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SLR Change - Markup of SRP-SLR Structural Chapter 3.5
	ML20049H361
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Issue date:	02/18/2020
From:	William Burton; NRC/NRR/DNRL/NLRP
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	Burton W, NRR-DNRL 415-6332
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3.5.1 Aging Management of Containments, Structures, and Component Supports Review Responsibilities Primary The branch(es) assigned responsibility by the Project Manager for the safety review of the subsequent license renewal application.

SecondaryNone 3.5.1 Areas of Review This section addresses the aging management review (AMR) and the associated aging management programs (AMPs) for containments, structures and components (SC) supports. For a recent vintage plant, the information related to containments, supports is contained in Chapter 3, Design of Structures, Components, Equipment, and Systems, of the plants final safety analysis report (FSAR), consistent with the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800). For older vintage plants, the location of applicable information is plant-specific because an older plants FSAR may have predated NUREG-0800. The scope of this section is containment structures, and safety-related and other SC supports.

The pressurized water reactor (PWR) containment structures consist of concrete (reinforced or prestressed) and steel containments. The boiling water reactor (BWR) containment structures consist of Mark I, Mark II, and Mark III steel and concrete (reinforced or prestressed) containments.

The safety-related structures (other than containments) are organized into nine groups: Group 1:

BWR reactor building, PWR shield building, control room/building; Group 2: BWR reactor building with steel superstructure; Group 3: auxiliary building, diesel generator building, radwaste building, turbine building, switchgear room, yard structures (auxiliary feedwater (AFW) pump house, utility/piping tunnels, security lighting poles, manholes, duct banks), station blackout (SBO) structures (transmission towers, startup transformer circuit breaker foundation, electrical enclosure); Group 4: containment internal structures, excluding refueling canal; Group 5: fuel storage facility, refueling canal; Group 6: water-control structures (e.g., intake structure, cooling tower, and spray pond); Group 7: concrete tanks and missile barriers; Group 8: steel tank foundations and missile barriers; and Group 9: BWR unit vent stack.

The component supports are organized into seven groups: Group B1.1: supports for American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class 1 piping and components; Group B1.2: supports for ASME Class 2 and 3 piping and components; Group B1.3: supports for ASME Class MC components; Group B2: supports for cable tray, conduit, heating, ventilation, and air conditioning (HVAC) ducts, TubeTrack, instrument tubing, non-ASME piping and components; Group B3: anchorage of racks, panels, cabinets, and enclosures for electrical equipment and instrumentation; Group B4: supports for miscellaneous equipment (e.g., emergency diesel generator (EDG), HVAC components); and Group B5:

supports for miscellaneous structures (e.g., platforms, pipe whip restraints, jet impingement shields, masonry walls).

The responsible review organization is to review the following subsequent license renewal application (SLRA) AMR and AMP items assigned to it, per SRP-SLR Section 1.2, for review:

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AMRs

AMR results consistent with the Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report

AMR results for which further evaluation is recommended

AMR results that are not consistent with or not addressed in the GALL-SLR Report AMPs

Consistent with GALL-SLR Report AMPs

Plant-specific AMPs FSAR Supplement

The responsible review organization is to review the FSAR Supplement associated with each assigned AMP.

3.5.2 Acceptance Criteria The acceptance criteria for the areas of review describe methods for determining whether the applicant has met the requirements of the U.S. Nuclear Regulatory Commission (NRC) regulations in Title 10 of the Code of Federal Regulations (10 CFR) 54.21.

3.5.2.1 Aging Management Review Results Consistent With the Generic Aging Lessons Learned for Subsequent License Renewal Report The AMRs and the AMPs applicable to structures and component supports are described and evaluated in Chapters II and III of the GALL-SLR Report.

The applicants SLRA should provide sufficient information so that the reviewer is able to confirm that the specific SLRA AMR item and the associated SLRA AMP are consistent with the cited GALL-SLR Report AMR item. The reviewer should then confirm that the SLRA AMR item is consistent with the GALL-SLR Report AMR item to which it is compared.

When the applicant is crediting a different AMP than recommended in the GALL-SLR Report, the reviewer should confirm that the alternate AMP is valid to use for aging management and will be capable of managing the effects of aging as adequately as the AMP recommended by the GALL-SLR Report.

3.5.2.2 Aging Management Review Results for Which Further Evaluation Is Recommended by the Generic Aging Lessons Learned for Subsequent License Renewal Report The basic acceptance criteria defined in Section 3.5.2.1 need to be applied first for all of the AMRs and AMPs as part of this section. In addition, if the GALL-SLR Report AMR item to which the SLRA AMR item is compared identifies that further evaluation is recommended, then additional criteria apply for each of the following aging effect/aging mechanism combinations.

Refer to Table 3.5-1, comparing the Further Evaluation Recommended column and the GALL-SLR Item column, for the AMR items that reference the following subsections.

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3.5.2.2.1 Pressurized Water Reactor and Boiling Water Reactor Containments 3.5.2.2.1.1 Cracking and Distortion Due to Increased Stress Levels from Settlement; Reduction of Foundation Strength, and Cracking Due to Differential Settlement and Erosion of Porous Concrete Subfoundations Cracking and distortion due to increased stress levels from settlement could occur in PWR and BWR concrete and steel containments. The existing program relies on ASME Code Section XI, Subsection IWL to manage these aging effects. Also, reduction of foundation strength and cracking, due to differential settlement and erosion of porous concrete subfoundations could occur in all types of PWR and BWR containments. The existing program relies on the structures monitoring program to manage these aging effects. However, some plants may rely on a dewatering system to lower the site groundwater level. If the plants current licensing basis (CLB) credits a dewatering system to control settlement, further evaluation is recommended to verify the continued functionality of the dewatering system during the subsequent period of extended operation.

3.5.2.2.1.2 Reduction of Strength and Modulus Due to Elevated Temperature Reduction of strength and modulus of concrete due to elevated temperatures could occur in PWR and BWR concrete and steel containments. The implementation of 10 CFR 50.55a and ASME Code Section XI, Subsection IWL would not be able to identify the reduction of strength and modulus of concrete due to elevated temperature. Subsection CC-3440 of ASME Code Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. Further evaluation is recommended to determine if of a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects if for any portions of the concrete containment components that exceeds specified temperature limits {i.e., general area temperature greater than 66 °C (Celsius) [150 °F (Fahrenheit)] and local area temperature greater than 93 °C (200 °F)}. Higher temperatures may be allowed if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations. Acceptance criteria are described in Branch Technical Position (BTP) RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.1.3 Loss of Material Due to General, Pitting and Crevice Corrosion

1. Loss of material due to general, pitting, and crevice corrosion could occur in steel elements of inaccessible areas for all types of PWR and BWR containments. The existing program relies on ASME Code Section XI, Subsection IWE, and 10 CFR Part 50, Appendix J AMPs, to manage this aging effect. Further evaluation is recommended of plant-specific programs to manage this aging effect if corrosion is indicated from the IWE examinations. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

2. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus shell of Mark I containments. The existing program relies on ASME Code Section XI, Subsection IWE, and 10 CFR Part 50, Appendix J, to manage this aging effect. If corrosion is significant, recoating of the torus is recommended. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

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3. Loss of material due to general, pitting, and crevice corrosion could occur in steel torus ring girders and downcomers of Mark I containments, downcomers of Mark II containments, and interior surface of suppression chamber shell of Mark III containments. The existing program relies on ASME Code Section XI, Subsection IWE to manage this aging effect. Further evaluation is recommended of plant-specific programs to manage this aging effect if corrosion is significant. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.1.4 Loss of Prestress Due to Relaxation, Shrinkage, Creep, and Elevated Temperature Loss of prestress forces due to relaxation, shrinkage, creep, and elevated temperature for PWR prestressed concrete containments and BWR Mark II prestressed concrete containments is a time-limited aging analysis (TLAA) as defined in 10 CFR 54.3. TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.5, Concrete Containment Unbonded Tendon Pre-stress Analysis, and/or Section 4.7 Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR.

3.5.2.2.1.5 Cumulative Fatigue Damage Evaluations involving time-dependent fatigue, cyclical loading, or cyclical displacement of metal liner, metal plates, suppression pool steel shells (including welded joints) and penetrations (including personnel airlock, equipment hatch, control rod drive (CRD) hatch, penetration sleeves, dissimilar metal welds, and penetration bellows) for all types of PWR and BWR containments and BWR vent header, vent line bellows, and downcomers may be TLAAs as defined in 10 CFR 54.3.

TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c)(1). The evaluation of this TLAA is addressed in Section 4.6, Containment Liner Plates, Metal Containments, and Penetrations Fatigue Analysis, and for cases of plant-specific components, in Section 4.7 Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR. For plant-specific cumulative usage factor calculations, the method used is appropriately defined and discussed in the applicable TLAAs.

3.5.2.2.1.6 Cracking Due to Stress Corrosion Cracking Stress corrosion cracking (SCC) of stainless steel (SS) penetration sleeves, penetration bellows, vent line bellows, suppression chamber shell (interior surface), and dissimilar metal welds could occur in PWR and/or BWR containments. The existing program relies on ASME Code Section XI, Subsection IWE and10 CFR Part 50, Appendix J, to manage this aging effect. Further evaluation, including consideration of SCC susceptibility and applicable operating experience (OE) related to detection, is recommended of additional appropriate examinations/evaluations implemented to detect this aging effect for these SS components and dissimilar metal welds.

3.5.2.2.1.7 Loss of Material (Scaling, Spalling) and Cracking Due to Freeze-Thaw Loss of material (scaling, spalling) and cracking due to freeze-thaw could occur in inaccessible areas of PWR and BWR concrete containments. Further evaluation is recommended to determine if of a plant specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects for plants located in moderate to severe weathering conditions. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

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3.5.2.2.1.8 Cracking Due to Expansion From Reaction With Aggregates Cracking due to expansion from reaction with aggregates could occur in inaccessible areas of concrete elements of PWR and BWR concrete and steel containments. The GALL-SLR Report recommends further evaluation to determine if a plant-specific aging management programAMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed is requiredessential to manage this aging effect. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.1.9 Increase in Porosity and Permeability Due to Leaching of Calcium Hydroxide and Carbonation Increase in porosity and permeability due to leaching of calcium hydroxide and carbonation could occur in inaccessible areas of concrete elements of PWR and BWR concrete and steel containments. Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects if leaching is observed in accessible areas that impact intended functions. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.2 Safety-Related and Other Structures and Component Supports 3.5.2.2.2.1 Aging Management of Inaccessible Areas

1. Loss of material (spalling, scaling) and cracking due to freeze-thaw could occur in below-grade inaccessible concrete areas of Groups 1-3, 5 and 7-9 structures. Further evaluation is recommended of this aging effect for inaccessible areas of these Groups of structures for plants located in moderate to severe weathering conditions to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

2. Cracking due to expansion and reaction with aggregates could occur in inaccessible concrete areas for Groups 1-5 and 7-9 structures. Further evaluation is recommended of inaccessible areas of these Groups of structures to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential is required to manage this aging effect.

Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3. Cracking and distortion due to increased stress levels from settlement could occur in below-grade inaccessible concrete areas of structures for all Groups, and reduction in foundation strength, and cracking due to differential settlement and erosion of porous concrete subfoundations could occur in below-grade inaccessible concrete areas of Groups 1-3, 5-9 structures. The existing program relies on structure monitoring programs to manage these aging effects. Some plants may rely on a dewatering system to lower the site groundwater level. If the plants CLB credits a dewatering system, verification is recommended of the continued functionality of the dewatering system during the subsequent period of extended operation. No further evaluation is recommended if this activity is included in the scope of the applicants structures monitoring program.

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4. Increase in porosity and permeability, and loss of strength due to leaching of calcium hydroxide and carbonation could occur in below-grade inaccessible concrete areas of Groups 1-5 and 7-9 structures. Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects if leaching is observed in accessible areas that impact intended functions. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.2.2 Reduction of Strength and Modulus Due to Elevated Temperature Reduction of strength and modulus of concrete due to elevated temperatures could occur in PWR and BWR Group 1-5 concrete structures. For any concrete elements that exceed specified temperature limits, further evaluations are recommended. Appendix A of American Concrete Institute (ACI) 349-85 specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 66 °C (150 °F) except for local areas, which are allowed to have increased temperatures not to exceed 93 °C (200°F). Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects of a plant-specific program if any portion of the safety-related and other concrete structures exceeds specified temperature limits [i.e., general area temperature greater than 66 °C (150°F) and local area temperature greater than 93 °C (200 °F)]. Higher temperatures may be allowed if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations.

The acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.2.3 Aging Management of Inaccessible Areas for Group 6 Structures Further evaluation is recommended for inaccessible areas of certain Group 6 structure/aging effect combinations as identified below, whether or not they are covered by inspections in accordance with the GALL-SLR Report, AMP XI.S7, Inspection of Water-Control Structures Associated with Nuclear Power Plants, or Federal Energy Regulatory Commission (FERC)/U.S. Army Corp of Engineers dam inspection and maintenance procedures.

1. Loss of material (spalling, scaling) and cracking due to freeze-thaw could occur in below-grade inaccessible concrete areas of Group 6 structures. Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effect of this aging effects for inaccessible areas for plants located in moderate to severe weathering conditions. Acceptance criteria are described in BTP RLSB-1 (Appendix A1 of this SRP-SLR).

2. Cracking due to expansion and reaction with aggregates could occur in inaccessible concrete areas of Group 6 structures. Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential is required to manage this aging effect. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3. Increase in porosity and permeability and loss of strength due to leaching of calcium hydroxide and carbonation could occur in inaccessible areas of concrete elements of 6

Group 6 structures. Further evaluation is recommended to determine if a plant-specific AMP or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, deemed essential to manage theseis aging effects if leaching is observed in accessible areas that impact intended functions. Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.2.2.4 Cracking Due to Stress Corrosion Cracking, and Loss of Material Due to Pitting and Crevice Corrosion Cracking due to SSC and loss of material due to pitting and crevice corrosion could occur in (a) Group 7 and 8 SS tank liners exposed to standing water; and (b) SS and aluminum alloy support members; welds; bolted connections; or support anchorage to building structure exposed to air or condensation (see SRP-SLR Sections 3.2.2.2.2, 3.2.2.2.4, 3.2.2.2.8, and 3.2.2.2.10 for background information).

For Group 7 and 8 SS tank liners exposed to standing water, further evaluation is recommended of plant-specific programs to manage these aging effects. The acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

For SS and aluminum alloy support members; welds; bolted connections; support anchorage to building structure exposed to air or condensation, the plant-specific OE and condition of the SS and aluminum alloy components are evaluated to determine if the plant-specific air or condensation environments are aggressive enough to result in loss of material or cracking after prolonged exposure. The aging effects of loss of material and cracking in SS and aluminum alloy components is not applicable and does not require management if (a) the plant-specific OE does not reveal a history of pitting or crevice corrosion or cracking and (b) a one-time inspection demonstrates that the aging effects are not occurring or that an aging effect is occurring so slowly that it will not affect the intended function of the components during the subsequent period of extended operation. The applicant documents the results of the plant-specific OE review in the SLRA. Visual inspections conducted in accordance with GALL-SLR Report AMP XI.M32, One-Time Inspection, are an acceptable method to demonstrate that the aging effects are not occurring at a rate that affects the intended function of the components. One-time inspections are conducted between the 50th and 60th year of operation, as recommended by the detection of aging effects program element in AMP XI.M32. If loss of material or cracking has occurred and is sufficient to potentially affect the intended function of SS or aluminum alloy support members; welds; bolted connections; or support anchorage to building structure, either: (a) enhancing the applicable AMP (i.e., GALL-SLR Report AMP XI.S3, ASME Section XI, Subsection IWF, or AMP XI.S6, Structures Monitoring); (b) conducting a representative sample inspection consistent with GALL-SLR Report AMP XI.M36, External Surfaces Monitoring of Mechanical Components; or (c) developing a plant-specific AMP are acceptable programs to manage loss of material or cracking (as applicable). Tempers have been specifically developed to improve the SCC resistance for some aluminum alloys. Aluminum alloy and temper combinations which are not susceptible to SCC when used in structural support applications include 1xxx series, 3xxx series, 6061-T6x, and 5454-x. For these alloys and tempers, the susceptibility of cracking due to SCC is not applicable. If these alloys or tempers have been used, the SLRA states the specific alloy or temper used for the applicable in-scope components.

3.5.2.2.2.5 Cumulative Fatigue Damage Evaluations involving time-dependent fatigue, cyclical loading, or cyclical displacement of component support members, anchor bolts, and welds for Groups B1.1, B1.2, and B1.3 7

component supports are TLAAs as defined in 10 CFR 54.3 only if a CLB fatigue analysis exists.

TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.3, Metal Fatigue Analysis, and/or Section 4.7, Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR. For plant-specific cumulative usage factor calculations, the method used is appropriately defined and discussed in the applicable TLAAs.

3.5.2.2.2.6 Reduction of Strength and Mechanical Properties of Concrete Due to Irradiation Reduction of strength, loss of mechanical properties, and cracking due to irradiation could occur in PWR and BWR Group 4 concrete structures that are exposed to high levels of neutron and gamma radiation. These structures include the reactor (primary/biological) shield wall, the sacrificial shield wall, and the reactor vessel support/pedestal structure. Data related to the effects and significance of neutron and gamma radiation on concrete mechanical and physical properties is limited, especially for conditions (dose, temperature, etc.) representative of light-water reactor (LWR) plants. However, based on literature review of existing research, radiation fluence limits of 1 x 1019 neutrons/cm2 neutron radiation and 1 x 108 Gy (1 x 1010 rad) gamma dose are considered conservative radiation exposure levels beyond which concrete material properties may begin to degrade markedly (Ref. 17, 18, 19).

Further evaluation is recommended of if a plant-specific AMP or plant-specific enhancements to selected existing AMPs deemed essential program to manage the aging effects of irradiation if the estimated (calculated) fluence levels or irradiation dose received by any portion of the concrete from neutron (fluence cutoff energy E > 0.1 MeV) or gamma radiation exceeds the respective threshold level during the subsequent period of extended operation or if plant-specific OE of concrete irradiation degradation exists that may impact intended functions. Higher fluence or dose levels may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in strength and/or loss of mechanical properties of concrete from those fluence levels, at or above the operating temperature experienced by the concrete, and the effects are applied to the design calculations. Supporting calculations/analyses, test data, and other technical basis are provided to estimate and evaluate fluence levels and the plant-specific program. The acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR ).

3.5.2.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components Acceptance criteria are described in BTP IQMB-1 (Appendix A.2 of this SRP-SLR).

3.5.2.2.4 Ongoing Review of Operating Experience Acceptance criteria are described in Appendix A.4, Operating Experience for Aging Management Programs.

3.5.2.3 Aging Management Review Results Not Consistent With or Not Addressed in the Generic Aging Lessons Learned for Subsequent License Renewal Report Acceptance criteria are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.2.4 Aging Management Programs For those AMPs that will be used for aging management and are based on the program elements of an AMP in the GALL-SLR Report, the NRC reviewer performs an audit of AMPs credited in the 8

SLRA to confirm consistency with the GALL-SLR Report AMPs identified in Chapter X, Aging Management Programs That May Be Used to Demonstrate Acceptability of Time-Limited Aging Analyses in Accordance With 10 CFR 54.21(c)(1)(iii), and Chapter XI, Chapter XIAging Management Programs.

If the applicant identifies an exception to any of the program elements of the cited GALL-SLR Report AMP, the SLRA AMP should include a basis demonstrating how the criteria of 10 CFR 54.21(a)(3) would still be met. The NRC reviewer should then confirm that the SLRA AMP with all exceptions would satisfy the criteria of 10 CFR 54.21(a)(3). If, while reviewing the SLRA AMP, the reviewer identifies a difference from the GALL-SLR Report AMP that should have been identified as an exception to the GALL-SLR Report AMP, this difference should be reviewed and properly dispositioned. The reviewer should document the disposition of all SLRA-defined exceptions and NRC staff-identified differences.

The SLRA should identify any enhancements that are needed to permit an existing SLRA AMP to be declared consistent with the GALL-SLR Report AMP to which the SLRA AMP is compared.

The reviewer is to confirm both that the enhancement, when implemented, would allow the existing SLRA AMP to be consistent with the GALL-SLR Report AMP and that the applicant has a commitment in the FSAR Supplement to implement the enhancement prior to the subsequent period of extended operation. The reviewer should document the disposition of all enhancements.

If the applicant chooses to use a plant-specific program that is not a GALL-SLR Report AMP, the NRC reviewer should confirm that the plant-specific program satisfies the criteria of BTP RLSB-1 (Appendix A.1.2.3 of this SRP-SLR).

3.5.2.5 Final Safety Analysis Report Supplement The summary description of the programs and activities for managing the effects of aging for the subsequent period of extended operation in the FSAR Supplement should be sufficiently comprehensive, such that later changes can be controlled by 10 CFR 50.59. The description should contain information associated with the bases for determining that aging effects are managed during the subsequent period of extended operation. The description should also contain any future aging management activities, including enhancements and commitments, to be completed before the subsequent period of extended operation. Table X-01 and Table XI-01 of the GALL-SLR Report provide examples of the type of information to be included in the FSAR Supplement. Table 3.5-2 lists the programs that are applicable for this SRP-SLR subsection.

3.5.3 Review Procedures For each area of review, the review procedures below are to be followed.

3.5.3.1 Aging Management Review Results Consistent With the Generic Aging Lessons Learned for Subsequent License Renewal Report The applicant may reference the GALL-SLR Report in its SLRA, as appropriate, and demonstrate that the AMRs and AMPs at its facility are consistent with those reviewed and approved in the GALL-SLR Report. The reviewer should not conduct a review of the substance of the matters described in the GALL-SLR Report. If the applicant has provided the information necessary to adopt the finding of program acceptability as described and evaluated in the GALL-SLR Report, the reviewer should find acceptable the applicants reference to GALL-SLR in its SLRA. In making this determination, the reviewer confirms that the applicant has provided a brief 9

description of the system, components, materials, and environment. The reviewer also confirms that the applicable aging effects have been addressed based on the staffs review of industry and plant-specific OE.

Furthermore, the reviewer should confirm that the applicant has addressed OE identified after the issuance of the GALL-SLR Report. Performance of this review requires the reviewer to confirm that the applicant has identified those aging effects for the SC supports that are contained in the GALL-SLR Report as applicable to its plant.

3.5.3.2 Aging Management Review Results for Which Further Evaluation Is Recommended by the Generic Aging Lessons Learned for Subsequent License Renewal Report The basic review procedures defined in Section 3.5.3.1 need to be applied first for all of the AMRs and AMPs provided in this section. In addition, if the GALL-SLR AMR item to which the SLRA AMR item is compared identifies that further evaluation is recommended, then additional criteria apply for each of the following aging effect/aging mechanism combinations.

3.5.3.2.1 Pressurized Water Reactor and Boiling Water Reactor Containments 3.5.3.2.1.1 Cracking and Distortion Due to Increased Stress Levels From Settlement; Reduction of Foundation Strength and Cracking Due to Differential Settlement and Erosion of Porous Concrete Subfoundations Further evaluation is recommended of aging management of (1) cracking and distortion due to increases in component stress level from settlement for PWR and BWR concrete and steel containments and (2) reduction of foundation strength and cracking due to differential settlement and erosion of porous concrete subfoundations for all types of PWR and BWR containments if a dewatering system is relied upon to control settlement. The reviewer reviews and confirms that, if the applicant credits a dewatering system in its CLB, the applicant has committed to monitor the functionality of the dewatering system under the applicants ASME Code Section XI, Subsection IWL or the structures monitoring program. If not, the reviewer evaluates the plant-specific program for monitoring the dewatering system during the subsequent period of extended operation.

3.5.3.2.1.2 Reduction of Strength and Modulus Due to Elevated Temperature Further evaluation is recommended of programs to manage reduction of strength and modulus of concrete due to elevated temperature for PWR and BWR concrete and steel containments. The implementation of ASME Code Section XI, Subsection IWL examinations and 10 CFR 50.55a would not be able to detect the reduction of concrete strength and modulus due to elevated temperature and also notes that no mandated aging management exists for managing this aging effect.

A plant-specific evaluation should be performed if any portion of the concrete containment components exceeds specified temperature limits [i.e., general temperature greater than 66 °C (150 °F) and local area temperature greater than 93 °C (200 °F)]. Higher temperatures may be allowed if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations. The reviewer reviews and confirms that the applicants discussion in the renewal application indicates that the affected PWR and BWR containment components are not exposed to a temperature that exceeds the temperature limits. If active cooling is relied upon to maintain acceptable temperatures, then the 10

reviewer ensures that the aging effects associated with the cooling system are being properly managed or temperatures are being monitored to identify a problem with the cooling system. If the limits are exceeded the reviewer reviews the technical basis (i.e., tests and/or calculations) provided by the applicant to justify the higher temperature. Otherwise, the reviewer reviews the applicants proposed-plant- specific AMPprograms or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage these aging effects. Performed plant-specific evaluations verify that, where appropriate, an effective enhanced inspection program has been developed and implemented, to ensure that to ensure that the effects reduction of strength and modulus of elasticity due to of elevated temperatures will beare adequately managed during the subsequent period of extended operation.

3.5.3.2.1.3 Loss of Material Due to General, Pitting, and Crevice Corrosion

1. The GALL-SLR Report identifies programs to manage loss of material due to general, pitting, and crevice corrosion in accessible and inaccessible areas of the steel elements in drywell and torus or the steel liner and integral attachments for all types of PWR and BWR containments. The AMP consists of ASME Code Section XI, Subsection IWE, and 10 CFR Part 50, Appendix J, leak tests. Subsection IWE exempts from examination portions of the containments that are inaccessible, such as embedded or inaccessible portions of steel liners and steel elements in drywell and torus, and integral attachments.

To cover the inaccessible areas, 10 CFR 50.55a(b)(2)(ix) requires that the applicant evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of, or result in, degradation to such inaccessible areas. In addition, further evaluation of plant-specific programs to manage the aging effects for inaccessible areas is recommended if the following cannot be satisfied: (1) concrete meeting the requirements of ACI 318 or ACI 349 (low water-to-cement ratio, low permeability, and adequate air entrainment) as cited in NUREG-1557 and the guidance of ACI 201.2R, as applicable, was used for the containment concrete in contact with the embedded containment shell or liner; (2) the moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Code Section XI, Subsection IWE requirements; (3) the concrete is monitored to ensure that it is free of penetrating cracks that provide a path for water seepage to the surface of the containment shell or liner; and (4) borated water spills and water ponding on the concrete floor are common and when detected are cleaned up or diverted to a sump in a timely manner. OE has identified significant corrosion in some plants. If any of the above conditions cannot be satisfied, then a plant-specific AMP for corrosion is necessary.

The reviewer reviews the applicants proposed AMP to confirm that, where appropriate, an effective inspection program has been developed and implemented to ensure that the aging effects in inaccessible areas are adequately managed.

2. The GALL-SLR Report identifies programs to manage loss of material due to general, pitting, and crevice corrosion in steel torus shell of Mark I containments. The AMP consists of ASME Code Section XI, Subsection IWE, and 10 CFR Part 50, Appendix J, leak tests. In addition, further evaluation is recommended of plant-specific programs to manage the aging effects if corrosion is significant. Further evaluation of torus shell corrosion is warranted as a result of industry-wide OE that identified a number of incidences of torus corrosion. The reviewer reviews the applicants proposed AMP to confirm that, where appropriate, an effective inspection program has been developed and implemented to ensure that the aging effects are adequately managed. A plant-specific program may include the recoating of the torus, if necessary.

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3. The GALL-SLR Report identifies programs to manage loss of material due to general, pitting, and crevice corrosion in steel torus ring girders and downcomers of Mark I containments, suppression chambers and downcomers of Mark II containments, and interior surface of suppression chamber shell of Mark III containments. GALL-SLR Report AMP XI.S1, ASME Section XI, Subsection IWE, is recommended for aging management. In addition, further evaluation of plant-specific programs is recommended to manage the aging effects if plant OE identified significant corrosion of the torus ring girders, downcomers and suppression chambers.

3.5.3.2.1.4 Loss of Prestress Due to Relaxation, Shrinkage, Creep, and Elevated Temperature Loss of prestress is a TLAA as defined in 10 CFR 54.3. TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.5, Concrete Containment Unbonded Tendon Prestress Analysis, or Section 4.7, Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR.

The staff reviews the information on a case-by-case basis consistent with the review procedures in SRP-SLR Sections 4.5 and/or 4.7 (as applicable) to determine whether the applicant has provided a sufficient basis for dispositioning the TLAAs in accordance with the acceptance criteria in 10 CFR 54.21(c)(1)(i), (ii), or (iii).

3.5.3.2.1.5 Cumulative Fatigue Damage Evaluations involving time-dependent fatigue, cyclical loading, or cyclical displacement included in the CLB for the metal liner, metal plates, suppression pool steel shells (including welded joints) and penetrations (including personnel airlock, equipment hatch, CRD hatch, penetration sleeves, dissimilar metal welds, and penetration bellows) for all types of PWR and BWR containments and BWR vent header, vent line bellows, and downcomers are TLAAs as defined in 10 CFR 54.3.

TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.6, Containment Liner Plate, Metal Containments, and Penetrations Fatigue Analysis, and for cases of plant-specific components, in Section 4.7, Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR.

The staff reviews the information on a case-by-case basis consistent with the review procedures in SRP-SLR Sections 4.6 or 4.7 (as applicable) to determine whether the applicant has provided a sufficient basis for dispositioning the TLAAs in accordance with the acceptance criteria in 10 CFR 54.21(c)(1)(i), (ii), or (iii). This includes staffs review of those cumulative usage factor analyses that qualify as TLAAs based on plant-specific calculation methods.

3.5.3.2.1.6 Cracking Due to Stress Corrosion Cracking Further evaluation is recommended of programs to manage cracking due to SCC in SS penetration sleeves, penetration bellows, vent line bellows, suppression chamber shell (interior surface), and dissimilar metal welds in PWR and/or BWR containments. Transgranular stress corrosion cracking (TGSCC) is a concern for dissimilar metal welds. In the case of bellows assemblies, SCC may cause aging effects particularly if the material is not shielded from a corrosive environment. Containment inservice inspection (ISI) IWE and leak rate testing may not be sufficient to detect cracks, especially for dissimilar metal welds. Additional appropriate examinations to detect SCC in the listed SS components and dissimilar metal welds, considering SCC susceptibility and applicable OE (e.g., cracking of two-ply bellows) related to detection, are recommended to address this issue. The reviewer reviews and evaluates the applicants 12

proposed programs to confirm that adequate inspection methods will be implemented to ensure that cracks are detected.

3.5.3.2.1.7 Loss of Material (Scaling, Spalling) and Cracking Due to Freeze-Thaw Further evaluation is recommended of programs to manage loss of material (scaling, spalling) and cracking due to freeze-thaw for concrete elements of PWR and BWR containments. Containment ISI Subsection IWL may not be sufficient for plants located in moderate to severe weathering conditions. Evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557). The weathering index for the continental United States is shown in American Society for Testing and Materials (ASTM) C33-90, Figure 1. A plant-specific AMPprogram or plant-specific enhancements to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect are is not required if documented evidence confirms that the existing concrete had air content of 3 percent to 8 percent (including tolerance) and subsequent inspection of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections are considered a part of the evaluation. The reviewer reviews and confirms that the applicant has satisfied the recommendations for inaccessible concrete. Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage theseis aging effects.

Performed Where appropriate, a plant-specific evaluations is performed existing AMP(s), to verify that, where appropriate, an effective enhanced inspection program has been developed and implemented to ensure that these aging effects loss of material (scaling, spalling) and cracking due to freeze thaw in inaccessible areas for plants located in moderate to severe weathering conditions are adequately managed during the subsequent period of extended operation.

3.5.3.2.1.8 Cracking Due to Expansion from Reaction With Aggregates Further evaluation is recommended of programs to manage cracking due to expansion from reaction with aggregates in inaccessible areas of concrete elements of PWR and BWR concrete and steel containments. A plant-specific AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect, is necessary if (1) reactivity tests or petrographic examinations of concrete samples identify reaction with aggregates, or (2) accessible concrete exhibits visual indications of aggregate reactions, such as map or patterned cracking, alkali-silica gel, exudations, surface staining, expansion causing structural deformation, relative movement or displacement, or misalignment/distortion of attached components. The reviewer confirms that the applicant has not identified one of the above conditions. Otherwise, the reviewer reviews the applicants proposed plant specific AMP or plant specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect. Where appropriate, a or pPerformed plant-specific evaluations is performed to verify that, where appropriate, an effective enhanced evaluation or inspection program has been developed and implemented to ensure that this aging effect cracking due to expansion from reaction with aggregates in inaccessible areas is adequately managed during the subsequent period of extended operation..

3.5.3.2.1.9 Increase in Porosity and Permeability Due to Leaching of Calcium Hydroxide and Carbonation Further evaluation is recommended of programs to manage increase in porosity and permeability due to leaching of calcium hydroxide and carbonation in inaccessible areas of PWR and BWR concrete and steel containments. A plant-specific AMP is not required, even if reinforced concrete 13

is exposed to flowing water if (1) there is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas is not significant and has no impact on the intended function of the concrete structure. The reviewer confirms that the applicant has satisfied these conditions. Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage theseis aging effects. P Where appropriate, a plant-specific evaluation is performedexisting AMP(s) , to verify that, where appropriate, where appropriate, an effective enhanced inspection program has been developed and implemented to ensure that this aging effect increase in porosity and permeability due to leaching in inaccessible areas is are adequately managed during the subsequent period of extended operation..

3.5.3.2.2 Safety-Related and Other Structures, and Component Supports 3.5.3.2.2.1 Aging Management of Inaccessible Areas

1. Further evaluation is recommended of programs to manage loss of material (spalling, scaling) and cracking due to freeze-thaw in below-grade inaccessible concrete areas of Groups 1-3, 5, and 7-9 structures. Structure monitoring programs may not be sufficient for plants located in moderate to severe weathering conditions. Further evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557). The weathering index for the continental United States is shown in ASTM C33-90, Figure 1. A plant-specific program is not required if documented evidence confirms that the existing concrete had air content of 3 percent to 8 percent and subsequent inspection did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation.

The reviewer confirms that the applicant has satisfied these conditions. Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage theseis aging effects. Where appropriate, a Performed plant-specific evaluations is performedexisting AMP(s), to verify that, where appropriate, where appropriate, an effective enhanced inspection program has been developed and implemented to ensure that this aging effect loss of material (spalling, scaling) and cracking due to freeze-thaw in inaccessible areas for plants located in moderate to severe weathering conditions is are adequately managed during the subsequent period of extended operation. .

2. Further evaluation is recommended to determine if a plant-specific program is required to manage cracking due to expansion from reaction with aggregates in inaccessible concrete areas of Groups 1-5 and 7-9 structures. A plant-specific evaluation or program is required if (1) reactivity tests or petrographic examinations of concrete samples identify reaction with aggregates, or (2) accessible concrete exhibits visual indications of aggregate reactions, such as map or patterned cracking, alkali-silica gel exudations, surface staining, expansion causing structural deformation, relative movement or displacement, or misalignment/distortion of attached components. The reviewer confirms that the applicant has not identified any of the above conditions.

Otherwise, the reviewer reviews the applicants proposed AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect. Where appropriate, aPerformed plant-specific evaluations is performed to verify that, where appropriate, or plant-specific evaluation to verify that, an effective enhanced evaluation or inspection 14

program has been developed and implemented to ensure that the cracking due to expansion from reaction with aggregates in inaccessible concrete areas aging effectis is adequately managed during the subsequent period of extended operation..

3. Further evaluation is recommended of aging management of (a) cracking and distortion due to increased stress levels from settlement for inaccessible concrete areas of structures for all Groups and (b) reduction of foundation strength, and cracking due to differential settlement and erosion of porous concrete subfoundations for inaccessible concrete areas of Groups 1-3, and 5-9 structures if a dewatering system is relied upon to manage the aging effect. The reviewer confirms that, if the applicants plant credits a dewatering system in its CLB, the applicant has committed to monitor the functionality of the dewatering system under the applicants structures monitoring program. If not, the reviewer reviews and evaluates the plant-specific program for monitoring the dewatering system during the subsequent period of extended operation.

4. Further evaluation is recommended of programs to manage increase in porosity and permeability due to leaching of calcium hydroxide and carbonation in below-grade inaccessible concrete areas of Groups 1-5, and 7-9 structures. A plant-specific AMP is not required for the reinforced concrete exposed to flowing water if (1) there is evidence in the accessible areas that the flowing water has not caused leaching of calcium hydroxide and carbonation or (2) evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure. The reviewer confirms that the applicant has satisfied these conditions. Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage theseis aging effectsexisting AMP(s). Performed plant-specific evaluations Where appropriate, , a plant-specific evaluation is performed to verify that, where appropriate, an effective enhanced inspection program has been developed and implemented to ensure that this aging effect iincrease in porosity and permeability due to leaching of calcium hydroxide and carbonation in inaccessible areas is are adequately managed during the subsequent period of extended operation.

3.5.3.2.2.2 Reduction of Strength and Modulus Due to Elevated Temperature Further evaluation is recommended of programs to manage reduction of strength and modulus of concrete structures due to elevated temperatures for PWR and BWR safety-related and other structures.

A plant-specific evaluation should be performed if any portion of the concrete Groups 1-5 structures exceeds specified temperature limits [i.e., general temperature greater than 66 °C (150 °F) and local area temperature greater than 93 °C (200 °F)]. Higher temperatures may be allowed if tests and/or calculations are provided to evaluate the reduction in strength and modulus of elasticity and these reductions are applied to the design calculations. The reviewer reviews and confirms that the applicants discussion in the renewal application indicates that the affected Groups 1-5 structures are not exposed to temperature that exceeds the temperature limits. If active cooling is relied upon to maintain acceptable temperatures, then the reviewer ensures that the aging effects associated with the cooling system are being properly managed or temperatures are being monitored to identify a problem with the cooling system. If the limits are exceeded, the reviewer reviews the technical basis (i.e., tests and/or calculations) provided by the applicant to justify the higher temperature. Otherwise the reviewer reviews the applicants proposed plant-15

specific AMPor plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage these aging effects. Performed plant-specific evaluations verify that, where appropriate, an effective enhanced inspection program has been developed and implemented, to ensure that programs on a case-by-case basis to ensure that the effects of reduction of strength and modulus of concrete structures due to elevated temperatures will beare adequately managed during the subsequent period of extended operation.

3.5.3.2.2.3 Aging Management of Inaccessible Areas for Group 6 Structures Further evaluation is recommended for inaccessible areas of certain Group 6 structure/aging effect combinations as identified below, whether or not they are covered by inspections in accordance with GALL-SLR Report AMP XI.S7, or FERC/US Army Corp of Engineers dam inspection and maintenance procedures.

1. Loss of material (spalling, scaling) and cracking due to freeze-thaw could occur in below-grade inaccessible concrete areas of Group 6 structures. Further evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557, Ref. 15). The weathering index for the continental U.S. is shown in ASTM C33-90, Figure 1. A plant-specific program is not required if documented evidence confirms that the existing concrete had air content of 3 percent to 8 percent and subsequent inspection of accessible areas did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation. The reviewer reviews and confirms that the applicant has satisfied these conditions. Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage theseis aging effects.

Performed plant-specific evaluations verify Where appropriate, a plant-specific evaluation is performed existing AMP(s), to determine that, where appropriate, an effective enhanced inspection program has been developed and implemented, to ensure that this aging effect loss of material (spalling, scaling) and cracking due to freeze-thaw in inaccessible areas for plants located in moderate to severe weathering conditions will beare adequately managed.during the subsequent period of extended operation.

2. Cracking due to expansion from reaction with aggregates could occur in inaccessible concrete areas of Group 6 structures. Further evaluation is recommended to determine if a plant-specific program is required to manage the aging effect. A plant-specific evaluation or program is required if (1) reactivity tests or petrographic examinations of concrete samples identify reaction with aggregates, or (2) accessible concrete exhibits visual indications of aggregate reactions, such as map or patterned cracking, alkali-silica gel exudations, surface staining, expansion causing structural deformation, relative movement or displacement, or misalignment/distortion of attached components.

The reviewer confirms that the applicant has not identified any of the above conditions.

Otherwise, the reviewer reviews the applicants proposed plant-specific AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect. . Performed plant-specific evaluations Where appropriate, a or plant-specific evaluation is performed to verify that, where appropriate, an effective enhanced evaluation or inspection program has been developed and implemented to ensure that the aging effect cracking due to expansion from reaction with aggregates will beare adequately managed during the subsequent period of extended operation.

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3. Increase in porosity and permeability due to leaching of calcium hydroxide and carbonation could occur in below-grade inaccessible concrete areas of Group 6 structures. Further evaluation is recommended to determine if a plant-specific program is required to manage the aging effect. A plant-specific program is not required for the reinforced structures exposed to flowing water if (1) there is evidence in the accessible areas that the flowing water has not caused leaching and carbonation, or (2) evaluation determined that the observed leaching of calcium hydroxide and carbonation in accessible areas has no impact on the intended function of the concrete structure. The reviewer confirms that the applicant has satisfied these conditions. Otherwise, the reviewer reviews the applicants proposed AMP, or plant-specific enhancement(s) to ASME Code Section XI, Subsection IWL and/or Structures Monitoring AMPs, essential to manage this aging effect. Where appropriate, aPerformed plant-specific evaluations is performedexisting AMP(s), to verify that, where appropriate, an effective enhanced inspection program has been developed and implemented to ensure that this aging effect porosity and permeability due to leaching of calcium hydroxide and carbonation in inaccessible areas will beare adequately managed during the subsequent period of extended operation.

3.5.3.2.2.4 Cracking Due to Stress Corrosion Cracking and Loss of Material Due to Pitting and Crevice Corrosion Further evaluation is recommended of plant-specific programs to manage cracking due to SCC and loss of material due to pitting and crevice corrosion for SS tank liners exposed to standing water. The reviewer reviews the applicants proposed AMP on a case-by-case basis to ensure that the intended functions will be maintained during the subsequent period of extended operation.

The GALL-SLR Report recommends further evaluation to manage loss of material due to pitting and crevice corrosion and cracking due to SCC in SS and aluminum alloy support members; welds; bolted connections; or support anchorage to building structure exposed to any air, condensation, or underground environment where the presence of sufficient halides (e.g., chlorides) and moisture is possible; or in the vicinity of potentially transportable halogens.

The possibility of these aging effects also extends to indoor components located in close proximity to sources of outdoor air (e.g., components near intake vents).

The reviewer independently verifies the sufficiency of the applicants evaluation of plant-specific OE. If the review of plant-specific OE reveals loss of material due to pitting or crevice corrosion or cracking due to SCC in SS or aluminum alloys, the reviewer determines whether an adequate program is credited to manage the aging effect. If the review of plant-specific OE reveals that loss of material due to pitting and crevice corrosion and cracking due to SCC is not applicable, the reviewer verifies that AMP XI.M32, One-Time Inspection, is cited for all applicable AMR line items.

An applicant may refine its OE search, and subsequent one-time inspections, by binning plant-specific environments into subcategories. For example, the OE search could be based on two environments including outdoor air and indoor air. The results could be that loss of material or cracking has occurred in the outdoor air environment but not the indoor air environment. The applicant could further categorize the indoor air locations as those where leakage could impinge on a components surface (e.g., leakage from mechanical connections) and those where there is not a potential for leakage. When the applicant chooses to conduct its OE search in this manner, the reviewer is to also confirm that the applicant has adequately addressed the potential for the 17

periodic introduction of either moisture or halides from secondary sources. Secondary sources of moisture or halides should be considered for all environments including indoor conditioned air.

Typical secondary sources of moisture or halides include: leakage from mechanical connections; leakage into vaults; insulation containing halides; and outdoor air intrusion. Grouping of environments consistent with that described in the detection of aging effects program element of GALL-SLR Report AMP XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components, is appropriate.

3.5.3.2.2.5 Cumulative Fatigue Damage Evaluations involving time-dependent fatigue, cyclical loading, or cyclical displacement of support members, anchor bolts, and welds for Groups B1.1, B1.2, and B1.3 component supports are TLAAs as defined in 10 CFR 54.3 only if a CLB fatigue analysis exists. TLAAs are required to be evaluated in accordance with 10 CFR 54.21(c). The evaluation of this TLAA is addressed in Section 4.3, Metal Fatigue Analysis, and/or Section 4.7, Other Plant-Specific Time-Limited Aging Analyses, of this SRP-SLR.

The staff reviews the information on a case-by-case basis consistent with the review procedures in SRP-SLR Sections 4.3 and/or 4.7 (as applicable) to determine whether the applicant has provided a sufficient basis for dispositioning the TLAAs in accordance with the acceptance criteria in 10 CFR 54.21(c)(1)(i), (ii), or (iii). This includes staffs review of those cumulative usage factor analyses that qualify as TLAAs based on plant-specific calculation methods.

3.5.3.2.2.6 Reduction of Strength and Mechanical Properties of Concrete Due to Irradiation Further evaluation is recommended of a plant-specific AMPprogram or plant-specific enhancements to selected AMPs to manage reduction of strength, loss of mechanical properties, and cracking of concrete due to irradiation in PWR and BWR Group 4 concrete structures, exposed to high levels of neutron and gamma radiation. These structures include the reactor (primary/biological) shield wall, the sacrificial shield wall, and the reactor vessel support/pedestal structure. The irradiation mechanism consists of radiation interactions with the material and heating due to absorption of radiation energy at the operating temperature experienced by the concrete. The intensity of radiation is typically characterized by the measure of its field or fluence.

Both neutron and gamma radiation produce internal heating from absorption of radiation energy and, at high fluence levels, changes in microstructure and certain mechanical properties of concrete (e.g., compressive strength, tensile strength, modulus of elasticity) from radiation interactions with the material. Limited data are available in the open literature related to the effects and significance of radiation fluences (neutron and gamma radiation) on intended functions of concrete structures, especially for conditions (dose, temperature, etc.) representative of existing LWR plants. However, based on literature review of existing research, fluence limits of 1 x 1019 neutrons/cm2 neutron radiation and 1 x 108 Gy (1 x 1010 rad) gamma dose are considered conservative radiation exposure levels beyond which concrete material properties may begin to degrade markedly.

Plant-specific calculations/analyses should be performed to identify the neutron (fluence cutoff energy E > 0.1 MeV) and gamma fields that develop in any portion of the concrete structures of interest at 80 years of operation and compare them to the above threshold limits. The impact of any plant-specific OE of concrete irradiation effects on intended functions are evaluated. The reviewer reviews these analyses, OE and supporting technical basis (e.g., calculations, test data, plant-specific evaluations) on a case-by-case basis. Higher fluence or dose levels may be allowed in the concrete if tests and/or calculations are provided to evaluate the reduction in 18

strength and/or change in mechanical properties of concrete, if any, from those fluence levels and the effects are applied to the design calculations. The reviewer confirms that the applicants discussion in the SLRA indicates that the affected PWR and BWR concrete components are not exposed to neutron and gamma radiation fluence levels that exceed the threshold limits, or are otherwise evaluated, for example, the concrete is primarily for shielding and non-structural. The reviewer also confirms that the impact of any plant-specific OE of concrete irradiation degradation on intended functions is addressed. If the limits are exceeded, the technical basis (i.e., tests and/or calculations or evaluations) provided by the applicant to justify higher fluence or dose limits is reviewed. Otherwise, the applicants proposed plant-specific AMPprogram or plant-specific enhancements to selected AMPs and the supporting technical basis is reviewed to ensure that the effects of irradiation on the concrete components will be adequately managed during the subsequent period of extended operation.

3.5.3.2.3 Quality Assurance for Aging Management of Nonsafety-Related Components The applicants AMP for subsequent license renewal (SLR) should contain the elements of corrective actions, the confirmation process, and administrative controls. Safety-related components are covered by 10 CFR Part 50 Appendix B, which is adequate to address these program elements. However, Appendix B does not apply to nonsafety-related components that are subject to an AMR for SLR. Nevertheless, an applicant has the option to expand the scope of its 10 CFR Part 50 Appendix B program to include these components and address these program elements. If the applicant chooses this option, the reviewer verifies that the applicant has documented such a commitment in the FSAR Supplement. If the applicant chooses alternative means, the branch responsible for quality assurance should be requested to review the applicants proposal on a case-by-case basis.

3.5.3.2.4 Ongoing Review of Operating Experience The applicants AMPs should contain the element of OE. The reviewer verifies that the applicant has appropriate programs or processes for the ongoing review of both plant-specific and industry OE concerning age-related degradation and aging management. Such reviews are used to ensure that the AMPs are effective to manage the aging effects for which they are created. The AMPs are either enhanced or new AMPs are developed, as appropriate, when it is determined through the evaluation of OE that the effects of aging may not be adequately managed.

Additional information is in Appendix A.4, Operating Experience for Aging Management Programs of this SRP-SLR. In addition, the reviewer confirms that the applicant has provided an appropriate summary description of these activities in the FSAR Supplement.

3.5.3.3 Aging Management Review Results Not Consistent With or Not Addressed in the Generic Aging Lessons Learned for Subsequent License Renewal Report The reviewer should confirm that the applicant, in their SLRA, has identified applicable aging effects, listed the appropriate combination of materials and environments, and credited AMPs that will adequately manage the aging effects. The AMP credited by the applicant could be an AMP that is described and evaluated in the GALL-SLR Report or a plant-specific program. Review procedures are described in BTP RLSB-1 (Appendix A.1 of this SRP-SLR).

3.5.3.4 Aging Management Programs The reviewer confirms that the applicant has identified the appropriate AMPs as described and evaluated in the GALL-SLR Report. If the applicant commits to an enhancement to make its 19

SLRA AMP consistent with a GALL-SLR Report AMP, then the reviewer is to confirm that this enhancement, when implemented, will make the SLRA AMP consistent with the GALL-SLR Report AMP. If the applicant identifies, in the SLRA AMP, an exception to any of the program elements of the GALL-SLR Report AMP, the reviewer is to confirm that the SLRA AMP with the exception will satisfy the criteria of 10 CFR 54.21(a)(3). If the reviewer identifies a difference, not identified by the SLRA, between the SLRA AMP and the GALL-SLR Report AMP, with which the SLRA claims to be consistent, the reviewer should confirm that the SLRA AMP with this difference satisfies 10 CFR 54.21(a)(3). The reviewer should document the basis for accepting enhancements, exceptions, or differences. The AMPs evaluated in the GALL-SLR Report pertinent to the containments, structures, and component supports are summarized in Table 3.5-1 of this SRP-SLR. The GALL-SLR Item column identifies the AMR item numbers in the GALL-SLR Report, Chapters II and III, presenting detailed information summarized by this row.

If the applicant chooses to use a plant-specific program that is not a GALL-SLR Report AMP, the NRC reviewer should confirm that the plant-specific program satisfies the criteria of BTP RLSB-1 (Appendix A.1.2.3 of this SRP-SLR).

3.5.3.5 Final Safety Analysis Report Supplement The reviewer confirms that the applicant has provided in its FSAR Supplement information for aging management of the containments, structures, and component supports. Table 3.5-2 lists the AMPs that are applicable for this SRP-SLR subsection. The reviewer also confirms that the applicant has provided information for Subsection 3.5.3.3, Aging Management Review Results Not Consistent With or Not Addressed in the Generic Aging Lessons Learned for Subsequent License Renewal Report.

The NRC staff expects to impose a license condition on any renewed license to require the applicant to update its FSAR to include this FSAR Supplement at the next update required pursuant to 10 CFR 50.71(e)(4). As part of the license condition, until the FSAR update is complete, the applicant may make changes to the programs described in its FSAR Supplement without prior NRC approval, provided that the applicant evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59. If the applicant updates the FSAR to include the final FSAR Supplement before the license is renewed, no condition will be necessary.

An applicant should incorporate the implementation schedule into its FSAR. The reviewer should verify that the applicant has identified and committed in the SLRA to any future aging management activities, including enhancements and commitments, to be completed before entering the subsequent period of extended operation. The NRC staff expects to impose a license condition on any renewed license to ensure that the applicant will complete these activities no later than the committed date.

3.5.4 Evaluation Findings If the reviewer determines that the applicant has provided information sufficient to satisfy the provisions of this section, then an evaluation finding similar to the following text should be included in the NRC staffs safety evaluation report:

On the basis of its review, as discussed above, the NRC staff concludes that the applicant has demonstrated that the aging effects associated with the containments, structures, and component supports components will be adequately managed so that the intended functions will be maintained consistent 20

with the CLB for the subsequent period of extended operation, as required by 10 CFR 54.21(a)(3).

The NRC staff also reviewed the applicable FSAR Supplement program summaries and concludes that they adequately describe the AMPs credited for managing aging of the containments, structures, and component supports, as required by 10 CFR 54.21(d).

3.5.5 Implementation Except for cases in which the applicant proposes an alternative method for complying with specified portions of NRC regulations, NRC staff members follow the methods described herein in their evaluation of conformance with NRC regulations. The staff evaluates these alternatives and finds them acceptable if the staff determines that the alternatives provide reasonable assurance that the components intended functions will be maintained.

3.5.6 References

1. 10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. Washington, DC: U.S. Nuclear Regulatory Commission.

2016.

2. 10 CFR 50.55a, Codes and Standards. Washington, DC: U.S. Nuclear Regulatory Commission. 2016.

3. 10 CFR 50.59, Changes, Tests, and Experiments. Washington, DC: U.S. Nuclear Regulatory Commission. 2016.

4. 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. Washington, DC: U.S. Nuclear Regulatory Commission.

2016.

5. 10 CFR 50.71, Maintenance of Record, Making of Reports. Washington, DC:

U.S. Nuclear Regulatory Commission. 2016.

6. 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. Washington, DC: U.S. Nuclear Regulatory Commission. 2016.

7. 10 CFR 54.4, Scope. Washington, DC: U.S. Nuclear Regulatory Commission. 2016.

8. NRC. Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants. Revision 1. Agencywide Documents Access and Management System (ADAMS) Accession No. ML003739392. Washington, DC: U.S. Nuclear Regulatory Commission. March 1978.

9. NEI. NEI 95-10, Industry Guideline for Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule. Revision 6. ADAMS Accession No. ML051860406. Washington, DC: Nuclear Energy Institute. June 2005.

10. ASME. ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWL, Requirements for Class CC Concrete Components of 21

Light-Water Cooled Power Plants. New York, New York: The American Society of Mechanical Engineers. 2008.

11. ASME. ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Power Plants. New York, New York: The American Society of Mechanical Engineers. 2008.

12. ASME. ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWF, Requirements for Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants. New York, New York: The American Society of Mechanical Engineers. 2008.

13. NEI. NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. Revision 2. ADAMS Accession No. ML11116A198. Washington, DC: Nuclear Energy Institute. April 1996.

14. NRC. Regulatory Guide 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. Revision 2. Agencywide Documents Access and Management System (ADAMS) Accession No. ML003761662. Washington, DC: U.S. Nuclear Regulatory Commission. March 31 1997.

15. NRC. NUREG-1557, Summary of Technical Information and Agreements from Nuclear Management and Resources Council Industry Report addressing License Renewal.

Washington, DC: U.S. Nuclear Regulatory Commission. October 1996.

16. ACI. ACI Standard 318, Building Code Requirements for Reinforced Concrete and Commentary. Farmington Hills, Michigan: American Concrete Institute. 1995.

17. Hilsdorf, H.K., J. Kropp, and H.J. Koch. The Effects of Nuclear Radiation on the Mechanical Properties of Concrete. ACI SP 55-10. pp 223-251. Farmington Hills, Michigan: American Concrete Institute. 1978.

22

18. NRC. NUREG/CR-7171, A Review of the Effects of Radiation on Microstructure and Properties of Concretes Used in Nuclear Power Plants. ADAMS Accession No. ML13325B077. Washington, DC: U.S. Nuclear Regulatory Commission.

November 2013.

19. Field, K.G., Y. Le Pape, and I. Remec. Perspectives on Radiation Effects in Concrete for Nuclear Power Plants-Part I: Quantification of Radiation Exposure and Radiation Effects. Nuclear Engineering and Design. Vol 285. pp 126-143. February 2015.

20. ACI. ACI Standard 349-85, Code Requirements for Nuclear Safety-Related Concrete Structures. Farmington Hills, Michigan: American Concrete Institute. 1985.

23

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 001 BWR/PWR Concrete: dome; wall; Cracking and distortion AMP XI.S2, Yes (SRP-SLR II.A1.CP-101 basemat; ring girders; due to increased stress "ASME Section XI, Section 3.5.2.2.1.1) II.A2.CP-69 buttresses, concrete levels from settlement Subsection IWL," II.B1.2.CP-105 elements, all and/or II.B2.2.CP-105 AMP XI.S6, II.B3.1.CP-69 "Structures II.B3.2.CP-105 Monitoring" E 002 BWR/PWR Concrete: foundation; Reduction of foundation AMP XI.S6, Yes (SRP-SLR II.A1.C-07 subfoundation strength and cracking due "Structures Section 3.5.2.2.1.1) II.A2.C-07 to differential settlement Monitoring" II.B1.2.C-07 and erosion of porous II.B2.2.C-07 concrete subfoundation II.B3.1.C-07 II.B3.2.C-07 24 M 003 BWR/PWR Concrete: dome; wall; Reduction of strength and Plant-specific Yes (SRP-SLR II.A1.CP-34 basemat; ring girders; modulus of elasticity due aging Section 3.5.2.2.1.2) II.B1.2.CP-57 buttresses, concrete: to elevated temperature management II.B2.2.CP-57 containment; wall; (>150°F general; >200°F program, or XI.S2, II.B3.1.CP-65 basemat, concrete: local) "ASME Section II.B3.2.CP-108 basemat, concrete fill-in XI, Subsection annulus IWL," and/or AMP XI.S6, "Structures Monitoring,"

enhanced as necessary E 004 BWR Steel elements Loss of material due to AMP XI.S1, Yes (SRP-SLR II.B3.1.CP-113 (inaccessible areas): general, pitting, crevice "ASME Section XI, Section 3.5.2.2.1.3.1) drywell shell; drywell corrosion Subsection IWE,"

head and AMP XI.S4, "10 CFR Part 50, Appendix J"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 005 BWR/PWR Steel elements Loss of material due to AMP XI.S1, Yes (SRP-SLR II.A1.CP-98 (inaccessible areas): general, pitting, crevice "ASME Section XI, Section 3.5.2.2.1.3.1) II.A2.CP-98 liner; liner anchors; corrosion Subsection IWE," II.B1.2.CP-63 integral attachments, and AMP XI.S4, II.B2.1.CP-63 steel elements "10 CFR Part 50, II.B2.2.CP-63 (inaccessible areas): Appendix J" II.B3.2.CP-98 suppression chamber; drywell; drywell head; embedded shell; region shielded by diaphragm floor (as applicable)

E 006 BWR Steel elements: torus Loss of material due to AMP XI.S1, Yes (SRP-SLR II.B1.1.CP-48 shell general, pitting, crevice "ASME Section XI, Section 3.5.2.2.1.3.2) 25 corrosion Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J" E 007 BWR Steel elements: torus ring Loss of material due to AMP XI.S1, Yes (SRP-SLR II.B1.1.CP-109 girders; downcomers;, general, pitting, crevice "ASME Section XI, Section 3.5.2.2.1.3.3) II.B3.1.CP-158 Steel elements: corrosion Subsection IWE" suppression chamber shell (interior surface)

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 008 BWR/PWR Prestressing system: Loss of prestress due to TLAA, SRP-SLR Yes (SRP-SLR II.A1.C-11 tendons relaxation; shrinkage; Section 4.5, Section 3.5.2.2.1.4) II.B2.2.C-11 creep; elevated "Concrete temperature Containment Tendon Prestress," and/or SRP-SLR Section 4.7, "Other Plant-Specific Time-Limited Aging Analyses" M 009 BWR/PWR Metal liner, metal plate, Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR II.A3.C-13 personnel airlock, damage due to cyclic Section 4.6, Section 3.5.2.2.1.5) II.B1.1.C-21 26 equipment hatch, CRD loading (Only if CLB "Containment II.B2.1.C-45 hatch, penetration fatigue analysis exists) Liner Plate and II.B2.2.C-48 sleeves; penetration Penetration II.B4.C-13 bellows, steel elements: Fatigue Analysis" torus; vent line; vent header; vent line bellows; downcomers, suppression pool shell; unbraced downcomers, steel elements: vent header; downcomers E 010 BWR/PWR Penetration sleeves; Cracking due to SCC AMP XI.S1, Yes (SRP-SLR II.A3.CP-38 penetration bellows "ASME Section XI, Section 3.5.2.2.1.6) II.B4.CP-38 Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 011 BWR/PWR Concrete (inaccessible Loss of material (spalling, Plant-specific Yes (SRP-SLR II.A1.CP-147 areas): dome; wall; scaling) and cracking due aging Section 3.5.2.2.1.7) II.A2.CP-70 basemat; ring girders; to freeze-thaw management II.B3.2.CP-135 buttresses program, or XI.S2, "ASME Section XI, Subsection IWL," and/or AMP XI.S6, "Structures Monitoring,"

enhanced as necessary 27 M 012 BWR/PWR Concrete (inaccessible Cracking due to Plant-specific Yes (SRP-SLR II.A1.CP-67 areas): dome; wall; expansion from reaction aging Section 3.5.2.2.1.8) II.A2.CP-104 basemat; ring girders; with aggregates management II.B1.2.CP-99 buttresses, containment, program, or XI.S2, II.B2.2.CP-99 concrete fill-in annulus "ASME Section II.B3.1.CP-83 XI, Subsection II.B3.2.CP-121 IWL," and/or AMP XI.S6, "Structures Monitoring,"

enhanced as necessary D 013

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 014 BWR/PWR Concrete (inaccessible Increase in porosity and Plant-specific Yes (SRP-SLR II.A1.CP-102 areas): dome; wall; permeability; loss of aging Section 3.5.2.2.1.9) II.A2.CP-53 basemat; ring girders; strength due to leaching management II.B1.2.CP-110 buttresses, containment of calcium hydroxide and program, or XI.S2, II.B2.2.CP-110 carbonation "ASME Section II.B3.1.CP-53 XI, Subsection II.B3.2.CP-122 IWL," and/or AMP XI.S6, "Structures Monitoring,"

enhanced as necessary 28 D 015 M 016 BWR/PWR Concrete (accessible Increase in porosity and AMP XI.S2, No II.A1.CP-87 areas): basemat, permeability; cracking; "ASME Section XI, II.A2.CP-72 concrete: containment; loss of material (spalling, Subsection IWL," II.B1.2.CP-106 wall scaling) due to and/or AMP XI.S6, II.B2.2.CP-106 aggressive chemical "Structures II.B3.1.CP-72 attack Monitoring" D 017 M 018 BWR/PWR Concrete (accessible Loss of material (spalling, AMP XI.S2, No II.A1.CP-31 areas): dome; wall; scaling) and cracking due "ASME Section XI, II.A2.CP-51 basemat; ring girders; to freeze-thaw Subsection IWL," II.B3.2.CP-52 buttresses and/or AMP XI.S6, "Structures Monitoring"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 019 BWR/PWR Concrete (accessible Cracking due to AMP XI.S2, No II.A1.CP-33 areas): dome; wall; expansion from reaction "ASME Section XI, II.A2.CP-58 basemat; ring girders; with aggregates Subsection IWL," II.B1.2.CP-59 buttresses, containment; and/or AMP XI.S6, II.B2.2.CP-59 concrete fill-in annulus "Structures II.B3.1.CP-66 Monitoring" II.B3.2.CP-60 M 020 BWR/PWR Concrete (accessible Increase in porosity and AMP XI.S2, No II.A1.CP-32 areas): dome; wall; permeability; loss of "ASME Section XI, II.A2.CP-155 basemat; ring girders; strength due to leaching Subsection IWL" II.B1.2.CP-54 buttresses, containment of calcium hydroxide and II.B2.2.CP-54 carbonation II.B3.1.CP-156 II.B3.2.CP-55 29 E 021 BWR/PWR Concrete (accessible Cracking; loss of bond; AMP XI.S2, No II.A1.CP-68 areas): dome; wall; and loss of material "ASME Section XI, II.A2.CP-74 basemat; ring girders; (spalling, scaling) due to Subsection IWL," II.B1.2.CP-79 buttresses; reinforcing corrosion of embedded and/or AMP XI.S6, II.B2.2.CP-79 steel steel "Structures II.B3.1.CP-74 Monitoring" II.B3.2.CP-88 D 022 M 023 BWR/PWR Concrete (inaccessible Cracking; loss of bond; AMP XI.S2, No II.A1.CP-97 areas): basemat; and loss of material "ASME Section XI, II.A2.CP-75 reinforcing steel, dome; (spalling, scaling) due to Subsection IWL," II.B1.2.CP-80 wall corrosion of embedded and/or AMP XI.S6, II.B2.2.CP-80 steel "Structures II.B3.1.CP-75 Monitoring" II.B3.2.CP-89

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 024 BWR/PWR Concrete (inaccessible Increase in porosity and AMP XI.S2, No II.A1.CP-100 areas): dome; wall; permeability; cracking; "ASME Section XI, II.A2.CP-71 basemat; ring girders; loss of material (spalling, Subsection IWL," II.B3.1.CP-71 buttresses, concrete scaling) due to and/or AMP XI.S6, II.B3.2.CP-73 (accessible areas): aggressive chemical "Structures II.B3.2.CP-84 dome; wall; basemat attack Monitoring" D 025 026 BWR/PWR Moisture barriers Loss of sealing due to AMP XI.S1, No II.A3.CP-40 (caulking, flashing, and wear, damage, erosion, "ASME Section XI, II.B4.CP-40 other sealants) tear, surface cracks, other Subsection IWE" defects 30 M 027 BWR/PWR Metal liner, metal plate, Cracking due to cyclic AMP XI.S1, No II.A3.CP-37 airlock, equipment hatch, loading (CLB fatigue "ASME Section XI, II.B1.1.CP-49 CRD hatch; penetration analysis does not exist) Subsection IWE," II.B2.1.CP-107 sleeves; penetration and AMP XI.S4, II.B4.CP-37 bellows, steel elements: "10 CFR Part 50, torus; vent line; vent Appendix J" header; vent line bellows; downcomers, suppression pool shell 028 BWR/PWR Personnel airlock, Loss of material due to AMP XI.S1, No II.A3.C-16 equipment hatch, CRD general, pitting, crevice "ASME Section XI, II.B4.C-16 hatch corrosion Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 029 BWR/PWR Personnel airlock, Loss of leak tightness AMP XI.S1, No II.A3.CP-39 equipment hatch, CRD due to mechanical wear "ASME Section XI, II.B4.CP-39 hatch: locks, hinges, and Subsection IWE,"

closure mechanisms and AMP XI.S4, "10 CFR Part 50, Appendix J" 030 BWR/PWR Pressure-retaining bolting Loss of preload due to AMP XI.S1, No II.A3.CP-150 self-loosening "ASME Section XI, II.B4.CP-150 Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J" 31 031 BWR/PWR Pressure-retaining Loss of material due to AMP XI.S1, No II.A3.CP-148 bolting, steel elements: general, pitting, crevice "ASME Section XI, II.B1.2.CP-117 downcomer pipes corrosion Subsection IWE" II.B2.1.CP-117 II.B2.2.CP-117 II.B4.CP-148 032 BWR/PWR Prestressing system: Loss of material due to AMP XI.S2, No II.A1.C-10 tendons; anchorage corrosion "ASME Section XI, II.B2.2.C-10 components Subsection IWL" 033 BWR/PWR Seals and gaskets Loss of sealing due to AMP XI.S4, No II.A3.CP-41 wear, damage, erosion, "10 CFR Part 50, II.B4.CP-41 tear, surface cracks, other Appendix J "

defects 034 BWR/PWR Service Level I coatings Loss of coating or lining AMP XI.S8, No II.A3.CP-152 integrity due to blistering, "Protective II.B4.CP-152 cracking, flaking, peeling, Coating Monitoring delamination, rusting, or and Maintenance" physical damage

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 035 BWR/PWR Steel elements Loss of material due to AMP XI.S1, Yes (SRP-SLR II.A1.CP-35 (accessible areas): liner; general, pitting, crevice "ASME Section XI, Section 3.5.2.2.1.3.1) II.A2.CP-35 liner anchors; integral corrosion Subsection IWE," II.A3.CP-36 attachments, penetration and AMP XI.S4, II.B1.1.CP-43 sleeves, drywell shell; "10 CFR Part 50, II.B1.2.CP-46 drywell head; drywell Appendix J" II.B2.1.CP-46 shell in sand pocket II.B2.2.CP-46 regions; suppression II.B3.1.CP-43 chamber; drywell; II.B3.2.CP-35 embedded shell; region II.B4.CP-36 shielded by diaphragm floor (as applicable)

M 036 BWR Steel elements: drywell Loss of material due to AMP XI.S1, No II.B1.1.C-23 32 head; downcomers mechanical wear, "ASME Section XI, II.B1.2.C-23 including fretting Subsection IWE" II.B2.1.C-23 II.B2.2.C-23 037 BWR Steel elements: Loss of material due to AMP XI.S1, No II.B1.2.C-49 suppression chamber general (steel only), "ASME Section XI, II.B2.2.C-49 (torus) liner (interior pitting, crevice corrosion Subsection IWE,"

surface) and AMP XI.S4, "10 CFR Part 50, Appendix J" M 038 BWR Steel elements: Cracking due to SCC AMP XI.S1, Yes (SRP-SLR II.B3.1.C-24 suppression chamber "ASME Section XI, Section 3.5.2.2.1.6) II.B3.2.C-24 shell (interior surface) Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 039 BWR Steel elements: vent line Cracking due to SCC AMP XI.S1, Yes (SRP-SLR II.B1.1.CP-50 bellows "ASME Section XI, Section 3.5.2.2.1.6)

Subsection IWE,"

and AMP XI.S4, "10 CFR Part 50, Appendix J" 040 BWR Unbraced downcomers, Cracking due to cyclic AMP XI.S1, No II.B2.1.CP-142 steel elements: vent loading (CLB fatigue "ASME Section XI, II.B2.2.CP-64 header; downcomers analysis does not exist) Subsection IWE" E 041 BWR Steel elements: drywell None None No II.B1.1.CP-44 support skirt, steel II.B1.2.CP-114 elements (inaccessible II.B2.1.CP-114 33 areas): support skirt II.B2.2.CP-114 M 042 BWR/PWR Groups 1-3, 5, 7- 9: Loss of material (spalling, Plant-specific Yes (SRP-SLR III.A1.TP-108 concrete (inaccessible scaling) and cracking due aging Section 3.5.2.2.2.1.1) III.A2.TP-108 areas): foundation to freeze-thaw management III.A3.TP-108 program, or XI.S2, III.A5.TP-108 "ASME Section XI, III.A7.TP-108 Subsection IWL," III.A8.TP-108 and/or III.A9.TP-108 AMP XI.S6, "Structures Monitoring, enhanced as necessary "

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 043 BWR/PWR All Groups except Group Cracking due to Plant-specific Yes (SRP-SLR III.A1.TP-204 6: concrete (inaccessible expansion from reaction aging Section 3.5.2.2.2.1.2) III.A2.TP-204 areas): all with aggregates management III.A3.TP-204 program, or XI.S2, III.A4.TP-204 "ASME Section XI, III.A5.TP-204 Subsection IWL," III.A7.TP-204 and/or III.A8.TP-204 III.A9.TP-204 AMP XI.S6, "Structures Monitoring, enhanced as necessary "

34 E 044 BWR/PWR All Groups: concrete: all Cracking and distortion AMP XI.S6, Yes (SRP-SLR III.A1.TP-30 due to increased stress "Structures Section 3.5.2.2.2.1.3) III.A2.TP-30 levels from settlement Monitoring" III.A3.TP-30 III.A4.TP-30 III.A5.TP-30 III.A6.TP-30 III.A7.TP-30 III.A8.TP-30 III.A9.TP-30 D 045 E 046 BWR/PWR Groups 1-3, 5-9: Reduction of foundation AMP XI.S6, Yes (SRP-SLR III.A1.TP-31 concrete: foundation; strength and cracking due "Structures Section 3.5.2.2.2.1.3) III.A2.TP-31 subfoundation to differential settlement Monitoring" III.A3.TP-31 and erosion of porous III.A5.TP-31 concrete subfoundation III.A6.TP-31 III.A7.TP-31 III.A8.TP-31 III.A9.TP-31

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 047 BWR/PWR Groups 1-5, 7-9: concrete Increase in porosity and Plant-specific Yes (SRP-SLR III.A1.TP-67 (inaccessible areas): permeability; loss of aging Section 3.5.2.2.2.1.4) III.A2.TP-67 exterior above- and strength due to leaching management III.A3.TP-67 below-grade; foundation of calcium hydroxide and program, or XI.S2, III.A4.TP-305 carbonation "ASME Section XI, III.A5.TP-67 Subsection IWL," III.A7.TP-67 and/or III.A8.TP-67 III.A9.TP-67 AMP XI.S6, "Structures Monitoring, enhanced as necessary "

35 M 048 BWR/PWR Groups 1-5: concrete: all Reduction of strength and Plant-specific Yes (SRP-SLR III.A1.TP-114 modulus due to elevated aging Section 3.5.2.2.2.2) III.A2.TP-114 temperature (>150°F management III.A3.TP-114 general; >200°F local) program, or XI.S2, III.A4.TP-114 "ASME Section XI, III.A5.TP-114 Subsection IWL,"

and/or AMP XI.S6, "Structures Monitoring, enhanced as necessary "

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 049 BWR/PWR Groups 6 - concrete Loss of material (spalling, Plant-specific Yes (SRP-SLR III.A6.TP-110 (inaccessible areas): scaling) and cracking due aging Section 3.5.2.2.2.3.1) exterior above- and to freeze-thaw management below-grade; foundation; program, or XI.S2, interior slab "ASME Section XI, Subsection IWL,"

and/or AMP XI.S6, "Structures Monitoring, enhanced as necessary "

36 M 050 BWR/PWR Groups 6: concrete Cracking due to Plant-specific Yes (SRP-SLR III.A6.TP-220 (inaccessible areas): all expansion from reaction aging Section 3.5.2.2.2.3.2) with aggregates management program, or XI.S2, "ASME Section XI, Subsection IWL,"

and/or AMP XI.S6, "Structures Monitoring, enhanced as necessary "

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 051 BWR/PWR Groups 6: concrete Increase in porosity and Plant-specific Yes (SRP-SLR III.A6.TP-109 (inaccessible areas): permeability; loss of aging Section 3.5.2.2.2.3.3) exterior above- and strength due to leaching management below-grade; foundation; of calcium hydroxide and program, or XI.S2, interior slab carbonation "ASME Section XI, Subsection IWL,"

and/or AMP XI.S6, "Structures Monitoring, enhanced as necessary "

37 E 052 BWR/PWR Groups 7, 8 - steel Cracking due to SCC; Plant-specific Yes (SRP-SLR III.A7.T-23 components: tank liner Loss of material due to aging Section 3.5.2.2.2.4) III.A8.T-23 pitting and crevice management corrosion program M 053 BWR/PWR Support members; welds; Cumulative fatigue TLAA, SRP-SLR Yes (SRP-SLR III.B1.1.T-26 bolted connections; damage due to cyclic Section 4.3 "Metal Section 3.5.2.2.2.5) III.B1.2.T-26 support anchorage to loading (Only if CLB Fatigue," and/or III.B1.3.T-26 building structure fatigue analysis exists) Section 4.7 "Other Plant-Specific Time-Limited Aging Analyses"

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 054 BWR/PWR All groups except 6: Cracking due to AMP XI.S6, No III.A1.TP-25 concrete (accessible expansion from reaction "Structures III.A2.TP-25 areas): all with aggregates Monitoring" III.A3.TP-25 III.A4.TP-25 III.A5.TP-25 III.A6.TP-25 III.A7.TP-25 III.A8.TP-25 III.A9.TP-25 055 BWR/PWR Building concrete at Reduction in concrete AMP XI.S6, No III.B1.1.TP-42 locations of expansion anchor capacity due to "Structures III.B1.2.TP-42 and grouted anchors; local concrete Monitoring" III.B1.3.TP-42 grout pads for support degradation/ service- III.B2.TP-42 38 base plates induced cracking or other III.B3.TP-42 concrete aging III.B4.TP-42 mechanisms III.B5.TP-42 E 056 BWR/PWR Concrete: exterior above- Loss of material due to AMP XI.S7, No III.A6.T-20 and below- grade; abrasion; cavitation "Inspection of foundation; interior slab Water-Control Structures Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 057 BWR/PWR Constant and variable Loss of mechanical AMP XI.S3, No III.B1.1.T-28 load spring hangers; function due to corrosion, "ASME Section XI, III.B1.2.T-28 guides; stops distortion, dirt or debris Subsection IWF" III.B1.3.T-28 accumulation, overload, wear E 058 BWR/PWR Earthen water-control Loss of material; loss of AMP XI.S7, No III.A6.T-22 structures: dams; form due to erosion, "Inspection of embankments; settlement, Water-Control reservoirs; channels; sedimentation, frost Structures canals and ponds action, waves, currents, Associated with surface runoff, seepage Nuclear Power Plants" or the FERC/US Army 39 Corp of Engineers dam inspections and maintenance programs.

E 059 BWR/PWR Group 6: concrete Cracking; loss of bond; AMP XI.S7, No III.A6.TP-38 (accessible areas): all and loss of material "Inspection of (spalling, scaling) due to Water-Control corrosion of embedded Structures steel Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 060 BWR/PWR Group 6: concrete Loss of material (spalling, AMP XI.S7, No III.A6.TP-36 (accessible areas): scaling) and cracking due "Inspection of exterior above- and to freeze-thaw Water-Control below-grade; foundation Structures Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

E 061 BWR/PWR Group 6: concrete Increase in porosity and AMP XI.S7, No III.A6.TP-37 40 (accessible areas): permeability; loss of "Inspection of exterior above- and strength due to leaching Water-Control below-grade; foundation; of calcium hydroxide and Structures interior slab carbonation Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 062 BWR/PWR Group 6: Wooden Piles; Loss of material; change AMP XI.S7, No III.A6.TP-223 sheeting in material properties due "Inspection of to weathering, chemical Water-Control degradation, and insect Structures infestation repeated Associated with wetting and drying, fungal Nuclear Power decay Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

063 BWR/PWR Groups 1-3, 5, 7-9: Increase in porosity and AMP XI.S6, No III.A1.TP-24 41 concrete (accessible permeability; loss of "Structures III.A2.TP-24 areas): exterior above- strength due to leaching Monitoring" III.A3.TP-24 and below-grade; of calcium hydroxide and III.A5.TP-24 foundation carbonation III.A7.TP-24 III.A8.TP-24 III.A9.TP-24 064 BWR/PWR Groups 1-3, 5, 7-9: Loss of material (spalling, AMP XI.S6, No III.A1.TP-23 concrete (accessible scaling) and cracking due "Structures III.A2.TP-23 areas): exterior above- to freeze-thaw Monitoring" III.A3.TP-23 and below-grade; III.A5.TP-23 foundation III.A7.TP-23 III.A8.TP-23 III.A9.TP-23

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item 065 BWR/PWR Groups 1-3, 5, 7-9: Cracking; loss of bond; AMP XI.S6, No III.A1.TP-212 concrete (inaccessible and loss of material "Structures III.A1.TP-27 areas): below-grade (spalling, scaling) due to Monitoring" III.A2.TP-212 exterior; foundation, corrosion of embedded III.A2.TP-27 Groups 1-3, 5, 7-9: steel III.A3.TP-212 concrete (accessible III.A3.TP-27 areas): below-grade III.A5.TP-212 exterior; foundation, III.A5.TP-27 Groups 6: concrete III.A6.TP-104 (inaccessible areas): all III.A7.TP-212 III.A7.TP-27 III.A8.TP-212 III.A8.TP-27 III.A9.TP-212 42 III.A9.TP-27 066 BWR/PWR Groups 1-5, 7, 9: Cracking; loss of bond; AMP XI.S6, No III.A1.TP-26 concrete (accessible and loss of material "Structures III.A2.TP-26 areas): interior and (spalling, scaling) due to Monitoring" III.A3.TP-26 above-grade exterior corrosion of embedded III.A4.TP-26 steel III.A5.TP-26 III.A7.TP-26 III.A9.TP-26

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item 067 BWR/PWR Groups 1-5, 7, 9: Increase in porosity and AMP XI.S6, No III.A1.TP-28 Concrete: interior; permeability; cracking; "Structures III.A1.TP-29 above-grade exterior, loss of material (spalling, Monitoring" III.A2.TP-28 Groups 1-3, 5, 7 scaling) due to III.A2.TP-29 concrete (inaccessible aggressive chemical III.A3.TP-28 areas): below-grade attack III.A3.TP-29 exterior; foundation, III.A4.TP-28 Group 6: concrete III.A5.TP-28 (inaccessible areas): all III.A5.TP-29 III.A6.TP-107 III.A7.TP-28 III.A7.TP-29 III.A8.TP-29 III.A9.TP-28 43 III.A9.TP-29 M 068 BWR/PWR High-strength steel Cracking due to SCC AMP XI.S3, No III.B1.1.TP-41 structural bolting "ASME Section XI, Subsection IWF" D 069 070 BWR/PWR Masonry walls: all Cracking due to restraint AMP XI.S5, No III.A1.T-12 shrinkage, creep, "Masonry Walls" III.A2.T-12 aggressive environment III.A3.T-12 III.A5.T-12 III.A6.T-12 M 071 BWR/PWR Masonry walls: all Loss of material (spalling, AMP XI.S5, No III.A1.TP-34 scaling) and cracking due "Masonry Walls" III.A2.TP-34 to freeze-thaw III.A3.TP-34 III.A5.TP-34 III.A6.TP-34

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 072 BWR/PWR Seals; gasket; moisture Loss of sealing due to AMP XI.S6, No III.A6.TP-7 barriers (caulking, wear, damage, erosion, "Structures flashing, and other tear, surface cracks, other Monitoring" sealants) defects 073 BWR/PWR Service Level I coatings Loss of coating or lining AMP XI.S8, No III.A4.TP-301 integrity due to blistering, "Protective cracking, flaking, peeling, Coating Monitoring delamination, rusting, or and Maintenance" physical damage M 074 BWR/PWR Sliding support bearings; Loss of mechanical AMP XI.S6, No III.B2.TP-46 sliding support surfaces function due to corrosion, "Structures III.B2.TP-47 distortion, dirt or debris Monitoring" III.B4.TP-46 44 accumulation, overload, III.B4.TP-47 wear M 075 BWR/PWR Sliding surfaces Loss of mechanical AMP XI.S3, No III.B1.1.TP-45 function due to corrosion, "ASME Section XI, III.B1.2.TP-45 distortion, dirt or debris Subsection IWF" III.B1.3.TP-45 accumulation, overload, wear M 076 BWR/PWR Sliding surfaces: radial Loss of mechanical AMP XI.S6, No III.A4.TP-35 beam seats in BWR function due to corrosion, "Structures drywell distortion, dirt or debris Monitoring" accumulation, overload, wear

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item E 077 BWR/PWR Steel components: all Loss of material due to AMP XI.S6, No III.A1.TP-302 structural steel corrosion "Structures III.A2.TP-302 Monitoring" III.A3.TP-302 III.A4.TP-302 III.A5.TP-302 III.A7.TP-302 III.A8.TP-302 M 078 BWR/PWR Stainless steel fuel pool Cracking due to SCC; AMP XI.M2, No III.A5.T-14 liner Loss of material due to "Water Chemistry,"

pitting and crevice and monitoring of corrosion the spent fuel pool water level and leakage from the 45 leak chase channels.

079 BWR/PWR Steel components: piles Loss of material due to AMP XI.S6, No III.A3.TP-219 corrosion "Structures Monitoring" 080 BWR/PWR Structural bolting Loss of material due to AMP XI.S6, No III.A1.TP-248 general, pitting, crevice "Structures III.A2.TP-248 corrosion Monitoring" III.A3.TP-248 III.A4.TP-248 III.A5.TP-248 III.A6.TP-248 III.A7.TP-248 III.A8.TP-248 III.A9.TP-248 III.B2.TP-248 III.B3.TP-248 III.B4.TP-248 III.B5.TP-248

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item 081 BWR/PWR Structural bolting Loss of material due to AMP XI.S3, No III.B1.1.TP-226 general, pitting, crevice "ASME Section XI, III.B1.2.TP-226 corrosion Subsection IWF" III.B1.3.TP-226 082 BWR/PWR Structural bolting Loss of material due to AMP XI.S6, No III.A1.TP-274 general, pitting, crevice "Structures III.A2.TP-274 corrosion Monitoring" III.A3.TP-274 III.A4.TP-274 III.A5.TP-274 III.A7.TP-274 III.A8.TP-274 III.A9.TP-274 III.B2.TP-274 III.B3.TP-274 46 III.B4.TP-274 III.B5.TP-274 E 083 BWR/PWR Structural bolting Loss of material due to AMP XI.S7, No III.A6.TP-221 general, pitting, crevice "Inspection of corrosion Water-Control Structures Associated with Nuclear Power Plants" or the FERC/US Army Corp of Engineers dam inspections and maintenance programs.

D 084

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 085 BWR/PWR Structural bolting Loss of material due to AMP XI.M2, No III.B1.1.TP-232 pitting, crevice corrosion "Water Chemistry," III.B1.2.TP-232 and AMP XI.S3, III.B1.3.TP-232 "ASME Section XI, Subsection IWF" 086 BWR/PWR Structural bolting Loss of material due to AMP XI.S3, No III.B1.1.TP-235 pitting, crevice corrosion "ASME Section XI, III.B1.2.TP-235 Subsection IWF" III.B1.3.TP-235 087 BWR/PWR Structural bolting Loss of preload due to AMP XI.S3, No III.B1.1.TP-229 self-loosening "ASME Section XI, III.B1.2.TP-229 Subsection IWF" III.B1.3.TP-229 47 088 BWR/PWR Structural bolting Loss of preload due to AMP XI.S6, No III.A1.TP-261 self-loosening "Structures III.A2.TP-261 Monitoring" III.A3.TP-261 III.A4.TP-261 III.A5.TP-261 III.A6.TP-261 III.A7.TP-261 III.A8.TP-261 III.A9.TP-261 III.B2.TP-261 III.B3.TP-261 III.B4.TP-261 III.B5.TP-261

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item 089 PWR Support members; welds; Loss of material due to AMP XI.M10, No III.B1.1.T-25 bolted connections; boric acid corrosion "Boric Acid III.B1.1.TP-3 support anchorage to Corrosion" III.B1.2.T-25 building structure III.B1.3.TP-3 III.B1.2.TP-3 III.B2.T-25 III.B2.TP-3 III.B3.T-25 III.B3.TP-3 III.B4.T-25 III.B4.TP-3 III.B5.T-25 III.B5.TP-3 48 E 090 BWR/PWR Support members; welds; Loss of material due to AMP XI.M2, No III.B1.1.TP-10 bolted connections; general (steel only), "Water Chemistry,"

support anchorage to pitting, crevice corrosion and AMP XI.S3, building structure "ASME Section XI, Subsection IWF" 091 BWR/PWR Support members; welds; Loss of material due to AMP XI.S3, No III.B1.1.T-24 bolted connections; general, pitting corrosion "ASME Section XI, III.B1.2.T-24 support anchorage to Subsection IWF" III.B1.3.T-24 building structure 092 BWR/PWR Support members; welds; Loss of material due to AMP XI.S6, No III.B2.TP-43 bolted connections; general, pitting corrosion "Structures III.B3.TP-43 support anchorage to Monitoring" III.B4.TP-43 building structure III.B5.TP-43 M 093 BWR/PWR Galvanized steel support Loss of material due to AMP XI.S6, No III.B2.TP-6 members; welds; bolted pitting, crevice corrosion "Structures III.B4.TP-6 connections; support Monitoring" anchorage to building structure

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item M 094 BWR/PWR Vibration isolation Reduction or loss of AMP XI.S3, No III.B1.1.T-33 elements isolation function due to "ASME Section XI, III.B1.2.T-33 radiation hardening, Subsection IWF," III.B1.3.T-33 temperature, humidity, and/or AMP XI.S6, III.B4.TP-44 sustained vibratory "Structures loading Monitoring" E 095 BWR/PWR Galvanized steel support None None No III.B1.1.TP-8 members; welds; bolted III.B1.2.TP-8 connections; support III.B1.3.TP-8 anchorage to building III.B2.TP-8 structure III.B3.TP-8 III.B4.TP-8 III.B5.TP-8 49 N 096 BWR/PWR Groups 6: concrete Cracking due to AMP XI.S7, No III.A6.T-34 (accessible areas): all expansion from reaction "Inspection of with aggregates Water-Control Structures Associated with Nuclear Power Plants" N 097 BWR/PWR Group 4: Concrete Reduction of strength; Plant-specific Yes (SRP-SLR III.A4.T-35 (reactor cavity area loss of mechanical aging Section 3.5.2.2.2.6) proximate to the reactor properties due to management vessel): reactor irradiation (i.e., radiation program or plant-(primary/biological) shield interactions with material specific wall; sacrificial shield and radiation-induced enhancements to wall; reactor vessel heating) selected AMPs support/pedestal structure

Table 3.5.1-1 Summary of Aging Management Programs for Containments, Structures and Component Supports Evaluated in Chapters II and III of the GALL-SLR Report New, Aging Modified, Management Deleted, Aging Program Further Evaluation GALL-SLR Edited Item ID Type Component Effect/Mechanism (AMP)/TLAA Recommended Item N 098 BWR/PWR Stainless steel, aluminum None None No III.B1.1.TP-4 alloy support members; III.B1.2.TP-4 welds; bolted III.B1.3.TP-4 connections; support III.B2.TP-4 anchorage to building III.B3.TP-4 structure III.B4.TP-4 III.B5.TP-4 N 099 BWR/PWR Aluminum, stainless steel Loss of material due to AMP XI.M32, Yes (SRP-SLR III.B1.1.T-36a support members; welds; pitting and crevice "One-Time Section 3.5.2.2.2.4) III.B1.1.T-36b bolted connections; corrosion, cracking due to Inspection," III.B1.1.T-36c support anchorage to SCC AMP XI.S3, III.B1.2.T-36a building structure "ASME Section XI, III.B1.2.T-36b Subsection IWF," III.B1.2.T-36c 50 or AMP XI.M36, III.B1.3.T-36a "External Surfaces III.B1.3.T-36b Monitoring of III.B1.3.T-36c Mechanical Components" N 100 BWR/PWR Aluminum, stainless steel Loss of material due to AMP XI.M32, Yes (SRP-SLR III.B2.T-37a support members; welds; pitting and crevice "One-Time Section 3.5.2.2.2.4) III.B2.T-37b bolted connections; corrosion, cracking due to Inspection," III.B2.T-37c support anchorage to SCC AMP XI.S6, III.B3.T-37a building structure "Structures III.B3.T-37b Monitoring," or III.B3.T-37c AMP XI.M36, III.B4.T-37a "External Surfaces III.B4.T-37b Monitoring of III.B4.T-37c Mechanical III.B5.T-37a Components" III.B5.T-37b III.B5.T-37c

Table 3.5.1-2 AMPs and Additional Guidance Appendices Recommended for Containments, Structures, and Component Supports GALL-SLR Report Chapter/AMP Program Name AMP XI.M2 Water Chemistry AMP XI.M10 Boric Acid Corrosion AMP XI.M32 One-Time Inspection AMP XI.M36 External Surfaces Monitoring of Mechanical Components AMP XI.S1 ASME Section XI, Subsection IWE AMP XI.S2 ASME Section XI, Subsection IWL AMP XI.S3 ASME Section XI, Subsection IWF AMP XI.S4 10 CFR Part 50, Appendix J AMP XI.S5 Masonry Walls AMP XI.S6 Structures Monitoring AMP XI.S7 Inspection of Water-Control Structures Associated with Nuclear Power Plants AMP XI.S8 Protective Coating Monitoring and Maintenance GALL-SLR Report Appendix A Quality Assurance for Aging Management Programs GALL-SLR Report Appendix B Operating Experience for Aging Management Programs SRP-SLR Appendix A.1 Aging Management ReviewGeneric (Branch Technical Position RLSB-1) 51

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ML20049H361

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