Structural) (Ext) material (spalling, scaling)

Hatches and FB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Plugs HLBS, Weather porosity and (B2.1.31)

MB, SH (Structural) (Ext) permeability; cracking; loss of material (spalling, scaling)

Hatches and FB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Plugs HLBS, Weather material (B2.1.13) and MB, SH (Structural) (Ext) Structures Monitoring (B2.1.31)

Hatches and FB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Plugs HLBS, Weather (B2.1.13) and MB, SH (Structural) (Ext) Structures Monitoring (B2.1.31)

ULNRC-06080 February 14, 2014 Page 69 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-4 to delete the fire barrier structural intended functions from the turbine building components consistent with NFPA-805 changes. Also added a portion of the turbine building that provides a NFPA-805 return path for the circulating water system.

Table 3.5.2-4 (Pages 3.5-84 through 3.5-92) is revised as follows (new text underlined and deleted text shown in strikethrough):

Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete Block FB, SH, Concrete Block Atmosphere/ Cracking Fire Protection III.A3.T-12 3.5.1.070 E, 1 (Masonry SS (Masonry Weather (B2.1.13) and A Walls) Walls) (Structural) Masonry Walls (Ext) (B2.1.30)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3.TP-23 3.5.1.064 A Elements SH, SS Weather (spalling, scaling) (B2.1.31)

(Structural) and cracking (Ext)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; loss (Ext) of strength Concrete FB, MB, Concrete Atmosphere/ Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements SH, SS Weather (B2.1.31)

(Structural)

(Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements SH, SS Weather bond; and loss of (B2.1.31)

(Structural) material (spalling, (Ext) scaling)

ULNRC-06080 February 14, 2014 Page 70 of 100 Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; (Ext) cracking; loss of material (spalling, scaling)

Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; loss of strength Concrete FB, FLB, Concrete Plant Indoor Air Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements SH, SS (Structural) (B2.1.31)

(Ext)

Concrete FB, FLB, Concrete Plant Indoor Air Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements SH, SS (Structural) bond; and loss of (B2.1.31)

(Ext) material (spalling, scaling)

Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 71 of 100 Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, FLB, Concrete Plant Indoor Air Cracking and Structures Monitoring III.A3.TP-30 3.5.1.044 A Elements SH, SS (Structural) distortion (B2.1.31)

(Ext)

Concrete FB, FLB, Concrete Plant Indoor Air Concrete cracking Fire Protection VII.G.A-90 3.3.1.060 A Elements SH, SS (Structural) and spalling (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Concrete FB, FLB, Concrete Plant Indoor Air Loss of material Fire Protection VII.G.A-91 3.3.1.062 A Elements SH, SS (Structural) (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Concrete SPB, SS Concrete Submerged Loss of material RG 1.127, Inspection III.A6.T-20 3.5.1.056 A Elements (Structural) of Water-Control (Ext) Structures Associated with Nuclear Power Plants (B2.1.32)

Concrete SPB, SS Concrete Submerged Increase in RG 1.127, Inspection III.A6.TP-37 3.5.1.061 A Elements (Structural) porosity and of Water-Control (Ext) permeability; loss Structures of strength Associated with Nuclear Power Plants (B2.1.32)

Fire Barrier FB Fire Barrier Plant Indoor Air Cracking, loss of Fire Protection None None J, 2 Coatings/ (Cementitious (Structural) material (B2.1.13)

Wraps Coating) (Ext)

Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3.TP-302 3.5.1.077 A Doors Weather (B2.1.31)

(Structural)

(Ext)

ULNRC-06080 February 14, 2014 Page 72 of 100 Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 A Doors Weather (B2.1.13)

(Structural)

(Ext)

Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural)

(Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) shrinkage; loss of (Ext) strength Hatches and FB, MB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Plugs SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; loss of strength Hatches and FB, MB, Concrete Plant Indoor Air Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Plugs SH, SS (Structural) (B2.1.31)

(Ext)

Hatches and FB, MB, Concrete Plant Indoor Air Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Plugs SH, SS (Structural) bond; and loss of (B2.1.31)

(Ext) material (spalling, scaling)

Hatches and FB, MB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Plugs SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 73 of 100 Table 3.5.2-4 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Turbine Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Hatches and FB, MB, Concrete Plant Indoor Air Cracking and Structures Monitoring III.A3.TP-30 3.5.1.044 A Plugs SH, SS (Structural) distortion (B2.1.31)

(Ext)

Hatches and FB, MB, Concrete Plant Indoor Air Concrete cracking Fire Protection VII.G.A-90 3.3.1.060 A Plugs SH, SS (Structural) and spalling (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Hatches and FB, MB, Concrete Plant Indoor Air Loss of material Fire Protection VII.G.A-91 3.3.1.062 A Plugs SH, SS (Structural) (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Metal Siding FB, SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A3.TP-302 3.5.1.077 A Weather (B2.1.31)

(Structural)

(Ext)

Metal Siding FB, SH Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 C Weather (B2.1.13)

(Structural)

(Ext)

Metal Siding FB, SH Carbon Steel Plant Indoor Air Loss of material Structures Monitoring III.A3.TP-302 3.5.1.077 A (Structural) (B2.1.31)

(Ext)

Metal Siding FB, SH Carbon Steel Plant Indoor Air Loss of material Fire Protection VII.G.A-21 3.3.1.059 C (Structural) (B2.1.13)

(Ext)

Notes for Table 3.5.2-4:

Standard Notes:

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

ULNRC-06080 February 14, 2014 Page 74 of 100 Notes for Table 3.5.2-4: (continued)

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.

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

Plant Specific Notes:

1 NUREG-1801 does not provide a line in which concrete masonry is inspected per the Fire Protection program (B2.1.13).

2 NUREG-1801 does not provide a line in which fire barriers (ceramic fiber or cementitious coating) are inspected per the Fire Protection program (B2.1.13).

ULNRC-06080 February 14, 2014 Page 75 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-5 to delete the fire barrier structural intended functions from the diesel generator building components consistent with NFPA-805 changes.

Table 3.5.2-5 (Pages 3.5-93, 3.5-94, and 3.5-97) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3.TP-23 3.5.1.064 A Elements SH, SS Weather (spalling, scaling) (B2.1.31)

(Structural) (Ext) and cracking Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) (Ext) permeability; loss of strength Concrete FB, MB, Concrete Atmosphere/ Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements SH, SS Weather (B2.1.31)

(Structural) (Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements SH, SS Weather bond; and loss of (B2.1.31)

(Structural) (Ext) material (spalling, scaling)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) (Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 76 of 100 Table 3.5.2-5 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Diesel Generator Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural) (Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) (Ext) shrinkage; loss of strength

ULNRC-06080 February 14, 2014 Page 77 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-9 to delete the fire barrier structural intended functions from the radwaste building components consistent with NFPA-805 changes.

Table 3.5.2-9 (Pages 3.5-123 through 3.5-128) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A3.TP-23 3.5.1.064 A Elements SH, SS Weather (spalling, scaling) (B2.1.31)

(Structural) and cracking (Ext)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; loss (Ext) of strength Concrete FB, MB, Concrete Atmosphere/ Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements SH, SS Weather (B2.1.31)

(Structural)

(Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements SH, SS Weather bond; and loss of (B2.1.31)

(Structural) material (spalling, (Ext) scaling)

ULNRC-06080 February 14, 2014 Page 78 of 100 Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) permeability; (Ext) cracking; loss of material (spalling, scaling)

Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) Structures Monitoring (Ext) (B2.1.31)

Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-24 3.5.1.063 A Elements SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; loss of strength Concrete FB, FLB, Concrete Plant Indoor Air Cracking Structures Monitoring III.A3.TP-25 3.5.1.054 A Elements SH, SS (Structural) (B2.1.31)

(Ext)

Concrete FB, FLB, Concrete Plant Indoor Air Cracking; loss of Structures Monitoring III.A3.TP-26 3.5.1.066 A Elements SH, SS (Structural) bond; and loss of (B2.1.31)

(Ext) material (spalling, scaling)

Concrete FB, FLB, Concrete Plant Indoor Air Increase in Structures Monitoring III.A3.TP-28 3.5.1.067 A Elements SH, SS (Structural) porosity and (B2.1.31)

(Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 79 of 100 Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, FLB, Concrete Plant Indoor Air Cracking and Structures Monitoring III.A3.TP-30 3.5.1.044 A Elements SH, SS (Structural) distortion (B2.1.31)

(Ext)

Concrete FB, FLB, Concrete Plant Indoor Air Concrete cracking Fire Protection VII.G.A-90 3.3.1.060 A Elements SH, SS (Structural) and spalling (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Concrete FB, FLB, Concrete Plant Indoor Air Loss of material Fire Protection VII.G.A-91 3.3.1.062 A Elements SH, SS (Structural) (B2.1.13) and (Ext) Structures Monitoring (B2.1.31)

Fire Barrier FB Fire Barrier Plant Indoor Air Cracking, loss of Fire Protection None None J, 1 Coatings/ (Cementitious (Structural) material (B2.1.13)

Wraps Coating) (Ext)

Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Structures Monitoring III.A3.TP-302 3.5.1.077 A Doors (Structural) (B2.1.31)

(Ext)

Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Fire Protection VII.G.A-21 3.3.1.059 A Doors (Structural) (B2.1.13)

(Ext)

Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural)

(Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) shrinkage; loss of (Ext) strength Fire Barrier FB Elastomer Plant Indoor Air Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals (Structural) (B2.1.31)

(Ext)

ULNRC-06080 February 14, 2014 Page 80 of 100 Table 3.5.2-9 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Radwaste Building (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Fire Barrier FB Elastomer Plant Indoor Air Increased Fire Protection VII.G.A-19 3.3.1.057 A Seals (Structural) hardness; (B2.1.13)

(Ext) shrinkage; loss of strength Notes for Table 3.5.2-9:

Standard Notes:

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

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

Plant Specific Notes:

1 NUREG-1801 does not provide a line in which fire barriers (ceramic fiber or cementitious coating) are inspected per the Fire Protection program (B2.1.13).

None

ULNRC-06080 February 14, 2014 Page 81 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-10 to delete fire barrier doors and the fire barrier structural intended functions from the fuel building components consistent with NFPA-805 changes.

Table 3.5.2-10 (Pages 3.5-129, 3.5-130, and 3.5-133) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material Structures Monitoring III.A5.TP-23 3.5.1.064 A Elements SH, SS Weather (spalling, scaling) (B2.1.31)

(Structural) (Ext) and cracking Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A5.TP-24 3.5.1.063 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) (Ext) permeability; loss of strength Concrete FB, MB, Concrete Atmosphere/ Cracking Structures Monitoring III.A5.TP-25 3.5.1.054 A Elements SH, SS Weather (B2.1.31)

(Structural) (Ext)

Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of Structures Monitoring III.A5.TP-26 3.5.1.066 A Elements SH, SS Weather bond; and loss of (B2.1.31)

(Structural) (Ext) material (spalling, scaling)

Concrete FB, MB, Concrete Atmosphere/ Increase in Structures Monitoring III.A5.TP-28 3.5.1.067 A Elements SH, SS Weather porosity and (B2.1.31)

(Structural) (Ext) permeability; cracking; loss of material (spalling, scaling)

ULNRC-06080 February 14, 2014 Page 82 of 100 Table 3.5.2-10 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Fuel Building (Continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material Structures Monitoring III.A5.TP-302 3.5.1.077 A Doors Weather (B2.1.31)

(Structural) (Ext)

Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 A Doors Weather (B2.1.13)

(Structural) (Ext)

Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Structures Monitoring III.A5.TP-302 3.5.1.077 A Doors (Structural) (Ext) (B2.1.31)

Fire Barrier FB, SH Carbon Steel Plant Indoor Air Loss of material Fire Protection VII.G.A-21 3.3.1.059 A Doors (Structural) (Ext) (B2.1.13)

ULNRC-06080 February 14, 2014 Page 83 of 100 Callaway Plant License Renewal Application Amendment 31 Revised Table 3.5.2-11 to delete the fire barrier structural intended functions from the essential service water structures components consistent with NFPA-805 changes.

Table 3.5.2-11 (Pages 3.5-138, 3.5-139, and 3.5-143) is revised as follows (deleted text shown in strikethrough):

Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Essential Service Water Structures Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Loss of material RG 1.127, Inspection III.A6.T-20 3.5.1.056 A Elements SH, SS Weather of Water-Control (Structural) (Ext) Structures Associated with Nuclear Power Plants (B2.1.32)

Concrete FB, MB, Concrete Atmosphere/ Loss of material RG 1.127, Inspection III.A6.TP-36 3.5.1.060 A Elements SH, SS Weather (spalling, scaling) of Water-Control (Structural) (Ext) and cracking Structures Associated with Nuclear Power Plants (B2.1.32)

Concrete FB, MB, Concrete Atmosphere/ Increase in RG 1.127, Inspection III.A6.TP-37 3.5.1.061 A Elements SH, SS Weather porosity and of Water-Control (Structural) (Ext) permeability; loss Structures of strength Associated with Nuclear Power Plants (B2.1.32)

ULNRC-06080 February 14, 2014 Page 84 of 100 Table 3.5.2-11 Containments, Structures, and Component Supports - Summary of Aging Management Evaluation - Essential Service Water Structures (continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Program Item Management Concrete FB, MB, Concrete Atmosphere/ Cracking; loss of RG 1.127, Inspection III.A6.TP-38 3.5.1.059 A Elements SH, SS Weather bond; and loss of of Water-Control (Structural) (Ext) material (spalling, Structures scaling) Associated with Nuclear Power Plants (B2.1.32)

Concrete FB, MB, Concrete Atmosphere/ Cracking, loss of Fire Protection VII.G.A-92 3.3.1.061 A Elements SH, SS Weather material (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Concrete FB, MB, Concrete Atmosphere/ Loss of material Fire Protection VII.G.A-93 3.3.1.062 A Elements SH, SS Weather (B2.1.13) and (Structural) (Ext) Structures Monitoring (B2.1.31)

Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material RG 1.127, Inspection III.A6.TP-221 3.5.1.083 C Doors Weather of Water-Control (Structural) (Ext) Structures Associated with Nuclear Power Plants (B2.1.32)

Fire Barrier FB, SH Carbon Steel Atmosphere/ Loss of material Fire Protection VII.G.A-22 3.3.1.059 A Doors Weather (B2.1.13)

(Structural) (Ext)

Fire Barrier FB Elastomer Atmosphere/ Loss of sealing Structures Monitoring III.A6.TP-7 3.5.1.072 A Seals Weather (B2.1.31)

(Structural) (Ext)

Fire Barrier FB Elastomer Atmosphere/ Increased Fire Protection VII.G.A-20 3.3.1.057 A Seals Weather hardness; (B2.1.13)

(Structural) (Ext) shrinkage; loss of strength

ULNRC-06080 February 14, 2014 Page 85 of 100 Appendix A Final Safety Analysis Report Supplement A1.23 INSPECTION OF INTERNAL SURFACES IN MISCELLANEOUS PIPING AND DUCTING COMPONENTS The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program manages changes in material properties, cracking, loss of material, hardening and loss of strength. The program inspects internal surfaces of metallic piping, concrete piping, piping components, ducting, polymeric components, and other components that are exposed to plant indoor air, ventilation atmosphere, atmosphere/weather, condensation, borated water leakage, diesel exhaust, lubricating oil, and water system environment not managed by Open-Cycle Cooling Water System (A1.10), Closed Treated Water System (A1.11), Fire Water System (A1.14), and Water Chemistry (A1.2) programs.

Internal inspections are normally performed at opportunities where the internal surfaces are made accessible, such as periodic system and component surveillance activities or maintenance activities. Visual inspections of internal surfaces of plant components are performed by qualified personnel. For certain materials, such as polymers, visual inspections will be augmented by physical manipulation or pressurization to detect hardening, loss of strength, and cracking. The program includes inspections to detect material degradation that could result in a loss of component intended function.

If work opportunities are not sufficient to allow inspection of a representative sample of components, supplemental inspections are also performed. A representative sample size is 20 percent of the accessible and inaccessible component population (defined as components having the same material and environment combination) up to a maximum of 25 components. The locations and intervals for supplemental inspections are based on assessments of the likelihood of significant aging effects, derived from current industry and plant-specific operating experience.

Components having the same material-environment combination with repetitive failures due to aging require a plant-specific program, unless the component material has been replaced by a material of more corrosion resistance for the environment of interest.

In addition, the internal coatings of the service water pump strainers are periodically visually inspected to ensure that loss of coating integrity is detected prior to (1) loss of component intended function, including loss of function due to accelerated degradation caused by localized coating failures, and (2) degradation of downstream component performance due to flow blockage.

The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program is a new program and will be implemented prior to the period of extended operation.

Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

Callaway Plant Unit 1 Page A-13 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 86 of 100 Appendix A Final Safety Analysis Report Supplement A1.25 BURIED AND UNDERGROUND PIPING AND TANKS The Buried and Underground Piping and Tanks program manages loss of material, cracking, blistering, and change of color of the external surfaces of buried and underground piping and tanks. The program augments other programs that manage the aging of internal surfaces of buried and underground piping and tanks. The materials managed by this program include steel, stainless steel, concrete, and high-density polyethylene. The program manages aging through preventive, mitigative, and inspection activities.

Preventive and mitigative actions include selection of component materials, external coatings for corrosion control, backfill quality control and the application of cathodic protection. The cathodic protection system is operated consistent with the guidance of NACE SP 0169-2007 for piping, and NACE RP 0285-2002 for tanks. Trending of the cathodic protection system is performed to identify changes in the effectiveness of the system and to ensure that the rectifiers are available to protect buried components. An annual cathodic protection survey is performed consistent with NACE SP 0169-2007.

Soil samples will be conducted during the 10-year period prior to the period of extended operation and in each subsequent 10-year period during the period of extended operation.

Soil samples will be performed in the vicinity of buried steel piping in which the cathodic protection system does not meet the following availability or effectiveness requirements:

  • Cathodic protection has been operational (available) at least 85 percent of the time since either 10 years prior to the period of extended operation or since installation/refurbishment, whichever is shorter; or
  • Cathodic protection has provided effective protection for buried piping as evidenced by meeting the acceptance criteria of -850 mV relative to a copper/copper sulfate electrode, instant off, at least 80 percent of the time since either 10 years prior to the period of extended operation or since installation/refurbishment, whichever is shorter.

Inspection activities include non-destructive evaluation of pipe or tank wall thickness, and visual inspection of the exterior, as permitted by opportunistic or directed excavations.

The Buried and Underground Piping and Tanks program is a new program that will be implemented within the 10-year period prior to entering the period of extended operation.

Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

Callaway Plant Unit 1 Page A-13 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 87 of 100 Appendix A Final Safety Analysis Report Supplement A1.32 RG 1.127, INSPECTION OF WATER-CONTROL STRUCTURES ASSOCIATED WITH NUCLEAR POWER PLANTS The RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program, which is implemented as part of the Structures Monitoring program (SMP),

manages the following aging effects:

  • Cracking; loss of bond; and loss of material (spalling, scaling)
  • Increase in porosity and permeability; loss of strength
  • Loss of material
  • Loss of material (spalling, scaling) and cracking
  • Loss of material; loss of form The scope of this program also includes structural steel and structural bolting associated with water-control structures. SNUPPS-Callaway positions are compliant with that of the Regulatory Guide 1.127 with respect to the ultimate heat sink (UHS) retention pond. The Structures Monitoring program (A1.31) includes all water-control structures within the scope of Regulatory Guide 1.127. The UHS retention pond, the essential service water pumphouse, the ESW supply lines yard vault, the UHS cooling tower, and the associated submerged discharge structures, and the concrete structures in the turbine building that provide a flowpath for the circulating water system are the water-control structures within the scope for license renewal that are monitored by this program. The UHS retention pond and its associated structures receive periodic in-service inspections for assessment of their structural safety and operational adequacy every five years. Callaway performs algae treatment and riprap inspections along the UHS retention pond to ensure smooth operation of the essential service water pumps. Callaway maintains benchmarks for monitoring settlement in any of the Category 1 structures including the UHS cooling tower. The inspections of all structural components, including masonry walls and water-control structures, are performed at intervals no more than 5 years.

Callaway Plant Unit 1 Page A-16 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 88 of 100 Appendix A Final Safety Analysis Report Supplement Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 34 Callaway replacement steam generator divider plate assemblies are fabricated of Alloy 690. Section Option 1 completed The divider plate to primary head and tubesheet junctions are welded with Alloy 152 weld 3.1.2.2.11. between Fall 2025 materials. The tubesheet cladding is Alloy 182 and the primary head cladding is stainless 1, and Fall 2029 when steel. There is a concern regarding potential failure at the divider plate welds to primary head Table the replacement and tubesheet cladding and Callaway commits to perform one of the following three resolution 3.1.2-4 steam generators are options: in service for more than 20 years.

Option 1: Inspection Option 2 or Option 3 Perform a one-time inspection of each steam generator to assess the condition of the divider available for NRC plate welds. The examination technique(s) will be capable of detecting PWSCC in the divider review in the Fall plate assemblies and the associated welds. 2023.

OR Option 2: Analysis Perform an analytical evaluation of the steam generator divider plate welds in order to establish a technical basis which concludes that the steam generator reactor coolant system pressure boundary is adequately maintained with the presence of steam generator divider plate weld cracking. The analytical evaluation will be submitted to the NRC for review and approval.

OR Option 3: Industry/NRC Studies If results of industry and NRC studies and operating experience document that potential failure of the steam generator reactor coolant system pressure boundary due to PWSCC cracking of steam generator divider plate welds is not a credible concern, this commitment will be revised to reflect that conclusion.

Callaway Plant Unit 1 Page A-48 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 89 of 100 Appendix A Final Safety Analysis Report Supplement Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 35 The material of steam generator tubesheet cladding is Alloy 182. The tubes are made of Alloy Section Option 1 completed 690 and are secured to the tubesheet by means of tube to tubesheet leaktight weld and tube 3.1.2.2.11. between Fall 2025 expansion. There is a concern regarding potential failure of primary-to-secondary pressure 2, and Fall 2029 when boundary due to PWSCC cracking of tube-to-tubesheet welds. Callaway commits to perform Table the replacement one of the following two resolution options: 3.1.2-4 steam generators are in service for more Option 1: Inspection than 20 years.

Perform a one-time inspection of a representative number of tube-to-tubesheet welds in each Option 2 available for steam generator to determine if PWSCC cracking is present. The examination technique(s) NRC review in the will be capable of detecting PWSCC in the tube-to-tubesheet welds. If weld cracking is Fall 2023.

identified, the condition will be resolved through repair or engineering evaluation to justify continued service, as appropriate, and a periodic monitoring program will be established to perform routine tube-to-tubesheet weld inspections for the remaining life of the steam generators.

OR Option 2: Analysis Perform an analytical evaluation of the steam generator tube-to-tubesheet welds either determining that the welds are not susceptible to PWSCC, or redefining the reactor coolant pressure boundary of the tubes, where the steam generator tube-to-tubesheet welds are not required to perform a reactor coolant pressure boundary function. The redefinition of the reactor coolant pressure boundary will be submitted as part of a license amendment request requiring approval from the NRC. The evaluation for determination that the welds are not susceptible to PWSCC and do not require inspection will be submitted to the NRC for review.

Callaway Plant Unit 1 Page A-48 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 90 of 100 Appendix A Final Safety Analysis Report Supplement Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 39 NFPA 805 and LRA GAP analysis: B2.1.13 Within thirty days A gap analysis of LRA Tables 2.3.3-20 and 3.3.2-20 will be provided to identify B2.1.14 after the final NFPA differences between the existing and NFPA 805 post-transition changes. The results 805 Safety and the impacts of these gaps on the fire protection program described in LRA Tables Evaluation Report is 2.3.3-20 and 3.3.2-20 will be summarized, as the basis for transitioning to the NFPA issued. (Revised 805 nuclear safety capabilities. The summary will also list the fire protection systems Amendment 23) and components including structural fire barriers, (e.g., fire walls and slabs, fire doors, Completed fire barrier penetration seals, fire dampers, fire barrier coatings/wraps, equipment/personnel hatchways and plugs, metal siding), that will be added or removed based on the NFPA 805 transition in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21(a)(1).

(Completed Amendment 31) 43 The core design procedure will be modified to include a review for the following core design B2.1.6 Completed before parameters to ensure that these limits are met in future core designs: December 19, 2014

  • Active fuel - upper core plate distance > 12.2 inches (prior to 30 years of
  • Average core power density < 124 watts/cm3 service on the reactor
  • Heat generation figure of merit, F 68 watts/cm3 vessel internals)

(Completed Amendment 31) Completed Callaway Plant Unit 1 Page A-49 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 91 of 100 Appendix A Final Safety Analysis Report Supplement Table A4-1 License Renewal Commitments Item # Commitment LRA Implementation Section Schedule 45 Enhance the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Completed no later Plants program procedures to: than six months prior

  • include the concrete structures in the turbine building that provide a flowpath for the to the PEO.

circulating water system in the scope of the program. Inspections to be completed no later than six months prior to PEO or the end of the last refueling outage prior to the PEO, whichever occurs later.

Callaway Plant Unit 1 Page A-49 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 92 of 100 Appendix B AGING MANAGEMENT PROGRAMS B2.1.23 Inspection of Internal Surfaces of Miscellaneous Piping and Ducting Components Program Description The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program manages changes in material properties, cracking, loss of material, hardening and loss of strength. The program inspects internal surfaces of metallic piping, concrete piping, piping components, ducting, polymeric components, and other components that are exposed to plant indoor air, ventilation atmosphere, atmosphere/weather, condensation, borated water leakage, diesel exhaust, lubricating oil, and any water system environment not managed by Open-Cycle Cooling Water System (B2.1.10),

Closed Treated Water System (B2.1.11), Fire Water System (B2.1.14), and Water Chemistry (B2.1.2) programs.

Internal inspections are performed opportunistically whenever the internal surfaces are made accessible, such as periodic system and component surveillance activities or maintenance activities. Visual inspections of internal surfaces of plant components are performed by qualified personnel. For certain materials, such as polymers, visual inspections will be augmented by physical manipulation of at least 10 percent of the accessible surface area or pressurization to detect hardening, loss of strength, and cracking. Volumetric evaluations are performed when appropriate for the component environment and material. Volumetric evaluations such as ultrasonic examinations are used to detect stress corrosion cracking of internal surfaces such as stainless steel components exposed to diesel exhaust.

If work opportunities are not sufficient to allow inspection of a representative sample of components, supplemental inspections are also performed. A representative sample size is 20 percent of the accessible and inaccessible component population (defined as components having the same material and environment combination) up to a maximum of 25 components. The locations and intervals for supplemental inspections are based on assessments of the likelihood of significant aging effects, derived from current industry and plant-specific operating experience.

Identified aging deficiencies are documented and evaluated by the Corrective Action Program. Acceptance criteria are established in the maintenance and surveillance procedures or are established during engineering evaluation of the degraded condition.

If the inspection results are not acceptable, the condition is evaluated to determine whether the component intended function is affected, and a corrective action is implemented.

Components having the same material-environment combination with repetitive failures due to aging require a plant-specific program, unless the component material has been replaced by a material of more corrosion resistance for the environment of interest.

Callaway Plant Unit 1 Page B-81 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 93 of 100 Appendix B AGING MANAGEMENT PROGRAMS In addition, the internal coatings of the service water pump strainers are periodically visually inspected to ensure that loss of coating integrity is detected prior to (1) loss of component intended function, including loss of function due to accelerated degradation caused by localized coating failures, and (2) degradation of downstream component performance due to flow blockage.

The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program is a new program that will be implemented prior to entering the period of extended operation.

NUREG-1801 Consistency The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program is a new program that, when implemented, will be consistent with exception to NUREG-1801,Section XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components.

Exceptions to NUREG-1801 Program Elements Affected:

Scope of Program (Element 1), Parameters Monitored or Inspected (Element 3),

Detection of Aging Effects (Element 4), and Monitoring and Trending (Element 5)

NUREG-1801 requires a visual examination of the internal surface of components within the scope of this program. The diesel exhaust is not available for internal surface inspection, so a volumetric examination will be performed for this component. The volumetric examination is adequate for detecting loss of material (wall thinning) and cracking of piping and tubing.

Enhancements None Operating Experience The following discussion of operating experience provides objective evidence that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program will be effective in ensuring that intended functions are maintained consistent with the current licensing basis for the period of extended operation.

Callaway Plant Unit 1 Page B-82 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 94 of 100 Appendix B AGING MANAGEMENT PROGRAMS

1. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program will be a new program at Callaway. Internal surface monitoring through visual inspections conducted during maintenance activities and surveillance testing are already in effect in Callaway. The results of the inspections provide data for performance trending, are an input to work planning and prioritization process, and are communicated in the System Health Reports and System Performance Monitoring Indicators. Plant-specific operating experience since 2000 was reviewed to ensure that the operating experience discussed in the corresponding NUREG-1801 aging management program is bounding, i.e., that there is no unique plant-specific operating experience in addition to that described in NUREG-1801. The review also showed that the Plant Health and Performance Monitoring Program had been effective in maintaining the condition of component internal surfaces.
2. In 2007, during maintenance activities, the threaded tube end plugs on the 'B' centrifugal charging pump room cooler were found to have a loss of material due to corrosion as introduced by wear and deformation to the plugs from the repeated assembly/disassembly and cleanings. None of the plugs were leaking. An evaluation determined that 125 plugs would be replaced, future inspections of the room cooler coils would include inspection of tube plugs for loss of material due to corrosion, and replacements would be determined on a case-by-case basis. Later in 2007, the 'A' containment spray pump room cooler was inspected. There was no noticeable damage to the plugs in this cooler. Additional corrective action was to ensure a continuous on-site availability of enough plugs to replace all the plugs in one room cooler.

Internal inspections conducted during maintenance activities and surveillance testing and the Plant Health and Performance Monitoring Program have been effective in maintaining the condition of component internal surfaces. Occurrences that would be identified under the Internal Surfaces in Miscellaneous Piping and Ducting Components program will be evaluated to ensure there is no significant impact to safe operation of the plant and corrective actions will be taken to prevent recurrence. Guidance for re-evaluation, repair, or replacement is provided for locations where aging is found. There is confidence that the implementation of the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program will effectively identify aging prior to loss of intended function.

Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

Conclusion The implementation of the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components program will provide reasonable assurance that aging effects will be managed such that the systems and components within the scope of this program will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Callaway Plant Unit 1 Page B-83 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 95 of 100 Appendix B AGING MANAGEMENT PROGRAMS B2.1.25 Buried and Underground Piping and Tanks Program Description The Buried and Underground Piping and Tanks program manages loss of material, cracking, blistering, and changes in color of external surfaces of buried and underground piping and tanks. The program augments other programs that manage the aging of internal surfaces of buried and underground piping and tanks. The materials managed by this program include steel, stainless steel, concrete, and high-density polyethylene. The program manages aging through preventive, mitigative, and inspection activities.

Preventive and mitigative actions include the selection of component materials, external coatings for corrosion control, backfill quality control, and the application of cathodic protection. The cathodic protection system is operated consistent with the guidance of NACE SP0169-2007 for piping and NACE RP 0285-2002 for tanks. Trending of the cathodic protection system is performed to identify changes in the effectiveness of the system and to ensure that the rectifiers are available to protect buried components. An annual cathodic protection survey is performed consistent with NACE SP0169-2007.

Soil samples will be conducted during the 10-year period prior to the period of extended operation and in each subsequent 10-year period during the period of extended operation.

Soil samples will be performed in the vicinity of buried steel piping in which the cathodic protection system does not meet the following availability or effectiveness requirements:

  • Cathodic protection has been operational (available) at least 85 percent of the time since either 10 years prior to the period of extended operation or since installation/refurbishment, whichever is shorter; or
  • Cathodic protection has provided effective protection for buried piping as evidenced by meeting the acceptance criteria of -850 mV relative to a copper/copper sulfate electrode, instant off, at least 80 percent of the time since either 10 years prior to the period of extended operation or since installation/refurbishment, whichever is shorter.

Inspection activities may include nondestructive evaluation of pipe and tank wall thicknesses, and visual inspections of pipe and tank exterior surfaces, as permitted by opportunistic or directed excavations. The fire protection system jockey pump is monitored to identify changes in jockey pump activity.

Direct visual inspections will be performed on buried steel piping, stainless steel, piping, concrete piping, and carbon steel tanks. Inspection locations will be selected based on susceptibility to degradation and consequences of failure. A minimum of 10 feet of pipe of each material type must be inspected. The inspection will consist of a 100 percent visual inspection of the exposed pipe. If adverse indications are detected, inspection sample sizes within the affected piping categories are doubled. If adverse indications are Callaway Plant Unit 1 Page B-87 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 96 of 100 Appendix B AGING MANAGEMENT PROGRAMS found in the expanded sample, further increases in inspection sample size would be based on an analysis of extent of cause and extent of condition. Visual inspections of metallic components will be supplemented with surface or volumetric nondestructive testing (NDT) if significant indications are observed, to determine local area wall thickness. All buried high density polyethylene piping is encased in controlled low strength material; therefore, no direct visual inspections are required.

Direct visual inspections will be performed on underground steel, stainless steel and high density polyethylene piping, tank access covers, and valves to detect external corrosion.

Inspection locations will be selected based on susceptibility to degradation and consequences of failure.

Inspections will begin during the 10-year period prior to entering the period of extended operation. Upon entering the period of extended operation, inspections will occur every 10 years.

The internal surfaces of buried and underground piping and tanks are managed through other programs. Internal surfaces may be managed by the Open-Cycle Cooling Water System (B2.1.10), Closed Treated Water Systems (B2.1.11), Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (B2.1.23), Fuel Oil Chemistry (B2.1.16), Fire Water System (B2.1.14) or Water Chemistry (B2.1.2) programs. The Selective Leaching program (B2.1.19) works in conjunction with this program to manage buried or underground components subject to selective leaching.

NUREG-1801 Consistency The Buried and Underground Piping and Tanks program is a new program that, when implemented, will be consistent with NUREG-1801,Section XI.M41, Buried and Underground Piping and Tanks.

Exceptions to NUREG-1801 None Enhancements None Operating Experience The following discussion of operating experience provides objective evidence that the Buried and Underground Piping and Tanks program will be effective in ensuring that intended functions are maintained consistent with the current licensing basis for the period of extended operation:

Callaway Plant Unit 1 Page B-88 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 97 of 100 Appendix B AGING MANAGEMENT PROGRAMS

1. In the winter of 2005, an alarm was triggered for fire protection loop jockey pump excessive run time and an investigation was initiated. The location of the leak was determined and promptly isolated from the main fire water loop. The isolation of the leak did not affect any required suppression systems. The leak was promptly repaired and the fire water piping was returned to service.
2. Prior to Refuel 15 (Spring 2007), Close Interval Surveys (CIS) were performed on various tanks and associated piping systems to identify cathodic protection effectiveness. The CIS testing measures cathodic protection levels along the pipeline at approximately 2.5 foot intervals. These surveys were performed on the following structures and components within the scope of license renewal: emergency fuel oil storage tanks, fire water storage tank bottoms, ESW system piping, and condensate storage tank piping. The results indicated that emergency fuel oil storage tanks, condensate storage tank piping, and one quadrant of the fire water storage tank, were not meeting the 850mV polarization potential criterion of the National Association of Corrosion Engineers (NACE). Corrective actions were taken to correct these deficiencies by adjusting the cathodic protection where possible. In some instances the cathodic protection system could not be adjusted to correct a condition. Cathodic protection system refurbishment and modifications are planned in areas where the system does not meet the NACE criteria.
3. From 2008 to 2009, the underground portions of the ESW supply from the ESW pump house and return to the ultimate heat sink cooling tower were replaced with HDPE piping. In addition, sections of above ground or underground carbon steel piping that interfaces with the buried piping was replaced with stainless steel piping. These modifications were performed as a result of the material condition of the ESW system.

These modifications were performed as a result of corrective action documents that have been written concerning pinhole leaks, pitting, and other localized degradation of the ESW piping system.

4. In the summer of 2011, the annual cathodic protection survey was performed. Several locations in the fire water system had a negative potential below the NACE criteria of 850 mV. Modification and refurbishment of the cathodic protection system will address areas of low negative potential identified during the annual survey and the CIS described above.
5. Due to industry operating experience with buried condensate system piping, Callaway reviewed cathodic protection records related to the buried carbon steel piping for the condensate storage tank to determine if the external corrosion control provided for this piping was adequate. The review of the cathodic protection for this line found that the negative potential was below the NACE criteria. The cathodic protection system will be refurbished/modified in areas where it does not meet the NACE criteria. The buried portion of the condensate storage tank suction line will be inspected prior to the period of extended operation.

Callaway Plant Unit 1 Page B-89 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 98 of 100 Appendix B AGING MANAGEMENT PROGRAMS Inspection and preventive measures that will be implemented by the Buried and Underground Piping and Tanks program will be effective in managing aging of underground and buried components. Occurrences that would be identified under the Buried and Underground Piping and Tanks program will be evaluated to ensure there is no significant impact to safe operation of the plant and corrective actions will be taken to prevent recurrence. Guidance for re-evaluation, repair, or replacement is provided for locations where aging is found. There is confidence that the implementation of the Buried and Underground Piping and Tanks program will effectively identify aging prior to loss of intended function.

Industry and plant-specific operating experience will be evaluated in the development and implementation of this program.

Conclusion The implementation of the Buried and Underground Piping and Tanks program will provide reasonable assurance that aging effects will be managed such that the systems and components within the scope of this program will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Callaway Plant Unit 1 Page B-90 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 99 of 100 Appendix B AGING MANAGEMENT PROGRAMS B2.1.32 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants Program Description The RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program, which is implemented as part of the Structures Monitoring program (SMP), manages the following aging effects:

  • Cracking; loss of bond; and loss of material (spalling, scaling)
  • Increase in porosity and permeability; loss of strength
  • Loss of material
  • Loss of material (spalling, scaling) and cracking
  • Loss of material; loss of form The scope of this program also includes structural steel and structural bolting associated with water-control structures. SNUPPS-Callaway positions are compliant with that of Regulatory Guide 1.127 with respect to the ultimate heat sink (UHS) retention pond. The Structures Monitoring program (B2.1.31), which is in compliance with 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, includes all water-control structures within the scope of RG 1.127. The UHS retention pond, the essential service water pumphouse, the ESW supply lines yard vault, the UHS cooling tower, and the associated submerged discharge structures, and the concrete structures in the turbine building that provide a flowpath for the circulating water system are the water-control structures within the scope for license renewal that are monitored by this program. The UHS retention pond and its associated structures receive periodic inservice inspections for assessment of their structural safety and operational adequacy every five years. Callaway performs algae treatment and riprap inspections along the UHS retention pond. Callaway maintains benchmarks for monitoring settlement in any of the Category 1 structures including the UHS cooling tower. The inspections of all structural components, include masonry walls and water-control structures, are performed at intervals of no more than 5 years.

NUREG-1801 Consistency The RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program, is an existing program that, following enhancement, will be is consistent with NUREG-1801,Section XI.S7, RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants.

Exceptions to NUREG-1801 None Enhancements None Callaway Plant Unit 1 Page B-108 License Renewal Application Amendment 31

ULNRC-06080 February 14, 2014 Page 100 of 100 Appendix B AGING MANAGEMENT PROGRAMS Prior to the period of extended operation, the following enhancement will be implemented in the following program element:

Scope of the Program (Element 1)

Procedures will be enhanced to include the concrete structures in the turbine building that provide a flowpath for the circulating water system in the scope of the program.

Operating Experience The following discussion of operating experience provides objective evidence that the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program will be effective in ensuring that intended functions are maintained consistent with the current licensing basis for the period of extended operation:

1. An instance of concrete delamination occurred in 2005. Open electrical boxes that were part of the abandoned lighting system in the 'A' UHS fan deck room allowed water to enter the embedded conduits located in the concrete wall. This water contributed to the corrosion growth on the conduit which eventually deteriorated enough to cause spalling on the plant north face of the wall separating 'A' and 'B' UHS fan deck rooms.

The spalled area was patched with cement grout in 2006.

2. Similar spalling was noted on the south wall in the 'D' UHS cooling tower fan room which had an area approximately 1 ft by 1 ft where the concrete had popped out. The degradation appeared to be about two to three inches deep. The apparent cause was rainwater seeping through an abandoned electrical conduit. A job was initiated to repair both spalled areas in the "D" cooling tower fan room. To prevent recurrence of the concrete spalling, prior to installing the grout patch, a hole was drilled in the exposed part of the conduit to drain any water remaining in the abandoned conduits.

The above examples provide objective evidence that the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program is capable of both monitoring and detecting the aging effects associated with the program. Occurrences that would be identified under the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program will be evaluated to ensure there is no significant impact to safe operation of the plant and corrective actions will be taken to prevent recurrence. Guidance for re-evaluation, repair, or replacement is provided for locations where aging is found. There is confidence that the continued implementation of the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program will effectively identify aging prior to loss of intended function.

Conclusion The continued implementation of the RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants program, following enhancement, provides reasonable assurance that aging effects will be managed such that the systems and components within the scope of this program will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Callaway Plant Unit 1 Page B-109 License Renewal Application Amendment 31

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