ML022210450
| ML022210450 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/30/2002 |
| From: | Mecredy R Rochester Gas & Electric Corp |
| To: | Jack Cushing Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022210450 (195) | |
Text
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Volume 2 Section 3 - Aging Management Review Results Section 4 - Time-Limited Aging Analysis Appendix A - UFSAR Supplement Appendix B - Aging Management Programs Appendix C - Not Used in this Application Appendix D - Technical Specification Changes
APPLICATION FOR RENEWED OPERATING LICENSE R. E. GINNA NUCLEAR POWER PLANT
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.0 AGING MANAGEMENT REVIEW RESULTS For those structures and components that are subject to aging management review, paragraph 54.21(a)(3) of the license renewal rule requires demonstration that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation.
This chapter describes the results of the aging management reviews for structures and components that were identified in Chapter 2, Structures and Components Subject to Aging Management Review.
3.1 Review Methodology The overall process by which aging effects requiring management were identified and evaluated is summarized in this section.
3.1.1 Determination of Materials of Construction Material(s) of construction were identified for all systems, structures and components subject to aging management review. Sources of information used to identify materials of construction included original Westinghouse and Gilbert Associates, Inc. (GAI) equipment and material specifications, vendor technical manuals and drawings, fabrication drawings, piping and instrument drawings, and piping line specifications. Field walkdowns were also used to identify/verify materials of construction for some components.
3.1.2 Determination of Operating Environments Internal operating environments were defined by fluid medium and chemistry (i.e., treated water, raw water, lubricating oil and fuel oil, air/gas, etc.), service temperature, and condition of fluid flow. External environments were defined by plant location, including temperature and humidity (i.e., indoor with no air-conditioning, outdoor with exposure to weather),
exposure to soil/soil water (i.e., buried), embedment in concrete, and exposure to borated water leaks.
Table 3.1-1 and Table 3.1-2 contain descriptions of the internal and external service environments at Ginna Station which are used in subsequent sections of this chapter. Within this Application, some of the internal environments have been subdivided into subgroups based on the fluid chemistry or flow rate. The subgroups are identified in the Description column in Table 3.1-1.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.1.3 Component Grouping by Material/Environment Combination The aging mechanisms and effects that apply to a structure or component are determined by the material(s) of construction and operating environment (including temperature and stress) to which the material is exposed. Structures or components constructed of the same material and exposed to the same environment would therefore be susceptible to the same aging mechanisms and effects. As a result, structures and components were grouped together according to material/environment combinations. This facilitated the aging management review process, in that a single aging management review could be performed for an entire group of structures or components.
3.1.4 Aging Effects Analysis - Non-Class 1 Mechanical Systems and Components Aging effects requiring management for Non-Class 1 systems and components were determined using the evaluation processes described in standard industry guidance for aging evaluation of mechanical systems and components. Systems and components were evaluated by applying a set of material/environment-based rules derived from known age-related degradation mechanisms documented in the technical literature and published industry operating experience. A plant-specific review of this guidance document was conducted to demonstrate applicability of this document at Ginna Station and to provide corrections and/or enhancements to criteria for evaluating aging of specific materials in certain environments (see Section 3.1.9).
3.1.4.1 Treated Water Systems In accordance with NUREG-1801 for treated water systems, aging mechanisms and effects were identified and evaluated without crediting the mitigative effects of water chemistry controls.
3.1.4.2 Protective Coatings Coatings are used at Ginna Station to protect the surfaces of steel components in mechanical systems and structures. Although the benefits derived from protective coatings are recognized, coatings, in and of themselves, do not perform License Renewal intended functions. Therefore, protective coatings are not credited with managing the effects of aging. However, the condition of steel surfaces protected by coatings is evaluated during inspections directed by aging management programs at Ginna Station. When evidence of superficial surface corrosion caused by coating degradation is found, the coating is evaluated and repaired in accordance with plant procedures. That notwithstanding, protective coatings applied to surfaces in containment are managed within the current licensing basis.
This is further discussed in Appendix B2.1.24.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.1.5 Aging Effect Analysis - Essential Structures Aging effects requiring management for Essential Structures (including Yard Structures) were determined using the evaluation processes described in standard industry guidance for aging evaluation of structures and structural components. Aging mechanisms and effects identified in the EPRI document for structural materials were derived from a number of sources, including collective nuclear plant operating experience and relevant operating experience from other industries. A plant-specific review of this guidance document was conducted to evaluate applicability of various aging mechanisms at Ginna Station (see Section 3.1.9).
3.1.6 Aging Effects Analysis - Class 1 Systems, Structures and Components Aging effects requiring management for Class 1 mechanical systems, components and the Containment Structure were determined using the information and guidance presented in Westinghouse Generic Topical Reports (GTRs). The following Class 1 components were evaluated using the GTRs:
- Containment Structure
- Reactor Vessel Internals
- Reactor Coolant System Piping
- Reactor Coolant System Supports
- Pressurizer The GTRs have undergone extensive peer review and, in some cases, NRC review. In addition, they contain thorough reviews of equipment maintenance histories as well as discussions and assessments of industry/regulatory issues. For those GTRs with U. S. NRC Final Safety Evaluation Reports (FSERs), detailed responses to all Applicant Action Items were prepared.
3.1.7 Industry and Plant-Specific Operating Experience Review A thorough review of appropriate industry and plant-specific operating experience was conducted to confirm that applicable aging effects had been identified. Industry operating experience sources included NRC Generic Publications, INPO Significant Operating Event Reports (SOER), EPRI Technical Reports, Westinghouse Generic Technical Reports (GTRs), and NUREG-1 801 (Generic Aging Lessons Learned (GALL) report). Plant-specific operating experience sources included Reports to AEC/NRC, Abnormal Occurrence and Licensee Event Reports (LERs), Non-Conformance Reports (NCRs), Corrective Action Page 3-3
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Reports (CARs), Refueling, Inspection and Overhaul Reports (RIOs), Inservice Inspection (ISI) Reports, Identified Deficiency Reports (IDRs), and ACTION Reports (ARs) from 1969 to the present. This review was conducted not only to confirm that the aging effects determined by material/environment-based rules were appropriate, but also to assure that any additional plant-specific aging mechanisms and related effects were identified for management.
3.1.8 Assignment of Aging Management Programs Appropriate aging management program(s) credited for managing each aging effect were assigned to each structure or component evaluated in the aging management review process. Aging management programs are described in Appendix B of this Application.
3.1.9 Standard Industry Guidance Document Review (Mechanical Systems and Components)
A technical review of standard industry guidance for aging evaluation of mechanical systems and components was conducted to demonstrate that the materials and internal/external operating environments evaluated in the document were applicable and bounding for Ginna Station. In addition, an evaluation of the aging mechanisms identified for specific materials in certain environments was performed. Positions were developed for mechanisms such as stress corrosion cracking (SCC) and intergranular attack/stress corrosion cracking (IGA/IGSCC) of austenitic stainless steels in treated and raw water environments. A position was also established for SCC of bolting materials.
3.1.9.1 Position on SCC of Austenitic Stainless Steel The threshold temperature for the onset of stress corrosion cracking of austenitic stainless steels in the presence of halides (>150 ppb) and sulfates (>100 ppb) is generally agreed to be approximately 140OF (Reference 1 and Reference 2). The validity of this threshold temperature is also supported by industry operating experience. This threshold temperature has been applied to austenitic stainless steels in all environments evaluated in this LRA. However, it should be noted that the Water Chemistry Control Program (supplemented by one-time inspections in stagnant or low-flow areas) is the aging management program credited for managing cracking due to SCC in treated water systems. This aging management approach is consistent with NUREG-1801.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.1.9.2 Position on IGAIIGSCC of Austenitic Stainless Steels Cracking of austenitic stainless steels due to IGA/IGSCC requires a threshold level of grain boundary sensitization and a threshold temperature of approximately 140OF (Reference 1 and Reference 2). IGA/IGSCC is not a credible aging mechanism for welded austenitic stainless steel piping and components at Ginna Station due to controls imposed on heat input and interpass temperature during fabrication which limited grain boundary sensitization in heat affected zones of welded joints. Susceptibility of austenitic stainless steels to IGA/IGSCC may be increased only after prolonged exposure to elevated temperatures above 4820F.
3.1.9.3 Position on SCC of SA 193 Grade B7 Bolting Materials Although there have been a few reported cases of cracking of bolting in the industry caused by SCC, these have been attributed to susceptible high yield stress materials exposed to aggressive environments, such as lubricants containing molybdenum disulfide. One such case occurred at Ginna Station early in plant life. The bolting which cracked was high-strength (ASTM A 490) RCP embedment anchor studs which had been improperly heat treated, installed with excessive preload, and exposed to borated water leakage. The failure mechanism was determined to be SCC. Replacement A-490 bolting (properly heat-treated and installed with proper preload) has not cracked.
However, a survey of industry experience, technical literature, and laboratory corrosion studies (documented in EPRI Report NP-5769) indicates that SCC should not be a concern for closure bolting in nuclear power plant applications if the specified minimum yield strength is <150 Ksi. For quenched and tempered low-alloy steels typically used for closure bolting (e.g., SA1 93, Grade B7),
susceptibility to SCC is controlled by yield strength. The minimum yield strength specified in SA193 for Grade B7 material is 105 Ksi, which is well below the threshold value of 150 Ksi identified in EPRI Report NP-5769. Furthermore, the selection and use of fastener lubricants for pressure boundary components has been controlled by the Ginna Station Quality Assurance Program since 1983 as part of the response to IE Bulletin 82-02. Limits are also imposed on levels of contaminants such as chlorides and sulfur compounds (including molybdenum disulfide) in lubricants and sealant compounds. Therefore, it is reasonable to conclude that failure by SCC should not be a significant issue for SA1 93 Grade B7 bolting materials. Ginna Station operating experience supports this conclusion.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.1.10 Standard Industry Guidance Document Review (Structures and Structural Components)
A technical review of standard industry guidance for aging evaluation of structures and structural components was conducted to evaluate the applicability of aging mechanisms identified for structural materials at Ginna Station. This included a review of original construction contractual requirements, specifications for concrete structures and other materials, site-specific environments, and plant operating experience. Certain aging mechanisms/effects were determined not to be applicable at Ginna Station. Nevertheless, appropriate aging management/monitoring programs are credited for verification that these mechanisms/effects do not, in fact, result in age-related degradation.
3.1.11 Standard Industry Guidance Document Review (Electrical Commodities)
A technical review of standard industry guidance for aging evaluation of electrical commodities was conducted to evaluate the applicability of aging mechanisms identified for electrical components at Ginna Station. This included a review of original construction requirements, specifications for selected electrical components and other insulating materials, site-specific environments, and plant operating experience. Certain aging mechanisms/effects were determined not to be applicable at Ginna Station. Nevertheless, appropriate aging management/monitoring programs are credited for verification that these mechanisms/effects do not, in fact, result in age-related degradation.
3.1.12 Generic Component Assets It was recognized that certain items/assets such as carbon/low-alloy steel closure bolting or other carbon steel components are present in almost every mechanical system or structure and therefore may be conveniently treated as commodity groups. To facilitate aging management review of such items, generic assets were created in every system and structure to account for the presence of closure bolting and external surfaces of carbon steel components which are subject to the effects of aging. Carbon steel components (CS components) are identified as a specific commodity group to ensure that carbon steel components potentially exposed to borated water leaks are evaluated. The normal external operating environment is evaluated with the specific system-identified components.
Aging effects requiring management for closure bolting were assigned to the generic asset in each system/structure and appropriate aging management programs were identified and credited. For borated water systems or non-borated water systems in close proximity to borated water systems, the potential for boric acid corrosion of carbon/low-alloy steel closure bolting, structural bolting, and external surfaces of equipment and structural Page 3-6
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information members was recognized and accounted for by assigning the applicable aging effects to the generic assets. Appropriate aging management programs were then identified and credited.
Aging management review results for Reactor Coolant Systems are contained in Section 3.2, for Engineered Safety Features Systems in Section 3.3, for Auxiliary Systems in Section 3.4, for Steam and Power Conversion Systems in Section 3.5, for Structures and Component Supports in Section 3.6, and for Electrical and Instrument and Controls Systems in Section 3.7.
3.1.13 Review of NUREG-0933 NUREG-0933 has been reviewed in accordance with the guidance provided in Appendix A.3 of the Standard Review Plan. As a result of this review, the following generic safety issues (GSI) have been evaluated for license renewal and have been addressed in the LRA:
"* GSI-168, Environmental Qualification of Electrical Equipment, is addressed in Section 4.4, Environmental Qualification (EQ) of Electric Equipment.
"* GSI-190, Fatigue Evaluation of Metal Components for 60-Year Plant Life, is addressed in Section 4.3.7, Environmentally Assisted Fatigue.
"* GSI-191, Assessment of Debris Accumulation on PWR Sump Performance, is addressed in Appendix B2.1.24, Protective Coatings Monitoring and Maintenance Program Page 3-7
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information TableA-.1' I nririal "iC e Environments Environment Description Treated Water -
Treated water containing boric acid in the Reactor Coolant System (RCS),
Primary, T<140'F T<1400F. The chemistry of this water is monitored and controlled in accordance with the requirements of the Ginna Station Water Chemistry Control Program. Includes consideration of Stagnant, Low Flow <3 fps.
Treated Water -
Treated water containing boric acid in the Reactor Coolant System (RCS),
Primary, T>480°F T>4800F. The chemistry of this water is monitored and controlled in accordance with the requirements of the Ginna Station Water Chemistry Control Program. Includes consideration of Stagnant, Low Flow <3 fps.
Treated Water -
Treated water containing boric acid in the Reactor Coolant System (RCS),
- Primary, 140 0F<T<480°F. The chemistry of this water is monitored and controlled in 1400F<T<480°F accordance with the requirements of the Ginna Station Water Chemistry Control Program. Includes consideration of Stagnant, Low Flow <3 fps.
Treated Water -
Demineralized, deaerated water; secondary water chemistry is monitored and Secondary, controlled in accordance with the requirements of the Ginna Station Optimized T>120°F Secondary Water Chemistry Program (included in the Water Chemistry Control Program) and includes High Energy Piping in Main Steam, Feedwater, Blowdown, Auxiliary Feedwater, Condensate, and Sample System - Secondary. Includes steam and consideration of Stagnant, Low Flow, <3 fps.
Treated Water -
Demineralized, deaerated water; secondary water chemistry is monitored and Secondary, controlled in accordance with the requirements of the Ginna Station Optimized T<120°F (Stagnant, Secondary Water Chemistry Program (included in the Water Chemistry Low Flow <3 fps)
Control Program). Includes portions of Aux Feedwater, Condensate, and Sample System - Secondary Treated Water -
Treated water containing boric acid in systems other than the RCS, i.e.,
Borated, T<140°F Sample System NSSS, CVCS Charging and Letdown, Residual Heat (Stagnant, Low Flow Removal, Safety Injection, Spent Fuel Cooling, Containment Spray, and
<3 fps)
Waste Disposal Systems. Borated water chemistry is monitored and controlled in accordance with the requirements of the Ginna Station Primary Water Chemistry Control Program.
Treated Water -
Stagnant, low flow (<3 fps) treated water containing boric acid in systems Borated, T>1400 F other than the RCS, i.e., Sample System NSSS, CVCS Charging and (Stagnant, Low Flow Letdown, Residual Heat Removal, Safety Injection, Spent Fuel Cooling,
<3 fps)
Containment Spray, and Waste Disposal Systems. Borated water chemistry is monitored and controlled in accordance with the requirements of the Ginna Station Primary Water Chemistry Control Program.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.1-1 Internal Service Environments Environment Description Treated Water -
Treated water is demineralized water which may be deaerated and include Other corrosion inhibitors and biocides or some combination of these treatments.
The chemistry of this water is monitored and controlled in accordance with the requirements of the Ginna Station Primary Water Chemistry Control Program.
Ginna Station treated water systems include Primary Makeup Water, Emergency Diesel Generator Cooling Water, Component Cooling Water, and Chilled Water.
Treated Water -
Treated water is demineralized water which may be deaerated and include Other (Stagnant, corrosion inhibitors and biocides or some combination of these treatments.
Low Flow <3 fps)
The chemistry of this water is monitored and controlled in accordance with the requirements of the Ginna Station Primary Water Chemistry Control Program.
Ginna Station treated water systems include Primary Makeup Water, Emergency Diesel Generator Cooling Water, Component Cooling Water, and Chilled Water.
Treated Water -
Treated water is demineralized water which may be deaerated and include Other (High velocity, corrosion inhibitors and biocides or some combination of these treatments.
change in flow The chemistry of this water is monitored and controlled in accordance with the direction) requirements of the Ginna Station Primary Water Chemistry Control Program.
Ginna Station treated water systems include Primary Makeup Water, Emergency Diesel Generator Cooling Water, Component Cooling Water, and Chilled Water.
Raw Water Raw water at Ginna Station includes the lake water used both for Circulating (Flowing, >3 fps)
Water (in the main condensers) and for the Service Water System, as well as city water used for the Fire Protection System. The Standby Auxiliary Feedwater System also contains raw water.
Raw Water Raw water at Ginna Station includes the lake water used both for Circulating (Stagnant, low flow Water (in the main condensers) and for the Service Water System, as well as
<3 fps) city water used for the Fire Protection System. The Standby Auxiliary Feedwater System also contains raw water.
Raw Water (High Raw water at Ginna Station includes the lake water used both for Circulating velocity, change in Water (in the main condensers) and for the Service Water System, as well as flow direction) city water used for the Fire Protection System. The Standby Auxiliary Feedwater System also contains raw water.
Raw Water Fluids collected in building drains. These can be treated waters (primary, Drainage borated, secondary, or other), raw water (service water, city water), fuel oil or lubricating oil.
Lubricating Oil and This category comprises either lubricating oil or diesel fuel oil. Ginna Station Fuel Oil systems with this internal environment include the Emergency Diesel Generator (EDG) Fuel Oil and Lube Oil System, and Diesel Fire Pump Fuel Oil and Lube Oil System.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.1-1 Internal Service Environments Environment Description Lubricating Oil and This category comprises either lubricating oil or diesel fuel oil with the Fuel Oil - Pooling potential for pooling of water.
Air and Gas The environments in this category include atmospheric (breathing) air, dry/
filtered instrument air, nitrogen, carbon dioxide, hydrogen, helium and halon.
Ginna Station systems exposed to this internal environment include the Instrument Air, Breathing Air, Nitrogen, EDG Air Start System, Control Room HVAC, Computer/Cable Spread Room HVAC, CRDM Cooling, Containment Purge, Emergency Containment Coolers, Emergency Containment Filters, Containment Post Accident evaluation, the Normal Containment Coolers, portions of Waste Disposal, Fire Suppression, and Refrigerated Systems.
Note that air operated valves assigned to balance of plant systems are also exposed to this environment.
Air and Gas -
Moist atmospheric air, unfiltered Wetted Environment Air and Gas -
Moist atmospheric air, unfiltered, T>140°F Wetted Environment, T>140°F Page 3-10
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.1-2 External Service Environments Category Description Outdoor Moist air, temperature: 0-91 OF, 5-100% relative humidity. Exposed to weather including precipitation and wind.
Indoor - No Air Moist air, temperature: 50-1040F, 60% nominal humidity. Not exposed to Conditioning weather.
Indoor - Air Specific temperature range/humidity dependent upon building/room.
Conditioning Typically, temperature: 70-78°F, 60% relative humidity. Not exposed to weather.
Containment Moist air, temperature: 60-120°F, 50% nominal humidity, Radiation - total integrated dose 1 rad per hour max. (excluding equipment located inside the reactor cavity). Not exposed to weather.
Buried Exposed to soil/fill or ground water Borated Water Potentially exposed to borated water leaks Leaks Embedded Embedded/encased in concrete Page 3-11
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Section 3.1 References
- 1.
D. Peckner and I.M. Bernstein, Handbook of Stainless Steels, McGraw Hill, 1977.
- 2.
A.J. Sedricks, Corrosion of Stainless Steels, John Wiley & Sons, 1979, pp. 152-156.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.2 Aging Management of Reactor Coolant System The results of the aging management review of the Reactor Coolant System components are provided in this section and summarized in Tables 3.2-1 and 3.2-2. Table 3.2-1 shows the aging management of system components evaluated in NUREG-1801 that are relied on for license renewal of the Reactor Coolant System components at Ginna. Included in the table is a discussion column. The discussion column will provide a conclusion indicating if the aging management evaluation results are consistent with NUREG-1 801 along with any clarifications or explanations required to support the stated conclusion if that conclusion is different than those of the NUREG. For a determination to be made that a table line item is "Consistent with NUREG-1 801" several criteria must be met. First the plant specific component is reviewed against the GALL to ensure that the component, materials of construction and internal or external service environment are comparable to those described in a particular GALL item. Second, for those that are comparable, the results of the plant aging management review-aging effect evaluation are compared to the aging effects/mechanisms in the GALL. Finally, the programs credited in the GALL for managing those aging effects are compared to the programs invoked in the plant evaluation. If, using good engineering judgment, it could be reasonably concluded that the plant evaluation is in agreement with the GALL evaluation a line item was considered consistent with NUREG-1 801. There are cases where components and component material/environment combinations and aging effects are common between a NUREG-1 801 line item and the plant evaluation but the aging management program selections differ. In those cases the discussion column will indicate the plant aging management program selection but no conclusion will be made that the line item is consistent with the GALL. Table 3.2-2 contains the Reactor Coolant System components aging management review results that are not addressed in NUREG-1801. A plant component is considered not addressed by the NUREG if the component type is not evaluated in the GALL or has a different material of construction or operating environment than evaluated in the GALL. This table includes the component types, materials, environments, aging effects requiring management, the programs and activities for managing aging, and a discussion column. To avoid confusion, no attempt was made to interrelate material/environment/aging effects from one NUREG-1 801 chapter to another.
Note that these tables only include those components, materials and environments that are applicable to a PWR.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Materials The materials of construction of a component have a major influence on the evaluation of aging effects applicable to the component. Sources of information used to identify materials of construction include original equipment specifications, vendor technical manuals and drawings, fabrication drawings, piping line specifications, modification design records and field walkdowns/verifications. The tables below account for the materials of construction for the components requiring an aging management review.
Since similar materials are susceptible to the same aging effects/mechanisms, the tables itemize the component types (i.e., groupings) while factoring in the materials of construction.
Environment As previously described, the environment(s) to which components are exposed are critical in the determination of potential aging mechanisms and effects. A review of plant design documentation was performed to quantify the environmental conditions to which Ginna Station equipment is exposed. This review identified that some equipment is exposed to a variety of environments. This can include normal operating conditions and post accident conditions. Since aging mechanisms and effects will be primarily driven by the environmental conditions to which equipment is exposed on a daily basis, under normal operating conditions, these conditions will differ from the design parameters which are established based upon the worst case scenario (e.g., LOCA conditions). Ginna Station equipment environments may be categorized into basic external and internal environments detailed in Section 3.1.2.
Aging Effects Requiring Management After the components requiring aging management review were identified and grouped by materials of construction and environment, a review of industry and plant-specific operating experience was performed. The purpose of this review was to assure that all applicable aging effects were identified, and to evaluate the effectiveness of existing aging management programs.
This experience review was performed utilizing various industry and plant-specific programs and databases. Industry operating experience sources included NRC Generic Publications (including Information Notices, Circulars, Bulletins, and Generic Letters),
INPO Significant Operating Event Reports (SOER), EPRI Technical Reports, and other information sources, such as the B&W Owners Group Non-Class 1 Mechanical Tools Implementation document, Westinghouse Generic Technical Reports (GTRs), and the Generic Aging Lessons Learned (GALL) report.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Plant specific operating experience sources included Semi-annual and Annual Reports to AEC/NRC, Abnormal Occurrence and Licensee Event Reports (LERs),
Non-Conformance Reports (NCRs), Corrective Action Reports (CARs), Refueling, Inspection and Overhaul Reports (RIOs), Inservice Inspection (ISI) Reports, Identified Deficiency Reports (IDRs), and ACTION Reports (ARs) from 1969 to the present.
Information from these sources was compiled in various databases. Based upon the material of construction, the applicable environments, and operating experience the potential aging effects requiring management for each of the components was identified as documented in the tables below.
Time-Limited Aging Analysis In addition to those identified in NUREG-1 801, any additional time-limited aging analyses (TLAA) identified as appropriate to the system are identified in Section 4.0.
Confirmation of Topical Report Applicability Class 1 Piping and Associated Pressure Boundary Components The Westinghouse Owners' Group Life Cycle Management & License Renewal Program has prepared topical report, WCAP-1 4575-A, Aging Management Evaluation for Class 1 Piping and Associated Pressure Boundary Components (Reference 1), which has been utilized in the aging management review of the Ginna Class 1 piping and associated pressure boundary components. The scope of the RC components described in the topical report bounds the Ginna Class 1 piping and associated pressure boundary components. A reconciliation of the final SER for WCAP 14575-A applicant action items is provided in Table 3.2.0-1.
Reactor Internals The Westinghouse Owners' Group Life Cycle Management & License Renewal Program has prepared topical report, WCAP-1 4577, Rev. 1-A, License Renewal Evaluation: Aging Management for Reactor Internals (Reference 2), which has been utilized in the aging management review of the Ginna Reactor Vessel Internals components. The scope of the Reactor Vessel Internals components described in the topical report bounds the Ginna Reactor Vessel Internals components. A reconciliation of the final SER for WCAP-14577, Rev. 1 -A applicant action items is provided in Table 3.2.0-2.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Pressurizer The Westinghouse Owners' Group Life Cycle Management & License Renewal Program has prepared topical report, WCAP-14574-A, License Renewal Evaluation: Aging Management Evaluation for Pressurizers (Reference 3), which has been utilized in the aging management review of the Ginna Pressurizer components. The Ginna pressurizer is included in WCAP-14574 -A. The scope of the Pressurizer components described in the topical report bounds the Ginna Pressurizer components with the following clarifications:
"* For the Ginna pressurizer, the design, fabrication, and installed configuration are the same as specified in the WCAP with the exception of the earthquake lugs and valve support brackets.
"* The WCAP identifies stress corrosion cracking (SCC) of the pressurizer sensitized stainless steel nozzle safe ends as a potential aging mechanism. However, the WCAP recognizes that service experience with nozzles and safe ends in Westinghouse pressurizers has been excellent and bases the need for aging management on general industry concerns. The WCAP identifies ASME Section Xl inspections as the program to manage SCC of the safe ends. Consistent with the other Class 1 AMRs, SCC of stainless steel materials in the RCS environment can be effectively managed by the Ginna Station Water Chemistry Control Program. Cracking due to flaw growth is considered in the Ginna Pressurizer AMR and the Ginna Station ASME Section Xl Inservice Inspection is credited to manage the aging effects. As such, ASME Section Xl inspections remain as an aging management program for pressurizer safe-ends.
A reconciliation of the final SER for WCAP-1 4574 -A applicant action items is provided in Table 3.2.0-3.
Conclusion The programs and activities selected to manage the aging effects of the Reactor Coolant System are identified in Table 3.2-1 and Table 3.2-2. The results of the applicant action item reviews are also contained in these tables, but in the SRP format. A description of these aging management activities is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the system components will be adequately managed so that there is reasonable assurance that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (1) The license renewal applicant is to verify that The Ginna Station Class 1 piping and reactor its plant is bounded by the topical report. Further, coolant pumps are bounded by the topical the renewal applicant is to commit to programs report with regard to design criteria and described as necessary in the topical report to features, materials of construction, fabrication manage the effects of aging during the period of techniques, installed configuration, modes of extended operation on the functionality of the operation and environments/exposures.
reactor coolant system piping. Applicants for license renewal will be responsible for describing Aging management programs necessary to any such commitments and identifying how such manage the effects of aging are consistent with commitments will be controlled. Any deviations those described in the topical report. Program from the aging management programs within this commitments to manage the effects of aging topical report described as necessary to manage for Class 1 piping and reactor coolant pumps the effects of aging during the period of extended are described in Appendix B of the License operation and to maintain the functionality of the Renewal Application and include the following:
reactor coolant system piping and associated pressure boundary components or other
- One-Time Inspection Program for Small-Bore information presented in the report, such as Class 1 Piping materials of construction, will have to be identified
- Water Chemistry Control Program by the renewal applicant and evaluated on a
- ASME Section XI, Subsections IWB, IWC, &
plant-specific basis in accordance with 10 CFR IWD Inservice Inspection Program 54.21 (a)(3) and (c)(1).
- Boric Acid Corrosion Program.
(2) Summary description of the programs and A summary of the programs identified to evaluation of Time-Limited Aging Analyses are to manage the effects of aging for Class 1 piping be provided in the license renewal FSAR and reactor coolant pumps will be included in supplement in accordance with 10 CFR 54.21 (d).
the UFSAR. A markup of the UFSAR sections affected by the TLAA evaluations will also be included in the UFSAR revision.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (3) The renewal applicant should complete the The entire set of NRC Generic updated review of generic communications and Communications was reviewed using an capture any additional items not identified by the automated text search routine developed for original review.
WOG. Initial searches were made for the occurrence of terms relating to components within the scope of WCAP-14575-A. Then, the titles of all selected documents were reviewed to eliminate those which did not relate to age-related degradation or which related to equipment not included in WCAP-14575-A.
The remaining documents were individually reviewed to determine the applicable aging effect(s). These resulting documents are included in the summary provided in Table 3-1 in WCAP-14575-A An updated review of industry operating experience has been conducted independently by RG&E in support of license renewal activities. This review has included NRC Generic Communications through December 2001.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (4) The license renewal applicant must provide a During construction, the Class 1 piping was description of all insulation used on austenitic insulated in accordance with the applicable stainless steel NSSS piping to ensure the piping Westinghouse Equipment Specification. As is not susceptible to stress-corrosion cracking described in the Ginna Station UFSAR Section from halogens.
5.2.3.2, "All external insulation of the reactor coolant system components is compatible with the component materials. All other external corrosion resistant surfaces in the reactor coolant system are insulated with a low or halide-free insulating material." Generally, the piping is insulated with a calcium carbonate material covered with a stainless steel sheet covering. Blanket insulation made from a halide-free fabric is also used at locations where periodic inspections and maintenance are required. The Reactor Coolant Pump casings and the SG Channel Heads are insulated with a stainless steel reflective insulation.
Since the insulation that is used on the reactor coolant piping is low halide or halide free, the piping is not susceptible to stress corrosion cracking initiated by such halides.
(5) The license renewal applicant should Programs necessary to manage the effects of describe how each plant-specific AMP addresses aging for Class 1 piping and reactor coolant the following 10 elements: (1) scope of the pumps address the 10 elements identified.
program, (2) preventive actions, (3) parameters These programs (including the 10 elements) monitored or inspected, (4) detection of aging are described in Appendix B of the License effects, (5) monitoring and trending, (6)
Renewal Application.
acceptance criteria, (7) corrective actions, (8) confirmation process, (9) administrative controls, and (10) operating experience.
Page 3-19
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (6) The license renewal applicant should perform A sample of small-bore (< 4-inch NPS) piping additional inspection of small-bore Reactor welds will be inspected by a volumetric Coolant System piping, that is, less than technique prior to the end of the current 4-inch-size piping, for license renewal to provide licensing period. The sample population will be assurance that potential cracking of small-bore selected on the basis of piping geometry, size, Reactor Coolant System piping is adequately and flow condition. The aging management managed during the period of extended review and specific program commitments for operation.
Class 1 small-bore piping are addressed in Appendix B of the License Renewal Application.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-14575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (7) Components that have delta ferrite levels below the susceptibility screening criteria have adequate fracture toughness and do not require supplemental inspection. As a result of thermal embrittlement, components that have delta ferrite levels exceeding the screening criterion may not have adequate fracture toughness and do require additional evaluation or examination. The license renewal applicant should address thermal-aging issues in accordance with the staff's comments in Section 3.3.3 of this evaluation.
Page 3-21 Reduction in fracture toughness for CASS Class 1 piping components and reactor coolant pump casings due to thermal aging embrittlement is addressed by Leak-Before-Break (LBB) analyses. These analyses are identified as TLAAs and are discussed in Section 4.0 of the License Renewal Application. The LBB (fracture mechanics) analyses demonstrate that significant margin exists between detectable flaw sizes and unstable flaws assuming "fully-aged" CASS properties. The Ginna Station methodology is consistent with the staff comments.
The following clarification is also provided:
The WOG approach to the potential for reduced fracture toughness in CASS components in WCAP-14575-A does not rely on susceptibility screening using delta ferrite; it conservatively assumes that all CASS Class 1 RCS components are potentially susceptible.
The WOG report specifies an accepted analytical technique (Leak-Before-Break analysis) as the primary aging management approach to demonstrate adequate fracture toughness at end-of-life. Only if this approach fails are alternative "corrective" actions specified: repair, replacement, or the ASME Section Xl inservice examination and flaw evaluation approach. (NOTE: Open item #6 deals with clarifications of these corrective actions.)
The staff's comments in Section 3.3.3 of the DSER for valve bodies / pump casings state that existing ASME Section Xl inspection requirements are adequate, with the alternative being ASME Code Case N-481 for pump casings. The WOG report specifies demonstration of compliance with the N-481 requirements as the primary aging
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (7) (continued) management approach, with the supplemental visual inspections. If this approach fails, then ASME Section XI volumetric ISI is specified as the alternative. For both LBB and N-481, the WOG report clarifies that "fully-aged" fracture toughness data must be used for the limiting materials for the extended period of operation.
(8) The license renewal applicant should perform An automated cycle counting and Fatigue additional fatigue evaluations or propose an AMP Monitoring Program (FatigueProTM ) has been to address the components labeled I-M and I-RA implemented at Ginna Station. A review has in Tables 3-2 through 3-16 of WCAP-14575.
been conducted of fatigue-sensitive locations in Class 1 piping systems, including components labeled I-M and I-RA in Tables 3-2 through 3-16 of WCAP-1 4575-A. Locations with highest predicted fatigue usage have been selected for monitoring. These include the surge line, charging nozzle, safety injection nozzle, and RHR tee. Locations subjected to severe thermal transients or fluctuations due to stratification are monitored using a stress-based fatigue methodology. A discussion of the fatigue-monitoring methodology is included in Section 4.0 of the License Renewal Application.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class I Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (9) The staff recommendation for the closure of GSI-190 "Fatigue Evaluation of Metal Components for 60-Year Plant Life" is contained in a December 26, 1999, memorandum from Ashok Thadani to William Travers. The license renewal applicant should address the effects of the coolant environment on component fatigue life as aging management programs are formulated in support of license renewal. The evaluation of a sample of components with high-fatigue usage factors using the latest available environmental fatigue data is an acceptable method to address the effects of the coolant environment on component fatigue life.
Transient cycle projections to 60 years of plant operation have been made using both a conservative linear cycle projection and a more realistic weighted projection, which assumes that the more recent plant operating history is more representative of future operation than earlier plant history. This assessment of the frequency and severity of actual plant transients demonstrates that there is sufficient conservatism in the original design basis transient set, based on either method of projection (linear or weighted), to adequately bound the period of extended operation.
However, a sample of Class 1 piping components with potentially high fatigue usage factors has been selected for monitoring using the FatigueProTM Automated Cycle-Counting and Fatigue Monitoring Program. Fatigue usage for these locations will be computed by cycle-based or stress-based software modules including the latest available environmental factors. For components with CUFs which are expected to exceed 1.0 during the period of extended operation, corrective actions will include one or more of the following options:
"* Perform an explicit fatigue analysis (i.e., using sophisticated methods in ASME Section III NB-3200 or NB-3600) including environmental factors to lower the CUF below 1.0 prior to the end of the current license period, or
"* Repair of the fatigue-sensitive location(s), or
"* Replacement of the fatigue-sensitive location(s), or
"* Manage the effects of fatigue by an inspection program that has been reviewed and approved by the NRC (i.e., periodic non-destructive examination of the fatigue-sensitive locations at inspection intervals to be determined by a method accepted by the NRC).
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-1 Class 1 Piping and Associated Pressure Boundary Components WCAP-1 4575-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (9) (continued)
A further discussion of the Metal Fatigue TLAA is presented in Section 4.3 of the License Renewal Application.
(10) The license renewal applicant should revise An LBB analysis has been performed in AMP-3.6 to include an assessment of the margin accordance with NUREG-1 061, for the Ginna on loads in conformance with the staff guidance reactor coolant loop piping applicable to the provided in Reference 11. In addition, AMP-3.6 extended period of operation. The analysis should be revised to indicate If the CASS considered loading, pipe geometry and fracture component is repaired or replaced per ASME toughness (including the reduction in fracture Code,Section XI IWB4000 or IWB7000, a new toughness of CASS components in the RCS, LBB analysis based on the material properties of i.e., elbows and RCP casings, due to thermal the repaired or replaced component (and aging) to assess crack stability in the reactor accounting for its thermal aging through the coolant piping for the period of extended period of extended operation, as appropriate), is operation. The results demonstrated that required to confirm the applicability of LBB. The significant margin exists between detectable inservice examination/flaw evaluation option is, flaw sizes and unstable flaws. Additionally, per the basis on which the NRC staff has fatigue crack growth rates including approved LBB in the past, insufficient to environmental effects were evaluated for reestablish LBB approval, primary loop piping materials and shown to be insignificant.
The Ginna Station Inservice Inspection Program requires that any repair or replacement of CASS components be performed in accordance with the requirements of ASME Section XI. This would include a new LBB analysis based on the material properties of the repaired or replaced component (and accounting for thermal aging through the period of extended operation).
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-2 Reactor Internals - WCAP-14577, Rev. 1-A, Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (1) To ensure applicability of the results and The Ginna Station reactor vessel internals are conclusions of WCAP-14577 to the applicant's bounded by WCAP-1 4577 Rev. 1-A with plant(s), the license renewal applicant is to verify respect to design criteria and features, that the critical parameters for the plant are materials of construction, fabrication bounded by the topical report. Further, the techniques, installed configuration, mode of renewal applicant must commit to programs operation and environments/ exposures.
described as necessary in the topical report to Programs necessary to manage the effects of manage the effects of aging during the period of aging are identified in Table 3.2-1 and Table extended operation on the functionality of the 3.2-2 and summarized in Appendix B of the reactor vessel components. Applicants for license Application.
renewal will be responsible for describing any such commitments and proposing the appropriate regulatory controls. Any deviations from the aging management programs described in this topical report as necessary to manage the effects of aging during the period of extended operation and to maintain the functionality of the reactor vessel internal components or other information presented in the report, such as materials of construction, must be identified by the renewal applicant and evaluated on a plant-specific basis in accordance with 10 CFR 54.21 (a)(3) and (c)(1).
(2) A summary description of the programs and Programs necessary to manage the effects of activities for managing the effects of aging and aging for the Ginna reactor vessel internals are the evaluation of TLAAs must be provided in the the ASME Section XI, Subsections IWB, IWC, license renewal FSAR supplement in accordance
& IWD Inservice Inspection Program, the with 10 CFR 54.21(d).
Reactor Vessel Internals Program, and the Water Chemistry Control Program. Summary descriptions of these programs are provided in Appendix A and Appendix B of the LRA. The only TLAA applicable to the Ginna reactor internals is fatigue. The TLAA for metal fatigue is evaluated in Section 4.3 of the LRA.
(3) For the holddown spring, applicants for The holddown spring is within the scope of license renewal are expected to address intended license renewal for the Ginna reactor vessel function, aging management review, and internals. The intended function, results of the appropriate aging management program(s).
aging management review, and aging management program for the holddown spring are provided in Table 2.3.1-3, Table 3.2-1, Table 3.2-2 and Appendix B of the LRA.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-2 Reactor Internals - WCAP-14577, Rev. 1-A, Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (4) The license renewal applicant must address In Section 2.6.7.2 of the GTR, it is stated, "As aging management review, and appropriate aging noted above, pin degradation does not lead to management program(s), for guide tube support a loss of intended function. Generally, pin pins replacement is considered to be a sound maintenance practice to preclude degradation when industry experience indicates that such degradation has been observed."
All 33 guide tube support pins were replaced at Ginna Station during the 1986 Refueling outage. The new pins were fabricated using a Framatome design which had been installed in French nuclear reactors where SCC pin failures had occurred. The original design of the support pin was susceptible to SCC due to an undesirable microstructure caused by solution heat treatment of the pins at a temperature less than 18000F, followed by age-hardening and application of high preload, resulting in high tensile stresses. The replacement pins were solution heat-treated at 20000 F, followed by age-hardening at 13000 F.
Other improvements in machined configuration and surface finish were incorporated in the new design. Final installation torque was reduced to achieve adequate cold preload and still maintain a tight joint. No evidence of cracking of the redesigned guide tube support pins has since been observed at Ginna. The effects of SCC on reactor internals guide tube support pins fabricated from Alloy X-750 with the updated pin designs may therefore be considered insignificant (GTR 3.1.2.2).
However, loss of material due to wear is also identified as an aging effect requiring management for the support pins. The ASME Section XI, Subsections IWB, IWC. & IWD Inservice Inspection Program (Subsection IWB) is credited with managing loss of material due to wear for the support pins.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-2 Reactor Internals - WCAP-14577, Rev. 1-A, Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (5) The license renewal applicant must explicitly The materials of fabrication were explicitly identify the materials of fabrication of each of the identified for all subcomponents of the Ginna components within the scope of the topical report.
reactor vessel internals within the scope of The applicable aging effect should be reviewed license renewal. The list of these materials and for each component based on the materials of source documents are available for review on fabrication and the environment, site. The aging effect evaluations are performed based on these materials and the appropriate environment.
(6) The license renewal applicant must describe There are no reactor vessel internals its aging management plans for loss of fracture components at Ginna Station within the scope toughness in cast austenitic stainless steel RVI of license renewal which are fabricated from components, considering the synergistic effects of cast austenitic stainless steel.
thermal aging and neutron irradiation embrittlement in reducing the fracture toughness of these components.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-2 Reactor Internals - WCAP-14577, Rev. 1-A, Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (7) The license renewal applicant must describe its aging management plans for void swelling during the license renewal period.
(8) Applicants for license renewal must describe how each plant-specific AMP addresses the following elements: (1) scope of the program, (2) preventative actions, (3) parameters monitored or inspected, (4) detection of aging effects, (5) monitoring and trending, (6) acceptance criteria, (7) corrective actions, (8) confirmation process, (9) administrative controls, and (10) operating experience.
Recent studies of irradiation-induced swelling and stress relaxation suggest that swelling problems, if they arise in PWR core internals, would be highly localized, occurring in the higher flux and temperature locations.
Irradiation-enhanced stress relaxation (or irradiation creep) refers to the accumulation of deformation strain over an extended time period, typically at elevated temperatures.
Stress relaxation may mitigate loads resulting from void swelling.
TEM studies of thin foils prepared from an intact baffle/former bolt and locking device removed from the Ginna reactor vessel internals in 1999 indicate that voids were present in the threaded end of the bolt but not in the head or the 304 SS locking device. The void volume, 0.004% maximum observed in the 347 SS bolt material, is small and preliminary extrapolation to the end of extended life using a simple square law suggests that void swelling should not be a concern.
Ginna Station is participating in industry initiatives to determine the extent of the concerns associated with void swelling and what appropriate changes to the Reactor Vessel Internals Program may be required once an industry position has been established.
The programs necessary to manage the effects of aging for the Ginna reactor vessel internals (RVIs) address the 10 elements identified.
These elements are described in Appendix B of the LRA.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-2 Reactor Internals - WCAP-14577, Rev. 1-A, Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (9) The license renewal applicant must address The Ginna Station Reactor Vessel Internals plant-specific plans for management of cracking Program is credited for managing cracking and (and loss of fracture toughness) of RVI loss of fracture toughness of RVI components.
components, including any plans for augmented This program is described in Appendix B of the inspection activities.
LRA and includes participation in industry initiatives and efforts for development of appropriate enhanced inspection techniques to permit detection and characterizing very small features of interest.
(10) The license renewal applicant must address During the 1999 refueling outage, the entire plant-specific plans for management of population of 728 Type 347 stainless steel age-related degradation of baffle/former and baffle/former bolts were selected for inspection barrel/former bolting, including any plans for by UT at Ginna Station. Of this number, only augmented inspection activities.
639 bolts could actually be inspected due to limitations on accessibility. A total of 56 bolts were replaced with Type 316 stainless steel bolts during the outage. These were bolts that were found to contain defect-like indications and were part of a pre-qualified minimum bolt pattern for two-loop nuclear plants that was generated by the Westinghouse Owners Group (WCAP-15036). Maintaining the structural integrity of the bolts within this pattern assures compliance with requirements of ASME III, Subsection NG (1989), considering dynamic loads generated by a 10" line break in the reactor coolant system. This LOCA load bounds those that are generated by effects of earthquake, thermal, deadweight, and flow-induced vibration. No further inspections of baffle/former or barrel/former bolts are planned at Ginna Station. However, RG&E will continue to monitor and participate in industry initiatives with regard to baffle/former and barrel/former bolt cracking.
(11) The license renewal applicant must address A discussion of fatigue of reactor vessel the TLAA of fatigue on a plant-specific basis internals is presented in Section 4.3 of the LRA.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (1) 3.3.1.1 License renewal applicants should identify the TLAAs for the pressurizer components, define the associated CUF and, in accordance with 10 CFR 54.21 (c)(1),
demonstrate that the TLAAs meet the CLB fatigue design criterion, CUF <1.0, for the extended period of operation, including the insurge/outsurge and other transient loads not included in the CLB which are appropriate to such an extended TLAA, as described in the WOG report "Mitigation and Evaluation of Thermal Transients Caused by Insurges and Outsurges,"
MUHP-5060/5061/5062, and considering the effects of the coolant environment on critical fatigue location. The applicant must describe the methodology used for evaluating insurge/outsurge and other off-normal and additional transients in the fatigue TLAAs.
The only TLAA identified for the Ginna pressurizer is thermal fatigue. Transient cycle projections to 60 years of plant operation have been made using both a conservative linear cycle projection and a more realistic weighted projection, which assumes that the more recent plant operating history is more representative of future operation than earlier plant history.
This assessment of the frequency and severity of actual plant transients demonstrates that there is sufficient conservatism in the original design basis transient set, based on either method of projection (linear or weighted), to adequately bound the period of extended operation. However, in order to address insurge/outsurge transients and thermal stratification, an automated cycle countinr and Fatigue Monitoring Program (FatigueProviM) has been implemented at Ginna Station. Four fatigue-sensitive pressurizer locations (spray nozzle, surge nozzle, upper shell, and heater well penetration) have been selected for fatigue monitoring using a stress-based method which computes real-time fatigue usage based on actual plant transient data.
These locations will be monitored for a sufficient period of time to establish a baseline cyclic history and cumulative fatigue usage.
The effects of coolant environment are included in this computation. For locations with CUFs which are expected to exceed 1.0 during the period of extended operation, corrective actions will include one or more of the following options:
"* Perform an explicit fatigue analysis (i.e., using sophisticated methods in ASME Section III NB-3200 or NB-3600) including environmental factors to lower the CUF below 1.0 prior to the end of the current license period, or
"* Repair of the fatigue-sensitive location(s), or
"* Replacement of the fatigue-sensitive location(s), or Page 3-30
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (1) (continued)
- Manage the effects of fatigue by an inspection program that has been reviewed and approved by the NRC (i.e., periodic non-destructive examination of the fatigue-sensitive locations at inspection intervals to be determined by a method accepted by the NRC).
(2) 3.2.2.1 In the report, WOG concluded that Hydrogen concentration in the reactor coolant general corrosion is nonsignificant for the internal system (RCS) primary water at Ginna Station is surfaces of Westinghouse-designed pressurizers strictly maintained within specified limits (25 to and that no further evaluations of general 50 cc/kg) by measurement of hydrogen corrosion are necessary. While the staff concurs concentrations in periodic RCS samples, and that hydrogen overpressure can mitigate the adjusting hydrogen overpressure in the volume aggressive corrosive effect of oxygen in creviced control tanks accordingly. The hydrogen geometries on the internal pressurizer surfaces, concentration limits established for the RCS applicants for license renewal will have to provide ensure that general corrosion is non-significant a basis (statement) in their plant-specific for the internal surfaces of the Ginna applications about how their water chemistry pressurizer as well as other Class 1 control programs will provide for a sufficient level components. Hydrogen concentration limits for of hydrogen overpressure to manage crevice the RCS are delineated in the Ginna Station corrosion of the internal surfaces of their Water Chemistry Control Program described in pressurizer.
Appendix B of the License Renewal Application.
(3) 3.2.2.1 The staff finds that the criteria in Leak testing of the Ginna pressurizer is GL 88-05 and the Section Xl requirements for required by ASME Section Xl, Subsection IWB, conducting system leak tests and VT-2 type Table IWB-2500-1, Category B-P.
visual examinations of the pressurizer pressure boundary are acceptable programs for managing boric acid corrosion of the extemal, ferritic surfaces and components of the pressurizer.
However, the report fails to refer to the actual provisions in the ASME Code, Section Xl that require mandatory system leak tests of the pressurizer boundary. The applicants must identify the appropriate Code inspection requirements from ASME Code Table IWB-2500-1.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item (4) 3.2.2.3.2 The staff concurs that the potential to develop SCC in the bolting materials will be minimized if the yield strength of the material is held to less than 150 ksi, or the hardness is less than 32 on the Rockwell C hardness scale; however, the staff concludes that conformance with the minimum yield strength criteria in ASME Specification SA-193 Grade B7 does not in itself preclude a quenched and tempered low-alloy steel from developing SCC, especially if the acceptable yield strength is greater than 150 ksi. To take credit for the criteria in EPRI Report NP-5769, the applicant needs to state that the acceptable yield strengths for the quenched and tempered low-alloy steel bolting materials (e.g., SA-1 93, Grade B7 materials) are in the range of 105-150 ksi.
Plant-Specific Response Although there have been a few reported cases of cracking of bolting in the industry caused by SCC, these have been attributed to susceptible high yield stress materials exposed to aggressive environments, such as lubricants containing molybdenum disulfide. However, a survey of industry experience, technical literature, and laboratory corrosion studies (documented in EPRI Report NP-5769) indicates that SCC should not be a concern for closure bolting in nuclear power plant applications if the specified minimum yield strength is <150 Ksi. For quenched and tempered low-alloy steels typically used for closure bolting (e.g., SA193, Grade 87),
susceptibility to SCC is controlled by yield strength. The minimum yield strength specified in SA1 93 for Grade B7 material is 105 Ksi, which is well below the threshold value of 150 Ksi identified in EPRI Report NP-5769.
Furthermore, the selection and use of fastener lubricants for pressure boundary components has been controlled by the Ginna Station Quality Assurance Program since 1983 as part of the response to IE Bulletin 82-02. Limits are also imposed on levels of contaminants such as chlorides and sulfur compounds (including molybdenum disulfide) in lubricants and sealant compounds. Therefore, it is reasonable to conclude that failure by SCC should not be a significant issue for SA193 Grade B7 bolting materials. Ginna Station operating experience supports this conclusion.
Therefore, cracking due to SCC is not considered to be an aging effect requiring management for the Ginna pressurizer bolting.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (5) 3.2.5 The staff considers the discussion in Based on the aging management review of the Section 3.5.2 to be extremely confusing in that it Ginna pressurizer, loss of material due to appears WOG is making three different erosion is not an aging effect requiring conclusions that conflict with one another:
management. Austenitic stainless steels are considered to be resistant to erosion in PWR
- a. That fluid flow velocity and particulate operating environments. The austenitic conditions are not sufficient in the stainless steel surge and spray nozzle thermal pressurizer to consider that erosion is a sleeves and safe ends, and the surge nozzle plausible degradation mechanism that could retaining baskets are not subject to flow rates affect the integrity of the subcomponents in that are sufficiently high to cause erosion. The the pressurizer, spray head couplings and the spray heads do not perform license renewal intended functions
- b. That seven components in the pressurizer and, thus, do not require an aging (refer to the list above) are exposed to fluid management review.
flows that have the potential to result in erosion of the components.
- c. That only one component in the pressurizer (the spray head) is exposed to a fluid flow that has the potential to result in erosion of the component.
The applicant should state why erosion is not plausible for the surge nozzle thermal sleeve, spray nozzle thermal sleeve, surge nozzle safe-end, and spray nozzle safe-end. If erosion is plausible, then an AMP is required.
(6) 3.3 Applicants for license renewal must Programs necessary to manage the effects of describe how each plant-specific AMP addresses aging for the Ginna pressurizer address the 10 the following 10 elements: (1) scope of the elements identified. Detailed program program, (2) preventive action, (3) parameters descriptions (including the 10 elements) are monitored or inspected, (4) detection of aging provided in Appendix B of the License Renewal effects, (5) monitoring and trending, (6)
Application.
acceptance criteria, (7) corrective actions, (8) confirmation process, (9) administrative controls, and (10) operating experience.
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R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (7) 3.3.2.1 Applicants for license renewal Loss of material due to boric acid wastage must provide sufficient details in their LRAs about resulting from boric acid leakage is an aging how their GL 88-05 programs and ISI programs effect requiring management affecting the will be sufficient to manage the corrosive effects external surfaces of the Ginna pressurizer, of boric acid leakage on their pressurizer including bolting materials. The Ginna Station components during the proposed extended Boric Acid Corrosion Program and the ASME operating terms for their facilities, including Section XI, Subsections IWB, IWC, & IWD postulated leakage from the pressurizer nozzles, Inservice Inspection Program are credited with pressurizer nozzle-to-vessel welds, pressurizer managing this aging effect. Detailed program nozzle-to-safe end welds, and pressurizer descriptions provided in Appendix B of the manway bolting materials.
License Renewal Application demonstrate that the effects of aging due to boric acid leakage will be adequately managed during the period of extended operation.
Page 3-34
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item (8) 3.3.2.2 The staff concludes that an AMP is necessary to control and manage the potential for SCC to occur in welded pressurizer penetration nozzles and manway bolting materials, and recommends that a licensee could credit the following programs as the basis for managing the phenomena of PWSCC/IGSCC of the pressurizer components: (1) the primary coolant chemistry control program; (2) the ISI program for the pressurizers; and (3) the plant-specific quality assurance program as it pertains to assuring that previous welding activities on welds in the pressurizer have been controlled in accordance with the pertinent requirements of 10 CFR Part 50, Appendix B, and with the pertinent welding requirements of the ASME Code for Class 1 systems. The staff concludes that applicants need to extend AMP-2-1 to the pressurizer penetration nozzles, to the nozzle-to-vessel welds, and to the manway bolting materials, and to include the appropriate Code requirements among the program attributes listed in Table 4-1 and summarized in the text in Section 4.1 of the report. Applicants for license renewal must provide sufficient details in their LRAs as to how their primary coolant chemistry control programs, ISI programs, and 10 CFR Part 50, Appendix B, quality assurance programs will be sufficient to manage the potential for SCC to occur in the pressurizer nozzle components and bolted manway covers during the proposed extended operating terms for their facilities.
Plant-Specific Response Stress corrosion cracking (SCC), as it applies to the pressurizers, is identified as an aging effect requiring management for pressurizer parts exposed to primary (treated) water. The Ginna Station Water Chemistry Control Program and the ASME Section X1, Subsections IWB, IWC, & IWD Inservice Inspection Program are credited for managing cracking due to SCC. The Quality Assurance Program applies to all aging management programs credited for license renewal. The program descriptions provided in Appendix B of the License Renewal Application demonstrate that these programs will adequately manage cracking due to SCC throughout the extended period of operation.
As stated previously in the response to Applicant Action Item 3.2.2.3.2-1, cracking due to SCC is not an aging effect requiring management for pressurizer bolting.
Page 3-35 i
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (9) 3.3.2.2 Applicants must propose an AMP to verify whether or not thermal fatigue-induced cracking has propagated through the clad into the ferritic base metal or weld metal beneath the clad.
There is no industry experience to suggest that cracks initiating at the clad inner surfaces in the pressurizer will propagate into the underlying base metal or weld material. Observed flaws in other plants were monitored for an extended period of time, and no significant flaw growth was observed. In 1990, several indications were discovered at the Connecticut Yankee Plant. UT inspection confirmed that the indications did not penetrate into the ferritic base metal, and therefore, in accordance with ASME Section Xl, the indications were acceptable without repair. A surveillance program was initiated, and after two follow-up inspections that showed no change, the surveillance program was discontinued with NRC approval. In several of the cases of observed cracking, fracture mechanics analyses were performed and demonstrated that the cladding indications would not compromise the integrity of the primary system components.
At temperatures >1800 F, the cladding has virtually no impact on fracture behavior. This is the low end of the plant operating range. ASME Section XI flaw evaluation rules require that the effects of cladding must be considered in any structural integrity evaluation, especially for postulated flaws that penetrate the cladding into the base metal. The actual impact of the cladding on such an evaluation is negligible.
The pressurizer shell design considers fatigue usage throughout the operating lifetime and includes adequate margin. This is expected to preclude the formation of fatigue cracks in the cladding material. The fracture mechanics evaluations performed for actual observed cracks in other plants indicate that the cracks do not grow significantly over the plant lifetime.
Therefore, a specific aging management program to manage fatigue cracking of the pressurizer cladding is not required.
Page 3-36
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item (9) (continued)
Plant-Specific Response Cracking due to fatigue is identified as a Time-Limited Aging Analysis for the Ginna pressurizer, and is analytically addressed in this TLAA. The conclusion of this analysis is that adequate margin exists in the original design-basis transient set to envelope the period of extended operation. However, a Fatigue Monitoring Program has been implemented as a confirmatory program to ensure that the fatigue analysis remains valid for the license renewal term. Cracking due to flaw growth and stress corrosion is an aging effect requiring management. As noted above, programs credited to manage cracking of pressurizer parts include the Water Chemistry Control Program and the ASME Section Xl, Subsections IWB, IWC, & IWD Inservice Inspection Program, both of which are described in Appendix B of the License Renewal Application. Based on the aging management review performed for the Ginna pressurizer, no additional aging management program is required.
Page 3-37
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item (10) 3.3.2.2 The staff is concerned that IGSCC in the heat-affected zones of 304 stainless steel supports that are welded to the pressurizer cladding could grow as a result of thermal fatigue into the adjacent pressure boundary during the license renewal term. The staff considers that these welds will not require aging management in the extended operating periods if applicants can provide a reasonable justification that sensitization has not occurred in these welds during the fabrication of these components. Therefore, applicants for license renewal must provide a discussion of how the implementation of their plant-specific procedures and quality assurance requirements, if any, for the welding and testing of these austenitic stainless steel components provides reasonable assurance that sensitization has not occurred in these welds and their associated heat-affected zones. In addition, the staff requests that applicants for license renewal identify whether these welds fall into Item B8.20 of Section XI Examination Category B-H, Integral Attachments for Vessels, and if applicable, whether the applicants have performed the mandatory volumetric or surface examinations of these welds during the ISI intervals referenced in the examination category.
Plant-Specific Response Both the cladding material (308L) used to protect the pressurizer alloy steel shell from primary water, and the weld material (309L) used to join the pressurizer internal supports and the pressurizer cladding were selected to have sufficiently low carbon content to minimize the likelihood of sensitization in these welds.The low carbon (and nitrogen) content of the 304 stainless steel material in the heater support plates and the surge nozzle retaining basket minimize the susceptibility of the material to sensitization as a result of welding.
However, in spite of material selection and manufacturing processes which minimize sensitization, the possibility cannot be precluded that sensitized areas exist in the 304 stainless steel supports or their welds.
The same Water Chemistry Control Program which precludes SCC in other PWR primary system materials is also effective in preventing SCC in these pressurizer components and welds. Rigorous control of oxygen and chlorides provides an essentially benign environment which has been shown to be effective both in laboratory experiments and years of operating experience.
Therefore, the presence of sensitized stainless steel material does not necessarily result in any increase in susceptibility to IGSCC. Note that even in laboratory cases where severely sensitized stainless steels have been deliberately exposed to PWR environments, no intergranular attack has been observed.
In summary, the Ginna Station Water Chemistry Control Program is an adequate aging management program to preclude SCC in the pressurizer internal attachment welds for the period of extended operation for the following reasons:
Page 3-38
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Table 3.2.0-3 Pressurizers - WCAP-14574-A Final Safety Evaluation Report Response to Applicant Action Items Renewal Applicant Action Item Plant-Specific Response (10) (continued)
- 1. It is possible that some locations of the welded stainless steel attachments in the pressurizer are sensitized, even with the use of 308L weld material and careful control of the welding processes;
- 2. Studies and operating experience have shown that PWR environments do not lead to stress corrosion cracking in sensitized stainless steel;
- 3. Service experience has demonstrated that stress corrosion cracking does not occur in stainless steels in a PWR environment, whether or not they are sensitized.
In response to the question regarding the applicability of Item B8.20 of Examination Category B-H, this category applies to exterior attachments such as the support skirt, seismic lug and support bracket, and is not applicable to the interior attachment welds.
Page 3-39
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component EffectlMechanism Programs Recommended Discussion (1) Reactor coolant pressure Cumulative fatigue TLAA, evaluated in Yes, TLAA Consistent with NUREG-1 801. Cumulative fatigue damage was boundary components damage accordance with 10 identified as an aging effect requiring management during the CFR 54.21(c) period of extended operation for components listed in this component grouping. Thermal fatigue is addressed as a TLAA in Section 4.3 for those components which contain time-limited assumptions defined by the current operating term and incorporated into the current licensing basis. Secondary-side steam generator pressure boundary components such as the top head, steam nozzle, upper and lower shells, transition cone and feedwater nozzle/impingement plate are included in this grouping although they are not part of the reactor coolant pressure boundary.
(2) Steam generator shell Loss of material Inservice Yes, detection of Consistent with NUREG-1 801. Loss of material due to general, assembly due to pitting and inspection; water aging effects is to pitting and crevice corrosion of the steam generator shell crevice corrosion chemistry be further assembly (including transition cone) are identified as an aging evaluated effect requiring management at Ginna Station. Loss of material from all applicable aging mechanisms on steam generator secondary-side internal surfaces is effectively managed by control of secondary-side water chemistry through the Water Chemistry Control Program and inservice inspections performed in accordance with the ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program.
In addition, the Ginna Station Steam Generator Tube Integrity Program which was developed in accordance with NEI Initiative 97-06 provides all-inclusive guidance for the management of steam generator assets. Assessment of secondary-side aging mechanisms is included in the scope of Steam Generator Tube Integrity Program.
Page 3-40 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further 4Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (3) Pressure vessel ferritic Loss of fracture TLAA, evaluated in Yes, TLAA Consistent with NUREG-1801. Loss of fracture toughness in materials that have a nq1tron toughness due to accordance with ferritic reactor pressure vessel materials due to neutron fluen~e greater than 10 neutron irradiation Appendix G of 10 irradiation embrittlement has been identified as an aging effect n/cm (E>1 MeV) embrittlement CFR 50 and RG requiring management during the period of extended operation.
1.99 Reactor pressure vessel TLAAs, including RTPTS, adjusted reference temperature, and equivalent margins analysis are addressed in Section 4.2. This component group includes the vessel shell and nozzles.
(4) Reactor vessel beltline Loss of fracture Reactor vessel Yes, plant specific Consistent with NUREG-1801. Loss of fracture toughness in shell and welds toughness due to surveillance reactor vessel beltline shell and weld materials due to neutron neutron irradiation irradiation embrittlement has been identified as an aging effect embrittlement requiring management during the period of extended operation.
The upper shell and nozzles are not subject to significant neutron irradiation exposure because of their physical distance from the reactor core. The limiting beltline material in the Ginna Station reactor vessel is the intermediate-to-lower shell beltline circumferential weld. The Ginna Station Reactor Vessel Surveillance Program, in conjunction with TLAA analyses, effectively manages loss of fracture toughness in the beltline materials. The Reactor Vessel Surveillance Program provides adequate material property and neutron dosimetry data to predict fracture toughness in beltline materials at the end of the period of extended operation. In addition, equivalent margins analyses have been performed in accordance with 10 CFR 50 Appendix G methods. These fracture mechanics analyses (see TLAAs, Section 4.2) provide assurance that beltline material toughness values in the Ginna Station reactor vessel will remain at acceptable levels through the period of extended operation.
Page 3-41 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (5) Westinghouse and B&W Loss of fracture Plant specific Yes, plant specific Consistent with NUREG-1801. Loss of fracture toughness due baffle/former bolts toughness due to to neutron irradiation embrittlement was identified as an aging neutron irradiation effect requiring management for the Ginna Station embrittlement and baffle/former bolts. A combination of the ASME Section XI, void swelling Subsections IWB, IWC, & IWD Inservice Inspection Program and the Reactor Vessel Internals Program (described in Appendix B) will be used to manage this aging effect.
During the 1999 refueling outage, all accessible Type 347 stainless steel baffle/former bolts were inspected at Ginna Station and bolts with defect-like indications were replaced with Type 316 stainless steel bolts. The bolt inspection and replacement program assured the structural integrity of bolts within a pre-qualified minimum pattern generated by WOG and thereby assured compliance with ASME Section III, Subsection NB (1989). In addition, destructive metallurgical analysis of intact Type 347 bolts revealed only minor evidence of voids near the threaded end of one bolt, but not in the head end. The void volume (.004%) was small and preliminary extrapolations to the end of life suggest that void swelling should not be a concern. For this reason, change in dimensions due to void swelling is not expected to represent a concern for baffle/former bolts in the Ginna Station reactor vessel internals.
These facts notwithstanding, Ginna Station will continue to participate in WOG activities and monitor industry initiatives for the purpose of evaluating the significance of voidswelling on selected PWR reactor vessel internals components. As new information and technology becomes available, the plant-specific Reactor Vessel Internals Program will be modified to incorporate enhanced surveillance techniques Page 3-42 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (6) Small-bore reactor coolant Crack initiation and Inservice Yes, parameters Consistent with NUREG-1 801. Included and evaluated with this system and connected growth due to SCC, inspection; water monitored/
component grouping are Non-Class 1 RCS small-bore piping, systems piping intergranular SCC, chemistry; one-time inspected and tubing, valves, and other components in connected systems.
and thermal and inspection detection of aging Crack initiation and growth due to SCC was identified as an mechanical loading effects are to be aging effect requiring management in small-bore (<NPS 4) further evaluated reactor coolant system piping and branch lines. Aging management of service-induced cracking will be accomplished by a combination of the Water Chemistry Control Program and the One-Time Inspection Program (described in Appendix B).
NUREG-1801 further identifies the ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program as an applicable aging management program, but also notes that volumetric inspections are not required for piping < NPS 4.
A sample of small-bore piping welds will be inspected using appropriate volumetric examination techniques near, but prior to, the end of the current license period. This sample will be selected to include various piping sizes, configurations and flow conditions. If a flaw is detected in the sample, the successive examinations described in ASME Code, Section Xl, IWB-2420 and additional examinations as described in IWB-2430 would apply as appropriate.
The proposed combination of water chemistry controls and volumetric inspections (implemented by the Water Chemistry Control Program and One-Time Inspection Program) is an effective means of managing service-induced cracking in small-bore reactor coolant system piping and connected branch lines during the period of extended operation.
(7) Vessel shell Crack growth due TLAA Yes, TLAA Consistent with NUREG-1801. Underclad cracking in to cyclic loading carbon/low-alloy steel which has been clad with austenitic stainless steel using weld-overlay processes has been identified as an aging effect requiring management and is addressed as a TLAA. An evaluation of the TLAA for underclad cracking is contained in Section 4.3.
Page 3-43 Application for Renewed Operating License
(
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (8) Reactor internals Changes in Plant specific Yes, plant specific Consistent with NUREG-1801. The specific concerns arising dimension due to from the effects of void swelling in reactor internals are void swelling constriction of flow paths, interference with control rod insertion, and excessive baffle/former bolt loading. Recent destructive examinations of baffle/former bolts removed from the Ginna Station reactor internals suggest that void volumes are very small and changes in dimension in baffle/former bolts due to void swelling should not be a concern during the period of extended operation. In addition, recent studies of irradiation-induced swelling and stress relaxation suggest that swelling problems, if they arise in PWR core internals, would be highly localized, occurring in the higher flux and temperature locations. Irradiation-enhanced stress relaxation (or irradiation creep) may mitigate or limit loads resulting from void swelling. For many reactor internals components, change in dimension does not represent an aging effect requiring management because the intended function of the component(s) is not affected. Additional reactor internal components not identified in NUREG-1801 that are susceptible to changes in dimension due to void swelling are identified in Table 3.2-2 Line Number (7)
These facts notwithstanding, the Reactor Vessel Internals Program manages changes in dimension due to void swelling.
In addition to inservice inspections performed according to the requirements of ASME Section Xl, Subsection IWB, the Reactor Vessel Internals Program provides for augmented visual (VT-1) inspections for certain susceptible (or limiting) components using high resolution techniques yet to be developed. Ginna Station will continue to participate in industry investigations of aging effects applicable to reactor vessel internals as well as initiatives to develop advanced inspection techniques which will permit resolution and measurement of very small features of interest. Ginna Station will incorporate applicable results of industry initiatives related to void swelling in the Reactor Vessel Internals Program.
Page 3-44 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (9) PWR core support pads, Crack initiation and Plant specific Yes, plant specific Consistent with NUREG-1801. The reactor vessel leak instrument tubes (bottom head growth due to SCC detection line is fabricated from stainless steel. The portion of penetrations), pressurizer and/or primary the line that is in scope to license renewal is included in the spray heads, and nozzles for water stress small-bore piping category. Management of service-induced the steam generator corrosion cracking cracking for small-bore piping is addressed in Item 6, and is instruments and drains (PWSCC) consistent with NUREG-1801. The pressurizer spray head performs no license renewal intended functions at Ginna Station. The steam generator instrument nozzles are low-alloy steel, not Alloy 600, and therefore are not included in this component group.
The core support pads and the bottom head instrument penetrations are fabricated from Alloy 600. Crack initiation and growth of the core support pads and the bottom head penetrations due to SCC/PWSCC is managed at Ginna Station by a combination of the Water Chemistry Control Program and the Reactor Vessel Head Penetration Inspection Program (described in Appendix B). The Reactor Vessel Head Penetration Inspection Program is a plant-specific program which includes participation in industry initiatives related to management of Alloy 600 penetration cracking issues.
Page 3-45 Application for Renewed Operating License t
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component EffectlMechanism Programs Recommended Discussion (10) Cast austenitic stainless Crack initiation and Plant specific Yes, plant specific Consistent with NUREG-1801. The Ginna Station pressurizer steel (CASS) reactor coolant growth due to SCC surge line nozzle is cast carbon steel (integral with the system piping pressurizer bottom head) and clad with weld-deposited austenitic stainless steel overlay. The reactor coolant system piping is forged Type 316 stainless steel. However, the fittings (elbows) are CASS (Type CF8M). In addition, the CASS (Type CF8M) reactor coolant pump casings are also included in this component grouping.
As in NUREG-1801, crack initiation and growth due to SCC was identified as an aging effect requiring management for reactor coolant system CASS components. The Ginna Station Water Chemistry Control Program monitors and controls primary water chemistry in accordance with the guidelines of EPRI TR-105714 (Rev. 5) and therefore effectively manages crack initiation and growth due to SCC. Additionally, the flaw tolerance evaluations performed by fracture mechanics analysis under the Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program (described in Appendix B) provide assurance that large margins exist for postulated flaw sizes which satisfy leakage detection criteria as compared to unstable flaw sizes.
(11) Pressurizer Crack initiation and Inservice Yes, AMP for There are no components fabricated from Alloy 600 in the instrumentation penetrations growth due to inspection; water PWSCC of Inconel Ginna Station pressurizer. Instrument penetrations, heater well and heater sheaths and PWSCC chemistry 182 weld is to be tubes and adapters are wrought Type 316 stainless steel.
sleeves made of Ni-alloys evaluated Page 3-46 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (12) Westinghouse and B&W Crack initiation and Plant specific Yes, plant specific Consistent with NUREG-1801. Crack initiation and growth due baffle former bolts growth due to SCC to SCC and IASCC were identified as aging effects requiring and IASCC management for Ginna Station baffle/former bolts. A combination of the Water Chemistry Control Program, ASME Section XI, Subsections IWB, IWC. & IWD Inservice Inspection Program and the Reactor Vessel Internals Program will be used to manage this aging effect.
During the 1999 refueling outage, all accessible Type 347 stainless steel baffle/former bolts were inspected at Ginna Station and bolts with defect-like indications were replaced with Type 316 stainless steel bolts. The bolt inspection and replacement activities assured the structural integrity of bolts within a pre-qualified minimum pattern generated by WOG and thereby assured compliance with ASME Section III, Subsection NB (1989).
No further inspections of baffle/former bolts are anticipated at Ginna Station. However, Ginna Station will continue to participate in WOG activities and monitor industry initiatives for the purpose of evaluating the significance of cracking due to IASCC on selected PWR reactor vessel internals components.
As new information and technology becomes available, the plant-specific Reactor Vessel Internals Program (described in Appendix B) will be modified to incorporate enhanced surveillance techniques.
Page 3-47 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Page 3-48 Application for Renewed Operating License Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (13) Westinghouse and B&W Loss of preload due Plant specific Yes, plant specific Consistent with NUREG-1 801. Loss of mechanical closure baffle former bolts to stress relaxation integrity due to irradiation creep/stress relaxation was identified as an aging effect requiring management for Ginna Station baffle/former bolts. Irradiation-enhanced stress relaxation (or irradiation creep) refers to the accumulation of deformation strain over an extended time period, typically at elevated temperatures.
Loss of preload due to stress relaxation will be managed jointly by the ASME Section Xl, Subsections IWB, IWC, & IWD Inservice Inspection Program and the Reactor Vessel Internals Program. Ginna Station will continue to participate in industry investigations of aging effects applicable to reactor vessel intemals as well as initiatives to develop advanced inspection techniques which will permit resolution and measurement of very small features of interest. Aging management activities or surveillance techniques resulting from these initiatives will be incorporated, as required, as enhancements to the Reactor Vessel Internals Program.
(14) Steam generator Loss of section Plant specific Yes, plant specific This component group is not applicable to Ginna Station. The feedwater impingement plate thickness due to feedwater delivery to the steam generators at Ginna Station is and support erosion through feedrings to Alloy 690 J-tubes. The feedrings and J-tubes perform no license renewal intended function.
Table 3.2-1 Reactor Coolant System - Aging Management License Renewal Programs Evaluated in NUREG-1801 that are Relied on for Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (15) (Alloy 600) Steam Crack initiation and Steam generator Yes, effectiveness Consistent with NUREG-1801. Cracking due to PWSCC and generator tubes, repair growth due to tubing integrity; of a proposed AMP IGA/IGSCC and loss of material due to pitting and wear were sleeves, and plugs PWSCC, outside water chemistry is to be evaluated identified as aging effects requiring management for the Ginna diameter stress Station steam generator tubes and plugs. These aging effects corrosion cracking will be jointly managed by the Water Chemistry Control (ODSCC), and/or Program (both primary and secondary water chemistry) and inter-granular the Steam Generator Tube Integrity Program (described in attack (IGA) or loss Appendix B). The Steam Generator Tube Integrity Program at of material due to Ginna Station was developed to meet the guidelines in NEI wastage and pitting 97-06. Consistent with these guidelines, the requirements for corrosion, and SG degradation management are included in Section 3.4.13 of fretting and wear:
Ginna Station Technical Specifications. These requirements, or deformation due including tube inspection scope and frequency, plugging, repair to corrosion at tube and leakage monitoring have been incorporated in plant support plate administrative controls.
intersections New, replacement recirculating steam generators (SG) were installed at Ginna Station in 1996. These generators incorporate many enhancements in design and materials of construction. The tubes are fabricated from drawn Alloy 690 TT (thermally-treated) material. The tubes are hydraulically expanded over the full depth of the tubesheet. The tube support design is a lattice-grid structure fabricated from Type 410 stainless steel bars. Anti-vibration supports in the U-bend region of the bundle are also Type 410 stainless steel fan-bars.
Sufficient corrosion of the tube support structure to cause tube-denting is not expected based on the resistance of Type 410 stainless steel to the secondary water environment. After four operating cycles (six years), no service-induced defects have been detected in the tubes and no repair plugs or sleeves have been installed other than two factory-installed Alloy 690 TT plugs in each generator. Secondary-side water chemistry control at Ginna Station is based on all-volatile-treatment (AVT), not phosphate treatment.
Page 3-49 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Page 3-50 Application for Renewed Operating License Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (16) Tube support lattice bars Loss of section Plant specific Yes, plant specific Tube support lattice bars are fabricated from Type 410 made of carbon steel thickness due to stainless steel in Ginna Station replacement steam generators.
FAC Type 410 stainless steel is not susceptible to FAC. Therefore this component group is not applicable to Ginna Station. A discussion of steam generator components susceptible to FAC is given in Item 21.
(17) Carbon steel tube Ligament cracking Plant specific Yes, effectiveness There are no carbon steel tube support materials in the Ginna support plate due to corrosion of a proposed AMP Station steam generators. Therefore this component group is is to be evaluated not applicable to Ginna Station.
NUREG-1801 does not specify the corrosion mechanisms which might cause ligament cracking. Cracking due to SCC and loss of material due to pitting and crevice corrosion were identified as aging effects requiring management for the lattice grid support bars in the Ginna Station steam generators. These aging effects are managed jointly by the Water Chemistry Control Program and the Steam Generator Tube Integrity Program, which provides for secondary side inspections to verify the effectiveness of water chemistry control. These aging management programs will be identified in Appendix B.
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (18) Reactor vessel closure Crack initiation and Reactor head No Consistent with NUREG-1801. Crack initiation and growth due studs and stud assembly growth due to SCC closure studs to SCC or IGSCC were not identified as an aging effect and/or IGSCC requiring management for the Ginna Station reactor vessel closure studs. Nevertheless, the Reactor Head Closure Studs Program which includes ASME Section Xl visual, surface and volumetric inservice inspections capable of detecting cracking due to SCC, is credited for managing aging effects applicable to the reactor head closure studs.
NUREG-1801 identifies crack initiation and growth due to SCC is a potential aging effect for reactor vessel closure studs exposed to borated water leaks. Although there have been a few reported cases of cracking of bolting in the industry caused by SCC, these have been attributed to susceptible high yield-stress materials exposed to aggressive environments, such as lubricants containing molybdenum disulfide. A survey of industry experience, technical literature, and laboratory corrosion studies (documented in EPRI Report NP-5769) indicates that SCC should not be a concern for closure bolting in nuclear power plant applications if the specified minimum yield strength is <150 Ksi. The Ginna Station studs are fabricated from SA-320 Gr. L43 material (corresponding to AISI Grade 4340) which is not a high strength steel. The minimum yield strength specified in SA-320 for Grade L43 material is 105 Ksi, which is well below the 150 Ksi threshold.
Furthermore, the selection and use of fastener lubricants for pressure boundary components has been controlled by the Ginna Station Quality Assurance Program since 1983 as part of the response to IE Bulletin 82-02. Limits are also imposed on levels of contaminants such as chlorides and sulfur compounds in lubricants and sealant compounds. Therefore, it is reasonable to conclude that failure by SCC should not be a significant issue for SA-320 Gr. L43 bolting materials. Industry and plant-specific operating experience support this conclusion.
Page 3-51 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (19) CASS pump casing and Loss of fracture Inservice inspection No Consistent with NUREG-1801. Loss of fracture toughness due valve body toughness due to to thermal aging embrittlement was identified as an aging effect thermal aging requiring management for the CASS reactor coolant pump embrittlement (RCP) casings and Class 1 valve bodies.
The ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program (as modified by ASME Code Case N-481) is credited for managing this aging effect for the RCP casings. One of the requirements of Code Case N-481 is a flaw tolerance evaluation performed by fracture mechanics methods for the RCP casings to verify that adequate margin exists for flaw stability after consideration is given to reduction in fracture toughness due to thermal aging embrittlement. This evaluation has been performed and adequate margin was demonstrated throughout the period of extended operation.
For Class 1 valve bodies, the ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program is credited for managing loss of fracture toughness due to thermal aging embrittlement.
Page 3-52 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (20) CASS piping Loss of fracture Thermal aging No Consistent with NUREG-1801. The Thermal Aging toughness due to embrittlement of Embrittlement of Cast Austenitic Stainless Steel (CASS) thermal aging CASS Program is credited with managing loss of fracture toughness embrittlement due to thermal aging embrittlement. This program invokes ASME Section Xl ISI requirements as well as flaw-tolerance analyses using fracture mechanics methods which take into account the effects of thermal aging during the period of extended operation. An updated leak-before-break (LBB) analysis has been performed for the Ginna Station reactor coolant system piping and elbows based on loading, pipe geometry, and end-of-life fracture toughness considering thermal aging effects through the end of the period of extended operation. This analysis is addressed as a TLAA and is discussed in Section 4.0 of the Application.
The CRDM pressure housings and all reactor coolant system nozzle safe ends at Ginna Station are wrought stainless steel, not CASS. The pressurizer spray head performs no license renewal intended function at Ginna Station. In addition, the pressurizer nozzle is cast carbon steel (integral with the pressurizer) and clad with austenitic stainless steel weld overlay. The reactor coolant system piping is forged Type 316 stainless steel. However, the fittings (elbows) are CASS (Type CF8M).
(21) BWR piping and fittings; Wall thinning due to Flow-accelerated No Consistent with NUREG-1801. The aging management review steam generator components flow-accelerated corrosion for the replacement steam generators did not identify loss of corrosion material due to FAC as an aging effect requiring management for the steam outlet nozzle and feedwater inlet nozzle. The steam quality and flows at the steam outlet nozzle are such that FAC would not represent a concern. Furthermore, the design of the feedwater inlet nozzle includes an Alloy 690 thermal sleeve which is extremely resistant to flow-accelerated corrosion damage. Nevertheless, the Flow-Accelerated Corrosion Program is credited for verification that steam generator components are not degraded due to FAC.
Page 3-53 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management License Renewal Programs Evaluated in NUREG-1801 that are Relied on for Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (22) Reactor coolant pressure Loss of material Bolting integrity No Consistent with NUREG-1801. The closure bolting for reactor boundary (RCPB) valve due to wear; loss of coolant system valves, reactor coolant pump, steam generator, closure bolting, manway and preload due to and pressurizer is SA-1 93 Grade B7 material, with specified holding bolting, and closure stress relaxation; minimum yield strength of 105 Ksi. Consequently, crack bolting in high pressure and crack initiation and initiation and growth due to SCC is not an applicable aging high temperature systems growth due to cyclic effect (see discussion for Item 18). Loss of mechanical closure loading and/or SCC integrity due to boric acid corrosion was also identified as an aging effect requiring management for all RCPB bolting potentially exposed to borated water leaks. The applicable aging management program is the Boric Acid Corrosion Program.
For all RCPB bolting other than the reactor vessel closure studs, loss of material due to wear and loss of mechanical closure integrity due to stress relaxation are managed at Ginna Station by the Bolting Integrity Program (described in Appendix B). The Bolting Integrity Program invokes the ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program for assurance that effects of aging for RCPB closure bolting are effectively managed.
There are no flanged connections associated with the CRDM penetrations with reactor coolant pressure boundary (RCPB) bolting at Ginna Station.
(23) CRD nozzle Crack initiation and Ni-alloy nozzles No Consistent with NUREG-1801. Crack initiation and growth due growth due to and penetrations; to PWSCC was identified as an aging effect requiring PWSCC water chemistry management for the Alloy 600 CRDM nozzles and reactor head vent pipe. The aging management programs credited for managing this effect are the Water Chemistry Control Program and the Reactor Vessel Head Penetration Inspection Program.
Page 3-54 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (24) Reactor vessel nozzles Crack initiation and Inservice No Consistent with NUREG-1 801. Crack initiation and growth due safe ends and CRD housing; growth due to cyclic inspection; water to SCC and flaw growth were identified as aging effects reactor coolant system loading, and/or chemistry requiring management for the reactor vessel nozzle safe ends, components (except CASS SCC, and PWSCC CRD housing and RCS components. Aging management and bolting) programs credited for managing these effects are the Water Chemistry Control Program and ASME Section Xl, Subsections IWB, IWC, & IWD Inservice Inspection Program.
The pressurizer manway and flange are integrally cast with the carbon steel heads and are evaluated with the pressurizer heads.
The pressurizer relief tank is not in scope to license renewal at Ginna Station.
For small-bore connected systems piping and fittings, aging management programs for managing crack initiation and growth due to SCC are discussed in Item 6.
(25) Reactor vessel internals Loss of fracture Thermal aging and No The upper and lower internals assemblies in the Ginna Station CASS components toughness due to neutron irradiation reactor vessel contain no CASS components. The lower thermal aging, embrittlement support forging and lower support plate columns are wrought neutron irradiation stainless steel. Therefore this component grouping is not embrittlement, and applicable to Ginna Station.
void swelling I_
I_1___
Page 3-55 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management License Renewal Programs Evaluated in NUREG-1801 that are Relied on for Page 3-56 Application for Renewed Operating License Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (26) Extemal surfaces of Loss of material Boric acid corrosion No Consistent with NUREG-1801. Loss of material due to boric carbon steel components in due to boric acid acid corrosion was identified as an aging effect requiring reactor coolant system corrosion management for external surfaces of carbon steel components pressure boundary (including closure bolting) in the reactor coolant system pressure boundary. The Boric Acid Corrosion Program is credited for managing this aging effect.
Additionally, loss of material due to boric acid corrosion was identified for all borated water systems as well as non-borated water systems in proximity to borated water systems at Ginna Station. The Boric Acid Corrosion Program was also credited for aging management of boric acid corrosion in these additional systems.
(27) Steam generator Loss of material Inservice inspection No This line item applies to once-through steam generators and is secondary manways and due to erosion therefore not applicable to Ginna Station.
handholds (CS)
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (28) Reactor internals, reactor Loss of material Inservice inspection No Consistent with items IV.A2.5-f, B2.1-1, B2.5-o, and B2.6-c of vessel closure studs, and core due to wear NUREG-1801. Loss of material due to wear was identified as support pads an aging effect requiring management for the reactor vessel flange and internals components identified in NUREG-1 801.
However, loss of material due to wear was also identified for the reactor vessel closure studs and the core support pads for which no specific line items appear in the NUREG-1800 (SRP) table. The ASME Section Xl, Subsections IWB, IWC, & IWD Inservice Inspection Program was credited for managing loss of material due to wear for all components except the flux thimble tubes and the reactor vessel closure studs.
For the flux thimble tubes, Ginna Station credits the Thimble Tubes Inspection Program for managing loss of material due to wear. This program was implemented in response to NRC Bulletin 88-09 which required that an inspection program be established to manage the effects of thimble wear for Westinghouse reactors with bottom-mounted instrumentation.
The program provides for eddy current inspections at an appropriate frequency, includes acceptance criteria and corrective actions and has effectively managed thimble tube wear at Ginna Station (see Appendix B).
The Reactor Head Closure Studs Program (see Appendix B) is credited for managing loss of material due to wear of reactor vessel closure studs (see Item 35).
(29) Pressurizer integral Crack initiation and Inservice inspection No Consistent with NUREG-1801. Cracking due to flaw growth support growth due to cyclic was identified as an aging effect requiring management for the loading pressurizer support skirt and flange. Flaw growth occurs as a result of cyclic loading. The ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program was credited for managing this aging effect. Although the aging effect identified by Ginna Station is not described as crack initiation and growth due to cyclic loading, cracking due to any mechanism would be acceptably managed by the ASME Section Xl ISI Program.
Page 3-57 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (30) Upper and lower internals Loss of preload due Inservice No Not consistent with NUREG-1801. Loss of mechanical closure assembly (Westinghouse) to stress relaxation inspection; loose integrity due to stress-relaxation was identified as an aging part and/or neutron effect requiring management for the holddown spring in the noise monitoring upper internals assembly and for the clevis-insert bolts in the lower internals assembly. However, the ASME Section Xl, Subsections IWB, IWC, & IWD Inservice Inspection Program was credited for managing this aging effect. Ginna Station does not employ loose-parts or neutron noise monitoring methods for aging management as referenced in NUREG-1801. This item will therefore be included in Table 3.2-2.
Page 3-58 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Page 3-59 Application for Renewed Operating License Aging Further Aging Management Evaluation Component EffectlMechanism Programs Recommended Discussion (31) Reactor vessel internals Loss of fracture PWR vessel No Consistent with NUREG-1801. Loss of fracture toughness due in fuel zone region (except toughness due to internals; water to neutron irradiation embrittlement was identified as an aging Westinghouse and Babcock & neutron irradiation chemistry effect requiring management for reactor vessel internals Wilcox [B&W] baffle bolts) embrittlement, and components in the fuel zone. However, void swelling was not void swelling specifically identified as an aging mechanism. The results of recent destructive examinations of one of the Ginna Station baffle/former bolts removed during the 1999 refueling outage suggest that void swelling should not represent a concern during the period of extended operation (see discussion in Item 8). In addition, the lower support forging and the core barrel outlet nozzle were not included among the components subject to significant irradiation embrittlement because of their location remote from the fuel zone.
The aging management program referred to in NUREG-1 801 is the PWR Vessel Internals Program. However, the SRP references Water Chemistry as well as the PWR Vessel Internals Program.
Nevertheless, the Reactor Vessel Internals Program is credited with managing loss of fracture toughness due to neutron irradiation embrittlement and void swelling for the internals components in this component grouping. Ginna Station will incorporate applicable results of industry initiatives related to void swelling in the Reactor Vessel Internals Program as they become available.
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (32) Steam generator upper Crack initiation and Inservice No Consistent with NUREG-1801. The only components in this and lower heads; tubesheets; growth due to SCC, inspection; water grouping applicable to Ginna Station are the primary nozzles primary nozzles and safe ends PWSCC and chemistry and safe ends (NUREG-1801, Item IV D1.1-i).
IASCC The steam generator primary head, inlet and outlet nozzles, and manways at Ginna Station are low-alloy steel clad with austenitic stainless steel weld overlay. The primary nozzle safe ends are Type 316 stainless steel. Since the interior (clad) surface of the nozzles, manway, and head are exposed to the same environment, the primary head and manways are included with this component grouping. Crack initiation and growth due to SCC was identified as an aging effect requiring management for the stainless steel-clad primary head, inlet and outlet nozzles, manways, and stainless steel safe ends.
The ASME Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program and the Water Chemistry Control Program are credited for managing applicable aging effects for components in this grouping.
Page 3-60 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (33) Vessel internals (except Crack initiation and PWR vessel No Consistent with NUREG-1801. Ginna Station credited either Westinghouse and B&W baffle growth due to SCC internals; water the Water Chemistry Control Program alone (for components former bolts) and IASCC chemistry subject to SCC) or in combination with the Reactor Vessel Internals Program (for components subject to IASCC) for management of crack initiation and growth due to SCC/IASCC.
Crack initiation and growth due to SCC was identified as an aging effect requiring management for all reactor vessel internals components fabricated from stainless steel. Crack initiation and growth due to IASCC was identified as an aging effect requiring manement for those components exposed to neutron fluence >10' n/cm2 in the core. However, the Ginna Station evaluation determined that not all components listed in NUREG-1 801 were considered susceptible to crack initiation and growth due to IASCC. This is a resull of fluence exposures being less than the threshold value of 10:'1 n/cm2. In addition, plant-specific data obtained from destructive evaluation of Type 347 stainless steel baffle/former bolts removed in 1999 indicated very limited evidence of IASCC. Those components determined by evaluation not to be susceptible to IASCC are enumerated in Table 3.2-2.
(34) Reactor internals (B&W Loss of preload due Inservice No The components in this grouping are not applicable to Ginna screws and bolts) to stress relaxation inspection; loose Station.
part monitoring (35) Reactor vessel closure Loss of material Reactor head No Consistent with NUREG-1801. Loss of material due to wear studs and stud assembly due to wear closure studs was identified as an aging effect requiring management for the reactor vessel closure studs. The Reactor Head Closure Studs Program is credited with managing this effect.
Page 3-61 Application for Renewed Operating License
Table 3.2-1 Reactor Coolant System - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Page 3-62 Application for Renewed Operating License Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (36) Reactor internals Loss of preload due Inservice No Loss of mechanical closure integrity due to stress relaxation (Westinghouse upper and to stress relaxation inspection; loose was identified as an aging effect requiring management for the lower internal assemblies; CE part monitoring upper and lower support plate column bolts. The ASME bolts and tie rods)
Section XI, Subsections IWB, IWC, & IWD Inservice Inspection Program is credited for managing this aging effect. Therefore this is consistent with NUREG-1 801.
NUREG-1801 cites the Loose Parts Monitoring Program as well as the ASME Section Xl ISI Program. However, loose-parts monitoring is not considered to be effective as an aging management program at Ginna Station. This is not consistent with NUREG-1 801 and will be further discussed in Table 3.2-2.
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (1) RPV Closure Low-Alloy Steel Primary Water Cracking due to Water Chemistry Cracking due to SCC is not identified as an aging Head Dome, with Stainless Steel SCC Control Program effect requiring management for these components Closure Head Cladding in NUREG-1801. The aging management Flange, Vessel program(s) referenced are appropriate for the aging Flange, Upper effects identified and provide assurance that the Shell, Primary Inlet aging effects are effectively managed through the Nozzles, Primary period of extended operation.
Outlet Nozzles, Intermediate Shell (including circumferential Beltline weld),
Lower Shell, Bottom Head Torus, Bottom Head Dome BMI Guide Tubes, Stainless Steel Seal Table Fittings Page 3-63 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (2) RPV Closure Low-Alloy Steel Primary Water Cracking due to ASME Section XI.
Cracking due to flaw growth is not identified as an Head Dome, with Stainless Steel Flaw Growth Subsections IWB, aging effect requiring management for these Closure Head Cladding IWC, & IWD components in NUREG-1801. The aging Flange, Vessel Inservice management program(s) referenced are appropriate Flange, Upper Inspection Program for the aging effects identified and provide Shell, Primary Inlet assurance that the aging effects are effectively Nozzles, Primary managed through the period of extended operation.
Outlet Nozzles, Intermediate Shell (including circumferential weld), Lower Shell, Bottom Head Torus, Bottom Head Dome Primary Nozzle Stainless Steel ASME Section XI, Safe Ends Weld Butter Subsections IWB, IWC, & IWD BMI Guide Tubes Stainless Steel Inservice Inspection Program Core Support Pads Alloy 600 CRDM Head Alloy 600 Reactor Vessel Housing Tubes Head Penetration (Head Adapters),
Inspection Vent Pipe, Program Instrumentation Tubes and Safe ASME Section XI.
Ends Subsections IWB, IWC, & IWD Inservice Inspection Program Page 3-64 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (3) RPV Core Alloy 600 Primary Water Loss of Material ASME Section XI, Loss of material due to wear was not identified as Support Pads due to Wear Subsections IWB, an aging effect requiring management in IWC, & IWD NUREG-1801. The aging management program(s)
Inservice referenced are appropriate for the aging effects Inspection Program identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(4) RPV Primary Low-Alloy Steel Primary Water Loss of Fracture Reactor Vessel As discussed in Table 3.2-1 Line Number (4) the Inlet and Outlet with Stainless Steel Toughness due to Surveillance RPV upper shell and the lower sides of the primary Nozzles and Upper Cladding Neutron Irradiation Program inlet and outlet nozzles are not subject to significant Shell Embrittlement neutron irradiation embrittlement because of their physical distance from the reactor core. Therefore loss of fracture toughness due to neutron irradiation embrittlement is not identified as an aging effect requiring management at Ginna Station. This is not consistent with NUREG-1 801.
(5) RPV Ventilation Carbon/Low-Alloy Borated Water Loss of Material Boric Acid Loss of material due to boric acid corrosion of Shroud Support Steel Leaks due to Boric Acid Corrosion Program external surfaces of these components was not Ring, Refueling Corrosion identified as an aging effect requiring management Seal Ledge, Upper in NUREG-1801. The aging management Shell, Primary Inlet program(s) referenced are appropriate for the aging Nozzles, Primary effects identified and provide assurance that the Outlet Nozzles, aging effects are effectively managed through the Intermediate Shell, period of extended operation.
Lower Shell, Bottom Head Torus, Bottom Head Dome (CS Components)
(6) Closure Studs, Carbon/Low-Alloy Containment Air Loss of Mechanical Reactor Head Loss of mechanical closure integrity due to stress Nuts, Washers Steel Closure Integrity Closure Studs relaxation was not identified in NUREG-1801 as an due to Stress Program aging effect requiring management for the reactor Relaxation vessel closure studs. The aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-65 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (7) Lower Core Stainless Steel, Primary Water Changes in Reactor Vessel As discussed in Table 3.2-1 Line Number (8)
Plate and Fuel Alloy 600 (Clevis Dimension due to Internals Program change in dimension due to void swelling was not Pins, Lower Inserts), Alloy Void Swelling explicitly identified as an aging effect requiring Support Forging, X-750 (Guide Tube management for these components at Ginna Lower Support Support Pins)
Station. However, the Reactor Vessel Internals Columns, Core Program manages the effects of void swelling Barrel and Flange, should it become a concern.
Radial Keys and Clevis Inserts, Baffle and Former Assembly, Core Barrel Outlet Nozzle, Upper Support Plate Assembly, Upper Core Plate and Fuel Alignment Pins, Upper Support Columns, RCCA Guide Tubes and Flow Downcomers, Guide Tube Support Pins, Upper Core Plate Alignment Pins, Holddown Spring, Thermal Shield and Neutron Panels, Bolting for all Bolted Closures Page 3-66 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (8) Lower Support Forged Stainless Primary Water Loss of Fracture Reactor Vessel As discussed in Table 3.2-1 Line Number (31) at Forging, Core Steel Toughness due to Internals Program Ginna Station, loss of fracture toughness due to Barrel Outlet Irradiation irradiation embrittlement was not identified as an Nozzle Embrittlement Water Chemistry aging effect requiring management in the AMR for Control Program these components because of their location remote Program from the fuel zone. In addition, void swelling was not explicitly identified as an applicable aging mechanism, although the Reactor Vessel Internals Inspection program manages the effects of void swelling should it become a concern.
(9) Lower Support Stainless Steel Primary Water Cracking due to Reactor Vessel As discussed in Table 3.2-1 Line Number Forging, Radial IASCC Internals Program (33) cracking due to IASCC was not identified as an Keys and Clevis aging effect requiring management in the AMR for Supports, Core Water Chemistry these components because neutron fluence Barrel Outlet Control Program exposure is below the threshold value for IASCC Nozzle, Upper Program susceptibility. That not withstanding, the aging Support Plate management program(s) referenced are appropriate Assembly, Upper for the aging effects identified should cracking due Core Plate and to IASCC become a concern.
Fuel Alignment Pins, Upper Support Columns, RCCA Guidetubes and Flow Downcomers, Upper Core Plate Alignment Pins, Holddown Spring, Upper Support Column Bolting, Guide Tube Bolts, Clevis Insert Bolts Page 3-67 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (10) Lower Core Stainless Steel Primary Water Loss of Material ASME Section XI, Loss of material due to wear was not identified as Plate and Fuel due to Wear Subsections IWB, an aging effect requiring management for these Pins, Core Barrel IWC, & IWD components in NUREG-1801. The aging Flange, Fuel Inservice management program(s) referenced are appropriate Alignment Pins, Inspection Program for the aging effects identified and provide Guide Tube assurance that the aging effects are effectively Support Pins, managed through the period of extended operation.
Holddown Spring (11) Secondary Stainless Steel Primary Water Cracking due to Water Chemistry Cracking due to SCC was not identified as an aging Core Support, SCC Control Program effect requiring management for these components Diffuser Plate, in NUREG-1801. The aging management Guide Tube program(s) referenced are appropriate for the aging Support Pins, Head effects identified and provide assurance that the Vessel Alignment aging effects are effectively managed through the Pins, BMI Columns period of extended operation.
and Flux Thimbles, Head Cooling Spray Nozzles, Upper Instrumentation Column, Conduits and Supports (12) Upper and Stainless Steel Primary Water Loss of Preload ASME Section XI, As discussed in Table 3.2-1 Line Number (30) and Lower Internals due to Stress Subsections IWB, Table 3.2-1 Line Number (36) loss of mechanical Assembly -
Relaxation IWC, & IWD closure integrity was identified as an aging effect Holdown Spring, Inservice requiring management for these components.
Upper and Lower Inspection Program However, loose parts or neutron noise monitoring Support Column programs are not used for the purpose of aging Bolts, Clevis Insert management at Ginna Station. This is not consistent Bolts with NUREG-1801.
(13) RCS Primary CASS Primary Water Cracking due to ASME Section XI, Cracking due to flaw growth is not identified as an Loop Elbows Flaw Growth Subsections IWB, aging effect requiring management for these IWC, & IWD components in NUREG-1801. The aging Inservice management program(s) referenced are appropriate Inspection Program for the aging effects identified and provide RCS Valves > 4 in.
Wrought Stainless assurance that the aging effects are effectively NPS, Valves < 4 in.
Steel managed through the period of extended operation.
NPS Page 3-68 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (14) RCS Valves>
Wrought Stainless Primary Water Cracking due to Water Chemistry Cracking due to SCC is not identified as an aging 4 in. NPS, Valves <
Steel SCC Control Program effect requiring management in NUREG-1 801 for 4 in. NPS wrought stainless steel valves > 4 in. NPS and < 4 in. NPS. The aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(15) Reactor Wrought Stainless Primary Water Cracking due to Water Chemistry The Reactor Coolant Pump Thermal Barrier Flange, Coolant Pump Steel SCC, Cracking due Control Program Heat Exchanger Tubing, and Orifices and Reducers Thermal Barrier to Flaw Growth are not identified in NUREG-1801. Although these Flange, Thermal ASME Section XI, component types are not included in the NUREG, Barrier Heat Subsections IWB, the aging management program(s) referenced are Exchanger Tubing, IWC, & IWD appropriate for the aging effects identified and Orifices and Inservice provide assurance that the aging effects are Reducers Inspection Program effectively managed through the period of extended operation.
(16) Reactor Stainless Steel Containment Air Cracking due to ASME Section XI.
Cracking due to flaw growth for the Reactor Coolant Coolant Pump Lugs Flaw Growth Subsections IWB, Pump Lugs is not identified as an aging effect IWC, & IWD requiring management in NUREG-1801. The aging Inservice management program(s) referenced are appropriate Inspection Program for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(17) Pressurizer Carbon Steel with Primary Water Cracking due to Water Chemistry The Pressurizer Safety and Relief Nozzles are not Safety Nozzle, Stainless Steel SCC, Cracking due Control Program explicitly identified in NUREG-1801. Although these Pressurizer Relief Cladding to Flaw Growth component types are not included in the NUREG, Nozzle ASME Section XI, the aging management program(s) referenced are Subsections IWB, appropriate for the aging effects identified and IWC, & IWD provide assurance that the aging effects are Inservice effectively managed through the period of extended Inspection Program operation.
Page 3-69 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (18) Pressurizer Carbon Steel with Primary Water Cracking due to Water Chemistry The Pressurizer Manway Cover is not explicitly Manway Cover Stainless Steel SCC Control Program identified in NUREG-1801. Although these Disc Insert component types are not included in the NUREG, the aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(19) Pressurizer Carbon Steel with Borated Water Loss of Material Boric Acid Loss of material due to boric acid corrosion was not Spray Nozzle, Stainless Steel Leaks due to Boric Acid Corrosion Program identified as an aging effect requiring management Relief Nozzle, Cladding or Disc Corrosion for these components in NUREG-1 801. The aging Safety Nozzle, Insert management program(s) referenced are appropriate Surge Nozzle and for the aging effects identified and provide Manway Cover (CS assurance that the aging effects are effectively Components) managed through the period of extended operation.
(20) SG Primary Low-Alloy Steel Primary Water Cracking due to ASME Section XI, Cracking due to Flaw Growth is not identified as an Channel Head, with Stainless Steel Flaw Growth Subsections IWB, aging effect requiring management for these Primary Inlet and Cladding IWC, & IWD components in NUREG-1801. The aging Outlet Nozzles, Inservice management program(s) referenced are appropriate Primary Inlet and Inspection Program for the aging effects identified and provide Outlet Nozzle Safe assurance that the aging effects are effectively
- Ends, managed through the period of extended operation.
Steam Generator Carbon Steel Secondary Water Shell and Transition Cone, Feedwater Nozzle, Steam Outlet Nozzle, Blowdown Piping Nozzle and Secondary-Side Shell Penetrations Page 3-70 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (21) SG Tubesheet Low-Alloy Steel Primary Water Cracking due to Water Chemistry Cracking due to SCC and flaw growth is not (Primary Side) with Alloy 600 SCC Control Program identified as an aging effect requiring management cladding for the primary side of the SG tubesheet in Cracking due to ASME Section XI, NUREG-1801. The aging management program(s)
Flaw Growth Subsections IWB, referenced are appropriate for the aging effects IWC, & IWD identified and provide assurance that the aging Inservice effects are effectively managed through the period Inspection Program of extended operation.
(22) SG Tubesheet Low Alloy Steel Secondary Water Loss of Material Water Chemistry Loss of material due to general, pitting and crevice (Secondary Side) due to General, Control Program corrosion and cracking due to flaw growth are not Pitting and Crevice identified as aging effects requiring management for Corrosion the secondary side of the SG tubesheet in NUREG-1801. The aging management program(s)
Cracking due to ASME Section XI, referenced are appropriate for the aging effects Flaw Growth Subsections IWB, identified and provide assurance that the aging IWC, & IWD effects are effectively managed through the period Inservice of extended operation.
Inspection Program (23) SG Primary Alloy 690 Primary Water Cracking due to Water Chemistry Cracking due to SCC is not identified as an aging Channel Head SCC Control Program effect requiring management for the SG divider Divider Plate plate in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-71 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (24) SG Feedwater Carbon/Low-Alloy Secondary Water Loss of Material Water Chemistry Loss of material due to general, pitting and crevice Nozzle, Steam Steel due to General, Control Program corrosion was not identified in NUREG-1 801 as an Outlet Nozzle, Pitting and Crevice aging effect requiring management for these Steam Flow Corrosion components exposed to the secondary-side SG Restrictor, environment. The aging management program(s)
Blowdown Piping referenced are appropriate for the aging effects Nozzles and identified and provide assurance that the aging Secondary-Side effects are effectively managed through the period Shell Penetrations, of extended operation.
Secondary Closures, and Internal Shroud, Primary and Secondary Decks (25) SG Lattice Stainless Steel Secondary Water Cracking due to Water Chemistry As discussed in Table 3.2-1 Line Number (17)
Grid Tube SCC Control Program cracking due to SCC and loss of material due to Supports, U-Bend pitting and crevice corrosion were not identified as Fan Bar Restraints Loss of Material Steam Generator aging effects requiring management in due to Pitting and Tube Integrity NUREG-1801 for the lattice grid tube supports and Crevice Corrosion Program U-bend fan bar restraints. The aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(26) SG Primary Carbon/Low-Alloy Borated Water Loss of Material Boric Acid Loss of material due to boric acid corrosion was not Inlet and Outlet Steel Leaks due to Boric Acid Corrosion Program identified as an aging effect requiring management Nozzles and Corrosion in NUREG-1 801 for the external surfaces of the Support Pads (CS primary inlet and outlet nozzles and support pads.
Components)
The aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-72 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (27) SG Support Carbon Steel Containment Air Cracking due to ASME Section XI, Cracking due to flaw growth was not identified in Pads, Seismic Lugs Flaw Growth Subsections IWB, NUREG-1 801 as an aging effect requiring IWC, & IWD management for the support pads and seismic lugs.
Inservice The aging management program(s) referenced are Inspection Program appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(28) Non-Class 1 Carbon Steel, Air and Gas No Aging Effects No AMP Required Non-Class 1 RCS carbon steel, stainless steel, RCS Manual Stainless Steel, CASS and copper alloy components exposed to air
Valves, Strainers, PORV Operators, Stainless Steel Air and Gas, Accumulators, Wetted (<1400F)
Nitrogen Surge Tanks, Piping (29) Non-Class 1 Carbon Steel Air and Gas, Loss of Material Periodic Non-Class 1 RCS carbon steel piping exposed to a RCS Piping Wetted (<1400F) due to General, Surveillance and wetted air and gas (<1400 F) environment is not Crevice, Pitting, Preventive identified in NUREG-1801. Although these Galvanic Corrosion Maintenance component types are not included in the NUREG, and MIC the aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(30) Reactor Carbon Steel Treated Water -
Loss of Material Water Chemistry The Reactor Coolant Pump upper bearing cooler is Coolant Pump Other due to General, Control Program a Non-Class 1 RCS component which is not Upper Bearing Crevice, and identified in NUREG-1801. Although these Cooler Galvanic Corrosion component types are not included in the NUREG, and MIC the aging management program(s) referenced are appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-73 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (31) Reactor Copper Alloy Oil and Fuel Oil Loss of Material Periodic The Reactor Coolant Pump Motor upper and lower Coolant Pump (Zn<15%, Zn>15%)
due to MIC Surveillance and bearing cooling coils are Non-Class 1 components Motor Upper and Preventive which are not identified in NUREG-1801. Although Lower Bearing Maintenance these component types are not included in the Cooling Coil NUREG, the aging management program(s) referenced are appropriate for the aging effects Treated Water -
Loss of Material Water Chemistry identified and provide assurance that the aging Other due to MIC, Control Program effects are effectively managed through the period Crevice and of extended operation.
Galvanic Corrosion, and Selective Leaching Treated Water -
Loss of Heat Water Chemistry Other Transfer due to Control Program Particulate and Biological Fouling (32) Seal Table Stainless Steel Treated Water -
Loss of Material Water Chemistry The seal table is a Non-Class 1 component which is Borated (<1400F) due to Crevice and Control Program not identified in NUREG-1 801 Although these Pitting Corrosion component types are not included in the NUREG, and MIC One-Time the aging management program(s) referenced are Inspection Program appropriate for the aging effects identified and provide assurance that the aging effects are effectively managed through the period of extended operation.
(33) External Carbon/Low Alloy Containment No Aging Effects No AMP Required External surfaces of carbon/low-alloy steel Surfaces of Steel Atmosphere components in the Reactor Coolant System Carbon/Low-Alloy
(>212-F) exposed to the Containment atmosphere are not Steel Components identified in NUREG-1801. No aging effects are in Reactor Coolant Containment Loss of Material Systems Monitoring identified for those components which normally System Atmosphere due to General and Program operate at temperatures > 212 0F. For components
(<212'F)
Pitting Corrosion with service temperatures < 212 0F, loss of material due to general and pitting corrosion is an applicable aging effect which is effectively managed by the Systems Monitoring Program.
Page 3-74 Application for Renewed Operating License
Table 3.2-2 Reactor Coolant System - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion L34) External Stainless Steel Borated Water No Aging Effects No AMP Required External surfaces of stainless steel and nickel alloy surfaces of Nickel Alloy Leaks components in the Reactor Coolant System Stainless Steel and exposed to the Containment atmosphere or borated Nickel-Alloy Containment water leaks are not identified in NUREG-1 801.
Components in Atmosphere There are no applicable aging effects for stainless Reactor Coolant steel or nickel alloy components exposed to borated System water leaks or the Containment atmosphere.
Page 3-75 Application for Renewed Operating License
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Section 3.2 References
- 1.
WCAP-1 4575-A, Aging Management Evaluation for Class I Piping and Associated Pressure Boundary Components, December, 2000.
- 2.
WCAP-1 4577, Rev. l-A, License Renewal Evaluation: Aging Management for Reactor Internals, March, 2001.
- 3.
WCAP-14574-A, License Renewal Evaluation: Aging Management Evaluation for Pressurizers, December, 2000.
Page 3-76
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.3 Aging Management of Engineered Safety Features Systems The results of the aging management review of the Engineered Safety Features Systems components are provided in this section and summarized in Tables 3.3-1 and 3.3-2. Table 3.3-1 shows the aging management of system components evaluated in NUREG-1 801 that are relied on for license renewal of the Engineered Safety Features Systems components at Ginna. Included in the table is a discussion column. The discussion column will provide a conclusion indicating if the aging management evaluation results are consistent with NUREG-1 801 along with any clarifications or explanations required to support the stated conclusion if that conclusion is different than those of the NUREG. For a determination to be made that a table line item is "Consistent with NUREG-1 801" several criteria must be met. First the plant specific component is reviewed against the GALL to ensure that the component, materials of construction and internal or external service environment are comparable to those described in a particular GALL item.
Second, for those that are comparable, the results of the plant aging management review-aging effect evaluation are compared to the aging effects/mechanisms in the GALL. Finally, the programs credited in the GALL for managing those aging effects are compared to the programs invoked in the plant evaluation. If, using good engineering judgment, it could be reasonably concluded that the plant evaluation is in agreement with the GALL evaluation a line item was considered consistent with NUREG-1 801. There are cases where components and component material/environment combinations and aging effects are common between a NUREG-1 801 line item and the plant evaluation but the aging management program selections differ. In those cases the discussion column will indicate the plant aging management program selection but no conclusion will be made that the line item is consistent with the GALL. Table 3.3-2 contains the Engineered Safety Features Systems components aging management review results that are not addressed in NUREG-1801. A plant component is considered not addressed by the NUREG if the component type is not evaluated in the GALL or has a different material of construction or operating environment than evaluated in the GALL. This table includes the component types, materials, environments, aging effects requiring management, the programs and activities for managing aging, and a discussion column. To avoid confusion, no attempt was made to interrelate material/environment/aging effects from one NUREG-1 801 chapter to another. Note that these tables only include those components, materials and environments that are applicable to a PWR.
Page 3-77
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Materials The materials of construction of a component have a major influence on the evaluation of aging effects applicable to the component. Sources of information used to identify materials of construction include original equipment specifications, vendor technical manuals and drawings, fabrication drawings, piping line specifications, modification design records and field walkdowns/verifications. The tables below account for the materials of construction for the components requiring an aging management review.
Since similar materials are susceptible to the same aging effects/mechanisms, the tables itemize the component types (i.e., groupings) while factoring in the materials of construction.
Environment As previously described, the environment(s) to which components are exposed are critical in the determination of potential aging mechanisms and effects. A review of plant design documentation was performed to quantify the environmental conditions to which Ginna Station equipment is exposed. This review identified that some equipment is exposed to a variety of environments. This can include normal operating conditions and post accident conditions. Since aging mechanisms and effects will be primarily driven by the environmental conditions to which equipment is exposed on a daily basis, under normal operating conditions, these conditions will differ from the design parameters which are established based upon the worst case scenario (e.g., LOCA conditions). Ginna Station equipment environments may be categorized into basic external and internal environments detailed in Section 3.1.2.
Aging Effects Requiring Management After the components requiring aging management review were identified and grouped by materials of construction and environment, a review of industry and plant-specific operating experience was performed. The purpose of this review was to assure that all applicable aging effects were identified, and to evaluate the effectiveness of existing aging management programs.
This experience review was performed utilizing various industry and plant-specific programs and databases. Industry operating experience sources included NRC Generic Publications (including Information Notices, Circulars, Bulletins, and Generic Letters),
INPO Significant Operating Event Reports (SOER), EPRI Technical Reports, and other information sources, such as the B&W Owners Group Non-Class 1 Mechanical Tools Implementation document, Westinghouse Generic Technical Reports (GTRs), and the Generic Aging Lessons Learned (GALL) report.
Page 3-78
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Plant specific operating experience sources included Semi-annual and Annual Reports to AEC/NRC, Abnormal Occurrence and Licensee Event Reports (LERs),
Non-Conformance Reports (NCRs), Corrective Action Reports (CARs), Refueling, Inspection and Overhaul Reports (RIOs), Inservice Inspection (ISI) Reports, Identified Deficiency Reports (IDRs), and ACTION Reports (ARs) from 1969 to the present.
Information from these sources was compiled in various databases. Based upon the material of construction, the applicable environments, and operating experience the potential aging effects requiring management for each of the components was identified as documented in the tables below.
Time-Limited Aging Analysis In addition to those identified in NUREG-1 801, any additional time-limited aging analyses (TLAA) identified as appropriate to the system are identified in Section 4.0.
Conclusion The programs and activities selected to manage the aging effects of the Engineered Safety Features Systems are identified in Table 3.3-1 and Table 3.3-2. A description of these aging management activities is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the system components will be adequately managed so that there is reasonable assurance that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation.
Page 3-79
Table 3.3-1 Engineered Safety Features Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (1) Piping, fittings, and Cumulative fatigue TLAA, evaluated in Yes, TLAA Consistent with NUREG-1 801. Cumulative Fatigue Damage is valves in emergency core damage accordance with 10 addressed as a TLAA in Section 4.3.
cooling system CFR 54.21(c)
(2) Components in Loss of material Plant specific Yes, plant specific The combination of components, materials and environments containment spray (PWR due to general identified in Items V.A.2-a and V.A.5-a are not applicable at only), standby gas corrosion Ginna Station. Components identified in Item V.C.1-a are treatment (BWR only),
included in the containment isolation valves and associated containment isolation, and piping entry under line item 4 below in this table.
emergency core cooling systems (3) Components in Loss of material Plant specific Yes, plant specific Consistent with NUREG-1801 (containment isolation containment spray (PWR due to pitting and components and RWST bottom). The One-Time Inspection only), standby gas crevice corrosion Program manages these aging effects for RWST bottom. The treatment (BWR only),
Systems Monitoring Program is credited for managing all other containment isolation, and applicable aging effects.
emergency core cooling systems (4) Containment isolation Loss of material Plant specific Yes, plant specific Consistent with NUREG-1 801 (containment isolation valves and associated due to components such as valves and pipe penetrations). The aging piping microbiologically effect "loss of material due to microbiologically influenced influenced corrosion (MIC)" is managed by the plant-specific Periodic corrosion Surveillance and Preventive Maintenance Program.
(5) High pressure safety Loss of material Plant specific Yes, plant specific The high pressure safety injection pumps are not used for injection (charging) pump due to erosion normal charging at Ginna Station. Loss of material due to miniflow orifice erosion of miniflow orifices is not applicable at Ginna Station.
(6) Piping and fittings of Loss of fracture Thermal aging No There are no CASS piping and fittings in the emergency core CASS in emergency core toughness due to embrittlement of cooling system at Ginna Station which are subject to loss of cooling system thermal aging CASS fracture toughness due to thermal aging embrittlement.
embrittlement Page 3-80 Application for Renewed Operating License
Table 3.3-1 Engineered Safety Features Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (7) Components serviced Local loss of Open-cycle cooling No The combination of components, materials and environments by open-cycle cooling material due to water system identified in Items V.A.6-a, V.A.6-b, V.D1.6-b and V.D1.6-c are system corrosion and/or not applicable at Ginna Station.
buildup of deposit due to biofouling (8) Components serviced Loss of material Closed-cycle No Consistent with NUREG-1 801. The Closed-Cycle (Component) by closed-cycle cooling due to general, cooling water Cooling Water System Program is credited with managing the system pitting, and crevice system aging effect "loss of material due to general, pitting and crevice corrosion corrosion." The program includes maintenance of corrosion inhibitor concentrations to minimize corrosion and periodic surveillance testing and inspections to evaluate system and component performance and condition.
(9) Pumps, valves, piping, Crack initiation and Water chemistry No Consistent with NUREG-1801. Although the NUREG and fittings in containment growth due to SCC references a temperature gate of < 900C (2000F) and a single spray and emergency core aging effect (cracking due to SCC), materials science supports cooling systems (1) a temperature gate > 1401F for cracking due to SCC, and (2) loss of material due to pitting (stagnant or low flow conditions) and crevice corrosion for all temperatures. Although the aging effect identified by Ginna (loss of material) for temperatures < 140OF differs from that of the NUREG, the Water Chemistry Control Program credited for managing the aging effects for all temperatures is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. A One-Time Inspection Program is also credited to verify the adequacy of the Water Chemistry Control program.
(10) Carbon steel Loss of material Boric acid corrosion No Consistent with NUREG-1801. The Boric Acid Corrosion components due to boric acid Program is credited with managing the aging effect "loss of corrosion material due to boric acid corrosion."
Page 3-81 Application for Renewed Operating License
Table 3.3-1 Engineered Safety Features Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (11)
Closure bolting in high Loss of material Bolting integrity No Consistent with NUREG-1801. The Bolting Integrity Program is pressure or high due to general credited for managing the aging effects "loss of material due to temperature systems corrosion, loss of general corrosion and crack initiation and growth due to cyclic preload due to loading and SCC." There are no bolts with a specified minimum stress relaxation, yield strength > 150 ksi in the ESF Systems. Therefore, SCC is and crack initiation not an applicable aging effect/mechanism.
and growth due to cyclic loading or SCC Page 3-82 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (1) ACCUMULATOR Carbon/Low Alloy Containment Loss of Material Systems Consistent with Item E.1 -b of NUREG-1 801.
Steel Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(2) BLOWER Carbon/Low Alloy Air and Gas Loss of Material Periodic Material and environment grouping are not CASING Steel (Wetted) < 140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(3) BLOWER Carbon/Low Alloy Containment Loss of Material Systems Consistent with Item E.l-b of NUREG-1 801.
CASING Steel Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(4) CONTROLLER 1 Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (5) CONTROLLER 1 Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (6) CONTROLLER 1 Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required Page 3-83 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types NUREG-1801 Subject to Aging Management not Evaluated in Component Type Material Type Environment Type AERMs Program/Activity Discussion (7) DELAY COIL Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (8) EDUCTOR Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (9) FASTENERS Carbon/Low Alloy Indoor (No Air Cracking due to Bolting Integrity There are no bolts with a specified minimum yield (BOLTING)
Steel Conditioning)
SCC Program strength > 150 ksi in this system. Therefore, SCC is not an applicable aging effect/mechanism.
(10) FASTENERS Carbon/Low Alloy Indoor (No Air Loss of Preload Bolting Integrity Material and environment grouping are included in (BOLTING)
Steel Conditioning) due to Stress Program NUREG-1801. Aging effect of loss of preload due Relaxation to stress relaxation is applicable, but is not included in Chapter V - Section E, Chapter VII Section I, or Chapter VIII - Section H of the NUREG.
(11) FASTENERS Stainless Steel Borated Water No Aging Effects No Aging Material and environment grouping are not (BOLTING)
Leaks Management included in NUREG-1801.
Program Required (12) FILTER Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not HOUSING Steel Management included in NUREG-1801.
Program Required (13) FILTER Carbon/Low Alloy Indoor (No Air Loss of Material Systems Consistent with Item E.1-b of NUREG-1801.
HOUSING Steel Conditioning)
Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
Page 3-84 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (14) FLANGE Carbon/Low Alloy Containment Loss of Material Systems Consistent with Item E.1-b of NUREG-1801.
Steel Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(15) FLANGE Carbon/Low Alloy Outdoor Loss of Material Systems Consistent with Item E.1-b of NUREG-1801.
Steel Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(16) FLOW Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not ELEMENT Steel Management included in NUREG-1801.
Program Required (17) FLOW Carbon/Low Alloy Indoor (No Air Loss of Material Systems Consistent with Item E.1-b of NUREG-1801.
ELEMENT Steel Conditioning)
Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(18) FLOW Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not ELEMENT Management included in NUREG-1801.
Program Required (19) FLOW Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT Conditioning)
Management included in NUREG-1801.
Program Required Page 3-85 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (20) FLOW Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not NOZZLES Management included in NUREG-1801.
Program Required (21) FLOW Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not NOZZLES Management included in NUREG-1801.
Program Required (22) HEAT Carbon/Low Alloy Indoor (No Air Loss of Material Systems Consistent with Item E. -b of NUREG-1801.
EXCHANGER Steel Conditioning)
Monitoring Volume 1, Table 2 includes "External surface of Program carbon steel components" with a plant specific aging management program. This material and environment grouping is not included in NUREG-1800 Table 3.2-1. The Systems Monitoring Program is credited for managing this aging effect.
(23) HEAT Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not EXCHANGER Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(24) HEAT Cast Iron Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not EXCHANGER Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(25) HEAT Cast Iron Raw Water Loss of Material One-Time Material and environment grouping are not EXCHANGER Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-86 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (26) HEAT HX-Cast Iron 2 Oil and Fuel Oil Loss of Heat Periodic Material and environment grouping are not EXCHANGER Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(27) HEAT HX-Cast Iron 2 Raw Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(28) HEAT HX-Nickel Alloy 2 Treated Water Loss of Heat Water Chemistry Material and environment grouping are not EXCHANGER Borated <140 Transfer Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(29) HEAT HX-Nickel Alloy 2 Treated Water Loss of Heat Closed-Cycle Material and environment grouping are not EXCHANGER Other Transfer (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(30) HEAT Nickel Alloy Treated Water Loss of Material One-Time Material and environment grouping are not EXCHANGER Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-87 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (31) HEAT Nickel Alloy Treated Water Loss of Material Water Chemistry Material and environment grouping are not EXCHANGER Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(32) HEAT Nickel Alloy Treated Water Loss of Material Closed-Cycle Material and environment grouping are not EXCHANGER Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(33) HEAT Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not EXCHANGER Conditioning)
Management included in NUREG-1801.
Program Required (34) INDICATOR 1 Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (35) ORIFICE Cast Austenitic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Stainless Steel Conditioning)
Management included in NUREG-1801.
Program Required (36) ORIFICE Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-88 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types NUREG-1801 Subject to Aging Management not Evaluated in Component Type Material Type Environment Type AERMs Program/Activity Discussion (37) ORIFICE Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(38) ORIFICE Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (39) ORIFICE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (40) PIPE Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not Steel Management included in NUREG-1801.
Program Required (41) PIPE Carbon/Low Alloy Air and Gas Loss of Material One-Time Material and environment grouping are not Steel (Wetted) < 140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(42) PIPE Carbon/Low Alloy Buried Loss of Material One-Time Material and environment grouping are not Steel Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(43) PIPE Copper Alloy (Zn Air and Gas No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required Page 3-89 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (44) PIPE Copper Alloy (Zn Containment No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (45) PIPE Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (46) PIPE Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (47) PIPE Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (48) PIPE Stainless Steel Concrete No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (49) PIPE Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (50) PIPE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (51) PIPE Stainless Steel Outdoor No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required 1__
Page 3-90 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (52) PIPE Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(53) PIPE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(54) PUMP CASING Cast Austenitic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Stainless Steel Conditioning)
Management included in NUREG-1801.
Program Required (55) PUMP CASING Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(56) PUMP CASING Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-91 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (57) PUMP CASING Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (58) PUMP CASING Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (59) RECOMBINER Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not CASING Management included in NUREG-1801.
Program Required (60) RECOMBINER Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not CASING Management included in NUREG-1801.
Program Required (61) SWITCH1 Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (62) TANK Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (63) TANK Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-92 Application for Renewed Operating License
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Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (64) TANK Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(65) TEMPERATURE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT' Conditioning)
Management included in NUREG-1801.
Program Required (66) THERMOWELL Copper Alloy (Zn Air and Gas Loss of Material One-Time Material and environment grouping are not
< 15%)
(Wetted) <140 Inspection included in NUREG-1 801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(67) THERMOWELL Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (68) TRANSMITTER' Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (69) VALVE BODY Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not Steel Management included in NUREG-1801.
Program Required (70) VALVE BODY Carbon/Low Alloy Air and Gas Loss of Material Periodic Material and environment grouping are not Steel (Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-93 Application for Renewed Operating License
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Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (71) VALVE BODY Cast Austenitic Air and Gas No Aging Effects No Aging Material and environment grouping are not Stainless Steel Management included in NUREG-1801.
Program Required (72) VALVE BODY Cast Austenitic Air and Gas No Aging Effects No Aging Material and environment grouping are not Stainless Steel (Wetted) <140 Management included in NUREG-1801.
Program Required (73) VALVE BODY Cast Austenitic Containment No Aging Effects No Aging Material and environment grouping are not Stainless Steel Management included in NUREG-1801.
Program Required (74) VALVE BODY Cast Austenitic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Stainless Steel Conditioning)
Management included in NUREG-1801.
Program Required (75) VALVE BODY Cast Austenitic Raw Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(76) VALVE BODY Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(77) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-94 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (78) VALVE BODY Cast Austenitic Treated Water Cracking due to One-Time Material and environment grouping are not Stainless Steel Borated >140 SCC Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(79) VALVE BODY Cast Austenitic Treated Water Cracking due to Water Chemistry Material and environment grouping are not Stainless Steel Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(80) VALVE BODY Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Borated >140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(81) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated >140 Contro! Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-95 Application for Renewed Operating License
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f
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (82) VALVE BODY Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(83) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(84) VALVE BODY Cast Iron Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (85) VALVE BODY Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(86) VALVE BODY Copper Alloy (Zn Air and Gas No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (87) VALVE BODY Copper Alloy (Zn Air and Gas Loss of Material One-Time Material and environment grouping are not
< 15%)
(Wetted) <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-96 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (88) VALVE BODY Copper Alloy (Zn Containment No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (89) VALVE BODY Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (90) VALVE BODY Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (91) VALVE BODY Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (92) VALVE BODY Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1 801.
Program Required (93) VALVE BODY Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (94) VALVE BODY Stainless Steel Outdoor No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (95) VALVE BODY Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-97 Application for Renewed Operating License
Table 3.3-2 Engineered Safety Features Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Type Material Type Environment Type AERMs Program/Activity Discussion (96) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(97) VENTILATION Galvanized Air and Gas No Aging Effects No Aging Material and environment grouping are not DUCTWORK Carbon Steel (Wetted) <140 Management included in NUREG-1801.
Program Required (98) VENTILATION Galvanized Containment No Aging Effects No Aging Material and environment grouping are not DUCTWORK Carbon Steel Management included in NUREG-1801.
I___I___I___Program Required 1_1_
- 1. Selected instruments were conservatively included within the scope of License Renewal. Consideration was given to the consequences of an instrument housing pressure boundary failure. Where an instrument was unisolable from a pressure source and is of sufficient size that a system function would be degraded should the pressure boundary fail, that instrument is included for License Renewal review.
- 2. Material prefixes with HX are used to identify heat exchanger materials which perform a heat transfer intended function in addition to the typical material usage function of pressure boundary.
Page 3-98 Application for Renewed Operating License
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information 3.4 Aging Management of Auxiliary Systems The results of the aging management review of the Auxiliary Systems components are provided in this section and summarized in Tables 3.4-1 and 3.4-2. Table 3.4-1 shows the aging management of system components evaluated in NUREG-1801 that are relied on for license renewal of the Auxiliary Systems components at Ginna. Included in the table is a discussion column. The discussion column will provide a conclusion indicating if the aging management evaluation results are consistent with NUREG-1801 along with any clarifications or explanations required to support the stated conclusion if that conclusion is different those of the NUREG. For a determination to be made that a table line item is "Consistent with NUREG-1801" several criteria must be met. First the plant specific component is reviewed against the GALL to ensure that the component, materials of construction and internal or external service environment are comparable to those described in a particular GALL item. Second, for those that are comparable, the results of the plant aging management review-aging effect evaluation are compared to the aging effects/mechanisms in the GALL. Finally, the programs credited in the GALL for managing those aging effects are compared to the programs invoked in the plant evaluation. If, using good engineering judgment, it could be reasonably concluded that the plant evaluation is in agreement with the GALL evaluation a line item was considered consistent with NUREG-1 801. There are cases where components and component material/environment combinations and aging effects are common between a NUREG-1 801 line item and the plant evaluation but the aging management program selections differ. In those cases the discussion column will indicate the plant aging management program selection but no conclusion will be made that the line item is consistent with the GALL. Table 3.4-2 contains the Auxiliary Systems components aging management review results that are not addressed in NUREG-1 801. A plant component is considered not addressed by the NUREG if the component type is not evaluated in the GALL or has a different material of construction or operating environment than evaluated in the GALL. This table includes the component types, materials, environments, aging effects requiring management, the programs and activities for managing aging, and a discussion column. To avoid confusion, no attempt was made to interrelate material/environment/aging effects from one NUREG-1 801 chapter to another. Note that these tables only include those components, materials and environments that are applicable to a PWR.
Page 3-99
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Materials The materials of construction of a component have a major influence on the evaluation of aging effects applicable to the component. Sources of information used to identify materials of construction include original equipment specifications, vendor technical manuals and drawings, fabrication drawings, piping line specifications, modification design records and field walkdowns/verifications. The tables below account for the materials of construction for the components requiring an aging management review.
Since similar materials are susceptible to the same aging effects/mechanisms, the tables itemize the component types (i.e., groupings) while factoring in the materials of construction.
Environment As previously described, the environment(s) to which components are exposed are critical in the determination of potential aging mechanisms and effects. A review of plant design documentation was performed to quantify the environmental conditions to which Ginna Station equipment is exposed. This review identified that some equipment is exposed to a variety of environments. This can include normal operating conditions and post accident conditions. Since aging mechanisms and effects will be primarily driven by the environmental conditions to which equipment is exposed on a daily basis, under normal operating conditions, these conditions will differ from the design parameters which are established based upon the worst case scenario (e.g., LOCA conditions). Ginna Station equipment environments may be categorized into basic external and internal environments detailed in Section 3.1.2.
Aging Effects Requiring Management After the components requiring aging management review were identified and grouped by materials of construction and environment, a review of industry and plant-specific operating experience was performed. The purpose of this review was to assure that all applicable aging effects were identified, and to evaluate the effectiveness of existing aging management programs.
This experience review was performed utilizing various industry and plant-specific programs and databases. Industry operating experience sources included NRC Generic Publications (including Information Notices, Circulars, Bulletins, and Generic Letters),
INPO Significant Operating Event Reports (SOER), EPRI Technical Reports, and other information sources, such as the B&W Owners Group Non-Class 1 Mechanical Tools Implementation document, Westinghouse Generic Technical Reports (GTRs), and the Generic Aging Lessons Learned (GALL) report.
Page 3-100
R. E. Ginna Nuclear Power Plant Application for Renewed Operating License Technical and Administrative Information Plant specific operating experience sources included Semi-annual and Annual Reports to AEC/NRC, Abnormal Occurrence and Licensee Event Reports (LERs),
Non-Conformance Reports (NCRs), Corrective Action Reports (CARs), Refueling, Inspection and Overhaul Reports (RIOs), Inservice Inspection (ISI) Reports, Identified Deficiency Reports (IDRs), and ACTION Reports (ARs) from 1969 to the present.
Information from these sources was compiled in various databases. Based upon the material of construction, the applicable environments, and operating experience the potential aging effects requiring management for each of the components was identified as documented in the tables below.
Time-Limited Aging Analysis In addition to those identified in NUREG-1 801, any additional time-limited aging analyses (TLAA) identified as appropriate to the system are identified in Section 4.0.
Conclusion The programs and activities selected to manage the aging effects of the Auxiliary Systems are identified in Table 3.4-1 and Table 3.4-2. A description of these aging management activities is provided in Appendix B, along with the demonstration that the identified aging effects will be managed for the period of extended operation. Therefore, based on the demonstrations provided in Appendix B, the effects of aging associated with the system components will be adequately managed so that there is reasonable assurance that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation.
Page 3-101
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (1) Components in spent Loss of material Water chemistry Yes, detection of Consistent with NUREG-1801. The Water Chemistry Control fuel pool cooling and due to general, and one-time aging effects is to Program is credited with managing the aging effects of loss of cleanup pitting, and crevice inspection be further material due to general, pitting, and crevice corrosion. The corrosion evaluated One-Time Inspection as well as the Periodic Surveillance and Preventive Maintenance Programs will be used to verify the effectiveness of the Water Chemistry Control Program.
(2) Linings in spent fuel Hardening, Plant specific Yes, plant specific Consistent with NUREG-1801. The Spent Fuel Cooling system pool cooling and cleanup cracking and loss (Section A3 of the NUREG) at Ginna Station contains no system; seals and collars in of strength due to components that are elastomer lined.
ventilation systems elastomer For ventilation systems, the One-Time Inspection and Periodic degradation; loss of Surveillance and Preventive Maintenance Programs are material due to credited for managing the hardening, cracking and loss of wear strength aging effects. The Systems Monitoring Program is credited for managing the aging effect of loss of material due to wear.
(3) Components in load Cumulative fatigue TLAA, evaluated in Yes, TLAA Consistent with NUREG-1801. Cumulative Fatigue Damage is handling, chemical and damage accordance with 10 addressed as a TLAA in Section 4.3.
volume control system CFR 54.21 (c)
(PWR), and reactor water cleanup and shutdown cooling systems (older BWR)
Page 3-102 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (4) Heat exchangers in Crack initiation and Plant specific Yes, plant specific Consistent with NUREG-1801. Although the NUREG reactor water cleanup growth due to SCC references a temperature gate of < 900C (2000F) and a single system (BWR); high or cracking aging effect (cracking due to SCC), materials science supports pressure pumps in chemical (1) a temperature gate > 140OF for cracking due to SCC, and andevolume controln syemia (2) loss of material due to pitting (stagnant or low flow and volume control system conditions) and crevice corrosion for all temperatures. The (PWR) aging effect identified by Ginna (loss of material) for temperatures < 140°F differs from that of the NUREG. That not withstanding, the Water Chemistry Control Program, credited for managing the aging effects for all temperatures, is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. The One-Time Inspection Program as well as the Periodic Surveillance and Preventive Maintenance Program are credited with verifying the adequacy of the Chemistry program.
(5) Components in Loss of material Plant specific Yes, plant specific Consistent with NUREG-1 801. For the internal environments of ventilation systems, diesel due to general, ventilation systems, the diesel fuel oil systems, and the fuel oil system, and pitting, and crevice emergency diesel generator system, the One-Time Inspection, emergency diesel generator corrosion, and MIC Periodic Surveillance and Preventive Maintenance, Closed-Cycle (Component) Cooling Water System, and the systems; external surfaces Fuel Oil Chemistry Programs are credited for managing of carbon steel components applicable aging effects.
For the external surfaces of all carbon steel components, the Systems Monitoring Program will be credited for managing the aging effects of loss of material.
(6) Components in reactor Loss of material One-time Yes, detection of Consistent with NUREG-1801. The aging effects of coolant pump oil collect due to galvanic, inspection aging effects is to components within the Reactor Coolant Pump Oil Collection system of fire protection general, pitting, and be further system will managed by the One-Time Inspection Program. In crevice corrosion evaluated addition, selected components will be inspected on a periodic basis in conjunction with the Periodic Surveillance and Preventive Maintenance Program.
Page 3-103 Application for Renewed Operating License
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Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in License Renewal NUREG-1801 that are Relied on for Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (7) Diesel fuel oil tanks in Loss of material Fuel oil chemistry Yes, detection of The Fuel Oil Chemistry Program is credited with managing diesel fuel oil system and due to general, and one-time aging effects is to applicable aging effects. In lieu of the One-Time Inspection emergency diesel generator pitting, and crevice inspection be further Program, Ginna Station has chosen to use the Periodic system corrosion, MIC, and evaluated Surveillance and Preventive Maintenance Program to verify the biofouling adequacy of the Fuel Oil Chemistry Program in managing these aging effects.
(8) Heat exchangers in Crack initiation and Water chemistry Yes, plant specific Consistent with NUREG-1801. Although the NUREG chemical and volume growth due to SCC and a plant-specific references a temperature gate of < 90'C (2000F) and a single control system and cyclic loading verification program aging effect (cracking due to SCC), materials science supports (1) a temperature gate > 140OF for cracking due to SCC, and (2) loss of material due to pitting (stagnant or low flow conditions) and crevice corrosion for all temperatures. The aging effect identified by Ginna (loss of material) for temperatures < 140OF differs from that of the NUREG. That not withstanding, the Water Chemistry Control Program, credited for managing the aging effects for all temperatures, is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. The One-Time Inspection Program as well as the Periodic Surveillance and Preventive Maintenance Program are credited with verifying the adequacy of the Water Chemistry Control Program.
(9) Neutron absorbing Reduction of Plant specific Yes, plant specific Consistent with NUREG-1801. The Periodic Surveillance and sheets in spent fuel storage neutron absorbing Preventive Maintenance Program will direct the scheduling of racks capacity and loss of activities that will detect applicable aging effects under the material due to Spent Fuel Pool Neutron Absorber Monitoring Program.
general corrosion (Boral, boron steel)
(10) New fuel rack Loss of material Structures No Consistent with NUREG-1801. The Structures Monitoring assembly due to general, monitoring Program is credited with managing the aging effects of loss of pitting, and crevice material due to general, pitting, and crevice corrosion.
corrosion Page 3-104 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (11) Spent fuel storage Crack initiation and Water chemistry No Consistent with NUREG-1 801. Although the NUREG racks and valves in spent growth due to references a temperature gate of < 900C (2000 F) and a single fuel pool cooling and stress corrosion aging effect (cracking due to SCC), materials science supports cleanup cracking (1) a temperature gate > 140'F for cracking due to SCC, and (2) loss of material due to pitting (stagnant or low flow conditions) and crevice corrosion for all temperatures. The aging effect identified by Ginna (loss of material) for temperatures < 140OF differs from that of the NUREG. That not withstanding, the Water Chemistry Control Program, credited for managing the aging effects for all temperatures, is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. The One-Time Inspection Program as well as the Periodic Surveillance and Preventive Maintenance Program are credited with verifying the adequacy of the Chemistry program.
(12) Neutron absorbing Reduction of Boraflex monitoring No Consistent with NUREG-1801. The Spent Fuel Pool Neutron sheets in spent fuel storage neutron absorbing Absorber Monitoring Program is functionally equivalent to the racks capacity due to Boraflex Monitoring Program. However, borated stainless steel Boraflex neutron absorber panels (line item 9 above) are included in the degradation scope of this monitoring program. Existing boraflex neutron absorber panels are not credited in the CLB for reactivity control in the Spent Fuel Pool, and therefore are excluded from the scope of this monitoring program.
The Spent Fuel Pool Neutron Absorber Monitoring Program manages the aging effects of reduction of neutron absorbing capacity and loss of material due to general corrosion of the borated stainless steel panels.
Page 3-105 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (13) Closure bolting and Loss of material Boric acid corrosion No Consistent with NUREG-1 801. The Boric Acid Corrosion external surfaces of carbon due to boric acid Program is credited with managing the aging effect of loss of steel and low-alloy steel corrosion material due to boric acid corrosion on the external surfaces of components carbon/low alloy steel components (including closure bolting).
Although not addressed in the NUREG, the following additional systems at Ginna Station contain carbon/low alloy steel components and have the potential for exposure to boric acid spillage (located in Containment or the Auxiliary Building) and are included in this evaluation: Component Cooling Water, Service Water, Fire Protection, Containment Ventilation, Essential Ventilation, Waste Disposal, Radiation Monitoring, and Cranes, Hoists and Lifting Devices.
(14) Components in or Loss of material Closed-cycle No Consistent with NUREG-1 801. Components within the serviced by closed-cycle due to general, cooling water Chemical and Volume Control, Component Cooling Water, cooling water system pitting, and crevice system Waste Disposal, and the Emergency Power systems are corrosion, and MIC subject to the Closed-Cycle (Component) Cooling Water System Program. This program is credited with managing the aging effects of loss of material due to general, pitting, and crevice corrosion as well as micro-biologically influenced corrosion (MIC).
(15) Cranes including Loss of material Overhead heavy No The Periodic Surveillance and Preventive Maintenance bridge and trolleys and rail due to general load and light load Program implements the Inspection of Heavy Load and system in load handling corrosion and wear handling systems Refueling Handling Systems procedures at Ginna Station. The system periodic inspections are credited with managing the aging effects of loss of material due to general corrosion and wear.
Page 3-106 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component EffectlMechanism Programs Recommended Discussion (16) Components in or Loss of material Open-cycle cooling No Consistent with NUREG-1801. Components within the Service serviced by open-cycle due to general, water system Water, Component Cooling Water, Containment Ventilation, cooling water systems pitting, crevice, and Spent Fuel Cooling, and the Emergency Power systems are galvanic corrosion, subject to the Open-Cycle Cooling (Service) Water System MIC, and Program as implemented by the Service Water System biofouling; buildup Reliability Optimization Program (SWSROP). This program is of deposit due to credited with managing the aging effects of loss of material due biofouling to general, pitting, crevice, and galvanic corrosion, MIC, and biofouling.
The Periodic Surveillance and Preventive Maintenance Program is used at Ginna Station to verify the effectiveness of the Open-Cycle Cooling (Service) Water System Program.
(17) Buried piping and Loss of material Buried piping and No The Buried Piping and Tanks Inspection Program is fittings due to general, tanks surveillance implemented by the Periodic Surveillance and Preventive pitting, and crevice Maintenance Program at Ginna Station. Tanks in the corrosion, and MIC or Emergency Power system are periodically inspected for signs Buried piping and Yes, detection of of applicable aging effects. In addition, a one-time ultrasonic tanks inspection aging effects and inspection will be performed to verify the effectiveness of the operating Preventive Maintenance Program.
experience are to For buried piping, the Fire Water System Program is credited be further for managing the effects of aging for buried cast iron piping and evaluated fittings. External surfaces of buried piping are visually examined during maintenance activities (inspections of opportunity) performed as a result of performance tests. No evidence of age-related degradation has been detected from inspections performed to date. Cast iron fire system and service water piping at Ginna Station is ductile cast iron, not gray cast iron. Ductile irons are not susceptible to loss of structural integrity due to selective leaching mechanisms, and generally display excellent resistance to general corrosion due to exposure to non-aggressive ground water. Ground water/lake water at Ginna Station is analyzed periodically and analyses performed to date confirm that the water is non-aggressive.
Page 3-107 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems-Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (18) Components in Loss of material Compressed air No The Instrument and Service Air systems are not in scope to compressed air system due to general and monitoring License Renewal and therefore not subject to an aging pitting corrosion management review.
(19) Components (doors Loss of material Fire protection No Consistent with NUREG-1801. The Fire Protection Program is and barrier penetration due to wear; credited with managing the aging effects of loss of material due seals) and concrete hardening and to wear and general corrosion and hardening and shrinkage for structures in fire protection shrinkage due to components/structures that act as fire barriers.
weathering (20) Components in Loss of material Fire water system No Consistent with NUREG-1801. The Fire Water System water-based fire protection due to general, Program is credited with managing the aging effects of loss of pitting, crevice, and material due to general, pitting, crevice, and galvanic corrosion, galvanic corrosion, MIC, and biofouling. At Ginna Station, the Periodic Surveillance MIC, and biofouling and Preventive Maintenance Program is used to verify the effectiveness of the Fire Water System Program.
(21) Components in diesel Loss of material Fire protection and No The Fuel Oil Chemistry Program is credited with managing the fire system due to galvanic, fuel oil chemistry applicable aging effects. At Ginna Station, the Periodic general, pitting, and Surveillance and Preventive Maintenance Program is used to crevice corrosion verify the effectiveness of this program.
(22) Tanks in diesel fuel oil Loss of material Above ground No There are no aboveground diesel fuel oil tanks in the system due to general, carbon steel tanks Emergency Power system at Ginna Station.
pitting, and crevice corrosion (23) Closure bolting Loss of material Bolting integrity No The Bolting Integrity Program is credited for managing the due to general aging effects "loss of material due to general corrosion, loss of corrosion; crack preload due to stress relaxation, and crack initiation and growth initiation and due to cyclic loading and SCC." There are no bolts with a growth due to cyclic specified minimum yield strength > 150 ksi in the Auxiliary loading and SCC Systems. Therefore, SCC is not an applicable aging mechanism.
Page 3-108 Application for Renewed Operating License
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Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (24) Components Loss of material Selective leaching No In addition to the Open-Cycle Cooling (Service) Water System (aluminum bronze, brass, due to selective of materials and Closed-Cycle (Component) Cooling Water System cast iron, cast steel) in leaching Programs, the Periodic Surveillance and Preventive open-cycle and Maintenance Program or the One-Time Inspection Program will closed-cycle cooling water be credited with managing the aging effect of loss of material for components within the Open and Closed-Cycle Cooling systems, and ultimate heat Water systems.
sink Page 3-109 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further 1
Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (25) Fire barriers, walls, ceilings and floors in fire protection Concrete cracking and spalling due to freeze-thaw, aggressive chemical attack, and reaction with aggregates; loss of material due to corrosion of embedded steel Fire protection and structures monitoring No
.1 _______________
L _______________
Page 3-110 Application for Renewed Operating License The Fire Protection Program in conjunction with the Structures Monitoring Program identifies the evidence that an aging mechanism is present and active and also provides confirmation and verification of the absence of all types of aging effects. Indication of aging effects may be absent if the materials of construction, design specifications, and operational environment preclude an aging mechanism but, due to the long lead time necessary for some effects to manifest themselves, it is prudent to periodically assess the condition of SSCs regardless of the likelihood that a particular aging mechanism is applicable. The degradation of inaccessible concrete can create symptoms of aging effects that are detectable in accessible areas. Conversely, if aging effects are present in accessible areas it is sensible to extrapolate those effects into inaccessible areas and perform additional evaluations.
Concrete in indoor and outdoor environments have been evaluated for the following aging mechanisms:
Aging Mechanism: Freeze-Thaw Aging Effect: Loss of Material Evaluation: The contract-specified air contents are within the range specified by current revisions of ACI 318, and the contract-specified water-to-cement ratio meets the recommendations of ACI 318-63 L< 0.53). Therefore, loss of material and cracking of concrete due to freeze-thaw are not probable aging effects at Ginna Station and have not been observed to date.
Aging Mechanism: Aggressive Chemical Attack Aging Effect: Loss of Material, Changes in Material Properties Evaluation: Concrete degradation in air due to aggressive rainwater is insignificant and the below-grade/lake water environment is non-aggressive. Additionally, recent structural inspections revealed no evidence of degradation owing to aggressive chemical attack; therefore, loss of material and change in material properties due to aggressive chemical
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (25) (continued) attack are not probable aging effects at Ginna Station and have not been observed to date. The Structures Monitoring Program requires periodic monitoring of ground/lake water to verify chemistry remains non-aggressive.
Aging Mechanism: Corrosion of Embedded Steel Aging Effect: Loss of Material, Cracking, Loss of Bond Evaluation: Since the embedded steel is not exposed to an environment which is considered aggressive, loss of material, cracking, and loss of bond due to corrosion of embedded steel are not probable aging effects at Ginna Station and have not been observed to date.
Aging Mechanism: Reaction with Aggregates Aging Effect: Cracking, Expansion Evaluation: During construction the aggregates were tested for potential reactivity in accordance with ASTM C227 and ASTM C295, cracking and expansion due to reaction with aggregates are not probable aging effects at Ginna Station and have not been observed to date.
Aging Mechanism: Settlement Aging Effect: Cracking, Distortion, Increase in Component Stress Level Evaluation: All structures at Ginna Station are either founded on bedrock, steel foundation piles that are driven to bedrock, or have foundations that consist of caissons extending to bedrock. Structural inspections indicate no visible evidence of settlement since construction of the station. During the Systematic Evaluation Program, the NRC concluded that settlement of foundations and buried equipment is not a safety concern for Ginna Station. Cracking, distortion, and an increase in component stress levels due to settlement are not probable aging effects at Ginna Station and have not been observed to date.
Page 3-111 Application for Renewed Operating License
Table 3.4-1 Auxiliary Systems - Aging Management Programs Evaluated in NUREG-1801 that are Relied on for License Renewal Aging Further Aging Management Evaluation Component Effect/Mechanism Programs Recommended Discussion (25) (continued)
Aging Mechanism: Leaching of Calcium Hydroxide Aging Effect: Change in Material Properties Evaluation: The original construction specifications met the intent of ACI 201.2R. Change in material properties due to leaching of calcium hydroxide is not a probable aging effect at Ginna Station and has not been observed to date.
Additionally, masonry walls are used as fire barriers at Ginna Station. Masonry wall inspections are incorporated into the Structures Monitoring Program. The Structures Monitoring Program effectively manages cracking due to restraint, shrinkage and creep.
Operating experience has shown that concrete has not experienced unanticipated aging effects at Ginna Station. That notwithstanding, the identification of the above aging effects by the Structures Monitoring Program, as well as the resistance provided by the materials of construction provide adequate assurance that all types of concrete aging effects will be identified and managed through out the extended period of operation.
Page 3-112 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (1) AIR OPERATED Cast Iron Air and Gas Loss of Material One-Time Material and environment grouping are not DAMPER HOUSING (Wetted) <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(2) AIR OPERATED Cast Iron Containment Loss of Material Systems Material and environment grouping are not DAMPER HOUSING Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(3) AIR OPERATED Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to DAMPER HOUSING Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140'F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(4) AIR OPERATED Galvanized Containment No Aging Effects No Aging Not consistent with NUREG-1 801. According to DAMPER HOUSING Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-113 Application for Renewed Operating License
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Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (5) AIR OPERATED Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to DAMPER HOUSING Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140°F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(6) AIR OPERATED Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1801. According to DAMPER HOUSING Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(7) BELL' Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(8) BLOWER Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1 801. According to CASING Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-114 Application for Renewed Operating License
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Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (9) BLOWER Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1801. According to CASING Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, stainless steel exposed to ventilation air (T<1400F) would not be expected to exhibit loss of material due to pitting and crevice corrosion.
Therefore no aging effects are applicable and no aging management program is required.
(10) COMPRESSOR Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not CASING (included for Steel Management included in NUREG-1801.
conservatism)
Program Required (11)
CONDENSER Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (12) CONDENSER Stainless Steel Treated Water Cracking due to Periodic Structure/component type, material and Borated >140 SCC Surveillance and environment grouping are not included in Preventive NUREG-1801. The aging management program(s)
Maintenance referenced are appropriate for the aging effects Program identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(13) CONDENSER Stainless Steel Treated Water Cracking due to Water Chemistry Structure/component type, material and Borated >140 SCC Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(14) CONDENSER Stainless Steel Treated Water Loss of Material Periodic Structure/component type, material and Borated >140 Surveillance and environment grouping are not included in Preventive NUREG-1801. The aging management program(s)
Maintenance referenced are appropriate for the aging effects Program identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-115 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (15) CONDENSER Stainless Steel Treated Water Loss of Material Water Chemistry Structure/component type, material and Borated >140 Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(16) CONDENSER Stainless Steel Treated Water Loss of Material Closed-Cycle Structure/component type, material and Other (Component) environment grouping are not included in Cooling Water NUREG-1801. The aging management program(s)
System Program referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(17) CONTROLLER' Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (18) COOLER Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(19) COOLER Cast Iron Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(20) COOLER Cast Iron Raw Water Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-116 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (21) COOLER Cast Iron Treated Water Loss of Material Periodic Material and environment grouping are not Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(22) COOLER Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (23) COOLER Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(24) COOLER Copper Alloy (Zn Raw Water Loss of Material Periodic Material and environment grouping are not
> 15%)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(25) COOLER Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
> 15%)
Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(26) COOLER Stainless Steel Concrete No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (27) COOLER Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required Page 3-117 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (28) COOLER Stainless Steel Treated Water Cracking due to Periodic Structure/component type, material and Borated >140 SCC Surveillance and environment grouping are not included in Preventive NUREG-1801. The aging management program(s)
Maintenance referenced are appropriate for the aging effects Program identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(29) COOLER Stainless Steel Treated Water Cracking due to Water Chemistry Structure/component type, material and Borated >140 SCC Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(30) COOLER Stainless Steel Treated Water Loss of Material Periodic Structure/component type, material and Borated >140 Surveillance and environment grouping are not included in Preventive NUREG-1801. The aging management program(s)
Maintenance referenced are appropriate for the aging effects Program identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(31) COOLER Stainless Steel Treated Water Loss of Material Water Chemistry Structure/component type, material and Borated >140 Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(32) COOLER Stainless Steel Treated Water Loss of Material Closed-Cycle Structure/component type, material and Other (Component) environment grouping are not included in Cooling Water NUREG-1801. The aging management program(s)
System Program referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-118 Application for Renewed Operating License
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Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (33) COOLING COIL Carbon/Low Alloy Air and Gas Loss of Material Periodic Material and environment grouping are not Steel (Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(34) COOLING COIL Copper Alloy (Zn Air and Gas Loss of Material One-Time Material and environment grouping are not
< 15%)
(Wetted) <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(35) COOLING COIL Copper Alloy (Zn Air and Gas Loss of Material Periodic Material and environment grouping are not
< 15%)
(Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(36) COOLING COIL Copper Alloy (Zn Containment No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (37) COOLING COIL Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (38) COOLING COIL Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1 801. According to Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-119 Application for Renewed Operating License
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Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (39) COOLING COIL Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1801. According to Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(40) COOLING COIL Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (41) COOLING COIL Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (42) COOLING COIL Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (43) CUTTER Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not ASSEMBLY Management included in NUREG-1801.
Program Required (44) CUTTER Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ASSEMBLY Conditioning)
Management included in NUREG-1801.
Program Required (45) DAMPER Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not HOUSING/FRAME (Wetted) <140 Management included in NUREG-1801.
Program Required (46) DAMPER Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HOUSING/FRAME Conditioning)
Management included in NUREG-1801.
Program Required Page 3-120 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (47) DAMPER Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to HOUSING/FRAME Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140°F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(48) DAMPER Galvanized Containment No Aging Effects No Aging Not consistent with NUREG-1801. According to HOUSING/FRAME Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(49) DAMPER Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING/FRAME Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(50) DAMPER Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING/FRAME Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-121 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (51) DAMPER Galvanized Outdoor No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING/FRAME Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140°F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(52) DEMINERALIZER Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (53) DEMINERALIZER Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(54) DEMINERALIZER Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(55) DIAPHRAGM Neoprene Air and Gas No Aging Effects No Aging Material and environment grouping are not SEAL Management included in NUREG-1801.
Program Required (56) DIAPHRAGM Neoprene Treated Water Change in Periodic Material and environment grouping are not SEAL Borated <140 Material Surveillance and included in NUREG-1801. The aging management Properties and Preventive program(s) referenced are appropriate for the Cracking Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-122 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (57) ENGINE Carbon/Low Alloy Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not CASING Steel Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(58) ENGINE Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not CASING Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(59) EXPANSION Flexible Asbestos Air and Gas No Aging Effects No Aging Material and environment grouping are not JOINT Cloth (Wetted) <140 Management included in NUREG-1801.
Program Required (60) EXPANSION Flexible Asbestos Containment No Aging Effects No Aging Material and environment grouping are not JOINT Cloth Management included in NUREG-1801.
Program Required (61) EXPANSION Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1 801. According to JOINT Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140'F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(62) EXPANSION Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1 801. According to JOINT Carbon Steel (Wetted) >140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-123 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (63) EXPANSION Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to JOINT Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(64) EXPANSION Neoprene Indoor (Air No Aging Effects No Aging Material and environment grouping are not JOINT Conditioning)
Management included in NUREG-1801.
Program Required (65) EXPANSION Neoprene Raw Water No Aging Effects No Aging Material and environment grouping are not JOINT Management included in NUREG-1801.
Program Required (66) EXPANSION Rubber Coated Air and Gas Change in Periodic Material and environment grouping are not JOINT Asbestos (Wetted) <140 Material Surveillance and included in NUREG-1801. The aging management Properties and Preventive program(s) referenced are appropriate for the Cracking Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(67) EXPANSION Rubber Coated Containment Change in Periodic Material and environment grouping are not JOINT Asbestos Material Surveillance and included in NUREG-1801. The aging management Properties and Preventive program(s) referenced are appropriate for the Cracking Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(68) EXPANSION Stainless Steel Air and Gas Cracking due to One-Time Material and environment grouping are not JOINT (Wetted) >140 SCC Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-124 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (69) EXPANSION Stainless Steel Air and Gas Loss of Material One-Time Material and environment grouping are not JOINT (Wetted) >140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(70) EXPANSION Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not JOINT Conditioning)
Management included in NUREG-1801.
Program Required (71) FAN CASING Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1 801.
Program Required (72) FAN CASING Aluminum Indoor (Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (73) FAN CASING Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (74) FAN CASING Aluminum Outdoor Loss of Material Systems Material and environment grouping are not Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(75) FAN CASING Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not Steel Conditioning)
Management included in NUREG-1801.
Program Required (76) FAN CASING Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-125 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (77) FAN CASING Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(78) FAN CASING Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1801. According to Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140°F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(79) FASTENERS Carbon/Low Alloy Indoor (No Air Cracking due to Bolting Integrity There are no bolts with a specified minimum yield (BOLTING)
Steel Conditioning)
SCC Program strength > 150 ksi in this system. Therefore, SCC is not an applicable aging effect/mechanism.
(80) FASTENERS Carbon/Low Alloy Indoor (No Air Loss of Preload Bolting Integrity Material and environment grouping are included in (BOLTING)
Steel Conditioning) due to Stress Program NUREG-1801. Aging effect of loss of preload due Relaxation to stress relaxation is applicable, but is not included in Chapter V - Section E, Chapter VII Section I, or Chapter VIII - Section H of the NUREG.
(81) FASTENERS Stainless Steel Borated Water No Aging Effects No Aging Material and environment grouping are not (BOLTING)
Leaks Management included in NUREG-1801.
Program Required (82) FILTER Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not HOUSING Management included in NUREG-1801.
Program Required (83) FILTER Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HOUSING Conditioning)
Management included in NUREG-1801.
I Program Required Page 3-126 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (84) FILTER Aluminum Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not HOUSING Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(85) FILTER Aluminum Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not HOUSING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(86) FILTER Aluminum Treated Water Loss of Material Periodic Material and environment grouping are not HOUSING Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(87) FILTER Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not HOUSING Steel Conditioning)
Management included in NUREG-1801.
Program Required (88) FILTER Carbon/Low Alloy Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not HOUSING Steel Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(89) FILTER Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not HOUSING Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-127 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (90) FILTER Cast Iron Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not HOUSING Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(91) FILTER Cast Iron Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not HOUSING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(92) FILTER Fiberglass Air and Gas No Aging Effects No Aging Material and environment grouping are not HOUSING Reinforced Plastic (Wetted) <140 Management included in NUREG-1801.
(FRP)
Program Required (93) FILTER Fiberglass Containment No Aging Effects No Aging Material and environment grouping are not HOUSING Reinforced Plastic Management included in NUREG-1801.
(FRP)
Program Required (94) FILTER Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(95) FILTER Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-128 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (96) FILTER Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to HOUSING Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(97) FILTER Stainless Steel Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to HOUSING (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, stainless steel exposed to ventilation air (T<1400F) would not be expected to exhibit loss of material due to pitting and crevice corrosion.
Therefore no aging effects are applicable and no aging management program is required.
(98) FILTER Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not HOUSING Management included in NUREG-1801.
Program Required (99) FILTER Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HOUSING Conditioning)
Management included in NUREG-1801.
Program Required (100) FILTER Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not HOUSING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-129 Application for Renewed Operating License
K Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (101) FILTER Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not HOUSING Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(102) FILTER Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not HOUSING Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(103) FLAME Aluminum Containment No Aging Effects No Aging Material and environment grouping are not ARRESTOR Management included in NUREG-1801.
Program Required (104) FLAME Aluminum Oil and Fuel Oil Loss of Material One-Time Material and environment grouping are not ARRESTOR Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(105) FLANGE Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not Steel Management included in NUREG-1801.
Program Required (106) FLOW Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not ELEMENT (Wetted) <140 Management included in NUREG-1801.
Program Required (107) FLOW Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not ELEMENT Management included in NUREG-1801.
Program Required Page 3-130 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (108) FLOW Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT Conditioning)
Management included in NUREG-1801.
Program Required (109) FLOW Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not ELEMENT Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(110) FLOW Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not ELEMENT Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(111) FLOW Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not ELEMENT Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(112) FLOW Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not METER 1 Management included in NUREG-1801.
Program Required (113) FLOW Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not METER1 Conditioning)
Management included in NUREG-1801.
Program Required (114) FLOW Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not NOZZLES
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required Page 3-131 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (115) GAS Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not CYLINDER Steel Management included in NUREG-1801.
Program Required (116) HAND Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not CONTROL STATION Steel Management included in NUREG-1801.
Program Required (117) HAND Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not CONTROL STATION Steel Conditioning)
Management included in NUREG-1801.
Program Required (118) HAND Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not CONTROL STATION
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (119) HEAT Carbon/Low Alloy Raw Water Loss of Material One-Time Material and environment grouping are not EXCHANGER Steel Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(120) HEAT Carbon/Low Alloy Raw Water Loss of Material Periodic Structure/component type, material, and EXCHANGER Steel Surveillance and environment grouping are not included in Preventive NUREG-1801. The aging management program(s)
Maintenance referenced are appropriate for the aging effects Program identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(121) HEAT Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not EXCHANGER Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-132 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems-Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (122) HEAT Cast Iron Raw Water Loss of Material Periodic Material and environment grouping are not EXCHANGER Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(123) HEAT Cast Iron Treated Water Loss of Material Periodic Material and environment grouping are not EXCHANGER Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(124) HEAT Copper Alloy (Zn Raw Water Loss of Material Open-Cycle Material and environment grouping are not EXCHANGER
< 15%)
Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(125) HEAT Copper Alloy (Zn Raw Water Loss of Material Periodic Material and environment grouping are not EXCHANGER
< 15%)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(126) HEAT Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not EXCHANGER
< 15%)
Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-133 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (127) HEAT Copper Alloy (Zn Air and Gas Loss of Heat Periodic Material and environment grouping are not EXCHANGER
> 15%)
(Wetted) >140 Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(128) HEAT Copper Alloy (Zn Air and Gas Loss of Material One-Time Material and environment grouping are not EXCHANGER
> 15%)
(Wetted) >140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(129) HEAT Copper Alloy (Zn Raw Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER
>15%)
Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(130) HEAT Copper Alloy (Zn Raw Water Loss of Material Periodic Material and environment grouping are not EXCHANGER
> 15%)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(131) HEAT Copper Alloy (Zn Treated Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER
> 15%)
Other Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-134 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (132) HEAT Copper Alloy (Zn Treated Water Loss of Material Closed-Cycle Material and environment grouping are not EXCHANGER
> 15%)
Other (Component) included in NUREG-1 801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(133) HEAT Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not EXCHANGER
>15%)
Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(134) HEAT HX-Copper Alloy Raw Water Loss of Heat Open-Cycle Material and environment grouping are not EXCHANGER (Zn < 15%)2 Transfer Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(135) HEAT HX-Copper Alloy Raw Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER (Zn < 15%)2 Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(136) HEAT HX-Copper Alloy Treated Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER (Zn < 15%)2 Other Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-135 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (1137) HEAT HX-Copper Alloy Treated Water Loss of Heat Closed-Cycle Material and environment grouping are not EXCHANGER (Zn > 15%)2 Other Transfer (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(138) HEAT HX-Copper Alloy Treated Water Loss of Heat Open-Cycle Material and environment grouping are not EXCHANGER (Zn > 15%)2 Other Transfer Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(139) HEAT HX-Stainless Raw Water Loss of Heat Periodic Material and environment grouping are not EXCHANGER Steel Transfer Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(140) HEAT HX-SIainless Treated Water Loss of Heat Closed-Cycle Structure/component type, material and EXCHANGER Steel Other Transfer (Component) environment grouping are not included in Cooling Water NUREG-1801. The aging management program(s)
System Program referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(141) HEAT HX-Stainless Treated Water Loss of Heat Water Chemistry Structure/component type, material and EXCHANGER Steel2 Primary <140 Transfer Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-136 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (142) HEAT HX-Stainless Treated Water Loss of Heat Water Chemistry Structure/component type, material and EXCHANGER Steel2 Secondary >120 Transfer Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(143) HEAT Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not EXCHANGER (Wetted) <140 Management included in NUREG-1801.
Program Required (144) HEAT Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not EXCHANGER Conditioning)
Management included in NUREG-1801.
Program Required (145) HEAT Stainless Steel Raw Water Loss of Heat Open-Cycle Structure/component type, material and EXCHANGER Transfer Cooling (Service) environment grouping are not included in Water System NUREG-1801. The aging management program(s)
Program referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(146) HEAT Stainless Steel Raw Water Loss of Material Periodic Material and environment grouping are not EXCHANGER Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(147) HEAT Stainless Steel Treated Water Loss of Heat Water Chemistry Material and environment grouping are not EXCHANGER Borated <140 Transfer Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-137 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (148) HEAT Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not EXCHANGER Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(149) HEAT Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not EXCHANGER Borated <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(150) HEAT Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not EXCHANGER Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(151) HEAT Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not EXCHANGER Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(152) HEAT Stainless Steel Treated Water Loss of Material Water Chemistry Structure/component type, material and EXCHANGER Primary <140 Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-138 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (153) HEAT Stainless Steel Treated Water Cracking due to Water Chemistry Structure/component type, material and EXCHANGER Secondary >120 SCC Control Program environment grouping are not included in NUREG-1 801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(154) HEAT Stainless Steel Treated Water Loss of Material Water Chemistry Structure/component type, material and EXCHANGER Secondary >120 Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(155) HEATER Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (156) HEATER Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Secondary >120 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(157) HEATING Carbon/Low Alloy Air and Gas Loss of Material Periodic Material and environment grouping are not COIL Steel (Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(158) HEATING Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not COIL Steel Conditioning)
Management included in NUREG-1801.
Program Required Page 3-139 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (159) HEATING Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT Conditioning)
Management included in NUREG-1801.
Program Required (160) HEATING Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not ELEMENT Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(161) HEATING Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not ELEMENT Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(162) HVAC Carbon/Low Alloy Air and Gas Loss of Material One-Time Material and environment grouping are not EQUIPMENT Steel (Wetted) <140 Inspection included in NUREG-1801. The aging management PACKAGE 3 Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(163) HVAC Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to EQUIPMENT Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance PACKAGE 3 Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-140 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (164) HVAC Galvanized Containment No Aging Effects No Aging Not consistent with NUREG-1 801. According to EQUIPMENT Carbon Steel Management site-specific review of standard industry guidance PACKAGE 3 Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(165) HVAC Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1801. According to EQUIPMENT Carbon Steel Conditioning)
Management site-specific review of standard industry guidance PACKAGE 3 Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(166) HVAC Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1801. According to EQUIPMENT Carbon Steel Conditioning)
Management site-specific review of standard industry guidance PACKAGE 3 Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400 F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(167) INDICATOR 1 Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (168) INDICATOR 1 Copper Alloy (Zn Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not
< 15%)
Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-141 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (169) INDICATOR 1 Copper Alloy (Zn Raw Water Loss of Material Open-Cycle Material and environment grouping are not
< 15%)
Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(170) INDICATOR 1 Copper Alloy (Zn Treated Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(171) INDICATOR 1 Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(172) INDICATOR 1 Plastic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (173) INDICATOR 1 Plastic Oil and Fuel Oil No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (174) INDICATOR 1 Plastic Raw Water No Aging Effects No Aging Material and environment grouping are not (Stagnant)
Management included in NUREG-1801.
Program Required (175) INDICATOR 1 Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (176) INDICATOR' Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required Page 3-142 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (177) INDICATOR 1 Stainless Steel Treated Water Loss of Material One-Time Structure/component type, material and Borated <140 Inspection environment grouping are not included in Program NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation. One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(178) INDICATOR' Stainless Steel Treated Water Loss of Material Water Chemistry Structure/component type, material and Borated <140 Control Program environment grouping are not included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(179) INDICATOR' Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(180) LEVEL GLASS Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (181) LEVEL GLASS Copper Alloy (Zn Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not
< 15%)
Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-143 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (182) LEVEL GLASS Copper Alloy (Zn Oil and Fuel Oil Loss of Material Periodic Consistent with NUREG-1 801.
< 15%)
Surveillance and Material/environment grouping and aging effect Preventive are included in NUREG-1801. The Periodic Maintenance Surveillance and Preventive Maintenance Program Program will be used to verify the effectiveness of the Fuel Oil Chemistry Program.
(183) LEVEL GLASS Copper Alloy (Zn Treated Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(184) LEVEL GLASS Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(185) LEVEL GLASS Glass Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (186) LEVEL GLASS Glass Oil and Fuel Oil No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (187) LEVEL GLASS Plastic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (188) LEVEL GLASS Plastic Treated Water No Aging Effects No Aging Material and environment grouping are not Other Management included in NUREG-1801.
Program Required (189) LEVEL GLASS Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required Page 3-144 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (190) LEVEL GLASS Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(191) MOTOR Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to OPERATED Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance DAMPER Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(192) MOTOR Galvanized Outdoor No Aging Effects No Aging Not consistent with NUREG-1 801. According to OPERATED Carbon Steel Management site-specific review of standard industry guidance DAMPER Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(193) MUFFLER Galvanized Air and Gas No Aging Effects No Aging Material and environment grouping are not Carbon Steel (Wetted) >140 Management included in NUREG-1801.
Program Required (194) MUFFLER Galvanized Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Carbon Steel Conditioning)
Management included in NUREG-1801.
Program Required (195) ORIFICE Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
<15%)
Conditioning)
Management included in NUREG-1801.
Program Required (196) ORIFICE Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required Page 3-145 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (197) ORIFICE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (198) ORIFICE Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(199) ORIFICE Stainless Steel Raw Water Loss of Material One-Time Material and environment grouping are not Drainage Inspection included in NUREG-1801.
Program (200) ORIFICE Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(201) PENETRATION Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not SEAL Steel Conditioning)
Management included in NUREG-1801.
Program Required (202) PENETRATION Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not SEAL Steel Management included in NUREG-1801.
Program Required (203) PIPE Carbon/Low Alloy Indoor (Air No Aging Effects No Aging Material and environment grouping are not Steel Conditioning)
Management included in NUREG-1801.
Program Required (204) PIPE Carbon/Low Alloy Treated Water Loss of Material One-Time Material and environment grouping are not Steel Other (Stagnant)
Inspection included in NUREG-1801. One-time inspections Program are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-146 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (205) PIPE Carbon/Low Alloy Treated Water Loss of Material Water Chemistry Material and environment grouping are not Steel Other (Stagnant)
Control Program included in NUREG-1801.
(206) PIPE Carbon/Low Alloy Treated Water Loss of Material Periodic Material and environment grouping are not Steel Secondary >120 Surveillance and included in NUREG-1801.
Preventive Maintenance Program (207) PIPE Cast Iron Buried Loss of Material Fire Water Not consistent with NUREG-1 801. The Fire Water System Program System Program is credited for managing the effects of aging for buried cast iron piping and fittings. External surfaces of buried piping are visually examined during maintenance activities (inspections of opportunity) performed as a result of performance tests. No evidence of age-related degradation has been detected from inspections performed to date. Cast iron fire system and service water piping at Ginna Station is ductile cast iron, not gray cast iron. Ductile irons are not susceptible to loss of structural integrity due to selective leaching mechanisms, and generally display excellent resistance to general corrosion due to exposure to non-aggressive ground water.
Ground water/lake water at Ginna Station is analyzed periodically and analyses performed to date confirm that the water is non-aggressive.
(208) PIPE Cast Iron Concrete No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (209) PIPE Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-147 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (210) PIPE Concrete Buried No Aging Effects No Aging Material and environment grouping are not (Reinforced)
Management included in NUREG-1801.
Program Required (211) PIPE Concrete Raw Water Loss of Material Periodic Material and environment grouping are not (Reinforced)
Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(212) PIPE Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (213) PIPE Copper Alloy (Zn Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not
< 15%)
Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(214) PIPE Copper Alloy (Zn Raw Water Loss of Material Fire Water Material and environment grouping are not
< 15%)
(Stagnant)
System Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(215) PIPE Copper Alloy (Zn Raw Water Loss of Material Periodic Consistent with NUREG-1 801.
< 15%)
(Stagnant)
Surveillance and Material/environment grouping and aging effect Preventive are included in NUREG-1801. The Periodic Maintenance Surveillance and Preventive Maintenance Program Program will be used to verify the effectiveness of the Fire Water System Program.
Page 3-148 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (216) PIPE Copper Alloy (Zn Raw Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(217) PIPE Copper Alloy (Zn Treated Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(218) PIPE Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(219) PIPE Neoprene Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (220) PIPE Neoprene Containment Change in One-Time Material and environment grouping are not Material Inspection included in NUREG-1801. The aging management Properties and Program program(s) referenced are appropriate for the Cracking aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(221) PIPE Neoprene Containment Change in Periodic Material and environment grouping are not Material Surveillance and included in NUREG-1801. The aging management Properties and Preventive program(s) referenced are appropriate for the Cracking Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-149 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (222) PIPE Neoprene Containment Change in Systems Material and environment grouping are not Material Monitoring included in NUREG-1801. The aging management Properties and Program program(s) referenced are appropriate for the Cracking aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(223) PIPE Neoprene Indoor (No Air Change in Periodic Material and environment grouping are not Conditioning)
Material Surveillance and included in NUREG-1801. The aging management Properties and Preventive program(s) referenced are appropriate for the Cracking Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(224) PIPE Neoprene Indoor (No Air Change in Systems Material and environment grouping are not Conditioning)
Material Monitoring included in NUREG-1801. The aging management Properties and Program program(s) referenced are appropriate for the Cracking aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(225) PIPE Neoprene Oil and Fuel Oil No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (226) PIPE Neoprene Raw Water No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (227) PIPE Neoprene Raw Water No Aging Effects No Aging Material and environment grouping are not (Stagnant)
Management included in NUREG-1801.
Program Required (228) PIPE Neoprene Treated Water No Aging Effects No Aging Material and environment grouping are not Other Management included in NUREG-1801.
Program Required (229) PIPE Plastic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required Page 3-150 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (230) PIPE Plastic Raw Water No Aging Effects No Aging Material and environment grouping are not Drainage Management included in NUREG-1801.
Program Required (231) PIPE Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (232) PIPE Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (233) PIPE Stainless Steel Buried No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (234) PIPE Stainless Steel Concrete No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (235) PIPE Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (236) PIPE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (237) PIPE Stainless Steel Raw Water Loss of Material One-Time Material and environment grouping are not Drainage Inspection included in NUREG-1801.
Program Page 3-151 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (238) PIPE Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(239) PIPE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(240) PIPE Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not Borated >140 SCC Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(241) PIPE Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(242) PIPE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-152 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (243) PIPE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(244) PIPE Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(245) PIPE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Primary <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(246) PIPE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Primary <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(247) PIPE Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not
- Primary, SCC Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-153 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (248) PIPE Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not
- Primary, SCC Control Program included in NUREG-1 801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(249) PIPE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not
- Primary, Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(250) PIPE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not
- Primary, Control Program included in NUREG-1 801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(251) PROTOMATIC Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1 801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(252) PULSATION Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not DAMPER Conditioning)
Management included in NUREG-1801.
Program Required Page 3-154 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (253) PULSATION Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not DAMPER Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(254) PULSATION Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not DAMPER Borated <140 Control Program included in NUREG-1801.The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(255) PUMP Aluminum Indoor (Air No Aging Effects No Aging Material and environment grouping are not CASING Conditioning)
Management included in NUREG-1801.
Program Required (256) PUMP Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not CASING Conditioning)
Management included in NUREG-1801.
Program Required (257) PUMP Aluminum Raw Water Loss of Material One-Time Material and environment grouping are not CASING Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(258) PUMP Aluminum Raw Water Loss of Material Periodic Material and environment grouping are not CASING Drainage Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-155 Application for Renewed Operating License C
f
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (259) PUMP Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not CASING Steel Management included in NUREG-1801.
Program Required (260) PUMP Cast Iron Air and Gas Loss of Material One-Time Material and environment grouping are not CASING (Wetted) >140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(261) PUMP Cast Iron Indoor (Air No Aging Effects No Aging Material and environment grouping are not CASING Conditioning)
Management included in NUREG-1801. The aging management Program Required program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(262) PUMP Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not CASING Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(263) PUMP Cast Iron Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not CASING Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(264) PUMP Cast Iron Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not CASING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-156 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (265) PUMP Cast Iron Raw Water Loss of Material One-Time Material and environment grouping are not CASING Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(266) PUMP Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not CASING
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (267) PUMP Copper Alloy (Zn Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not CASING
< 15%)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(268) PUMP Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not CASING (Wetted) <140 Management included in NUREG-1801.
Program Required (269) PUMP Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not CASING Management included in NUREG-1801.
Program Required (270) PUMP Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not CASING Conditioning)
Management included in NUREG-1801.
Program Required (271) PUMP Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not CASING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-157 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (272) PUMP Stainless Steel Raw Water Loss of Material One-Time Material and environment grouping are not CASING Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(273) PUMP Stainless Steel Raw Water Loss of Material Periodic Material and environment grouping are not CASING Drainage Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(274) PUMP Stainless Steel Treated Water Loss of Material One-Time Consistent with NUREG-1801. Although the CASING Borated <140 Inspection NUREG references a temperature gate of < 900C Program (2000F) and a single aging effect (cracking due to SCC), materials science supports (1) a temperature gate > 140OF for cracking due to SCC, and (2) loss of material due to pitting (stagnant or low flow conditions) and crevice corrosion for all temperatures. The aging effect identified by Ginna (loss of material) for temperatures < 140OF differs from that of the NUREG. That not withstanding, the Water Chemistry Control Program, credited for managing the aging effects for all temperatures, is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-158 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (275) PUMP Stainless Steel Treated Water Loss of Material Water Chemistry Consistent with NUREG-1 801. Although the CASING Borated <140 Control Program NUREG references a temperature gate of < 90'C (2000F) and a single aging effect (cracking due to SCC), materials science supports (1) a temperature gate > 140°F for cracking due to SCC, and (2) loss of material due to pitting (stagnant or low flow conditions) and crevice corrosion for all temperatures. The aging effect identified by Ginna (loss of material) for temperatures < 140'F differs from that of the NUREG. That not withstanding, the Water Chemistry Control Program, credited for managing the aging effects for all temperatures, is consistent with the NUREG and will preclude the possibility of crack initiation and growth due to SCC. A One-Time Inspection Program is also credited to verify the adequacy of the Chemistry program.
(276) RADIATION Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not DETECTOR Management included in NUREG-1801.
Program Required (277) RADIATION Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not DETECTOR (Wetted) <140 Management included in NUREG-1801.
Program Required (278) RADIATION Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not DETECTOR Conditioning)
Management included in NUREG-1801.
Program Required (279) RADIATION Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not DETECTOR (Wetted) <140 Management included in NUREG-1801.
Program Required (280) RADIATION Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not DETECTOR Conditioning)
Management included in NUREG-1801.
I Program Required Page 3-159 Application for Renewed Operating License
C Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (281) RADIATION Stainless Steel Raw Water Loss of Material Periodic Material and environment grouping are not DETECTOR Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(282) RADIATION Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not MONITOR SKID Management included in NUREG-1801.
Program Required (283) RADIATION Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not MONITOR SKID (Wetted) <140 Management included in NUREG-1801.
Program Required (284) RADIATION Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not MONITOR SKID Conditioning)
Management included in NUREG-1801.
Program Required (285) RELEASE Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not ASSEMBLY Management included in NUREG-1801.
Program Required (286) RELEASE Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ASSEMBLY Conditioning)
Management included in NUREG-1801.
Program Required (287) RELEASE Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not ASSEMBLY Steel Management included in NUREG-1801.
Program Required (288) RELEASE Copper Alloy (Zn Air and Gas No Aging Effects No Aging Material and environment grouping are not ASSEMBLY
<15%)
Management included in NUREG-1801.
Program Required (289) RELEASE Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ASSEMBLY
<15%)
Conditioning)
Management included in NUREG-1801.
Program Required Page 3-160 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (290) SCREEN Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(291) SPECIAL Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not ELEMENT Management included in NUREG-1801.
Program Required (292) SPECIAL Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT Conditioning)
Management included in NUREG-1801.
Program Required (293) SPECTACLE Carbon/Low Alloy Air and Gas Loss of Material Periodic Material and environment grouping are not FLANGE Steel (Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(294) SPECTACLE Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not FLANGE
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (295) SPECTACLE Stainless Steel Buried No Aging Effects No Aging Material and environment grouping are not FLANGE Management included in NUREG-1801.
Program Required (296) SPECTACLE Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not FLANGE Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-161 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (297) SPECTACLE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not FLANGE Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(298) SPRINKLER Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HEAD
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (299) STRAINER Carbon/Low Alloy Treated Water Loss of Material Periodic Material and environment grouping are not HOUSING Steel Secondary >120 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(300) STRAINER Cast Iron Containment Loss of Material Periodic Material and environment grouping are not HOUSING Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(301) STRAINER Cast Iron Containment Loss of Material Systems Material and environment grouping are not HOUSING Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(302) STRAINER Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not HOUSING Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-162 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (303) STRAINER Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HOUSING
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (304) STRAINER Copper Alloy (Zn Raw Water Loss of Material Open-Cycle Material and environment grouping are not HOUSING
< 15%)
(Stagnant)
Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(305) STRAINER Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not HOUSING Conditioning)
Management included in NUREG-1801.
Program Required (306) STRAINER Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not HOUSING Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(307) STRAINER Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not HOUSING Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(308) STRUCTURE Aluminum Indoor (No Air No Aging Effects Fire Protection Material and environment grouping are not Conditioning)
Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-163 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (309) STRUCTURE Concrete Air and Gas No Aging Effects No Aging Material and environment grouping are not (Reinforced)
(Wetted) <140 Management included in NUREG-1801.
Program Required (310) STRUCTURE Concrete Outdoor No Aging Effects Periodic Material and environment grouping are not (Reinforced)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(311) STRUCTURE Fire Stop Indoor (No Air Cracking/Delamin Fire Protection Material and environment grouping are not Materials Conditioning) ation due to Program included in NUREG-1801. The aging management Movement program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(312) STRUCTURE Fire Stop Indoor (No Air Cracking/Delamin Fire Protection Material and environment grouping are not Materials Conditioning) ation due to Program included in NUREG-1801. The aging management Shrinkage program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(313) STRUCTURE Fire Stop Indoor (No Air Cracking/Delamin Fire Protection Material and environment grouping are not Materials Conditioning) ation due to Program included in NUREG-1801. The aging management Vibration program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(314) STRUCTURE Fire Stop Indoor (No Air Hardening and Fire Protection Material and environment grouping are not Materials Conditioning)
Shrinkage due to Program included in NUREG-1801. The aging management Weathering program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-164 Application for Renewed Operating License f
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (315) STRUCTURE Fire Stop Indoor (No Air Loss of Material Fire Protection Material and environment grouping are not Materials Conditioning)
Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(316) STRUCTURE Fire Stop Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Materials Conditioning)
Movement Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(317) STRUCTURE Fire Stop Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Materials Conditioning)
Shrinkage Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(318) STRUCTURE Fire Stop Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Materials Conditioning)
Vibration Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(319) STRUCTURE Fire Wrap Indoor (No Air Cracking/
Fire Protection Material and environment grouping are not Materials Conditioning)
Delamination due Program included in NUREG-1801. The aging management to Movement program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-165 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (320) STRUCTURE Fire Wrap Indoor (No Air Cracking/
Fire Protection Material and environment grouping are not Materials Conditioning)
Delamination due Program included in NUREG-1801. The aging management to Vibration program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(321) STRUCTURE Fire Wrap Indoor (No Air Loss of Material Fire Protection Material and environment grouping are not Materials Conditioning)
Program included in NUREG-1 801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(322) STRUCTURE Grout Indoor (No Air Cracking/
Fire Protection Material and environment grouping are not Conditioning)
Delamination due Program included in NUREG-1801. The aging management to Movement program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(323) STRUCTURE Grout Indoor (No Air Cracking/
Fire Protection Material and environment grouping are not Conditioning)
Delamination due Program included in NUREG-1801. The aging management to Shrinkage program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(324) STRUCTURE Grout Indoor (No Air Cracking/
Fire Protection Material and environment grouping are not Conditioning)
Delamination due Program included in NUREG-1801. The aging management to Vibration program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-166 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (325) STRUCTURE Grout Indoor (No Air Hardening and Fire Protection Material and environment grouping are not Conditioning)
Shrinkage due to Program included in NUREG-1801. The aging management Weathering program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(326) STRUCTURE Grout Indoor (No Air Loss of Material Fire Protection Material and environment grouping are not Conditioning)
Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(327) STRUCTURE Grout Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Conditioning)
Movement Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(328) STRUCTURE Grout Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Conditioning)
Shrinkage Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(329) STRUCTURE Grout Indoor (No Air Separation due to Fire Protection Material and environment grouping are not Conditioning)
Vibration Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-167 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (330) STRUCTURE Structural Steel -
Indoor (No Air No Aging Effects Fire Protection Material and environment grouping are not Stainless Conditioning)
Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(331) SWITCH1 Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (332) SWITCH1 Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (333) SWITCH' Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(334) TANK Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not Steel Management included in NUREG-1801.
Program Required (335) TANK Carbon/Low Alloy Buried Loss of Material One-Time Material and environment grouping are not Steel Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-168 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (336) TANK Carbon/Low Alloy Treated Water Loss of Material One-Time Material and environment grouping are not Steel Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(337) TANK Carbon/Low Alloy Treated Water Loss of Material Periodic Material and environment grouping are not Steel Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(338) TANK Carbon/Low Alloy Treated Water Loss of Material Water Chemistry Material and environment grouping are not Steel Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(339) TANK Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(340) TANK Copper Alloy (Zn Air and Gas Loss of Material Periodic Material and environment grouping are not
< 15%)
(Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-169 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (341) TANK Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (342) TANK Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (343) TANK Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (344) TANK Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(345) TANK Stainless Steel Raw Water Loss of Material One-Time Material and environment grouping are not Drainage Inspection included in NUREG-1801.The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(346) TANK Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-170 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (347) TANK Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(348) TANK Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not Borated >140 SCC Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(349) TANK Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(350) TANK Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(351) TANK Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-171 Application for Renewed Operating License
(
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (352) TANK Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(353) TEMPERATURE Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not ELEMENT1 Management included in NUREG-1801.
Program Required (354) TEMPERATURE Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not ELEMENT1 Conditioning)
Management included in NUREG-1801.
Program Required (355) TEMPERATURE Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not ELEMENT1 Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(356) TEMPERATURE Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not ELEMENT1 Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(357) TEMPERATURE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not ELEMENT1 Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed L_ through the period of extended operation.
Page 3-172 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (358) TEMPERATURE Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not ELEMENT1 Borated >140 SCC Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(359) TEMPERATURE Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not ELEMENT 1 Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(360) TEMPERATURE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not ELEMENT 1 Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(361) TEMPERATURE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not ELEMENT 1 Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(362) TEMPERATURE Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not ELEMENT 1 Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-173 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (363) TEMPERATURE Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not ELEMENT1 Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(364) TEMPERATURE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not ELEMENT1 Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(365) TEMPERATURE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not ELEMENT1 Primary <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(366) TEMPERATURE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not ELEMENT1 Primary <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(367) TEMPERATURE Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not ELEMENT1
- Primary, SCC Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-174 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (368) TEMPERATURE Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not ELEMENT 1
- Primary, SCC Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(369) TEMPERATURE Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not ELEMENT 1
- Primary, Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(370) TEMPERATURE Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not ELEMENT 1
- Primary, Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(371) TRANSMITTER 1 Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
Program Required (372) TRANSMITTER 1 Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (373) TRANSMITTER' Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
L____
I I
Program Required 1___
Page 3-175 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (374) TRANSMITTER 1 Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(375) TRANSMITTER 1 Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated <140 Control Program included in NUREG-1801.The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(376) TRANSMITTER1 Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not Borated >140 SCC Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(377) TRANSMITTER 1 Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(378) TRANSMITTER 1 Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-176 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (379) TRANSMITFER1 Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(380) TRANSMITTER 1 Stainless Steel Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(381) TRANSMITTER 1 Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Primary <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(382) TRANSMITTER1 Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Primary <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(383) TRAP Carbon/Low Alloy Treated Water Loss of Material Periodic Material and environment grouping are not HOUSING Steel Secondary >120 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(384) VALVE BODY Aluminum Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required Page 3-177 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (385) VALVE BODY Aluminum Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (386) VALVE BODY Carbon/Low Alloy Air and Gas No Aging Effects No Aging Material and environment grouping are not Steel Management included in NUREG-1801.
Program Required (387) VALVE BODY Carbon/Low Alloy Air and Gas Loss of Material One-Time Material and environment grouping are not Steel (Wetted) <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(388) VALVE BODY Carbon/Low Alloy Treated Water Loss of Material One-Time Material and environment grouping are not Steel Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(389) VALVE BODY Carbon/Low Alloy Treated Water Loss of Material Periodic Material and environment grouping are not Steel Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(390) VALVE BODY Carbon/Low Alloy Treated Water Loss of Material Water Chemistry Material and environment grouping are not Steel Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(391) VALVE BODY Cast Austenitic Air and Gas No Aging Effects No Aging Material and environment grouping are not Stainless Steel Management included in NUREG-1801.
Program Required Page 3-178 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (392) VALVE BODY Cast Austenitic Air and Gas No Aging Effects No Aging Material and environment grouping are not Stainless Steel (Wetted) <140 Management included in NUREG-1 801.
Program Required (393) VALVE BODY Cast Austenitic Containment No Aging Effects No Aging Material and environment grouping are not Stainless Steel Management included in NUREG-1801.
Program Required (394) VALVE BODY Cast Austenitic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Stainless Steel Conditioning)
Management included in NUREG-1801.
Program Required (395) VALVE BODY Cast Austenitic Oil and Fuel Oil Loss of Material One-Time Material and environment grouping are not Stainless Steel Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(396) VALVE BODY Cast Austenitic Raw Water Loss of Material Periodic Material and environment grouping are not Stainless Steel Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(397) VALVE BODY Cast Austenitic Raw Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-179 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (398) VALVE BODY Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(399) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(400) VALVE BODY Cast Austenitic Treated Water Cracking due to Periodic Material and environment grouping are not Stainless Steel Borated >140 SCC Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(401) VALVE BODY Cast Austenitic Treated Water Cracking due to Water Chemistry Material and environment grouping are not Stainless Steel Borated >140 SCC Control Program included in NUREG-1 801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(402) VALVE BODY Cast Austenitic Treated Water Loss of Material Periodic Material and environment grouping are not Stainless Steel Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-180 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (403) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(404) VALVE BODY Cast Austenitic Treated Water Loss of Material Closed-Cycle Material and environment grouping are not Stainless Steel Other (Component) included in NUREG-1801.The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(405) VALVE BODY Cast Austenitic Treated Water Loss of Material One-Time Material and environment grouping are not Stainless Steel Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(406) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(407) VALVE BODY Cast Austenitic Treated Water Loss of Material Periodic Material and environment grouping are not Stainless Steel Primary <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-181 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (408) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel Primary <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(409) VALVE BODY Cast Austenitic Treated Water Cracking due to Periodic Material and environment grouping are not Stainless Steel
- Primary, SCC Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(410) VALVE BODY Cast Austenitic Treated Water Cracking due to Water Chemistry Material and environment grouping are not Stainless Steel
- Primary, SCC Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(411) VALVE BODY Cast Austenitic Treated Water Loss of Material Periodic Material and environment grouping are not Stainless Steel
- Primary, Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(412) VALVE BODY Cast Austenitic Treated Water Loss of Material Water Chemistry Material and environment grouping are not Stainless Steel
- Primary, Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-182 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (413) VALVE BODY Cast Iron Air and Gas Loss of Material One-Time Material and environment grouping are not (Wetted) <140 Inspection included in NUREG-1 801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(414) VALVE BODY Cast Iron Air and Gas Loss of Material Periodic Material and environment grouping are not (Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(415) VALVE BODY Cast Iron Buried Loss of Material Fire Water Material and environment grouping are not System Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(416) VALVE BODY Cast Iron Containment Loss of Material Systems Material and environment grouping are not Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(417) VALVE BODY Cast Iron Indoor (No Air Loss of Material Systems Material and environment grouping are not Conditioning)
Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-183 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (418) VALVE BODY Cast Iron Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(419) VALVE BODY Cast Iron Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(420) VALVE BODY Cast Iron Outdoor Loss of Material Systems Material and environment grouping are not Monitoring included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(421) VALVE BODY Cast Iron Raw Water Loss of Material Open-Cycle Material and environment grouping are not Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(422) VALVE BODY Cast Iron Raw Water Loss of Material Open-Cycle Material and environment grouping are not (Stagnant)
Cooling (Service) included in NUREG-1801. The aging management Water System program(s) referenced are appropriate for the Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-184 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (423) VALVE BODY Cast Iron Raw Water Loss of Material Periodic Material and environment grouping are not (Submerged)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(424) VALVE BODY Cast Iron Treated Water Loss of Material Periodic Material and environment grouping are not Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(425) VALVE BODY Copper Alloy (Zn Air and Gas No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (426) VALVE BODY Copper Alloy (Zn Air and Gas Loss of Material One-Time Material and environment grouping are not
< 15%)
(Wetted) <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(427) VALVE BODY Copper Alloy (Zn Air and Gas Loss of Material Periodic Material and environment grouping are not
< 15%)
(Wetted) <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(428) VALVE BODY Copper Alloy (Zn Containment No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (429) VALVE BODY Copper Alloy (Zn Indoor (No Air No Aging Effects No Aging Material and environment grouping are not
< 15%)
Conditioning)
Management included in NUREG-1801.
I Program Required Page 3-185 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (430) VALVE BODY Copper Alloy (Zn Indoor (No Air No Aging Effects Periodic Material and environment grouping are not
< 15%)
Conditioning)
Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(431) VALVE BODY Copper Alloy (Zn Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not
< 15%)
Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(432) VALVE BODY Copper Alloy (Zn Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not
< 15%)
Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(433) VALVE BODY Copper Alloy (Zn Outdoor No Aging Effects No Aging Material and environment grouping are not
< 15%)
Management included in NUREG-1801.
Program Required (434) VALVE BODY Copper Alloy (Zn Raw Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(435) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Borated <140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-186 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (436) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material Closed-Cycle Material and environment grouping are not
< 15%)
Other (Component) included in NUREG-1801. The aging management Cooling Water program(s) referenced are appropriate for the System Program aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(437) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other Surveillance and included in NUREG-1801.The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(438) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material One-Time Material and environment grouping are not
< 15%)
Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(439) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(440) VALVE BODY Copper Alloy (Zn Treated Water Loss of Material Periodic Material and environment grouping are not
< 15%)
Secondary >120 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(441) VALVE BODY Plastic Indoor (Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
I Program Required Page 3-187 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (442) VALVE BODY Plastic Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (443) VALVE BODY Plastic Raw Water No Aging Effects No Aging Material and environment grouping are not Drainage Management included in NUREG-1801.
Program Required (444) VALVE BODY Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (445) VALVE BODY Stainless Steel Air and Gas No Aging Effects No Aging Material and environment grouping are not (Wetted) <140 Management included in NUREG-1801.
Program Required (446) VALVE BODY Stainless Steel Containment No Aging Effects No Aging Material and environment grouping are not Management included in NUREG-1801.
Program Required (447) VALVE BODY Stainless Steel Indoor (No Air No Aging Effects No Aging Material and environment grouping are not Conditioning)
Management included in NUREG-1801.
Program Required (448) VALVE BODY Stainless Steel Oil and Fuel Oil Loss of Material Fuel Oil Material and environment grouping are not Chemistry included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(449) VALVE BODY Stainless Steel Oil and Fuel Oil Loss of Material One-Time Material and environment grouping are not Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Page 3-188 Application for Renewed Operating License
Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (450) VALVE BODY Stainless Steel Oil and Fuel Oil Loss of Material Periodic Material and environment grouping are not Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(451) VALVE BODY Stainless Steel Raw Water Loss of Material One-Time Material and environment grouping are not Drainage Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(452) VALVE BODY Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Borated <140 Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
(453) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(454) VALVE BODY Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not Borated >140 SCC Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-189 Application for Renewed Operating License Table 3.4-2
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (455) VALVE BODY Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not Borated >140 SCC Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(456) VALVE BODY Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Borated >140 Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(457) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Borated >140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(458) VALVE BODY Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Other Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(459) VALVE BODY Stainless Steel Treated Water Loss of Material One-Time Material and environment grouping are not Other (Stagnant)
Inspection included in NUREG-1801. The aging management Program program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
One-time inspections are used to verify the effectiveness of the Water Chemistry Control Program.
Page 3-190 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (460) VALVE BODY Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Other (Stagnant)
Surveillance and included in NUREG-1801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(461) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Other (Stagnant)
Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(462) VALVE BODY Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not Primary <140 Surveillance and included in NUREG-1 801. The aging management Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(463) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not Primary <140 Control Program included in NUREG-1801. The aging management program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(464) VALVE BODY Stainless Steel Treated Water Cracking due to Periodic Material and environment grouping are not
- Primary, SCC Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
Page 3-191 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (465) VALVE BODY Stainless Steel Treated Water Cracking due to Water Chemistry Material and environment grouping are not
- Primary, SCC Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(466) VALVE BODY Stainless Steel Treated Water Loss of Material Periodic Material and environment grouping are not
- Primary, Surveillance and included in NUREG-1801. The aging management 140<T<480 Preventive program(s) referenced are appropriate for the Maintenance aging effects identified and provides assurance Program that the aging effects are effectively managed through the period of extended operation.
(467) VALVE BODY Stainless Steel Treated Water Loss of Material Water Chemistry Material and environment grouping are not
- Primary, Control Program included in NUREG-1801. The aging management 140<T<480 program(s) referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
(468) VENTILATION Galvanized Air and Gas No Aging Effects No Aging Not consistent with NUREG-1801. According to DUCTWORK Carbon Steel (Wetted) <140 Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(469) VENTILATION Galvanized Containment No Aging Effects No Aging Not consistent with NUREG-1 801. According to DUCTWORK Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1401F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
Page 3-192 Application for Renewed Operating License
Table 3.4-2 Auxiliary Systems - Component Types Subject to Aging Management not Evaluated in NUREG-1801 Component Types Material Environment AERMs Program/Activity Discussion (470) VENTILATION Galvanized Indoor (Air No Aging Effects No Aging Not consistent with NUREG-1 801. According to DUCTWORK Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(471) VENTILATION Galvanized Indoor (No Air No Aging Effects No Aging Not consistent with NUREG-1801. According to DUCTWORK Carbon Steel Conditioning)
Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<140°F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
(472) VENTILATION Galvanized Outdoor No Aging Effects No Aging Not consistent with NUREG-1801. According to DUCTWORK Carbon Steel Management site-specific review of standard industry guidance Program Required for aging evaluation of mechanical systems and components, galvanized carbon steel exposed to ventilation air (T<1400F) would be expected to exhibit minimal deterioration of the zinc coating.
Therefore no aging effects are applicable and no aging management program is required.
- 1. Selected instruments were conservatively included within the scope of License Renewal. Consideration was given to the consequences of an instrument housing pressure boundary failure. Where an instrument was unisolable from a pressure source and is of sufficient size that a system function would be degraded should the pressure boundary fail, that instrument is included for License Renewal review.
- 2. Material prefixes with HX are used to identify heat exchanger materials which perform a heat transfer intended function in addition to the typical material usage function of pressure boundary.
- 3. HVAC equipment packages include the pressure boundary attributes associated with the package and sub-components such as filter housings, internal damper housings, and fan housings. Both the HVAC package units and their associated sub-components are uniquely identified on plant drawings.
Page 3-193 Application for Renewed Operating License