LIC-02-0042, Ft. Calhoun Station, Unit 1 - LRA Technical Information - Aging Management Review

Ft. Calhoun Station, Unit 1 - LRA Technical Information - Aging Management Review

ML022180852
Person / Time
Site:	Fort Calhoun
Issue date:	04/25/2003
From:	Omaha Public Power District
To:	Office of Nuclear Reactor Regulation
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ML022180857	List: LIC-02-0042, Ft. Calhoun Station, Unit 1 - LRA Technical Information - Aging Management Review
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LIC-02-0042
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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.0 AGING MANAGEMENT REVIEW For those structures and components identified as subject to an aging management review, 10 CFR 54.21 (a)(3) requires demonstration that the effects of aging will be adequately managed so that their intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. This section describes the results of the aging management reviews of the components and structures identified in Section 2, Scoping and Screening Methodology for Identifying Structures and Components Subject to Aging Management Review, and Implementation Results.

The aging management reviews were conducted by:

1. Identifying the materials and environments of these structures and components;

2. Determining the applicable aging effect(s) requiring management; and

3. Assigning the appropriate aging management program to those components and structures with materials and environments that were determined to be subject to an aging effect requiring management.

The result of each mechanical and structural aging management review is documented as a unique set of component(s) or subcomponent(s), made of a material, exposed to an environment, with an Aging Effect Requiring Management (AERM), managed by an Aging Management Program (AMP). This unique set of

"* component(s) or subcomponent(s)

"* material

"* environment

"* AERM

"* AMP is defined as a FCS Aging Management Group (AMG). The aging management review results for systems, structures, or component groupings are made up of several AMGs.

Four types of aging management review results are discussed in this section of the application. The first of these are the FCS AMGs that credit AMPs evaluated in NUREG 1801. To identify those FCS AMGs that credit AMPs evaluated in NUREG-1801, each FCS AMG was compared to the NUREG-1801, Volume 2 aging management review results using the process documented below. FCS aging management review results were classified as being consistent with NUREG-1801 if the comparison between each FCS AMG and a single row from the tables in NUREG-1 801, Volume 2 met the following criteria.

1. The FCS AMG component, material, environment and AERM are determined to be the same, using engineering judgment, as the component, material, environment and AERM documented in NUREG-1 801, Volume 2.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

2. The FCS AMP is determined to be the same, using engineering judgment, as the AMP documented in NUREG-1801, Volume 2; or NUREG-1801, Volume 2 specifies a plant specific AMP.

FCS AMG aging management review results were classified as consistent with NUREG-1801 with deviation if the comparison between the FCS AMG and a single row from the tables in NUREG-1801, Volume 2 met criterion 1 above, and the FCS AMP deviates from one or more of the acceptance criteria for the AMP documented in Chapters 10 and 11 of NUREG-1801, Volume 2.

The Aging Management Review results for FCS AMGs that credit AMPs evaluated in NUREG-1 801 are reported in Tables 3.x. 1 of sections 3.1 through 3.6. The process used to develop these tables is described below.

The component, aging effect/mechanism, aging management programs and further evaluation recommended columns from Table 3.x.1 of NUREG-1 800 were copied from NUREG-1800 for those rows applicable to a PWR.

A discussion column was added to the four columns. Where applicable, the following information was entered in the discussion column:

"* A statement that the FCS AMGs are consistent with NUREG-1801, that the FCS AMGs are consistent with NUREG-1 801 with deviation(s), or that the components, materials and environments identified in NUREG-1801 are not applicable to FCS

"* Identification of the FCS AMP when NUREG-1801 specifies a plant specific program; the applicable Appendix B section is also identified

"* A discussion of the materials and environments included in the FCS AMGs that are consistent with the materials and environments reported in NUREG-1801

"* Ifnecessary, a description of component(s) in the FCS AMGs that is not included in NUREG-1801

"* If necessary, a description of material(s) in the FCS AMGs that is not included in NUREG-1801 In Table 3.6-1, discussions of a FCS specific AMP and modification are included for electrical cables and connectors not subject to 10 CFR 50.49 EQ requirements.

The second type of aging management review result discussed in Sections 3.1, 3.2, 3.3, 3.4, and 3.5 of the application are the FCS AMGs that do not credit AMPs evaluated in NUREG-1801. These aging management review results are reported in Tables 3.x.2 of Sections 3.1, 3.2, 3.3, 3.4, and 3.5. The entries in Tables 3.x.2 were developed by identifying components with the same material, environment, AERM and AMP, and entering these results as a single row in the table. The AERM column of Tables 3.x.2 includes a discussion of the applicable aging mechanisms for the AERM. The applicable Appendix B section is also identified for each AMP.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The third type of Aging Management Review results discussed in Sections 3.1, 3.2, 3.3, 3.4, and 3.5 of the application are the FCS AMGs with components or materials not evaluated in NUREG-1 801 that rely on aging management programs in NUREG-1 801 for FCS License Renewal and the justification for the use of these programs. These aging management review results are reported in Tables 3.x.3 of Sections 3.1, 3.2, 3.3, 3.4, and 3.5.

The fourth type of Aging Management Review results discussed in this section of the application includes the components replaced on the basis of performance or condition.

The performance or condition monitoring programs to ensure functionality during the period of extended operation are discussed in Section 3.3 of this application.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.1 AGING MANAGEMENT OF REACTOR COOLANT SYSTEMS The FCS reactor coolant systems evaluated in this section of the application consist of the Reactor Coolant System, the Reactor Vessel and the Reactor Vessel Internals and associated components.

The Reactor Coolant System consists of two heat transfer loops connected in parallel to the reactor vessel. Each loop contains one steam generator, two reactor coolant pumps, connecting piping and instrumentation. A pressurizer is connected to one of the reactor vessel outlet (hot leg) pipes by a surge line. All components of the Reactor Coolant System are located within the Containment Building.

The Reactor Vessel is a 140-inch beltline inner diameter two-loop vessel. This configuration has four coolant inlet nozzles and two coolant outlet nozzles. The vessel includes a removable head with multiple penetrations (control element drive mechanisms, in-core instrumentation nozzles, and the reactor vessel vent line). The vessel includes two leakage detection lines. The vessel is an all welded, manganese molybdenum-nickel steel plate and forging construction. The interior surfaces of the vessel in contact with reactor coolant are clad with austenitic stainless steel.

The Reactor Vessel Internals are designed to support and align the fuel assemblies, control element assemblies (CEAs), and in-core instrumentation (ICI) assemblies, and to guide reactor coolant through the reactor vessel. The components of the Reactor Vessel Internals consist of the upper guide structure, core support barrel, thermal shield, core shroud, CEA shroud assemblies, ICI assemblies, lower support structure, and flow skirt.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience were consistent with those identified in NUREG-1801.

Industry: A review of industry-wide operating experience was conducted to identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.1.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.1-1 shows the aging management programs evaluated in NUREG-1801 that are relied on for license renewal of the reactor coolant systems at FCS. Note that this table only includes those components, materials and environments that are applicable to a PWR. Information on FCS specific components and materials, not listed in NUREG-1801 but included in the component group of this application, is included in the discussion column.

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FORT CALHOUi, ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Discussion Reactor coolant Cumulative TLAA, evaluated 1. The FCS aging management review results pressure boundary fatigue damage in accordance are consistent with those reviewed and components with 10 CFR approved in NUREG-1801 except as noted 54.21(c) in item 4 below.

2. The metal fatigue time limited aging analyses are discussed in Section 4.3.

3. Consistent with NUREG-1 801, this group includes the low alloy steel and carbon steel with stainless steel cladding, stainless steel, CASS, and nickel alloy in borated treated water; and low alloy steel in deoxygenated water and steam at FCS.

4. Cumulative fatigue damage is not an aging effect requiring management for control element assembly shroud bolts and core support barrel snubber assembly socket head cap screws. These components are preloaded to prevent fatigue cycles.

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FORT CALHOU,.. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect/ Management ut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended 3.1.1.02 Steam generator Loss of material Inservice Yes, detection of 1. The FCS aging management review results shell assembly due to pitting and inspection; water aging effects is to are consistent with those reviewed and crevice corrosion chemistry be further approved in NUREG-1801.

evaluated 2. This aging effect is managed by the Inservice Inspection Program (B.1.6), the Chemistry Program (B.1.2) and the Steam Generator Program (B.2.9). The Steam Generator Program includes methods to detect general, crevice and pitting corrosion discussed in NUREG-1801, Volume 2, IV.D1.1-c. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes carbon steel in deoxygenated treated water at FCS.

3.1.1.03 Pressure vessel Loss of fracture TLAA, evaluated Yes, TLAA 1. The FCS aging management review results ferritic materials toughness due to in accordance are consistent with those reviewed and that have a neutron irradiation with Appendix G approved in NUREG-1801.

neutron fluence embrittlement of 10 CFR 50 2. The reactor vessel neutron embrittlement greater than 1017 and RG 1.99 time limited aging analyses are discussed in Section 4.2.

n/cm 2 (E>1 MeV) 3. Consistent with NUREG-1801, this group includes low alloy steel with stainless steel cladding in borated treated water.

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FORT CALHO6.. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Aging Further Row Aging Effect/ Management utDiscussion Number Evaluation Dsuso Component Mechanism Programs Recommended 3.1.1.04 Reactor vessel Loss of fracture Reactor vessel Yes, plant specific 1. The FCS aging management review results beltline shell and toughness due to surveillance are consistent with those reviewed and welds neutron irradiation approved in NUREG-1801.

embrittlement 2. The Reactor Vessel Integrity Program (B.1.7) manages this aging effect. This program is described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes low alloy steel with stainless steel cladding in borated treated water.

3.1.1.05 Westinghouse and Loss of fracture Plant specific Yes, plant specific This item is not applicable since FCS is a B&W baffle/former toughness due to Combustion Engineering designed and bolts neutron irradiation manufactured reactor.

embrittlement and void swelling Page 3-8 AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-8

K FORT CALHOU,. iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Aging Further Row Aging Effect/ Management utDiscussion Number Evaluation Dsuso Component Mechanism Programs Recommended 3.1.1.06 Small-bore reactor Crack initiation Inservice Yes, parameters 1. The FCS aging management review results coolant system and growth due to inspection; water monitored/ are consistent with those reviewed and and connected SCC, chemistry; one- inspected and approved in NUREG-1801.

systems piping intergranular time inspection detection of aging 2. This aging effect is managed by the SCC, and thermal effects are to be Inservice Inspection Program (B. 1.6), the and mechanical further evaluated Chemistry Program (B. 1.2) and the One loading Time Inspection Program (B.3.5). These programs are described in Appendix B of this application. The One-Time Inspection Program verifies that service-induced weld cracking is not occurring in the small-bore piping less than NPS 4, including pipe, fittings, and branch connections.

3. Consistent with NUREG-1801, this group includes stainless steel in borated treated water at FCS.

3.1.1.07 Vessel shell Crack growth due TLAA Yes, TLAA Underclad crack growth due to cyclic loading to cyclic loading was not identified as a TLAA for FCS.

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(,

FORT CALHOUo, 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Evaluation Evaluation Discussion Recommended Changes in Yes, plant specific 1. The FCS aging management review results dimension due to are consistent with those reviewed and void swelling approved in NUREG-1801 with the exception noted in item 4 below.

2. This aging effect is managed by the Reactor Vessel Internals Inspection Program (B2.8).

FCS will continue to participate in industry programs to investigate aging effects and determine appropriate aging management programs. This program is described in Appendix B of this application.

3. Consistent with NUREG-1 801, this group includes stainless steel in borated treated water at FCS.

4. Changes in dimension due to void swelling are not an aging effect requiring management for some reactor internals components because the intended function of the component is not affected. As noted in the Safety Evaluation Report Related to the License Renewal of Arkansas Nuclear One, Unit 1, the specific impacts of concern for void swelling are constriction of flow paths, interference with control rod insertion and excessive baffle bolt loading.

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FORT CALHOUit..,TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect/ Management ut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended This is consistent with NUREG-1 705, Safety Evaluation Report Related to the License Renewal of Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Final Report), and NUREG-1723, Safety Evaluation Report Related to the License Renewal of Oconee Nuclear Station, Units 1, 2 and 3. Swelling of certain components does not impact the noted concerns. These components are the core support barrel alignment key, core support barrel fasteners, core support barrel locking collar, core support barrel spacer, core support barrel upper flange, upper guide structure alignment lug (NUREG-1 801 FAP guide lug), upper guide structure fasteners, upper guide structure guide pins, hold down ring, upper guide structure locking strip, upper guide structure plate (a support for an instrument tube), upper guide structure shim ring, upper guide structure tab, thermal shield positioning pins and screws, thermal shield pins, thermal shield shim, lower internals anchor block, Page 3-11 AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-11

FORT CALHOL,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Aging Effect/ Management Evaluation Discussion Number Component Mechanism Programs Recommended lower internals fasteners, lower vessel internals dowel pins, core shroud fasteners, control element assembly shroud nuts and bolts, in-core instrumentation guide tubes (above instrumentation support plate), in core instrumentation guide tube fasteners, incore instrumentation support plate and gussets.

3.1.1.09 PWR core support Crack initiation Plant specific Yes, plant specific 1. The FCS aging management review results pads, instrument and growth due to are consistent with those reviewed and tubes (bottom SCC and/or approved in NUREG-1801.

head primary water 2. This aging effect is managed by the Alloy penetrations), stress corrosion 600 Program (B.3.1). This program is pressurizer spray cracking described in Appendix B of this application.

heads, and (PWSCC) 3. Consistent with NUREG-1 801, this group nozzles for the includes Alloy 600 in borated treated water steam generator at FCS. The vessel flange leak detection line instruments and at FCS is made of Alloy 600.

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FORT CALHOb.. jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Aging Effect/ Management Evaluation Discussion Number Mechanism Programs Recommended Component

3. 1 1.10 Cast austenitic Crack initiation Plant specific Yes, plant specific 1. The FCS aging management review results stainless steel and growth due to are consistent with those reviewed and (CASS) reactor SCC approved in NUREG-1801.

coolant system 2. This aging effect is managed by the piping Chemistry Program (B.1.2), the Inservice Inspection Program (B.1.6) and the Thermal Embrittlement of Cast Austenitic Stainless Steel Program (B.3.7). These programs are described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes cast austenitic stainless steel (CASS) reactor coolant system piping.

3.1.1.11 Pressurizer Crack initiation Inservice Yes, AMP for 1. The FCS aging management review results instrumentation and growth due to inspection; water PWSCC of Inconel are consistent with those reviewed and penetrations and PWSCC chemistry 182 welds is to be approved in NUREG-1801.

heater sheaths and evaluated 2. This aging effect is managed by the Alloy 600 sleeves made of Program (B.3.1), Chemistry Program (B.1.2)

Ni-alloys and Inservice Inspection Program (B.1.6)

These programs are described in Appendix B of this application. The Alloy 600 Program manages the AERM of PWSCC in Inconel 182 welds.

3. Consistent with NUREG-1 801, this group includes Alloy 600 and nickel alloys in borated treated water at FCS.

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"FORTCALHObh.. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Aging Effect/ Management Evaluation Discussion Number Component Mechanism Programs Recommended 3.1.1.12 Westinghouse and Crack initiation Plant specific Yes, plant specific This item is not applicable since FCS is a B&W baffle former and growth due to Combustion Engineering designed and bolts SCC and IASCC manufactured reactor.

3.1.1.13 Westinghouse and Loss of preload Plant specific Yes, plant specific This item is not applicable since FCS is a B&W baffle former due to stress Combustion Engineering designed and bolts relaxation manufactured reactor.

3.1.1.14 Steam generator Loss of section Plant specific Yes, plant specific The components identified in NUREG-1801, feedwater thickness due to Volume 2, IV.l. 1-e are not applicable to FCS.

impingement plate erosion and support Page 3-14 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-14

FORT CALHOU,. .TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Management Evaluation Discussion Number Component Mechanism Programs Recommended 3.1.1.15 (Alloy 600) Steam Crack initiation Steam generator Yes, effectiveness 1. The FCS aging management review results generator tubes, and growth due to tubing integrity; of a proposed AMP are consistent with those reviewed and repair sleeves, and PWSCC, outside water chemistry is to be evaluated approved in NUREG-1801.

plugs diameter stress 2. This aging effect is managed by the Steam corrosion cracking Generator Program (B13.7) and Chemistry (ODSCC), and/or Program (B.1.2). These programs are intergranular described in Appendix B of this application.

attack (IGA) or The FCS Technical Specifications have loss of material already incorporated the NRC-approved due to wastage basis for steam generator degradation and pitting management.

corrosion, and 3. Consistent with NUREG-1801, this group fretting and wear; includes Alloy 600 in borated treated and or deformation deoxygenated treated water.

due to corrosion 4. Combustion Engineering (Westinghouse) at tube support mechanical and welded steam generator plate intersections tube plugs are installed at FCS.

5. NUREG-1801 IV.D 1.2-f is not pertinent to FCS, as phosphate chemistry has never been used. Regarding NUREG-1801 IV.D 1.2-g, FCS did not require analysis in accordance with NRC Bulletin 88-02.

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FORT CALHOU,, TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Discussion 3.1.1.16 Tube support Loss of section Plant specific Yes, plant specific 1. The FCS aging management review results lattice bars made thickness due to are consistent with those reviewed and of carbon steel FAC approved in NUREG-1801.

2. The inspection of the tube support lattice bars for loss of thickness is included in the Steam Generator Program (B.2.9) described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes carbon steel in deoxygenated water.

J .1- 4 + I 3.1.1.17 Carbon steel tube Ligament cracking Plant specific Yes, effectiveness 1. The FCS aging management review results support plate due to corrosion of a proposed AMP are consistent with those reviewed and is to be evaluated approved in NUREG-1801.

2. This aging effect is managed by the Steam Generator Program (B.2.9) and Chemistry Program (B, .12).These programs are described in Appendix B of this application.

The FCS Technical Specifications have already incorporated NRC-approved guidance for steam generator degradation management.

3. Consistent with NUREG-1801, this group includes carbon steel in deoxygenated water.

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FORT CALHOU,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect/ Management ut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended 3.1.1.18 Steam generator Loss of material Combustion Yes, plant specific As stated in NUREG-1801, Volume 2, VI.D1.3 feedwater inlet ring due to flow- Engineering (CE) a, this effect is only applicable to certain CE and supports corrosion steam generator System 80 steam generators. Because of feedwater ring differences in design between the FCS steam inspection generators and the System 80 steam generators, this effect is not applicable to FCS.

3.1.1.19 Reactor vessel Crack initiation Reactor head No 1. The FCS aging management review results closure studs and and growth due to closure studs are consistent with those reviewed and stud assembly SCC and/or approved in NUREG-1801.

IGSCC 2. Consistent with NUREG-1801, this group includes low alloy steel in air possibly exposed to borated treated water.

3. The Reactor Head Closure Studs Program is incorporated into the Bolting Integrity Program at FCS.

3.1.1.20 CASS pump Loss of fracture Inservice No 1. The FCS aging management review results casing and valve toughness due to inspection are consistent with those reviewed and body thermal aging approved in NUREG-1801.

embrittlement 2. Consistent with NUREG-1801, this group includes CASS in borated treated water.

3.1.1.21 CASS piping Loss of fracture Thermal aging No 1. The FCS aging management review results toughness due to embrittlement of are consistent with those reviewed and thermal aging CASS approved in NUREG-1801.

embrittlement 2. Consistent with NUREG-1 801, this group includes CASS in borated treated water.

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FORT CALHOU'r ,,TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect/ Management ut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended 3.1.1.22 BWR piping and Wall thinning due Flow-accelerated No 1. The FCS aging management review results fittings; steam to flow- corrosion are consistent with those reviewed and generator accelerated approved in NUREG-1801.

components corrosion 2. Consistent with NUREG-1801, this group includes carbon steel in deoxygenated treated water.

3.1.1.23 Reactor coolant Loss of material Bolting integrity No 1. The FCS aging management review results pressure boundary due to wear; loss are consistent with those reviewed and (RCPB) valve of preload due to approved in NUREG-1801.

closure bolting, stress relaxation; 2. Consistent with NUREG-1801, this group manway and crack initiation includes stainless steel, low alloy steel and holding bolting, and growth due to carbon steel in air possibly exposed to and closure bolting cyclic loading and/ borated treated water.

in high pressure or SCC and high temperature systems 3.1.1.24 CRD nozzle Crack initiation Ni-alloy nozzles No 1. The FCS aging management review results and growth due to and penetrations; are consistent with those reviewed and PWSCC water chemistry approved in NUREG-1801.

2. Consistent with NUREG-1801, this group includes Alloy 600 in borated treated water.

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FORT CALHOU,. 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Aging Effect/ Management Evaluation Discussion Number Recommended Component Mechanism Programs 3.1.1.25 Reactor vessel Crack initiation Inservice No 1. The FCS aging management review results nozzles safe ends and growth due to inspection; water are consistent with those reviewed and and CRD housing; cyclic loading, chemistry approved in NUREG-1801.

reactor coolant and/or SCC, and 2. Consistent with NUREG-1801, this group system PWSCC includes stainless steel, austenitic stainless components steel, Alloy 600 and carbon or low alloy steel (except CASS and clad with stainless steel in borated treated bolting) water.

Note: NUREG 1801, Volume 2, items IV C2.3-b and IV C2.4-b that include CASS are includedin this group.

3.1.1.26 Reactor vessel Loss of fracture Thermal aging No 1. The FCS aging management review results internals CASS toughness due to and neutron are consistent with those reviewed and components thermal aging, irradiation approved in NUREG-1801.

neutron irradiation embrittlement 2. Consistent with NUREG-1801, this group embrittlement, includes CASS in borated treated water.

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FORT CALHOU,..iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Aging Effect/ Management Evaluation Discussion Number Component Mechanism Programs Recommended 3.1.1.27 External surfaces Loss of material Boric acid No 1. The FCS aging management review results of carbon steel due to boric acid corrosion are consistent with those reviewed and components in corrosion approved in NUREG-1801.

reactor coolant 2. Consistent with NUREG-1801, this group system pressure includes carbon steel in air possibly exposed boundary to borated treated water.

3.1.1.28 Steam generator Loss of material Inservice No This item is not applicable since FCS is a secondary due to erosion inspection Combustion Engineering designed and manways and manufactured reactor.

handholds (CS) 3.1.1.29 Reactor internals, Loss of material Inservice No 1. The FCS aging management review results reactor vessel due to wear inspection are consistent with those reviewed and closure studs, and approved in NUREG-1801.

core support pads 2. Consistent with NUREG-1 801, this group includes low alloy steel and stainless steel in borated treated water.

3.1.1.30 Pressurizer Crack initiation Inservice No The component identified in NUREG-1801 is integral support and growth due to inspection not applicable to FCS.

cyclic loading 3.1.1.31 Upper and lower Loss of preload Inservice No These items are not applicable since FCS is a internals assembly due to stress inspection; loose Combustion Engineering designed and (Westinghouse) relaxation part and/or manufactured reactor.

neutron noise monitoring AGING MANAGEMENT REVIEW Revision 1 Page 3-20

FORT CALHOUh0. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect Management Fut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended 3.1.1.32 Reactor vessel Loss of fracture PWR vessel No 1. The FCS aging management review results internals in fuel toughness due to internals; water are consistent with those reviewed and zone region neutron irradiation chemistry approved in NUREG-1801.

(except embrittlement, 2. Consistent with NUREG-1801, this group Westinghouse and and void swelling includes stainless steel and nickel alloys in Babcock & Wilcox borated treated water at FCS.

[B&W] baffle bolts) 3.1.1.33 Steam generator Crack initiation Inservice No 1. The FCS aging management review results upper and lower and growth due to inspection; are consistent with those reviewed and heads; SCC, PWSCC. water chemistry approved in NUREG-1801.

tubesheets; IASCC 2. Consistent with NUREG-1801, this group primary nozzles includes stainless steel in borated treated and safe ends water.

3.1.1.34 Vessel internals Crack initiation PWR vessel No 1. The FCS aging management review results (except and growth due to internals; water are consistent with those reviewed and Westinghouse and SCC and IASCC chemistry approved in NUREG-1801.

B&W baffle former 2. Consistent with NUREG-1801, this group bolts) includes stainless steel, nickel alloys and CASS in borated treated water.

3.1.1.35 Reactor internals Loss of preload Inservice No These items are not applicable since FCS is a (B&W screws and due to stress inspection; loose Combustion Engineering designed and bolts) relaxation part monitoring manufactured reactor.

Revision I1 Page 3-21 AGING MANAGEMENT REVIEW AGING Revision Page 3-21

FORT CALHOUN jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL RwAging Further Row Aging Effect/ Management ut Discussion Number Maaeet Evaluation Component Mechanism Programs Recommended 3.1.1.36 Reactor vessel Loss of material Reactor head No 1. The FCS aging management review results closure studs and due to wear closure studs are consistent with those reviewed and stud assembly approved in NUREG-1801.

2. Consistent with NUREG-1801, this group includes high strength steel in air possibly exposed to borated treated water at FCS.

3. The Reactor Head Closure Studs Program is incorporated into the Bolting Integrity Program (B.1.1) at FCS.

3.1.1.37 Reactor internals Loss of preload Inservice No 1. The FCS aging management review results (Westinghouse due to stress inspection; loose are consistent with those reviewed and upper and lower relaxation part monitoring approved in NUREG-1801 with the deviation internal that FCS does not credit the Loose Parts assemblies; CE Monitoring Program as discussed in bolts and tie rods) NUREG-1801, Volume 2, IV.B3.2-g and IV.B3.4-h.

2. The Reactor Vessel Internals Inspection Program (B.2.8) manages this aging effect.

This program is described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes nickel alloy and stainless steel in borated treated water.

Page 3-22 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-22

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.1.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 Table 3.1-2 contains the reactor coolant systems aging management review results that are not addressed in NUREG-1801. This table includes the component types, materials, environments, aging effects requiring management and the programs and activities for managing aging. Table 3.1-3 contains components and materials in reactor coolant systems not evaluated in NUREG-1801 that rely on aging management programs in NUREG-1 801 for FCS License Renewal and the justification for the use of these programs.

Page 3-23 REVIEW Revision I AGING MANAGEMENT REVIEW AGING Revision I Page 3-23

FORT CALHOUi.. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-2 FCS REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.1.2.01 External surfaces of Stainless Steel Ambient Air None Not Applicable stainless steel components in reactor coolant system pressure boundary 3.1.2.02 Pressurizer heater Nickel Based Alloy Borated Treated Water Loss of Material Chemistry Program (B. 1.2) sleeves, steam generator - including Alloy 600 Crevice corrosion in tubes, ICI nozzles, nozzle the presence of safe ends, CEDM and sufficient levels of incore instrument oxygen, halogens, housings, reactor head sulfates, or copper vent pipe, pressurizer bottom head plate cladding, steam generator primary head cladding and shock suppressors &

supports, nozzle welds, thermal sleeves 3.1.2.03 External surfaces of nickel Nickel Based Alloy Ambient Air None Not Applicable based alloy components in including Alloy 600 reactor coolant system pressure boundary 3.1.2.04 Steam generator lower Nickel Based Alloy Borated Treated Water Cracking Chemistry Program (B.1.2) head and manway cladding and primary side tube sheet AGING MANAGEMENT REVIEW Revision I Page 3-24

FORT CALHOU,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-2 (CONTINUED)

FCS REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.1.2.05 Reactor coolant pump Cast Austenitic Corrosion-Inhibited Cracking Chemistry Program (B.1.2) thermal barrier Stainless Steel Treated Water (CASS) 3.1.2.06 Secondary side of the Low-Alloy Steel Deoxygenated Treated Loss of Material Chemistry Program tubesheet, steam Water

• General and crev- (B.1.2), Steam Generator generator feedwater, ice corrosion due Program (B.2.9) and steam and instrument to the exposure of Inservice Inspection nozzles, and feedwater low-alloy steel to Program (B.1.6))

nozzle safe ends dissolved oxygen Pitting corrosion due to the expo sure of low-alloy steel to halogens and sulfates 3.1.2.07 Steam generator tube Nickel Based Alloy Deoxygenated Treated Loss of Material Chemistry Program (B.1.2) plugs Water Crevice and pitting and Steam Generator corrosion due to the Program (B.2.9) exposure of nickel based alloys to halogens and sulfates Revision II Page 3-25 AGING MANAGEMENT REVIEW AGING MANAGEMENT Revision Page 3-25

FORT CALHOUI,. oTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-2 (CONTINUED)

FCS REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.1.2.08 Reactor vessel internals - Alloy 600 Borated Treated Water Changes in Reactor Vessel Internals flow skirt Dimensions Inspection Program Void swelling as a (B.2.8) result of helium bubble nucleation and growth from nuclear transmutation reactions of nickel or boron in the austenitic stainless steel or nickel-based alloy material.

3.1.2.09 Reactor vessel internals - Alloy 600 Borated Treated Water Cracking Alloy 600 Program (B.3.1) flow skirt . Primary Water Stress Corrosion Cracking

. irradiation-assisted stress corrosion cracking in the presence of oxygen concentrations > 5 ppb, halogen concentrations > 150 ppb, and fluence levels > 5 E20 n/cm2 AGING MANAGEMENT REVIEW Revision I Page 3-26

(

FORT CALHOU,, .,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-2 (CONTINUED)

FCS REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.1.2.10 Reactor vessel internals - Alloy 600 Borated Treated Water Fatigue Fatigue Monitoring flow skirt Due to repeated Program (B.2.4) stress/strain cycles caused by fluctuating loads and temperatures 3.1.2.11 Reactor vessel internals - Alloy 600 Borated Treated Water Reduction of Fracture Reactor Vessel Internals flow skirt Toughness Inspection Program Due to changes in the (B.2.8) properties of the stainless steel and nickel-base alloys used in reactor internals 3.1.2.12 Steam generator Carbon Steel Ambient Air Loss of preload Bolting Integrity Program secondary manway steel Due to stress (B.1.1) bolts relaxation in high temperature environments 3.1.2.13 Pressurizer manway cover Carbon Steel Ambient Air Loss of Material Boric Acid Corrosion plate, SG feedwater and Due to the exposure to Prevention Program steam nozzle safe ends leaking boric acid (B.2.1)

Page 3-27 AGING MANAGEMENT AGING REVIEW MANAGEMENT REVIEW Revision I1 Revision Page 3-27

FORT CALHO.,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-2 (CONTINUED)

FCS REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.1.2.14 Steam generator steam Carbon Steel Deoxygenated Treated Loss of Material Chemistry Program nozzle safe end, steam Water . General and pit- (B.1.2), Steam Generator generator feed ring ting corrosion due Program (B.2.9) and to the exposure to Inservice Inspection dissolved oxygen Program (B.1.6)

• pitting corrosion due to the expo sure to halogens and sulfates 3.1.2.15 Pressurizer base Low-Alloy Steel Ambient Air Loss of Material Boric Acid Corrosion Due to the exposure to Prevention Program leaking boric acid (B.2. 1) 3.1.2.16 Pressurier relief valve and Nickel Based Alloy Borated Treated Water Cracking Chemistry Program (B.1.2)

Instrument nozzle nozzle Stress corrosion and Inservice Inspection inserts cracking due to Program (B.1.6) potential exposure to halogens or sulfates.

Page 3-28 AGING MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-28

FORT CALHOU.. .. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number 3.1.3.01 Thermal Shield Stainless High Temp/ Cracking Chemistry 3.1.1.34 The FCS components are and Thermal Steel Neutron Program made of the same material, Shield Fluence/ (B.1.2) exposed to the same Positioning Pin Borated environment, subject to the

& Bolt Treated Water same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IV.B3.4-a and IV.B3.4-e 3.1.3.02 Thermal Shield Stainless High Temp/ Cracking Reactor 3.1.1.34 The FCS components are and Thermal Steel Neutron Vessel made of the same material, Shield Fluence/ Internals exposed to the same Positioning Pin Borated Inspection environment, subject to the

&Bolt Treated Water Program same aging effects and (B.2.8) managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IV.1B3.4-a and IV.B3.4-e Page 3-29 MANAGEMENT REVIEW AGING MANAGEMENT AGING REVIEW Revision II Revision Page 3-29

FORT CALHOU, .,jTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number Bolt - Thermal Stainless High Temp/ Loss of Inservice 3.1.1.37 The FCS components are Shield Steel Neutron preload Inspection made of the same material, Fluence/ Program exposed to the same Borated (B.1.6) environment, subject to the Treated Water same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IV.B3.4-h

-I. 4 t 1- 1 Thermal Shield Stainless High Temp/ Reduction Reactor 3.1.1.32 The FCS components are and Thermal Steel Neutron of Fracture Vessel made of the same material, Shield Fluence/ Toughness Integrity exposed to the same Positioning Pin Borated Program environment, subject to the

& Bolt Treated Water (B.1.7) same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IV.B3.4-c and IV.B3.4-g AGING MANAGEMENT REVIEW Revision I Page 3-30

FORT CALHOUh, vTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number 3.1.3.05 Thermal Shield Stainless High Temp/ Changes in Reactor 3.1.1.08 The FCS components are and Thermal Steel Neutron Dimensions Vessel made of the same material, Shield Fluence/ Internals exposed to the same Positioning Pin Borated Inspection environment, subject to the

& Bolt Treated Water Program same aging effects and (B.2.8) managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IV.B3.4-b 3.1.3.06 Reactor coolant Stainless Borated treated Cracking Chemistry 3.1.1.25 The FCS components are valves including Steel water (B. 1.2) and made of the same material, PORV, drain Inservice exposed to the same valves, head Inspection environment, subject to the and pressurizer Programs same aging effects and vent valves, (B. 1.6) managed by the same aging instrument management programs as isolation valves the components evaluated in etc.; Reactor NUREG-1801, Volume 2, vessel cladding IV.C2.2-f and IV.A2.4-b 3.1.3.07 Not used in application Revision II Page 3-31 AGING MANAGEMENT REVIEW AGING Revision Page 3-31

FORT CALHOU,, ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number I. 4 + 4

0. Feedwater Low-Alloy Containment Loss of Boric Acid 3.1.1.27 The FCS components are nozzle safe end Steel Air Material Corrosion made of the same material, Prevention exposed to the same Program environment, subject to the (B.2.1) same aging effects and managed by the same aging management programs as the components evaluated in NUREG-1801, Volume 2, IV.D1.1-g 3.1.3.09 Reactor coolant Carbon Containment Loss of Boric Acid 3.1 1.27 The FCS components are pump driver Steel Air Material Corrosion made of the same material, mounts Prevention exposed to the same Program environment, subject to the (B.2.1) same aging effects and managed by the same aging management programs as the components evaluated in NUREG-1801 ,Volume 2, IV.C2.3-f Revision II Page 3-32 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision Page 3-32

FORT CALHOUi, STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number 3.1.3.10 Pressurizer Carbon Containment Loss of Boric Acid 3.1.1,27 The FCS components are relief valve Steel Air Material Corrosion made of the same material, external portion Prevention exposed to the same of body Program environment, subject to the (B.2.1) same aging effects and managed by the same aging management programs as the components evaluated in NUREG-1801, Volume 2, IV.C2.4-f 3.1.3.11 Reactor vessel Low-Alloy Containment Loss of Boric Acid 3.1.1.27 The FCS components are nozzles and Steel Air Material Corrosion made of the same material, safe ends, Prevention exposed to the same pressurizer shell Program environment, subject to the (B.2.1) same aging effects and managed by the same aging management programs as the components evaluated in NUREG-1801, Volume 2, IV.A2.1-a Page 3-33 MANAGEMENT REVIEW AGING MANAGEMENT AGING REVIEW Revision II Revision Page 3-33

FORT CALHOIJ,, ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number 3.1.3.12 Steam Low-Alloy Deoxygenated Loss of Flow- 3.1.1.22 The material is subject to the generator Steel Treated Water Material Accelerated same environment and aging feedwater and Corrosion effect, and managed by the steam nozzles Program same aging management (B. 1.5) program as evaluated in Table 3.1-1, Item 3.1.1.22.

The aging effect is independent of component type.

3.1.3.13 ICI Nozzles, RV Alloy 600 Borated Cracking Chemistry 3. 1 1.24 The FCS components are Vent Nozzle Treated Water Program made of the same material, (B. 1.2) exposed to the same Alloy 600 environment, subject to the Program same aging effects and (B.3.1) managed by the same aging management programs as the components evaluated in NUREG-1801, Volume 2, IV.A2.2-a and IV.A2.7-b Revision II Page 3-34 AGING MANAGEMENT REVIEW AGING MANAGEMENT Revision Page 3-34

FORT CALHOUI.. iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.1-3 (CONTINUED)

COMPONENTS IN REACTOR VESSEL, INTERNALS, AND REACTOR COOLANT SYSTEM NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL Row FCS FCS FCS FCS FCS Program Applicable Justification for applying Number Components Material Environment AERMs Activity NUREG-1801 NUREG-1801 Aging Aging Management Review Management Results Review Results Row Number 3.1.3.14 Thermal Shield Stainless High Temp/ Fatigue TLAA 3.1.1.01 The FCS components are Steel Neutron made of the same material, Fluence/ exposed to the same Borated environment, subject to the Treated Water same aging effects and managed by the same aging management programs as the components evaluated in NUREG-1801, Volume 2, IV.B3.4-d Page 3-35 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-35

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.2 AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES SYSTEMS The Engineered Safety Features Systems are composed of the Safety Injection and Containment Spray System and the Mechanical Containment Penetrations Commodity Group at FCS.

The Safety Injection (SI) System injects borated water into the Reactor Coolant System to provide emergency core cooling. The major components of the SI system are the three high pressure safety injection (HPSI) pumps, two low pressure safety injection (LPSI) pumps, four safety-injection tanks, four safety-injection leakage coolers, eight HPSI control valves, four LPSI control valves and other various valves, instrumentation, and piping.

During normal plant operation the SI system is maintained in a standby mode with all of its components lined up for emergency injection. A safety injection actuation signal (SIAS) automatically starts the HPSI and LPSI pumps and automatically opens the high pressure and low pressure injection valves. During the injection mode of operation, the HPSI and LPSI pumps take suction from the Safety Injection and Refueling Water Tank (SIRWT) and inject borated water into the Reactor Coolant System (RCS) via the safety injection nozzles located on the RCS cold legs. The four safety injection tanks constitute a passive injection system.

The Containment Spray (CS) System consists of three spray pumps, two heat exchangers (shutdown cooling heat exchangers) and all necessary piping, valves, instruments, and accessories. The pumps discharge the borated water through the two heat exchangers, during recirculation, to a dual set of spray headers and spray nozzles in the containment. These spray headers are supported from the containment roof.

The Containment Penetrations and System Interface Components for Non-CQE Systems Commodity Group consists of isolation valves, piping, and mechanical penetrations into containment for the following mechanical systems: Compressed Air (CA-PA), Demineralized Water (DW), Blowpipe and Feedwater Blowdown (FW-BD). The safety related heat exchangers in the Demineralized Water System are included. The mechanical portions of all electrical penetrations (i.e., canister and header plate) are also included.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience were consistent with those identified in NUREG-1 801.

Industry: A review of industry-wide operating experience was conducted to AGING MANAGEMENT REVIEW Revision I Page 3-36

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

3.2.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.2-1 shows the aging management programs evaluated in NUREG-1 801 that are relied on for license renewal of the Engineered Safeguards Features Systems at FCS.

Note that this table only includes those components, materials and environments that are applicable to a PWR. Information on FCS specific components and materials, not listed in NUREG-1801 but included in the component group of this application, is included in the discussion column.

Page 3-37 MANAGEMENT REVIEW Revision I AGING MANAGEMENT AGING REVIEW Revision 1 Page 3-37

FORT CALHOU,, aTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Management Further Discussion Number Component Mechanism Programs Evaluation Recommended 3.2.1.01 Piping, fittings, and Cumulative TLAA, evaluated in Yes, TLAA 1. The FCS aging management review valves in emergency fatigue damage accordance with results are consistent with those core cooling system 10 CFR 54.21(c) reviewed and approved in NUREG 1801.

2. The metal fatigue time limited aging analyses are discussed in Section 4.3.

3.2.1.02 Components in Loss of material Plant specific Yes, plant The applicable FCS components, materi containment spray due to general specific als and environments identified in (PWR only), standby corrosion NUREG-1801 are discussed in row num gas treatment (BWR ber 3.2.1.06 of this table.

only), containment isolation, and emergency core cooling systems Page 3-38 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-38

FORT CALHOUiv oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Management Further Discussion Number Component Mechanism Programs Evaluation Recommended 3.2.1.03 Components in Loss of material Plant specific Yes, plant 1. The FCS aging management review containment spray due to pitting and specific results are consistent with those (PVVR only), standby crevice corrosion reviewed and approved in NUREG gas treatment (BWR 1801.

only), containment 2. The Chemistry Program (B.1.2) isolation, and supplemented by the One Time emergency core Inspection Program (B.3.5) to verify the cooling systems effectiveness of the Chemistry Program's management of the aging effects of these components. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1801, this group only includes stainless steel in oxygenated treated water for components in containment isolation at FCS.

3.2.1.04 Containment isolation Loss of material Plant specific Yes, plant No FCS containment isolation valves and valves and due to specific associated piping in systems that are not associated piping microbiologically addressed in this or other sections of this influenced application were determined to be subject corrosion to the aging effect of loss of material due to microbiologically influenced corrosion 3.2.1.05 High pressure safety Loss of material Plant specific Yes, plant The component identified in NUREG-1801 injection (charging) due to erosion specific is not applicable to FCS.

pump miniflow orifice AGING MANAGEMENT REVIEW Revision I Page 3-39

FORT CALHOUI- . iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Management Further Discussion Number Component Mechanism Programs Evaluation Recommended 3.2.1.06 External surface of Loss of material Plant specific Yes, plant 1. The FCS aging management review carbon steel due to general specific results are consistent with those components corrosion reviewed and approved in NUREG 1801.

2. The General Corrosion of External Surfaces Program (B.3.3) manages the This row is only found aging effects of these components.

in Table 2 of This program is described in Appendix NUREG-1801, B of this application.

Volume 1. It is not 3. Consistent with NUREG-1 801, this found in Table 3.2-1 group includes carbon steel of NUREG-1800. components in ambient air at FCS.

3.2.1.07 Piping and fittings of Loss of fracture Thermal aging No The material identified in NUREG-1801 is CASS in emergency toughness due to embrittlement of not applicable to FCS. CASS piping and core cooling system thermal aging CASS fittings are not used in the ESF systems at embrittlement FCS.

3.2.1.08 Components Local loss of Open-cycle cooling No The FCS ESF components are not serviced by open- material due to water system serviced by open-cycle cooling system.

cycle cooling system corrosion and/or buildup of deposits due to biofouling Page 3-40 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision II Revision Page 3-40

FORT CALHOt.,. oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Management Further Discussion Number Component Mechanism Programs Evaluation Recommended 3.2.1.09 Components Loss of material Closed-cycle cooling No 1. The aging management results are serviced by closed- due to general, water system consistent with the results documented cycle cooling system pitting, and in NUREG-1801.

crevice corrosion 2. Consistent with NUREG-1801, this group includes stainless steel, carbon steel and cast iron in corrosion inhibited treated water at FCS.

3.2.1.10 Pumps, valves, Crack initiation Water chemistry No 1. The aging management results are piping, and fittings in and growth due consistent with the results documented containment spray to SCC in NUREG-1801.

and emergency core 2. Consistent with NUREG-1 801, this cooling systems group includes stainless steel and stainless steel clad carbon steel in chemically treated borated water at FCS.

3.2.1.11 Carbon steel Loss of material Boric acid corrosion No 1. The aging management results are components due to boric acid consistent with the results documented corrosion in NUREG-1801.

2. Consistent with NUREG-1 801, this group includes carbon and low alloy steel at FCS.

Page 3-41 AGING MANAGEMENT REVIEW AGING Revision I1 Revision Page 3-41

FORT CALHOUi. .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ENGINEERED SAFETY FEATURES EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Management Further Discussion Number Component Mechanism Programs Evaluation Recommended 3.2.1.12 Closure bolting in Loss of material Bolting integrity No 1. The aging management results are high pressure or high due to general consistent with the results documented temperature systems corrosion, loss of in NUREG-1801.

preload due to 2. Consistent with NUREG-1801, this stress relaxation, group includes carbon and low alloy and crack steel in ambient air at FCS.

initiation and growth due to cyclic loading or SCC Page 3-42 AGING MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-42

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.2.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 Table 3.2-2 contains Engineered Safety Features Systems aging management review results that are not addressed in NUREG-1 801. This table includes the component types, materials, environments, and aging effects requiring management, and the programs and activities for managing aging. Table 3.2-3 contains components in Engineered Safety Features not evaluated in NUREG-1801 that rely on aging management programs in NUREG-1 801 for FCS License Renewal and the justification for the use of these programs.

Page 3-43 Revision I AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision 1 Page 3-43

FORT CALHOU.. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-2 FCS ENGINEERED SAFETY FEATURES COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.2.2.01 Heat Exchanger - Tubes Alloy 600 Chemically Treated Loss of Material Chemistry Program Borated Water Crevice corrosion in the (B.1.2) presence of sufficient levels of oxygen, halogens, sulfates, or copper 3.2.2.02 Heat Exchanger - Tubes Alloy 600 Chemically Treated Cracking Chemistry Program Borated Water Stress Corrosion Cracking (B.1.2) due to exposure to halogens or sulfates 3.2.2.03 Heat Exchanger - Tubes Alloy 600 Corrosion-Inhibited Loss of Material Chemistry Program Treated Water

• Crevice and pitting cor- (B.1.2) and Cooling rosion in the presence Water Corrosion of sufficient levels of Program (B.2.2) oxygen, halogens, or sulfates MIC due to exposure to microbiological activity 3.2.2.04 External surface of Stainless Steel Ambient Air None Not Applicable stainless steel components AGING MANAGEMENT REVIEW Revision I Page 3-44

FORT CALHOU,..,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-2 (CONTINUED)

FCS ENGINEERED SAFETY FEATURES COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.2.2.05 Filter/Strainers Galvanized Steel Containment Air Loss of Material Period Surviellance

"* Crevice corrosion and Preventive where crevices exist Maintenance that allow a corrosive Program environment to develop

"* General corrosion where both oxygen and moisture are present 3.2.2.06 Heat Exchanger - Shell Cast Iron Corrosion-Inhibited Loss of Material Selectrive Leaching Treated Water Selective leaching due to Program the exposure of cast iron to dissolved oxygen 3.2.2.07 Valve, Pipes & Fittings Carbon Steel Dry Air/Gas None Not Applicable Page 3-45 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-45

FORT CALHOUN oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.2-3 COMPONENTS IN ENGINEERED SAFETY FEATURES NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCS Applicable Justification for applying Row Components Material Environment Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.2.3.01 Safety injection Stainless Chemically Crack Chemistry 3.2.1.10 The FCS components are tanks, flow steel Treated initiation and Program made of the same material, element and Borated Water growth I (B.1.2) exposed to the same orifice bodies, Stress environment, subject to the orifice plate, corrosion same aging effects and tubing and heat cracking managed by the same aging exchangers management program as the components evaluated in NUREG-1801, Volume 2, V.D1.1-a 3.2.3.02 Leakage Carbon Chemically Crack Chemistry 3.2.1.10 The FCS components are accumulators steel with Treated initiation and Program made of the same material, stainless Borated Water growth I (B.1.2) exposed to the same steel Stress environment, subject to the cladding corrosion same aging effects and cracking managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, V.D1.7-b Page 3-46 AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-46

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.3 AGING MANAGEMENT OF AUXILIARY SYSTEMS The Auxiliary Systems consist of the following systems and components:

"* Spent Fuel Pool Cooling System

"* Fuel Handling and Heavy Load Cranes (including New and Spent Fuel Storage Racks)

"* Raw Water System (Open Cycle Cooling Water System in NUREG-1801)

"* Component Cooling Water System (Closed Cycle Cooling Water System in NUREG 1801)

"* Chemical and Volume Control System

"* Instrument Air System

"* Nitrogen Gas System

"* Control Room HVAC and Toxic Gas Monitoring System

"* Auxiliary Building HVAC System

"* Containment HVAC System

"* Ventilating Air System (includes Diesel Generator rooms)

"* Fire Protection System including the Fire Protection Fuel Oil System

"* Diesel Generator Fuel Oil System and Auxiliary Boiler Fuel Oil System

"* Diesel Generator System including the Diesel Jacket Water System, the Diesel Gen erator Lube Oil System, and the Diesel Generators Starting Air System

"* Primary Sampling System

"* Liquid Waste Disposal System

"* Gaseous Waste Disposal System

"* Radiation Monitoring-Mechanical Components The Spent Fuel Pool Cooling System consists of a stainless steel lined storage pool, two storage pool circulation pumps, a storage pool heat exchanger, a demineralizer and filter, two fuel transfer canal drain pumps, piping, and manual valves. The pool concrete and liner are evaluated with the Auxiliary Building.

The Fuel Handling and Heavy Load Cranes System consists of the refueling machine, tilting machines in the Auxiliary Building and in Containment, fuel transfer conveyor, fuel transfer carrier box, fuel transfer tube, new and spent fuel handling tools, new and spent fuel storage racks, thirty-six (36) cranes of varying types (i.e., polar crane, overhead crane, hoist with monorail, and jib crane) and three (3) elevators.

The Raw Water (RW) system is an open-cycle cooling water system which uses screened water from the Missouri River. The system includes four parallel vertical mixed flow pumps installed in the Intake Structure pump house. The pumps discharge into an interconnected header which splits into two parallel supply headers. The two supply headers run underground from the Intake Structure to the Auxiliary Building, where they join in an interconnected inlet header to the four Component Cooling Water (CCW) heat exchangers. Downstream of the CCW heat exchangers, the Raw Water discharge header runs through the Turbine Building and discharges to the river.

AGING MANAGEMENT REVIEW Revision 1 Page 3-47

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The Component Cooling Water System is a closed loop system used to transfer heat from various components carrying radioactive or potentially radioactive fluids to the raw water. This system consists of three motor driven circulating pumps, four heat exchangers, a surge tank, valves, and piping. The water in the system is demineralized and deaerated and an inhibitor is added for protection against corrosion.

The Chemical and Volume Control System includes one regenerative heat exchanger, one letdown heat exchanger, five ion exchangers, one volume control tank, three positive-displacement charging pumps, one boric acid batching tank, two boric acid storage tanks, two centrifugal boric acid transfer pumps, and one chemical addition tank.

The Instrument Air System provides oil-free, filtered, and dried air for pneumatic controls, instrumentation, and the actuation of valves, dampers and similar devices. Instrument Air is distributed to the various pneumatic components it serves through a network of supply headers and distribution risers. The Instrument Air System also feeds the suction of the compressors for the Diesel Starting Air system. Backup accumulators containing instrument air or nitrogen are provided on selected pneumatic devices to ensure their operability if instrument air pressure drops.

The Nitrogen Gas System provides compressed nitrogen gas to the Safety Injection Tanks and provides a gas blanket to various vessels and contained areas of the plant.

The Control Room HVAC and Toxic Gas Monitoring System consists of two air conditioning units; two outside air filter units, each with its own supply fan; an outside air intake plenum; and distribution ductwork.

The Auxiliary Building HVAC System is a once-through, non-recirculating type using supply and exhaust fans. Portions of the Auxiliary Building HVAC System may be utilized to purge hydrogen from the containment.

The Containment HVAC System provides ventilation and cooling of the containment.

Containment HVAC consists of four separate sub-systems. These sub-systems provide containment air re-circulation, cooling, nuclear detector well cooling, containment purge, and hydrogen purge.

The Ventilating Air System passive equipment is contained within the Emergency Diesel Generator rooms.

The Fire Protection System water supply system has two vertical turbine type fire pumps.

One fire pump is driven by an electric motor and the other fire pump is driven by a diesel engine. Both pumps deliver screened and strained Missouri River water to the underground water distribution system, which in turn supply the automatic water fire I Page 3-48 REVIEW MANAGEMENT REVIEW Revision Revision 1 AGING MANAGEMENT AGING Page 3-48

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION suppression systems, interior hose stations and fire hydrants in the yard. An independent underground looped yard main system capable of delivering sprinkler flow plus adequate hose flow to support manual fire fighting for a single fire is provided for the Fire Protection System.

Four safety related plant areas are provided with automatic halon 1301 extinguishing systems. These areas include the Cable Spreading Room, both Switchgear Rooms and the Control Room cabinets. The plant is divided into unique fire areas as required by Appendix A to NRC Branch Technical Position APCSB 9.5-1, and 10CFR 50, Appendix R. Walls enclosing separate fire areas utilize fire resistive construction. Openings in plant fire barriers are protected by rated fire doors, fire dampers, and fire barrier penetration seals. Portable fire extinguishers are identified in the Fire Hazards Analysis as being provided throughout the station, generally in accordance with NFPA 10. Fire extinguishers, fire hoses, and air packs are not subject to an aging management review because they are replaced based on condition in accordance with applicable NFPA standards and plant procedures for fire protection equipment. This position is consistent with the NRC Staff s guidance on consumables, which has been incorporated into NEI 95-10 Revision 2.

RCP lube oil collection neoprene hoses will be replaced on condition in accordance with the Period Surveillance and Preventive Maintenance Program. These hoses provide a gravity drain of RCP lube oil from the collection pans to the lube oil collection tanks. The hoses are not pressurized and do not normally contain fluid.

The Fire Protection Fuel Oil System supplies the sole source of fuel oil to the diesel engine fire pump. The unit is located at the north end of the Intake Structure. A 10-gallon fuel oil day tank for the diesel engine is located adjacent to the engine. Fuel is transferred from the 550-gallon diesel fire pump fuel oil tank to the day tank.

The Diesel Generator Fuel Oil System provides fuel to the emergency diesel generators in the proper amount to maintain engine speed and load. An 18,000 gallon underground storage tank serves both engines. Two transfer pumps for each diesel transfer fuel from the underground storage tank to the wall-mounted auxiliary tank. Fuel gravity drains from the wall mounted tank to the engine base tank. One engine-driven fuel oil pump and one motor driven fuel oil pump delivers fuel to the engine fuel injectors. Warehoused components include a portable hand pump, a rubber hose and hose couplings. These components will be replaced on performance or condition in accordance with the Periodic Surveillance and Preventive Maintenance Program. These components contribute to the first intended function listed above, involving the transfer of diesel fuel from the auxiliary boiler fuel oil storage tank to the diesel engine fuel oil storage tank.

The components are normally not pressurized and normally do not contain fluid. The Auxiliary Boiler Fuel Oil System consists of a fuel oil transfer pump, piping, filters, instrumentation and warehoused equipment for delivery of fuel oil from the auxiliary boiler fuel oil storage tank to the diesel engine fuel oil storage tank.

I Page 3-49 REVIEW Revision 1 AGING MANAGEMENT REVIEW AGING Revision Page 3-49

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The Diesel Generator System includes emergency diesel generators designed to furnish reliable in-plant ac power when power is not available from the 345 or 161-kV systems.

Each emergency diesel generator is provided with an exhaust silencer and auxiliaries.

Each emergency diesel generator interfaces with an integral cooling system, two air starting systems, a lubricating system, two fuel systems between the engine mounted fuel oil tanks and the engine fuel lines. Both emergency diesel generators are supplied fuel from a common, underground fuel oil storage tank by redundant transfer pumps.

Immersion heaters are provided to maintain engine jacket water and lubricating oil temperatures at desirable temperatures for quick, reliable starting. The emergency diesel generators are located in separate rooms of the Auxiliary Building.

The Diesel Jacket Water System provides cooling to the engine. Each engine has its own self contained radiator type cooling system. Two different coolant mixtures are used in the diesels. For DG-1 a glycol based coolant mixture is used during the winter months with the coolant mixture being changed out to a nitrite based coolant mixture during the summer to ensure the rating of the generator. DG-2 uses a glycol based coolant mixture year round. The Diesel Generator Lube Oil System lubricates the diesel engine components and filters the engine lube oil. The Diesel Generators Starting Air System provides stored pressurized air for starting the emergency diesel generators. Each tank has the capacity for five starts of the diesel (combining for a total of ten emergency starts).

The Primary Sampling system includes the primary sampling panel, the CVCS panel, the steam generator blowdown analyzer rack, the instrument panel, steam generator blowdown sample chiller, and the manual sampling sink and hood.

The Liquid Waste Disposal system is used to collect, store, prepare for disposal, and dispose of liquid radioactive wastes. Radioactive liquid wastes are generated as a result of plant operation, repair, and maintenance activities.

The Gaseous Waste Disposal System includes the containment isolation valves that close on a Containment Isolation Actuation Signal (CIAS) and the piping between the containment penetrations and the containment isolation valves. Also included are the waste gas compressor seal water heat exchangers that receive cooling water from the Component Cooling Water System.

The Radiation Monitoring-Mechanical Components System consists of the mechanical portions of the radiation monitors and their supporting components.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience AGING MANAGEMENT REVIEW Revision I Page 3-50

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION were consistent with those identified in NUREG-1801.

Industry: A review of industry-wide operating experience was conducted to identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

3.3.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.3-1 shows the aging management programs evaluated in NUREG-1801 that are relied on for license renewal of the Auxiliary Systems at FCS. Note that this table only includes those components, materials and environments that are applicable to a PWR.

Information on FCS-specific components and materials, not listed in NUREG-1801 but included in the component group of this application, is included in the discussion column.

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FORT CALHO6.. .TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect] Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.01 Components in Loss of material Water Yes, detection of The material identified in NUREG-1801 is not spent fuel pool due to general, chemistry aging effects is to applicable to FCS. These components are cooling and pitting, and crevice and one-time be further addressed in Section 3.3.2 of this application.

cleanup corrosion inspection evaluated 3.3.1.02 Linings in spent Hardening, Plant specific Yes, plant specific 1. The FCS aging management review results fuel pool cooling cracking and loss are consistent with those reviewed and and cleanup of strength due to approved in NUREG-1801.

system; seals and elastomer 2. The General Corrosion of External Surfaces collars in degradation; Program (B.3.3) manages this aging effect.

ventilation systems loss of material due This program is described in Appendix B of to wear this application.

3. Consistent with NUREG-1801, this group only includes elastomer seals in the ventilation systems exposed to ambient air at FCS.

3.3.1.03 Components in Cumulative fatigue TLAA, Yes, TLAA 1. The FCS aging management review results load handling, damage evaluated in are consistent with those reviewed and chemical and accordance approved in NUREG-1801 for the chemical volume control with 10 CFR and volume control and primary sampling system (PWR), 54.21(c) systems.

and reactor water 2. The metal fatigue time limited aging cleanup and analyses are discussed in Section 4.3.1 of shutdown cooling this application.

systems (older BWR)

Revision II Page 3-52 AGING AGING MANAGEMENT REVIEW MANAGEMENT REVIEW Revision Page 3-62

FORT CALHObI.. .,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.04 Heat exchangers in Crack initiation and Plant specific Yes, plant specific 1. The FCS aging management review results reactor water growth due to SCC are consistent with those reviewed and cleanup system or cracking approved in NUREG-1801.

(BWR); high 2. The Chemistry (B.1.2) and One-Time pressure pumps in Inspection Programs (B.35) manage this chemical and aging effect. One-Time Inspection will be volume control conducted prior to the period of extended system (PWR) operation to confirm the effectiveness of the Chemistry Program. This program is described in Appendix B of this application.

3. Consistent with NUREG-1801, this group includes stainless steel in chemically treated borated water at FCS.

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FORT CALHOU,,. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.05 Components in Loss of material Plant specific Yes, plant specific 1. The FCS aging management review results ventilation due to general, are consistent with those reviewed and systems, diesel pitting, and crevice approved in NUREG-1801.

fuel oil system, and corrosion, and MIC 2. The Periodic Surveillance and Preventive emergency diesel Maintenance (B.2.7), General Corrosion of generator systems; External Surfaces (B.3.3), and Fire external surfaces Protection Programs (B.2.5) manage this of carbon steel aging effect. These programs are described components in Appendix B of this application. The FCS Fire Protection Program provides guidance for detecting loss of material due to general, pitting, crevice, and microbiologically influenced corrosion (MIC).

3. Consistent with NUREG-1 801, this group includes carbon steel, galvanized steel, and copper inair, and carbon steel in diesel engine exhaust gases at FCS.

Revision II Page 3-54 AGING AGING MANAGEMENT MANAGEMENT REVIEWREVIEW Revision Page 3-54

FORT CALHOUi,. oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.06 Components in Loss of material One-time Yes, detection of 1. The FCS aging management review results reactor coolant due to galvanic, inspection aging effects is to are consistent with those reviewed and pump oil collect general, pitting, and be further approved in NUREG-1801.

system of fire crevice corrosion evaluated 2. The One-Time Inspection Program (B.3.5) protection manages this aging effect. These inspections will be conducted prior to the period of extended operation. This program is described in Appendix B of this application.

3. Consistent with NUREG-1 801, this group includes copper in lubricating oil at FCS.

Revision I Page 3-55 MANAGEMENT REVIEW AGING MANAGEMENT AGING REVIEW Revision I Page 3-55

FORT CALHOU,, iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.07 Diesel fuel oil tanks Loss of material Fuel oil Yes, detection of 1. The FCS aging management review results in diesel fuel oil due to general, chemistry and aging effects is to are consistent with those reviewed and system and pitting, and crevice one-time be further approved in NUREG-1801.

emergency diesel corrosion, MIC, and inspection evaluated 2. The Diesel Fuel Monitoring and Storage generator system biofouling Program (B2.3) manages this aging effect.

This program is described in Appendix B of this application. Diesel Fuel Monitoring and Storage Program includes the Fuel Oil Chemistry Program at FCS. The Diesel Fuel Monitoring and Storage Program includes measures to verify the effectiveness of the fuel oil chemistry control. These inspections will be conducted prior to the period of extended operation to confirm the effectiveness of the oil chemistry control.

3, Consistent with NUREG-1 801, this group includes carbon steel in fuel oil at FCS.

AGING MANAGEMENT REVIEW Revision 1 Page 3-56

FORT CALHOLJ,. ..TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.08 Heat exchangers in Crack initiation and Water Yes, plant specific 1. The FCS aging management review results chemical and growth due to SCC chemistry and a are consistent with those reviewed and volume control and cyclic loading plant-specific approved in NUREG-1801.

system verification 2. The Chemistry Program (B.1.2) verified by program the One-Time Inspection Program (B.3.5),

Cooling Water Corrosion Program (B.2.2) and Periodic Surveillance and Preventive Maintenance Program (B.2.7) manage this aging effect. Inspections will be conducted prior to the period of extended operation to confirm the effectiveness the Chemistry Program. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1 801, this group includes stainless steel in chemically treated borated and corrosion inhibited treated water at FCS.

AGING MANAGEMENT REVIEW Revision I Page 3-57

FORT CALHOULd TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.09 Neutron absorbing Reduction of Plant specific Yes, plant specific 1. The FCS aging management review results sheets in spent fuel neutron absorbing are consistent with those reviewed and storage racks capacity and loss of approved in NUREG-1801.

material due to 2. The Periodic Surveillance and Preventive general corrosion Maintenance Program (B.2.7) manages (Boral, boron steel) this aging effect. This program is described in Appendix B of this application. The surveillance test evaluates the neutron absorbing samples for dimensional change, weight change, neutron attenuation change and specific gravity change.

3. Consistent with NUREG-1801, this group includes Boral encapsulated in stainless steel in chemically treated borated water at FCS.

3.3.1.10 New fuel rack Loss of material Structures No 1. The FCS aging management review results assembly due to general, monitoring are consistent with those reviewed and pitting, and crevice approved in NUREG-1801.

corrosion 2. Consistent with NUREG-1801, this group includes carbon steel in ambient air at FCS.

3.3.1.11 Spent fuel storage Crack initiation and Water No 1. The aging management results are racks and valves in growth due to chemistry consistent with those reviewed and spent fuel pool stress corrosion approved in NUREG-1801.

cooling and cracking 2. Consistent with NUREG-1 801, this group cleanup includes stainless steel in borated treated water at FCS.

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FORT CALHOU.. ,jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.12 Neutron absorbing Reduction of Boraflex No The material identified in NUREG-1801 is not sheets in spent fuel neutron absorbing monitoring applicable to FCS.

storage racks capacity due to Boraflex degradation 3.3.1.13 Closure bolting and Loss of material Boric acid No 1. The aging management results are external surfaces due to boric acid corrosion consistent with those reviewed and of carbon steel and corrosion approved in NUREG-1801.

low-alloy steel 2. Consistent with NUREG-1801, this group components includes carbon and low alloy steel in air exposed to leaking and dripping borated treated water at FCS.

3.3.1.14 Components in or Loss of material Closed-cycle No 1. The aging management results are serviced by closed- due to general, cooling water consistent with those reviewed and cycle cooling water pitting, and crevice system approved in NUREG-1801.

system corrosion, and MIC 2. Consistent with NUREG-1801, this group includes carbon steel and stainless steel in chemically treated corrosion inhibited water at FCS.

3.3.1.15 Cranes including Loss of material Overhead No 1. The aging management results are bridge and trolleys due to general heavy load and consistent with those reviewed and and rail system in corrosion and wear light load approved in NUREG-1801.

load handling handling 2. Consistent with NUREG-1 801, this group system systems includes carbon steel in ambient air at FCS.

AGING MANAGEMENT REVIEW Revision I Page 3-59

FORT CALHOL. - .,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.16 Components in or Loss of material Open-cycle No 1. The aging management results are serviced by open- due to general, cooling water consistent with the results documented in cycle cooling water pitting, crevice, and system NUREG-1801.

systems galvanic corrosion, 2. Consistent with NUREG-1 801, this group MIC, and includes carbon steel, bronze, cast iron and biofouling; buildup stainless steel in raw water at FCS.

of deposits due to biofouling 3.3.1.17 Buried piping and Loss of material Buried piping No 1. The aging management results are fittings due to general, and tanks consistent with the results documented in pitting, and crevice surveillance NUREG-1801.

corrosion, and MIC 2. The aging effects are managed by the or Buried Surfaces External Corrosion Yes, detection of Program (B.3.2) and the Fire Protection Buried piping aging effects and Program (B.2.4 ) described inAppendix B and tanks operating of this application. The aging management inspection experience are to activities of the Fire Protection Program are be further the same as those of the Buried Surfaces evaluated External Corrosion Program.

3. Consistent with NUREG-1801, this group includes carbon steel in soil at FCS.

3.3.1.18 Components in Loss of material Compressed air No The environment identified in NUREG-1 801 is compressed air due to general and monitoring not applicable to FCS. Components in the system pitting corrosion instrument air system at FCS are exposed to dry air.

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FORT CALHOt,. 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.19 Components Loss of material Fire protection No 1. The aging management results are (doors and barrier due to wear; consistent with those reviewed and penetration seals) hardening and approved in NUREG-1801.

and concrete shrinkage due to 2. Consistent with NUREG-1801, this group structures in fire weathering includes carbon steel and sealant in protection ambient air at FCS.

3.3.1.20 Components in Loss of material Fire water No 1. The aging management results are water-based fire due to general, system consistent with those reviewed and protection pitting, crevice, and approved in NUREG-1801.

galvanic corrosion, 2. Consistent with NUREG-1801, this group MIC, and biofouling includes carbon steel, cast iron, stainless steel, and bronze in raw water at FCS.

3.3.1.21 Components in Loss of material Fire protection No 1. The aging management results are diesel fire system due to galvanic, and fuel oil consistent with those reviewed and general, pitting, and chemistry approved in NUREG-1801.

crevice corrosion 2. Consistent with NUREG-1801, this group includes carbon steel in fuel oil at FCS.

3.3.1.22 Tanks in diesel fuel Loss of material Above ground No The components identified in NUREG-1801 oil system due to general, carbon steel are not applicable to FCS.

pitting, and crevice tanks corrosion Page 3-61 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision II Revision Page 3-61

FORT CALHO i, ,,jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR AUXILIARY SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Effect/ Aging Further Discussion Number Component Mechanism Management Evaluation Programs Recommended 3.3.1.23 Closure bolting Loss of material Bolting integrity No 1. The aging management results are due to general consistent with those reviewed and corrosion; crack approved in NUREG-1801.

initiation and 2. Consistent with NUREG-1801, this group growth due to cyclic includes carbon steel and low alloy steel in loading and SCC ambient air at FCS.

3.3.1.24 Components Loss of material Selective No 1. The aging management results are (aluminum bronze, due to selective leaching of consistent with those reviewed and brass, cast iron, leaching materials approved in NUREG-1801.

cast steel) in open- 2. Consistent with NUREG-1 801, this group cycle and closed- includes cast iron and bronze in raw water cycle cooling water and soil at FCS.

systems, and ultimate heat sink 3.3.1.25 Fire barriers, walls, Concrete cracking Fire protection No 1. The aging management results are ceilings and floors and spalling due to and structures consistent with the results documented in in fire protection freeze-thaw, monitoring NUREG-1801.

aggressive 2. Consistent with NUREG-1801, this group chemical attack, includes concrete in ambient air at FCS.

and reaction with aggregates; loss of material due to corrosion of embedded steel Revision II Page 3-62 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision Page 3-62

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.3.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 Table 3.3-2 contains Auxiliary Systems aging management review results that are not addressed in NUREG-1801. This table includes the component types, materials, environments, and aging effects requiring management, and the programs and activities for managing aging. Table 3.3-3 contains components in Auxiliary Systems not evaluated in NUREG-1801 that rely on aging management programs in NUREG-1801 for FCS License Renewal and the justification for the use of these programs.

I Page 3-63 MANAGEMENT REVIEW Revision 1 Revision AGING MANAGEMENT AGING REVIEW Page 3-63

FORT CALHOU,. ,jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.01 External surfaces of aluminum components Aluminum Ambient Air None Not Applicable 3.3.2.02 Filter/Strainer housing, valve bodies Aluminum Fuel Oil Loss of Material Diesel Fuel Monitoring

" MIC due to the potential and Storage Program for microorganism intro- (B2.3) duction and moisture contamination during bulk fuel oil supply and delivery

" Pitting/Crevice/General Corrosion due to poten tial for water contamina tion and water pooling in a fuel oil system 3.3.2.03 Not used in application 3.3.2.04 Filter/Strainer housing, Valve Operators, Aluminum Instrument Air None Not Applicable Valve bodies 3.3.2.05 Valve bodies Aluminum Gas - Nitrogen None Not Applicable 3.3.2.06 Switch/Bistable housing Aluminum Raw Water Loss of Material Fire Protection Crevice and pitting Program (B.2.5) corrosion and MIC due to stagnant conditions RevIsIon II Page 3-84 AGING MANAGEMENT REVIEW AGING REVIEW Revision Page 3-64

FORT CALHOb.. TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.07 New and spent fuel handling tools Aluminum Occasionally Cracking Chemistry Program exposed to Stress corrosion cracking (B,1.2)

Treated Water (SCC) due to the exposure

-Borated of aluminum to halogens and stress 3.3.2.08 New and spent fuel handling tools Aluminum Occasionally Loss of Material Chemistry Program exposed to

• Pitting corrosion due to (B.1.2)

Treated Water the exposure of alumi

-Borated num to halogens and sulfates

"* Galvanic corrosion due to aluminum in contact with stainless steel and exposed to halogens

"* Exfoliation due to the exposure of aluminum to halogens 3.3.2.09 Subcomponent - new fuel storage rack - Boral Ambient Air None Not Applicable boral sheets 3.3.2.10 External surfaces of brass or bronze Brass or Ambient Air None Not Applicable components Bronze Page ;5-e AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision II Revision Page 3-6,5

FORT CALHOU,. jTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.11 Valve bodies, filters/strainer housing, pump Brass or Fuel Oil Loss of Material Diesel Fuel Monitoring casings Bronze

• MIC due to the potential and Storage Program for microorganism intro- (B.2.3) duction and moisture contamination during bulk fuel oil supply and delivery Pitting/Crevice/General Corrosion due to poten tial for water contamina tion and water pooling in a fuel oil system 3.3.2.12 Valve bodies Brass Gas - Halon None Not Applicable 3.3.2.13 Valve bodies Brass or Gas - None Not Applicable Bronze Instrument Air 3.3.2.14 Valve bodies Brass or Gas - Nitrogen None Not Applicable Bronze 3.3.2.15 Valve bodies Brass Gas - None Not Applicable Refrigerant (Liquid) 3.3.2.16 Heat exchanger Brass or Lubricating Oil Loss of Material Cooling Water Bronze General corrosion due to Corrosion Program the possibility for water (B.2.2) contamination and water pooling AGING MANAGEMENT REVIEW Revision I Page 3-66

FORT CALHOUI. iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.17 Heat exchanger Brass Corrosion- Cracking Cooling Water Inhibited Due to SCC because of the Corrosion Program Treated ammonium compounds (B.2.2)

Water present in the water due to and Chemistry the nitrite corrosion inhibitor Program (B.1.2) 3.3.2.18 Heat exchanger Brass, Corrosion- Loss of Material Cooling Water Copper Inhibited

• Crevice and pitting cor- Corrosion Program Alloy Treated rosion due to potential (B.2.2)

Water stagnant or low flow and Chemistry conditions Program (B. 1.2)

"* Galvanic corrosion due to the high conductivity of the process fluid and the presence of dissimi lar metals in contact

"* MIC due to the exposure of copper alloy to micro biological activity 3.3.2.19 Switch/Bistable housing Brass Raw Water Loss of Material Fire Protection

"* Crevice and pitting cor- Program (B.2.5) rosion and MIC due to stagnant conditions

"* Galvanic corrosion due to the conductivity of the process fluid and the presence of dissimilar metals in contact Revision II Page 3-87 AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision Page 3-67

FORT CALHOL . jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.20 Valve bodies Cadmium Gas - None Not Applicable Plated Steel Instrument Air 3.3.2.21 Pipes & fittings Carbon Above Loss of Material Diesel Fuel Monitoring Steel ground, buried External surface corrosion and Storage Program in gravel and due to the potential for the (B.2.3) protected from existence of sufficient the elements oxygen, moisture levels, and/or soil contaminants 3.3.2.22 Pipes & fittings Carbon Concrete None Not Applicable Steel 3.3.2.23 Filter/Strainer housing, heat exchangers, Carbon Gas - None Not Applicable lubricator motors, pipes & fittings, tanks, Steel Instrument valve bodies, accumulators, valve operators Air 3.3.2.24 Pipes and fittings Carbon Gas - None Not Applicable Steel Hydrogen 3.3.2.25 Valve bodies, accumulators, pipes &fittings Carbon Gas - Nitrogen None Not Applicable Steel 3.3.2.26 Pipes & fittings, valves Carbon Concrete None Not Applicable Steel or Cast Iron Page 3-68 AGING AGING MANAGEMENT REVIEWREVIEW Revision II Revision Page 3-68

FORT CALHOUk. *TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.27 Heat exchanger - shell Carbon Oxygenated Loss of Material Chemistry Program Steel Treated Water

• General and crevice cor- (B.1.2) and Cooling

<200 deg F rosion due to dissolved Water Corrosion oxygen Program (B.2.2)

"* Pitting corrosion due to halogens

"* Galvanic corrosion due to the conductivity of the process fluid and the presence of dissimilar metals in contact 3.3.2.28 Valve bodies Cast Iron Gas - None Not Applicable Refrigerant (Liquid) 3.3.2.29 Pump casings, valve bodies, pipes & fittings, Cast Iron Corrosion- Loss of Material Chemistry Program heat exchanger - channel/channel head Inhibited

• General and crevice cor- (B.1.2) and Cooling Treated Water rosion due to the expo- Water Corrosion sure of cast iron to Program (B.2.2) dissolved oxygen

. Pitting corrosion due to exposure to halogens 3.3.2.30 Pump casings, valve bodies, pipes &fittings Cast Iron Corrosion- Loss of Material Selective Leaching Inhibited Selective leaching due to Program (B.3.6)

Treated Water the exposure of cast iron to dissolved oxygen AGING MANAGEMENT REVIEW Revision I Page 3-69

f FORT CALHOL~h oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.31 Valve bodies, pipes &fittings Cast Iron Buried in Loss of Material The Fire Protection Ground

• General corrosion due Program (B.2.5) to exposure to dis- governs implementing solved oxygen procedures that

° Selective leaching due provide reasonable to the exposure of cast assurance the Fire iron to dissolved oxygen Protection System pressure-retaining components will be adequately managed by specific performance and/or condition monitoring activities in accordance with Current Licensing Basis requirements.

3.3.2.32 Tanks, pipes &fittings, filter/strainers, valves Coated Fuel Oil Loss of Material Diesel Fuel Monitoring Carbon

• MIC due to the potential and Storage Program Steel, Cast for microorganism intro- (B.2.3)

Iron, duction and moisture Stainless contamination during Steel, bulk fuel oil supply and Galvanized delivery Steel

• Pitting/Crevice/General Corrosion due to poten tial for water contamina tion and water pooling in a fuel oil system AGING MANAGEMENT REVIEW Revision I Page 3-70

FORT CALHOUi. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.33 Pressure vessels Coated Gas - Halon None Not Applicable Carbon (Liquid)

Steel 3.3.2.34 Pipes & fittings Concrete Buried in None Not Applicable Ground 3.3.2.35 Pipes & fittings Concrete Raw Water None Not Applicable 3.3.2.36 Safety Injection Refueling Water Tank Concrete Treated Water Loss of Material Structures Monitoring (SIRWT) with coated - Borated Due to exposure of the Program (B.2.10) carbon steel material to moisture, liner contaminants, dissolved oxygen, and boric acid (i.e.,

general corrosion, crevice corrosion, pitting corrosion, boric acid corrosion and galvanic corrosion) 3.3.2.37 Pipes & fittings, tubing Copper, Gas - None Not Applicable Copper Instrument Air Alloy, Copper Zinc Alloy 3.3.2.38 Valve bodies, pipes & fittings, heat Copper, Gas - None Not Applicable exchanger tubes Copper Refrigerant Alloy Page 3-71 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-71

FORT CALHOUt. .JTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.39 Heat exchangers, valves Brass, Corrosion- Loss of Material Cooling Water Copper, Inhibited

• Crevice and pitting cor- Corrosion Program Copper Treated Water rosion due to potential (B,2.2)

Alloy stagnant or low flow and Chemistry conditions Program (B.1.2)

"° Galvanic corrosion due to the high conductivity of the process fluid and the presence of dissimi lar metals in contact

"* MIC due to the exposure of copper alloy to micro biological activity 3.3.2.40 External surfaces of brass, bronze, copper, Brass, Ambient Air None Not Applicable copper alloy or copper-zinc alloy components Bronze, Copper, Copper Alloy, Copper Zinc Alloy 3.3.2.41 Heat exchangers, valves Copper Corrosion- Cracking Cooling Water Alloy Inhibited Due to SCC because of the Corrosion Program Treated Water ammonium compounds (B2.2) and Chemistry present in the water due to Program (B.1.2) the nitrite corrosion inhibitor Revision I Page 3-72 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision I Page 3-72

FORT CALHOOI,, jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.42 Tubing Copper- Buried in Loss of Material Buried Surfaces Zinc Alloy Ground General and pitting corro- External Corrosion sion due to the potential for Program (B.3.2) the existence of sufficient oxygen, moisture levels, and/or soil contaminants 3.3.2.43 Tubing Copper- Buried in Loss of Material Selective Leaching Zinc Alloy Ground Due to dezincification Program (B.3.6) 3.3.2.44 Tubing Copper- Above Loss of Material Diesel Fuel Monitoring Zinc Alloy ground, buried General and pitting corro- and Storage Program in gravel and sion due to the potential for (B2.3) protected from the existence of sufficient the elements oxygen, moisture levels, and/or soil contaminants 3.3.2.45 Tubing Copper- Fuel Oil Loss of Material Diesel Fuel Monitoring Zinc Alloy

• MIC due to the potential and Storage Program for microorganism intro- (B.2.3) duction and moisture contamination during bulk fuel oil supply and delivery Pitting/Crevice/General Corrosion due to poten tial for water contamina tion and water pooling in a fuel oil system Page 3-73 AGING AGING MANAGEMENT REVIEW MANAGEMENT REVIEW Revision II RevisIon Page 3-73

(

FORT CALHO&t..TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.46 Pipes & fittings Galvanized Gas - Diesel Cracking Periodic Surveillance Steel Exhaust Due to embrittlement at and Preventive elevated temperatures. Maintenance Program Loss of Material (B.2.7)

"* Crevice corrosion due to the presence of an aggressive chemical species and moisture

"* Pitting corrosion due to halides, chlorides or hypochlorites 3.3.2.47 Pipes & fittings Galvanized Above Loss of Material Diesel Fuel Monitoring Steel ground, buried General and pitting and Storage Program in gravel and corrosion due to the (B.2.3) protected from potential for the existence the elements of sufficient oxygen, moisture levels, and/or soil contaminants 3.3.2.48 External surfaces of galvanized steel Galvanized Ambient Air Loss of Material General Corrosion of components Steel 0 Crevice corrosion due to External Surfaces crevices existing that Program (B.3.3) allow a corrosive envi ronment to develop

. General corrosion due to presence of both oxy gen and moisture Page 3-74 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-74

FORT CALHOU. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.49 Sight glass Glass Fuel Oil, None Not Applicable Lubricating Oil, Corrosion Inhibited Treated Water, Air 3.3.2.50 Flow element/orifice body, pipes & Heat- Plant Indoor Cracking One Time Inspection fittings, pump casings, valve bodies Traced Air Due to possible leachables Program (B.3.5)

Stainless in heat-tracing adhesive Steel (cement) combined with component temperatures exceeding 160 deg F due to the heat tracing 3.3.2.51 Fire barriers Mineral Ambient Air Separation Fire Protection Fiber Due to vibration, Program (B.2.5) movement, and shrinkage 3.3.2.52 Fire barriers Mineral Ambient Air Cracking Fire Protection Fiber Due to vibration and Program (B.2.5)

Board movement 3.3.2.53 Fire barriers Mineral Ambient Air Loss of Material Fire Protection Fiber Due to abrasion Program (B.2.5)

Board 3.3.2.54 Fire barriers Mineral Ambient Air Separation Fire Protection Fiber Due to vibration, Program (B.2.5)

Board movement, and shrinkage AGING MANAGEMENT REVIEW Revision I Page 3-75

FORT CALHO.. jTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.55 Heat exchanger - tubes, heat Nickel-Base Deoxygenated Cracking Chemistry Program exchanger - shell Alloy Treated Water Stress Corrosion Cracking (B.1.2) and Cooling

(>200 deg F) due to exposure to Water Corrosion halogens or sulfates Program (B.2.2) 3.3.2.56 Heat exchanger - tubes, heat Nickel-Base Deoxygenated Loss of Material Chemistry Program exchanger - shell Alloy Treated Water - Crevice corrosion due to (B.1.2), Cooling Water

(>200 deg F) potential exposure to Corrosion Program dissolved oxygen (B.2.2) and One Time

"* MIC due to the potential Inspection Program for microbiological activ- (B.3.5) ity

"* Pitting corrosion due to potential exposure to halogens and sulfates 3.3.2.57 Heat exchanger - tubes, heat Copper Corrosion- Loss of Material Chemistry Program exchanger - shell Alloy, Inhibited Crevice and pitting (B.1.2) and Cooling Nickel-Base Treated Water corrosion due to the Water Corrosion Alloy exposure of nickel-based Program (B.2.2) alloys to halogens and sulfates 3.3.2.58 Heat exchanger - shell Nickel-Base Plant Indoor None Not Applicable Alloy Air 3.3.2.59 Fire barriers Pyrocrete Ambient Air Cracking Fire Protection Due to vibration, Program (B.2.5) movement, and shrinkage Page 3-76 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-76

FORT CALHOU.. PTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.60 Fire barriers Pyrocrete Ambient Air Loss of Material Fire Protection

"* Due to vibration that Program (B.2.5) may cause delamination

"* Due to movement that may cause separation 3.3.2.61 Fire barriers Pyrocrete Ambient Air Separation Fire Protection

"* Due to contact with pipe Program (B.2.5) surfaces

"* Due to hydration 3.3.2.62 Indicator/Recorder body Polysulfone Plant Indoor None Not Applicable Air 3.3.2.63 Indicator/Recorder body Polysulfone Raw Water None Not Applicable 3.3.2.64 External surfaces of stainless steel Stainless Ambient Air None Not Applicable components Steel 3.3.2.65 Pipes & fittings Stainless Concrete None Not Applicable Steel 3.3.2.66 Pipes & fittings, valve bodies Stainless Deoxygenated Cracking Chemistry Program Steel Treated Water Due to exposure of (B.1.2) and One Time

(>200 deg F) stainless steel to halogens Inspection Program and sulfates (B.3.5)

Revision II Page 3-77 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision Page 3-77

FORT CALHOO.h,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.67 Pipes &fittings, valve bodies Stainless Deoxygenated Loss of Material Chemistry Program Steel Treated Water

• Crevice corrosion due (B.1.2) and One Time

(>200 deg F) exposure of stainless Inspection Program steel to dissolved oxy- (B13.5) gen

. Pitting corrosion due to the exposure of stain less steel to halogens and sulfates 3.3.2.68 Filter/Strainer housing, valve bodies, tubing Stainless Fuel Oil Loss of Material Diesel Fuel Monitoring Steel

• MIC due to the potential and Storage Program for microorganism intro- (B.2.3) duction and moisture contamination during bulk fuel oil supply and delivery Pitting/Crevice/General Corrosion due to poten tial for water contamina tion and water pooling in a fuel oil system Page 3-78 AGING MANAGEMENT REVIEW AGING REVIEW Revision II Revision Page 3-78

FORT CALHOUi, STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.69 Pipes & fittings Stainless Gas - Diesel Cracking Periodic Surveillance Steel Exhaust Due to moisture-containing and Preventive contaminants concentrate, Maintenance Program resulting in an environment (B.2.7) conducive to SCC/IGA.

Loss of Material

"* Crevice corrosion due to the presence of an aggressive chemical species and moisture

"* Pitting corrosion due to halides, chlorides or hypochlorites 3.3.2.70 Valve bodies Stainless Gas - None Not Applicable Steel Hydrogen 3.3.2.71 Pipes & fittings, valve bodies, tubing Stainless Gas - None Not Applicable Steel Instrument Air 3.3.2.72 Pipes & fittings, valve bodies, tubing Stainless Gas - Nitrogen None Not Applicable Steel 3.3.2.73 Pipes & fittings, valve bodies, piping spray Stainless Lubricating Oil Loss of Material Fire Protection shield Steel General corrosion due to Program (B.2.5) the possibility for water contamination and water pooling Page 3-79 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-79

FORT CALHOG. - ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.3.2.74 Flow element/orifice body; indicator/recorder Stainless Corrosion- Cracking Chemistry Program housing, orifice plate, pipes & Steel Inhibited Due to exposure to (B.1.2) and Cooling fittings, valve bodies, heat exchanger Treated halogens and sulfates Water Corrosion

- tubes Water Program (B.2.2) 3.3.2.75 External surfaces of stainless steel Stainless Ambient Air None Not Applicable componenets Steel 3.3.2.76 Heat exchanger - tubes Stainless Oxygenated Loss of Material Chemistry Program Steel Treated Water

• Crevice corrosion due to (B.1.2) and Cooling

<200 deg F an oxygenated treated Water Corrosion water environment Program (B.2.2)

• Pitting corrosion due to exposure to halogens and sulfates 3.3.2.77 Filter strainer housing Stainless Raw Water Loss of Material Periodic Surveillance Steel

• Crevice corrosion due to and Preventive the presence of dis- Maintenance Program solved oxygen and (B.2.7) impurities

"* MIC due to exposure to microbiological activity

"* Pitting corrosion due to exposure to halide ions 3.3.2.78 Not used in application 3.3.2.79 Glass in metal fire penetration barriers Glass Ambient Air None Not Applicable Page 3-80 AGING MANAGEMENT REVIEW AGING Revision I1 Revision Page 3-80

FORT CALHOIk,. jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.80 Calcium silicate board Calcium Ambient Air None Not Applicable Silicate 3.3.2.81 Fuel transfer carrier box, fuel transfer Stainless Ambient Air Loss of Material Chemistry Program conveyor, UGS lift rig, reactor head lift rig, Steel and Borated

• Crevice corrosion due to (B. 1.2) fuel handling tools, fuel transfer tilting Water the exposure to dis machine, spent fuel storage racks solved oxygen.

° Pitting corrosion due to the exposure to halo gens and sulfates.

3.3.2.82 Valve bonnets protected by rubber Ductile Iron Possibly Loss of material due to Periodic Surveillance diaphragm exposed to boric acid corrosion and Preventive borated water Maintenance Program (B,2.7) 3.3.2.83 Pipes & fittings Galvanized Ambient Air Loss of material Periodic Surveillance Steel

• General corrosion due and Preventive to exposure to oxygen Maintenance Program and moisture (8.2.7)

. Crevice corrosion due to exposure to moisture 3.3.2.84 Heat exchanger tubes, valve bodies Copper Corrosion- Loss of material Selective Leaching Alloy Inhibited Due to selective leaching Program (B.3.6)

Treated Water 3.3.2.85 Heat exchanger tubes, valves Copper Lubricating Oil Loss of Material Periodic Surveillance Alloy, Pitting, general and crevice and Preventive Brass, corrosion due to potential Maintenance Program Bronze for water contamination (B.2.7)

AGING MANAGEMENT REVIEW Revision I Page 3-81

FORT CALHOUI,, ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.86 Pipes & fittings, tanks Coated Buried in Loss of Material Buried Surfaces Carbon Ground External surface corrosion External Corrosion Steel due to the potential for the Program (B.3.2) existence of sufficient oxygen, moisture levels, and/or soil contaminants.

3.3.2.87 Pump Casing Cast Iron Fuel Oil Loss of Material Diesel Fuel Monitoring

"* MIC due to the potential and Storage Program for microorganism intro- (B.2.7) duction and moisture contamination during bulk fuel oil supply and delivery

"* Pitting, general and crevice corrosion due to potential for water con tamination 3.3.2.88 Pump Casing Cast Iron Lubricating Oil Loss of Material Periodic Surveillance Pitting, general and crevice and Preventive corrosion due to potential Maintenance Program for water contamination (B.2.7) 3.3.2.89 Heat exchangers - shell and tube sheet, Carbon Lubricating Oil Loss of Material Periodic Surveillance tanks, valves Steel, General corrosion due to and Cadmium the possibility for water Preventive Plated Steel contamination and water Maintenance Program pooling. (B,2.7)

Page 3-82 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-82

FORT CALHOUI'i .,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.90 Blower and fan housing Cast Iron Containment Loss of Material due to Periodic Surveillance Air general corrosion where and Preventive both oxygen and moisture Maintenance Program are present (B12.7) 3.3.2.91 Piping and fittings Copper Ambient Air Loss of Material due to Periodic Surveillance wear and Preventive Maintenance Program (B.2.7) 3.3.2.92 Bolting Zinc Plated Buried in Loss of Material Fire Protection Steel Ground External surface corrosion Program (B.2.5) due to the potential for the existence of sufficient oxygen, moisture levels, and/or soil contaminants 3.3.2.93 Filter/Strainers, valves Cast Iron Ambient Air Loss of Material due to Fire Protection general corrosion where Program (B.2.5) both oxygen and moisture are present 3.3.2.94 Piping and fittings Galvanized Raw Water Loss of Material due to Fire Protection Steel general, crevice, pitting and Program (B.2.5) galvanic corrosion and MIC.

3.3.2.95 Traveling Screen Frame Carbon Raw Water Loss of Material due to Periodic Surveillance Steel general, crevice, pitting and and Preventive galvanic corrosion and Maintenance Program MIC. (B.2.7)

AGING MANAGEMENT REVIEW Revision 1 Page 3-83

FORT CALHOU.,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-2 (CONTINUED)

FCS AUXILIARY SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.3.2.96 Piping and fittings Stainless Borated Cracking Periodic Surveillance Steel Treated Water Stress corrosion cracking and Preventive Maintenance Program (8.2.7)

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FORT CALHOU,. STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.01 Pipes, fittings, Stainless Borated Cracking Chemistry 3.3.1.10 The FCS components are valve bodies, Steel Treated Water Stress Program made of the same material, filter casings, corrosion (B.1.2) exposed to the same pump casings, cracking environment, subject to the ion exchangers same aging effects and and heat managed by the same aging exchangers management program as the components evaluated in NUREG-1801, Volume 2, V.D1.1-a.

3.3.3.02 Fuel transfer Stainless Ambient Air Cracking Chemistry 3.3.1.12 The FCS components are carrier box, fuel Steel and Borated Stress Program made of the same material, transfer Treated Water corrosion (B. 1.2) exposed to the same conveyor, UGS cracking environment, subject to the lift rig, reactor same aging effects and head lift rig, fuel managed by the same aging handling tools, management program as the fuel transfer components evaluated in tilting machine NUREG-1801, Volume 2, VII.A2.1-c.

Revision II Page :3-85 AGING AGING MANAGEMENT MANAGEMENT REVIEW REVIEW Revision Page 3-85

FORT CALHO0i,. TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.03 Pipes, fittings Stainless Deoxygenated Loss of Chemistry 3.4-1.02 The FCS components are Steel Treated Water Material Program made of the same material,

(<200F) (8.1.2) exposed to the same environment, subject to the same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VIII.G4-b.

3.3.3.04 Pipes, fittings, Stainless Borated Cracking Chemistry 3.3.1.08 The FCS components are valve bodies Steel Treated Water Stress Program made of the same material, corrosion (8. 1.2) exposed to the same cracking environment, subject to the same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VIIEI.7-c.

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FORT CALHOUr, ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.05 Filter/Strainer Carbon Lubricating Oil Loss of Periodic 3.4-1.04 The FCS components are bodies, flow Steel Material Surveillance made of the same material, element/orifice, and exposed to the same pipes &fittings, Preventive environment, subject to the braided flexible Maintenance same aging effects and hose Program managed by the same aging (1.2.7) management program as the components evaluated in NUREG-1801, Volume 2, VIII.G5-d.

3.3.3.06 Filter/Strainer Carbon Fuel Oil Loss of Diesel Fuel 3.3.1.07 The FCS components are bodies, pipes & Steel Material Monitoring made of the same material, fittings, valves, and Storage exposed to the same pumps, tanks Program environment, subject to the (B.2.3) same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VII.H1 .4-a.

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FORT CALHO,. .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS INAUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.07 Valve bodies, Cast Iron, Ambient Air Loss of General 3.3.1.05 The material is subject to the piping & fittings, cadmium Material Corrosion of same environment and aging fan housings, plated Ext. Surfaces effect, and managed by the bolts, duct, steel, Program same aging management pumps galvanized (B.3.3) program as evaluated in steel Table 3.3-1, Item 3.3.1.05.

The aging effect is independent of component type.

3.3.3.08 Electric heater Carbon Corrosion- Loss of Chemistry 3.3.1.14 The FCS components are sleeves, tanks, Steel Inhibited Material Program made of the same material, heat exchanger, Treated Water (B. 1.2) and exposed to the same orifice, Cooling environment, subject to the Water same aging effects and Corrosion managed by the same aging Program management program as the (B.2.2) components evaluated in NUREG-1801, Volume 2, VII.H2.1-a and VII.C2.5-a.

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FORT CALHOb., -TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.09 Valve bodies, Cast Iron, Ambient Air Loss of Boric Acid 3.3.1.13 The material is subject to the piping & fittings, cadmium Material Corrosion same environment and aging duct, damper, plated (BAC) effect, and managed by the bolts, heat steel, Prevention same aging management exchangers galvanized Program program as evaluated in steel, (B.2.1) Table 3.3-1, Item 3.3.1.13.

copper The aging effect is alloy independent of component type.

3.3.3.10 Fire blocking Galvanized Ambient Air Loss of Periodic 3.3.1.05 The FCS components are damper, duct, steel, cast Material Surveillance made of the same material, valve bodies, iron and exposed to the same fan housings Preventive environment, subject to the Maintenance same aging effects and Program managed by the same aging (B.2.7) management program as the components evaluated in NUREG-1801, Volume 2, VII. F2.1-a.

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FORT CALHOUI,%,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.11 Filter/Strainer, Cast iron Raw Water Loss of Cooling 3.3.1.16 The FCS components are valve, heat Material Water 3.3.1.24 made of the same material, exchanger Corrosion exposed to the same Program environment, subject to the (B.2.2) and same aging effects and Selective managed by the same aging Leaching management program as the Program components evaluated in (B.3.6) or NUREG-1801, Volume 2, Periodic VII.C1.5-a.

Surveillance and Preventive Maintenance Program (B.2.7) for externally exposed components Page 3-90 MANAGEMENT REVIEW AGING MANAGEMENT AGING REVIEW Revision II Revision Page 3-90

FORT CALHOUIi .,TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.12 Heat Stainless Raw Water Loss of Cooling 3.3.1.16 The FCS components are exchanger, Steel Material Water made of the same material, Pumps, Biofouling Corrosion exposed to the same Indicator/ Program environment, subject to the Recorder (B2.2) same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VII.C1.4-a.

3.3.3.13 Heat exchanger Stainless Corrosion- Cracking Cooling 3.3.1.08 The FCS components are Steel Inhibited Water made of the same material, Treated Water Corrosion exposed to the same Program environment, subject to the (B.2.2) same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VII.E1.8-b.

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FORT CALHOU,. ,aTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.3-3 (CONTINUED)

COMPONENTS IN AUXILIARY SYSTEMS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS FCS Applicable Justification for applying Row Components Material Environment AERMs Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.3.3.14 Traveling Carbon Raw Water Loss of Cooling 3.3.1.16 The FCS components are Screen Frame Steel Material Water made of the same material, Corrosion exposed to the same Program environment, subject to the (B.2.2) same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VII.C1.1-a.

3.3.3.15 Pipes & fittings, Stainless Corrosion- Loss of Chemistry 3.3.1.14 The FCS components are Indicator / Steel Inhibited Material Program made of the same material, Recorder, Heat Treated Water (B.1.2) and exposed to the same Exchanger Cooling environment, subject to the Water same aging effects and Corrosion managed by the same aging Program management program as the (B.2.2) components evaluated in NUREG-1801, Volume 2, VII.C2.2-a.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEMS The Steam and Power Conversion Systems consist of the Main Steam System, the Main and Auxiliary Feedwater Systems, Steam Generator Blowdown System and associated components at FCS.

The Main Steam System consists of piping from each steam generator that penetrates the containment wall to the main steam isolation valves that are located in each pipe just outside containment. Also included in the Main Steam System boundary is the piping to the turbine-driven auxiliary feedwater pump and the associated drains and vents.

The Feedwater System consists of a supply line to each steam generator. A feedwater isolation valve in each steam generator supply line is located just outside the containment penetration.

The Auxiliary Feedwater (AFW) System supplies feedwater to the steam generators whenever the reactor coolant system temperature is above 300 deg F and the main feedwater system is not in operation. The AFW System contains the emergency feedwater storage tank (EFWST), two pumps, plus related piping, valves, and instrumentation. One pump is electric motor driven, and the other is steam turbine driven. The AFW System can supply the steam generators through two different flow paths. One flow path is through an interconnection with the main feedwater piping upstream of the feedwater regulating valves, after which the water enters the each steam generator through the normal feed ring. This flow path is typically used during normal plant heatup and cooldown evolutions. The other flow path connects to the AFW nozzles on the steam generators. Either AFW pump can pump water from the EFWST to the steam generators.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience were consistent with those identified in NUREG-1 801.

Industry: A review of industry-wide operating experience was conducted to identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

AGING MANAGEMENT REVIEW Revision 1 Page 3-93

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.4.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.4-1 shows the aging management programs evaluated in NUREG-1 801 that are relied on for license renewal of the Steam and Power Conversion Systems at FCS. Note that this table only includes those components, materials and environments that are applicable to a PWR. Information on FCS specific components and materials, not listed in NUREG-1801 but included in the group described in a particular line of the table, is included in the discussion column.

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I FORT CALHOIJi,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number AgIng Effect I Management Evaluation Component Group Mchanism Program Recommended Discussion 3.4.1.01 Piping and fittings in main Cumulative TLAA, Yes, TLAA 1. The TLAA is applicable to Class IIand feedwater line, steam line fatigue damage evaluated in III piping at FCS. See Section 4.3.4 for and AFW piping (PWR accordance the TLAA discussion of Class IIand III only) with 10 CFR Piping.

54.21(c) 2. Consistent with NUREG-1801, this group includes piping, fittings, and valve bodies at FCS.

3.4.1.02 Piping and fittings, valve Loss of material Water Yes, detection of 1. The Chemistry Program (B.1.2),

bodies and bonnets, pump due to general Chemistry and aging effects is supplemented by the One-Time casings, tanks, tubes, (carbon steel One-Time to be further Inspection Program (B.3.5) manages tubesheets, channel head, only), pitting, Inspection evaluated the aging effects of these components.

and shell (except main and crevice The programs are described in steam system) corrosion Appendix B of this application.

NUREG-1801 indicates that the verification of the effectiveness of the water chemistry program should be conducted with an inspection of stagnant flow locations within the systems. These inspections will be conducted in accordance with the One-Time Inspection Program.

2. Consistent with NUREG-1 801, this group includes carbon steel in treated water at FCS.

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FORT CALHOh. . TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Aging Effect I Management Evaluation Component Group Mechanism Program Recommended Discussion 3.4.1.03 Auxiliary feedwater (AFW) Loss of material Plant specific Yes, plant The environment identified in NUREG piping due to general, specific 1801 is not applicable to FCS. The AFW pitting, and piping at FCS is not exposed to untreated crevice water from a backup water supply corrosion, MIC, and biofouling 3.4.1.04 Oil coolers in AFW system Loss of material Plant specific Yes, plant 1. The Periodic Surveillance and (lubricating oil side due to general specific Preventive Maintenance Program possibly contaminated (carbon steel (8.2.7) manages this aging effect by with water) only), pitting, ensuring water is not present in and crevice lubricating oil and that the oil is corrosion, and changed on a refueling frequency. This MIC program is described in Appendix B of this application.

2. Consistent with NUREG-1801, this group includes carbon steel and stainless steel in lubricating oil possibly contaminated with water at FCS 3.4.1.05 External surface of carbon Loss of material Plant specific Yes, plant 1. The General Corrosion of External steel components due to general specific Surfaces Program (B.3.3) manages corrosion this aging effect. This program is described in Appendix B of this application.

2. Consistent with NUREG-1 801, this group includes carbon and low alloy steel in ambient air at FCS.

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FORT CALHOIk,. jTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Aging Effect I Management Evaluation Component Group Mechanism Program Recommended Discussion 3.4.1.06 Carbon steel piping and Wall thinning Flow No 1. The aging management results are valve bodies due to flow- Accelerated consistent with the results reviewed accelerated Corrosion and approved in NUREG-1801.

corrosion 2. Consistent with NUREG-1801, this group includes carbon steel in treated water and saturated steam at FCS.

3.4.1.07 Carbon steel piping and Loss of material Water No 1. The aging management results are valve bodies in main due to pitting Chemistry consistent with the results documented steam system and crevice in NUREG-1801.

corrosion 2. Consistent with NUREG-1801, this group includes carbon steel in saturated steam at FCS.

3.4.1.08 Closure bolting in high- Loss of material Bolting Integrity No 1. The aging management results are pressure or high- due to general consistent with the results documented temperature systems corrosion; crack in NUREG-1801.

initiation and 2. Consistent with NUREG-1801, this growth due to group includes carbon and low alloy cyclic loading steel bolting in ambient air in high and/or SCC. pressure or high temperature systems at FCS.

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FORT CALHOUi, ,jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Aging Effect I Management Evaluation Component Group Mechanism Program Recommended Discussion 3.4.1.09 Heat exchangers and Loss of material Open-cycle No The combinations of materials and coolers/condensers due to general Cooling Water environment identified in NUREG-1801 serviced by open-cycle (carbon steel System are not applicable to FCS. The applicable cooling water only), pitting, heat exchangers are not serviced by open and crevice cycle cooling water corrosion, MIC, and biofouling; buildup of deposits due to biofouling 3.4.1.10 Heat exchangers and Loss of material Closed-cycle No 1. The aging management results are coolers/condensers due to general Cooling Water consistent with the results documented serviced by closed-cycle (carbon steel System in NUREG-1801.

cooling water only), pitting, 2. Consistent with NUREG-1801, this and crevice group includes stainless steel corrosion components in corrosion inhibited treated water at FCS.

3.4.1.11 External surface of above Loss of material Above Ground No The component identified in NUREG-1801 ground condensate due to general Carbon Steel is not applicable to FCS.

storage tank (carbon steel Tanks only), pitting, and crevice corrosion Page 3-98 AGING MANAGEMENT REVIEW AGING REVIEW Revision II Revision Page 3-98

FORT CALHOU. ,oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Aging Effect I Management Evaluation Component Group Mechanism Program Recommended Discussion 3.4.1.12 External surfaces of Loss of material Buried piping No The component identified in NUREG-1801 buried condensate due to general, and tanks is not applicable to FCS.

storage tank and AFW pitting, and surveillance piping crevice corrosion and or MIC Yes, detection of Buried piping aging effects and and tanks operating inspection experience are to be further evaluated 3.4.1.13 External surface of carbon Loss of material Boric acid No 1. The aging management results are steel components due to boric acid corrosion consistent with the results documented corrosion in NUREG-1801.

2. Consistent with NUREG-1801, this group includes carbon and low alloy steel components in ambient air and leaking and dripping, chemically treated, borated water at FCS.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.4.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 Table 3.4-2 contains Steam and Power Conversion Systems aging management review results that are not addressed in NUREG-1801. This table includes the component types, materials, environments, aging effects requiring management, and the programs and activities for managing aging. Table 3.4-3 contains components in Steam and Power Conversion Systems not evaluated in NUREG-1801 that rely on aging management programs in NUREG-1 801 for FCS License Renewal and the justification for the use of these programs.

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FORT CALHOb.. .TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-2 FCS STEAM AND POWER CONVERSION SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.4.2.01 Pumps Aluminum Lubricating Oil Loss of Material Periodic Surveillance and General corrosion due to the Preventive Maintenance possibility for water contamination Program (B.2.7) and water pooling 3.4.2.02 Pumps Aluminum Plant Indoor Air None Not Applicable 3.4.2.03 Heat exchanger Copper Deoxygenated Treated Loss of Material One Time Inspection (channel, channel Alloy Water

• Crevice and pitting corrosion Program (B.3.5) head, tubes) and due to potential stagnant or valves low flow conditions

• Wear due to flow induced vibration 3.4.2.04 Heat exchanger Copper Deoxygenated Treated Loss of Material Selective Leaching Program (channel, channel Alloy Water Selective leaching (B,3,5) head, tubes) and valves 3.4.2.05 Filters/Strainers, Copper Lubricating Oil Loss of Material Periodic Surveillance and heat exchanger Alloy General corrosion due to the Preventive (shell and tubes), possibility for water contamination Maintenance Program indicator/ recorder and water pooling (B.2.7) body, pipes, fittings and valves 3.4.2.06 External surface of Copper Ambient Air None Not Applicable copper alloy Alloy components Revision I1 Page 3-101 AGING MANAGEMENT REVIEW AGING Revision Page 3-101

FORT CALHOUi. JTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-2 (CONTINUED)

FCS STEAM AND POWER CONVERSION SYSTEMS COMPONENT TYPES SUBJECT TO AGING MANAGEMENT REVIEW NOT EVALUATED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.4.2.07 Indicator/Recorder Glass Deoxygenated Treated None Not Applicable (sightglass) Water Lubricating Oil Ambient Air 3.4.2.08 External surface of Stainless Ambient Air None Not Applicable stainless steel Steel components 3.4.2.09 Pipes, fittings, Stainless Oxygenated or Cracking Water Chemistry (B. 1.2) and valves, filter/strainer, Steel Deoxygenated Treated Due to exposure of stainless steel One-Time Inspection (B.3.5) flow element/orifice, Water to halogens and sulfates transmitter element, pump casing 3.4.2.10 Pipes, fittings, and Stainless Deoxygenated Treated Cracking Water Chemistry (B. 1.2) and valves Steel Water or Saturated Steam Due to exposure of stainless steel One-Time Inspection (B.3.5) to halogens and sulfates 3.4.2.11 Pipes, fittings, and Stainless Deoxygenated Treated Loss of Material Water Chemistry (B.1.2) and valves Steel Water or Saturated Steam

• Crevice corrosion due expo- One-Time Inspection (B.3.5) sure of stainless steel to dis solved oxygen

. Pitting corrosion due to the exposure of stainless steel to halogens and sulfates Page 3-102 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision II Revision Page 3-102

FORT CALHOU,, STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-3 COMPONENTS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCS Program Applicable Justification for applying Row Components Material Environment Activity NUREG-1801 NUREG-1801 Aging Number Aging Management Review Management Results Review Results Row Number 3.4.3.01 Filter/Strainer, Carbon Lubricating Oil Loss of Periodic 3.4.1.04 The FCS components are pumps Steel Material Surveillance made of the same material, and exposed to the same Preventive environment, subject to the Maintenance same aging effects and Program managed by the same (B.2.8) aging management program as the components evaluated in NUREG-1801, Volume 2, VIII.G5-d.

3.4.3.02 Filter/Strainer, Stainless Deoxygenated Loss of Chemistry 3.4.1.02 The FCS components are flow element/ Steel Treated Water Material Program made of the same material, orifice housing, (B. 1.2), exposed to the same pipes & fittings supplemented environment, subject to the by the One- same aging effects and Time managed by the same Inspection aging management Program program as the (B13.5) components evaluated in NUREG-1801, Volume 2, VIII.G4-b.

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FORT CALHO6.. .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-3 (CONTINUED)

COMPONENTS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCSProgram Applicable Justification for applying Row Components Material Environment Activity NUREG-1801 NUREG-1801 Aging Number Aging Management Review Management Results Review Results Row Number 3.4.3.03 Turbine casing, Carbon Saturated Loss of Chemistry 3.4.1.07 The FCS components are filter/strainer, Steel Steam Material Program made of the same material, pipes & fittings, (B.1.2) exposed to the same valve bodies environment, subject to the same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VIII.B1 .2-a and VIII.B1.1-a.

3.4.3.04 Filter/strainer, Carbon Saturated Loss of Flow 3.4.1.06 The FCS components are pipes & fittings, Steel Steam Material Accelerated made of the same material, valve bodies Corrosion exposed to the same (FAC) environment, subject to the Program same aging effects and (B.1.5) managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, VIII.B1I.1-c.

Revision II Page 3-104 MANAGEMENT REVIEW AGING MANAGEMENT AGING REVIEW Revision Page 3-104

FORT CALHOUiv jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.4-3 (CONTINUED)

COMPONENTS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS FOR STEAM AND POWER CONVERSION SYSTEMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCS Program Applicable Justification for applying Row Components Material Environment Activity NUREG-1801 NUREG-1801 Aging Number Aging Management Review Management Results Review Results Row Number 3.4.3.05 Valves Low- Deoxygenated Loss of Chemistry 3.4.1.02 The material is subject to Alloy Treated Water Material Program the same environment and Steel (B, 1.2) aging effect, and managed supplemented by the same aging by the One- management program as Time evaluated in Table 3.4-1, Inspection Item 3.4.1.02. The aging Program effect is independent of (B.3.5) component type.

Page 3-105 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-105

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.5 AGING MANAGEMENT OF CONTAINMENT, STRUCTURES AND COMPONENT SUPPORTS The Containment, Structures and Component Supports are comprised of the Containment, Auxiliary Building, Turbine and Service Building, Intake Structure, Building Piles and associated component supports at FCS.

The Containment structure is a partially prestressed, reinforced concrete Class I structure composed of cylindrical walls, domed roof and a bottom mat. The mat is common to both the Containment structure and the Auxiliary Building and is supported on steel piles driven to bedrock. The mat incorporates a depressed center portion for the reactor vessel. The Containment has a 1/4-inch internal carbon steel liner. The unbonded tendons are in conduits filled with waterproof grease. The tendon anchors are accessible for inspection, testing, and re-tensioning via the tendon access gallery located directly beneath the cylinder walls and at the dome roof.

The Auxiliary Building is a multi-floored, reinforced concrete, Class I structure. From the bottom of the foundation mat to the roof, the structure is of box-type construction with internal bracing provided by vertical concrete walls and horizontal floor slabs. The spent fuel pool is contained within the Auxiliary Building and consists of a stainless steel lined concrete structure. The control room is located within the Auxiliary Building. The Auxiliary Building masonry walls in the area of safety-related equipment have been reinforced to provide protection for Class I equipment and components located nearby.

The Turbine and Service Building is a multi-floored Class II structure. From the basement floor to the operating floor, the structure is a box-type, reinforced concrete structure with internal bracing provided by concrete walls, floor slabs and structural steel.

The mat foundation is supported on steel piles driven to bedrock. From the operating floor to the roof, the structure is braced steel frame clad with aggregate resin panels. The multi-layered built-up roof is supported by metal decking spanning between open web steel joists. The turbine generator is located on the operating floor. It is supported by a mass concrete structure referred to as the turbine pedestal.

The Intake Structure is a multi-floored Class I structure. From the bottom of the foundation mat to seven feet above the operating floor, the structure is a box-type reinforced concrete structure with internal bracing provided by concrete walls and floor slabs. The mat foundation is supported on steel pipe piles driven to bedrock. Above the reinforced concrete structure to the roof the structure is a braced steel frame clad with aggregate resin panels. The multi-layered built-up roof is supported by metal decking spanning between open web steel joists. The diesel-driven fire pump fuel tank enclosure is included in the Intake Structure.

Page 3-106 MANAGEMENT REVIEW Revision I AGING MANAGEMENT AGING REVIEW Revision 1 Page 3-106

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The Building Piles commodity group consists of four types of piles: Class A steel pipe piles, Class B steel pipe piles, concrete caissons, and steel H-piles. Class A piles are 20 inch OD open-end pipe piles with 1.031-inch thick walls driven to bedrock. The piles are filled with sand to the point four feet below the top of the pile. The remaining top four feet is filled with concrete. Class A piles are capped with a 2-inch thick steel plate end closure. Class B piles are 12.75-inch OD closed-end pipe piles with 0.25-inch thick walls and filled with concrete. Class B piles are capped with a 1.25-inch steel plate end closure. Concrete caissons are 3-foot diameter reinforced concrete cylinders that extend 10 feet into bedrock. Steel H-piles are used in the foundations of the diesel engine fuel oil storage tank.

Duct banks are comprised of conduits encased in concrete and are located below grade.

Duct banks are used to route electrical power cables between buildings. Electrical manholes are reinforced concrete box-type structures which allow for inspection and routing of the cables. Duct banks and electrical manholes contain both CQE and Non CQE cables. Only the duct banks and electrical manholes of Class I design that contain safety-related cables are within the scope of license renewal.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience were consistent with those identified in NUREG-1 801.

Industry: A review of industry-wide operating experience was conducted to identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

3.5.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.5-1 shows the aging management programs evaluated in NUREG-1 801 that are relied on for license renewal of Structures, and Component Supports at FCS. Note that this table only includes those components, materials and environments that are applicable to a PWR. Information on FCS specific components and materials, not listed in NUREG-1801 but included in the component group of this application, is included in the discussion column.

AGING MANAGEMENT REVIEW Revision I Page 3-107

FORT CALHOU. .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1 801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended Common Components to all Types of PWR and BWR Containments 3.5.1.01 Penetration Cumulative TLAA evaluated Yes, TLAA 1. The metal fatigue time limited aging analyses are sleeves, fatigue damage in accordance discussed in Section 4.6 of this application.

penetration (CLB fatigue with 10 CFR 2. Consistent with NUREG-1801, this group includes bellows, and analysis exists) 54.21(c) penetration sleeves, penetration bellows, and dissimilar metal dissimilar metal welds at FCS.

welds 3.5.1.02 Penetration Cracking due to Containment ISI Yes, detection of 1. The FCS aging management review results are sleeves, bellows, cyclic loading, or and aging effects is to consistent with those reviewed and approved in and dissimilar crack initiation Containment be evaluated NUREG-1801 with the exception of item 4 below.

metal welds. and growth due leak rate test 2. The Containment Inservice Inspection Program to SCC (B.1.3) and the Containment Leak Rate Program (B. 1.4) manage these aging effects. These programs are described in Appendix B of this application.

3. Consistent with NUREG-1 801, this group includes stainless steel in ambient air at FCS.

4. Stress corrosion cracking for stainless steel bellows with dissimilar metal welds is applicable only if the susceptible material is exposed to a corrosive environment. The bellows at FCS are not exposed to a corrosive environment; therefore, Stress Corrosion Cracking is not an aging effect requiring management.

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FORT CALHOU,, oTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.03 Penetration Loss of material Containment ISI No 1. The FCS aging management review results are sleeves, due to corrosion and consistent with those reviewed and approved in penetration Containment NUREG-1801.

bellows, and leak rate test 2. Consistent with NUREG-1801, this group includes dissimilar metal carbon steel in ambient air at FCS.

welds 3.5.1.04 Personnel airlock Loss of material Containment ISI No 1. The FCS aging management review results are and equipment due to corrosion and consistent with those reviewed and approved in hatch Containment NUREG-1 801.

leak rate test 2. Consistent with NUREG-180, this group includes carbon steel in ambient air at FCS.

3.5.1.05 Personnel airlock Loss of leak Containment No 1. The FCS aging management review results are and equipment tightness in leak rate test consistent with those reviewed and approved in hatch closed position and Plant NUREG-1801.

due to Technical 2. Consistent with NUREG-1801, this group includes mechanical wear Specifications carbon steel in ambient air at FCS.

of locks, hinges and closure mechanism 3.5.1.06 Seals, gaskets, Loss of sealant Containment ISI No 1. The FCS aging management review results are and moisture and leakage and consistent with those reviewed and approved in barriers through Containment NUREG-1801.

containment due leak rate test 2. The equipment hatch gasket, made of neoprene, is to deterioration the only component included in this component of joint seals, group at FCS.

gaskets, and moisture barriers AGING MANAGEMENT REVIEW Revision 1 Page 3-109

FORT CALHOU,, .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended PWR Concrete (Reinforced and Prestressed) and Steel Containment 3.5.1.07 Concrete Aging of Containment ISI Yes, if aging 1. The FCS aging management review results are elements: accessible and mechanism is consistent with those reviewed and approved in foundation, walls, inaccessible significant for NUREG-1801.

dome. concrete areas inaccessible areas 2. The Containment Inservice Inspection Program due to leaching (B. 1.3) manages the aging effects for these of calcium components. This program is described in Appendix B of this application.

hydroxide, 3. Leaching of calcium hydroxide from reinforced aggressive concrete becomes significant only ifthe concrete chemical attack, is exposed to flowing water. The reinforced and corrosion of concrete at FCS is not exposed to flowing water.

embedded steel Cracking is controlled through proper arrangement and distribution of reinforcing bars. The concrete at FCS was designed in accordance with ACI 318 63 (per USAR Section 5.3.1 and USAR Section 5.11.3.1 ) and has these characteristics. Therefore, a plant specific program for below-grade inaccessible areas is not required.

4. Below-grade exterior reinforced concrete at FCS is not exposed to an aggressive environment (pH less than 5.5), or to chloride or sulfate solutions beyond defined limits (greater than 500 ppm chloride, or greater than 1500 ppm sulfate).

Periodic monitoring of below-grade water chemistry will be conducted during the period of extended operation to demonstrate that the below grade environment is not aggressive. Therefore, a plant specific aging management program for below-grade inaccessible areas is not required.

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FORT CALHOUi. .TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.08 Concrete Cracks, Structures No, if within the 1. The aging management results are consistent with elements: distortion, and Monitoring scope of the those reviewed and approved in NUREG 1801.

foundation increases in applicant's Applicable components are within the scope of the component Structures Structures Monitoring Program (B.2.10) described stress level due Monitoring in Appendix B of this application.

to settlement Program 2. The structures at FCS are supported on end bearing steel pipe piles driven to bedrock.

Settlement of the concrete subfoundation is not a plausible aging mechanism. A de-watering system is not relied upon for control of settlement at FCS.

3.5.1.09 Concrete Reduction in Structures No, ifwithin the 1. The aging management results are consistent with elements: foundation Monitoring scope of the those reviewed and approved in NUREG-1801.

foundation strength due to applicant's Applicable components are within the scope of the erosion of Structures Structures Monitoring Program (B.2.10) described porous concrete Monitoring in Appendix B of this application.

subfoundation Program 2. The reinforced concrete at FCS is not exposed to flowing water and a de-watering system is not relied upon for control of erosion of cement from porous concrete subfoundations.

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FORT CALHOI,. 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.10 Concrete Reduction of Plant specific Yes, for any Subsection CC-3400 of ASME Section III, Division 2, elements: strength and portions of specifies the concrete temperature limits for normal foundation, dome, modulus due to concrete operation or any other long-term period. The and wall elevated containment that temperatures shall not exceed 150 deg F except for temperature exceed specified local areas that are allowed to have increased temperature limits temperatures not to exceed 200 deg F.

Per USAR Section 2.5.2.3, the record high temperature in the vicinity of FCS was 114 deg F in July 1936. This is below the temperature limit of 150 deg F. USAR Table 9.10-1 provides maximum building/room temperatures for the Auxiliary Building, Turbine Building, Containment, Control Room, Engine Driven Auxiliary Feedwater Pump Room, Radioactive Waste Processing Building, Chemistry and Radiation Protection Building, and Office/Cafeteria Addition.

Revision II Page 3-112 AGING MANAGEMENT AGING REVIEW MANAGEMENT REVIEW Revision Page 3-112

FORT CALHOU,. STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended The maximum indoor plant temperature in Table 9.10 1 is 120 deg F inside the main area of containment.

This is below the temperature limit of 150 deg F. Per USAR Section 5.5.4, sleeve radiation fins and thermal sleeves (in conjunction with pipe insulation) are used to limit maximum temperature at the containment penetration sleeves to 150 deg F under operating conditions.

The nuclear detector well cooling system cools the out-of-core neutron detectors, which are located in tubes or wells in the reactor compartment annulus between the lower portion of the reactor vessel and the biological shield, and maintains the shield concrete temperature below 150 deg F.Technical Specification Limiting Condition for Operation 2.13 requires that the annulus exit temperature from the nuclear detector cooling system shall not exceed a temperature found to correlate to 150 deg F concrete temperature. Therefore, no portions of concrete containment exceed specified temperature limits and no aging management is required.

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FORT CALHOUh. oTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.11 Prestressed Loss of TLAA evaluated Yes, TLAA 1. See Section 4.5 for the TLAA discussion of containment: prestress due to in accordance containment tendons.

tendons and relaxation, with 10 CFR 2. Consistent with NUREG-1801, this group includes anchorage shrinkage, 54.21(c) containment tendons and anchorage components components creep, and at FCS.

elevated temperature 3.5.1.12 Steel elements: Loss of material Containment ISI Yes, if corrosion is 1. The aging management results are consistent with liner plate, due to corrosion and significant for those reviewed and approved in NUREG-1801.

containment shell in accessible Containment inaccessible areas 2. Corrosion for inaccessible areas (embedded and inaccessible leak rate test containment liner) is not significant because:

areas a. Concrete meeting the requirements of ACI 318 or 349 and the guidance of 201.2R was used for the containment concrete in contact with the embedded containment liner.

b. The concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner.

c. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with IVVE requirements.

d. Borated water spills and water ponding on the containment concrete floor are not common and when detected are cleaned up in a timely manner.

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FORT CALHOUn, .TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.13 Steel elements: Loss of material Protective No The combinations of components, materials and protected by due to corrosion coating environments identified in NUREG-1801 are not coating in accessible monitoring and applicable to FCS. Protective coatings are not relied areas only maintenance on to manage the effects of aging at FCS. The Aging Management Review evaluated in NUREG-1801 is not relied on for FCS license renewal.

3.5.1.14 Prestressed Loss of material Containment ISI No 1. The aging management results are consistent with containment: due to corrosion those reviewed and approved in NUREG-1 801.

tendons and of prestressing 2. Consistent with NUREG-1801, this group includes anchorage tendons and containment tendons and anchorage components components anchorage at FCS.

components 3.5.1.15 Concrete Scaling, Containment ISI No 1. The aging management results are consistent with elements: cracking, and those reviewed and approved in NUREG-1801.

foundation, dome, spalling due to 2. Consistent with NUREG-1801, this group includes and wall freeze-thaw; concrete exposed to ambient air and below grade expansion and concrete at FCS.

cracking due to reaction with aggregate Page 3-115 AGING MANAGEMENT REVIEW AGING REVIEW Revision II Revision Page 3-115

/

FORT CALHOU.i 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended Class I Structures 3.5.1.16 All Groups except All types of Structures No, ifwithin the 1. The aging management results are consistent with Group 6: aging effects Monitoring scope of the those reviewed and approved in NUREG 1801.

accessible interior/ applicant's Applicable components are within the scope of the exterior concrete & Structures Structures Monitoring Program (B.2.10) described steel components Monitoring in Appendix B of this Application Program 2. As described in NUREG-1 557, freeze/thaw does not cause loss of material from reinforced concrete in foundations, and in above and below grade exterior concrete, for plants located in a geographic region of negligible weathering conditions (weathering index <100 day-inch/yr).

Loss of material from such concrete is not significant at plants located in areas in which weathering conditions are severe (weathering index >500 day-inch/yr) or moderate (100-500 day-inch/yr), provided that the concrete mix design meets the air content (entrained air 3-6%) and water-to-cement ratio (0.35-0.45) specified in ACI 318-63 or ACI 349-85. The weathering index for FCS is >500 day-inch/yr. The concrete mix design specified a water-to-cement ratio of 0.38 and air entrainment of 4.75% + 0.75% for Class A concrete for FCS. It specified a water-to-cement ratio of 0.44 and air entrainment of 5.00% + 1.00%

for Class B concrete. Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

AGING MANAGEMENT REVIEW Revision I Page 3-116

FORT CALHOUi, JTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended

3. Leaching of calcium hydroxide from reinforced concrete becomes significant only if the concrete is exposed to flowing water. Leaching is not significant if the concrete is constructed to ensure that it is dense, well-cured, has low permeability, and that cracking is well controlled. Cracking is controlled through proper arrangement and distribution of reinforcing bars. The concrete at FCS was designed in accordance with ACI 318-63 (per USAR Section 5.3.1 and USAR Section 5.11.3.1 ) and has these characteristics. Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

4. Investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227 50 demonstrated that the aggregates used in the construction of FCS do not react within reinforced concrete. Concrete for FCS was constructed in accordance with ACI 201.2R-77. C. Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

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FORT CALHOUI0n ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended

5. Per NUREG-1557, corrosion of embedded steel is not significant for concrete structures above or below grade that are exposed to a non-aggressive environment. A non-aggressive environment, as defined by NUREG-1 557, is one with a pH greater than 11.5 or chlorides less than 500 ppm. NUREG 1557 also concludes that corrosion of embedded steel is not significant for concrete structures exposed to an aggressive environment that have a low water-to-cement ratio, adequate air entrainment, and have been designed in accordance with ACI 318-63 or ACI 349-85. A low water-to-cement ratio is defined as 0.35 to 0.45 and adequate air entrainment is defined as 3 to 6 percent. The concrete at FCS is not exposed to aggressive river water or groundwater. There is no heavy industry in the area whose emissions would cause degradation to concrete or steel. The concrete that surrounds the embedded steel has a pH greater than or equal to 12.5. The concrete mix design specified a water-to-cement ratio of 0.38 and air entrainment of 4.75% + 0.75% for Class A concrete. It specified a water-to-cement ratio of 0.44 and air entrainment of 5.00% + 1.00% for Class B concrete.

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FORT CALHOUNh 6TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended Class C concrete was only used for radiation shields; therefore, itwould not be exposed to an environment that would promote corrosion of embedded steel. The concrete at FCS was designed in accordance with ACI 318-63 (per USAR Section 5.3.1, Revision 0 and USAR Section 5.11.3.1, Revision 2). Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied and aging management is not required. Below-grade exterior reinforced concrete at FCS is not exposed to an aggressive environment (pH less than 5.5), or to chloride or sulfate solutions beyond defined limits (greater than 500 ppm chloride, or greater than 1500 ppm sulfate). Periodic monitoring of below-grade water chemistry will be conducted during the period of extended operation to demonstrate that the below grade environment is not aggressive. Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

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FORT CALHOU. . TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended

6. Aggressive chemical attack on reinforced concrete is not significant if the concrete is exposed to a nonaggressive environment. A non-aggressive environment, as defined by GALL, is one with a pH greater than 5.5, chlorides less than 500 ppm, or sulfates less than 1500 ppm. The concrete at FCS is not exposed to aggressive river water or groundwater. There is no heavy industry in the area whose emissions would cause degradation to concrete or steel. Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

7. The structures at FCS are supported on end bearing steel pipe piles driven to bedrock.

Settlement of the concrete subfoundations is not plausible aging mechanism. A de-watering system is not relied upon for control of settlement at FCS.

8. The reinforced concrete at FCS is not exposed to flowing water and a de-watering system is not relied upon for control of erosion of cement from porous concrete subfoundations.

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FORT CALHOLG.. jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended

9. Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period.

The temperatures shall not exceed 150 deg F except for local areas that are allowed to have increased temperatures not to exceed 200 deg F.

Per USAR Section 2.5.2.3, the record high temperature in the vicinity of FCS was 114 deg F in July 1936. This is below the temperature limit of 150 deg F. USAR Table 9.10-1 provides maximum building/room temperatures for the Auxiliary Building, Turbine Building, Containment, Control Room, Engine Driven Auxiliary Feedwater Pump Room, Radioactive Waste Processing Building, Chemistry and Radiation Protection Building, and Office/Cafeteria Addition. The maximum indoor plant temperature in Table 9.10-1 is 120 deg F inside the main area of Containment. This is below the temperature limit of 150 deg F. Per USAR Section 5.5.4, sleeve radiation fins and thermal sleeves (in conjunction with pipe insulation) are used to limit maximum temperature at the containment penetration sleeves to 150 deg F under operating conditions.

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FORT CALHOUN, jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended The nuclear detector well cooling system cools the out-of-core neutron detectors, which are located in tubes or wells in the reactor compartment annulus between the lower portion of the reactor vessel and the biological shield, and maintains the shield concrete temperature below 150 deg F. Technical Specification Limiting Condition for Operation 2.13 requires that the annulus exit temperature from the nuclear detector cooling system shall not exceed a temperature found to correlate to 150 deg F concrete temperature. Therefore, no portions of concrete containment exceed specified temperature limits and no aging management is required.

3.5.1.17 Groups 1-3, 5, 7-9: Aging of Plant-specific Yes, ifan Below-grade exterior reinforced concrete at FCS is inaccessible inaccessible aggressive below- not exposed to an aggressive environment (pH less concrete concrete areas grade environment than 5.5), or to chloride or sulfate solutions beyond components, such due to exists defined limits (greater than 500 ppm chloride, or as exterior walls aggressive greater than 1500 ppm sulfate). Periodic monitoring of below grade and chemical attack, below grade water chemistry will be conducted during foundation and corrosion of the period of extended operation to demonstrate that embedded steel the below-grade environment is not aggressive.

Therefore, the conditions of NUREG-1801, Volume 2, Chapter III are satisfied.

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FORT CALHOUh ,iTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.18 Group 6: all All types of Inspection of No The components identified in NUREG-1801 are not accessible/inacce- aging effects, Water-Control applicable to FCS. The plant specific programs for ssible concrete, including loss of Structures or Intake Structure components exposed to flowing river steel, and earthen material due to FERC/US Army water are discussed in Items 3.5.202, 3.5.2.08 and components abrasion, Corps of 3.5.2.32 of Table 3.5-2.

cavitation, and Engineers dam corrosion inspections and maintenance 3.5.1.19 Group 5: Crack initiation Water No 1. The aging management results are consistent with liners and growth from Chemistry those reviewed and approved in NUREG-1801.

SCC and loss of Program and 2. Consistent with NUREG-1801, this group includes material due to Monitoring of stainless steel in borated water at FCS.

crevice spent fuel pool 3. In addition to monitoring of spent fuel pool level, the corrosion water level Periodic Surveillance and Preventive Maintenance Program (8.2.7) performs a leak rate analysis of the refueling canal liner.

3.5.1.20 Groups 1-3, 5, 6: Cracking due to Masonry Wall No 1. The aging management results are consistent with all masonry block restraint, those reviewed and approved in NUREG-1801.

walls shrinkage, The masonry wall program is included in the FCS creep, and Structures Monitoring Program (B.2.10).

aggressive 2. Consistent with NUREG-1801, this group includes environment concrete block in ambient air at FCS.

Page 3-123 AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-123

FORT CALHOU,. ,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.21 Groups 1-3, 5, 7-9: Cracks, Structures No, ifwithin the 1. The aging management results are consistent with foundation distortion, and Monitoring scope of the those reviewed and approved in NUREG-1801.

increases in applicant's Applicable components are within the scope of the component Structures Structures Monitoring Program (82.10) described stress level due Monitoring in Appendix B of this application to settlement Program 2. The structures at FCS are supported on end bearing steel pipe piles driven to bedrock.

Settlement of the concrete subfoundation are not plausible aging mechanisms. A de-watering system is not relied upon for control of settlement at FCS.

3. Consistent with NUREG-1801, this group includes reinforced concrete at FCS.

3.5.1.22 Groups 1-3, 5-9: Reduction in Structures No, ifwithin the 1. The aging management results are consistent with foundation foundation Monitoring scope of the those reviewed and approved in NUREG-1801.

strength due to applicant's Applicable components are within the scope of the erosion of Structures Structures Monitoring Program (1.2.10) described porous concrete Monitoring in Appendix B of this application.

subfoundation Program 2. The reinforced concrete at FCS is not exposed to flowing water and a de-watering system is not relied upon for control of erosion of cement from porous concrete subfoundations.

3. Consistent with NUREG-1801, this group includes reinforced concrete at FCS.

Page 3-124 REVIEW AGING MANAGEMENT REVIEW AGING Revision II Revision Page 3-124

FORT CALHOU,. STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.22 Groups 1-5: Reduction of Plant-specific Yes, for any Subsection CC-3400 of ASME Section III, Division 2, concrete strength and portions of specifies the concrete temperature limits for normal modulus due to concrete that operation or any other long-term period. The elevated exceed specified temperatures shall not exceed 150 deg F except for temperature temperature limits local areas that are allowed to have increased temperatures not to exceed 200 deg F.

Per USAR Section 2.5.2.3, the record high temperature in the vicinity of FCS was 114 deg F in July 1936. This is below the temperature limit of 150 deg F. USAR Table 9.10-1 provides maximum building/room temperatures for the Auxiliary Building, Turbine Building, Containment, Control Room, Engine Driven Auxiliary Feedwater Pump Room, Radioactive Waste Processing Building, Chemistry and Radiation Protection Building, and Office/Cafeteria Addition.

The maximum indoor plant temperature in Table 9.10 1 is 120 deg F inside the main area of Containment.

This is below the temperature limit of 150 deg F. Per USAR Section 5.5.4, sleeve radiation fins and thermal sleeves (in conjunction with pipe insulation) are used to limit maximum temperature at the containment penetration sleeves to 150 deg F under operating conditions.

Page 3-125 AGING MANAGEMENT AGING REVIEW MANAGEMENT REVIEW Revision I1 Revision Page 3-125

FORT CALHOUW, oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended The nuclear detector well cooling system cools the out-of-core neutron detectors, which are located in tubes or wells in the reactor compartment annulus between the lower portion of the reactor vessel and the biological shield, and maintains the shield concrete temperature below 150 deg F.

Technical Specification Limiting Condition for Operation 2.13 requires that the annulus exit temperature from the nuclear detector cooling system shall not exceed a temperature found to correlate to 150 deg F concrete temperature. Therefore, no portions of concrete containment exceed specified temperature limits and no aging management is required.

3.5.1.23 Groups 7, 8: Crack Initiation Plant-specific Yes The combinations of components, materials and liners and growth due environments identified in NUREG-1801 are not to SCC; Loss of applicable to FCS.

material due to crevice corrosion Page 3-125 AGING AGING MANAGEMENT REVIEWREVIEW Revision II Revision Page 3-126

FORT CALHOU,. .,TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended Component Supports 3.5.1.25 All Groups: Aging of Structures No, if within the 1. The aging management results are consistent with support members: component Monitoring scope of the those reviewed and approved in NUREG-1801.

anchor bolts, supports applicant's Applicable components are within the scope of the concrete Structures Structures Monitoring Program (B.2.10) described surrounding Monitoring in Appendix B of this application.

anchor bolts, Program 2. Consistent with NUREG-1 801, this group includes welds, grout pad, carbon steel, grout and epoxy grout and reinforced bolted concrete exposed to ambient air at FCS.

connections, etc.

Groups B1.1, B1.2, Cumulative TLAA evaluated Yes, TLAA A CLB fatigue analysis does not exist at FCS and B1.3: fatigue damage in accordance Station.

support members: (CLB fatigue with 10 CFR anchor bolts, analysis exists) 54.21(c) welds All Groups: Loss of material Boric acid No 1. The aging management results are consistent with support members: due to boric acid corrosion those reviewed and approved in NUREG-1 801.

anchor bolts, corrosion 2. Consistent with NUREG-1801, this group includes welds carbon steel exposed to ambient air at FCS.

Page 3-127 AGING MANAGEMENT REVIEW AGING REVIEW Revision II RevIsion Page 3-127

FORT CALHOUi, JTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-1 (Continued)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR STRUCTURES AND COMPONENT SUPPORTS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Discussion Number Aging Effect/ Management Evaluation Component Mechanism Programs Recommended 3.5.1.28 Groups B 1.1, B 1.2, Loss of material ISI No 1. The aging management results are consistent with and B1.3: due to those reviewed and approved in NUREG-1801.

support members: environmental 2. Consistent with NUREG-1801, this group includes anchor bolts, corrosion; loss of carbon steel exposed to ambient air at FCS.

welds, spring mechanical hangers, guides, function due to stops, and corrosion, vibration isolators distortion, dirt, overload, etc.

3.5.1.29 Group B1.1: Crack initiation Bolting integrity No 1. The aging management results are consistent high strength low- and growth due (with deviation) with the results documented in alloy bolts to SCC NUREG-1801.

2. The Bolting Integrity Program (B.1.1) discussed in Appendix B of this application includes an alternative means of managing cracking due to SCC.

3. Consistent with NUREG-1801, this group includes high strength low-alloy bolts exposed to ambient air at FCS.

Page 3-125 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision II Revision Page 3-128

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.5.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 Table 3.5-2 contains Containment, Structures and Component Supports aging management review results that are not addressed in NUREG-1801. This table includes the component types, materials, environments, aging effects requiring management, and the programs and activities for managing aging. Table 3.5-3 contains components in Containment, Structures and Component Supports not evaluated in NUREG-1801 that rely on aging management programs in NUREG-1 801 for FCS License Renewal and the justification for the use of these programs.

I Page 3-129 AGING MANAGEMENT REVIEW Revision Revision I Page 3-129 AGING MANAGEMENT REVIEW

(

FORT CALHOUi,. ,JTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.01 Removable slab lifting Bronze Plant Indoor Air None Not Applicable devices 3.5.2.02 Intake Structure sluice Bronze, brass Raw Water Loss of Material Structures Monitoring gate operator gland, pump

• Crevice and pitting cor- Program (B.2. 10) gland and gland bolting rosion and MIC due to stagnant conditions

° Galvanic corrosion due to the conductivity of the process fluid and the presence of dissimi lar metals in contact 3.5.2.03 Class A pipe piles are Carbon Steel Below Grade None Not Applicable partially filled with soil during placement and then are filled with sand to the point four feet below the top of the pile. The remaining four feet are then filled with concrete.

3.5.2.04 Class B pipe piles Carbon Steel Below Grade None Not Applicable Diesel engine fuel oil storage tank H-piles 3.5.2.05 Class B pipe piles Carbon Steel Concrete None Not Applicable Page 3-130 AGING MANAGEMENT AGING MANAGEMENT REVIEW REVIEW Revision II Revision Page 3-130

K FORT CALHOUt, oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.06 Class A pipe piles are Carbon Steel Concrete/Sand/Soil None Not Applicable partially filled with soil during placement and then are filled with sand to the point four feet below the top of the pile. The remaining four feet are then filled with concrete.

3.5.2.07 Manhole flange, Flood Carbon Steel Outside Air Loss of Material Periodic Surveillance gates General corrosion due to and Preventive the exposure of external Maintenance Program surfaces to varying levels (B.2.7) of humidity Page 3-131 AGING MANAGEMENT REVIEW AGING MANAGEMENT REVIEW Revision II Revision Page 3-131

FORT CALHOU,. .,TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.08 Intake Structure carbon Carbon Steel Raw Water Loss of Material Periodic Surveillance steel pipe, pipe sleeve,

• Crevice and general and Preventive flange and pipe casing corrosion due to oxy- Maintenance Program floor penetration genated raw water (B.2.7) environment

"* Pitting corrosion due to oxygenated raw water environment and stag nant or low flow condi tions

"* Galvanic corrosion due to the conductivity of the process fluid and dissimilar metals in contact

"* MIC due to exposure to microbiological activity Revision II Page 3-132 AGING MANAGEMENT AGING REVIEW MANAGEMENT REVIEW Revision Page 3-132

FORT CALHOU.. .TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.5.2.09 Intake Structure cast iron Cast Iron Raw Water Loss of Material Structures Monitoring stuffing box floor

• Crevice and general Program (B.2.10) penetration corrosion due to oxy genated raw water environment

"* Pitting corrosion due to oxygenated raw water environment and stag nant or low flow condi tions

"* Galvanic corrosion due to the conductivity of the process fluid and dissimilar metals in contact

"* MIC due to exposure to microbiological activity 3.5.2.10 Concrete caissons Concrete Below Grade None Not Applicable Revision I1 Page 3-133 MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision Page 3-133

FORT CALHOUi, oTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.11 Concrete encased in Class Concrete Carbon Steel None Not Applicable B pipe piles is protected from aggressive environments. The concrete has a compressive strength of 4000 psi, a maximum water-to-cement ratio of 6 gallons/sack or 0.53, and the minimum cement content is 6.50 sacks/cubic yard. The aggregate used has been specified to be non-reactive when mixed with portland cement and water.

3.5.2.12 Pneumatic flood panel EPDM Rubber Plant Indoor Air None Not Applicable seals 3.5.2.13 Intake Structure EDPM EPDM Rubber Raw Water Change in Material Structures Monitoring rubber Link-Seal Properties due to chemical Program (B.2.10) exposure 3.5.2.14 Intake Structure raw water EPDM Rubber Raw Water Change in Material General Corrosion of pump rubber foundation Properties due to chemical External Surfaces seal exposure Program (B.3.3) 3.5.2.15 Glass in metal fire Glass Plant Indoor Air None Not Applicable penetration barriers Page 3-134 AGING REVIEW MANAGEMENT REVIEW AGING MANAGEMENT Revision I1 Revision Page 3-134

FORT CALHOU,, ,jTATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs Program/Activity Number 3.5.2.16 Intake Structure sand and Gravel Ambient Air Protected None Not Applicable gravel surrounding the from Weather diesel fire pump fuel storage tank 3.5.2.17 Manhole covers and flange Gray Cast Iron Ambient Air Loss of Material Periodic Surveillance General corrosion and and Preventive selective leaching due to Maintenance Program the exposure of external (B.2.7) surfaces to varying levels of humidity 3.5.2.18 Flood panel seals Neoprene Plant Indoor Air Change in Material Periodic Surveillance Properties and Preventive Due to the prolonged Maintenance Program exposure of neoprene to (B.2.7) temperatures above 95 deg F 3.5.2.19 Flood panel seals Neoprene Plant Indoor Air Cracking Periodic Surveillance Due to the prolonged and Preventive exposure of neoprene to Maintenance Program temperatures above 95 (B.2.7) deg F 3.5.2.20 Manhole foam blocks Polyurethane foam Ambient Air Protected Cracking Periodic Surveillance from Weather Due to vibration, and Preventive Mainte movement, and shrinkage nance Program (8.2.7)

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FORT CALHOIO.. jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.21 Manhole foam blocks Polyurethane foam Ambient Air Protected Separation Periodic Surveillance from Weather Due to vibration, and Preventive movement, and shrinkage Maintenance Program (B.2.7) 3.5.2.22 Auxiliary building pressure PVC Outside Air Change in Material Structures Monitoring relief panels Properties Program (B.2.10)

Due to ultraviolet (UV) radiation exposure 3.5.2.23 Auxiliary building pressure PVC Outside Air Cracking Structures Monitoring relief panels Due to ultraviolet (UV) Program (B.2.10) radiation exposure 3.5.2.24 Intake Structure stainless Stainless Steel Raw Water Loss of Material General Corrosion of steel raw water pump

• Crevice corrosion due External Surfaces gland bolting to the presence of dis- Program (B13.3) solved oxygen and impurities

"* MIC due to exposure to microbiological activity

"° Pitting corrosion due to (1) stagnant or low-flow conditions, and (2) halide ions, chlorides, bromides or hypochlo rites 3.5.2.25 Structural steel Stainless Steel Ambient Air None Not Applicable 3.5.2.26 Trisodium phosphate Stainless Steel Ambient Air None Not Applicable baskets AGING MANAGEMENT REVIEW Revision I Page 3-136

FORT CALHOt,. iTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-2 (CONTINUED)

AGING MANAGEMENT PROGRAMS FOR CONTAINMENT, STRUCTURES AND COMPONENTS THAT ARE NOT ADDRESSED IN NUREG-1801 Row Component Types Material Environment AERMs ProgramlActivity Number 3.5.2.27 Boot clamps for auxiliary Stainless Steel Ambient Air None Not Applicable building boot sealed fire penetration barrier 3.5.2.28 Structural steel, fuel Stainless Steel Borated treated water Loss of Material Structures Monitoring transfer penetration,

• Crevice corrosion due Program (B.2.10) and fasteners to an oxygenated Inservice Inspection treated water environ- Program (B.1.3) ment

. Pitting corrosion due to exposure to halogens and sulfates.

3.5.2.29 Not used in application 3.5.2.30 Radiant energy shield Carbon Steel Ambient Air Loss of Material Fire Protection Program sheet metal General corrosion due to (B.2.5) the exposure of external surfaces to varying levels of humidity.

3.5.2.31 Component Support Stainless Steel Borated treated water Cracking Chemistry Program Stainless Structural Steel Stress corrosion cracking (B.1.2) 3.5.2.32 Component Support Stainless Steel Ambient Air Cracking Bolting Integrity Program Stainless Steel Threaded Stress corrosion cracking (B. 1.1)

Fasteners 3.5.2.33 Intake Structure concreate Concrete Raw Water Loss of Material Structures Monitoring exposed to raw water Abrasion Program (B.2.10)

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FORT CALHOU,. .,TATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-3 COMPONENTS IN STRUCTURES AND COMPONENT SUPPORTS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCS Applicable Justification for applying Row Components Material Environment Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.5.3.01 Intake Bronze, Raw Water Loss of Selective 3.3.1.16 The FCS components are Structure Cast Iron Material Leaching 3.3.1.24 made of the same material, bronze sluice Due to Program exposed to the same gate operator Dezincification (B.3.6) environment, subject to the gland and same aging effects and gland bolting managed by the same aging and cast iron management program as stuffing box the components evaluated in floor NUREG-1801, Volume 2, penetrations VII.C1.2-a.

3.5.3.02 Steel spring Carbon Indoor Ambient Loss of Structures 3.5.1.25 The FCS components are support Steel Air Material Monitoring made of the same material, anchorage General Program exposed to the same Corrosion (B.2.10) environment, subject to the same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, Ill.1B4.1-a.

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FORT CALHO6.. ,*TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.5-3 (CONTINUED)

COMPONENTS IN STRUCTURES AND COMPONENT SUPPORTS NOT EVALUATED IN NUREG-1801 THAT RELY ON AGING MANAGEMENT PROGRAMS IN NUREG-1801 FOR FCS LICENSE RENEWAL FCS FCS FCS FCS AERMs FCS Applicable Justification for applying Row Components Material Environment Program NUREG-1801 NUREG-1801 Aging Number Activity Aging Management Review Management Results Review Results Row Number 3.5.3.03 Reactor cavity Stainless Plant Indoor Air/ Loss of Water 3.5.1.19 The FCS components are liner, reactor Steel Borated Water Material, Chemistry made of the same material, cavity seal ring, Cracking Program exposed to the same fuel transfer (B.1.2) and environment, subject to the penetration monitoring same aging effects and of spent managed by the same aging fuel pool management program as water level the components evaluated in NUREG-1801, Volume 2, III.A5.2-b.

3.5.3.04 Containment Masonry Plant Indoor Air Cracking Structures 3.5.1.20 The FCS components are Ungrouted Monitoring made of the same material, Masonry Block Program exposed to the same Walls in environment, subject to the Ambient Air same aging effects and managed by the same aging management program as the components evaluated in NUREG-1801, Volume 2, IIl.A3.3-a.

Revision II Page 3-139 AGING MANAGEMENT AGING REVIEW MANAGEMENT REVIEW Revision Page 3-139

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.6 AGING MANAGEMENT OF ELECTRICAL AND INSTRUMENTATION AND CONTROLS The components for FCS evaluated in this section of the application consist of the electrical cables, connectors, splices, fuse blocks, terminal blocks, electrical penetrations, and electrical bus bars subject to aging management review.

Cables and their associated connectors perform the function of providing electrical energy (either continuously or intermittently) to power various equipment and components throughout the plant. Cables and connectors associated with the 10 CFR 50.49 program (Environmental Qualification) are addressed either as short lived, periodically replaced, or long-lived Time Limited Aging Analysis (TLAA) candidates; as such, those candidates are not included in the set of cables and connectors requiring additional aging management review.

Electrical penetrations electrically connect specified sections of an electrical circuit through the containment boundary to deliver voltage, current or signal while maintaining the integrity of containment. The pigtail at each end of the penetration is connected to the field cable by industry accepted methods such as connectors, terminal blocks or splice connections. Non-EQ electrical penetrations will be assessed in a similar manner to the non-EQ cable and connectors requiring additional aging management review.

Bus bars electrically connect specified sections of an electrical circuit to deliver voltage, current or signal. The standoffs support the electrical bus bars. This assessment includes the bus bars located in the 480-volt motor control centers. No aging effects requiring management were identified for this group.

Operating Experience:

Site: A review of plant specific operating experience was conducted, including the review of Condition Reports and discussions with appropriate site personnel to identify AERM. These reviews concluded that the AERM identified by the FCS specific operating experience were consistent with those identified in NUREG-1 801.

Industry: A review of industry-wide operating experience was conducted to identify aging effects requiring management. This included a review of operating experience issued during 2001. This review concluded that the AERM identified by industry operating experience were consistent with those identified in NUREG-1801.

On-Going: The on-going review of plant specific and industry-wide operating experience is conducted in accordance with the FCS Operating Experience Program.

I Page 3-140 AGING REVIEW MANAGEMENT REVIEW Revision Revision I AGING MANAGEMENT Page 3-140

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.6.1 AGING MANAGEMENT PROGRAMS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR LICENSE RENEWAL Table 3.6-1 shows the aging management groups (combinations of components, materials and environments) and the aging management programs evaluated in NUREG-1801 that are relied on for license renewal of the Electrical and Instrumentation and Controls Systems at FCS. Information on FCS specific components, materials and aging effects, not listed in NUREG-1801 but included in the component group of this application, is included in the discussion column.

I Page 3-141 MANAGEMENT REVIEWREVIEW Revision Revision I AGING MANAGEMENT AGING Page 3-141

FORT CALHOUN,% jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.6-1

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROLS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Management Evaluation Component Aging Effect/Mechanism Programs Recommended Discussion 3.6.1.01 Electrical Degradation due to various Environmental Yes, TLAA The environmental qualification equipment subject aging mechanisms qualification of time limited aging analyses are to 10 CFR 50.49 electric discussed in Section 4.4 of this environmental components application.

qualification (EQ) requirements 3.6.1.02 Electrical cables Embrittlement, cracking, Aging No Addressed in FCS Plant Specific and connections melting, discoloration, swelling, management Non-EQ Cable Aging not subject to 10 or loss of dielectric strength program for Management Program (B.3.4),

CFR 50.49 EQ leading to reduced insulation electrical cables which is described in Appendix B requirements resistance (IR); electrical and connections of this application.

failure caused by thermal/ not subject to thermoxidative degradation of 10 CFR 50.49 organics; radiolysis and EQ requirements photolysis (ultraviolet [UV]

sensitive materials only) of organics; radiation-induced oxidation; moisture intrusion Page 3-142 AGING AGING MANAGEMENT MANAGEMENT REVIEW REVIEW Revision II Revision Page 3-142

FORT CALHOUh. 4TATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.6-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROLS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Management Evaluation Component Aging Effect/Mechanism Programs Recommended Discussion 3.6.1.03 Electrical cables Embrittlement, cracking, Aging No Addressed in FCS Plant Specific used in melting, discoloration, swelling, management Non-EQ Cable Aging instrumentation or loss of dielectric strength program for Management Program (B.3.4),

circuits not subject leading to reduced IR; electrical cables which is described in Appendix B to 10 CFR 50.49 electrical failure caused by used in of this application.

EQ requirements thermal/ thermoxidative instrumentation that are sensitive degradation of organics; circuits not subject to reduction in radiation-induced oxidation; to 10 CFR 50.49 conductor moisture intrusion EQ requirements insulation resistance 3.6.1.04 Inaccessible Formation of water trees; Aging No Modifications were made to the medium-voltage localized damage leading to management Duct Banks to preclude moisture (2kV to 15kV) electrical failure (breakdown of program for intrusion; therefore, there is no cables (e.g., insulation) caused by moisture inaccessible aging effect requiring installed in conduit intrusion and water trees medium-voltage management.

or direct buried) cables not subject not subject to 10 to 10 CFR 50.49 CFR 50.49 EQ EQ requirements requirements Page 3-143 REVIEW MANAGEMENT REVIEW AGING MANAGEMENT AGING Revision II Revision Page 3-143

FORT CALHOU. .jTATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION TABLE 3.6-1 (CONTINUED)

SUMMARY

OF AGING MANAGEMENT PROGRAMS FOR ELECTRICAL AND INSTRUMENTATION AND CONTROLS EVALUATED IN NUREG-1801 THAT ARE RELIED ON FOR FCS LICENSE RENEWAL Row Aging Further Number Management Evaluation Component Aging Effect/Mechanism Programs Recommended Discussion 3.6.1.05 Electrical Corrosion of connector contact Boric acid No 1. The aging management connectors not surfaces caused by intrusion of corrosion results are consistent with the subject to borated water results documented in 10 CFR 50.49 EQ NUREG-1801.

requirements that 2. Consistent with NUREG are exposed to 1801, this group includes borated water leak- connectors exposed to age borated water leakage at FCS.

Page 3-144 AGING AGING MANAGEMENT REVIEWREVIEW Revision II Revision Page 3-144

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION 3.6.2 COMPONENTS OR AGING EFFECTS THAT ARE NOT ADDRESSED IN NUREG-1801 All components subject to aging management review and aging effects for FCS Electrical and Instrumentation and Controls systems are addressed in Section 3.6.1.

Page 3-145 REVIEW MANAGEMENT REVIEW Revision II Revision Page 3-145 AGING MANAGEMENT AGING

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION APPENDIX A - UPDATED SAFETY ANALYSIS REPORT (USAR) SUPPLEMENT A.1 INTRODUCTION The application for a renewed operating license is required by 10 CFR 54.21(d) to include "an FSAR Supplement." This appendix provides that supplement for the FCS USAR. Section 2 of this appendix contains a summarized description of the programs and activities for managing the effects of aging. Section 3 of this appendix contains a summary of the evaluation of time-limited aging analyses (TLAAs) for the period of extended operation.

A.2 PROGRAMS AND ACTIVITIES FOR MANAGING THE EFFECTS OF AGING This section provides summaries of the programs and activities credited for managing the effects of aging, in alphabetical order. The FCS Quality Assurance Program implements the requirements of 10 CFR 50, Appendix B, and is consistent with the summary in Section A.2 of NUREG 1800, StandardReview Plan for the Review of License Renewal Applications for NuclearPowerPlants, published July 2001. The Quality Assurance Program includes the elements of corrective action, confirmation process, and administrative controls, and is applicable to the safety-related and non safety-related structures, systems, and components that are within the scope of license renewal.

A.2.1 ALLOY 600 PROGRAM The Alloy 600 Program includes a primary water stress corrosion cracking (PWSCC) susceptibility assessment to identify susceptible components and inservice inspection (ISI) of Reactor Coolant System penetrations to monitor PWSCC and its effect on the intended function of the component. For susceptible penetrations and locations, the program includes an industry-wide, integrated, long-term inspection program based on the industry response to NRC Generic Letter (GL) 97-01, Degradationof Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations.

A.2.2 BOLTING INTEGRITY PROGRAM The Bolting Integrity Program includes periodic inspection of closure and structural bolting for indications of potential problems, including loss of material, crack initiation, and loss of preload. The program implements guidelines on materials selection, strength and hardness properties, installation procedures, lubricants and sealants, corrosion considerations in the selection and installation of pressure-retaining bolting, and enhanced inspection techniques. The program is based on (1) the bolting integrity program delineated in NUREG-1339, Resolution of Generic Safety Issue 29: Bolting Degradiationor Failure in Nuclear Power Plants; (2) industry's recommendations Page A-I SUPPLEMENT USAR SUPPLEMENT Revision I1 Revision Page A-1

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION delineated in ERPRI NP-5769, Degradationand Failure of Bolting in Nuclear Power Plants, with the exceptions noted in NUREG-1339 for safety-related bolting; (3) EPRI TR-1 04213, Bolted Joint Maintenance and Application Guide, for pressure retaining bolting and structural bolting; and (4) routine examinations and inspections performed in accordance with the requirements of ASME Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components.

A.2.3 BORIC ACID CORROSION PREVENTION PROGRAM The Boric Acid Corrosion (BAC) Prevention Program implements administrative controls to (1) perform visual inspections of external surfaces that are potentially exposed to borated water leakage, (2) ensure timely discovery of leak path and removal of the boric acid residues, (3) perform assessments of degradation, and (4) perform follow-up inspections for adequacy of corrective actions. The program is implemented in response to NRC GL 88-05, Boric Acid Corrosionof Carbon Steel Reactor PressureBoundary Components in PVVR Plants.

A.2.4 BURIED SURFACES EXTERNAL CORROSION PROGRAM The Buried Surfaces External Corrosion Program provides for inspection of buried piping, tanks, and valves whenever they are uncovered due to excavation for maintenance or modifications. Piping and component coatings and wrappings will be inspected for degraded conditions that could be indicative of possible surface corrosion of the protected metal beneath. The scope and periodicity of inspections will be established and/or adjusted based on the inspection results.

A.2.5 CHEMISTRY PROGRAM The FCS Chemistry Program controls water chemistry to minimize contaminant concentration and provide chemical additions, such as corrosion inhibitors and biocides, to mitigate aging effects due to corrosion. The program includes specifications for chemical species, limits, representative sampling and analysis frequencies, and corrective actions for control of water chemistry. The program is based on EPRI Guidelines TR-105714, PWR PrimaryWater Chemistry Guidelines, for primary water chemistry, TR-102134, PWR Secondary Water Chemistry Guideline,for secondary water chemistry, and TR-1 07396, Closed Cooling Water Chemistry Guideline,for closed cycle cooling water corrosion inhibitor concentration.

A.2.6 CONTAINMENT INSERVICE INSPECTION PROGRAM The Containment Inservice Inspection Program implements the examination requirements of ASME Section XI, Rules for Inservice Inspection of Nuclear PowerPlant Components, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants, and Subsection IWL, Requirements for Class CC Concrete Components of Light-Water Cooled Power Plants, for the containment structure and support components. The ASME Section XI, USAR SUPPLEMENT Revision I Page A-2

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION Subsection IWL program consists of periodic visual inspection of concrete surfaces and periodic visual inspection and sample tendon testing for signs of degradation, assessment of damage, and corrective actions. Measured tendon lift-off forces are compared to predicted tendon forces calculated in accordance with NRC Regulatory Guide (RG) 1.35, Inservice Inspection of Ungrouted Tendons in PrestressedConcrete Containments.The ASME Section XI, Subsection IWE program consists of periodic visual, surface, and volumetric inspection of pressure retaining components for signs of degradation, assessment of damage and corrective actions. This program is in accordance with the requirements of 10 CFR 50.55a and ASME Section XI, Subsections IWE and IWL, 1992 edition including 1992 addenda.

A.2.7 CONTAINMENT LEAK RATE PROGRAM The Containment Leak Rate Program implements the requirements of 10 CFR Part 50, Appendix J, as well as those examination requirements needed to comply with ASME Section XI, Subsection IWE, RG 1.163, Performance-BasedContainment Leak-Test Program,and NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part50 Appendix J, Rev. 0 for the containment structure and pressure retaining components. The program consists of monitoring of leakage rates through containment liner/welds, penetrations, fittings, and other access openings for detecting degradation of the containment pressure boundary. Corrective actions are taken if leakage rates exceed acceptance criteria.

A.2.8 COOLING WATER CORROSION PROGRAM The Cooling Water Corrosion Program monitors and detects aging effects through inspection and nondestructive evaluations. The program also involves some mitigation activities of periodic flushing and draining. The program's aging management activities are based on EPRI TR-1 07396, Closed Cooling Water Chemistry Guideline, for closed cycle cooling water systems and NRC GL 89-13, Service Water System Problems Affecting Safety-Related Equipment, for open-cycle cooling water systems.

A.2.9 DIESEL FUEL MONITORING AND STORAGE PROGRAM The FCS Diesel Fuel Monitoring and Storage Program monitors and controls diesel fuel quality regarding water and other contaminants in accordance with the guidelines of ASTM Standards D2709, Standard Test Method for Water and Sediment in Middle Distillate Fuels by Centrifuge, and D4057, Standard Practicefor Manual Sampling of Petroleum and Petroleum Products.Exposure to fuel oil contaminants such as water and microbiological organisms is minimized by removal of water and sediment from tanks and by verifying the quality of new fuel oil before its introduction into the storage tanks.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.2.10 FATIGUE MONITORING PROGRAM The Fatigue Monitoring Program provides for the monitoring of reactor coolant and associated systems thermal fatigue, pressurizer surge line thermal stratification, and thermal fatigue of selected Class II and III components over the life of the plant to ensure that their operation does not result in exceeding the number of design basis transients included in the design basis of their respective design codes. It will be centered on the industry's automated cycle counting software, FatiguePro. Plant locations that cannot be counted automatically will continue to be counted manually. An FCS site specific evaluation is being performed to address environmental fatigue. Appropriate program enhancements will be made prior to the period of extended operation based on the evaluation results.

A.2.11 FIRE PROTECTION PROGRAM The FCS Fire Protection Program provides administrative requirements for ensuring the operability of fire protection equipment required to ensure plant safe shutdown. The program includes visual inspections, system flushing, and performance tests of fire barriers (penetration seals, fire doors, walls, ceilings, and floors), fire suppression system components (piping, valves, nozzles, yard hydrants and hose stations, sprinkler heads, and halon systems and cylinders), and the diesel fire pump. The FCS Fire Protection Program includes the requirements identified in Appendix A to NRC Branch Technical Position APCSB 9.5-1 and 10 CFR 50 Appendix R, Section Ill.G, J, and 0 and is further described in Section 9.11 of the USAR.

A.2.12 FLOW ACCELERATED CORROSION PROGRAM The FCS Flow Accelerated Corrosion (FAC) Program implements administrative controls to conduct appropriate analysis and baseline inspections, determine extent of thinning, replace/repair components, and perform follow-up inspections to confirm or quantify and take longer-term corrective actions. The program relies on implementation of EPRI guidelines of NSAC-202L-R2, Recommendations for an Effective Flow-Accelerated CorrosionProgram.

A.2.13 GENERAL CORROSION OF EXTERNAL SURFACES PROGRAM The General Corrosion of External Surfaces Program implements systematic inspections and observations to detect corrosion of external surfaces and conditions that can result in corrosion such as damaged coatings and fluid leaks. Inspections and observations include (1) rounds by operators, (2) system engineer walkdowns, and (3) refueling interval inspections inside containment in accordance with RG 1.54, QualityAssurance Requirements for Protective Coatings Applied to Water - Controlled NuclearPower Plants.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.2.14 INSERVICE INSPECTION PROGRAM The Fort Calhoun Station Inservice Inspection Program implements the examination requirements of the ASME Section XI, Rules for Inservice Inspection of NuclearPower Plant Components, Subsections IWB, IWC, IWD, IWF. The program consists of periodic volumetric, surface and/or visual examination of components and their supports for assessment, signs of degradation, and corrective actions. This program is in accordance with ASME Section XI, 1995 edition through the 1996 addenda.

A.2.15 NON-EQ CABLE AGING MANAGEMENT PROGRAM The FCS Non-EQ Cable Aging Management Program establishes a service life value for the Non-EQ cable in a similar fashion as the FCS EQ Program establishes a Qualified Life for the safety related equipment, components, and cable. Corrective actions for Non EQ Cable, determined not to meet the operational (Service Life) requirements established for the full period of extended operation, will consider using: (1) state of the art analytical techniques to determine if the service life can be further extended; (2) industry accepted and regulatory approved cable inspection techniques that provide aging related data; and/or (3) state of the art, in-situ, non-destructive testing of cable performance, and/or laboratory testing of cable to extend life. Cable replacement will be considered should the aforementioned methodologies not succeed in extending the required service life.

A.2.16 ONE-TIME INSPECTION PROGRAM The FCS One-Time Inspection Program is a new program that will implement a one-time inspection of internal surfaces of selected components to verify the effectiveness of mitigating programs such as the chemistry and diesel fuel oil programs. Inspections will be performed using suitable techniques at the most susceptible locations to verify that aging effects are not occurring or that the aging effect is progressing at such a slow rate it will not impact the intended function during the period of extended operation.

A.2.17 OVERHEAD LOAD HANDLING SYSTEMS INSPECTION PROGRAM The Overhead Load Handling Systems Inspection Program implements FCS commitments made in response to NRC GL 81-07, Controlof Heavy Loads at Nuclear Power Plants,and the maintenance monitoring requirements of 10 CFR 50.65. The program includes assessment of crane lift capabilities, periodic inspections of structural components, and functional tests to assure their integrity.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.2.18 PERIODIC SURVEILLANCE AND PREVENTIVE MAINTENANCE PROGRAM The Periodic Surveillance and Preventive Maintenance Program provides for periodic inspections and examinations of specific system and structural components using established NDE techniques. The inspection and examination techniques used and the periodicity of their performance provide reasonable assurance that age related degradation will not compromise the structure or component intended function(s) before the next scheduled inspection.

A.2.19 REACTOR VESSEL INTEGRITY PROGRAM The Reactor Vessel Integrity Program monitors the extent of changes in material properties and loss of fracture toughness of irradiated reactor pressure vessel materials by periodic removal and testing of surveillance capsules located within the reactor vessel in accordance with RG 1.99, Radiation Embrittlement of Reactor Vessel Materials, Rev.

2. The surveillance capsule removal and evaluation is an NRC-approved program that meets the requirements of 10 CFR 50, Appendix H. The program includes revising the FCS surveillance capsule removal schedule in order to optimize the program through the end of the period of extended operation. In addition, the program verifies 10 CFR 50, Appendix G and 10 CFR 50.61 requirements.

A.2.20 REACTOR VESSEL INTERNALS INSPECTION PROGRAM The Reactor Vessel (RV) Internals Inspection Program includes the following elements for cast austenitic stainless steel (CASS) and other reactor vessel internal components:

(a) determination of the susceptibility of CASS components to thermal aging and neutron irradiation embrittlement, (b) identification of the most susceptible or limiting items, (c) development of appropriate inspection techniques to permit detection and characterizing of the feature (cracks) of interest and demonstrate the effectiveness of the proposed technique, and (d) implementation of required inspections prior to the period of extended operation.

A.2.21 SELECTIVE LEACHING PROGRAM The FCS Selective Leaching Program implements inspection requirements for susceptible components for indication of selective leaching through dezincification or graphitization.

A.2.22 STEAM GENERATOR PROGRAM The FCS Steam Generator Program consists of inspection scope, frequency, and acceptance criteria for various steam generator components, including the plugging and repair of flawed tubes in accordance with the plant Technical Specifications and the guidance of NEI 97-06, Steam GeneratorProgram Guidelines.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.2.23 STRUCTURES MONITORING PROGRAM The Structures Monitoring Program provides for periodic visual inspection of designated FCS structures and component supports to ensure that aging degradation will be detected, evaluated, and repaired prior to any loss of intended functions. The inspection requirements are based on the following industry documents: NRC Bulletin 80-11, Masonry Wall Design; N RC IN 87-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11; NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants(Line-In/Line Out Version), Rev. 2; and NRC RG 1.160, Monitoring the Effectiveness of Maintenance at Nuclear PowerPlants, Rev. 2.

A.2.24 THERMAL AGING EMBRITTLEMENT OF CAST AUSTENITIC STAINLESS STEEL PROGRAM The Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program includes evaluation of the reactor coolant piping as bounded by the Leak-Before-Break (LBB) analysis, assessment of other CASS components for susceptibility to thermal embrittlement, and performance of volumetric inspection of piping or component-specific flaw tolerance evaluation for susceptible components.

A.3 EVALUATION OF TIME-LIMITED AGING ANALYSES A.3.1 REACTOR VESSEL NEUTRON EMBRITTLEMENT There are four analyses affected by neutron embrittlement that have been identified as TLAAs:

• Pressure/Temperature (P/T) Curves

• Low Temperature Overpressure Protection (LTOP) Power Operated Relief Valve (PORV) Setpoints

• Pressurized Thermal Shock (PTS)

• Reactor Vessel Upper Shelf Energy A.3.1.1 PRESSUREITEMPERATURE (PIT) CURVES Appendix G to 10 CFR 50 requires that PT limits be established during all phases of reactor operation and that thermal stresses be limited by determining maximum heatup and cooldown rates. The current pressure/temperature analyses are valid out to 40 effective full power years, which extends beyond the current operating license period but not to the end of the period of extended operation. The Technical Specifications will continue to be updated as required by either Appendices G or H of 10 CFR 50, or as operational needs dictate. This will assure that operational limits remain valid for current and projected cumulative neutron fluence levels. Therefore, the analyses will be projected to the end of the period of extended operation.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.3.1.2 LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) PORV SETPOINTS Low temperature overpressure protection limits are considered as part of the calculation of pressure/temperature curves. Loss of ductility at low temperatures due to neutron embrittlement must be evaluated during the period of extended operation. Therefore, the LTOP analyses will be projected to the end of the period of extended operation.

A.3.1.3 PRESSURIZED THERMAL SHOCK (PTS) 10 CFR 50.61 addresses another issue related to embrittlement and thermal stress called Pressurized Thermal Shock (PTS). Irradiation makes the vessel's beltline more susceptible to cracking during a pressurized thermal shock event. The parameter describing this fracture potential is called the transition temperature (or RTPTS) and it corresponds to the nil ductility reference temperature for the most limiting beltline material. It is a function of the projected fluence values and is calculated using guidance in Regulatory Guide 1.99, revision 2. Applicants are obligated to project the values of the increasing transition temperature into the period of extended operation.

OPPD has completed the projected calculation and the NRC has concluded that RTPTS for the FCS reactor vessel will remain below the 10 CFR 50.61 PTS screening criteria until 2033, the end of the proposed license renewal period. Therefore, the analyses have been projected to the end of the period of extended operation.

A.3.1.4 REACTOR VESSEL UPPER SHELF ENERGY Upper shelf energy is a measure of fracture toughness at temperatures above RTpTS when the vessel is exposed to neutron radiation. The screening criteria for the increase in transition temperature are found in 10 CFR 50.61. The screening criterion for the decrease in upper shelf energy is found in 10 CFR 50, Appendix G.

Preliminary calculations have shown that the vessel beltline Charpy upper-shelf energy for the limiting weld will be approximately 54.6 ft-lbs, based on position 1.2 of RG 1.99.

This value remains above the regulatory approved minimum of 50 ft-lbs through the period of extended operation. The existing Appendix G analysis will be finalized and formally revised to reflect that it bounds the minimum approved fluence value at the end of plant life. Therefore, the analyses will be projected to the end of the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.3.2 METAL FATIGUE There are three distinct issues considered separately under the TLAA for Metal Fatigue:

• Reactor Coolant and associated systems thermal fatigue,

• Pressurizer Surge Line Thermal Stratification, and

• Fatigue of Class II and III components.

Each of these issues is managed by the Fatigue Monitoring Program which is addressed in Section A.2. 10 of this Appendix.

A.3.3 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 10 CFR 50.49 requires that certain safety related and non-safety related electrical equipment remains functional during and after identified Design Basis Events (DBEs).

For the period of extended operation, Environmental Qualification (EQ) is a TLAA affecting all equipment in the scope of the EQ program, with a qualified life longer than the original license period but shorter than the combined original license period plus the period of extended operation, whether active or passive.

The FCS Electrical Equipment Qualification (EEQ) Program has been demonstrated to be capable of programmatically managing the qualified lives of EQ components within the scope of license renewal. The NRC has determined that the EEQ Program is an acceptable program to address environmental qualification in accordance with 10 CFR

54. The FCS EEQ Program will provide for extension of the qualification to the end of the period of extended operation. Therefore, the effects of aging on the intended functions will be adequately managed for the period of extended operation.

A.3.4 CONCRETE CONTAINMENT TENDON PRE-STRESS The containment wall and dome were pre-stressed by means of unbonded post tensioned tendons. The pre-stress on the containment tendons decreases over plant life as a result of elastic deformation, creep and shrinkage of concrete, anchorage seating losses, tendon wire friction, stress relaxation and corrosion. Pre-stressing tendon integrity is monitored and confirmed by a regular program of tendon surveillance. Curves showing anticipated variation of tendon force with time, together with the lower limit curves to be applied to surveillance readings are shown in the FCS USAR. The calculated pre-stress at end of plant life exceeds by a reasonable margin the intensity required to meet the design criteria.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The USAR curves will be extended to 60 years of plant life to cover the period of extended operation. This will also show that the pre-stressing force is acceptable for continued service at the end of the period of extended operation considering the assumed time dependent nature of pre-stress losses. The tendon surveillance program will be continued into the period of extended operation using the updated curves.

Therefore, the effects of aging on the intended function(s) will be adequately managed for the period of extended operation.

A.3.5 CONTAINMENT LINER PLATE AND PENETRATION SLEEVE FATIGUE The containment liner and penetration sleeves were designed to be leak-tight under all postulated loading combinations by limiting strains to those values that have been shown to result in leak-tight pressure vessels. The results of the containment fatigue analysis indicated that when the maximum compressive strain in the liner was reached under operating conditions and subsequent cyclic temperature variations were applied to the liner, there was no significant change in stress and strain in concrete or steel for the second cyclic load indicating that shakedown had occurred during the first cycle of loading. Also, the investigation for 500 cycles of loading for the liner steel, anchor steel and anchor welds resulted in a computed cumulative usage factor of 0.05 as compared with an allowable usage factor of 1.0. Consideration of 60 years of operation as opposed to 40 would have no relevant impact on these results. However, the observed buckling of the liner is slightly larger than was assumed in the original analyses. This condition has been evaluated and found adequate for the current term. FCS will complete an analysis considering the actual bulges for a 60-year life. The analysis will be completed before the beginning of the period of extended operation. Therefore, the analysis will be projected to the end of the period of extended operation.

A.3.6 PLANT-SPECIFIC TIME-LIMITED AGING ANALYSES A.3.6.1 REACTOR COOLANT PUMP FLYWHEEL FATIGUE A.3.6.1.1 GENERAL ELECTRIC RCP FLYWHEELS The resistance to rupture of the reactor coolant pump flywheels has been examined at 120 percent overspeed. The conclusion was that over 185,000 complete cycles from zero to 120 percent overspeed would be required to cause a crack to grow to critical size.

This number of cycles will not be exceeded if the licensing period is extended to 60 years. To do so would require in excess of 8 pump starts per day, which far exceeds actual and projected pump use. Since the cycle limit will not be exceeded, the analysis for the General Electric produced RCP flywheels remains valid for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION A.3.6.1.2 ASEA BROWN BOVERI (ABB) MOTOR FLYWHEEL During the 1996 refueling outage, reactor coolant pump RC-3B motor was replaced with a motor manufactured by ABB Industries. A crack growth analysis was performed which demonstrated that critical flaw growth would not occur with fewer than 10,000 complete cycles from zero to 120 percent overspeed.

This number of cycles will not be exceeded if the licensing period is extended to 60 years. To do so would require approximately 1 pump start every 2 days, which far exceeds actual and projected pump use. Since the cycle limit will not be exceeded, the analysis for the ABB produced RCP flywheel remains valid for the period of extended operation.

A.3.6.2 LEAK BEFORE BREAK (LBB) ANALYSIS FOR RESOLUTION OF USI A-2 There are two TLAA aspects to LBB, crack growth and thermal aging. While transient cycle fatigue crack growth is a TLAA for FCS and also a design consideration, thermal aging was not evaluated for FCS by either the original design code or the LBB analysis.

Consequently, OPPD will perform a plant-specific LBB analysis prior to the period of extended operation. This analysis will consider a 60-year life and thermal aging effects of the CASS RCS and will be completed before the beginning of the period of extended operation. Therefore, the analysis will be projected to the end of the period of extended operation.

A.3.6.3 HIGH ENERGY LINE BREAK (HELB)

The High Energy Line Break (HELB) analysis is a potential TLAA because postulated fatigue cumulative usage factors (CUFs) based on 40 years of operation may be used as screening criteria to determine piping locations that require further analysis regarding the effects of pipe ruptures outside the Containment Structure. For FCS, the Main Steam (MS) and Main Feedwater (MFW) systems contain piping for which CUFs have been evaluated for screening.

Fatigue analyses were previously performed for the B31.7 Class I portions of MS and MFW outside the Containment Structure to identify locations with cumulative usage factors greater than 0.1 as one of the criteria for selecting postulated break locations.

The Class I portions encompass the piping from the Containment Structure penetrations to the first isolation valves outside the Containment Structure.

For the Class I MFW piping, projection of the CUFs for the period of extended operation does not require either any additional pipe break analysis to be performed or hardware to be installed on the Class I portions of MFW outside the Containment Structure. Also, for the Class I MS piping, projection of the CUFs for the period of extended operation will not require any additional pipe break analysis to be performed or hardware to be installed on the Class I portions of MS outside the Containment Structure.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The circumferential breaks, already postulated, are bounding for all nodes with respect to direction and magnitude of force. Consideration of the period of extended operation will not impact the selection of the bounding locations. The barrel slats, which cover the piping segments, restrain longitudinal movements and jets along the length of the Class I pipe, not just at the postulated break points. In summary, projection of the CUFs used as HELB screening criteria for the period of extended operation will not require any additional pipe break analysis to be performed or hardware to be installed on the Class I piping. The CUFs are in fact not part of the actual analysis, but only represent screening criteria used to select bounding locations. Therefore, the analysis remains valid for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION APPENDIX B - AGING MANAGEMENT ACTIVITIES INTRODUCTION The aging management activity descriptions are provided in this appendix for each activity credited for managing aging effects based upon the aging management review results provided in Sections 3.1 through 3.6.

The FCS Quality Assurance Program implements the requirements of 10 CFR 50, Appendix B, and is consistent with the summary in Appendix A.2 of NUREG-1 800. The Quality Assurance Program includes the elements of corrective action, confirmation process, and administrative controls, and is applicable to the safety-related and non-safety-related structures, systems, and components that are subject to aging management review.

In many cases, existing activities were found adequate for managing aging effects during the period of extended operation. In some cases, aging management reviews revealed that existing activities should be enhanced to adequately manage aging. In a few cases, new activities were developed to provide reasonable assurance that aging effects are adequately managed.

Each aging management activity presented in this appendix is characterized as one of the following:

Existing Activity: A current activity that will continue to be implemented during the period of extended operation.

Enhanced Activity: A current activity that will be modified to manage aging during the period of extended operation.

New Activity: An activity that does not currently exist, which will manage aging during the period of extended operation.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The following aging management activities are described in the sections listed in this appendix. Site specific programs are indicated. All other programs correlate to some degree with programs in NUREG-1 801.

Existing Aging Management Activities B.1.1 Bolting Integrity Program B. 1.2 Chemistry Program B. 1.3 Containment Inservice Inspection Program B. 1,4 Containment Leak Rate Program B. 1.5 Flow Accelerated Corrosion Program B. 1.6 Inservice Inspection Program B. 1.7 Reactor Vessel Integrity Program Enhanced Aging Management Activities B.2.1 Boric Acid Corrosion Prevention Program B.2.2 Cooling Water Corrosion Program B.2.3 Diesel Fuel Monitoring and Storage Program B.2.4 Fatigue Monitoring Program B.2.5 Fire Protection Program B.2.6 Overhead Load Handling Systems Inspection Program B.2.7 Periodic Surveillance and Preventive Maintenance Program (site specific program)

B.2.8 Reactor Vessel Internals Inspection Program B.2.9 Steam Generator Program B.2.10 Structures Monitoring Program New Aging Management Activities B.3.1 Alloy 600 Program B.3.2 Buried Surfaces External Corrosion Program B.3.3 General Corrosion of External Surfaces Program (site specific program)

B.3.4 Non-EQ Cable Aging Management Program (site specific program)

B.3.5 One-Time Inspection Program B.3.6 Selective Leaching Program B.3.7 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel AGING MANAGEMENT ACTIVITIES Revision 1 Page B-2

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION Correlation between NUREG-1801 (Generic Aging Lessons Learned (GALL)) programs and FCS programs are shown below. For the FCS Programs, appropriate references to sections of this application are provided.

XI.M1 ASME Section Xl Inservice Inspec Inservice Inspection Program (B.1.6) I tion, Subsection IWB, IWC, IWD XI.M2 Water Chemistry Chemistry Program (B.1.2)

XI.M3 Reactor Head Closure Studs Bolting Integrity Program (B. 1.1)

XI.M4 BWR Vessel ID Attachment Welds Not applicable, FCS is a PWR.

XI.M5 BWR Feedwater Nozzle Not applicable, FCS is a PWR.

XI.M6 BWR Control Rod Drive Return Line Not applicable, FCS is a PWR.

Nozzle XI.M7 BWR Stress Corrosion Cracking Not applicable, FCS is a PWR.

XI.M8 BWR Penetrations Not applicable, FCS is a PWR.

XI.M9 BWR Vessel Internals Not applicable, FCS is a PWR.

XI.M10 Boric Acid Corrosion Boric Acid Corrosion Prevention Pro gram (B.2.1)

XI.M11 Nickel-Alloy Nozzles and Penetra- Alloy 600 Program (B. 3. 1) tions XI.M12 Thermal Aging Embrittlement of Cast Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Austenitic Stainless Steel (CASS)

(B.3.7)

XI.M13 Thermal Aging and Neutron Irradia- Reactor Vessel Internals Inspection tion Embrittlement of Cast Austenitic Program (B.2.8)

Stainless Steel (CASS)

XI.M14 Loose Part Monitoring Not credited for aging management.

Reactor vessel internals inspections were determined to be adequate to manage identified aging effects.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION XI.M15 Neutron Noise Monitoring Reactor vessel internals vibration monitoring is a current FCS licensing commitment. The implementing task is incorporated in the Reactor Vessel Internals Inspection Program (B.2.8).

XI.M16 PWR Vessel Internals Reactor Vessel Internals Inspection Program (B.2.8)

XI.M 17 Flow-Accelerated Corrosion Flow-Accelerated Corrosion Program (B.1.5)

XI.M18 Bolting Integrity Bolting Integrity Program (B.1.1)

XI.M19 Steam Generator Tube Integrity Steam Generator Program (B.2.9)

XI.M20 Open-Cycle Cooling Water System Cooling Water Corrosion Program (B.2.2)

XI.M21 Closed-Cycle Cooling Water System Cooling Water Corrosion Program (B.2.2)

XI.M22 Boraflex Monitoring Not applicable, FCS does not have Boraflex.

XI.M23 Inspection of Overhead Heavy Load Overhead Loading Handling Sys and Light Load (Related to Refuel- tems Inspection Program (B.2.6) ing) Handling Systems XI.M24 Compressed Air Monitoring Not credited for aging management.

No aging effects requiring manage ment were identified for the Com pressed Air System.

XI.M25 BWR Reactor Water Cleanup Sys- Not applicable, FCS is a PWR.

tem XI.M26 Fire Protection Fire Protection Program (B.2.5)

XI.M27 Fire Water System Fire Protection Program (B.2.5)

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION XI.M28 Buried Piping and Tanks Surveil Not credited for aging management.

lance FCS cathodic protection was not credited for managing aging effects.

The FCS aging management pro gram was based on the requirements of NUREG-1801 XI.M34.

XI.M29 Aboveground Carbon Steel Tanks Not credited for aging management.

Steel tanks were not treated as sepa rate components from their respec tive systems. Applicable aging management activities have been incorporated into programs credited for similar component, material, and environments in the system.

XI.M30 Fuel Oil Chemistry Diesel Fuel Monitoring and Storage Program (B.2.3)

XI.M31 Reactor Vessel Surveillance Reactor Vessel Integrity Program (B.1.7)

XI.M32 One-Time Inspection One-Time Inspection Program (B.3.5)

XI.M33 Selective Leaching of Materials Selective Leaching Program (B.3.6)

XI.M34 Buried Piping and Tanks Inspection Buried Surfaces External Corrosion Program (B.3.2)

XI.E1 Electrical Cables and Connections Plant Specific Program - Non-EQ Not Subject to 10 CFR 50.49 Envi- Cable Aging Management Program ronmental Qualification Require- (B.3.4) ments XI.E2 Electrical Cables Not Subject to 10 Plant Specific Program - Non-EQ CFR 50.49 Environmental Qualifica- Cable Aging Management Program tion Requirements Used in Instru- (B.3.4) mentation Circuits Page B-5 AGING MANAGEMENT ACTIVITIES AGING ACTIVITIES Revision II Revision Page B-5

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION NUREG-....NUREG-1801Prga FOS Program 1801 ID Number XI.E3 Inaccessible Medium Voltage Cables Plant Specific Program - Non-EQ Not Subject to 10 CFR 50.49 Envi- Cable Aging Management Program ronmental Qualification Require- (B.3.4) ments XI.S1 ASME Section Xl, Subsection IWE Containment Inservice Inspection Program (B. 1.3)

XI.S2 ASME Section Xl, Subsection IWL Containment Inservice Inspection Program (B.1.3)

XI.S3 ASME Section XI, Subsection IWF Inservice Inspection Program (B.1.6)

XI.S4 10 CFR 50, Appendix J Containment Leak Rate Program (B.1.4)

XI.S5 Masonry Wall Program Structures Monitoring Program (B.2.10)

XI.S6 Structures Monitoring Program Structures Monitoring Program (B.2.10)

XL.S7 RG 1.127, Inspection of Water-Con- Structures Monitoring Program trol Structures Associated with (B.2. 10)

Nuclear Power Plants XI.S8 Protective Coating Monitoring and Not credited for aging management.

Maintenance Program Chapter 10 X.M1 Metal Fatigue of Reactor Coolant Fatigue Monitoring Program (B.2.4)

Pressure Boundary X.E1 Environmental Qualification (EQ) of See Section 4.4 of this application.

Electric Components X.S1 Concrete Containment Tendon Pre- Containment Inservice Inspection stress Program (B. 1.3)

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1 EXISTING AGING MANAGEMENT ACTIVITIES B.1.1 BOLTING INTEGRITY PROGRAM The Bolting Integrity Program is consistent with XI.M3, "ReactorHead Closure Studs" and XI.M18, "Bolting Integrity," as identified in NUREG-1801 with the following exception:

§ XI.M18 - 3. Parameters Monitored/Inspected and 4. Detection of Aging Effects FCS has not identified stress corrosion cracking (SCC) as a creditable aging effect requiring management for high strength carbon steel bolting in plant indoor air. FCS will utilize ASME Section XI, Subsection IWF visual VT-3 inspection requirements rather than volumetric inspections for inspection of supports.

The scope of the FCS Bolting Integrity Program includes those plant specific components identified in Tables 3.1.2 and 3.5.2 of this application for which the Bolting Integrity Program is identified as an aging management program.

Operating Experience:

Inspections of bolted components have been conducted under the FCS Inservice Inspection Program (based on ASME Section XI code requirements), the FCS Boric Acid Corrosion (BAC) Prevention Program, and the Structures Monitoring Program. Visual inspections conducted under the Boric Acid Corrosion Prevention Program include inspection of bolted components in borated systems. Any indication of BAC residue or damage is reported and evaluated to determine if a component can remain in service per established procedures.

Documentation of operating experience is included in the BAC Inspection Program. On occasion, visual observations have identified BAC damage. These deficiencies were documented in accordance with the FCS corrective action program and resulted in repair or replacement if required. Review of the plant specific operating experience indicates that the inspections have been effective in managing the aging effects of bolted components.

==

Conclusion:==

The Bolting Integrity Program provides reasonable assurance that the aging effects will be managed such that the bolted components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.2 CHEMISTRY PROGRAM The FCS Chemistry Program is consistent with XI.M2, Water Chemistry,and the chemistry related portions of XI.M21, Closed-Cycle Cooling Water System, as identified in NUREG 1801. The scope of the FCS Chemistry Program includes those plant specific components identified in Tables 3.1.2 through 3.5.2 and Tables 3.1.3 through 3.5.3 of this application for which the Chemistry Program is identified as an aging management program.

Operating Experience:

Over the FCS operating history, chemistry related situations have occasionally occurred.

These include a steam generator tube leak, condenser tube leaks, and some resin intrusion into the primary water storage tank. These situations were properly corrected and long-term corrective actions were implemented to prevent recurrence. Chemistry management of aging effects has evolved over the years based on FCS and industry experience. OPPD has adopted industry practices throughout the years, and continues to do so in order to enhance chemistry control. The low percentage of plugged steam generator tubes based on the number of years the generators have been in service is indicative of the effective chemistry control. The overall experience illustrates that the Chemistry Program is effective in managing aging.

==

Conclusion:==

The Chemistry Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.3 CONTAINMENT INSERVICE INSPECTION PROGRAM The FCS Containment Inservice Inspection Program is consistent with X.S1, "Concrete Containment Tendon Prestress,"XI.S1, "ASME Section XI, Subsection IWE," and XI.S2, "ASME Section XI, Subsection IWL," as identified in NUREG-1801. The 10 Year Containment (IWE & IWL) Inservice Inspection Program Plan for FCS, incorporating Subsection IWE and Subsection IWL examination requirements, has been developed and implemented.

Operating Experience:

Inspections of the Containment Liner have been conducted in accordance with the Containment Leak Rate Testing Program and the Maintenance Rule Implementation Program. Inspections of the tendons and tendon anchorages have been conducted in accordance with Technical Specifications, the USAR, and plant procedures. The ASME Section XI, Subsection IWL Inservice Inspection Program incorporates all of the inspection criteria and guidelines of the previous tendon inspection program and is implemented using existing plant procedures. No significant age related degradation has been identified in theinspections performed.

==

Conclusion:==

The Containment Inservice Inspection Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.4 CONTAINMENT LEAK RATE PROGRAM The FCS Containment Leak Rate Program is consistent with XI.S4, "10 CFR Part 50, Appendix J," and applicable sections of XI.S1, "ASME XI, Subsection IWE" related to Appendix J testing as identified in NUREG-1801.

Operating Experience:

Containment leak-tight verification and visual examination of the steel components that are part of the leak-tight barrier have been conducted at FCS since initial unit startup. Prior to the development of the ASME Section X1, Subsection IWE Inservice Inspection Program, examinations were performed in accordance with 10 CFR 50, Appendix J. No significant age related degradation has been identified in the inspections performed.

==

Conclusion:==

The Containment Leak Rate Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.5 FLOW ACCELERATED CORROSION PROGRAM The FCS Flow Accelerated Corrosion (FAC) Program is consistent with XI.M1 7, "Flow Accelerated Corrosion,"as identified in NUREG-1801. The scope of the FCS FAC Program includes those plant specific components identified in Tables 3.1.3 and 3.4.3 of this application for which the FAC Program is identified as an aging management program.

Operating Experience:

FAC inspections have been performed periodically on both in-scope and out-of-scope piping.

These inspections have gone on for many years and the FAC program has been adjusted based on inspection and other results. On occasion, pipe wall has been found below established screening criteria and visual observations have identified through-wall erosion.

These deficiencies were documented in accordance with the FCS corrective action program and resulted in repair or replacement of the affected areas. A rupture occurred on a non-CQE extraction steam line in 1997 which resulted in significant upgrades to the FAC program.

Internal audits and NRC inspection of the program since 1997 have found the program to be maintained in accordance with NSAC-202L-R2, "Recommendationsfor an Effective Flow Accelerated CorrosionProgram."

==

Conclusion:==

The Flow Accelerated Corrosion Program provides reasonable assurance that flow accelerated corrosion will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.6 INSERVICE INSPECTION PROGRAM The Inservice Inspection Program is consistent with XI.M1, "ASME Section X1 Inselvice Inspection, Subsections IWB, IWC, and IWD," and XI.S3, "ASME Section X1, Subsections IWF," as identified in NUREG-1801. The scope of the FCS Inservice Inspection Program includes those plant specific components identified in Tables 3.1.2 and 3.1.3 of this application for which the Inservice Inspection Program is identified as an aging management program.

Operating Experience:

Review of the plant specific operating experience indicates that the FCS Inservice Inspection Program has been effective in managing the aging effects of components. No significant age related deterioration has been identified in the inspections performed.

==

Conclusion:==

The FCS Inservice Inspection Program provides reasonable assurance that the aging effects will be managed such that the ASME Class 1, 2, and 3 components and their integral supports subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.1.7 REACTOR VESSEL INTEGRITY PROGRAM The FCS Reactor Vessel Integrity Program is consistent with XI.31, "Reactor Vessel Surveillance,"as identified in NUREG-1 801 with the exception of the following enhancements that will be made to the Reactor Vessel Integrity Program prior to the period of extended operation.

NUREG-1801 Proaram Criteria Enhancement r 7 X1.31, Reactor Vessel Evaluation and Technical Surveillance Basis The revised, optimized withdrawal and test schedule Reactor vessel surveillance was submitted to the NRC programs are plant specific, staff for review and approval depending on matters such as per OPPD Letter LIC-01 the composition of limiting 0107 dated November 8, materials, availability of 2001.

surveillance capsules, and projected fluence levels. In accordance with 10 CFR Part 50, Appendix H, an applicant submits its proposed withdrawal schedule for approval prior to implementation. Thus, further staff evaluation is required for license renewal.

Operating Experience:

At FCS, three surveillance capsules have been removed and the materials tested. The FCS operating experience is being supplemented by surveillance capsule test results from other operating reactors whose surveillance capsules include materials that exactly match the materials of the various FCS reactor vessel beltline welds, including the limiting or critical weld. The results of testing of the early surveillance capsules, use of the chemistry factors for the limiting weld, and the early results of the updated fluence analysis indicated that the FCS reactor vessel could exceed the PTS screening criteria of 10 CFR 50.61 before the end of the current 40-year license period in 2013. As a result, FCS implemented core design limitations aimed at restricting the fluence of the reactor vessel beltline region. Analysis has been completed which demonstrates that FCS will be able to operate to the end of the extended period of operation without exceeding the PTS screening criteria. These analysis results have been reviewed and NRC approved by Amendment 199 to the FCS Operating License.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

==

Conclusion:==

The Reactor Vessel Integrity Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2 ENHANCED AGING MANAGEMENT ACTIVITIES B.2.1 BORIC ACID CORROSION PREVENTION PROGRAM The FCS Boric Acid Corrosion (BAC) Prevention Program is consistent with XI.M10, "Boric Acid Corrosion,"as identified in NUREG-1 801 with the exception of enhancements specified in the following table. These enhancements will be made to the Boric Acid Corrosion Program prior to the period of extended operation. The scope of the FCS Boric Acid Corrosion Program includes those plant specific components identified in Tables 3.1.2, 3.1.3, and 3.3.3 of this application for which the Boric Acid Corrosion Program is identified as an aging management program.

NUREG-1801 Proaram Criteria Enhancement XI.M10 Boric Acid Scope Specific guidance will be added to the Corrosion program basis document and applicable procedures to inspect components, structures, and electrical components where boric acid may have leaked.

Add Spent Fuel Pool Cooling and Waste Disposal Systems to the program.

Parameters Monitored/ Two areas not routinely inspected will be Inspected added to inspection scope.

Monitoring and Specific guidance will be implemented for Trending maintenance personnel to report boric acid leakage to the BAC Program Engineer.

Operating Experience:

FCS experienced severe boric acid corrosion on reactor coolant pump studs as documented in NRC Generic Letter (GL) 88-05, "Boric Acid Corrosionof Carbon Steel Reactor Pressure Boundary Components in PWR Plants." Significant program improvements were implemented in response to that GL. A review of the post GL 88-05 operating history indicates that the BAC Prevention Program at FCS routinely identifies and corrects borated water leakage and BAC in the Reactor Coolant System and other borated water systems, including any adjacent structures or components that could be adversely affected.

Conclusion:

The FCS Boric Acid Corrosion Prevention Program provides reasonable assurance that the aging effects will be managed such that the susceptible components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.2 COOLING WATER CORROSION PROGRAM The FCS Cooling Water Corrosion Program is consistent with XI.M20, "Open-Cycle Cooling Water System," and X1.21, "Closed-Cycle Cooling Water System," as identified in NUREG 1801, with the exception of the enhancements specified in the following table and with the following clarifications:

"* XI.M20 - Program Description, 3. Parameters Monitored/Inspected, 4.Detection of Aging Effects, 5. Monitoring and Trending, and 6. Acceptance Criteria External coatings are addressed by the FCS General Corrosion of External Surfaces Program.

"* XI.M21 - Program Description, 2. Preventative Actions, 5. Monitoring and Trending,

6. Acceptance Criteria, and 7. Corrective Action The Chemistry-related portions of the program are addressed in the FCS Chemistry Program.

" The scope of the FCS Cooling Water Corrosion Program includes those plant specific components identified in Tables 3.2.2, 3.3.2, and 3.3.3 of this application for which the Cooling Water Corrosion Program is identified as an aging management program.

The FCS Cooling Water Corrosion Program will also include the following exceptions to NUREG-1801:

• XI.M21 - 3. Parameters Monitored/Inspected, 4. Detection of Aging Effects, and 5.

Monitoring and Trending The license renewal commitment for these programs relates only to the mainte nance of the pressure boundary and not the maintenance of fluid flow. Fluid flow is considered an active function. Performance testing and other active sys tem function testing is not performed on an 18 month or 5 year frequency in accordance with EPRI TR-1 07396, Closed Cooling Water Chemistry Guideline, because this EPRI document does not address this criteria or specify that test ing frequency. Non-destructive testing and heat transfer performance to identify pressure boundary integrity are performed per EPRI TR-107396.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION The following enhancements will be made to the Cooling Water Corrosion Program prior to the period of extended operation.

NUREG-1801 Program Criteria Enhancement XI.M20, Open-Cycle 1. Scope of Program Inspections to various raw Cooling Water System 4. Detection of Aging water components will be Effects added based on FCS'

5. Monitoring and Trending Cooling Water Corrosion Program susceptibility evaluation. These inspection activities will be commensurate with the GALL Program.

XI.M21, Closed-Cycle 3. Parameters Monitored/ Inspections to various Cooling Water System Inspected cooling water components

4. Detection of Aging will be added based on Effects FCS' Cooling Water Corrosion Program susceptibility evaluation.

These inspection activities will be commensurate with the GALL Program.

Operating Experience:

Review of FCS operating experience has identified some component part replacements (and repairs) due to corrosion and cracking in the Component Cooling Water and Raw Water Systems. Appropriate long term corrective actions were implemented based on these experiences. These included material changes, additional preventive maintenance, and increased sample evaluation.

Conclusion:

The FCS Cooling Water Corrosion Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.3 DIESEL FUEL MONITORING AND STORAGE PROGRAM The FCS Diesel Fuel Monitoring and Storage Program is consistent with XI.M30, "FuelOil Chemistry," as identified in NUREG-1801 with the exception of the enhancements specified in the following table, and with the following clarifications:

" XI.M30-3. Parameters Monitored/Inspected Although OPPD does perform particulate analysis of fuel oil, OPPD does not credit this analysis for any aging management. Particulate analysis is per formed on diesel fuel for fuel burn quality concerns (i.e., clogging of filters), and does not have any impact on pressure boundary integrity.

"* XI.M30-4. Detection of Aging Effects Ultrasonic testing is not performed on the fire protection diesel fuel oil tank due to the inaccessibility of the tank. Leak detection is employed to monitor the con dition of the tank and is adequate to maintain the system design requirements.

" The scope of the FCS Diesel Fuel Monitoring and Storage Program includes those plant specific components identified in Tables 3.3.2 and 3.3.3 of this application for which the Diesel Fuel Monitoring and Storage Program is identified as an aging management program.

The following enhancements will be made to the Diesel Fuel Monitoring and Storage Program prior to the period of extended operation.

NUREG-1801 Program Criteria Enhancement XI.M30, Fuel Oil Chemistry 2. Preventive Actions Removal of sediment and water at the bottom of the Fire Protection diesel fuel tank will be added.

4. Detection of Aging Effects Inspection of diesel fuel day tanks for corrosion will be added.

5. Monitoring and Trending Fuel analysis of the Fire Protection Day Tank will be added.

Operating Experience:

FCS operating experience indicates there have been no instances of fuel oil system component failures due to aging effects.

AGING MANAGEMENT ACTIVITIES Revision I Page B-18

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

==

Conclusion:==

The FCS Diesel Fuel Monitoring and Storage Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.4 FATIGUE MONITORING PROGRAM The FCS Fatigue Monitoring Program is consistent with X.M1, "Metal Fatigue of Reactor Coolant PressureBoundary," as identified in NUREG-1801 with the exception of the enhancements specified in the following table. These enhancements will be made to the Fatigue Monitoring Program prior to the period of extended operation. The scope of the FCS Fatigue Monitoring Program includes those plant specific components identified in Table 3.1.2 of this application for which the Fatigue Monitoring Program is identified as an aging management program.

NUREG-1801 Program Criteria Enhancement X.M1, Metal Fatigue of 1. Scope Add the following to the Reactor Coolant Pressure scope of components Boundary subject to the FCS Fatigue Monitoring Program:

"* Pressurizer Surge Line bounding locations

"* Class 2 and 3 components not included in the NUREG-1801 program which are subject to fatigue as an aging effect requiring management.

2. Preventive Actions Perform site-specific

6. Acceptance Criteria analysis to address environmental fatigue concerns identified in NUREG/CR-6260.

Corrective actions or program enhancements will be implemented if necessary based on the results of evaluation.

Operating Experience:

There have been no thermal fatigue related failures at FCS; however, there have been two occurrences (with associated corrective action documents) at FCS relative to thermal fatigue that have resulted in enhancements to the FCS Fatigue Monitoring Program.

The first of these documents summarizes concerns about the operation of the Chemical and Volume Control System (CVCS) and whether specific components within or related to the system were having their thermal cycles monitored and tracked consistently. This resulted in the performance of an Engineering Assessment to document a review of Design Basis Documents, the USAR, Technical Specifications, and other documents to determine cycle counting requirements. This review resulted in revision to some of these documents. An AGIG MNAGMEN Revision II ACIVIIESRevsio ag A-Z AGING MANAGEMENT ACTIVITIES Page B-20

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION operating history review was performed to determine the number of cycles that the components of concern actually experienced. Part of this review was to ensure that the thermal cycles counted were, in fact, a result of design basis conditions that merited inclusion in the cycle counting.

The other document was written after a rash of industry small bore piping failures (generally detected as small cracks or leaks as opposed to major pressure boundary ruptures) in primary coolant systems. Two of the resulting action items created a small bore piping fatigue program and a systematic program for thermal fatigue. These actions have been ongoing and are being integrated with license renewal specific thermal fatigue action items to form the basis for this new program.

The sample frequency of the Primary Sampling System is such that its limit of 7000 cycles will be exceeded before the end of the period of extended operation. Prior to entering the period of extended operation, a stress analysis will be performed based on the sampling evolution parameters to determine whether or not the applicable sampling evolution piping will have to be replaced before the end of the period of extended operation.

Pressurizer surge line thermal stratification is an issue identified by NRC Bulletin 88-11.

Generic and bounding analysis for all CE plants was performed by CE and submitted to the NRC. The fatigue portion of this analysis calculated a 0.937 usage factor for the surge line after the 40-year design life that would obviously be exceeded during the period of extended operation. This value is based on the use of the most limiting configuration of the surge line that exists in the CE-designed plants and as a result is very conservative for FCS. To address this issue for the purposes of license renewal, the pressurizer surge line bounding locations will be included in the FCS Fatigue Monitoring Program. As part of this program, realistic usage factors will be compiled for the critical areas based on actual plant operating data to include the effects of thermal stratification. These are expected to be lower than those predicted by the generic evaluation. This reevaluation will take place prior to the period of extended operation. Based on the results of this plant specific analysis, realistic fatigue usage for the surge line will be tracked, and actions will be taken to reevaluate, repair, or replace the surge line as necessary.

Conclusion:

The Fatigue Monitoring Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended function consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.5 FIRE PROTECTION PROGRAM The Fire Protection Program is consistent with XI.M26, "Fire Protection,"and XI.M27, "Fire Water System," as identified in NUREG-1 801 with the exception of the enhancements specified in the following table and with the following clarification:

XI.M27-2. Preventative Action NUREG-1 801 specifies in Section XI.M27, "Fire Water System," that "portions of the fire protection sprinkler system, which are not routinely subjected to flow, are to be subjected to full flow tests at the maximum design flow and pressure."

The FCS USAR, Table 9.11-3, directs flow testing to be performed using a clean water source. The demineralized water booster pumps or Blair City water are used for flow testing at pressures slightly lower than the normal system operating pressure. This is not consistent with NUREG-1801; however, both the pressure and resulting flow are sufficient to effectively entrain and ade quately flow test/flush the sprinkler system piping. This ensures that aging effects are managed such that the intended function is maintained.

The following enhancements will be made to the Fire Protection Program prior to the period of extended operation. The scope of the FCS Fire Protection Program includes those plant specific components identified in Table 3.3.2 of this application for which the Fire Protection Program is identified as an aging management program.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION NUREG-1801 Proaram Enhancement XI.M26, Fire Protection 3. Parameters Monitored or Additional guidance will be Inspected added to the diesel fire pump maintenance procedure to inspect diesel fire pump fuel line and zinc plug for corrosion or mechanical damage.

Specific guidance will be added to halon and fire damper inspection procedures to inspect halon system components and fire dampers for corrosion, mechanical, and physical damage.

Specific acceptance criteria will be added to fire barrier inspection procedures for concrete walls, floors, and ceilings.

Specific guidance will be added to the fire door inspection procedure to inspect for wear and missing parts.

4 XI.M27, Fire Water System Program Description Specific guidance will be developed to replace or inspect in-scope sprinkler heads in accordance with NFPA 25

2. Preventive Actions Additional guidance will be added to one of the system valve cycling tests to improve system flushing.

3. Parameters Monitored or Specific guidance will be Inspected developed for flow testing in-scope sprinkler system.

Operating Experience:

Routine visual inspections of fire barriers have proven effective in identifying material degradation and damage. A recent decline in the number of identified fire barrier penetration discrepancies is attributed to a recent fire barrier and penetration upgrade effort. Historical operating experience shows fire barrier walls, ceilings, doors and floors are adequately managed through inspections.

AGING MANAGEMENT ACTIVITIES Revision I Page B-23

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION Through-wall leakage of seamed fire protection system piping has been identified at FCS.

Routine walkdowns and piping inspections (internal inspections performed when the system is breached for repair) have been implemented to accurately detect and identify early stages of pressure boundary deterioration and leakage. Historical operating experience and discussions with fire protection personnel show this program effectively manages and corrects pressure boundary failures. Operating history for yard fire hydrants, fire dampers, sprinklers and nozzles shows adequate management of the aging effects identified by chapters XI.M26 and XI.M27 of NUREG-1801. Halon system piping and tanks have shown few historical discrepancies and are adequately managed by the FCS program. No historical experience was identified concerning the diesel fire pump fuel oil supply line.

==

Conclusion:==

The Fire Protection Program provides reasonable assurance that the aging effects will be managed such that the structures and components subject to aging management review will continue to perform their intended function consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.6 OVERHEAD LOAD HANDLING SYSTEMS INSPECTION PROGRAM The FCS Overhead Load Handling Systems Inspection Program is consistent with XI.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems," as identified in NUREG-1 801 with the exception of the enhancements specified in the following table. The following enhancements will be made to the Overhead Load Handling Systems Inspection Program prior to the period of extended operation.

NUREG-1801 Proaram Criteria Enhancement XI.M23, Inspection of 5. Detection of Aging Specific guidance will be added to Overhead Heavy Load and Effects applicable inspection procedures Light Load (Relatedto to inspect for degradation of Refueling) Handling expansion anchors and Systems surrounding concrete.

6. Acceptance Criteria Specific guidance will be added to applicable inspection procedures to identify acceptance criteria for general corrosion and degradation of expansion anchors and surrounding concrete.

7. Corrective Actions Specific guidance will be added to applicable inspection procedures to initiate FCS corrective action documentation if excessive general corrosion or cracking of concrete around expansion anchors is identified.

___________________ J ___________________ 1 Operating Experience:

The subject load handling equipment is periodically inspected for degradation. No aging effects which impact the intended functions of the structures or components were identified in the inspections performed.

Conclusion:

The FCS Overhead Load Handling Systems Inspection Program provides reasonable assurance that aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Revision II Page B-25 AGING MANAGEMENT ACTIVITIES AGING ACTIVITIES Revision Page B-25

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.7 PERIODIC SURVEILLANCE AND PREVENTIVE MAINTENANCE (PM)

PROGRAM The stated purpose of the PM program is to prevent or minimize equipment breakdown and to maintain equipment in a condition that will enable it to perform its normal and emergency functions. The program and the site administrative control processes provide for a systematic approach in establishing the method, frequency, acceptance criteria, and documentation of results.

The FCS Periodic Surveillance and Preventive Maintenance Program consists of periodic inspections and tests that are relied on to manage aging for system and structural components and that are not evaluated as part of the other aging management programs addressed in this appendix. The preventive maintenance and surveillance testing activities are implemented through periodic work orders that provide for assurance of functionality of the components by confirmation of integrity of applicable parameters.

EVALUATION AND TECHNICAL BASIS (1) Scope of Program:

The FCS Periodic Surveillance and Preventive Maintenance Program provides for periodic inspection and testing of components in the following systems and structures.

"* Auxiliary Building

• Emergency Diesel Generators

"* Auxiliary Building HVAC

• Fire Protection

"* Auxiliary Feedwater

• Fuel Handling Equipment/Heavy Load Cranes

"* Chemical and Volume Control

• Intake Structure

"* Component Cooling

• Liquid Waste Disposal

"* Containment

• Containment Penetration, and System Interface Components for Non-CQE Systems

• Containment HVAC "* Reactor Coolant

"* Control Room HVAC and Toxic Gas "* Safety Injection and Containment Monitoring Spray

"* Diesel Generator Lube Oil "* Ventilating Air 0 Duct Banks Revision I1 Page B-26 ACTIVITIES AGING MANAGEMENT ACTIVITIES Revision Page B-26

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION (2) PreventiveActions:

The Periodic Surveillance and Preventive Maintenance Program includes periodic refurbishment or replacement of components, which could be considered to be preventive or mitigative actions. The inspections and testing to identify component aging degradation effects do not constitute preventive actions in the context of this element.

(3) ParametersMonitored or Inspected:

Inspection and testing activities monitor parameters including surface condition, loss of material, presence of corrosion products, signs of cracking and presence of water in oil samples.

(4) Detection of Aging Effects:

Preventive maintenance and surveillance testing activities provide for periodic component inspections and testing to detect the following aging effects and mechanisms:

" Change in Material

• Loss of Material - General Properties Corrosion

" Cracking

• Loss of Material - Pitting Corrosion

" Fouling

• Loss of Material - Pitting/

Crevice/Gen. Corrosion

"* Loss of Material ° Loss of Material - Wear

"° Loss of Material - Crevice

• Separation Corrosion

"* Loss of Material - Fretting The extent and schedule of the inspections and testing assures detection of component degradation prior to the loss of their intended functions. Established techniques such as visual inspections and dye penetrant testing are used.

(5) Monitoring and Trending:

Preventive maintenance and surveillance testing activities provide for monitoring and trending of aging degradation. Inspection intervals are established such that they provide for timely detection of component degradation. Inspection intervals are dependent on the component material and environment and take into consideration industry and plant-specific operating experience and manufacturers' recommendations.

The program includes provisions for monitoring and trending with the stated intent of identifying potential failures or degradation and making adjustments to ensure components AGING MANAGEMENT ACTIVITIES Revision I Page B-27

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION remain capable of performing their functions. PM review and update guidelines are provided that include adjustment of PM task and frequency based on the as-found results of previous performance of the PM. In particular, responsible system engineers are required to periodically review the results of preventive maintenance and recommend changes based on these reviews. The program includes guidance to assist the system engineers in achieving efficient and effective trending.

(6) Acceptance Criteria:

Periodic Surveillance and Preventive Maintenance Program acceptance criteria are defined in the specific inspection and testing procedures. They confirm component integrity by verifying the absence of the aging effect or by comparing applicable parameters to limits based on the applicable intended function(s) as established by the plant design basis.

(7) Corrective Actions:

Identified deviations are evaluated within the FCS corrective action process, which includes provisions for root cause determinations and corrective actions to prevent recurrence as dictated by the significance of the deviation. The FCS corrective action process is in accordance with 10 CFR 50 Appendix B.

(8) ConfirmationProcess:

The FCS corrective action process is in accordance with 10 CFR 50 Appendix B and includes:

"* Reviews to assure that proposed actions are adequate;

"* Tracking and reporting of open corrective actions; and

"* For root cause determinations, reviews of corrective action effectiveness.

(9) Administrative Controls:

All credited aging management activities are subject to the FCS administrative controls process, which is in accordance with 10 CFR 50 Appendix B and requires formal reviews and approvals.

(10) OperatingExperience:

Periodic surveillance and preventive maintenance activities have been in place at FCS since the plant began operation. These activities have a demonstrated history of detecting damaged and degraded components and causing their repair or replacement in accordance with the site corrective action process. With few exceptions, age-related degradation adverse to component intended functions was discovered and corrective actions were taken prior to loss of intended function.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

==

Conclusion:==

The Periodic Surveillance and Preventive Maintenance Program assures that various aging effects are managed for a wide range of components at FCS. Based on the program structure and administrative processes and FCS operating experience, there is reasonable assurance that the credited inspection and testing activities of the Periodic Surveillance and Preventive Maintenance Program will continue to adequately manage the identified aging effects of the applicable components so that the intended functions will be maintained consistent with the current licensing basis for the period of extended operation.

Revision I Page 6-29 MANAGEMENT ACTIVITIES AGING MANAGEMENT ACTIVITIES Revision I Page B-29

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.8 REACTOR VESSEL INTERNALS INSPECTION PROGRAM The FCS Reactor Vessel Internals Inspection Program is consistent with XI.M13, "Thermal Aging and Neutron IrradiationEmbnttlement of Cast Austenitic Stainless Steel (CASS)," and XI.M16, "PWR Vessel Intemals," as identified in NUREG-1801 with the exception of the enhancements specified in the following table and with the following exceptions:

" XI.M16-4. Detection of Aging Effects No augmented inspection of bolting is scheduled. The tensile stresses on the FCS reactor vessel internals bolting are lower than the industry levels where cracking was observed as an aging effect. Refer to discussion in Operating Experience below.

" XI.M16-Program Description, 1. Scope of Program and 2. Preventative Actions The Chemistry-related portions of the program are addressed in the FCS Chemistry Program.

The following enhancements will be made to the Reactor Vessel Internals Inspection Program prior to the period of extended operation. The scope of the FCS Reactor Vessel Internals Inspection Program includes those plant specific components identified in Tables 3.1.2 and 3.1.3 of this application for which the Reactor Vessel Internals Inspection Program is identified as an aging management program.

NUREG-1801 Proaram Criteria Enhancemnent XI.M13, ThermalAging and 4. Detection of Aging A fluence and stress analysis will be Neutron Irradiation Effects performed to identify critical locations.

Embrittlementof Cast A fracture mechanics analysis for Austenitic Stainless Steel critical locations will be performed to (CASS) determine flaw acceptance criteria and resolution required to detect flaws. Appropriate inspection techniques will be implemented based on analyses.

XI.M16, PWR Vessel 7. Parameters Monitored A fluence and stress analysis will be Internals 8. Detection of Aging performed to identify critical locations.

Effects A fracture mechanics analysis for critical locations will be performed to determine flaw acceptance criteria and resolution required to detect flaws. Appropriate inspection techniques will be implemented based on analyses.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION Operating Experience:

No cracking has been discovered in US pressurized water reactor (PWR) reactor vessel (RV) internals fabricated with austenitic stainless steel except for various bolting applications for Babcock & Wilcox and Westinghouse-designed NSSSs and thermal shield components at St. Lucie Unit 1 and Millstone Unit 2, which are CE designed Nuclear Steam Supply System (NSSS). The cracking at St. Lucie and Millstone was caused by flow-induced high cycle fatigue; the thermal shields at these plants were removed. Cracking of core barrel, baffle, and former bolts at Electricite de France (EdF), Westinghouse and Babcock & Wlcox designed RV internals has been discovered. The cause of cracking of core barrel bolts at Babcock & Wilcox designed plants was stress corrosion cracking (SCC) and the cracking of baffle bolts at Westinghouse and EdF plants is believed to be irradiation assisted stress corrosion cracking (IASCC).

Reactor vessel internals inspections are performed under the FCS Inservice Inspection Program. No cracking caused by high cycle fatigue was discovered in the FCS thermal shield and therefore the FCS thermal shield was not removed, as is the case for St. Lucie Unit 1 and Millstone Unit 2. In 1984 a commitment was made to the NRC to perform an inspection of the thermal shield during the 1987 refueling outage. However, in 1986 an inspection deferral program was implemented that allowed a thermal shield monitoring program to replace the inspection commitment. This monitoring program generated data from 1988 through 1990 that indicated the early stages of loosening of the thermal sleeve positioning pins. During the 1992 refueling outage, visual inspection of the support lugs and the positioning pins was performed. No noticeable cracks, weld cracks, missing parts, misalignment, gaps, looseness, or wear were found. Eleven pins (7 lower pins and 4 upper pins) were removed and replaced to reinstate the specified amount of initial relative displacement between the thermal shield and the core support barrel. The amount of initial relative displacement was based on maintaining specified preload over twenty years in the pins while accounting for radiation-induced relaxation and wear. This action reduced vibrations to below specified levels. No unacceptable vibration has been detected since 1992 and FCS continues to monitor thermal shield vibrations using the Internals Vibration Monitoring program. Any unacceptable vibration will be corrected when appropriate.

To date, no cracking has been discovered in bolting for Combustion Engineering (CE) designed RV internals bolting. The Combustion Engineering Owners Group (CEOG) provided an assessment of the cracking of the baffle former bolts reported in foreign PWRs, including the potential impact of the cracking on domestic CE plants. The results are in CEOG Report CE NPSD-1 098 for CEOG Task 1011, "Evaluation of the Applicability of Baffle Bolt Cracking to Ft. Calhoun and PalisadesInternals Bolts," Final Report, Revision 00, April 1998. The most likely mechanism for the cracking of cold-worked 316 stainless steel baffle former bolts in foreign plants is IASCC. There are only two CE-designed plants (FCS and Palisades) that use bolts to attach the core shroud panels (i.e., the baffle plates) to the former plates. The report indicates that these bolts in FCS are less susceptible to IASCC because:

(1) the material used in these bolts is annealed 316 stainless steel, which is not cold worked; (2) the bolt stress from preload, as a percentage of yield strength, is much less than the EdF plants; (3) the differential pressure across the core shroud panels does not result in tensile loads on the panel (i.e., the baffle bolts) during normal operation; and (4) the core shroud AGING MANAGEMENT ACTIVITIES Revision 1 Page B-31

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION panel design allows for some flexing of the former plate relative to the core barrel, thus reducing the load on the panel bolts. Since CE NPSD-1098 was issued, cracking has been discovered in Point Beach baffle bolts. However, as with the EdF experience, cracked bolts were highly stressed during preload, tensile stresses were applied during operation because of the Westinghouse design, and the bolts were fabricated with cold worked 316 stainless steel. Therefore, the findings of CE NPSD-1098 still apply.

Stress corrosion cracking was identified in B&W lower thermal shield and lower core barrel bolts that were fabricated with A-286. Most of the failed bolts were highly stressed to at or over the yield strength. Cracked bolts were replaced with bolts of improved design fabricated with Inconel X-750. No cracking of these bolts has recurred. Although there have been no failures of CEA Shroud Bolts in CE-designed RV internals, there is a concern that SCC may occur since these bolts are fabricated with Alloy A-286. CE provided an evaluation of the stress level for these bolts in 1984. According to CEN-282, "Investigationand Evaluation of A286 Bolt Applications in C-E's NSSS," September 1984, operating stress levels are just below 32 Ksi. The stress concentration factor for the CEA Shroud Bolts is 2.06, leading to a local stress of approximately 66 Ksi. Yield strength for A-286 is about 115 Ksi, so the stress is approximately 60 percent of yield. Most of the failed B&W bolts had working stresses of approximately 65 Ksi and a local stress of 134 Ksi which is above the yield strength of the material. There were no failed B&W bolts with working stresses of 35 Ksi. The conclusion of the report indicates a low probability for cracking of the CEA Shroud Bolts.

==

Conclusion:==

The Reactor Vessel Internals Inspection Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended function consistent with the current licensing basis for the period of extended operation.

Page B-32 ACTIVITIES AGING MANAGEMENT ACTIVITIES Revision II Revision Page B-32

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.9 STEAM GENERATOR PROGRAM The FCS Steam Generator Program is consistent with XI.M19, "Steam GeneratorTube Integrity," as identified in NUREG-1801 with the exception of the enhancements specified in the following table and with the following clarifications:

"* In addition to the requirements of XI.M19, the FCS Steam Generator Program also includes aging management activities to address plant specific AMP requirements identified in Table 3.1.1.

" The scope of the FCS Steam Generator Program includes those plant specific components identified in Tables 3.1.2 of this application for which the Steam Generator Program is identified as an aging management program.

The following enhancements will be made to the Steam Generator Program prior to the period of extended operation.

NUREG-1801 Proaram Criteria Enhancement XI.M 19, Steam Generator 2. Preventive Actions An Annunciator Response Tube Integrity 6. Acceptance Criteria Procedure will be written for the Loose Parts Monitor in the Steam Generator.

Operating Experience:

Steam generator management of aging effects has evolved and improved over the years based on industry experience. FCS has adopted industry practices throughout the years, and continues to do so. Past NRC inspections on this program cited sample plans and inspection evaluation as a strength. Only one noteworthy situation has occurred. In 1984, a misplug and misdiagnosed tube problem led to a tube rupture. This situation was corrected and long-term corrective actions were implemented to prevent recurrence. Current FCS practices are state of-the-art. The overall experience illustrates that the Steam Generator Program is effective in managing aging.

Conclusion:

The FCS Steam Generator Program provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Revision II Page B-33 ACTIVITIES MANAGEMENT ACTIVITIES AGING MANAGEMENT Revision Page B-33

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.2.10 STRUCTURES MONITORING PROGRAM The Structures Monitoring Program is consistent with XI.S5, Masonry Wall Program,XI.S6, "Structures Monitoring Program,"and XI.S7, RG 1.127, "Inspection of Water-Control Structures Associated with Nuclear PowerPlants," as identified in NUREG-1 801 with the exception of the enhancements specified in the following table and with the following clarifications:

" FCS does not have lubrite supports as identified in NUREG-1801, Chapter III, item A4.2-b. FCS does have lubrite on some steam generator supports which are inspected under the FCS Inservice Inspection Program rather than the Structures Monitoring Program.

"* XI.S7. Program Description FCS is not committed to RG 1.127. Applicable attributes from RG 1.127 have been incorporated into the Structures Monitoring Program as specified in the program description.

The following enhancements will be made to the Structures Monitoring Program prior to the period of extended operation. The scope of the FCS Structures Monitoring Program includes those plant specific components identified in Tables 3.3.2, 3.5.2, and 3.5.3 of this application for which the Structures Monitoring Program is identified as an aging management program.

NUREG-1801 Proaram 10 elements Enhancement XI.S5, Masonry Wall Program 3. Parameters Monitored Specific guidance will be added to or Inspected inspect masonry walls for cracking and condition of steel bracing.

6. Acceptance Criteria Specific acceptance criteria will be added to inspection procedures to be commensurate with industry codes, standards, and guidelines.

Page B-34 AGING MANAGEMENT ACTIVITIES ACTIVITIES Revision II Revision Page B-34

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION XI.S6, Structures Monitoring 3. Parameters Monitored Specific guidance will be added for Program or Inspected inspection of component supports, new fuel storage rack, and the plant specific components identified in the Section 3 tables. Aging management activities related to these components will be commensurate with industry standards and practices as identified in the NUREG-1801 Structures Monitoring Program criteria.

4. Detection of Aging Additional guidance commensurate Effects with industry codes, standards, and guidelines, will be added to inspection procedures.

6. Acceptance Criteria Specific acceptance criteria will be added to the inspection procedures to be commensurate with industry codes, standards, and guidelines.

XI.S7, Regulatory Guide 1.127, 3. Parameters Monitored Additional guidance will be added to Inspection of Water Control or Inspected the inspection procedure to identify Structures Associated with specific parameters to inspect.

Nuclear Power Plants

5. Monitoring and Additional guidance will be added to Trending review maintenance activities since last inspection.

6. Acceptance Criteria Specific acceptance criteria will be added to the inspection procedures to be commensurate with industry codes, standards, and guidelines.

In addition the following FCS specific tasks will be added to the Structures Monitoring Program prior to the period of extended operation.

"* Performance of periodic sampling and evaluation of ground water.

"* Guidance to inspect structural components when exposed by excavation.

Operating Experience:

Inspections have been performed in the Auxiliary Building, Containment, Intake Structure, and Turbine Building in 1996/1997 and 1999/2000. No significant deterioration was identified. Some examples of corrosion of support anchors have been observed and documented under the FCS corrective action program.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

==

Conclusion:==

The Structures Monitoring Program provides reasonable assurance that the identified aging effects will be managed such that the structures and components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Page B-36 AGING MANAGEMENT ACTIVITIES ACTIVITIES Revision II Revision Page B-36

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3 NEW AGING MANAGEMENT ACTIVITIES B.3.1 ALLOY 600 PROGRAM The FCS Alloy 600 Program will be consistent with the requirements of XI.M11, "Nickel-Alloy Nozzles and Penetrations,"as identified in NUREG-1801 prior to the period of extended operation with the following exceptions:

" XI.M11-4. Detection of Aging Effects The FCS Alloy 600 Program will not rely on an enhanced leakage detection system for detection of leaks caused by primary water stress corrosion crack ing (PWSCC) as suggested by XI.M11 in NUREG-1801. Bounding evaluations exist that demonstrate that PWSCC cracks can be detected via boric acid leak age prior to the structural integrity of the pressure boundary being compro mised and prior to unacceptable material loss of carbon steel vessels due to boric acid corrosion.

" XI.M11-Program Description, 1. Scope of Program, and 2. Preventative Action.

The Chemistry-related portions of the program are addressed in the FCS Chemistry Program.

The program includes participation in industry programs to determine an appropriate aging management program for SCC of Alloy 600 and PWSCC of Inconel 182 welds.

The scope of the FCS Alloy 600 program includes those plant specific components identified in Table 3.1.2 of this application for which the Alloy 600 Program is identified as an aging management program.

Operating Experience:

OPPD has proactively responded to industry experience with PWSCC of Alloy 600. In response to NRC Information Notice 90-10, "PrimaryWater Stress Corrosion Cracking (PWSCC) of Inconel 600," OPPD initiated an investigation of the applications of Alloy 600, Alloy 82 and Alloy 182 in the FCS reactor coolant system. OPPD participated in the industry integrated inspection program used to respond to Generic Letter 97-01, "Degradationof Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations,"and is currently following industry developments related to circumferential cracking in control rod drive mechanisms (CRDMS) as described in NRC Bulletin 2001-01. Experience with weld PWSCC at V.C. Summer and a pressurizer instrument nozzle leak at FCS (both in October, 2000) prompted OPPD to review fabrication records of Alloy 82 and Alloy 182 welds and Alloy 600 components for evidence of fabrication rework, since this was identified as a causal factor in both incidents. In response to the V.C. Summer incident, FCS engineering staff briefed plant operators and inspection personnel to sensitize them to the potential for Alloy 82/182 butt weld cracks.

AGING MANAGEMENT ACTIVITIES Revision I Page B-37

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION

==

Conclusion:==

The Alloy 600 Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Revision I1 Page B-38 AGING MANAGEMENT ACTIVITIES MANAGEMENT ACTIVITIES Revision Page B-38

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.2 BURIED SURFACES EXTERNAL CORROSION PROGRAM The Buried Surfaces External Corrosion Program will be consistent with XI.M34, "Buried Piping and Tanks Inspection," as identified in NUREG-1801 prior to the period of extended operation.

Operating Experience:

Tank wall thickness measurements, conducted as part of the Diesel Fuel Oil Monitoring and Storage Program for the emergency diesel generator and auxiliary boiler fuel oil storage tanks, have determined that there is no indication of external corrosion for either vessel.

As opportunities have arisen, visual inspections have been performed on excavated piping.

A recent excavation for the repair of buried valves in the Fire Protection System also exposed sections of Raw Water System piping. The applied coatings and wrappings of the excavated Fire Protection and Raw Water System piping and components were found to be in good condition with no indication of loss of material from the metal beneath.

==

Conclusion:==

The Buried Surfaces External Corrosion Program provides reasonable assurance that the identified aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Page B-39 AGING AGING MANAGEMENT ACTIVITIES MANAGEMENT ACTIVITIES Revision II Revision Page B-39

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.3 GENERAL CORROSION OF EXTERNAL SURFACES PROGRAM The General Corrosion of External Surfaces Program at FCS is credited for aging management of the effects of loss of material and cracking for applicable components, including piping, valves, supports, tanks, and bolting, which are made of cadmium plated steel, carbon steel, cast iron, copper alloy, galvanized steel, low alloy steel, and neoprene.

(1) Scope of Program The General Corrosion of External Surfaces Program consists of several FCS activities that manage the aging effects of loss of material and cracking for components in the following systems:

"* Auxiliary Boiler Fuel Oil "* Feedwater

"* Auxiliary Building HVAC "* Fire Protection Fuel Oil

"* Auxiliary Feedwater (AFVV) "* Gaseous Waste Disposal

"* Chemical and Volume Control "* Instrument Air

"* Component Cooling Water (CCW) "* Main Steam (MS) and Turbine Steam Extraction

" Containment HVAC " Containment Penetration, and System Interface Components for Non-CQE Systems

• Control Room HVAC "* Nitrogen Gas

"* Diesel Generator Lube Oil "* Primary Sampling

"* Diesel Jacket Water "* Raw Water

"* Starting Air "* Ventilating Air (2) Preventive Actions This program does not prevent aging.

(3) ParametersMonitoredor Inspected Surface conditions of components are monitored through visual observation and inspection to detect signs of external corrosion and to detect conditions that can result in external corrosion, such as fluid leakage.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION (4) Detection of Aging Effects The aging effects of concern are loss of material and cracking. These effects can be detected by visual observation and inspection of external surfaces. Inspection for evidence of leaking fluids also provides indirect monitoring of certain components that are not routinely accessible.

(5) Monitoring and Trending Various plant personnel including operators and system engineers perform periodic material condition inspections and observations outside containment. These inspections are performed in accordance with approved plant procedures. Evidence of fluid leaks, significant coating damage, or significant corrosion is documented.

Inspections and observations are performed at intervals based on previous inspections and industry experience. Operator rounds occur several times daily and system engineer walkdowns occur at least quarterly. Inspections inside containment are conducted each refueling outage by a team that includes knowledgeable subject matter experts from Engineering and Quality Control. The in-containment inspections for corrosion are part of the containment coatings inspections described in the OPPD response to NRC Generic Letter 98-04, "Potentialfor Degradationof the Emergency Core Cooling System and the Containment Spray System after a Loss-of-CoolantAccident Because of Constructionand Protective Coating Deficiencies and Foreign Materialin Containment."

(6) Acceptance Criteria Plant procedures provide criteria for determining the acceptability of as-found conditions and for initiating the appropriate corrective action. The acceptance criteria and guidance are related to avoiding unacceptable degradation of the component intended functions, and include existence of leakage, presence of corrosion products, coating defects, and elastomer cracking. Appropriate provisions of NRC and industry guidance are incorporated.

(7) CorrectiveAction The FCS corrective action process provides measures to verify completion and effectiveness of corrective action.

(8) ConfirmationProcess The FCS corrective action process is in accordance with 10 CFR 50 Appendix B and includes:

"* Reviews to assure that proposed actions are adequate;

"* Tracking and reporting of open corrective actions; and

"* For root cause determinations, reviews of corrective action effectiveness.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION (9) Administrative Controls The procedures governing inspections and observations for external corrosion are subject to the site administrative controls process which implements the requirements of 10 CFR 50, Appendix B.

(10) OperatingExperience The activities relied on to detect loss of material, cracking, and fouling of accessible cadmium plated steel, carbon steel, cast iron, copper alloy, galvanized steel, low alloy steel, and neoprene component external surfaces and the precursors thereof are a subset of a larger number of inspection activities that result in redundant inspections. The activities credited for license renewal were selected based on their effectiveness as indicated by a review of site corrective action documents.

The activities are elements of established FCS programs that have been ongoing for years.

They have been enhanced over the years based on site and industry experience. Review of plant records indicates they are effective in detecting loss of material due to corrosion and its precursors for accessible external surfaces. These findings are consistent with the findings of recent internal and external assessments of these activities, such as audits and NRC inspections.

Conclusion:

The General Corrosion of External Surfaces Program provides reasonable assurance that aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.4 NON-EQ CABLE AGING MANAGEMENT PROGRAM The FCS Non-EQ Cable Aging Management Program establishes a service life value for the Non-EQ cable in a similar fashion as the FCS EQ Program establishes a Qualified Life for the safety related equipment, components, and cable. Non-EQ cable was purchased to the same requirements and specifications as that included in the EQ Program for the cable installed and qualified under the FCS 10 CFR 50.49 Environmental Qualification Program.

Additional temperature and environmental data utilized to extend the qualified life of the EQ Program equipment and cables will be utilized to analyze and establish a service life for the Non-EQ cables. These analyses are relied upon to predict the life expectancy of the Non-EQ cable under the normal and abnormal plant operating conditions. Cables not capable of having a 60-year service life will be further analyzed using state of the art analytical techniques to determine if the service life can be further extended. Industry accepted and regulatory approved cable inspection techniques that provide aging related data, as well as state of the art in-situ, non-destructive testing of cable performance, and/or laboratory testing of cable to extend life, may also be considered should the aforementioned methodologies not succeed in extending the required service life.

EVALUATION AND TECHNICAL BASIS (1) Scope of Program The FCS Non-EQ Cable Aging Management Program is credited for managing the aging of all Non-EQ cables and connectors in the FCS plant electrical system subject to aging management review.

(2) Preventive Actions The program does not prevent aging from occurring.

(3) ParametersMonitored or Inspected The FCS Non-EQ Cable Program does not credit the inspections delineated within NUREG 1801 Section XI.E1, since specific analyses are provided for the Non-EQ cable which demonstrate that the cable will perform as intended. Additionally, this analysis takes credit for the manner in which the cable was procured, i. e., same as that in the EQ Program, and the methodology used to establish the 60 year service life.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION (4) Detection of Aging Effects The EQ program, as well as the program established for the Non-EQ cable, does not detect aging effects, but rather establishes a rate of aging based on analysis of materials (i.e., the insulation system). The material analysis includes consideration of material mechanical and electrical properties and their performance in ambient environments under operational conditions as well as self-heating effects. Additional environmental conditions such as humidity and radiation are also considered in the establishment of the service life. These analyses are relied upon to predict the life expectancy of the Non-EQ cable under the normal and abnormal plant operating conditions.

(5) Monitoringand Trending The FCS Non-EQ Cable Aging Management Program establishes a service life value for the Non-EQ cable in a similar fashion as the FCS EQ Program establishes a Qualified Life for the safety related equipment, components, and cable. Non-EQ cable was purchased to the same requirements and specifications as that included in the EQ Program for the cable installed and qualified under the FCS 10 CFR 50.49 Environmental Qualification Program.

Additional temperature and environmental data utilized to extend the qualified life of the EQ Program equipment and cables will be utilized to analyze and establish a service life for the Non-EQ cables.

(6) Acceptance Criteria Acceptance criteria are based on the cable insulation service life (i.e., the predicted life expectancy). The service life evaluation of the cable insulation material includes consideration of material mechanical and electrical properties and their performance in ambient environments under operational conditions as well as self-heating effects. Additional environmental conditions such as humidity and radiation are also considered in the establishment of the service life. These analyses are relied upon to predict the life expectancy of the Non-EQ cable under the normal and abnormal plant operating conditions.

(7) CorrectiveActions:

Cables for which a 60-year service life has not been or can not be demonstrated by state of the art analysis, inspection, or test, will be replaced prior to expiration of the established service life. This action is in accordance with the FCS 10 CFR 50 Appendix B corrective action process.

(8) Confirmation Process:

N/A. Cable replacement in accordance with the current licensing basis negates the need to confirm that the corrective action was effective in assuring the cable intended function(s). As noted above, the FCS corrective action process is in accordance with 10 CFR 50 Appendix B.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION (9) Administrative Controls:

Non-EQ Cable Aging Management Program activities will be subject to the FCS administrative controls process, which is in accordance with 10 CFR 50 Appendix B and requires formal reviews and approvals.

(10) OperatingExperience This program is based on the EQ program, which has been shown through operating experience to be effective in managing cable aging. There is extensive industry and FCS experience in establishing and monitoring the service life of cables and other EQ equipment.

The program will be improved, as appropriate, as additional industry experience becomes available.

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Conclusion:==

The FCS Non-EQ Cable Aging Management Program provides reasonable assurance that aging effects will be managed such that non-EQ cables subject to aging management review will continue to perform their intended functions consistent with the current licensing basis through the period on extended operation.

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FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.5 ONE-TIME INSPECTION PROGRAM The FCS One-Time Inspection Program will be consistent with XI.M.32, "One-Time Inspections," as identified in NUREG-1801 prior to the period of extended operation. The scope of the FCS One-Time Inspection Program includes those plant specific components identified in Tables 3.3.2 and 3.4.2 of this application for which the One-Time Inspection Program is identified as an aging management program.

Operating Experience:

This is a new FCS program implemented to meet license renewal requirements specified in NUREG-1801. Results obtained from the required program inspections will be reviewed and documented in accordance with plant procedures. Corrective actions will be taken if necessary in accordance with the plant corrective action program.

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Conclusion:==

The One-Time Inspection Program will provide reasonable assurance that applicable aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation Revision I1 Page BAG MANAGEMENT ACTIVITIES AGING MANAGEMENT ACTIVITIES Revision Page B-46

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.6 SELECTIVE LEACHING PROGRAM The FCS Selective Leaching Program will be consistent with XI.M.33, "Selective Leaching of Materials,"as identified in NUREG-1801 prior to the period of extended operation, with the following clarification:

XI.M33-Program Description, 3. Parameters Monitored/Inspected, and 4. Detection of Aging Effects OPPD does not perform hardness measurement, because brasses, bronzes, and other copper-alloys do not have hardness acceptance criteria. For cast irons, graphitization is easily visually identified and the ASTM and ASME stan dards do not prescribe hardness acceptance criteria.

The scope of the FCS Selective Leaching Program includes those plant specific components identified in Tables 3.2.2, 3.3.2, 3.3.3, 3.4.2, 3.5.2, and 3.5.3 of this application for which the Selective Leaching Program is identified as an aging management program.

Operating Experience:

FCS operating experience has revealed no problems related to selective leaching.

Conclusion:

The Selective Leaching Program provides reasonable assurance that the aging effects will be managed such that the components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TECHNICAL INFORMATION B.3.7 THERMAL AGING EMBRITTLEMENT OF CAST AUSTENITIC STAINLESS STEEL The FCS Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program will be consistent with XI.M 12, "ThermalAging Embrittlement of Cast Austenitic Stainless Steel (CASS)," as identified in NUREG-1 801 prior to the period of extended operation.

Operating Experience:

No age related degradiation associated with thermal embrittlement of CASS was identified in the FCS operating experience.

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Conclusion:==

The FCS Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Program provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

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