ML11349A093

New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS00146A, Generic Aging Lessons Learned (GALL) Report Summary

ML11349A093
Person / Time
Site:	Indian Point
Issue date:	09/30/2005
From:	Office of Nuclear Reactor Regulation
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21545, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 NUREG-1801, Vol. 1, Rev. 1
Download: ML11349A093 (323)

Text

NYS00146A Submitted: December 15, 2011 NUREG-1801, Vol. 1 , Rev. 1 Generic Aging Lessons Learned (GALL) Report Summary Manuscript Completed: September 2005 Date Published: September 2005 Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 OAGI0000203_001

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ABSTRACT NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is referenced as a technical basis document in N UREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR). The GALL Report identifies aging management programs (AMP), which were determined to be acceptable programs to manage the aging effects of systems, structures and components (SSC) in the scope of license renewal, as required by 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."

The GALL Report is split into two volumes. Volume 1 summarizes the aging management reviews that are discussed in Volume 2. Volume 2 lists generic aging management reviews (AMRs) of SSC that may be in the scope of License Renewal Applications (LRAs) and identifies GALL AM Ps that are acceptable to manage the listed aging effects. Revision 1 of the GALL Report incorporates changes based on experience gained from numerous NRC staff reviews of LRAs and other insights identified by stakeholders.

Ifan LRA references the GALL Report as the approach used to manage aging effect(s), the NRC staff will use the GALL Report as a basis for the LRA assessment consistent with guidance specified in the SRP-LR.

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TABLE OF CONTENTS Page ABSTRACT ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... iii LIST OF CONTRIBUTORS - 2004-2005 ................................................................................. vi ABBREVIATIONS ..................................................................................................................... viii INTRODUCTION .................................................................................................................... .

BACKGROUND ....................................................................................................................... .

OVERVIEW OF THE GALL REPORT EVALUATION PROCESS ......................................... 2 APPLICATION OF THE GALL REPORT ................................................................................ 3 APPENDIX: LISTING OF PLANT SYSTEMS EVALUATED IN THE GALL REPORT (VOLUME 2) ...................................................................... A-1 LIST OF TABLES Table 1. Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of the GALL Report. ... ... ... ... ... ... ... ... ... ... ... ... ... .... 7 Table 2. Summary of Aging Management Programs for the Engineered Safety Features Evaluated in Chapter V of the GALL Report ... ... ... ... ... ... ... ... ... .... 31 Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report. ... ... ... ... ... ... ... ... ... ... ... ... .... 47 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Evaluated in Chapter VIII of the GALL Report ...................... 67 Table 5. Summary of Aging Management Programs for the Structures and Component Supports Evaluated in Chapters II and III of the GALL Report. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... 77 Table 6. Summary of Aging Management Programs for the Electrical Components Evaluated in Chapter VI of the GALL Report. ... ... ... ... ... ... ... ... ... ... .... 93 September 2005 v NUREG-1801 Vol. 1. Rev. 1 OAGI0000203_005

LIST OF CONTRIBUTORS License Renewal and Environmental Programs Section of Division of Regulatorv Improvement Programs, Office of Nuclear Reactor Regulation P.T. Kuo Program Director S. Lee Section Chief S. West Section Chief J. Zimmerman Section Chief J. Dozier Team Leader K. Chang Mechanical Engineering K. Cozens Materials Engineering G. Cranston Reactor Systems Engineering D. Guha Systems Engineering M. Heath Mechanical Engineering S. Hoffman Mechanical Engineering A. Hull Materials Engineering K. Hsu Materials Engineering M. Lintz Mechanical Engineering D. Merzke Mechanical Engineering K. Naidu Reactor Engineering J. Rajan Mechanical Engineering R. Subbaratnam Mechanical Engineering T. Terry Civil Engineering L. Tran Electrical Engineering P.Wen Electrical Engineering Office of Nuclear Reactor Regulation T. Chan Section Chief S.Coffin Section Chief S. Jones Section Chief R. Jenkins Section Chief L. Lund Section Chief R. Karas Section Chief K. Manoly Section Chief M. Mitchell Section Chief J. Nakoski Section Chief D. Terao Section Chief S. Weerakkody Section Chief H. Ashar Structural Engineering S. Bailey Mechanical Engineering T. Cheng Structural Engineering R. Davis Materials Engineering B. Elliot Materials Engineering J. Fair Mechanical Engineering G. Georgiev Materials Engineering NUREG-1801 Vol. 1, Rev. 1 vi September 2005 OAGI0000203_006

LIST OF CONTRIBUTORS (continued)

A. Keim Materials Engineering N. Iqbal Fire Protection Engineering D. Jeng Structural Engineering K. Karwoski Materials Engineering C. Lauron Chemical Engineering L. Lois Reactor Systems Engineering Y.Li Mechanical Engineering R. McNally Mechanical Engineering J. Medoff Materials Engineering D. Nguyen Electrical Engineering A. Pal Electrical Engineering K. Parczewski Chemical Engineering J. Strnisha Mechanical Engineering P. Shemanski Electrical Engineering Office of Nuclear Regulatory Research A. Hiser Section Chief J. Vora Team Leader J. Davis Materials Engineering P. Kang Electrical Engineering Parallax, Inc A. Baione Team Leader M. Bowman Mechanical Engineering D. Jones Programming K. Larsen Technical Editing E. Patel Mechanical Engineering R. Wells License Engineering September 2005 vii NUREG-1801 Vol. 1, Rev. 1 OAGI0000203_007

ABBREVIATIONS ADS automatic depressurization system AFW auxiliary feedwater AMP aging management program ASME American Society of Mechanical Engineers B&W Babcock & Wilcox BWR boiling water reactor BWRVIP boiling water reactor vessel internals project CASS cast austenitic stainless steel CE Combustion Engineering CEA control element assembly CFR Code of Federal Regulations CFS core flood system CLB current licensing basis CRD control rod drive CRGT control rod guide tube CS carbon steel CVCS chemical and volume control system DHR decay heat removal DSCSS drywell and suppression chamber spray system ECCS emergency core cooling system EDG emergency diesel generator EQ environmental qualification FW feedwater GALL generic aging lessons learned HP high pressure HPCI high-pressure coolant injection HPCS high-pressure core spray HPSI high-pressure safety injection HVAC heating, ventilation, and air conditioning IASCC irradiation-assisted stress corrosion cracking IGA intergranular attack IGSCC intergranular stress corrosion cracking IR insulation resistance IRM intermediate range monitor lSI inservice inspection LER licensee event report LG lower grid NUREG-1801 Vol. 1, Rev. 1 viii September 2005 OAGI0000203_008

ABBREVIATIONS (continued)

LP low pressure LPCI low-pressure coolant injection LPCS low-pressure core spray LPRM low-power range monitor LPSI low-pressure safety injection MIC microbiologically influenced corrosion MSR moisture separatorireheater NEI Nuclear Energy Institute NPAR Nuclear Plant Aging Research NPS nominal pipe size NRC Nuclear Regulatory Commission NSSS nuclear steam supply system NUMARC Nuclear Management and Resources Council ODSCC outside diameter stress corrosion cracking PWR pressurized water reactor PWSCC primary water stress corrosion cracking QA quality assurance RCCA rod control cluster assembly RCIC reactor core isolation cooling RCP reactor coolant pump RCPB reactor coolant pressure boundary RCS reactor coolant system RG Regulatory Guide RHR residual heat removal RWC reactor water cleanup RWT refueling water tank SBO station blackout SC suppression chamber SCC stress corrosion cracking SDC shutdown cooling SFP spent fuel pool SG steam generator SLC standby liquid control SRM source range monitor SRM staff requirement memorandum SRP-LR Standard Review Plan for License Renewal TLAA time-limited aging analysis UCS Union of Concerned Scientists UV ultraviolet September 2005 ix NUREG-1801 Vol. 1, Rev. 1 OAGI0000203_009

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INTRODUCTION NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is referenced as a technical basis document in N UREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" (SRP-LR). The GALL Report identifies aging management programs (AMP) that were determined to be acceptable to manage aging effects of systems, structures and components (SSC) in the scope of license renewal, as required by 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."

The GALL Report is comprised of two volumes. Volume 1 summarizes the aging management reviews that are discussed in Volume 2. Volume 2 lists generic aging management reviews (AMRs) of SSCs that may be in the scope of license renewal applications (LRAs) and identifies GALL AMPs that are acceptable to manage the aging effects.

Wan LRA references the GALL Report as the approach used to manage aging effect(s), the NRC staff will use the GALL Report as a basis for the LRA assessment consistent with guidance specified in the SRP-LR.

BACKGROUND Revision 0 of the GALL Report By letter dated March 3,1999, the Nuclear Energy Institute (NEI) documented the industry's views on how existing plant programs and activities should be credited for license renewal. The issue can be summarized as follows: To what extent should the staff review existing programs relied on for license renewal in determining whether an applicant has demonstrated reasonable assurance that such programs will be effective in managing the effects of aging on the functionality of structures and components during the period of extended operation? In a staff paper, SECY-99-148, "Credit for Existing Programs for License Renewal," dated June 3, 1999, the staff described options for crediting existing programs and recommended one option that the staff believed would improve the efficiency of the license renewal process.

By staff requirements memorandum (SRM), dated August 27,1999, the Commission approved the staff's recommendation and directed the staff to focus the staff review guidance in the Standard Review Plan for License Renewal (SRP-LR) on areas where existing programs should be augmented for license renewal. The staff would develop a "Generic Aging Lessons Learned (GALL)" report to document the staff's evaluation of generic existing programs. The GALL Report would document the staff's basis for determining which existing programs are adequate without modification and which existing programs should be augmented for license renewal. The GALL Report would be referenced in the SRP-LR as a basis for determining the adequacy of existing programs.

This report builds on a previous report, NUREG/CR-6490, "Nuclear Power Plant Generic Aging Lessons Learned (GALL)," which is a systematic compilation of plant aging information. This report extends the information in NUREG/CR-6490 to provide an evaluation of the adequacy of aging management programs for license renewal. The NU REG/CR-6490 report was based on information in over 500 documents: Nuclear Plant Aging Research (NPAR) program reports sponsored by the Office of Nuclear Regulatory Research, Nuclear Management and Resources Council (NUMARC, now NEI) industry reports addressing license renewal for major structures and components, licensee event reports (LERs), information notices, generic letters, and September 2005 NUREG-1801 Vol. 1, Rev. 1 OAGI0000203_011

bulletins. The staff has also considered information contained in the reports provided by the Union of Concerned Scientists (UCS) in a letter dated May 5, 2000.

Following the general format of N U R EG-0800 for major plant sections except for refueling water, chilled water, residual heat removal, condenser circulating water, and condensate storage system in pressurized water reactor (PWR) and boiling water reactor (BWR) power plants, the staff has reviewed the aging effects on components and structures, identified the relevant existing programs, and evaluated program attributes to manage aging effects for license renewal. This report was prepared with the technical assistance of Argonne National Laboratory and Brookhaven National Laboratory. As directed in the SRM, this report has the benefit of the experience of the staff members who conducted the review of the initial license renewal applications. Also, as directed in the SRM, the staff has sought stakeholders' participation in the development of this report. The staff held many public meetings and workshops to solicit input from the public. The staff also requested comments from the public on the draft improved license renewal guidance documents, including the GALL Report, in the Federal Register Notice, Vol. 65, No. 170, August 31, 2000. The staff's analysis of stakeholder comments is documented in NUREG-1739. These documents can be found on-line at:

http://www.nrc.gov/reading-rm/doc-collections/.

Revision 1 of the GALL Report The GALL Report has been referenced in numerous license renewal applications (LRA) as a basis for aging management reviews to satisfy the regulatory criteria contained in 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," Section 54.21, "Contents of application - technical information." Based on lessons learned from these reviews, and other public input, including industry comments, the NRC staff proposed changes to the GALL Report to make the GALL Report more efficient. A preliminary version of Revision 1 of the GALL Report was posted on the NRC public web page on September 30,2004. The draft revisions of GALL Vol. 1 and Vol. 2 were further refined and issued for public comment on January 31, 2005. In addition, the staff also held public meetings with stakeholders to facilitate dialog and to discuss comments. The staff subsequently took into consideration comments received (see NUREG-1832) and incorporated its dispositions into the September 2005 version of the GALL Report.

OVERVIEW OF THE GALL REPORT EVALUATION PROCESS The results of the GALL effort are presented in a table format in the GALL Report, Volume 2.

The table column headings are: Item, Structure and/or Component; Material, Environment; Aging Effect/Mechanism; Aging Management Program (AMP); and Further Evaluation. The staff's evaluation of the adequacy of each generic aging management program in managing certain aging effects for particular structures and components is based on its review of the following 10 program elements in each aging management program:

AMP Element Description

1. Scope of the program The scope of the program should include the specific structures and components subject to an aging management review.

2. Preventive actions Preventive actions should mitigate or prevent the applicable aging effects.

3. Parameters monitored or Parameters monitored or inspected should be linked to the inspected effects of aging on the intended functions of the particular NUREG-1801 Vol. 1, Rev. 1 2 Septem ber 2005 OAGI0000203_012

AMP Element Description structure and component.

4. Detection of aging effects Detection of aging effects should occur before there is a loss of any structure and component intended function. This includes aspects such as method or technique (i.e., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new/one-time inspections to ensure timely detection of aging effects.

5. Monitoring and trending Monitoring and trending should provide for prediction of the extent of the effects of aging and timely corrective or mitigative actions.

6. Acceptance criteria Acceptance criteria, against which the need for corrective action will be evaluated, should ensure that the particular structure and component intended functions are maintained under all current licensing basis (CLB) design conditions during the period of extended operation.

7. Corrective actions Corrective actions, including root cause determination and prevention of recurrence, should be timely.

8. Confirmation process The confirmation process should ensure that preventive actions are adequate and appropriate corrective actions have been com pleted and are effective.

9. Administrative controls Administrative controls should provide a formal review and approval process.

10. Operating experience Operating experience involving the aging management program, including past corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support a determination that the effects of aging will be adequately managed so that the structure and component intended functions will be maintained during the period of extended operation.

If, on the basis of its evaluation, the staff determined that a program is adequate to manage certain aging effects for a particular structure or component without change, the "Further Evaluation" entry would indicate that no further evaluation is recommended for license renewal.

Chapter XI of the GALL Report, Volume 2, contains the staff's evaluation of generic aging management programs that are relied on in the GALL Report, such as the ASME Section XI inservice inspection, water chemistry, or structures monitoring program.

APPLICATION OF THE GALL REPORT The GALL Report is a technical basis document to the SRP-LR, which provides the staff with guidance in reviewing a license renewal application. The GALL Report should be treated in the same manner as an approved topical report that is generically applicable. An applicant may reference the GALL Report in a license renewal application to demonstrate that the programs at the applicant's facility correspond to those reviewed and approved in the GALL Report.

If an applicant takes credit for a program in GALL, it is incumbent on the applicant to ensure that the plant program contains all the elements of the referenced GALL program. In addition, the conditions at the plant must be bounded by the conditions for which the GALL program was evaluated. The above verifications must be documented on-site in an auditable form. The applicant must include a certification in the license renewal application that the verifications have been completed.

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The GALL Report contains one acceptable way to manage aging effects for license renewal. An applicant may propose alternatives for staff review in its plant-specific license renewal application. Use of the GALL Report is not required, but its use should facilitate both preparation of a license renewal application by an applicant and timely, uniform review by the NRC staff.

In addition, the GALL Report does not address scoping of structures and components for license renewal. Scoping is plant specific, and the results depend on the plant design and current licensing basis. The inclusion of a certain structure or component in the GALL Report does not mean that this particular structure or component is within the scope of license renewal for all plants. Conversely, the omission of a certain structure or component in the GALL Report does not mean that this particular structure or component is not within the scope of license renewal for any plants.

The GALL Report contains an evaluation of a large number of structures and components that may be in the scope of a typical LRA. The evaluation results documented in the GALL Report indicate that many existing, typical generic aging management programs are adequate to manage aging effects for particular structures or components for license renewal without change. The GALL Report also contains recommendations on specific areas for which generic existing programs should be augmented (require further evaluation) for license renewal and documents the technical basis for each such determination. In addition, the GALL Report identifies certain SSCs that mayor may not be subject to particular aging effects, and for which industry groups are developing generic aging management programs or investigating whether aging management is warranted. To the extent the ultimate generic resolution of such an issue will need NRC review and approval for plant-specific implementation, as indicated in a plant-specific FSAR supplement, and reflected in the SER associated with a particular LR application, an amendment pursuant to 10 CFR 50.90 will be necessary.

In the GALL Report, Volume 1, Tables 1 through 6 are summaries of the aging management review. These tables contain the same information as Tables 3.1-1 to 3.6-1, respectively, in the SRP-LR. These tables also include additional seventh and eighth columns that identify the related generic item and unique item associated with each structure and/or component (i.e.,

each row in the AMR tables contained in Volume 2 of the GALL Report). A locator for the plant systems evaluated in Volume 2 is also provided in the Appendix of Volume 1.

The Appendix of Volume 2 of the GALL Report addresses quality assurance (QA) for aging management programs. Those aspects of the aging management review process that affect the quality of safety-related structures, systems, and components are subject to the QA requirements of Appendix B to 10 CFR Part 50. For nonsafety-related structures and components subject to an aging management review, the existing 10 CFR Part 50, Appendix B, QA program may be used by an applicant to address the elements of the corrective actions, confirmation process, and administrative controls for an aging management program for license renewal.

The GALL Report provides a technical basis for crediting existing plant programs and recommending areas for program augmentation and further evaluation. The incorporation of the GALL Report information into the SRP-LR, as directed by the Commission, should improve the efficiency of the license renewal process and better focus staff resources.

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Table Column Headings The following describes the information presented in each column of Tables 1 through 6 contained in Volume 1 of this report. These tables present the relationship between the SRP-LR lines, the unique AMR line-item identifier (unique item) and the chapter-specific generic item that can be referenced repeatedly within a given chapter of GALL Vol. 2.

Column Heading Description ID A unique row identifier. This identifier is useful in matching the row with the row in the corresponding 3X-1 Table in the SRP-LR (where the "X" represents the chapter number within the SRP-LR). Thus, the Table 1 row labeled ID 1 in GALL Vol. 1 represents the same information contained in the row labeled ID 1 in Table 3.1-1 of the SRP-LR.

Type Identifies the plant design that the item applies to (i.e., BWR or PWR or both).

Component Identifies the structure or components to which the row applies Aging Effect/ Identifies the applicable aging effect and mechanism(s). See Chapter IX of Mechanism Volume 2 for more information.

Aging Identifies the time limited aging analysis or aging management program found Management acceptable for properly managing the affects of aging. See Chapter X and XI Programs of Volume 2.

Further Identifies whether further evaluation is required, and references the section of Evaluation the SRP-LR that provides further information on this evaluation.

Recommended Related Identifies the item number in Volume 2, Chapters II through VIII presenting the Generic Item detailed information summarized by this row. This chapter-specific generic identifier is used in the AMR subsystem rows and can appear multiple times within a chapter.

Unique Item The unique item is an AMR line-item identifier which is coded to indicate the chapter, AMR subsystem and unique row number within GALL Volume 2 (i.e.,

VIII.B1-1 is the first row in the steam and power conversion system, main steam system table, row 1).

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'"oo U1 Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 1 BWR Steel pressure vessel support skirt Cumulative fatigue TLAA, evaluated in Yes, TLAA R-70 IV.A1-6 and attachment welds damage accordance with 10 CFR IV.A2-20 5421(c) 2 BWR Steel; stainless steel; steel with Cumulative fatigue TLAA, evaluated in Yes, TLAA R-04 IV.A1-7 nickel-alloy or stainless steel damage accordance with 10 CFR cladding; nickel-alloy reactor vessel 5421 (c) and components: flanges; nozzles; environmental effects are penetrations; safe ends; thermal to be addressed for Class sleeves; vessel shells, heads and 1 components welds 3 BWR Steel; stainless steel; steel with Cumulative fatigue TLAA, evaluated in Yes, TLAA R-220 IV.C1-15 nickel-alloy or stainless steel damage accordance with 10 CFR cladding; nickel-alloy reactor coolant 5421 (c) and pressure boundary piping, piping environmental effects are components, and piping elements to be addressed for Class exposed to reactor coolant 1 components 4 BWR Steel pump and valve closure bolting Cumulative fatigue TLAA, evaluated in Yes, TLAA R-28 IV.C1-11 damage accordance with 10 CFR 5421 (c) check Code z limits for allowable cycles C (less than 7000 cycles) of

0 m thermal stress range Gl 5 BWRI Stainless steel and nickel alloy Cumulative fatigue TLAA, evaluated in Yes, TLAA R-53 IV.B1-14 PWR reactor vessel internals components damage accordance with 10 CFR IV.B2-31 5421(c) IV.B3-24 Q. IV.B4-37

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Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 6 PWR Nickel Alloy tubes and sleeves in a Cumulative fatigue TLAA, evaluated in Yes, TLAA R-46 IVD1-21

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reactor coolant and secondary damage accordance with 10 CFR IVD2-15

< feedwateristeam environment 5421(c) 7 PWR Steel and stainless steel reactor Cumulative fatigue TLAA, evaluated in Yes, TLAA R-13 IV.C2-23 coolant pressure boundary closure damage accordance with 10 CFR R-18 IV.C2-10 bolting, head closure studs, support 5421(c) R-33 IVD1-11 skirts and attachment welds, IVD2-10 pressurizer relief tank components, R-73 IV.A2-4 steam generator components, piping and components external surfaces and bolting 8 PWR Steel; stainless steel; and nickel- Cumulative fatigue TLAA, evaluated in Yes, TLAA R-223 IV.C2-25 OJ alloy reactor coolant pressure damage accordance with 10 CFR boundary piping, piping components, 5421 (c) and piping elements; flanges; nozzles environmental effects are and safe ends; pressurizer vessel to be addressed for Class shell heads and welds; heater 1 components sheaths and sleeves; penetrations; and thermal sleeves 9 PWR Steel; stainless steel; steel with Cumulative fatigue TLAA, evaluated in Yes, TLAA R-219 IV.A2-21 nickel-alloy or stainless steel damage accordance with 10 CFR cladding; nickel-alloy reactor vessel 5421 (c) and components: flanges; nozzles; environmental effects are penetrations; pressure housings; to be addressed for Class safe ends; thermal sleeves; vessel 1 components shells, heads and welds (f)

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'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 10 PWR Steel; stainless steel; steel with Cumulative fatigue TLAA, evaluated in Yes, TLAA R-221 IVD1-8 nickel-alloy or stainless steel damage accordance with 10 CFR R-222 IVD2-3 cladding; nickel-alloy steam 5421 (c) and generator components (flanges; environmental effects are penetrations; nozzles; safe ends, to be addressed for Class lower heads and welds) 1 components 11 BWR Steel top head enclosure (without Loss of material due Water Chemistry and Yes, detection of R-59 IV.A1-11 cladding) top head nozzles (vent, top to general, pitti ng and One-Time Inspection aging effects is head spray or RCIC, and spare) crevice corrosion to be evaluated exposed to reactor coolant 12 PWR Steel steam generator shell Loss of material due Water Chemistry and Yes, detection of R-224 IVD2-8 assembly exposed to secondary to general, pitti ng and One-Time Inspection aging effects is feedwater and steam crevice corrosion to be evaluated 13 BWR Steel and stainless steel isolation Loss of material due Water Chemistry and Yes, detection of R-16 IV.C1-6 condenser components exposed to to general (steel only), One-Time Inspection aging effects is reactor coolant pitting and crevice to be evaluated corrosion 14 BWR Stainless steel, nickel-alloy, and Loss of material due Water Chemistry and Yes, detection of RP-25 IV.A1-8 steel with nickel-alloy or stainless to pitting and crevice One-Time Inspection aging effects is z steel cladding reactor vessel corrosion to be evaluated C flanges, nozzles, penetrations, safe

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Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 15 BWR Stainless steel; steel with nickel- Loss of material due Water Chemistry and Yes, detection of RP-27 IV.C1-14

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alloy or stainless steel cladding; and to pitting and crevice One-Time Inspection aging effects is

< nickel-alloy reactor coolant pressure corrosion to be evaluated boundary components exposed to reactor coolant 16 PWR Steel steam generator upper and Loss of material due Inservice Inspection Yes, detection of R-34 IVD1-12 lower shell and transition cone to general, pilli ng and (IWB, IWC, and IWO), aging effects is exposed to secondary feedwater crevice corrosion and Water Chemistry to be evaluated and steam and, for Westinghouse Model 44 and 51 S/G, if general and pilling corrosion of the shell is known to exist, additional inspection procedures are to be developed.

17 BWR/ Steel (with or without stainless steel Loss of fracture TLAA, evaluated in Yes, TLAA R-62 IV.A1-13 PWR cladding) reactor vessel beltline toughness due to accordance with R-67 IV.A1-4 shell, nozzles, and welds neutron irradiation Appendix G of 10 CFR 50 R-81 IV.A2-16 embrilliement and RG 1.99. The R-84 IV.A2-23 appl icant may choose to demonstrate that the materials of the nozzles are not controlling for the TLAA evaluations.

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20 BWR Stainless steel isolation condenser Cracking due to Inservice Inspection Yes, detection of R-15 IV.C1-4 components exposed to reactor stress corrosion (IWB, IWC, and IWO), aging effects is coolant cracking and Water Chemistry, and to be evaluated intergranular stress plant -specific verification corrosion cracking program 21 PWR Reactor vessel shell fabricated of Crack growth due to TLAA Yes, TLAA R-85 IV.A2-22 z SA508-CI 2 forgings clad with cyclic loading C

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< EffectlMechanism Programs Item Q. Recommended Item 22 PWR Stainless steel and nickel alloy Loss of fracture FSAR supplement No, but licensee R-122 IV.B2-9

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reactor vessel internals components toughness due to commitment to (1) commitment to R-127 IV.B2-3

< exposed to reactor coolant and neutron irradiation participate in industry RVI be confirmed R-128 IV.B2-6 neutron flux embrittlement, void aging programs (2) IV.B4-1 swelling implement applicable R-132 IV.B2-18 results (3) submit for R-135 IV.B2-17 NRC approval> 24 R-141 IV.B2-22 months before the R-157 IV.B3-16 extended period an RVI R-161 IV.B3-12 inspection plan based on R-164 IV.B3-10 industry recommendation. R-169 IV.B3-20 R-178 IV.B4-46 R-188 IV.B4-16 R-196 IV.B4-12 R-205 IV.B4-31 R-212 IV.B4-24 R-216 IV.B4-41 23 PWR Stainless steel reactor vessel Cracking due to A plant-specific aging Yes, plant R-74 IV.A2-5 closure head flange leak detection stress corrosion management program is specific RP-13 IV.A2-1 line and bottom-mounted instrument cracking to be evaluated.

guide tubes 24 PWR Class 1 cast austenitic stainless Cracking due to Water Chemistry and, for Yes, plant R-05 IV.C2-3 steel piping, piping components, and stress corrosion CASS components that specific piping elements exposed to reactor cracking do not meet the NUREG-coolant 0313 guidelines, a plant specific aging (f)

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~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 25 BWR Stainless steel jet pump sensing line Cracking due to cyclic A plant-specific aging Yes, plant R-102 IV.B1-12 loading management program is specific to be evaluated.

26 BWR Steel and stainless steel isolation Cracking due to cyclic Inservice Inspection Yes, detection of R-225 IV.C1-5 condenser components exposed to loading (IWB, IWC, and IWO) and aging effects is reactor coolant plant -specific verification to be evaluated program 27 PWR Stainless steel and nickel alloy Loss of preload due to FSAR supplement No, but licensee R-108 IV.B2-33 reactor vessel internals screws, stress relaxation commitment to (1) commitment to R-114 IV.B2-38 bolts, tie rods, and hold-down participate in industry RVI be confirmed R-129 IV.B2-5 springs aging programs (2) R-136 IV.B2-25 implement applicable R-137 IV.B2-14 results (3) submit for R-154 IV.B3-6 NRC approval> 24 R-165 IV.B3-7 months before the R-184 IV.B4-6 extended period an RVI R-192 IV.B4-19 inspection plan based on R-197 IV.B4-14 industry recommendation. R-201 IV.B4-9 R-207 IV.B4-33 R-213 IV.B4-26 z 28 PWR Steel steam generator feedwater Loss of material due A plant-specific aging Yes, plant R-39 IVD1-13 C

0 impingement plate and support to erosion management program is specific m

Gl exposed to secondary feedwater to be evaluated.

29 BWR Stainless steel steam dryers Cracking due to flow- A plant-specific aging Yes, plant RP-18 IV.B1-16 exposed to reactor coolant induced vibration management program is specific Q. to be evaluated.

0 (D

OAGI0000203_023

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 30 PWR Stainless steel reactor vessel Cracking due to Water Chemistry and No, but licensee R-106 IV.B2-42

0 (D

internals components (e.g., Upper stress corrosion FSAR supplement commitment R-109 IV.B2-36

< internals assembly, RCCA guide cracking, irradiation- commitment to (1) needs to be R-116 IV.B2-30 tube assemblies, Bafflelformer assisted stress participate in industry RVI confirmed R-120 IV.B2-8 assembly, Lower internal assembly, corrosion cracking aging programs (2) R-123 IV.B2-2 shroud assemblies, Plenum cover implement applicable R-125 IV.B2-10 and plenum cylinder, Upper grid results (3) submit for IV.B4-7 assembly, Control rod guide tube NRC approval> 24 R-138 IV.B2-24 (CRGT) assembly, Core support months before the R-143 IV.B2-12 shield assembly, Core barrel extended period an RVI R-146 IV.B3-28 assembly, Lower grid assembly, inspection plan based on R-149 IV.B3-2 Flow distributor assembly, Thermal industry recommendation. R-155 IV.B3-15 shield, Instrumentation support R-159 IV.B3-11 structures) R-166 IV.B3-21 R-172 IV.B4-34 R-173 IV.B4-36 R-175 IV.B4-44 R-176 IV.B4-43 R-180 IV.B4-2 R-181 IV.B4-5 R-185 IV.B4-18 R-193 IV.B4-10 R-202 IV.B4-29 R-209 IV.B4-22 R-214 IV.B4-40 (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_024

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 31 PWR Nickel alloy and steel with nickel- Cracking due to Inservice Inspection No, but licensee R-01 IVD1-4 alloy cladding piping, piping primary water stress (IWB, IWC, and IWO) and commitment IVD2-2 component, piping elements, corrosion cracking Water Chemistry and needs to be R-06 IV.C2-21 penetrations, nozzles, safe ends, FSAR supp commitment confirmed R-88 IV.A2-12 and welds (other than reactor vessel to implement applicable R-89 IV.A2-19 head); pressurizer heater sheaths, plant com m itments to (1) RP-22 IV.C2-24 sleeves, diaphragm plate, manways NRC Orders, Bulletins, RP-31 IV.C2-13 and flanges; core support pads/core and Generic Letters guide lugs associated with nickel alloys and (2) staff-accepted industry U1 guidelines.

32 PWR Steel steam generator feedwater Wall thinning due to A plant-specific aging Yes, plant R-51 IVD1-26 inlet ring and supports flow-accelerated management program is specific corrosion to be evaluated.

z C

0 m

Gl Q.

0 (D

OAGI0000203_025

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 33 PWR Stainless steel and nickel alloy Changes in FSAR supplement No, but licensee R-107 IV.B2-41

0 (D

reactor vessel internals components dimensions due to commitment to (1) commitment to R-110 IV.B2-35

< void swelling participate in industry RVI be confirmed R-113 IV.B2-39 aging programs (2) R-117 IV.B2-29 implement applicable R-119 IV.B2-27 results (3) submit for R-121 IV.B2-7 NRC approval> 24 R-124 IV.B2-1 months before the R-126 IV.B2-4 extended period an RV I R-131 IV.B2-19 inspection plan based on R-134 IV.B2-15 industry recommendation. R-139 IV.B2-23 R-144 IV.B2-11 R-147 IV.B3-27 R-151 IV.B3-4 R-158 IV.B3-14 R-160 IV.B3-13 R-163 IV.B3-8 R-168 IV.B3-19 R-174 IV.B4-35 R-177 IV.B4-45 R-182 IV.B4-3 R-187 IV.B4-17 R-195 IV.B4-11 R-199 IV.B4-8 R-204 IV.B4-30 R-211 IV.B4-23 R-215 IV.B4-39 (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_026

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 34 PWR Stainless steel and nickel alloy Cracking due to Inservice Inspection No, but licensee R-76 IV.A2-11 reactor control rod drive head stress corrosion (IWB, IWC, and IWO) and commitment penetration pressure housings cracking and primary Water Chemistry and for needs to be water stress corrosion nickel alloy, FSAR confirmed cracking supplement commitment to implement applicable plant com m itments to (1)

NRC Orders, Bulletins and Generic Letters associated with nickel alloys and (2) staff-accepted industry guidelines.

35 PWR Steel with stainless steel or nickel Cracking due to Inserl.1ce Inspection No, but licensee R-35 IVD2-4 alloy cladding primary side stress corrosion (IWB, IWC, and IWO) and commitment components; steam generator upper cracking and primary Water Chemistry and for needs to be and lower heads, tubesheets and water stress corrosion nickel alloy, FSAR confirmed tube-to-tube sheet welds cracking supplement commitment to implement applicable plant com m itments to (1) z NRC Orders, Bulletins C and Generic Letters

0 m associated with nickel Gl alloys and (2) staff-accepted industry guidelines.

Q.

0 (D

OAGI0000203_027

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 36 PWR Nickel alloy, stainless steel Cracking due to Water Chemistry and No, unless R-24 IV.C2-17

0 (D

pressurizer spray head stress corrosion One-Time Inspection and, licensee

< cracking and primary for nickel alloy welded commitment water stress corrosion spray heads, provide needs to be cracking commitment in FSAR confirmed supplement to submit AMP delineating commitments to Orders, Bulletins, or Generic Lelters that inspect stipulated components for cracki ng of welted surfaces.

37 PWR Stainless steel and nickel alloy Cracking due to Water Chemistry and No, but licensee R-112 IV.B2-40 reactor vessel internals components stress corrosion FSAR supplement commitment R-118 IV.B2-28 (e.g., Upper internals assembly, cracking, primary commitment to (1) needs to be R-130 IV.B2-20 RCCA guide tube assemblies, Lower water stress corrosion participate in industry RVI confirmed R-133 IV.B2-16 internal assembly, CEA shroud cracking, irradiation- aging programs (2) R-150 IV.B3-5 assemblies, Core shroud assembly, assisted stress implement applicable R-162 IV.B3-9 Core support shield assembly, Core corrosion cracking results (3) submit for R-167 IV.B3-23 barrel assembly, Lower grid NRC approval> 24 R-186 IV.B4-20 assembly, Flow distributor months before the R-194 IV.B4-13 assembly) extended period an RVI R-203 IV.B4-32 inspection plan based on R-210 IV.B4-25 industry recommendation.

38 BWR Steel (with or without stainless steel Cracking due to cyclic BWR CR Drive Return No R-66 IV.A1-2 (f)

(D cladding) control rod drive return line loading Line Nozzle nozzles exposed to reactor coolant (D

3 0-

~

'"oo U1 OAGI0000203_028

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 39 BWR Steel (with or without stainless steel Cracking due to cyclic BWR Feedwater Nozzle No R-65 IV.A1-3 cladding) feedwater nozzles loading exposed to reactor coolant 40 BWR Stainless steel and nickel alloy Cracking due to BWR Penetrations and No R-69 IV.A1-5 penetrations for control rod drive stress corrosion Water Chemistry stub tubes instrumentation, jet pump cracking, instrument, standby liquid control, Intergranular stress flux monitor, and drain line exposed corrosion cracking, to reactor coolant cyclic loading 41 BWR Stainless steel and nickel alloy Cracking due to BWR Stress Corrosion No R-20 IV.C1-9 piping, piping components, and stress corrosion Cracki ng and Water R-21 IV.C1-8 piping elements greater than or cracking and Chemistry R-68 IV.A1-1 equal to 4 NPS; nozzle safe ends intergranular stress and associated welds corrosion cracking 42 BWR Stainless steel and nickel alloy Cracking due to BWR Vessel 10 No R-64 IV.A1-12 vessel shell attachment welds stress corrosion Attachment Welds and exposed to reactor coolant cracking and Water Chemistry intergranular stress corrosion cracking z 43 BWR Stainless steel fuel supports and Cracking due to BWR Vessel Internals No R-104 IV.B1-8 C control rod drive assemblies control stress corrosion and Water Chemistry

0 m rod drive housing exposed to reactor cracking and Gl coolant intergranular stress corrosion cracking Q.

0 (D

OAGI0000203_029

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 44 BWR Stainless steel and nickel alloy core Cracking due to BWR Vessel Internals No R-92 IV.B1-1

0 (D

shroud, core plate, core plate bolts, stress corrosion and Water Chemistry R-93 IV.B1-6

< support structure, top guide, core cracking, intergranular R-96 IV.B1-2 spray lines, spargers, jet pump stress corrosion R-97 IV.B1-3 assemblies, control rod drive cracking, irradiation- R-9S IV.B1-17 housing, nuclear instrumentation assisted stress R-99 IV.B1-7 guide tubes corrosion cracking R-100 IV.B1-13 R-105 IV.B1-10 45 BWR Steel piping, piping components, Wall thinning due to Flow-Accelerated No R-23 IV.C1-7 and piping elements exposed to flow-accelerated Corrosion reactor coolant corrosion 46 BWR Nickel alloy core shroud and core Cracking due to Inservice Inspection No R-95 IV.B1-4 plate access hole cover (mechanical stress corrosion (IWB, IWC, and IWO),

covers) cracking, intergranular and Water Chemistry stress corrosion cracking, irradiation-assisted stress corrosion cracking 47 BWR Stainless steel and nickel-alloy Loss of material due Inservice Inspection No RP-26 IV.B1-15 reactor vessel internals exposed to to pitting and crevice (IWB, IWC, and IWO),

reactor coolant corrosion and Water Chemistry (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_030

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 48 BWR Steel and stainless steel Class 1 Cracking due to Inservice Inspection No R-03 IV.C1-1 piping, fittings and branch stress corrosion (IWB, IWC, and IWO),

connections < NPS 4 exposed to cracking, intergranular Water chemistry, and reactor coolant stress corrosion One-Time Inspection of cracking (for stainless ASME Code Class 1 steel only), and Small-bore Piping thermal and mechanical loading 49 BWR Nickel alloy core shroud and core Cracking due to Inservice Inspection No R-94 IV.B1-5 plate access hole cover (welded stress corrosion (IWB, IWC, and IWO),

covers) cracking, intergranular Water Chemistry, and, for stress corrosion BWRs with a crevice in cracking, irradiation- the access hole covers, assisted stress augmented inspection corrosion cracking using UT or other demonstrated acceptable inspection of the access hole cover welds 50 BWR High-strength low alloy steel top Cracking due to Reactor Head Closure No R-60 IV.A1-9 head closure studs and nuts stress corrosion Studs z exposed to air with reactor coolant cracking and C

0 leakage intergranular stress m corrosion cracking Gl Q.

0 (D

OAGI0000203_031

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 51 BWR Cast austenitic stainless steel jet Loss of fracture Thermal Aging and No R-101 IV.B1-11

0 (D

pump assembly castings; orificed toughness due to Neutron Irradiation R-103 IV.B1-9

< fuel support thermal aging and Embrilliement of CASS neutron irradiation embrilliement 52 BWRI Steel and stainless steel reactor Cracking due to Bolting Integrity No R-10 IVD1-2 PWR coolant pressure boundary (RCPB) stress corrosion R-11 IV.C2-7 pump and valve closure bolting, cracking, loss of R-12 IV.C2-8 manway and holding bolting, flange material due to wear, R-26 IV.C1-12 bolting, and closure bolting in high- loss of preload due to R-27 IV.C1-10 pressure and high-temperature thermal effects, R-29 IV.C1-13 systems gasket creep, and R-32 IVD1-10 self-loosening IVD2-6 R-78 IV.A2-6 R-79 IV. A 2-7 R-80 IV.A2-8 53 BWRI Steel piping, piping components, Loss of material due Closed-Cycle Cooling No RP-10 IV.C2-14 PWR and piping elements exposed to to general, pilli ng and Water System closed cycle cooling water crevice corrosion 54 BWRI Copper alloy piping, piping Loss of material due Closed-Cycle Cooling No RP-11 IV.C2-11 PWR components, and piping elements to pilling, crevice, and Water System exposed to closed cycle cooling galvanic corrosion water (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_032

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 55 BWRI Cast austenitic stainless steel Class Loss of fracture Inservice inspection No R-D8 IV.C1-3 PWR 1 pump casings, and valve bodies toughness due to (IWB, IWC, and IWO) IV.C2-6 and bonnets exposed to reactor thermal aging Thermal aging coolant >25DoC (>482°F) embritllement susceptibility screening is not necessary, i nservice inspection requirements are sufficient for managing these aging effects. ASME Code Case N-481 also provides an alternative for pump casings.

56 BWRI Copper alloy >15% Zn piping, piping Loss of material due Selective Leaching of No RP-12 IV.C2-12 PWR components, and piping elements to selective leaching Materials exposed to closed cycle cooling water 57 BWRI Cast austenitic stainless steel Class Loss of fracture Thermal Aging No R-52 IV.C1-2 PWR 1 piping, piping component, and toughness due to Embritllement of CASS IV.C2-4 piping elements and control rod thermal aging R-n IV.A2-1D drive pressure housings exposed to embritllement z reactor coolant >25DoC (>482°F)

C

0 58 PWR Steel reactor coolant pressure Loss of material due Boric Acid Corrosion No R-17 IV.A2-13 m

Gl boundary external surfaces ex posed to Boric acid corrosion IV.C2-9 to air with borated water leakage IVD1-3 IVD2-1 Q.

0 (D

OAGI0000203_033

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 59 PWR Steel steam generator steam nozzle Wall thinning due to Flow-Accelerated No R-37 IVD1-5

0 (D

and safe end, feedwater nozzle and flow-accelerated Corrosion R-38 IVD2-7

< safe end, AFW nozzles and safe corrosion ends exposed to secondary feedwateristeam 60 PWR Stainless steel flux thimble tubes Loss of material due Flux Thimble Tube No R-145 IV.B2-13 (with or without chrome plating) to Wear Inspection 61 PWR Stainless steel, steel pressurizer Cracking due to cyclic Inservice Inspection No R-19 IV.C2-16 integral support exposed to air with loading (IWB, IWC, and IWO) metal temperature up to 288°C (550°F) 62 PWR Stainless steel, steel with stainless Cracking due to cyclic Inservice Inspection No R-56 IV.C2-26 steel cladding reactor coolant loading (IWB, IWC, and IWO) system cold leg, hot leg, surge line, and spray line piping and fittings exposed to reactor coolant 63 PWR Steel reactor vessel flange, stainless Loss of material due Inservice Inspection No R-87 IV.A2-25 steel and nickel alloy reactor vessel to Wear (IWB, IWC, and IWO) R-115 IV.B2-34 internals exposed to reactor coolant R-142 IV.B2-26 (e.g., upper and lower internals R-148 IV.B3-26 assembly, CEA shroud assembly, R-152 IV.B3-3 core support barrel, upper grid R-156 IV.B3-17 assembly, core support shield R-170 IV.B3-22 assembly, lower grid assembly) R-179 IV.B4-42 R-190 IV.B4-15 (f) R-208 IV.B4-27 (D

(D 3

0-

~

'"oo U1 OAGI0000203_034

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 64 PWR Stainless steel and steel with Cracking due to Inservice Inspection No R-25 IV.C2-19 stainless steel or nickel alloy stress corrosion (IWB, IWC, and IWO) and cladding pressurizer components cracking, primary Water Chemistry water stress corrosion cracking 65 PWR Nickel alloy reactor vessel upper Cracking due to Inservice Inspection No R-75 IV.A2-9 head and control rod drive primary water stress (IWB, IWC, and IWO) and R-90 IV.A2-18 penetration nozzles, instrument corrosion cracking Water Chemistry and tubes, head vent pipe (top head), Nickel-Alloy Penetration and welds Nozzles Welded to the Upper Reactor Vessel U1 Closure Heads of Pressurized Water Reactors 66 PWR Steel steam generator secondary Loss of material due Inservice Inspection No R-31 IVD2-5 manways and hand holds (cover to erosion (IWB, IWC, and IWO) for only) exposed to air with leaking Class 2 components secondary-side water and/or steam 67 PWR Steel with stainless steel or nickel Cracking due to cyclic Inservice Inspection No R-58 IV.C2-18 alloy cladding; or stainless steel loading (IWB, IWC, and IWO),

z pressurizer components exposed to and Water Chemistry C

0 reactor coolant m

Gl Q.

0 (D

OAGI0000203_035

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 68 PWR Stainless steel, steel with stainless Cracking due to Inservice Inspection No R-07 IV.C2-2

0 (D

steel cladding Class 1 piping, stress corrosion (IWB, lwe, and IWO), IVD1-1

< fittings, pump casings, valve bodies, cracking and Water Chemistry R-09 IV.C2-5 nozzles, safe ends, manways, R-14 IV.C2-22 flanges, CRO housing; pressurizer R-30 IV.C2-27 heater sheaths, sleeves, diaphragm R-217 IV.C2-20 plate; pressurizer relief tank components, reactor coolant system cold leg, hot leg, surge line, and spray line piping and fittings 69 PWR Stainless steel, nickel alloy safety Cracking due to Inservice Inspection No R-83 IV.A2-15 injection nozzles, safe ends, and stress corrosion (IWB, lwe, and IWO),

associated welds and buttering cracking, primary and Water Chemistry exposed to reactor coolant water stress corrosion cracking 70 PWR Stainless steel; steel with stainless Cracking due to Inservice Inspection No R-02 IV.C2-1 steel cladding Class 1 piping, fittings stress corrosion (IWB, lwe, and IWO),

and branch connections < NPS 4 cracking, thermal and Water chemistry, and exposed to reactor coolant mechanical loading One-Time Inspection of ASME Code Class 1 Small-bore Piping 71 PWR High-strength low alloy steel closure Cracking due to Reactor Head Closure No R-71 IV.A2-2 head stud assembly exposed to air stress corrosion Studs R-72 IV.A2-3 with reactor coolant leakage cracking; loss of material due to wear (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_036

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 72 PWR Nickel alloy steam generator tubes Cracking due to 00 Steam Generator Tube No R-47 IVD1-23 and sleeves exposed to secondary stress corrosion Integrity and Water IVD2-17 feedwaterl steam cracking and Chemistry R-48 IVD1-22 intergranular attack, IVD2-16 loss of material due to R-49 IVD1-24 fretting and wear IVD2-18 73 PWR Nickel alloy steam generator tubes, Cracking due to Steam Generator Tube No R-40 IVD1-18 repair sleeves, and tube plugs primary water stress Integrity and Water IVD2-12 exposed to reactor coolant corrosion cracking Chemistry R-44 IVD1-20 IVD2-14 74 PWR Chrome plated steel, stainless steel, Cracking due to Steam Generator Tube No RP-14 IVD1-14 nickel alloy steam generator anti- stress corrosion Integrity and Water RP-15 IVD1-15 vibration bars exposed to secondary cracking, loss of Chemistry feedwaterl steam material due to crevice corrosion and fretting 75 PWR Nickel alloy once-through steam Denting due to Steam Generator Tube No R-226 IVD2-13 generator tubes exposed to corrosion of carbon Integrity and Water secondary feedwaterl steam steel tube support Chemistry plate z

C 76 PWR Steel steam generator tube support Loss of material due Steam Generator Tube No R-42 IVD1-17

0 m plate, tube bundle wrapper exposed to erosion, general, Integrity and Water IVD2-11 Gl to secondary feedwaterlsteam pitting, and crevice Chemistry RP-16 IVD1-9 corrosion, ligament cracking due to Q. corrosion

0 (D

OAGI0000203_037

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 77 PWR Nickel alloy steam generator tubes Loss of material due Steam Generator Tube No R-50 IVD1-25

0 (D

and sleeves exposed to phosphate to wastage and pitli ng Integrity and Water

< chemistry in secondary feedwaterl corrosion Chemistry steam 78 PWR Steel steam generator tube support Wall thinning due to Steam Generator Tube No R-41 IVD1-16 latlice bars exposed to secondary flow-accelerated Integrity and Water feedwaterl steam corrosion Chemistry 79 PWR Nickel alloy steam generator tubes Denting due to Steam Generator Tube No R-43 IVD1-19 exposed to secondary feedwaterl corrosion of steel tube Integrity; Water steam support plate Chemistry and, for plants that could experience denting at the upper support plates, evaluate potential for rapidly propagating cracks and then develop and take corrective actions consistent with Bulletin 88-02.

80 PWR Cast austenitic stainless steel Loss of fracture Thermal Aging and No R-111 IV.B2-37 reactor vessel internals (e.g., upper toughness du e to Neutron Irradiation R-140 IV.B2-21 internals assembly, lower internal thermal aging and Embritllement of CASS R-153 IV.B3-1 assembly, CEA shroud assemblies, neutron irradiation R-171 IV.B3-18 control rod guide tube assembly, embritllement R-183 IV.B4-4 core support shield assembly, lower R-191 IV.B4-21 grid assembly) R-206 IV.B4-28 (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_038

(f)

(D (D

3 0- Table 1. Summary of Aging Management Programs for the Reactor Coolant System

~

Evaluated in Chapter IV of the GALL Report

'"oo Further Related U1 Aging Aging Management Unique 10 Type Component Evaluation Generic EffectlMechanism Programs Item Recommended Item 81 PWR Nickel alloy or nickel-alloy clad Cracking due to Water Chemistry No RP-21 IVD1-6 steam generator divider plate primary water stress exposed to reactor coolant corrosion cracking 82 PWR Stainless steel steam generator Cracking due to Water Chemistry No RP-17 IVD1-7 primary side divider plate exposed to stress corrosion reactor coolant cracking 83 PWR Stainless steel; steel with nickel- Loss of material due Water Chemistry No RP-23 IV.C2-15 alloy or stainless steel cladding; and to pitting and crevice RP-24 IV.B2-32 nickel-alloy reactor vessel internals corrosion IV.B3-25 and reactor coolant pressure IV.B4-38 boundary components exposed to RP-28 IV.A2-14 reactor coolant 84 PWR Nickel alloy steam generator Cracking due to Water Chemistry and No R-36 IVD2-9 components such as, secondary stress corrosion One-Time Inspection or side nozzles (vent, drain, and cracking Inservice Inspection instrumentation) exposed to (IWB, IWC, and IWO) secondary feedwaterl steam 85 BWRI Nickel alloy piping, piping None None NA - NoAEM or RP-03 IV.E-1 PWR components, and piping elements AMP z exposed to air - indoor uncontrolled C (external)

0 m

Gl 86 BWRI Stainless steel piping, piping None None NA - NoAEM or RP-04 IV.E-2 PWR components, and piping elements AMP RP-05 IV.E-3 exposed to air - indoor uncontrolled RP-06 IV.E-4

< (External); ai r with borated water RP-07 IV.E-5 Q. leakage; concrete; gas

0 (D

OAGI0000203_039

z C

0 Table 1. Summary of Aging Management Programs for the Reactor Coolant System m

Gl Evaluated in Chapter IV of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic

< EffectlMechanism Programs Item Q. Recommended Item 87 BWRI Steel piping, piping components, None None NA - NoAEM or RP-01 IV.E-6

0 (D

PWR and piping elements in concrete AMP (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_040

(f)

(D (D

3 0-

~

Table 2. Summary of Aging Management Programs for the Engineered Safety Features

'"oo Evaluated in Chapter V of the GALL Report U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 1 BWRI Steel and stainless steel Cumulative fatigue damage TLAA, evaluated in Yes, TLAA E-10 V.D2-32 PWR piping, piping components, accordance with 10 E-13 V.D1-27 and piping elements in CFR 5421(c) emergency core cooling system 2 PWR Steel with stainless steel Loss of materiall cladding A plant-specific aging Yes, verify that EP-49 V.D1-32 cladding pump casing exposed breach management program plant -specific to treated borated water is to be evaluated. program addresses cladding breach Reference NRC Information Notice 94-63, "Boric Acid Corrosion of Charging Pump Casings Caused by Cladding Cracks" 3 BWRI Stainless steel containment Loss of material due to Water Chemistry and Yes, detection of E-33 V.C-4 PWR isolation piping and pitting and crevice One- Time Inspection aging effects is to components internal surfaces corrosion be evaluated z

C exposed to treated water

0 m

Gl 4 BWRI Stainless steel piping, piping Loss of material due to A plant-specific aging Yes, plant specific EP-31 V.D1-26 PWR components, and piping pitting and crevice management program V.D2-27

< elements exposed to soil corrosion is to be eval uated.

Q.

0 (D

OAGI0000203_041

z C

0 Table 2. Summary of Aging Management Programs for the Engineered Safety Features m

Gl Evaluated in Chapter V of the GALL Report Related

< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

0 (D

5 BWR Stainless steel and aluminum Loss of material due to Water Chemistry and Yes, detection of EP-26 V.D2-19

< piping, piping components, pitting and crevice One- Time Inspection aging effects is to EP-32 V.D2-28 and piping elements exposed corrosion be evaluated to treated water 6 BWRI Stainless steel and copper Loss of material due to Lubricating Oil Analysis Yes, detection of EP-45 V.A-21 PWR alloy piping, piping pitting and crevice and One- Time aging effects is to V.D1-18 components, and piping corrosion Inspection be evaluated V.D2-22 elements exposed to EP-51 V.D1-24 lubricating oil 7 BWRI Partially encased stainless Loss of material due to A plant-specific aging Yes, plant specific E-01 V.D1-15 PWR steel tanks with breached pitting and crevice management program moisture barrier exposed to corrosion is to be evaluated for raw water pitting and crevice corrosion of tank bottoms because moisture and water can egress under the tank due to cracking of the perimeter seal from weathering.

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Evaluated in Chapter V of the GALL Report

'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 8 BWRI Stainless steel piping, piping Loss of material due to A plant-specific aging Yes, plant specific E-14 V.D2-35 PWR components, piping elements, pitting and crevice management program EP-53 V.A-26 and tank internal surfaces corrosion is to be evaluated. V.01-29 exposed to condensation (internal) 9 BWRI Steel, stainless steel, and Reduction of heat transfer Lubricating Oil Analysis Yes, detection of EP-40 V.A-17 PWR copper alloy heat exchanger due to fouling and One- Time aging effects is to V.01-12 tubes exposed to lubricating oil Inspection be evaluated V.D2-14 EP-47 V.A-12 w V.01-8 w

V.D2-9 EP-50 V.A-14 V.01-10 V.D2-11 10 BWRI Stainless steel heat exchanger Reduction of heat transfer Water Chemistry and Yes, detection of EP-34 V.A-16 PWR tubes exposed to treated water due to fouling One- Time Inspection aging effects is to V.D2-13 be evaluated z 11 BWR Elastomer seals and Hardening and loss of A plant-specific aging Yes, plant specific E-06 V.B-4 C

0 components in standby gas strength due to elastomer management program 5) rn treatment system exposed to degradation is to be eval uated.

Gl air - indoor uncontrolled Q.

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< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

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12 PWR Stainless steel high-pressure Loss of material due to A plant-specific aging Yes, plant specific E-24 V.D1-14

< safety injection (charging) erosion management program pump miniflow orifice exposed is to be evaluated for to treated borated water erosion of the orifice due to extended use of the centrifugal HPSI pump for normal charging.

13 BWR Steel drywell and suppression Loss of material due to A plant-specific aging Yes, plant specific E-04 V.D2-1 chamber spray system nozzle general corrosion and management program and flow orifice internal fouling is to be eval uated.

surfaces exposed to air -

indoor uncontrolled (internal) 14 BWR Steel piping, piping Loss of material due to Water Chemistry and Yes, detection of E-08 V.D2-33 components, and piping general, pitting, and One- Time Inspection aging effects is to elements exposed to treated crevice corrosion be evaluated water 15 BWRI Steel containment isolation Loss of material due to Water Chemistry and Yes, detection of E-31 V.C-6 PWR piping, piping components, general, pitting, and One- Time Inspection aging effects is to and piping elements internal crevice corrosion be evaluated surfaces exposed to treated water (f)

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Evaluated in Chapter V of the GALL Report

'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 16 BWRI Steel piping, piping Loss of material due to Lubricating Oil Analysis Yes, detection of EP-46 V.A-25 PWR components, and piping general, pitting, and and One- Time aging effects is to V.D1-28 elements exposed to crevice corrosion Inspection be evaluated V.D2-30 lubricating oil 17 BWRI Steel (with or without coating Loss of material due to Buried Piping and No E-42 V.B-9 PWR or wrapping) piping, piping general, pitting, crevice, Tanks Surveillance components, and piping and microbiologically-elements buried in soil influenced corrosion or w Buried Piping and Yes, detection of U1 Tanks Inspection aging effects and operating experience are to be further evaluated 18 BWR Stainless steel piping, piping Cracking due to stress BWR Stress Corrosion No E-37 V.D2-29 components, and piping corrosion cracking and Cracking and Water elements exposed to treated intergranular stress Chemistry water >60°C (>140°F) corrosion cracking z

C

0 19 BWR Steel piping, piping Wall thinning due to flow- Flow-Accelerated No E-07 V.D2-31 m components, and piping accelerated corrosion Corrosion E-09 V.D2-34 Gl elements exposed to steam or treated water Q.

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< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

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20 BWR Cast austenitic stainless steel Loss of fracture toughness Thermal Aging No E-11 V.D2-20

< piping, piping components, due to thermal aging Embrittlement of CASS and piping elements exposed embrittlement to treated water (borated or unborated) >250°C (>482°F) 21 BWRI High-strength steel closure Cracking due to cyclic Bolting Integrity No E-03 V.E-3 PWR bolting exposed to air with loading, stress corrosion steam or water leakage cracking 22 BWRI Steel closure bolting exposed Loss of material due to Bolting Integrity No E-02 V.E-6 PWR to air with steam or water general corrosion leakage 23 BWRI Steel bolting and closure Loss of material due to Bolting Integrity No EP-1 V.E-1 PWR bolting exposed to air - general, pitting, and EP-25 V.E-4 outdoor (external), or air - crevice corrosion indoor uncontrolled (external) 24 BWRI Steel closure bolting exposed Loss of preload due to Bolting Integrity No EP-24 V.E-5 PWR to air - indoor uncontrolled thermal effects, gasket (external) creep, and self-loosening (f)

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Evaluated in Chapter V of the GALL Report

'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 25 BWRI Stainless steel piping, piping Cracking due to stress Closed-Cycle Cooling No EP-44 V.A-24 PWR components, and piping corrosion cracki ng Water System V.C-8 elements exposed to closed V.D1-23 cycle cooling water >60°C V.D2-26

(>140°F) 26 BWRI Steel piping, piping Loss of material due to Closed-Cycle Cooling No EP-48 V.C-9 PWR components, and piping general, pitting, and Water System elements exposed to closed crevice corrosion cycle cooling water 27 BWRI Steel heat excha nger Loss of material due to Closed-Cycle Cooling No E-17 V.A-9 PWR components exposed to closed general, pitting, crevice, Water System V.D1-6 cycle cooling water and galvanic corrosion V.D2-7 28 BWRI Stainless steel piping, piping Loss of material due to Closed-Cycle Cooling No E-19 V.A-7 PWR components, piping elements, pitting and crevice Water System V.D1-4 and heat exchanger corrosion V.D2-5 components exposed to EP-33 V.A-23 closed-cycle cooling water V.C-7 z V.D1-22 C

0 V.D2-25 m

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< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

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29 BWRI Copper alloy piping, piping Loss of material due to Closed-Cycle Cooling No EP-13 V.A-5

< PWR components, piping elements, pitting, crevice, and Water System V.D1-2 and heat exchanger galvanic corrosion V.D2-3 components exposed to closed EP-36 V.A-20 cycle cooling water V.B-6 V.D1-17 V.D2-21 30 BWRI Stainless steel and copper Reduction of heat transfer Closed-Cycle Cooling No EP-35 V.A-13 PWR alloy heat exchanger tubes due to fouling Water System V.D1-9 exposed to closed cycle V.D2-10 cooling water EP-39 V.A-11 31 BWRI External surfaces of steel Loss of material due to External Su rfaces No E-26 V.A-1 PWR components including ducting, general corrosion Monitoring V.B-3 piping, ducting closure bolting, V.D2-2 and containment isolation E-30 V.C-2 piping external surfaces E-35 V.C-1 exposed to air - indoor E-40 V.B-2 uncontrolled (external); E-44 V.E-7 condensation (external) and air E-45 V.E-8

- outdoor (external) E-46 V.E-10 (f)

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'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 32 BWRI Steel piping and ducting Loss of material due to Inspection of Internal No E-25 V.B-1 PWR components and internal general corrosion Surfaces in E-29 V.A-19 surfaces exposed to air - Miscellaneous Piping V.D2-16 indoor uncontrolled (Internal) and Ducting Components 33 BWRI Steel encapsulation Loss of material due to Inspection of Internal No EP-42 V.A-2 PWR components exposed to air- general, pitting, and Surfaces in indoor uncontrolled (internal) crevice corrosion Miscellaneous Piping and Ducting w Components CD 34 BWRI Steel piping, piping Loss of material due to Inspection of Internal No E-27 V.D2-17 PWR components, and piping general, pitting, and Surfaces in elements exposed to crevice corrosion Miscellaneous Piping condensation (internal) and Ducting Components 35 BWRI Steel containment isolation Loss of material due to Open-Cycle Cooling No E-22 V.C-5 PWR piping and components general, pitting, crevice, Water System internal surfaces exposed to and microbiologically-raw water influenced corrosion, and z fouling C

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Gl Evaluated in Chapter V of the GALL Report Related

< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

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36 BWRI Steel heat exchanger Loss of material due to Open-Cycle Cooling No E-18 V.A-10

< PWR components exposed to raw general, pitting, crevice, Water System V.01-7 water galvanic, and V.D2-8 m icrobiolog ically-influenced corrosion, and fouling 37 BWRI Stainless steel piping, piping Loss of material due to Open-Cycle Cooling No EP-55 V.01-25 PWR components, and piping pitting, crevice, and Water System elements exposed to raw m icrobiolog ically-water influenced corrosion 38 BWRI Stainless steel containment Loss of material due to Open-Cycle Cooling No E-34 V.C-3 PWR isolation piping and pitting, crevice, and Water System components internal surfaces m icrobiolog ically-exposed to raw water influenced corrosion, and fouling 39 BWRI Stainless steel heat exchanger Loss of material due to Open-Cycle Cooling No E-20 V.A-8 PWR components exposed to raw pitting, crevice, and Water System V.01-5 water m icrobiolog ically- V.D2-6 influenced corrosion, and fouling (f)

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'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 40 BWRI Steel and stainless steel heat Reduction of heat transfer Open-Cycle Cooling No E-21 V.A-15 PWR exchanger tubes (serviced by due to fouling Water System V.D1-11 open-cycle cooling water) V.D2-12 exposed to raw water E-23 V.D2-15 41 BWRI Copper alloy >15% Zn piping, Loss of material due to Selective Leaching of No EP-27 V.A-22 PWR piping components, piping selective leaching Materials V.B-7 elements, and heat exchanger V.D1-19 components exposed to closed V.D2-23 cycle cooling water EP-37 V.A-6 V.B-5 V.D1-3 V.D2-4 42 BWRI Gray cast iron piping, piping Loss of material due to Selective Leaching of No EP-52 V.D1-20 PWR components, piping elements selective leaching Materials exposed to closed-cycle cooling water 43 BWRI Gray cast iron piping, piping Loss of material due to Selective Leaching of No EP-54 V.B-8 z PWR components, and piping selective leaching Materials V.D1-21 C

0 elements exposed to soil V.D2-24 m

Gl 44 BWRI Gray cast iron motor cooler Loss of material due to Selective Leaching of No E-43 V.A-18 PWR exposed to treated water selective leaching Materials V.D1-13 Q.

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Gl Evaluated in Chapter V of the GALL Report Related

< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

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45 PWR Aluminum, copper alloy >15% Loss of material due to Boric Acid Corrosion No E-28 V.A-4

< Zn, and steel external Boric acid corrosion V.D1-1 surfaces, bolting, and piping, V.E-9 piping components, and piping E-41 V.E-2 elements exposed to air with EP-2 V.D2-18 borated water leakage EP-38 V.E-11 46 PWR Steel encapsulation Loss of material due to Inspection of Internal No EP-43 V.A-3 components exposed to air general, pilling, crevice Surfaces in with borated water leakage and boric acid corrosion Miscellaneous Piping (internal) and Ducting Components 47 PWR Cast austenitic stainless steel Loss of fracture toughness Thermal Aging No E-47 VD1-16 piping, piping components, due to thermal aging Embrilliement of CASS and piping elements exposed embrilliement to treated borated water

>250°C (>482°F)

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'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 48 PWR Stainless steel or stainless- Cracking due to stress Water Chemistry No E-12 V.A-28 steel-clad steel piping, piping corrosion cracki ng V.01-31 components, piping elements, E-38 V.01-33 and tanks (including safety injection tanks/accumulators) exposed to treated borated water >60°C (>140°F) 49 PWR Stainless steel piping, piping Loss of material due to Water Chemistry No EP-41 V.A-27 components, piping elements, pitting and crevice V.01-30 and tanks exposed to treated corrosion borated water 50 BWR/ Aluminum piping, piping None None NA - NoAEM or EP-3 V.F-2 PWR components, and piping AMP elements exposed to air-indoor uncontrolled (internal/external) z C 51 BWR/ Galvanized steel ducting None None NA - NoAEM or EP-14 V.F-1

0 m PWR exposed to air - indoor AMP Gl controlled (external)

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Gl Evaluated in Chapter V of the GALL Report Related

< Aging Management Further Evaluation Unique Q. 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item

0 (D

52 BWRI Glass piping elements None None NA - NoAEM or EP-15 V.F-6

< PWR exposed to air - indoor AMP EP-16 V.F-7 uncontrolled (external), EP-28 V.F-8 lubricating oil, raw water, EP-29 V.F-10 treated water, or treated EP-30 V.F-9 borated water 53 BWRI Stainless steel, copper alloy, None None NA - NoAEM or EP-10 V.F-3 PWR and nickel alloy piping, piping AMP EP-17 V.F-11 components, and piping EP-18 V.F-12 elements exposed to air -

indoor uncontrolled (external) 54 BWRI Steel piping, piping None None NA - NoAEM or EP-4 V.F-16 PWR components, and piping AMP elements exposed to air -

indoor controlled (external) 55 BWRI Steel and stainless steel None None NA - NoAEM or EP-5 V.F-17 PWR piping, piping components, AMP EP-20 V.F-14 and piping elements in concrete (f)

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'"oo U1 Related Aging Management Further Evaluation Unique 10 Type Component Aging Effect/Mechanism Generic Programs Recommended Item Item 56 BWRI Steel, stainless steel, and None None NA - NoAEM or EP-7 V.F-18 PWR copper alloy piping, piping AMP EP-9 V.F-4 components, and piping EP-22 V.F-15 elements exposed to gas 57 PWR Stainless steel and copper None None NA - NoAEM or EP-12 V.F-5 alloy <15% Zn piping, piping AMP EP-19 V.F-13 components, and piping elements exposed to air with borated water leakage z

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Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 1 BWRI Steel cranes - structural Cumulative fatigue TLAA to be evaluated for Yes, TLAA A-06 VII.B-2 PWR girders exposed to air - damage structural girders of indoor uncontrolled (external) cranes. See the Standard Review Plan, Section 4.7 for generic guidance for meeting the requirements of 10 CFR 5421 (c)(1) 2 BWRI Steel and stainless steel Cumulative fatigue TLAA, evaluated in Yes, TLAA A-34 VII.E1-18 PWR piping, piping components, damage accordance with 10 CFR VII.E3-17 piping elements, and heat 54.21(c) A-57 VII.E1-16 exchanger components A-62 VII.E3-14 exposed to air - indoor VII.E4-13 uncontrolled, treated borated A-100 VII.E1-4 water or treated water 3 BWRI Stainless steel heat Reduction of heat Water Chemistry and Yes, detection of AP-62 VII.A4-4 PWR exchanger tubes exposed to transfer due to fouling One- Time Inspection aging effects is to VII.E3-6 treated water be evaluated 4 BWR Stainless steel piping, piping Cracking due to stress Water Chemistry and Yes, detection of A-59 VII.E2-2 components, and piping corrosion cracking One- Time Inspection aging effects is to elements exposed to sodium be evaluated pentaborate solution >60°C

(>140°F) z 5 BWRI Stainless steel and stainless Cracking due to stress Plant specific Yes, plant specific A-71 VII.E3-3 C

0 PWR clad steel heat exchanger corrosion cracking A-85 VII.E3-19 rn Gl components exposed to treated water >60°C

(>140°F)

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0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 6 BWRI Stainless steel diesel engine Cracking due to stress Plant specific Yes, plant specific AP-33 VII.H2-1 PWR exhaust piping, piping corrosion cracking components, and piping elements exposed to diesel exhaust 7 PWR Stainless steel non- Cracking due to stress Water Chemistry and a Yes, plant specific A-69 VII.E1-9 regenerative heat exchanger corrosion cracking and plant-specific verification components exposed to cyclic loading program. An acceptable treated borated water >60°C verification program is to

(>140°F) include temperature and radioactivity monitoring of the shell side water, and eddy current testing of tubes.

8 PWR Stainless steel regenerative Cracking due to stress Water Chemistry and a Yes, plant specific A-84 VII.E1-5 heat exchanger components corrosion cracking and plant -specific verification exposed to treated borated cyclic loading program. The AMP is to water >60°C (>140°F) be augmented by verifying the absence of cracking due to stress corrosion cracking and cyclic loading. A plant specific aging management program is to be evaluated.

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Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 9 PWR Stainless steel high-pressure Cracking due to stress Water Chemistry and a Yes, plant specific A-76 VII.E1-7 pump casing in PWR corrosion cracking and plant -specific verification chemical and volume control cyclic loading program. The AMP is to system be augmented by verifying the absence of cracking due to stress corrosion cracking and cyclic loading. A plant specific aging management program is to be evaluated.

10 BWR/ High-strength steel closure Cracking due to stress Bolting Integrity Yes, if the bolts A-104 VII.E1-8 PWR bolting exposed to air with corrosion cracking, The AMP is to be are not replaced steam or water leakage. cyclic loading augmented by appropriate during inspection to detect maintenance cracki ng if the bolts are not otherwise replaced during maintenance.

11 BWR/ Elastomer seals and Hardening and loss of Plant specific Yes, plant specific A-17 VII.F1-7 PWR components exposed to air - strength due to VII.F2-7 indoor uncontrolled elastomer degradation VI I. F3-7 (internal/external) VI I. F4-6 12 BWR/ Elastomer lining exposed to Hardening and loss of A plant-specific aging Yes, plant specific A-15 VII.A3-1 z PWR treated water or treated strength due to management program that A-16 VII.A4-1 C borated water elastomer degradation determines and assesses

0 rn the qualified life of the Gl linings in the environment is to be evaluated.

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0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 13 BWRI Boral, boron steel spent fuel Reduction of neutron- Plant specific Yes, plant specific A-88 VII.A2-5 PWR storage racks neutron- absorbing capacity A-89 VII.A2-3 absorbing sheets exposed to and loss of material treated water or treated due to general borated water corrosion 14 BWRI Steel piping, piping Loss of material due to Lubricating Oil Analysis Yes, detection of AP-30 VII.C1-17 PWR component, and piping general, pitting, and and One-Time Inspection aging effects is to VII.C2-13 elements exposed to crevice corrosion be evaluated VII.E1-19 lubricating oil VII.E4-16 VII.F1-19 VII.F2-17 VII.F3-19 VII.F4-15 VII.G-22 U1 o VII.H2-20 15 BWRI Steel reactor coolant pump Loss of material due to Lubricating Oil Analysis Yes, detection of A-83 VII.G-26 PWR oil collection system piping, general, pitting, and and One-Time Inspection aging effects is to tubing, and valve bodies crevice corrosion be evaluated exposed to lubricating oil 16 BWRI Steel reactor coolant pump Loss of material due to Lubricating Oil Analysis Yes, detection of A-82 VII.G-27 PWR oil collection system tank general, pitting, and and One-Time Inspection aging effects is to exposed to lubricating oil crevice corrosion to evaluate the thickness be evaluated of the lower portion of the tank 17 BWR Steel piping, piping Loss of material due to Water Chemistry and Yes, detection of A-35 VII.E3-18 components, and piping general, pitting, and One- Time Inspection aging effects is to VII.E4-17 elements exposed to treated crevice corrosion be evaluated (f)

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Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 18 BWRJ Stainless steel and steel Loss of materiall Plant specific Yes, plant specific A-27 VII.H2-2 PWR diesel engine exhaust piping, general (steel only),

piping components, and pitting and crevice piping elements exposed to corrosion diesel exhaust 19 BWRI Steel (with or without coating Loss of material due to Buried Piping and Tanks No A-01 VII.C1-18 PWR or wrapping) piping, piping general, pitting, Surveillance VII.C3-9 components, and piping crevice, and VII.G-25 elements exposed to soil microbiologically or VII.H1-9 influenced corrosion Buried Piping and Tanks Yes, detection of Inspection aging effects and operating experience are to be further evaluated 20 BWRI Steel piping, piping Loss of material due to Fuel Oil Chemistry and Yes, detection of A-3D VII.H1-10 PWR components, piping general, pitting, One- Time Inspection aging effects is to VII.H2-24 elements, and tanks exposed crevice, and be evaluated to fuel oil microbiologically influenced corrosion, and fouling 21 BWRI Steel heat exchanger Loss of material due to Lubricating Oil Analysis Yes, detection of AP-39 VII.H2-5 z PWR components exposed to general, pitting, and One-Time Inspection aging effects is to C lubricating oil crevice, and be evaluated

0 m microbiologically Gl influenced corrosion, and fouling Q.

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0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 22 BWR/ Steel with elastomer lining or Loss of material due to Water Chemistry and Yes, detection of A-39 VII.A3-9 PWR stainless steel cladding pitting and crevice One- Time Inspection aging effects is to A-40 VII.A4-12 piping, piping components, corrosion (only for be evaluated and piping elements exposed steel after to treated water and treated lining/cladding borated water degradation) 23 BWR Stainless steel and steel with Loss of material due to Water Chemistry and Yes, detection of A-70 VII.A4-2 stainless steel cladding heat pitting and crevice One- Time Inspection aging effects is to exchanger components corrosion be evaluated exposed to treated water 24 BWR/ Stainless steel and aluminum Loss of material due to Water Chemistry and Yes, detection of A-58 VII.A4-11 PWR piping, piping components, pitting and crevice One- Time Inspection aging effects is to VII.E3-15 and piping elem ents exposed corrosion be evaluated VII.E4-14 to treated water AP-38 VII.A4-5 VII.E3-7 VII.E4-4 25 BWR/ Copper alloy HVAC piping, Loss of material due to A plant-specific aging Yes, plant specific A-46 VII.F1-16 PWR piping components, piping pitting and crevice management program is VII.F2-14 elements exposed to corrosion to be evaluated. VII.F3-16 condensation (external) VII.F4-12 26 BWR/ Copper alloy piping, piping Loss of material due to Lubricating Oil Analysis Yes, detection of AP-47 VII.C1-8 PWR components, and piping pitting and crevice and One-Time Inspection aging effects is to VII.C2-5 elements exposed to corrosion be evaluated VII.E1-12 lubricating oil VII.E4-6 VII.G-11 VII.H2-10 (f)

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Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 27 BWRI Stainless steel HVAC Loss of material due to A plant-specific aging Yes, plant specific A-D9 VII.F1-1 PWR ducting and aluminum HVAC pitting and crevice management program is VII.F2-1 piping, piping components corrosion to be evaluated. VII.F3-1 and piping elements exposed AP-74 VII.F1-14 to condensation VII.F2-12 VII.F3-14 VII.F4-1D 28 BWRI Copper alloy fire protection Loss of material due to A plant-specific aging Yes, plant specific AP-78 VII.G-9 PWR piping, piping components, pitting and crevice management program is and piping elements exposed corrosion to be evaluated.

to condensation (internal) 29 BWRI Stainless steel piping, piping Loss of material due to A plant-specific aging Yes, plant specific AP-56 VII.C1-16 PWR components, and piping pitting and crevice management program is VII.C3-8 elements exposed to soil corrosion to be evaluated. VII.G-2D VII.H1-7 VII.H2-19 30 BWR Stainless steel piping, piping Loss of material due to Water Chemistry and Yes, detection of AP-73 VII.E2-1 components, and piping pitting and crevice One- Time Inspection aging effects is to elements exposed to sodium corrosion be evaluated pentaborate solution 31 BWR Copper alloy piping, piping Loss of material due to Water Chemistry and Yes, detection of AP-64 VII.A4-7 components, and piping pitting, crevice, and One- Time Inspection aging effects is to VII.E3-9 elements exposed to treated galvanic corrosion be evaluated VII.E4-7 z water C

0 rn 32 BWRI Stainless steel, aluminum Loss of material due to Fuel Oil Chemistry and Yes, detection of AP-35 VII.H1-1 Gl PWR and copper alloy piping, pitting, crevice, and One- Time Inspection aging effects is to VII.H2-7 piping components, and microbiologically be evaluated AP-44 VII.G-1D piping elements exposed to influenced corrosion VII.H1-3 Q.

fuel oil VII.H2-9 AP-54 VII.G-17 VII.H1-6

0 (D VII.H2-16 OAGI0000203_063

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 33 BWR/ Stainless steel piping, piping Loss of material due to Lubricating Oil Analysis Yes, detection of AP-59 VIIC1-14 PWR components, and piping pitting, crevice, and and One-Time Inspection aging effects is to VIIC2-12 elements exposed to microbiologically be evaluated VIIE1-15 lubricating oil influenced corrosion VIIE4-12 VIIG-18 VIIH2-17 34 BWR/ Elastomer seals and Loss of material due to Plant specific Yes, plant specific A-18 VIIF1-6 PWR components exposed to air - Wear VIIF2-6 indoor uncontrolled (internal VI I F3-6 or external) VI I F4-5 A-73 VIIF1-5 VIIF2-5 VI I F3-5 VIIF4-4 35 PWR Steel with stainless steel Loss of material/ A plant-specific aging Yes, verify plant- AP-85 VIIE1-21 cladding pump casing cladding breach management program is specific program exposed to treated borated to be evaluated. addresses water cladding breach Reference NRC Information Notice 94-63, "Boric Acid Corrosion of Charging Pump Casings Caused by Cladding Cracks."

36 BWR Boraflex spent fuel storage Reduction of neutron- Boraflex Monitoring No A-87 VIIA2-2 racks neutron-absorbing absorbing capacity sheets exposed to treated due to boraflex (f) water degradation (D

~ 37 BWR Stainless steel piping, piping Cracking due to stress BWR Reactor Water No A-60 VIIE3-16 3 components, and piping corrosion cracking, Cleanup System 0"

~

elements exposed to treated intergranular stress water >60"C (>140"F) corrosion cracking

'"oo U1 OAGI0000203_064

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 38 BWR Stainless steel piping, piping Cracking due to stress BWR Stress Corrosion No A-61 VII.E4-15 components, and piping corrosion cracking Cracking and Water elements exposed to treated Chemistry water >60°C (>140°F) 39 BWR Stainless steel BWR spent Cracking due to stress Water Chemistry No A-96 VII.A2-6 fuel storage racks exposed corrosion cracking to treated water >60°C

(>140°F) 40 BWRI Steel tanks in diesel fuel oil Loss of material due to Aboveground Steel Tanks No A-95 VII.H1-11 PWR system exposed to air - general, pitting, and outdoor (external) crevice corrosion 41 BWRI High-strength steel closure Cracking due to cyclic Bolting Integrity No A-04 V lie 3 PWR bolting exposed to air with loading, stress steam or water leakage corrosion cracking 42 BWRI Steel closure bolting Loss of material due to Bolting Integrity No A-03 VII. 1-6 PWR exposed to air with steam or general corrosion water leakage 43 BWRI Steel bolting and closure Loss of material due to Bolting Integrity No AP-27 V lie 4 PWR bolting exposed to air - general, pitting, and AP-28 Vlle1 indoor uncontrolled (external) crevice corrosion or air - outdoor (External) 44 BWRI Steel compressed air system Loss of material due to Bolting Integrity No A-103 VIID-1 z PWR closure bolting exposed to general, pitting, and C

0 condensation crevice corrosion rn Gl 45 BWRI Steel closure bolting Loss of preload due to Bolting Integrity No AP-26 V lie 5 PWR exposed to air - indoor thermal effects, gasket uncontrolled (external) creep, and self-Q.

loosening

0 (D

OAGI0000203_065

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 46 BWRI Stainless steel and stainless Cracking due to stress Closed-Cycle Cooling No A-68 VII.E3-2 PWR clad steel piping, piping corrosion cracking Water System AP-60 VII.C2-11 components, piping VII.E3-13 elements, and heat VII.E4-11 exchanger components exposed to closed cycle cooling water >60°C

(>140°F) 47 BWRI Steel piping, piping Loss of material due to Closed-Cycle Cooling No A-25 VII.C2-14 PWR components, piping general, pitting, and Water System VII.F1-20 elements, tanks, and heat crevice corrosion VII.F2-18 exchanger components VII.F3-20 exposed to closed cycle VII.F4-16 cooling water VII.H2-23 U1 OJ 48 BWRI Steel piping, piping Loss of material due to Closed-Cycle Cooling No A-63 VII.A3-3 PWR components, piping general, pitting, Water System VII.A4-3 elements, tanks, and heat crevice, and galvanic VII.C2-1 exchanger components corrosion VII.E1-6 exposed to closed cycle VII.E3-4 cooling water VII.E4-2 VII.F1-11 VII.F2-9 VII.F3-11 VI I. F4-8 49 BWRI Stainless steel; steel with Loss of material due to Closed-Cycle Cooling No A-67 VII.E3-1 PWR stainless steel cladding heat microbiologically Water System VII.E4-1 exchanger components influenced corrosion (f) exposed to closed cycle (D

cooling water

~

3 0"

~

'"oo U1 OAGI0000203_066

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 50 BWRI Stainless steel piping, piping Loss of material due to Closed-Cycle Cooling No A-52 VIIC2-10 PWR components, and piping pitting and crevice Water System elements exposed to closed corrosion cycle cooling water 51 BWRI Copper alloy piping, piping Loss of material due to Closed-Cycle Cooling No AP-12 VIIA3-5 PWR components, piping pitting, crevice, and Water System VIIA4-6 elements, and heat galvanic corrosion VIIC2-4 exchanger components VIIE1-11 exposed to closed cycle VIIE3-8 cooling water VIIE4-5 VIIF1-15 VIIF2-13 VIIF3-15 VIIF4-11 VIIH1-2 VIIH2-8 AP-34 VIIE1-2 VIIF1-8 VI I F3-8 52 BWRI Steel, stainless steel, and Reduction of heat Closed-Cycle Cooling No AP-63 VIIC2-3 PWR copper alloy heat exchanger transfer due to fouling Water System VIIE3-5 tubes exposed to closed VIIE4-3 cycle cooling water AP-77 VIIF1-13 VIIF2-11 z VIIF3-13 C

0 VI I F4-9 m

Gl AP-80 VIIC2-2 VIIF1-12 VIIF2-10

< VIIF3-12 Q.

0 (D

OAGI0000203_067

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 53 BWRI Steel compressed air system Loss of material due to Compressed Air No A-26 VIID-2 PWR piping, piping components, general and pitting Monitoring and piping elements exposed corrosion to condensation (internal) 54 BWRI Stainless steel compressed Loss of material due to Compressed Air No AP-81 VIID-4 PWR air system piping, piping pitting and crevice Monitoring com ponents, and pi pi ng corrosion elements exposed to internal condensation 55 BWRI Steel ducting closure bolting Loss of material due to External Surfaces No A-105 VII.F1-4 PWR exposed to air - indoor general corrosion Monitoring VI I. F2-4 uncontrolled (external) VI I. F3-4 VI I. F4-3 U1 VU7 OJ 56 BWRI Steel HVAC ducting and Loss of material due to External Surfaces No A-10 VII.F1-2 PWR components external general corrosion Monitoring VII.F2-2 surfaces exposed to air - VI I. F3-2 indoor uncontrolled (external) VII.F4-1 57 BWRI Steel piping and components Loss of material due to External Surfaces No A-80 VIID-3 PWR external surfaces exposed to general corrosion Monitoring air - indoor uncontrolled (External) 58 BWRI Steel external surfaces Loss of material due to External Surfaces No A-77 VU8 PWR exposed to air - indoor general corrosion Monitoring A-78 VII. 1-9 uncontrolled (external), air - A-81 VU11 outdoor (external), and (f) condensation (external)

(D

~

3 0"

~

'"oo U1 OAGI0000203_068

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 59 BWRI Steel heat exchanger Loss of material due to External Surfaces No AP-40 VILG-6 PWR components exposed to air - general, pitting, and Monitoring VILH2-4 indoor uncontrolled (external) crevice corrosion AP-41 VILF1-10 or air -outdoor (external) VILF2-S VILF3-10 VILF4-7 VILG-5 VILH2-3 60 BWRI Steel piping, piping Loss of material due to External Surfaces No A-24 VILH1-S PWR components, and piping general, pitting, and Monitoring elements exposed to air - crevice corrosion outdoor (external) 61 BWRI Elastomer fire barrier Increased hardness, Fire Protection No A-19 VILG-1 PWR penetration seals exposed to shrinkage and loss of A-20 VILG-2 air - outdoor or air - indoor strength due to uncontrolled weathering 62 BWRI Aluminum piping, piping Loss of material due to Fire Protection No AP-S3 VILG-S PWR components, and piping pitting and crevice elements exposed to raw corrosion water 63 BWRI Steel fire rated doors Loss of material due to Fire Protection No A-21 VILG-3 PWR exposed to air - outdoor or Wear A-22 VILG-4 air - indoor uncontrolled z

C 64 BWRI Steel piping, piping Loss of material due to Fire Protection and Fuel No A-2S VILG-21

0 rn PWR components, and piping general, pitting, and Oil Chemistry Gl elements exposed to fuel oil crevice corrosion 65 BWRI Reinforced concrete Concrete cracking and Fire Protection and No A-90 VILG-2S PWR structural fire barriers - spalling due to Structures Monitoring Q. walls, ceilings and floors aggressive chemical Program exposed to air - indoor attack, and reaction

0 uncontrolled with aggregates (D

OAGI0000203_069

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 66 BWRI Reinforced concrete Concrete cracking and Fire Protection and No A-92 VILG-30 PWR structural fire barriers - spalling due to freeze Structures Monitoring walls, ceilings and floors thaw, aggressive Program exposed to air - outdoor chemical attack, and reaction with aggregates 67 BWRI Reinforced concrete Loss of material due to Fire Protection and No A-91 VILG-29 PWR structural fire barriers - corrosion of embedded Structures Monitoring A-93 VILG-31 walls, ceilings and floors steel Program exposed to air - outdoor or air - indoor uncontrolled 68 BWRI Steel piping, piping Loss of material due to Fire Water System No A-33 VILG-24 PWR components, and piping general, pitting, OJ elements exposed to raw crevice, and o

water microbiologically influenced corrosion, and fouling 69 BWRI Stainless steel piping, piping Loss of material due to Fire Water System No A-55 VILG-19 PWR components, and piping pitting and crevice elements exposed to raw corrosion, and fouling water 70 BWRI Copper alloy piping, piping Loss of material due to Fire Water System No A-45 VILG-12 PWR components, and piping pitting, crevice, and elements exposed to raw microbiologically water influenced corrosion, and fouling (f) 71 BWRI Steel piping, piping Loss of material due to Inspection of Internal No A-23 VILG-23 (D

PWR components, and piping general, pitting, and Surfaces in Miscellaneous VILH2-21

~ elements exposed to moist crevice corrosion Piping and Ducting 3

0" air or condensation (Internal) Components

~

'"oo U1 OAGI0000203_070

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 72 BWR/ Steel HVAC ducting and Loss of material due to Inspection of Internal No A-08 VII.F1-3 PWR components internal general, pitting, Surfaces in Miscellaneous VII.F2-3 surfaces exposed to crevice, and (for drip Piping and Ducting VI I. F3-3 condensation (Internal) pans and drain lines) Components VI I. F4-2 microbiologically influenced corrosion 73 BWR/ Steel crane structural girders Loss of material due to Inspection of Overhead No A-07 VII.B-3 PWR in load handling system general corrosion Heavy Load and Light exposed to air- indoor Load (Related to uncontrolled (external) Refueling) Handling Systems 74 BWR/ Steel cranes - rails exposed Loss of material due to Inspection of Overhead No A-05 VII.B-1 PWR to air - indoor uncontrolled Wear Heavy Load and Light (external) Load (Related to Refueling) Handling Systems 75 BWR/ Elastomer seals and Hardening and loss of Open-Cycle Cooling No AP-75 VII.C1-1 PWR components exposed to raw strength due to Water System AP-76 VII.C1-2 water elastomer degradation; loss of material due to erosion 76 BWR/ Steel piping, piping Loss of material due to Open-Cycle Cooling No A-38 VII.C1-19 PWR components, and piping general, pitting, Water System VII.C3-10 z elements (without crevice, and VII.H2-22 C

0 lining/coating or with microbiologically m

Gl degraded lining/coating) influenced corrosion, exposed to raw water fouling, and lining/coating

< degradation Q.

0 (D

OAGI0000203_071

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 77 BWRI Steel heat exchanger Loss of material due to Open-Cycle Cooling No A-64 VIIC1-5 PWR components exposed to raw general, pitting, Water System water crevice, galvan ic, and microbiologically influenced corrosion, and fouling 78 BWRI Stainless steel, nickel alloy, Loss of material due to Open-Cycle Cooling No A-43 VIIC3-2 PWR and copper alloy piping, pitting and crevice Water System A-53 VIIC3-7 piping components, and corrosion AP-53 VIIC1-13 piping elements exposed to VIIC3-6 raw water 79 BWRI Stainless steel piping, piping Loss of material due to Open-Cycle Cooling No A-54 VIIC1-15 PWR components, and piping pitting and crevice Water System elements exposed to raw corrosion, and fouling water 80 BWRI Stainless steel and copper Loss of material due to Open-Cycle Cooling No AP-45 VIIH2-11 PWR alloy piping, piping pitting, crevice, and Water System AP-55 VIIH2-18 components, and piping microbiologically elements exposed to raw influenced corrosion water 81 BWRI Copper alloy piping, piping Loss of material due to Open-Cycle Cooling No A-44 VIIC1-9 PWR components, and piping pitting, crevice, and Water System elements, exposed to raw microbiologically water influenced corrosion, and fouling 82 BWRI Copper alloy heat exchanger Loss of material due to Open-Cycle Cooling No A-65 VIIC1-3 (f) PWR components exposed to raw pitting, crevice, Water System (D

water galvan ic, and

~ microbiologically 3

0" influenced corrosion,

~ and fouling

'"oo U1 OAGI0000203_072

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 83 BWRI Stainless steel and copper Reduction of heat Open-Cycle Cooling No A-72 VIIC1-6 PWR alloy heat exchanger tubes transfer due to fouling Water System AP-61 VIIC1-7 exposed to raw water VIIC3-1 VIIG-7 VIIH2-6 84 BWRI Copper alloy> 15% Zn Loss of material due to Selective Leaching of No A-47 VIIC1-10 PWR piping, piping components, selective leaching Materials VIIC3-3 piping elements, and heat VIIG-13 exchanger components VIIH2-13 exposed to raw water, A-66 VIIC1-4 treated water, or closed cycle AP-32 VIIA4-9 cooling water VIIC2-7 VIIE3-11 VIIE4-9 AP-43 VIIA3-6 VIIA4-8 VIIC2-6 VIIE1-13 VIIE3-10 VIIE4-8 VIIF1-17 VIIF2-15 VIIF3-17 VIIF4-13 z VIIH1-4 C VIIH2-12

0 m AP-65 VIIE1-3 Gl VIIF1-9 VI I F3-9 Q.

0 (D

OAGI0000203_073

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 85 BWRI Gray cast iron piping, piping Loss of material due to Selective Leaching of No A-02 VIIC1-12 PWR components, and piping selective leaching Materials VIIC3-5 elements exposed to soil, VIIG-15 raw water, treated water, or VIIH1-5 closed-cycle cooling water VIIH2-15 A-50 VIIC2-8 VIIF3-18 A-51 VIIC1-11 VIIC3-4 VIIG-14 VIIH2-14 AP-31 VIIA3-7 VIIA4-10 VIIC2-9 VIIE1-14 VIIE3-12 VIIE4-10 VIIF1-18 VIIF2-16 VIIF4-14 VIIG-16 86 BWRI Structural steel (new fuel Loss of material due to Structures Monitoring No A-94 VIIA1-1 PWR storage rack assembly) general, pitting, and Program exposed to air - indoor crevice corrosion uncontrolled (external) 87 PWR Boraflex spent fuel storage Reduction of neutron- Boraflex Monitoring No A-86 VIIA2-4 racks neutron-absorbing absorbing capacity sheets exposed to treated due to boraflex (f)

(D borated water degradation

~

3 0"

~

'"oo U1 OAGI0000203_074

Table 3. Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of the GALL Report Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item 88 PWR Aluminum and copper alloy Loss of material due to Boric Acid Corrosion No AP-1 VII.A3-4

>15% Zn piping, piping Boric acid corrosion VII.E1-10 components, and piping AP-66 VU12 elements exposed to air with borated water leakage 89 PWR Steel bolting and external Loss of material due to Boric Acid Corrosion No A-79 VII.A3-2 surfaces exposed to air with Boric acid corrosion VII.E1-1 borated water leakage VU10 A-102 VU2 90 PWR Stainless steel and steel with Cracking due to stress Water Chemistry No A-56 VII.A3-10 stainless steel cladding corrosion cracking A-97 VII.A2-7 piping, piping components, AP-82 VII.E1-20 piping elements, tanks, and fuel storage racks exposed to treated borated water

>60°C (> 140° F) 91 PWR Stainless steel and steel with Loss of material due to Water Chemistry No AP-79 VII.A2-1 stainless steel cladding pitting and crevice VII.A3-8 piping, piping components, corrosion VII.E1-17 and piping elements exposed to treated borated water 92 BWRI Galvanized steel piping, None None NA - No AEM or AP-13 VII.J.6 PWR piping components, and AMP z piping elements exposed to C

0 air - indoor uncontrolled rn Gl 93 BWRI Glass piping elements None None NA - NoAEM or AP-14 VI1.J.8 PWR exposed to air, air - indoor AMP AP-15 VI1.J.10 uncontrolled (external), fuel AP-48 VI1.J.7 Q.

oil, lubricating oil, raw water, AP-49 VI1.J.9 treated water, and treated AP-50 VI1.J.11 borated water AP-51 VI1.J.13

0 (D AP-52 VI1.J.12 OAGI0000203_075

z Table 3. Summary of Aging Management Programs for the Auxiliary Systems C

0 Evaluated in Chapter VII of the GALL Report m

Gl Further Related Aging Aging Management Unique 10 Type Component Evaluation Generic Effect/Mechanism Programs Item Recommended Item Q. 94 BWRI Stainless steel and nickel None None NA - NoAEM or AP-16 VII.J.14 PWR alloy piping, piping AMP AP-17 VI1.J.15 components, and piping elements exposed to air -

indoor uncontrolled (external) 95 BWRI Steel and aluminum piping, None None NA - NoAEM or AP-2 VI1.J.20 PWR piping components, and AMP AP-36 VI1.J.1 piping elements exposed to air - indoor controlled (external) 96 BWRI Steel and stainless steel None None NA - NoAEM or AP-3 VI1.J.21 PWR piping, piping components, AMP AP-19 VI1.J.17 and piping elements in OJ concrete OJ 97 BWRI Steel, stainless steel, None None NA - NoAEM or AP-6 VI1.J.23 PWR aluminum, and copper alloy AMP AP-9 VI1.J.4 piping, piping components, AP-22 VI1.J.19 and piping elements exposed AP-37 VI1.J.2 to gas 98 BWRI Steel, stainless steel, and None None NA - NoAEM or AP-4 VI1.J.22 PWR copper alloy piping, piping AMP AP-8 VI1.J.3 components, and piping AP-20 VI1.J.18 elements exposed to dried air 99 PWR Stainless steel and copper None None NA - NoAEM or AP-11 VI1.J.5 alloy <15% Zn piping, piping AMP AP-18 VI1.J.16 (f) components, and piping (D

elements exposed to air with

~ borated water leakage 3

0"

~

'"oo U1 OAGI0000203_076

(f)

(D (D

3 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 0-Evaluated in Chapter VIII of the GALL Report

~

'"oo 10 Type Component Aging Aging Further Evaluation Related Unique U1 Management Generic EffectlMechanism Recommended Item Programs Item 1 BWRI Steel piping, piping components, Cumulative fatigue TLAA, evaluated in Yes, TLAA S-08 VIII.B1-10 PWR and piping elements exposed to damage accordance with 10 VIII.B2-5 steam or treated water CFR 5421(c) S-11 VIIID1-7 VIIID2-6 VIII.G-37 2 BWRI Steel piping, piping components, Loss of material due to Water Chemistry Yes, detection of aging S-04 VIII.A-15 PWR and piping elements exposed to general, pitting and and One- Time effects is to be VIII.C-3 steam crevice corrosion Inspection evaluated S-06 VIII.A-16 VIII.C-4 3 PWR Steel heat exchanger components Loss of material due to Water Chemistry Yes, detection of aging S-19 VIII.E-37 exposed to treated water general, pitting and and One- Time effects is to be VIII.F-28 crevice corrosion Inspection evaluated 4 BWRI Steel piping, piping components, Loss of material due to Water Chemistry Yes, detection of aging S-09 VIII.B2-6 PWR and piping elements exposed to general, pitting and and One- Time effects is to be VIII.C-6 treated water crevice corrosion Inspection evaluated VIIID2-7 VIII.E-33 S-10 VIII.B1-11 VIII.C-7 VIIID1-8 VIII.E-34 VIII.F-25 z

C VIII.G-38

0 m 5 BWR Steel heat exchanger components Loss of material due to Water Chemistry Yes, detection of aging S-18 VIII.E-7 Gl exposed to treated water general, pitting, and One- Time effects is to be crevice, and galvanic Inspection evaluated corrosion Q.

0 (D

OAGI0000203_077

z C

0 m Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Gl Evaluated in Chapter VIII of the GALL Report Aging Related Aging Further Evaluation Unique

< 10 Type Component Management Generic Q. EffectlMechanism Recommended Item Programs Item 6 BWRI Steel and stainless steel tanks Loss of material due to Water Chemistry Yes, detection of aging S-13 VIILE-40

0 (D PWR exposed to treated water general (steel only) and One- Time effects is to be VIILG-41 pitting and crevice Inspection evaluated corrosion 7 BWRI Steel piping, piping components, Loss of material due to Lubricating Oil Yes, detection of aging SP-25 VIILA-14 PWR and piping elements exposed to general, pitting and Analysis and One- effects is to be VIIID1-6 lubricating oil crevice corrosion Time Inspection evaluated VIIID2-5 VIILE-32 VIILG-35 8 BWRI Steel piping, piping components, Loss of material due to Plant specific Yes, plant specific S-12 VIILG-36 PWR and piping elements exposed to general, pitting, OJ raw water crevice, and OJ m icrobiolog ically-influenced corrosion, and fouling 9 BWRI Stainless steel and copper alloy Reduction of heat Water Chemistry Yes, detection of aging SP-40 VIILE-13 PWR heat exchanger tubes exposed to transfer due to fouling and One- Time effects is to be VIILF-10 treated water Inspection evaluated SP-58 VIILE-10 VIILF-7 VIILG-10 10 BWRI Steel, stainless steel, and copper Reduction of heat Lubricating Oil Yes, detection of aging SP-53 VIILG-8 PWR alloy heat exchanger tubes transfer due to fouling Analysis and One- effects is to be SP-62 VIILG-12 exposed to lubricating oil Time Inspection evaluated SP-63 VIILG-15 (f)

(D

~

3 0"

~

'"oo U1 OAGI0000203_078

(f)

(D (D

3 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 0-Evaluated in Chapter VIII of the GALL Report

~

'"oo 10 Type Component Aging Aging Further Evaluation Related Unique U1 Management Generic EffectlMechanism Recommended Item Programs Item 11 BWRI Buried steel piping, piping Loss of material due to Buried Piping and No S-01 VIILE-1 PWR components, piping elements, and general, pitting, Tanks Surveillance VIILG-1 tanks (with or without coating or crevice, and wrapping) exposed to soil m icrobiolog ically- or influenced corrosion Buried Piping and Yes, detection of aging Tanks Inspection effects and operating experience are to be further evaluated 12 BWRI Steel heat exchanger components Loss of material due to Lubricating Oil Yes, detection of aging S-17 VIILG-6 PWR exposed to lubricating oil general, pitting, Analysis and One- effects is to be OJ crevice, and Time Inspection evaluated CD m icrobiolog ically-influenced corrosion 13 BWR Stainless steel piping, piping Cracking due to stress Water Chemistry Yes, detection of aging SP-45 VIILA-11 components, piping elements corrosion cracking and One- Time effects is to be VIILB2-1 exposed to steam Inspection evaluated 14 BWRI Stainless steel piping, piping Cracking due to stress Water Chemistry Yes, detection of aging S-39 VIILF-3 PWR components, piping elements, corrosion cracking and One- Time effects is to be SP-17 VIILB1-5 tanks, and heat exchanger Inspection evaluated VIILC-2 components exposed to treated VIIID1-5 z

C water >60°C (>140°F) VilLE-3~

0 m VIILF-24 Gl VIILG-33 SP-19 VIILE-31 SP-42 VIILE-38 Q.

0 (D

OAGI0000203_079

z C

0 m Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Gl Evaluated in Chapter VIII of the GALL Report Aging Related Aging Further Evaluation Unique

< 10 Type Component Management Generic Q. EffectlMechanism Recommended Item Programs Item 15 BWRI Aluminum and copper alloy piping, Loss of material due to Water Chemistry Yes, detection of aging SP-24 VIIID1-1

0 (D PWR piping components, and piping pitting and crevice and One- Time effects is to be VIIID2-1

< VIILE-15 elements exposed to treated water corrosion Inspection evaluated VIILF-12 VIILG-17 SP-61 VIILA-5 VIILF-15 16 BWRI Stainless steel piping, piping Loss of material due to Water Chemistry Yes, detection of aging S-21 VIILE-4 PWR components, and piping elements; pitting and crevice and One- Time effects is to be S-22 VIILE-36 tanks, and heat exchanger corrosion Inspection evaluated VIILF-27 components exposed to treated SP-16 VIILB1-4 water VIILC-1 VIIID1-4 VIIID2-4 VIILE-29 VIILF-23 VIILG-32 17 BWRI Stainless steel piping, piping Loss of material due to Plant specific Yes, plant specific SP-37 VIILE-28 PWR components, and piping elements pitting and crevice VIILG-31 exposed to soil corrosion 18 BWRI Copper alloy piping, piping Loss of material due to Lubricating Oil Yes, detection of aging SP-32 VIILA-3 PWR components, and piping elements pitting and crevice Analysis and One- effects is to be VIIID1-2 exposed to lubricating oil corrosion Time Inspection evaluated VIIID2-2 VIILE-17 VIILG-19 (f)

(D

~

3 0"

~

'"oo U1 OAGI0000203_080

(f)

(D (D

3 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 0-Evaluated in Chapter VIII of the GALL Report

~

'"oo 10 Type Component Aging Aging Further Evaluation Related Unique U1 Management Generic EffectlMechanism Recommended Item Programs Item 19 BWRI Stainless steel piping, piping Loss of material due to Lubricating Oil Yes, detection of aging S-20 VIII.G-3 PWR components, piping elements, and pitting, crevice, and Analysis and One- effects is to be SP-38 VIII.A-9 heat exchanger components m icrobiolog ically- Time Inspection evaluated VIIID1-3 exposed to lubricating oil influenced corrosion VIIID2-3 VIII.E-26 VIII.G-29 20 BWRI Steel tanks exposed to air - Loss of materiall Aboveground Steel No S-31 VIII.E-39 PWR outdoor (external) general, pitting, and Tanks VIII.G-40 crevice corrosion 21 BWRI High-strength steel closure bolting Cracking due to cyclic Bolting Integrity No S-03 VIII.H-3 PWR exposed to air with steam or water loading, stress leakage corrosion cracking 22 BWRI Steel bolting and closure bolting Loss of material due to Bolting Integrity No S-02 VIII.H-6 PWR exposed to air with steam or water general, pitting and S-32 VIII.H-1 leakage, air - outdoor (external), crevice corrosion; loss S-33 VIII.H-5 or air - indoor uncontrolled of preload due to S-34 VIII.H-4 (external) ; thermal effects, gasket creep, and self-loosening 23 BWRI Stainless steel piping, piping Cracking due to stress Closed-Cycle No SP-54 VIII.E-25 z PWR components, and piping elements corrosion cracking Cooling Water VIII.F-21 C

0 exposed to closed-cycle cooling System VIII.G-28 rn water >60°C (>140°F)

Gl 24 BWRI Steel heat exchanger components Loss of material due to Closed-Cycle No S-23 VIII.A-1 PWR exposed to closed cycle cooling general, pitting, Cooling Water VIII.E-5

< water crevice, and galvanic System VIII.F-4 Q. VIII.G-5 corrosion

0 (D

OAGI0000203_081

z C

0 m Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Gl Evaluated in Chapter VIII of the GALL Report Aging Related Aging Further Evaluation Unique

< 10 Type Component Management Generic Q. EffectlMechanism Recommended Item Programs Item 25 BWRI Stainless steel piping, piping Loss of material due to Closed-Cycle No S-25 VIILE-2

0 (D PWR components, piping elements, and pitting and crevice Cooling Water VIILF-1

< VIILG-2 heat exchanger components corrosion System exposed to closed cycle cooling SP-39 VIILE-24 water VIILF-20 VIILG-27 26 BWRI Copper alloy piping, piping Loss of material due to Closed-Cycle No SP-S VIILE-16 PWR components, and piping elements pitting, crevice, and Cooling Water VIILF-13 exposed to closed cycle cooling galvanic corrosion System VIILG-1S water 27 BWRI Steel, stainless steel, and copper Reduction of heat Closed-Cycle No SP-41 VIILE-11 PWR alloy heat exchanger tubes transfer due to fouling Cooling Water VIILF-S exposed to closed cycle cooling System VIILG-11 water SP-57 VIILE-S SP-64 VIILA-2 VIILE-14 VIILF-11 VIILG-14 2S BWRI Steel external surfaces exposed to Loss of material due to External Su rfaces No S-29 VIILH-7 PWR air - indoor uncontrolled (external), general corrosion Monitoring S-41 VIILH-S condensation (external), or air S-42 VIILH-10 outdoor (external)

(f)

(D

~

3 0"

~

'"oo U1 OAGI0000203_082

(f)

(D (D

3 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 0-Evaluated in Chapter VIII of the GALL Report

~

'"oo 10 Type Component Aging Aging Further Evaluation Related Unique U1 Management Generic EffectlMechanism Recommended Item Programs Item 29 BWRI Steel piping, piping components, Wall thinning due to Flow-Accelerated No S-15 VIILA-17 PWR and piping elements exposed to flow-accelerated Corrosion VIILB1-9 steam or treated water corrosion VIILB2-4 VIILC-5 S-16 VIIID1-9 VIIID2-8 VIILE-35 VIILF-26 VIILG-39 30 BWRI Steel piping, piping components, Loss of material due to Inspection of No SP-59 VIILB1-6 PWR and piping elements exposed to air general, pitting, and Internal Surfaces in SP-60 VIILB1-7 outdoor (internal) or condensation crevice corrosion Miscellaneous VIILG-34 (internal) Piping and Ducting Components 31 BWRI Steel heat exchanger components Loss of material due to Open-Cycle No S-24 VIILE-6 PWR exposed to raw water general, pitting, Cooling Water VIILF-5 crevice, galvanic, and System VIILG-7 m icrobiolog ically-influenced corrosion, and fouling 32 BWRI Stainless steel and copper alloy Loss of material due to Open-Cycle No SP-31 VIILA-4 z

C PWR piping, piping components, and pitting, crevice, and Cooling Water VIILE-18

0 rn piping elements exposed to raw m icrobiolog ically- System VIILF-14 Gl water influenced corrosion VIILG-20 SP-36 VIILE-27 VIILF-22 Q.

VIILG-30

0 (D

OAGI0000203_083

z C

0 m Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Gl Evaluated in Chapter VIII of the GALL Report Aging Related Aging Further Evaluation Unique

< 10 Type Component Management Generic Q. EffectlMechanism Recommended Item Programs Item 33 BWRI Stainless steel heat exchanger Loss of material due to Open-Cycle No S-26 VIILE-3

0 (D PWR components exposed to raw water pitting, crevice, and Cooling Water VIILF-2

< m icrobiolog ically- VIILG-4 System influenced corrosion, and fouling 34 BWRI Steel, stainless steel, and copper Reduction of heat Open-Cycle No S-27 VIILG-16 PWR alloy heat exchanger tubes transfer due to fouling Cooling Water S-28 VIILE-12 exposed to raw water System VIILF-9 VIILG-13 SP-56 VIILE-9 VIILF-6 VIILG-9 35 BWRI Copper alloy >15% Zn piping, Loss of material due to Selective Leaching No SP-29 VIILE-19 PWR piping components, and piping selective leaching of Materials VIILF-16 elements exposed to closed cycle VIILG-21 cooling water, raw water, or SP-30 VIILA-6 treated water VIILE-20 VIILF-17 VIILG-22 SP-55 VIILE-21 VIILF-18 VIILG-23 (f)

(D

~

3 0"

~

'"oo U1 OAGI0000203_084

(f)

(D (D

3 Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 0-Evaluated in Chapter VIII of the GALL Report

~

'"oo 10 Type Component Aging Aging Further Evaluation Related Unique U1 Management Generic EffectlMechanism Recommended Item Programs Item 36 BWRI Gray cast iron piping, piping Loss of material due to Selective Leaching No SP-26 VIILE-22 PWR components, and piping elements selective leaching of Materials VIILG-25 exposed to soil, treated water, or SP-27 VIILA-8 raw water VIILE-23 VIILF-19 VIILG-26 SP-28 VIILA-7 VIILG-24 37 BWRI Steel, stainless steel, and nickel- Loss of material due to Water Chemistry No S-05 VIILB2-3 PWR based alloy piping, piping pitting and crevice S-07 VIILB1-8 components, and piping elements corrosion SP-18 VIILB1-1 exposed to steam SP-43 VIILA-12 VIILB1-3 SP-46 VIILA-13 VIILB2-2 38 PWR Steel bolting and external surfaces Loss of material due to Boric Acid No S-30 VIILH-9 exposed to air with borated water boric acid corrosion Corrosion S-40 VIILH-2 leakage 39 PWR Stainless steel piping, piping Cracking due to stress Water Chemistry No SP-44 VIILA-10 components, and piping elements corrosion cracking VIILB1-2 z exposed to steam C

0 40 BWRI Glass piping elements exposed to None None NA - No AEM or AMP SP-9 VIILI-5 rn PWR air, lubricating oil, raw water, and SP-10 VIILI-6 Gl treated water SP-33 VIILI-4 SP-34 VIILI-7 SP-35 VIILI-8 Q.

0 (D

OAGI0000203_085

z C

0 m Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System Gl Evaluated in Chapter VIII of the GALL Report Aging Related Aging Further Evaluation Unique

< 10 Type Component Management Generic Q. EffectlMechanism Recommended Item Programs Item 41 BWRI Stainless steel, copper alloy, and None None NA - No AEM or AMP SP-6 VIILI-2

0 (D PWR nickel alloy piping, piping SP-11 VIILI-9

< SP-12 VIILI-10 components, and piping elements exposed to air - indoor uncontrolled (external) 42 BWRI Steel piping, piping components, None None NA - No AEM or AMP SP-1 VIILI-13 PWR and piping elements exposed to air

- indoor controlled (external) 43 BWRI Steel and stainless steel piping, None None NA - No AEM or AMP SP-2 VIILI-14 PWR piping components, and piping SP-13 VIILI-11 elements in concrete 44 BWRI Steel, stainless steel, aluminum, None None NA - No AEM or AMP SP-4 VIILI-15 PWR and copper alloy piping, piping SP-5 VIILI-3 components, and piping elements SP-15 VIILI-12 exposed to gas SP-23 VIILI-1 (f)

(D

~

3 0"

~

'"oo U1 OAGI0000203_086

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Related Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item PWR Concrete (Reinforced and Prestressed) and Steel Containment BWR Concrete (Mark II and III) and Steel (Mark I, II, and III) Containment 1 BWRI Concrete elements: Aging of accessible lSI (lWL) and for inaccessible Yes, plant -specific, if C-03 II.A1-4 PWR walls, dome, and inaccessible concrete, an examination of the environment is C-05 II.A1-7 basemat, ring girder, concrete areas due representative sam pies of below- aggressive C-25 II.A2-4 buttresses, to aggressive grade concrete and periodic II.B3.1-1 containment (as chemical attack, monitoring of groundwater if C-26 II.B12-5 applicable) and corrosion of environment is non-aggressive. II.B2.2-5 embedded steel A plant specific program is to be C-27 II.B3.2-5 evaluated if environment is C-41 II.B1.2-2 aggressive. II.B2.2-2 C-42 II.B3.2-7 C-43 II.A2-7 II.B3.1-6 2 BWRI Concrete elements; Cracks and Structures Monitoring Program. Yes, if not within the C-06 II.B1.2-1 PWR All distortion due to If a de-watering system is relied scope of the II.B2.2-1 increased stress upon for control of settlement, applicant's structures II.B3.2-1 levels from then the licensee is to ensure monitoring program or C-36 II.A2-5 settlement proper functioning of the de- a de-watering system II.B3.1-2 watering system through the is relied upon C-37 II.A1-5 period of extended operation.

z 3 BWRI Concrete elements: Red uction in Structures Monitoring Program. Yes, if not within the C-07 II.A1-8 C

0 PWR foundation, sub- foundation strength, If a de-watering system is relied scope of the II.A2-8 m II.B12-7 Gl foundation cracking, differential upon to control erosion of applicant's structures settlement due to cement from porous concrete monitoring program or II.B2.2-7 erosion of porous subfoundations, then the a de-watering system II.B3.1-7

< concrete licensee is to ensure proper is relied upon II.B3.2-8 Q. subfoundation functioning of the de-watering system through the period of

0 extended operation.

(D OAGI0000203_087

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 4 BWRI Concrete elements: Reduction of Plant-specific Yes, plant -specific if C-08 II.A1-1 PWR dome, wall, basemat, strength and temperature limits are C-33 II.B3.2-2 ring girder, modulus due to exceeded C-34 II.A2-1 buttresses, elevated C-35 II.B1.2-3 containment, temperature II.B2.2-3 concrete fill-in C-50 II.B3.1-4 annulus (as applicable) 5 BWR Steel elements: Loss of material due lSI (IWE) and 10 CFR Part 50, Yes, if corrosion is C-19 II.B1.1-2 Drywell; torus; drywell to general, pitting Appendix J significant for II.B3.1-8 head; embedded and crevice inaccessible areas C-46 II.B12-8 shell and sand pocket corrosion II.B2.1-1 regions; drywell II.B2.2-10 support skirt; torus ring girder; downcomers; liner plate, ECCS suction header, support skirt, region shielded by diaphragm floor, suppression chamber (as applicable) 6 BWRI Steel elements: steel Loss of material due lSI (IWE) and 10 CFR Part 50, Yes, if corrosion is C-09 II.A1-11 PWR liner, liner anchors, to general, pitting Appendix J significant for II.A2-9 integral attachments and crevice inaccessible areas II.B3.2-9 corrosion 7 BWRI Prestressed Loss of prestress TLAA evaluated in accordance Yes, TLAA C-11 II.A1-9 (f) II.B2.2-8 (D

PWR containment tendons due to relaxation, with 10 CFR 5421(c)

~ shrinkage, creep, 3 and elevated 0"

temperature

~

'"oo U1 OAGI0000203_088

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 8 BWR Steel and stainless Cumulative fatigue TLAA evaluated in accordance Yes, TLAA C-21 II.B1.1-4 steel elements: vent damage (CLB with 10 CFR 5421(c) C-48 II.B2.2-14 line, vent header, fatigue analysis vent line bellows; exists) downcomers; 9 BWR/ Steel, stainless steel Cumulative fatigue TLAA evaluated in accordance Yes, TLAA C-13 II.A3-4 PWR elements, dissimilar damage (CLB with 10 CFR 5421(c) II.B4-4 metal welds: fatigue analysis C-45 II.B2.1-4 penetration sleeves, exists) penetration bellows; suppression pool shell, unbraced downcomers 10 BWR/ Stainless steel Cracking due to lSI (IWE) and 10 CFR Part 50, Yes, detection of aging C-15 II.A3-2 PWR penetration sleeves, stress corrosion Appendix J and additional effects is to be II.B4-2 penetration bellows, cracking appropriate evaluated dissimilar metal welds examinations/evaluations for bellows assemblies and dissimilar metal welds 11 BWR Stainless steel vent Cracking due to lSI (IWE) and 10 CFR Part 50, Yes, detection of aging C-22 II.B11-5 line bellows, stress corrosion Appendix J, and additional effects is to be cracking appropriate evaluated examination/evaluation for z bellows assemblies and C

0 dissimilar metal welds m

Gl Q.

0 (D

OAGI0000203_089

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 12 BWR/ Steel, stainless steel Cracking due to lSI (IWE) and 10 CFR Part 50, Yes, detection of aging C-14 II.A3-3 PWR elements, dissimilar cyclic loading Appendix J supplemented to effects is to be II.B4-3 metal welds: detect fine cracks evaluated C-44 II.B2.1-3 penetration sleeves, penetration bellows; suppression pool shell, unbraced downcomers 13 BWR Steel, stainless steel Cracking due to lSI (IWE) and 10 CFR Part 50, Yes, detection of aging C-20 II.B1.1-3 elements, dissimilar cyclic loading Appendix J supplemented to effects is to be C-47 II.B2.2-13 metal welds: torus; detect fine cracks evaluated vent line; vent header; vent line OJ bellows; downcomers o

14 BWR/ Concrete elements: Loss of material lSI (lWL) Yes, for i naccessi ble C-01 II.A1-2 PWR dome, wall, basemat (Scaling, cracking, Evaluation is needed for plants areas of plants located C-28 II.A2-2 ring girder, and spalling) due to that are located in moderate to in moderate to severe C-29 II.B3.2-3 buttresses, freeze-thaw severe weathering conditions weathering conditions containment (as (weathering index >100 day-applicable) inch/yr) (NUREG-1557) 15 BWR/ Concrete elements: Increase in porosity, lSI (lWL) for accessible areas. Yes, if concrete was C-02 II.A1-6 PWR walls, dome, permeability due to None for inaccessible areas if not constructed as C-04 II.A1-3 basemat, ring girder, leaching of calcium concrete was constructed in stated for inaccessible C-30 II.A2-6 buttresses, hydroxide; cracking accordance with the areas II.B3.1-3 containment, due to expansion recommendations in ACI C-31 II.B1.2-6 concrete fill-in and reaction with 201.2R II.B2.2-6 annulus (as aggregate C-32 II.B3.2-6 (f) II.A2-3 (D

applicable) C-38

~ C-39 II.B1.2-4 3 II.B2.2-4 0"

C-40 II.B3.2-4

~

C-51 II.B3.1-5 o

o U1 OAGI0000203_090

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 16 BWRI Seals, gaskets, and Loss of sealing and lSI (IWE) and 10 CFR Part 50, No C-18 II.A3-7 PWR moisture barriers leakage through Appendix J II.B4-7 containment due to deterioration of joi nt seals, gaskets, and moisture barriers (caulking, flashing, and other sealants) 17 BWRI Personnel airlock, Loss of leak 10 CFR Part 50, Appendix J and No C-17 II.A3-5 PWR equipment hatch and tightness in closed Plant Technical Specifications II.B4-5 CRD hatch locks, position due to hinges, and closure mechanical wear of mechanisms locks, hinges and closure mechanisms 18 BWRI Steel penetration Loss of material due lSI (IWE) and 10 CFR Part 50, No C-12 II.A3-1 PWR sleeves and to general, pitting, Appendix J II.B4-1 dissimilar metal and crevice C-16 II.A3-6 welds; personnel corrosion II.B4-6 airlock, equipment hatch and CRD hatch 19 BWR Steel elements: Cracking due to lSI (IWE) and 10 CFR Part 50, No C-24 II.B3.1-9 stainless steel stress corrosion Appendix J II.B3.2-10 z suppression chamber cracking C

0 shell (inner surface) m Gl 20 BWR Steel elements: Loss of material due lSI (IWE) and 10 CFR Part 50, No C-49 II.B1.2-10 suppression chamber to general, pitting, Appendix J II.B2.2-12 liner (interior surface) and crevice Q.

corrosion

0 (D

OAGI0000203_091

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 21 BWR Steel elements: Fretting or lock up lSI (IWE) No C-23 II.B1.1-1 drywell head and due to mechanical II.B12-9 downcomer pipes wear II.B2.1-2 II.B2.2-11 22 BWRI Prestressed Loss of material due lSI (lWL) No C-10 II.A1-10 PWR containm en!: tendons to corrosion II.B2.2-9 and anchorage components Safety-Related and Other Structures; and Component Supports I 23 BWRI All Groups except Cracking, loss of Structures Monitoring Program Yes, if not within the T-01 III.A1-6 PWR Group 6: interior and bond, and loss of scope of the III.A2-6 above grade exterior material (spalling, applicant's structures III.A3-6 concrete scaling) due to monitoring program III.A5-6 corrosion of III.A7-5 embedded steel III.AS-5 III.A9-5 24 BWRI All Groups except Increase in porosity Structures Monitoring Program Yes, if not within the T-06 III.A1-10 PWR Group 6: interior and and permeability, scope of the III.A2-10 above grade exterior cracking, loss of applicant's structures III.A3-10 concrete material (spalling, monitoring program 111.A4-4 scaling) due to III.A5-10 aggressive III.A7-9 chemical attack III.A9-9 25 BWRI All Groups except Loss of material due Structures Monitoring Program. Yes, if not within the T-11 III.A1-12 PWR Group 6: steel to corrosion If protective coatings are relied scope of the III.A2-12 components: all upon to manage the effects of applicant's structures III.A3-12 (f)

(D structu ral steel aging, the structures monitoring monitoring program 111.A4-5 program is to include provisions III.A5-12

~ to address protective coating III.A7-10 3

0- monitoring and maintenance. III.AS-S

~

'"oo U1 OAGI0000203_092

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 26 BWR/ All Groups except Loss of material Structures Monitoring Program. Yes, if not within the T-01 III.A1-6 PWR Group 6: accessible (spalling, scaling) Evaluation is needed for plants scope of the III.A2-6 and inaccessible and cracki ng due to that are located in moderate to applicant's structures III.A3-6 concrete: foundation freeze-thaw severe weathering conditions monitoring program or III.A5-6 (weathering index >100 day- for inaccessible areas III.A7-5 inch/yr) (NUREG-1557) of plants located in III.AS-5 moderate to severe III.A9-5 weathering conditions 27 BWR/ All Groups except Cracking due to Structures Monitoring Program Yes, if not within the T-03 III.A1-2 PWR Group 6: accessible expansion due to None for inaccessible areas if scope of the III.A2-2 and inaccessible reaction with concrete was constructed in applicant's structures III.A3-2 interior/exterior aggregates accordance with the monitoring program or 111.A4-2 concrete recommendations in ACI concrete was not III.A5-2 201.2R-77. constructed as stated III.A7-1 for inaccessible areas III.AS-1 III.A9-1 2S BWR/ Groups 1-3, 5-9 All Cracks and Structures Monitoring Program. Yes, if not within the T-OS III.A1-3 PWR distortion due to If a de-watering system is relied scope of the III.A2-3 increased stress upon for control of settlement, applicant's structures III.A3-3 levels from then the licensee is to ensure monitoring program or III.A5-3 settlement proper functioning of the de- a de-watering system III.A6-4 watering system through the is relied upon III.A7-2 period of extended operation. III.AS-2 z III.A9-2 C

0 29 BWR/ Groups 1-3, 5-9: Red uction in Structures Monitoring Program. Yes, if not within the T-09 III.A1-S m PWR foundation foundation strength, If a de-watering system is relied scope of the III.A2-S Gl cracking, differential upon for control of settlement, applicant's structures III.A3-S settlement due to then the licensee is to ensure monitoring program or III.A5-S erosion of porous proper functioning of the de- a de-watering system III.A6-S

< III.A7-7 Q. concrete watering system through the is relied upon subfoundation period of extended operation. III.AS-7

0 III.A9-7 (D

OAGI0000203_093

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 30 BWR/ Group 4: Radial Lock-up due to lSI (IWF) or Structures Yes, if not within the T-13 111.A4-6 PWR beam seats in BWR wear Monitoring Program scope of lSI or drywell; RPV support structures monitoring shoes for PWR with program nozzle supports; Steam generator supports 31 BWR/ Groups 1-3, 5, 7-9: Increase in porosity Structures monitoring Program; Yes, plant -specific, if T-05 III.A1-4 PWR below-grade concrete and permeability, Examination of representative environment is III.A2-4 components, such as cracking, loss of samples of below-grade aggressive III.A3-4 exterior walls below material (spalling, concrete, and periodic III.A5-4 grade and foundation scaling)/ aggressive monitoring of groundwater, if the III.A7-3 chemical attack; environment is non-aggressive. III.AS-3 Cracking, loss of A plant specific program is to be III.A9-3 bond, and loss of evaluated if environment is T-07 III.A1-5 material (spalling, aggressive. III.A2-5 scaling)/ corrosion III.A3-5 of embedded steel III.A5-5 III.A7-4 III.AS-4 III.A9-4 32 BWR/ Groups 1-3, 5, 7-9: Increase in porosity Structures Monitoring Program Yes, if concrete was T-02 III.A1-7 PWR exterior above and and permeability, for accessible areas. None for not constructed as III.A2-7 below grade loss of strength due inaccessible areas if concrete stated for inaccessible III.A3-7 reinforced concrete to leaching of was constructed in accordance areas III.A5-7 foundations calcium hydroxide. with the recommendations in ACI III.A7-6 201.2R-77. III.AS-6 (f) III.A9-6 (D

~

3 0"

~

'"oo U1 OAGI0000203_094

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 33 BWR/ Groups 1-5: concrete Reduction of Plant-specific Yes, plant -specific if T-10 III.A1-1 PWR strength and temperature limits are III.A2-1 modulus due to exceeded III.A3-1 elevated 111.A4-1 temperature III.A5-1 34 BWR/ Group 6: Cracking, loss of Inspection of Water-Control Yes, plant -specific if T-18 III.A6-1 PWR Concrete; bond, loss of Structures Assoc with Nuclear environment is T-19 III.A6-3 all material due to Power Plants and for aggressive corrosion of inaccessible concrete, exam of embedded steel; rep. samples of below-grade increase in porosity concrete, and periodic and permeability, monitoring of groundwater, if cracking, loss of environment is non-aggressive.

material due to Plant specific if environment is aggressive aggressive.

chemical attack 35 BWR/ Group 6: exterior Loss of material Inspection of Water-Control Yes, for i naccessi ble T-15 III.A6-5 PWR above and below (spalling, scaling) Structures Associated with areas of plants located grade concrete and cracking due to Nuclear Power Plants. in moderate to severe foundation freeze-thaw Evaluation is needed for plants weathering conditions that are located in moderate to severe weathering conditions (weathering index >100 day-z inch/yr) (NUREG-1557)

C

0 m

Gl Q.

0 (D

OAGI0000203_095

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 36 BWRI Group 6: all Cracking due to Accessible areas: Inspection of Yes, if concrete was T-17 III.A6-2 PWR accessiblel expansionl reaction Water-Control Structures not constructed as inaccessible with aggregates Associated with Nuclear Power stated for inaccessible reinforced concrete Plants. areas None for inaccessible areas if concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

37 BWRI Group 6: exterior Increase in porosity For accessible areas, Inspection Yes, if concrete was T-16 III.A6-6 PWR above and below and permeability, of Water-Control Structures not constructed as grade reinforced loss of strength due Associated with Nuclear Power stated for inaccessible concrete foundation to leaching of Plants. None for inaccessible areas OJ interior slab calcium hydroxide areas if concrete was OJ constructed in accordance with the recommendations in ACI 201.2R-77.

38 BWRI Groups 7, 8: Tank Cracking due to Plant-specific Yes, plant specific T-23 III.A7-11 PWR liners stress corrosion III.A8-9 cracking; loss of material due to pitting and crevice corrosion 39 BWRI Support members; Loss of material due Structures Monitoring Program Yes, if not within the T-30 III.B2-10 PWR welds; bolted to general and scope of the III.B3-7 connections; support pitting corrosion applicant's structures III.B4-10 anchorage to building monitoring program III.B5-7 (f)

(D structure

~

3 0"

~

'"oo U1 OAGI0000203_096

Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 40 BWRI Building concrete at Red uction in Structures Monitoring Program Yes, if not within the T-29 III.B1.1-1 PWR locations of concrete anchor scope of the III.B1.2-1 expansion and capacity due to applicant's structures III.B1.3-1 grouted anchors; local concrete monitoring program III.B2-1 grout pads for degradationl III.B3-1 support base plates service-induced III.B4-1 cracking or other III.B5-1 concrete aging mechanisms 41 BWRI Vibration isolation Reduction or loss of Structures Monitoring Program Yes, if not within the T-31 III.B4-12 PWR elements isolation functionl scope of the radiation hardening, applicant's structures temperature, monitoring program humidity, sustained vibratory loading 42 BWRI Groups B1.1, B1.2, Cumulative fatigue TLAA evaluated in accordance Yes, TLAA T-26 III.B1.1-12 PWR and B1.3: support damage (CLB with 10 CFR 5421(c) III.B12-9 members: anchor fatigue analysis III.B13-9 bolts, welds exists) 43 BWRI Groups 1-3, 5, 6: all Cracking due to Masonry Wall Program No T-12 III.A1-11 PWR masonry block walls restraint shrinkage, III.A2-11 creep, and III.A3-11 aggressive III.A5-11 z environment III.A6-10 C

0 m 44 BWRI Group 6 elastomer Loss of sealing due Structures Monitoring Program No TP-7 III.A6-12 Gl PWR seals, gaskets, and to deterioration of moisture barriers seals, gaskets, and moisture barriers Q.

(caulking, flashing, and other sealants)

0 (D

OAGI0000203_097

z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 45 BWRI Group 6: exterior Loss of material due Inspection of Water-Control No T-20 III.A6-7 PWR above and below to abrasion, Structures Associated with grade concrete cavitation Nuclear Power Plants foundation; interior slab 46 BWRI Group 5: Fuel pool Cracking due to Water Chemistry and Monitoring No T-14 III.A5-13 PWR liners stress corros ion of spent fuel pool water level and cracking; loss of level of fluid in the leak chase material due to channel.

pitting and crevice corrosion 47 BWRI Group 6: all metal Loss of material due Inspection of Water-Control No T-21 III.A6-11 PWR structural members to general (steel Structures Associated with OJ OJ only), pitting and Nuclear Power Plants. If crevice corrosion protective coatings are relied upon to manage aging, protective coating monitoring and maintenance provisions should be included.

48 BWRI Group 6: earthen Loss of material, Inspection of Water-Control No T-22 III.A6-9 PWR water control loss of form due to Structures Associated with structures - dams, erosion, settlement, Nuclear Power Plants embankments, sedimentation, frost reservoirs, channels, action, waves, canals, and ponds currents, surface runoff, seepage (f) 49 BWR Support members; Loss of materiall Water Chemistry and lSI (IWF) No TP-10 III.B1.1-11 (D

welds; bolted general, pitting, and

~ connections; support crevice corrosion 3 anchorage to building 0"

~ structure

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Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 50 BWRI Groups B2, and B4: Loss of material due Structures Monitoring Program No TP-6 III.B2-7 PWR galvanized steel, to pitting and III.B4-7 aluminum, stainless crevice corrosion steel support members; welds; bolted connections; support anchorage to building structure 51 BWRI Group B1.1 high Cracking due to Bolti ng Integ nty No T-27 III.B1.1-3 PWR strength low-alloy stress corrosion TP-9 III.B1.1-4 bolts cracking; loss of material due to general corrosion 52 BWRI Groups B2, and B4: Loss of mechanical Structures Monitoring Program No TP-1 III.B2-2 PWR sliding support function due to III.B4-2 bearings and sliding corrosion, distortion, TP-2 III.B2-3 support surfaces dirt, overload, III.B4-3 fatigue due to vibratory and cyclic thermal loads 53 BWRI Groups B1.1, B1.2, Loss of material due lSI (IWF) No T-24 III.B1.1-13 PWR and B1.3: support to general and III.B1.2-10 members: welds; pitting corrosion III.B1.3-10 z bolted connections; C

0 support anchorage to m building structure Gl Q.

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z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 54 BWRI Groups B1.1, B1.2, Loss of mechanical lSI (IWF) No T-28 III.B1.1-2 PWR and B1.3: Constant function due to III.B1.2-2 and variable load corrosion, distortion, III.B1.3-2 spring hangers; dirt, overload, guides; stops fatigue due to vibratory and cyclic thermal loads 55 PWR Steel, galvanized Loss of material due Boric Acid Corrosion No T-25 III.B1.1-14 steel, and aluminum to boric acid III.B1.2-11 support members; corrosion III.B2-11 welds; bolted III.B3-8 connections; support III.B4-11 anchorage to building III.B5-8 CD structure TP-3 III.B11-8 o III.B1.2-6 III.B1.3-6 III.B2-6 III.B3-4 III.B4-6 III.B5-4 56 BWRI Groups B1.1, B1.2, Loss of mechanical lSI (IWF) No T-32 III.B1.1-5 PWR and B1.3 Sliding function due to III.B1.2-3 surfaces corrosion, distortion, III.B1.3-3 dirt, overload, fatigue due to vibratory and cyclic thermal loads (f)

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Table 5. Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapters II and III of the GALL Report Aging Further Evaluation Related Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item 57 BWRi Groups B1.1, B1.2, Reduction or loss of lSI (IWF) No T-33 III.B1.1-15 PWR and B1.3: Vibration isolation functioni III.B1.2-12 isolation elements radiation hardening, III.B1.3-11 temperature, humidity, sustained vibratory loading 58 BWRi Galvanized steel and None None NA - No AEM or AMP TP-8 III.B1.1-6 PWR aluminum support III.B1.2-4 members; welds; III.B1.3-4 bolted connections; III.B2-4 support anchorage to III.B3-2 building structure III.B4-4 exposed to air - III.B5-2 indoor uncontrolled TP-11 III.B1.1-7 III.B12-5 III.B13-5 III.B2-5 III.B3-3 III.B4-5 III.B5-3 z

C

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z Table 5. Summary of Aging Management Programs for Structures and Component Supports C

0 Evaluated in Chapters II and III of the GALL Report m

Gl Related Aging Further Evaluation Unique 10 Type Component Aging Management Programs Generic Effect/Mechanism Recommended Item Item Q. 59 BWRI Stainless steel None None NA - No AEM or AMP TP-4 III.B1.1-10 PWR support members; III.B12-8 welds; bolted III.B13-8 connections; support III.B2-9 anchorage to building III.B3-6 structure III.B4-9 III.B5-6 TP-5 III.B11-9 III.B12-7 III.B13-7 III.B2-8 III.B3-5 III.B4-8 III.B5-5 (f)

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(D Table 6. Summary of Aging Management Programs for the Electrical Components (D

Evaluated in Chapter VI of the GALL Report 3

0- Further Related

~

Aging Management Unique 10 Type Component Aging Effect/Mechanism Evaluation Generic Programs Item o

o Recommended Item U1 1 BWRI Electrical equipment Degradation due to various Environmental Yes, TLAA L-05 VLB-1 PWR subject to 10 CFR 50.49 aging mechanisms qualification d environmental electric components qualification (EO) requirements 2 BWRI Electrical cables, Reduced insulation resistance Electrical cables and No L-01 VLA-2 PWR connections and fuse and electrical failure due to connections not LP-03 VLA-6 holders (insulation) not various physical, thermal, subject to 10 CFR subject to 10 CFR 50.49 radiolytic, photolytic, and 50.49 EO EO requirements chemical mechanisms requirements 3 BWRI Conductor insulation for Reduced insulation resistance Electrical Cables And No L-02 VLA-3 PWR electrical cables and and electrical failure due to Connections Used In connections used in various physical, thermal, Instrumentation instrumentation circuits radiolytic, photolytic, and Circuits Not Subject not subject to 10 CFR chemical mechanisms To 10 CFR 50.49 EO 50.49 EO requirements Requirements that are sensitive to reduction in conductor insulation resistance (IR) 4 BWRI Conductor insulation for Localized damage and Inaccessible medium No L-03 VLA-4 PWR inaccessible medium breakdown of insulation voltage cables not voltage (2 kV to 35 kV) leading to electrical failure subject to 10 CFR z cables (e.g., installed in due to moisture intrusion, 50.49 EO C conduit or direct buried) water trees requirements

0 m not subject to 10 CFR Gl 50.49 EO requirements Q.

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z C Table 6. Summary of Aging Management Programs for the Electrical Components

0 m Evaluated in Chapter VI of the GALL Report Gl Further Related Aging Management Unique 10 Type Component Aging Effect/Mechanism Evaluation Generic Programs Item

< Recommended Item Q.

5 PWR Connector contacts for Corrosion of connector Boric Acid Corrosion No L-04 VLA-5 electrical connectors contact surfaces due to

0 (D exposed to borated intrusion of borated water

< water leakage 6 BWRI Fuse Holders (Not Part Fatigue due to ohmic heating, Fuse holders No LP-01 VLA-8 PWR of a Larger Assembly): thermal cycling, electrical Fuse holders - metallic transients, frequent clamp manipulation, vibration, chemical contamination, corrosion, and oxidation 7 BWRI Metal enclosed bus - Loosening of bolted Metal Enclosed Bus No LP-04 VLA-11 PWR Bus/connections connections due to thermal cycling and ohmic heating 8 BWRI Metal enclosed bus - Reduced insulation resistance Metal Enclosed Bus No LP-05 VLA-14 PWR Insulation/insu lators and electrical failure due to various physical, thermal, radiolytic, photolytic, and chemical mechanisms 9 BWRI Metal enclosed bus - Loss of material due to Structures Monitoring No LP-06 VLA-13 PWR Enclosure assemblies general corrosion Program 10 BWRI Metal enclosed bus- Hardening and loss of Structures Monitoring No LP-10 VLA-12 PWR Enclosure assemblies strength due to elastomers Program degradation (f)

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(D Table 6. Summary of Aging Management Programs for the Electrical Components (D

Evaluated in Chapter VI of the GALL Report 3

0- Further Related

~

Aging Management Unique 10 Type Component Aging Effect/Mechanism Evaluation Generic Programs Item o

o Recommended Item U1 11 BWRI High voltage insulators Degradation of insulation Plant specific Yes, plant LP-07 VLA-9 PWR quality due to presence of any specific LP-11 VLA-10 salt deposits and surface contamination; Loss of material caused by mechanical wear due to wind blowing on transmission conductors 12 BWRI Transmission conductors Loss of material due to wind Plant specific Yes, plant LP-08 VLA-16 PWR and connections; induced abrasion and fatigue; specific LP-09 VLA-15 switchyard bus and loss of conductor strength due connections to corrosion; increased resistance of connection due to oxidation or loss of preload 13 BWRI Cable Connections - Loosening of bolted Electrical cable No LP-12 VLA-1 PWR Metallic parts connections due to thermal connections not cycling, ohmic heating, subject to 10 CFR electrical transients, vibration, 50.49 environmental chemical contamination, qualification corrosion, and oxidation requirements 14 BWRI Fuse Holders (Not Part None None NA - NoAEM or LP-02 VLA-7 PWR of a Larger Assembly) AMP z Insulation material C

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APPENDIX LISTING OF PLANT SYSTEMS EVALUATED IN THE GALL REPORT (VOLUME 2)

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Plant Systems Evaluated in the GALL Report (Volume 2)

Section in GALL Type System (Vol. 2)

BWR Automatic depressurization system V.D2 BWR Containment structures:

Mark I steel containments II.B1 Mark II concrete and steel containments II.B2 Mark III concrete and steel containments II.B3 Common components II.B4 BWR High-pressure coolant injection V.D2 BWR High-pressure core spray V.D2 BWR Low-pressure coolant injection and residual heat removal V.D2 BWR Low-pressure core spray V.D2 BWR Reactor building III.A1 BWR Reactor building with steel superstructure III.A2 BWR Reactor coolant pressure boundary IV.C1 BWR Reactor coolant system connected systems (up to and including the second isolation valve):

Automatic depressurization system IV.C1 Feedwater IV.C1 High-pressure core spray IV.C1 High-pressure coolant injection IV.C1 Isolation condenser IV.C1 Low-pressure coolant injection IV.C1 Low-pressure core spray IV.C1 Main steam IV.C1 Reactor core isolation cooling IV.C1 Reactor water cleanup IV.C1 Recirculation system IV.C1 Residual heat removal IV.C1 Shutdown cooling IV.C1 Standby liquid control IV.C1 BWR Reactor core isolation cooling V.D2 BWR Reactor vessel IV.A1 BWR Reactor vessel internals IV.B1 BWR Reactor water cleanup system VII.E3 BWR Shutdown cooling system (older plants) VII.E4 BWR Standby gas treatment system V.B BWR Standby liquid control system VII.E2 BWR Suppression pool cleanup system VII.A5 BWR Unit vent stack III.A9 BWR/PWR Auxiliary and radwaste area ventilation system VII.F2 BWR/PWR Auxiliary building, diesel generator building, radwaste III.A3 building, turbine building, switchgear room, auxiliary feedwater pump house, and utility/piping tunnels BWR/PWR Carbon steel components V.E, VII.I, VIII.H BWR/PWR Closed-cycle cooling water system (reactor auxiliary cooling VII.C2 water)

September 2005 A-3 NUREG-1801 Vol. 1, Rev. 1 OAG10000203_ 109

Plant Systems Evaluated in the GALL Report (Volume 2) (continued)

Section in GALL Type System (Vol. 2)

BWR/PWR Component supports III.B BWR/PWR Compressed air system VII.D BWR/PWR Concrete tanks III.A7 BWR/PWR Condensate system VilLE BWR/PWR Containment internal structures, excluding refueling canal 111.A4 BWR/PWR Containment isolation components (containment isolation VC valves for in -scope systems are addressed in chapters IV, VII, and VIII)

BWR/PWR Control room/building III.A1 BWR/PWR Control room area ventilation system VII.F1 BWR/PWR Demineralized water makeup Not in scope of 10 CFR 50.54 BWR/PWR Diesel fuel oil system VII.H1 BWR/PWR Diesel generator building ventilation system VII.F4 BWR/PWR Electrical components VI.A, B BWR/PWR Emergency diesel generator system VII.H2 BWR/PWR Extraction steam system VIII.C BWR/PWR Feedwater system VIIID2,D1 BWR/PWR Fire protection VII.G BWR/PWR Fuel storage facility and refueling canal III.A5 BWR/PWR Heating and ventilation systems VII.F1, F2, F3, F4 BWR/PWR Main steam system VIII.B2, B1 BWR/PWR New and spent fuel storage VII.A1, A2 BWR/PWR Open-cycle cooling water system (service water system) VII.C1 BWR/PWR Overhead heavy load and light load (related to refueling) VII.B handling systems BWR/PWR Potable and sanitary water Not in scope of 10 CFR 50.54 BWR/PWR Primary containment heating and ventilation system VII.F3 BWR/PWR Refueling canal III.A5 BWR/PWR Spent fuel pool coolinq and cleanup VII.A3, A4 BWR/PWR Steam turbine system VilLA BWR/PWR Steel tanks III.A8 BWR/PWR Ultimate heat sink VII.C3 BWR/PWR Water-control structures (e.g., intake structure, cooling tower, III.A6 and spray pond)

PWR Accumulators V.D1 PWR Auxiliary feedwater system VIII.G PWR Chemical and volume control system VII.E1 PWR Combustible gas control (containment H2 control) V.E1 PWR Containment spray system V.A PWR Containments:

Concrete containments II.A1 Steel containments II.A2 Common components II.A3 PWR Coolant storage/refueling water system V.D1 NUREG-1801 Vol. 1, Rev. 1 A-4 Septem ber 2005 OAGI0000203_ 110

Plant Systems Evaluated in the GALL Report (Volume 2) (continued)

Section in GALL Type System (Vol. 2)

PWR Core flood system (see accumulators or safety injection V.01 tanks)

PWR High-pressure safety injection V.01 PWR Lines to chemical and volume control system V.01 PWR Low-pressure safety injection V.01 PWR Shield building III.A1 PWR Reactor coolant system and connected lines (up to and including the second isolation valve):

Chemical and volume control system IV.C2 Core flood system IV.C2 Drains and instrumentation lines IV.C2 High-pressure injection system IV.C2 Low-pressure injection IV.C2 Residual heat removal or shutdown cooling IV.C2 Safety injection IV.C2 Sampling system IV.C2 PWR Reactor coolant system, pressurizer, pressurizer relief tank, IV.C2 and other Class 1 components PWR Reactor vessel IV.A2 PWR Reactor vessel internals IV.B2, B3, B4 PWR Residual heat removal or shutdown cooling V.01 PWR Safety injection tanks V.01 PWR Steam generator blowdown system VIII.F PWR Steam qenerators IV.01, D2 September 2005 A-5 NUREG-1801 Vol. 1, Rev. 1 OAGI0000203_ 111

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NUREG-1801, Vol. 2, Rev. 1 Generic Aging Lessons Learned (GALL) Report Tabulation of Results Manuscript Completed: September 2005 Date Published: September 2005 Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 OAGI0000203_ 113

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ABSTRACT The Generic Aging Lessons Learned (GALL) report contains the staff's generic evaluation of the existing plant programs and documents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the extended period of operation. The evaluation results documented in the GALL report indicate that many of the existing programs are adequate to manage the aging effects for particular structures or components for license renewal without change. The GALL report also contains recommendations on specific areas for which existing programs should be augmented for license renewal. An applicant may reference the GALL report in a license renewal application to demonstrate that the programs at the applicant's facility correspond to those reviewed and approved in the GALL report and that no further staff review is required. The focus of the staff review is on the augmented existing programs for license renewal. The incorporation of the GALL report information into the N UREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," as directed by the Commission, should improve the efficiency of the license renewal process.

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TABLE OF CONTENTS Abstract.. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... iii List of Contributors - 2004-2005... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... xi Abbreviations. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... xv Introduction ...................................................................................................................... .

I. Application of ASME Code ..................................................................................... I-i II. Containment Structures.. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... II-i A Pressurized Water Reactor (PWR) Containments ..................................... . II Ai A1 Concrete Containments (Reinforced and Prestressed) ..................... . IIA1-1 K2. Steel Containments ............................................................................ . II K2.-1 K3 Common Components ....................................................................... . 1IK3-1 B Boiling Water Reactor (BWR) Containments .............................................. . II B-i B1 Mark I Containments .......................................................................... . II B1-1 B2 Mark II Containments ......................................................................... . II B2-1 B3 Mark III Containments ........................................................................ . II B3-1 B4 Common Components ....................................................................... . II B4-1 III. Structures and Component Supports ................................................................... III-i A Safety Related and Other Structures ........................................................... III Ai A1 Group 1 Structures (BWR Reactor Building, PWR Shield Building, Control Room/Building) ..................................................... III A1-1 K2. Group 2 Structures (BWR Reactor Building with Steel Superstructure)................................................................................. III K2.-1 K3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg.,

Radwaste Bldg., Turbine Bldg., Switchgear Rm., AFW Pumphouse, Utility/Piping Tunnels Yard Structures such as AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker Foundation, Electrical Enclosure) .................................................... III K3-1 A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) .............................................................. III A4-1 PO Group 5 Structures (Fuel Storage Facility, Refueling Canal) ............. III PO-1 AS Group S Structures (Water-Control Structures) .................................. III AS-1 A7 Group 7 Structures (Concrete Tanks and Missile Barriers)) .............. III A7-1 N3 Group 8 Structures (Steel Tanks and Missile Barriers) ...................... III N3-1

/¥i) Group 9 Structures (BWR Unit Vent Stack) ........................................ III /¥i)-1 B Component Supports ................................................................................... III B-i B1 Supports for ASME Piping and Components...................................... III B1-1 B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components ............. III B2-1 September 2005 v NUREG-1801, Rev. 1 OAGI0000203_ 117

III. Structures and Component Supports (continued)

B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation .................................. III B3-1 B4 Supports for Emergency Diesel Generator (EDG),

HVAC System Components, and Other Miscellaneous Mechanical Equipment .................................................................... III B4-1 B5 Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures........ III B5-1 IV. Reactor Vessel, Internals, and Reactor Coolant System.................................... IV-i A1 Reactor Vessel (BWR) ............................................................................... . IVA1-1 N. Reactor Vessel (PWR) ................................................................................ . IVN.-1 B1 Reactor Vessel Internals (BWR) ................................................................. . IVB1-1 B2 Reactor Vessel Internals (PWR) - Westinghouse ...................................... .. IVB2-1 B3 Reactor Vessel Internals (PWR) - Combustion Engineering ...................... . IVB3-1 B4 Reactor Vessel Internals (PWR) - Babcock and Wilcox ............................ .. IVB4-1 C1 Reactor Coolant Pressure Boundary (BWR) .............................................. . IVC1-1 C2 Reactor Coolant System and Connected Lines (PWR) .............................. . IVC2-1 D1 Steam Generator (Recirculating) ................................................................ . IVD1-1 D2 Steam Generator (Once-Through) .............................................................. . IVD2-1 E Common Miscellaneous Material/Environment Combinations .................. .. IVE-1 V. Engineered Safety Features................................................................................... V-i A Containment Spray System (PWR) ............................................................ . VA-1 B Standby Gas Treatment System (BWR) .................................................. .. VB-1 C Containment Isolation Components ............................................................ . VC-1 D1 Emergency Core Cooling System (PWR) .................................................. .. VD1-1 D2 Emergency Core Cooling System (BWR) .................................................. .. VD2-1 E External Surfaces of Components and Miscellaneous Bolting .................. .. VE-1 F Common Miscellaneous Material/Environment Combinations ............... . VF-1 VI. Electrical Components............................................................................................ VI-i A Equipment, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements ......................... VI A-1 B Equipment Subject to 10 CFR 50.49 Environmental Qualification Requirements ......................................................................................... VI B-1 VII. Auxiliary Systems .................................................................................................... VII-i A1 New Fuel Storage ......................................................................................... VII A1-1 N. Spent Fuel Storage ....................................................................................... VII N.-1 A3 Spent Fuel Pool Cooling and Cleanup (PWR) ............................................. VII A3-1 M Spent Fuel Pool Cooling and Cleanup (BWR) ............................................. VII M-1 A5 Suppression Pool Cleanup System (BWR) ................................................. VII A5-1 B Overhead Heavy Load and Light Load (Related to Refueling)

Handling Systems .................................................................................. VII B-1 NUREG-1801, Rev. 1 vi Septem ber 2005 OAGI0000203_ 118

VII. Auxiliary Systems (continued)

C1 Open-Cycle Cooling Water System (Service Water System) ..................... VII C1-1 C2 Closed-Cycle Cooling Water System ........................................................... VII C2-1 C3 Ultimate Heat Sink ....................................................................................... VII C3-1 D Compressed Air System............................................................................... VII D-1 E1 Chemical and Volume Control System (PWR) ............................................ VII E1-1 E2 Standby Liquid Control System (BWR) ....................................................... VII E2-1 E3 Reactor Water Cleanup System (BWR) ...................................................... VII E3-1 E4 Shutdown Cooling System (Older BWR) ..................................................... VII E4-1 F1 Control Room Area Ventilation System ....................................................... VII F1-1 F2 Auxiliary and Radwaste Area Ventilation System ........................................ VII F2-1 F3 Primary Containment Heating and Ventilation System ............................... VII F3-1 F4 Diesel Generator Building Ventilation System ............................................ VII F4-1 G Fire Protection ............................................................................................. VII G-1 H1 Diesel Fuel Oil System ................................................................................. VII H1-1 H2 Emergency Diesel Generator System ......................................................... VII H2-1 I External Surfaces of Components and Miscellaneous Bolting .................... VII ~1 J Common Miscellaneous Material/Environment Combinations .................... VII J-1 VIII. Steam and Power Conversion System ................................................................. VIlI-i A Steam Turbine System ................................................................................. VIII A-1 B1 Main Steam System (PWR) ......................................................................... VIII B1-1 B2 Main Steam System (BWR) ......................................................................... VIII B2-1 C Extraction Steam System............................................................................. VIII C-1 D1 Feedwater System (PWR) ............................................................................ VIII D1-1 D2 Feedwater System (BWR) ............................................................................ VIII D2-1 E Condensate System ..................................................................................... VIII E-1 F Steam Generator Blowdown System (PWR)............................................... VIII F-1 G Auxiliary Feedwater System (PWR) ............................................................. VIII G-1 H External Surfaces of Components and Miscellaneous Bolting .................... VIII 1-1-1 I Common Miscellaneous Material/Environment Combinations .................... VIII ~1 IX. Selected Definitions and Use of Terms For Structures, Components, Materials, Environments, Aging Effects, And Aging Mechanisms ................... IX-i X. Time -Limited Aging Analyses [Evaluation of Aging Management Programs under 10 CFR 54.21(c)(1)(iii)]................................................................ X-i X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary ............................ . X l1li-1 X.S1 Concrete Containment Tendon Prestress ............................................... . XS-1 X.E1 Environmental Qualification (EQ) of Electric Components ...................... . XE-1 XI. Aging Management Programs (AMPs) .................................................................. XI-i XI.M1 ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD ......................................................................................................... XI l1li-1 XI.M2 Water Chemistry......................................................................................... XI l1li-10 XI.M3 Reactor Head Closure Studs ..................................................................... XI l1li-16 September 2005 vii NUREG-1801, Rev. 1 OAGI0000203_ 119

XI. Aging Management Programs (AMPs) (continued)

XI.M4 BWR Vessel ID Attachment Welds ........................................................... . XI l1li-19 XI.M5 BWR Feedwater Nozzle ............................................................................ . XI l1li-22 XI.M6 BWR Control Rod Drive Return Line Nozzle ............................................ . XI l1li-24 XI.M7 BWR Stress Corrosion Cracking ............................................................... . XI l1li-26 XI.M8 BWR Penetrations ..................................................................................... . XI l1li-30 XI.M9 BWR Vessel Internals ............................................................................... . XI l1li-34 XI.M10 Boric Acid Corrosion .................................................................................. . XI l1li-41 XI.M11 Nickel-Alloy Nozzles and Penetrations .................................................... . XI l1li-44 XI.M11A Nickel-Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors ........................... XI l1li-45 XI.M12 Thermal Aging Embritllement of Cast Austenitic Stainless Steel (CASS) .......................................................................... XI l1li-49 XI.M13 Thermal Aging and Neutron Irradiation Embritllement of Cast Austenitic Stainless Steel (CASS) ............................................ . XI l1li-52 XI.M14 Loose Part Monitoring ............................................................................... . XI l1li-55 XI.M15 Neutron Noise Monitoring .......................................................................... . XI l1li-57 XI.M16 PWR Vessel Internals ............................................................................... . XI l1li-60 XI.M17 Flow-Accelerated Corrosion ...................................................................... . XI l1li-61 XI.M18 Bolting Integrity .......................................................................................... . XI l1li-64 XI.M19 Steam Generator Tube Integrity ................................................................ . XI l1li-68 XI.M20 Open-Cycle Cooling Water System .......................................................... . XI l1li-72 XI.M21 Closed-Cycle Cooling Water System ........................................................ . XI l1li-75 XI.M22 Boraflex Monitoring .................................................................................... . XI l1li-78 XI.M23 Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems.. ... ... ... ... ... ... ... ... ... ... ... ... ... .... XI l1li-81 XI.M24 Compressed Air Monitoring.. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... XI l1li-83 XI.M25 BWR Reactor Water Cleanup System ....................................................... XI l1li-86 XI.M26 Fire Protection. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... XI l1li-89 XI.M27 Fire Water System. ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... .... XI l1li-92 XI.M28 Buried Piping and Tanks Surveillance ....................................................... XI l1li-95 XI.M29 Aboveground Steel Tanks .......................................................................... XI l1li-97 XI.M30 Fuel Oil Chemistry ...................................................................................... XI l1li-99 XI.M31 Reactor Vessel Surveillance ...................................................................... XI l1li-102 XI.M32 One-Time Inspection .................................................................................. XI l1li-105 XI.M33 Selective Leaching of Materials ................................................................. XI l1li-109 XI.M34 Buried Piping and Tanks Inspection .......................................................... XI l1li-111 XI.M35 One-time Inspection of ASME Code Class 1 Small Bore-Piping .............. XI l1li-113 XI.M36 External Surfaces Monitoring .................................................................... XI l1li-115 XI.M37 Flux Thimble Tube Inspection ................................................................... XI l1li-118 XI.M38 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components .................................... XI1III-121 XI.M39 Lubricating Oil Analysis .............................................................................. XI l1li-123 XI.S1 ASME Section XI, Subsection IWE .......................................................... .. XIS-1 XI.S2 ASME Section XI, Subsection IWL .......................................................... .. XIS-6 XI.S3 ASME Section XI, Subsection IWF .......................................................... .. XIS-10 XI.S4 10 CFR 50, Appendix J ............................................................................ .. XIS-14 XI.S5 Masonry Wall Program .............................................................................. . XIS-17 XI.S6 Structures Monitoring Program ................................................................. . XIS-19 NUREG-1801, Rev. 1 viii Septem ber 2005 OAGI0000203_120

XI. Aging Management Programs (AMPs) (continued)

XI.S7 RG 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants ............................................................................. XI S-22 XI.S8 Protective Coating Monitoring and Maintenance Program ...... ...... ...... ....... XI S-25 XI.E1 Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements ............................................ . XI E-1 XI.E2 Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits .......................................................................... . XI E-4 XI.E3 Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements ............................................ . XI E-7 XI.E4 Metal Enclosed Bus ..................................................................................... . XI E-10 XI.E5 Fuse Holders ............................................................................................... . XI E-13 XI.E6 Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements ............................................ . XI E-15 Appendix: Quality Assurance for Aging Management Programs.............................. A-i September 2005 ix NUREG-1801, Rev. 1 OAGI0000203_121

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LIST OF CONTRIBUTORS License Renewal and Environmental Programs Section of Division of Regulatory Improvement Programs. Office of Nuclear Reactor Regulation P.T. Kuo Program Director S. Lee Section Chief S. West Section Chief J. Zimmerman Section Chief J. Dozier Team Leader K. Chang Mechanical Engineering K. Cozens Materials Engineering G. Cranston Reactor Systems Engineering D. Guha Systems Engineering M. Heath Mechanical Engineering S. Hoffman Mechanical Engineering A. Hull Materials Engineering K. Hsu Materials Engineering M. Lintz Mechanical Engineering D. Merzke Mechanical Engineering K. Naidu Reactor Engineering J. Rajan Mechanical Engineering R. Subbaratnam Mechanical Engineering T. Terry Civil Engineering L. Tran Electrical Engineering P. Wen Electrical Engineering Office of Nuclear Reactor Regulation T. Chan Section Chief S.Coffin Section Chief S. Jones Section Chief R. Jenkins Section Chief L. Lund Section Chief R. Karas Section Chief K. Manoly Section Chief M. Mitchell Section Chief J. Nakoski Section Chief D. Terao Section Chief S. Weerakkody Section Chief H. Ashar Structural Engineering S. Bailey Mechanical Engineering T. Cheng Structural Engineering R. Davis Materials Engineering B. Elliot Materials Engineering J. Fair Mechanical Engineering G. Georgiev Materials Engineering September 2005 xi NUREG-1801. Rev. 1 OAGI0000203_123

LIST OF CONTRIBUTORS (continued)

A. Keim Materials Engineering N. Iqbal Fire Protection Engineering D. Jeng Structural Engineering K. Karwoski Materials Engineering C. Lauron Chemical Engineering L. Lois Reactor Systems Engineering Y.Li Mechanical Engineering R. McNally Mechanical Engineering J. Medoff Materials Engineering D. Nguyen Electrical Engineering A. Pal Electrical Engineering K. Parczewski Chemical Engineering J. Strnisha Mechanical Engineering P. Shemanski Electrical Engineering Office of Nuclear Regulatory Research A. Hiser Section Chief J. Vora Team Leader J. Davis Materials Engineering P. Kang Electrical Engineering Parallax, Inc A. Baione Team Leader M. Bowman Mechanical Engineering D. Jones Programming K. Larsen Technical Editing E. Patel Mechanical Engineering F. Stetson Mechanical Engineering C. Urland Mechanical Engineering R. Wells License Engineering G. Worku Mechanical Engineering T. Kennedy Materials Engineering Argonne National Laboratory O. Chopra Team Leader Y.Liu Team Leader D. Diercks Materials Engineering R. Fabian Quality Assurance R. Foote Clerical Support Z.Li Nuclear Engineering D.Ma Mechanical Engineering V.Shah Mechanical and Materials Engineering NUREG-1801, Rev. 1 xii Septem ber 2005 OAGI0000203_124

LIST OF CONTRIBUTORS (continued)

B. Shelton Reactor and Plant Systems Engineering S. Tam Materials Engineering Information Systems Laboratories B. Gitnick Team Leader B. Mrowca Systems Engineering O. Mazzoni Electrical Engineering M. Patterson Systems Engineering R. Pond Materials Engineering S. Traiforos Structural Engineering C. Amoruso Technical Editing September 2005 xiii NUREG-1801, Rev. 1 OAGI0000203_125

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ABBREVIATIONS ACI American Concrete Institute ADS automatic depressurization system AFW auxiliary feedwater ALARA as low as reasonably achievable AMP aging management program AMR aging management review ANSI American National Standards Institute ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials B&PV boiler and pressure vessel B&W Babcock & Wilcox BWR boiling water reactor BWRVIP Boiling Water Reactor Vessel and Internals Project CASS cast austenitic stainless steel CB core barrel CCCW closed-cycle cooling water CE Combustion Engineering CEA control element assembly CEDM control element drive mechanism CFR Code of Federal Regulations CFS core flood system CLB current licensing basis CRD control rod drive CRDM control rod drive mechanism CRDRL control rod drive return line CRGT control rod guide tube CVCS chemical and volume control system DC direct current DHR decay heat removal DSCSS drywell and suppression chamber spray system ECP electrochemical potential EDG emergency diesel generator EFPD effective full power day EPRI Electric Power Research Institute EQ environmental qualification FAC flow-accelerated corrosion FERC Federal Energy Regulatory Commission FSAR Final Safety Analysis Report FW feedwater GALL Generic Aging Lessons Learned GE General Electric GL generic letter September 2005 xv NUREG-1801, Rev. 1 OAGI0000203_127

ABBREVIATIONS (continued)

HELBs high-energy line breaks HP high pressure HPCI high-pressure coolant injection HPCS high-pressure core spray HPSI high-pressure safety injection HVAC heating, ventilation, and air conditioning I&C instrumentation and control IASCC irradiation assisted stress corrosion cracking IC isolation condenser ID inside diameter IEB inspection and enforcement bulletin IEEE Institute of Electrical and Electronics Engineers IGA intergranular attack IGSCC intergranular stress corrosion cracking IN information notice INPO Institute of Nuclear Power Operations IPA integrated plant assessment IR insulation resistance IRM intermediate range monitor lSI inservice inspection ITG Issues Task Group LER licensee event report LG lower grid LOCA loss of coolant accident LP low pressure LPCI low-pressure coolant injection LPCS low-pressure core spray LPM loose part monitoring LPRM low-power range monitor LPSI low-pressure safety injection LRT leak rate test LWR light water reactor MFW main feedwater MIC microbiologically influenced corrosion MS main steam MSR moisture separatorireheater MT magnetic particle testing NDE nondestructive examination NEI Nuclear Energy Institute NFPA National Fire Protection Association NPAR nuclear plant aging research NPS nominal pipe size NRC Nuclear Regulatory Commission NRMS normalized root mean square NUREG-1801, Rev. 1 xv Septem ber 2005 OAGI0000203_128

ABBREVIATIONS (continued)

NSAC Nuclear Safety Analysis Center NSSS nuclear steam supply system NUMARC Nuclear Management and Resources Council OCCW open-cycle cooling water 00 outside diameter OOSCC outside diameter stress corrosion cracking OM operation and maintenance PT penetrant testing PWR pressurized water reactor PWSCC primary water stress corrosion cracking QA quality assurance RCCA rod control cluster assemblies RCIC reactor core isolation cooling RCP reactor coolant pump RCPB reactor coolant pressure boundary RCS reactor coolant system RG Regulatory Guide RHR residual heat removal RICSIL rapid information communication services information letter RMS root mean square RWC reactor water cleanup RWST refueling water storage tank RWT refueling water tank SAW submerged arc weld SC suppression chamber SCC stress corrosion cracking SOC shutdown cooling SFP spent fuel pool SG steam generator S/G standards and guides SIL services information letter SIT safety injection tank SLC standby liquid control SOER significant operating experience report SRM source range monitor SRM staff requirements memorandum SRP-LR standard review plan for license renewal SS stainless steel SSC systems, structures, and components TGSCC transgranular stress corrosion cracking TLAA time-limited aging analysis September 2005 xvii NUREG-1801, Rev. 1 OAGI0000203_129

ABBREVIATIONS (continued)

UCS Union of Concerned Scientists UHS ultimate heat sink USI unresolved safety issue UT ultrasonic testing UV ultraviolet NUREG-1801, Rev. 1 xviii Septem ber 2005 OAG10000203_ 130

INTRODUCTION The GALL Report, Volume 2 contains 11 chapters and an appendix. The majority of the chapters contain summary descriptions and tabulations of evaluations of aging management programs for a large number of structures and components in the various major plant systems in the light-water reactor nuclear power plants. The major plant systems include the containment structures (Chapter II), structures and component supports (Chapter III), reactor vessel, internals and reactor coolant system (Chapter IV), engineered safety features (Chapter V),

electrical components (Chapter VI), auxiliary systems (Chapter VII), and steam and power conversion system (Chapter VIII).

Also in Volume 2 of the GALL report, Chapter I addresses the application of the ASM E Code for license renewal. Chapter IX contains definitions of a selection of standard terms used within the GALL report. Chapter X contains the time-limited aging analysis evaluation of aging management programs under 10 CFR 54.21 (c)(1)(iii). Chapter XI contains the aging management programs for the structures and mechanical and electrical components.

The Appendix of Volume 2 of the GALL report addresses quality assurance (QA) for aging management programs.

The evaluation process for the aging management programs and the application of the GALL report is described in the Summary, Volume 1 , of the GALL report.

Table Column Headings The following describes the information presented in each column of tables 1 through 6 contained in Volume 2 of this report.

Column Heading Description Item Two items are listed in each row for this column. The first item is a unique row identifier which is coded to indicate the chapter, AM R subsystem and row number (i.e., VIII.B1-1 is the first row in the steam and power conversion system, main steam system table, row 1). The second identifier (shown in parentheses) is a unique chapter-specific identifier used in the AMR subsystem rows within a chapter, and is the related item used in tables 1 through 6 of GALL Volume 1.

Tables 1A through 6A in GALL Volume 1 show the relationship between these unique row identifiers and these unique chapter-specific identifiers.

Link For each row in the subsystem tables, this item identifies the corresponding row identifier from GALL Volume 2 revision 0, if the row was derived from the earlier version of this report. Otherwise, the item indicates a new row and to which AMR subsystem tables within the chapter it was added in this revision of the GALL Report.

Structure and Identifies the structure or components to which the row applies.

or Component Material Identifies the material of construction. See Chapter IX of this report for further information.

Environment Identifies the environment applicable to this row. See Chapter IX of this report for further information.

September 2005 NUREG-1801, Rev. 1 OAGI0000203_131

Aging Effect/ Identifies the applicable aging effect and mechanism(s). See Chapter IX of Mechanism Volume 2 for more information.

Aging Identifies the time limited aging analysis or aging management program found Management acceptable for properly managing the affects of aging. See Chapter X and XI Programs of Volume 2.

Further Identifies whether further evaluation is needed.

Evaluation Recommended NUREG-1801, Rev. 1 2 Septem ber 2005 OAGI0000203_ 132

CHAPTER I APPLICATION OF THE ASME CODE September 2005 I-i NUREG-1801, Rev. 1 OAGI0000203_ 133

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APPLICATION OF THE ASME CODE The American Society of Mechanical Engineers (ASME) codes were developed and are revised periodically by industry code committees composed of representatives of utilities, reactor designers, architect-engineers, component manufacturers, insurance companies, the U.S. Nuclear Regulatory Commission (NRC), and others. In 1971, NRC incorporated the ASME Boiler and Pressure Vessel Code into the regulations in 10 CFR 50.55a. [36 FR 11,423 (June 12,1971)].

The Statements of Consideration (SOC) for the final rule state:

"It has been generally recognized that, for boiling and pressurized water-cooled reactors, pressure vessels, piping, pumps, and valves which are part of the reactor coolant pressure boundary should, as a minimum, be designed, fabricated, inspected, and tested in accordance with the requirements of the applicable American Society of Mechanical Engineers (ASME) codes in effect at the time the equipment is purchased[.]"

The SOC also states:

"Because of the safety significance of uniform early compliance by the nuclear industry with the requirements of these ASM E ... codes and published code revisions, the Commission has adopted the following amendments to Part 50 and 115, which require that certain components and systems of water-cooled reactors important to safety comply with these codes and appropriate revisions to the codes at the earliest feasible time."

In addition, the SOC states:

"Compliance with the provisions of the amendments and the referenced codes is intended to insure a basic, sound quality level."

The ASME code, based on the collective engineering judgment of the code committees, documents the conditions that must be monitored, the inspection techniques adequate to observe those conditions, the frequency of the inspections, and the acceptance criteria that the results of the inspections must meet in order to assure the integrity of the structures and components considered in the code. The NRC has adopted this engineering judgment with respect to selected portions of the ASME code, as incorporated in 10 CFR 50.55a.

The NRC has amended 10 CFR 50.55a periodically to incorporate later editions of the ASME code into the regulations, with modifications and limitations, as appropriate. The latest such amendment was in 2001 (including the 2002 and 2003 Addenda). For the purpose of license renewal, the staff has extensively evaluated the appropriate ASME Section XI programs based on the ten program elements described in Volume 1 of this report. Except where noted, the staff has determined that the ASME Section XI programs provide processes for identifying degradation that is attributable to applicable aging effects and are therefore acceptable for managing the effects of aging during the period of extended operation. Where warranted, the NRC staff indicates that certain parts of the code programs should be augmented to satisfy aging management requirements for license renewal.

September 2005 1-1 NUREG-1801, Rev. 1 OAGI0000203_ 135

10 CFR 50.55a is revised periodically to adopt, by reference, new editions, and addenda of the ASME Code. Every 10 years applicants are required to revise the nuclear plant's lSI program to incorporate the requirements specified in the current version of the 10 CFR 50.55a regulations.

NRC SOC associated with the adoption of new editions and addenda of the ASME Code in 10 CFR 50.55a discusses the adequacy of the newer edition and addendum as they relate to the GALL Report. The information contained in these SOCs may provide a reasonable basis for exceptions relating to use of editions or addenda of the ASM E Code that are not the same as identified in the GALL Report.

The NRC Director of the Office of Nuclear Reactor Regulation may approve licensee proposed alternatives to the ASME Code in accordance with the provisions of 10 CFR 50.55a(a)(3).

These NRC approved ASME Code alternative requirements may have an associated applicability time limit. The applicability time limits associated with the approved alternatives do not extend beyond the current license term. Wan applicant seeks relief from specific requirements of 10 CFR 50.55a and Section XI of the ASME Code for the period of extended operation, the applicant will need to re-apply for relief through the 10 CFR 50.55a relief request process once the operating license for the facility has been renewed.

NUREG-1801, Rev. 1 1-2 September 2005 OAGI0000203_ 136

CHAPTER II CONTAINMENT STRUCTURES September 2005 II-i NUREG-1801, Rev. 1 OAGI0000203_ 137

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CONTAINMENT STRUCTURES A. Pressurized Water Reactor (PWR) Containments B. Boiling Water Reactor (BWR) Containments September 2005 II-iii NUREG-1801, Rev. 1 OAGI0000203_ 139

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PWR CONTAINMENTS A 1. Concrete Containments (Reinforced and Prestressed)

A2. Steel Containments A3. Common Components September 2005 IIA-1 NUREG-1801. Rev. 1 OAGI0000203_141

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A1. CONCRETE CONTAINMENTS (REINFORCED AND PRESTRESSED)

Systems, Structures, and Components This section addresses the elements of pressurized water reactor (PWR) concrete containment structures. Concrete containment structures are divided into three elements: concrete, steel, and prestressing system.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (V1I1.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

September 2005 IIA1-1 NUREG-1801, Rev. 1 OAGI0000203_143

z II CONTAINMENT STRUCTURES C

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< ILA1-1 ILA1.1-h Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-OS) Dome; wall; air - outdoor modulus! elevated limits are basemat; ring tem peratu re The implementation of 10 CFR 50.55a exceeded girder; (>150°F general; and ASME Section XI, Subsection IWL buttresses >200°F local) would not be able to identify the reduction of strength and modulus of elasticity due to elevated temperature.

Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted. Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above may be allowed in the concrete if tests (f) and!or calculations are provided to (D evaluate the reduction in strength and (D this reduction is applied to the design 3 allowables.

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Evaluation U1 ILA1-2 ILA1.1-a Concrete: Concrete Air - outdoor Loss of material Chapter XLS2, "ASME Section XI, Yes, for (spalling, scaling) Subsection IVVL" inaccessible (C-01) Dome; wall; and cracking/ areas of plants basemat; ring freeze-thaw Accessible areas: located in girders; Inspections performed in accordance moderate to buttresses with IVVL will indicate the presence of severe loss of material (spalling, scaling) and weathering surface cracking due to freeze-thaw conditions Inaccessible Areas:

Evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index

>100 day-inch/yr) (NUREG-1557)

Documented evidence confirms that where the existing concrete had air content of 3% to 6%, subsequent inspection did not exhibit degradation related to freeze-thaw. Such inspections should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig 1.

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OAGI0000203_145

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< ILA1-3 ILA11-d Concrete: Concrete Any Cracking due to Chapter XLS2, "ASME Section XI, Yes, if expansion! Subsection IVVL" concrete was (C-04) Dome; wall; reaction with not basemat; ring aggregates Accessible Areas: constructed as girders; Inspections performed in accordance stated for buttresses with IVVL will indicate the presence of inaccessible surface cracking due to reaction with areas aggregates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R.Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

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Evaluation U1 ILA1-4 ILA11-c Concrete: Concrete Ground Increase in Chapter XLS2, "ASME Section XI, Yes, plant-water/soil or air- porosity and Subsection IVVL" specific if (C-03) Dome; wall; indoor permeability, environment is basemat; ring uncontrolled or cracking, loss of Accessible Areas: aggressive girders; air-outdoor material (spalling, Inspections performed in accordance buttresses scaling)/ with IVVL will indicate the presence of aggressive increase in porosity and permeability, chemical attack surface cracking, or loss of material (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

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OAGI0000203_147

z II CONTAINMENT STRUCTURES C

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Mechanism Evaluation

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< ILA1-5 II.A11-f Concrete: Concrete Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not distortion due to Program" within the (C-37) Dome; wall; increased stress scope of the basemat; ring levels from If a de-watering system is relied upon for applicant's girders; settlement control of settlement, then the licensee is structures buttresses to ensure proper functioning of the de- monitoring watering system through the period of program or a extended operation. de-watering system is relied upon ILA1-6 ILA1.1-b Concrete: Concrete Water - flowing Increase in Chapter XLS2, "ASME Section XI, Yes, if porosity, Subsection IVVL" concrete was (C-02) Dome; wall; permeability! not basemat; ring leaching of calcium Accessi ble areas: constructed as girders; hydroxide Inspections performed in accordance stated for buttresses with IVVL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in (f) ACI201.2R-77.

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Evaluation U1 ILA1-7 ILA11-e Concrete: Concrete; Air - indoor Cracking, loss of Chapter XLS2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Subsection IVVL" specific if (C-05) Dome; wall; air - outdoor material (spalling, environment is basemat; ring scaling)/ corrosion Accessible Areas: aggressive girders; of embedded steel Inspections performed in accordance buttresses; with IVVL will indicate the presence of reinforcing surface cracking, loss of bond, and loss steel of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

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(D OAGI0000203_149

z II CONTAINMENT STRUCTURES C

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Mechanism Evaluation

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< ILA1-8 IIA11-g Concrete: Concrete; Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, cracking, scope of the su bfou ndatio differential Erosion of cement from porous concrete applicant's n settlement! erosion subfoundations beneath containment structures of porous concrete basemats is described in IN 97-11. IN monitoring subfoundation 98-26 proposes Maintenance Rule program or a Structures Monitoring for managing this de-wateri ng aging effect, if applicable If a de- system is watering system is relied upon for control relied upon of erosion of cement from porous concrete subfoundations, then the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

ILA1-9 ILA1.3-b Prestressing Steel Air - indoor Loss of prestress! Loss of tendon prestress is a time-limited Yes, system: uncontrolled or relaxation; aging analysis (TLAA) to be evaluated TLAA (C-11) air - outdoor shrinkage; creep; for the period of extended operation.

Tendons elevated tem peratu re See the Standard Review Plan, Section 4.5, "Concrete Containment Tendon Prestress" for acceptable methods for meeting the requirements of 10 CFR 5421(c)(1)(i) and (ii) See Chapter X.S1 of this report for meeting the requirements of (f)

(D 10 CFR 5421(c)(1)(iii)

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Evaluation U1 ILA1-10 ILA1.3-a Prestressing Steel Air - indoor Loss of material! Chapter XLS2, "ASME Section XI, No system: uncontrolled or corrosion Subsection IVVL" (C-10) air - outdoor Tendons; anchorage components ILA1-11 ILA1.2-a Steel Steel Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, Yes, if elements: uncontrolled general, pitting, Subsection IWE" corrosion is (C-09) and crevice significant for Liner; corrosion For inaccessible areas (embedded inaccessible Liner containment steel shell or liner), loss of areas anchors; material due to corrosion is not Integral significant if the following conditions are attachments satisfied:

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

2. 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.

3. The moisture barrier, at the junction z where the shell or liner becomes C embedded, is subject to aging

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4. Borated water spills and water

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< floor are not common and when detected OAGI0000203_ 151

z II CONTAINMENT STRUCTURES C

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Mechanism Evaluation

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< are cleaned up in a timely manner.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

Chapter XI.S4, "10 CFR Part 50, No Appendix J" o

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A2. STEEL CONTAINMENTS Systems, Structures, and Components This section addresses the elements of pressurized water reactor (PWR) steel containment structures. Steel containment structures are divided into two elements: steel and concrete.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (V1I1.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

September 2005 II A2-1 NUREG-1801, Rev. 1 OAGI0000203_ 153

z II CONTAINMENT STRUCTURES C

0 A2 Steel Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

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< ILA2-1 ILA2.2-h Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-34) Basemat air - outdoor modulus! limits are elevated The implementation of 10 CFR 50.55a exceeded temperature and ASME Section XI, Subsection

(>150°F general; IWL would not be able to identify the

>200°F local) reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above (f) may be allowed in the concrete if tests (D and!or calculations are provided to (D evaluate the reduction in strength and 3 this reduction is applied to the design 0-

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(f)

(D II CONTAINMENT STRUCTURES (D

A2 Steel Containments 3

0-

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Evaluation U1 ILA2-2 ILA2.2-a Concrete: Concrete Air - outdoor Loss of material Chapter XLS2, "ASME Section XI, Yes, for (spalling, scaling) Subsection IWL" inaccessible (C-28) Basemat and cracking/ areas of freeze-thaw Accessible areas: plants located Inspections performed in accordance in moderate to with IWL will indicate the presence of severe loss of material (spalling, scaling) and weathering surface cracking due to freeze-thaw. conditions Inaccessible Areas:

Evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557). Documented evidence confirms that where the existing concrete had air content of 3% to 6%,

subsequent inspection did not exhibit degradation related to freeze-thaw.

Such inspections should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig 1.

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Mechanism Evaluation

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< ILA2-3 ILA2.2-d Concrete: Concrete Any Cracking due to Chapter XLS2, "ASME Section XI, Yes, if expansion! Su bsection IWL" concrete was (C-38) Basemat reaction with not aggregates Accessible Areas: constructed as Inspections performed in accordance stated for with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas aggregates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227 -50 can demonstrate that those aggregates do not react within reinforced concrete.

For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

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A2 Steel Containments 3

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Evaluation U1 ILA2-4 ILA2.2-c Concrete: Concrete Ground Increase in Chapter XLS2, "ASME Section XI, Yes, plant-water/soil porosity and Su bsection IWL" specific if (C-25) Basemat permeability, environment is cracking, loss of Accessible Areas: aggressive material (spalling, Inspections performed in accordance scaling)/ with IWL will indicate the presence of aggressive increase in porosity and permeability, chemical attack surface cracking, or loss of material (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive z

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OAGI0000203_ 157

z II CONTAINMENT STRUCTURES C

0 A2 Steel Containments m

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Mechanism Evaluation

0 Component (D

< ILA2-5 ILA2.2-f Concrete: Concrete Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not distortion due to Program" within the (C-36) Basemat increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-wateri ng operation. system is relied upon ILA2-6 ILA2.2-b Concrete: Concrete Water - flowing Increase in Chapter XLS2, "ASME Section XI, Yes, if porosity, Subsection IWL" concrete was (C-3D) Basemat permeability! not leaching of Accessible areas: constructed as calcium Inspections performed in accordance stated for hydroxide with IWL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the (f) recommendations in ACI 2D1.2R.

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A2 Steel Containments 3

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Evaluation U1 ILA2-7 ILA2.2-e Concrete: Concrete; Air - indoor Cracking, loss of Chapter XLS2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Su bsection IWL" specific if (C-43) Basemat; air - outdoor material (spalling, environment is reinforcing scaling)/ Accessible Areas: aggressive steel corrosion of Inspections performed in accordance embedded steel with IWL will indicate the presence of surface cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the z

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OAGI0000203_ 159

z II CONTAINMENT STRUCTURES C

0 A2 Steel Containments m

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Mechanism Evaluation

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< ILA2-8 ILA22-g Concrete: Concrete; Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, scope of the subfoundatio cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of porous IN 97-11. IN 98-26 proposes program or a concrete Maintenance Rule Structures de-wateri ng subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, then the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

ILA2-9 ILA2.1-a Steel Steel Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, Yes, if elements: uncontrolled general, pitting, Subsection IWE" corrosion is (C-09) and crevice significant for Liner; corrosion For inaccessible areas (embedded inaccessible Liner containment steel shell or liner), loss areas anchors; of material due to corrosion is not Integral significant if the following conditions attachments are satisfied:

1 Concrete meeting the requirements (f) of ACI 318 or 349 and the guidance of (D

201.2R was used for the containment (D concrete in contact with the 3 embedded containment shell or liner.

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A2 Steel Containments 3

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Evaluation U1 cracks that provide a path for water seepage to the surface of the containment shell or liner.

3. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.

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

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for No corrosion is necessary.

Chapter XIS4, "10 CFR Part 50, Appendix J" z

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A3. COMMON COMPONENTS Systems, Structures, and Components This section addresses the common components of pressurized water reactor (PWR) containments. The common components include penetration sleeves and bellows; dissimilar metal welds; personnel airlock; equipment hatch; seals, gaskets, and moisture barriers.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and containment spray system (V.A). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B1) and feedwater system (V1I1.D1), or is supported by the containment structure, such as the polar crane (VII.B). The containment structure basemat typically provides support to the nuclear steam supply system (NSSS) components and containment internal structures.

September 2005 II A3-1 NUREG-1801, Rev. 1 OAGI0000203_163

z II CONTAINMENT STRUCTURES C

0 A3 Common Components m

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< ILA3-1 ILA3.1-a Penetration Steel; Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, No sleeves dissimilar uncontrolled general, pitting, Subsection IWE,"

(C-12) metal welds or air - outdoor and crevice corrosion (Note: IWE examination category E-F, surface examination of dissimilar metal welds, is recommended)

Chapter XLS4, "10 CFR Part 50, No Appendix J" ILA3-2 ILA3.1-d Penetration Stainless Air - indoor Cracking! stress Chapter XLS1, "ASME Section XI, Yes, detection sleeves; steel; uncontrolled or corrosion Subsection IWE" and Chapter XLS4, of aging (C-15) Penetration dissimilar air - outdoor cracking "10 CFR Part 50, Appendix J" effects is to bellows metal welds be evaluated Evaluation of 10 CFR 50.55a!ASME Section XI, Subsection IWE is augmented as follows:

(4) Detection of Aging Effects 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 ASME Section XI, Subsection IWE covers inspection of these items under examination (f) categories E-B, E-F, and E-P (10 CFR (D

Part 50, Appendix J pressure tests).

(D 10 CFR 50.55a identifies examination 3 categories E-B and E-F as optional 0-

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Evaluation U1 Examination Categories E-B & E-F, and additional appropriate examinations to detect SCC in bellows assemblies and dissimilar metal welds are warranted to address this issue.

(10) Operating Experience:

IN 92-20 describes an instance of containment bellows cracking, resulting in loss of leak tightness.

ILA3-3 ILA3.1-c Penetration Steel; Air - indoor Cracking! cyclic Chapter XLS1, "ASME Section XI, Yes, detection sleeves; stainless uncontrolled or loading Subsection IWE" and Chapter XLS4, of aging (C-14) Penetration steel; air - outdoor "10 CFR Part 50, Appendix J" effects is to bellows dissimilar (CLB fatigue be evaluated metal welds analysis does Evaluation of 10 CFR 50.55a!ASME not exist) Section XI, Subsection IWE is to be supplemented to consider the following:

(4) Detection of Aging Effects VT-3 visual inspection may not detect fine cracks.

ILA3-4 ILA3.1-b Penetration Steel; Air - indoor Cumulative Fatigue is a time-limited aging analysis Yes, sleeves; stainless uncontrolled or fatigue damage! (TLAA) to be evaluated for the period of TLAA (C-13) Penetration steel; air - outdoor fatigue extended operation. See the Standard bellows dissimilar Review Plan, Section 4.6, metal welds (Only if CLB "Containment Liner Plate and z

C fatigue analysis Penetration Fatigue Analysis" for

0 exists) acceptable methods for meeting the m

Gl requirements of 10 CFR 54.21 (c)(1)

OAGI0000203_165

z II CONTAINMENT STRUCTURES C

0 A3 Common Components m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< ILA3-5 ILA3.2-b Personnel Steel Air - indoor Loss of leak Chapter XLS4, "10 CFR Part 50, No airlock, uncontrolled tightness! Appendix J" and (C-17) equipment or air - outdoor mechanical hatch, CRD wear of locks, Plant Technical Specifications hatch: hinges and closure Locks, mechanisms hinges, and closure mechanisms ILA3-6 ILA3.2-a Personnel Steel Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, No airlock, uncontrolled or general, pitting, Subsection IWE,"

(C-16) equipment air - outdoor and crevice hatch, CRD corrosion Chapter XLS4, "10 CFR Part 50, No hatch Appendix J" ILA3-7 II.A3.3-a Seals, Elastomers, Air - indoor Loss of sealing; Chapter XLS1, "ASME Section XI, No gaskets, and rubber and uncontrolled or Leakage Subsection IWE" (C-18) moisture other similar air - outdoor through barriers materials containment! Leak tightness will be monitored by (caulking, deterioration of 10 CFR Part 50, Appendix J Leak Rate flashing, and seals, gaskets, Tests for pressure boundary, seals and other and moisture gaskets (including O-rings) sealants) barriers (caulking, flashing, and other sealants)

(f)

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8WR CONTAINMENTS 81 . Mark I Containments

82. Mark II Containments

83. Mark III Containments

84. Common Components September 2005 II B-i NUREG-1801. Rev. 1 OAGI0000203_167

This Page Intentionally Left Blank NUREG-1801, Rev. 1 II B-ii September 2005 OAGI0000203_168

B1. MARK I CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark I containment structures. Steel containments are discussed in II.B1.1 and concrete containments are discussed in II.B1.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and standby gas treatment system (V.B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VII I. D2), or is supported by the containment structure. The containment structure base mat may provide support to the NSSS components and containment internal structures.

September 2005 II B1-1 NUREG-1801, Rev. 1 OAGI0000203_169

z II CONTAINMENT STRUCTURES C

0 B1.1 Mark I Steel Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

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< II.B1.1-1 II.B1.1 1-e Steel elements: Steel Air - indoor Fretting or Chapter XI.S1, "ASME Section XI, No uncontrolled lockup! Subsection IWE" (C-23) Drywell head; mechanical Downcomers wear II.B1.1-2 II.B1.1.1-a Steel elements: Steel Air - indoor Loss of Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or material! Subsection IWE" corrosion is (C-19) Drywell; torus; treated water general, pitting, significant for drywell and crevice For inaccessible areas (embedded inaccessible head; corrosion containment steel shell or liner), loss of areas embedded material due to corrosion is not OJ shell significant if the following conditions and sand are satisfied:

r0 pocket regions; Concrete meeting the specifications of drywell ACI 318 or 349 and the guidance of support skirt; 201.2R was used for the containment torus ring concrete in contact with the embedded girder; containment shell or liner. The concrete downcomers; is monitored to ensure that it is free of ECCS penetrating cracks that provide a path suction for water seepage to the surface of the header containment shell or liner. The moisture barrier, at the junction where the shell NOTE or liner becomes embedded, is subject Inspection of to aging management activities in (f)

(D containment accordance with ASME Section XI, (D

supports is Subsection IWE requirements. Water 3 addressed by ponding on the containment concrete 0-ASME floor are not common and when

~

Section XI, detected are cleaned up in a timely

'"oo Subsection manner.

U1 OAG10000203_ 170

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(D II CONTAINMENT STRUCTURES (D

B1.1 Mark I Steel Containments 3

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Evaluation U1 IWF(see IIIB13) If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

No Chapter XIS4, "10 CFR Part 50, Appendix J" IIB1.1-3 IIB1.1.1-b Steel elements: Stainless Air - indoor Cracking! cyclic Chapter XIS1, "ASME Section XI, Yes, detection steel; steel uncontrolled loading Subsection IWE" and Chapter XIS4, of aging (C-20) Torus; "10 CFR Part 50, Appendix J" effects is to be OJ Vent line; (CLB fatigue evaluated W Vent header; analysis does Evaluation of 10 CFR 50.55a! ASME Vent line not exist) Section XI, Subsection IWE is bellows; augmented as follows:

Downcomers (4) Detection of Aging Effects VT-3 visual inspection may not detect fine cracks.

IIB1.1-4 IIB1.1.1-c Steel elements: Stainless Air - indoor Cumulative Fatigue is a time-limited aging analysis Yes, steel; steel uncontrolled fatigue damage! (TLAA) to be evaluated for the period TLAA (C-21) Torus; fatigue of extended operation. See the Vent line; Standard Review Plan, Section 4.6, z Vent header; (Only if CLB "Containment Liner Plate and C

0 Vent line fatigue analysis Penetration Fatigue Analysis" for m

Gl bellows; exists) acceptable methods for meeting the Downcomers requirements of 10 CFR 54.21 (c)(1)

0 (D

OAGI0000203_ 171

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0 B1.1 Mark I Steel Containments m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B11-5 ILB1.1.1-d Steel elements: Stainless Air - indoor Crackingl stress Chapter XLS1, "ASME Section XI, Yes, detection steel uncontrolled corrosion Subsection IWE" and Chapter XLS4, of aging (C-22) Vent line cracking "10 CFR Part 50, Appendix J" effects is to be bellows evaluated Evaluation of 10 CFR 50.55a/ASME Section XI, Subsection IWE is augmented as follows:

(4) Detection of Aging Effects Stress corrosion cracking (SCC) is a concern for dissimilar metal welds. In the case of bellows assemblies, SCC may cause aging effects particularly if the material OJ is not shielded from a corrosive

.h environment. ASME Code 1995 edition, with addenda through 1996, ASME Section XI, Subsection IWE covers inspection of these items under Examination Categories E-B, E-F, and E-P (10 CFR Part 50, Appendix J pressure tests). 10 CFR 50.55a identifies examination categories E-B and E-F as optional during the current term of operation. For the extended period of operation, Examination Categories E-B and E-F, and additional appropriate examinations to detect (f)

SCC in bellows assemblies and (D dissimilar metal welds are warranted to (D address this issue.

3 0-

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Evaluation U1 leak tightness.

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Mechanism Evaluation Component II.B1.2-1 II.B1.2. Concrete Concrete Soil Cracks and Chapter XI.S6, "Structures Monitoring Yes, if not elements; All distortion due to Program" within the (C-06) increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-watering operation. system is relied upon z

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OAGI0000203_ 175

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< II.B1.2-2 II.B1.2. Concrete: Concrete; Air - indoor Cracking, loss of Chapter XI.S2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Subsection IWL." specific if (C-41) Basemat; air - outdoor material environment i reinforcing (spalling, Accessible Areas: aggressive steel scaling)/ Inspections performed in accordance corrosion of with IWL will indicate the presence of em bedded steel surface cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steel.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, OJ chlorides < 500 ppm, or sulfates in <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have (f) experienced degradation, a plant (D specific AMP accounting for the (D extent of the degradation experienced 3 should be implemented to manage 0-

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'"oo U1 OAGI0000203_ 176

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(D II CONTAINMENT STRUCTURES (D

B1.2 Mark I Concrete Containments 3

0-

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Evaluation U1 II.B1.2-3 II.B1.2. Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-35) Containment; air - outdoor modulus! limits are wall; basemat elevated The implementation of exceeded temperature 10 CFR 50.55a and ASME Section

(>150°F general; XI, Subsection IWL would not be able

>200°F local) to identify the reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME OJ Section III, Division 2, specifies the cD concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipment loads are su pported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

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OAGI0000203_ 177

z II CONTAINMENT STRUCTURES C

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Mechanism Evaluation

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< II.B1.2-4 II.B1.2. Concrete: Concrete Any Cracking due to Chapter XI.S2, "ASME Section XI, Yes, if expansion! Subsection IWL" concrete was (C-39) Containment; reaction with not wall; basemat aggregates Accessible Areas: constructed as Inspections performed in accordance stated for with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas agg regates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates OJ performed in accordance with ASTM C295-54 or ASTM C227 -50 can o

demonstrate that those aggregates do not react within reinforced concrete.

For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R.

Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

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(D II CONTAINMENT STRUCTURES (D

B1.2 Mark I Concrete Containments 3

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Evaluation U1 II.B12-5 ILB1.2. Concrete: Concrete Ground Increase in Chapter XLS2, "ASME Section XI, Yes, plant-water/soil or porosity and Subsection IWL" specific if (C-26) Containment; air-indoor permeability, environment i wall; basemat uncontrolled or cracking, loss of Accessible Areas: aggressive air-outdoor material Inspections performed in accordance (spalling, with IWL will indicate the presence of scaling)/ increase in porosity and permeability, aggressive surface cracking, or loss of material chemical attack (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive OJ ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates

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For plants with aggressive z

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OAGI0000203_ 179

z II CONTAINMENT STRUCTURES C

0 B1.2 Mark I Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B1.2-6 II.B1.2. Concrete: Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, Yes, if porosity, Subsection IWL" concrete was (C-31) Containment; permeability! not wall; basemat leaching of Accessible areas: constructed as calcium Inspections performed in accordance stated for hydroxide with IWL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

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(D II CONTAINMENT STRUCTURES (D

B1.2 Mark I Concrete Containments 3

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Evaluation U1 II.B12-7 ILB1.2. Concrete: Concrete; Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, scope of the subfoundation cracking, Erosion of cement from porous applicant's differential concrete subfoundations ben eath structures settlement! containment base mats is described in monitoring erosion of porous IN 97-11. IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, then the OJ licensee is to ensure proper functioning of the de-watering system w

through the period of extended operation.

II.B12-8 ILB1.2. Steel elements: Steel Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, Yes, if uncontrolled or general, pitting, Subsection IWE" corrosion is (C-46) Suppression treated water and crevice significant for chamber; corrosion For inaccessible areas (embedded inaccessible drywell liner; containment steel shell or liner), loss areas drywell head; of material due to corrosion is not embedded significant if the following conditions shell; sand are satisfied:

z pocket region; C support skirt; Concrete meeting the specifications

0 m downcomer of ACI 318 or 349 and the guidance of Gl pipes; region 201.2R was used for the containment shielded by concrete in contact with the diaphragm embedded containment shell or liner.

0 floor (as The concrete is monitored to ensure (D

< applicable) that it is free of penetrating cracks OAGI0000203_181

z II CONTAINMENT STRUCTURES C

0 B1.2 Mark I Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< that provide a path for water seepage NOTE to the surface of the containment shell Inspection of or liner. The moisture barrier, at the containment junction where the shell cr liner supports is becomes embedded, is subject to addressed by aging management activities in ASME accordance with ASME Section XI, Section XI, Subsection IWE requirements. Water Subsection ponding on the containment concrete IWF (see floor are not common and when IIIB13) detected are cleaned up in a timely manner.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

Chapter XIS4, "10 CFR Part 50, No Appendix J" IIB1.2-9 IIB1.2. Steel elements: Steel Air - indoor Fretting or Chapter XIS1, "ASME Section XI, No uncontrolled lockup! Subsection IWE" (C-23) Drywell head; mechanical wear Downcomers IIB1.2-10 IIB1.2. Steel elements: Stainless Air - indoor Loss of material! Chapter XIS1, "ASME Section XI, No (f)

(D steel; steel uncontrolled or general, pitting, Subsection IWE" and Chapter XIS4, (D

(C-49) Su ppression treated water and crevice "10 CFR Part 50, Appendix J" 3 chamber liner corrosion 0-

~

(interior surface)

'"oo U1 OAGI0000203_ 182

B2. MARK II CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark II containment structures. Mark II steel containments are discussed in II.B2.1. Mark II concrete containments are discussed in II.B2.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and standby gas treatment system (V.B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure base mat may provide support to the NSSS components and containment internal structures.

September 2005 II B2-1 NUREG-1801, Rev. 1 OAGI0000203_ 183

z II CONTAINMENT STRUCTURES C

0 B2.1 Mark II Steel Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.1-1 II.B2.1 1-a Steel elements: Steel Air - indoor Loss of Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or material! Subsection IWE" corrosion is (C-46) Suppression treated water general, pitting, significant for chamber; and crevice For inaccessible areas (embedded inaccessible drywell liner; corrosion containment steel shell or liner), loss of areas drywell head; material due to corrosion is not embedded significant if the following conditions shell; sand are satisfied:

pocket region; support skirt; Concrete meeting the specifications of downcomer ACI 318 or 349 and the guidance of pipes; region 201.2R was used for the containment shielded by concrete in contact with the embedded diaphragm containment shell or liner. The concrete floor (as is monitored to ensure that it is free of applicable) penetrating cracks that provide a path for water seepage to the surface of the NOTE containment shell or liner. The moisture Inspection of barrier, at the junction where the shell containment or liner becomes embedded, is subject supports is to aging management activities in addressed by accordance with ASME Section XI, ASME Subsection IWE requirements. Water Section XI, ponding on the containment concrete Subsection floor are not common and when IWF(see detected are cleaned up in a timely III.B13) manner.

(f)

(D If any of the above conditions cannot (D be satisfied, then a plant-specific aging 3 management program for corrosion is 0-

~ necessary.

'"oo Chapter XI.S4, "10 CFR Part 50, No U1 OAGI0000203_ 184

(f)

(D II CONTAINMENT STRUCTURES (D

B2.1 Mark II Steel Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 Appendix J" II.B2.1-2 II.B2.1.1-d Steel elements: Steel Air - indoor Fretting or Chapter XI.S1, "ASME Section XI, No uncontrolled lockup! Subsection IWE" (C-23) Drywell head; mechanical Downcomers wear II.B2.1-3 II.B2.1.1-b Suppression Steel; Air - indoor Cracking! cyclic Chapter XI.S1, "ASME Section XI, Yes, detection pool shell; stainless uncontrolled loading Subsection IWE" and Chapter XI.S4, of aging (C-44) unbraced steel; "10 CFR Part 50, Appendix J" effects is to be downcomers dissimilar (CLB fatigue evaluated OJ metal analysis does Evaluation of 10 CFR 50.55a!ASME

'"w welds not exist) Section XI, Subsection IWE is to be supplemented to consider the following:

(4) Detection of Aging Effects VT-3 visual inspection may not detect fine cracks.

II.B2.1-4 II.B2.1.1-c Suppression Steel; Air - indoor Cumulative Fatigue is a time-limited aging analysis Yes, pool shell; stainless uncontrolled fatigue damage! (TLAA) to be evaluated for the period TLAA (C-45) unbraced steel; fatigue of extended operation. See the downcomers dissimilar Standard Review Plan, Section 4.6, metal (Only if CLB "Containment Liner Plate and z welds fatigue analysis Penetration Fatigue Analysis" for C

0 exists) acceptable methods for meeting the m requirements of 10 CFR 5421(c)(1)

Gl

0 (D

OAGI0000203_ 185

z C

0 m

Gl

--I

T iii"

-u (Q

CD

J CD

~

OJ 0"

.h

J

~

r-CD OJ or

J (f)

(D

'"3" (D

0"

~

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(f)

(D (D II CONTAINMENT STRUCTURES 3 B2.2 Mark II Concrete Containments 0-

~

'"oo Structure and/or Aging Effect! Further U1 Item Link Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-1 II.B2.2.1-e Concrete Concrete Soil Cracks and Chapter XI.S6, "Structures Monitoring Yes, if not elements; All distortion due to Program" within the (C-06) increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-watering operation. system is relied upon z

C

0 m

Gl

0 (D

OAGI0000203_ 187

z II CONTAINMENT STRUCTURES C

0 B2.2 Mark II Concrete Containments m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-2 II.B2.2.1-d Concrete: Concrete; Air - indoor Cracking, loss of Chapter XI.S2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Subsection IWL" specific if (C-41) Basemat; air - outdoor material environment reinforcing (spalling, Accessible Areas: is aggressive steel scaling)/ Inspections performed in accordance corrosion of with IWL will indicate the presence of embedded steel surface cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of em bedded steel.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or su Ifates < 1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have (f) experienced degradation, a plant (D specific AMP accounting for the extent (D of the degradation experienced should 3 be implemented to manage the 0-

~ concrete aging during the period of extended operation.

'"oo U1 OAGI0000203_ 188

(f)

(D II CONTAINMENT STRUCTURES (D

B2.2 Mark II Concrete Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B2.2-3 II.B221-g Concrete: Concrete Air - indoor Red uction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-35) Containment; air - outdoor modulus! limits are wall; basemat elevated The implementation of 10 CFR 50.55a exceeded temperature and ASME Section XI, Subsection IWL

(>150°F general; would not be able to identify the

>200°F local) reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipment loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given above z

C may be allowed in the concrete if tests

0 and!or calculations are provided to m

Gl evaluate the reduction in strength and this reduction is applied to the design allowables.

0 (D

OAGI0000203_ 189

z II CONTAINMENT STRUCTURES C

0 B2.2 Mark II Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-4 II.B2.2.1-c Concrete: Concrete Any Cracking due to Chapter XI.S2, "ASME Section XI, Yes, if expansion! Subsection IWL" concrete was (C-39) Containment; reaction with not wall; basemat aggregates Accessible Areas: constructed Inspections performed in accordance as stated for with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas aggregates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

(D (D

3 0-

~

'"oo U1 OAG10000203_ 190

(f)

(D II CONTAINMENT STRUCTURES (D

B2.2 Mark II Concrete Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B2.2-5 II.B2.2.1-b Concrete: Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, Yes, plant-water/soil or porosity and Subsection IWL" specific if (C-26) Containment; air-indoor permeability, environment wall; basemat uncontrolled or cracking, loss of Accessible Areas: is aggressive air-outdoor material Inspections performed in accordance (spalling, with IWL will indicate the presence of scaling)/ increase in porosity and permeability, aggressive surface cracking, or loss of material chemical attack (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or su Ifates < 1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive z

C groundwater/soil, and/or where the

0 concrete structural elements have m

Gl experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should

0 be implemented to manage the (D

concrete aging during the period of extended operation.

OAGI0000203_ 191

z II CONTAINMENT STRUCTURES C

0 B2.2 Mark II Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-6 II.B2.2.1-a Concrete: Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, Yes, if porosity, Subsection IWL" concrete was (C-31) Containment; permeability! not wall; basemat leaching of Accessible areas: constructed calcium Inspections performed in accordance as stated for hydroxide with IWL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is OJ documented evidence that confirms t;: the in-place concrete was constructed o

in accordance with the recommendations in ACI 201.2R-77.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_ 192

(f)

(D II CONTAINMENT STRUCTURES (D

B2.2 Mark II Concrete Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B2.2-7 II.B2.2.1-f Concrete: Concrete; Water - flowing Reduction in Chapter XI.S6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, scope of the subfoundatio n cracking, Erosion of cement from porous applicant's differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of IN 97-11. IN 98-26 proposes program or a porous concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, then the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

II.B2.2-8 II.B2.2.3-b Prestressing Steel Air - indoor Loss of Loss of tendon prestress is a time- Yes, system: uncontrolled or prestress! limited aging analysis (TLAA) to be TLAA (C-11) air - outdoor relaxation; evaluated for the period of extended Tendons shrinkage; operation.

creep; elevated temperature See the Standard Review Plan, Section 4.5, "Concrete Containment Tendon Prestress" for acceptable z methods for meeting the requirements C of 10 CFR 5421(c)(1)(i) and (ii) See

0 m Chapter X.S1 of this report for meeting Gl the requirements of 10 CFR 5421(c)(1)(iii)

0 For periodic monitoring of prestress, (D

< see Chapter XI.S2.

OAGI0000203_ 193

z II CONTAINMENT STRUCTURES C

0 B2.2 Mark II Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-9 II.B2.2.3-a Prestressing Steel Air - indoor Loss of material! Chapter XI.S2, "ASME Section XI, No system: uncontrolled or corrosion Subsection IWL" (C-10) air - outdoor Tendons; anchorage components II.B2.2-10 II.B2.2.2-a Steel elements: Steel Air - indoor Loss of material! Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or general, pitting, Subsection IWE" corrosion is (C-46) Suppression treated water and crevice significant for chamber; corrosion For inaccessible areas (embedded inaccessible drywell liner; containment steel shell or liner), loss of areas drywell head; material due to corrosion is not embedded significant if the following conditions shell; sand are satisfied:

pocket region; support skirt; Concrete meeting the specifications of downcomer ACI 318 or 349 and the guidance of pipes; region 201.2R was used for the containment shielded by concrete in contact with the embedded diaphragm containment shell or liner. The floor (as concrete is monitored to ensure that it applicable) is free of penetrating cracks that provide a path for water seepage to NOTE the surface of the containment shell or Inspection of liner. The moisture barrier, at the containment unction where the shell or liner supports is becomes embedded, is subject to (f) addressed by aging management activities in (D

ASME accordance with ASME Section XI, (D Section XI, Subsection IWE requirements. Water 3 Subsection ponding on the containment concrete 0-

~ IWF (see floor are not common and when

'"oo III.B13) detected are cleaned up in a timely U1 OAGI0000203_ 194

(f)

(D II CONTAINMENT STRUCTURES (D

B2.2 Mark II Concrete Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 manner.

If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

Chapter XI.S4, "10 CFR Part 50, No Appendix J" II.B2.2-11 II.B2.2.2-e Steel elements: Steel Air - indoor Fretting or Chapter XI.S1, "ASME Section XI, No uncontrolled lockup! Subsection IWE" (C-23) Drywell head; mechanical wear Downcomers II.B2.2-12 II.B2.2.2-b Steel elements: Stainless Air - indoor Loss of material! Chapter XI.S1, "ASME Section XI, No steel; steel uncontrolled or general, pitting, Subsection IWE" and Chapter XI.S4, (C-4g) Su ppression treated water and crevice "10 CFR Part 50, Appendix J" chamber liner corrosion (interior surface)

II.B2.2-13 II.B2.2.2-c Steel elements: Stainless Air - indoor Cracking! cyclic Chapter XI.S1, "ASME Section XI, Yes, detection steel; steel uncontrolled loading Subsection IWE" and Chapter XI.S4, of aging (C-4?) Vent header; "10 CFR Part 50, Appendix J" effects is to be z Downcomers (CLB fatigue evaluated C

0 analysis does Evaluation of 10 CFR 50.55a!ASME m not exist) Section XI, Subsection IWE is Gl augmented as follows:

(4) Detection of Aging Effects VT-3 visual inspection may not detect fine

0 (D

cracks.

OAGI0000203_ 195

z II CONTAINMENT STRUCTURES C

0 B2.2 Mark II Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component II.B2.2-14 II.B2.2.2-d Steel elements: Stainless Air - indoor Cumulative Fatigue is a time-limited aging analysis Yes, steel; steel uncontrolled or fatigue damage! (TLAA) to be evaluated for the period TLAA (C-4S) Vent header; treated water fatigue of extended operation. See the Downcomers Standard Review Plan, Section 4.6, (Only if CLB "Containment Liner Plate and fatigue analysis Penetration Fatigue Analysis" for exists) acceptable methods for meeting the requirements of 10 CFR 5421(c)(1)

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_ 196

83. MARK III CONTAINMENTS 83.1 Steel Containments 83.2 Concrete Containments September 2005 1183-1 NUREG-1801, Rev. 1 OAGI0000203_ 197

This Page Intentionally Left Blank NUREG-1801, Rev. 1 1183-2 September 2005 OAGI0000203_ 198

B3. MARK III CONTAINMENTS Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) Mark III containment structures. Mark III steel containments are discussed in II.B3.1. Mark III concrete containments are discussed in II.B3.2.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

September 2005 1183-3 NUREG-1801, Rev. 1 OAGI0000203_ 199

z II CONTAINMENT STRUCTURES C

0 B3.1 Mark III Steel Containments m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.1-1 II.B3.1.2-b Concrete: Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, Yes, plant-water/soil porosity and Subsection IWL" specific if (C-25) Basemat permeability, environment i cracking, loss of Accessible Areas: aggressive material Inspections performed in accordance (spalling, with IWL will indicate the presence of scaling)/ increase in porosity and permeability, aggressive surface cracking, or loss of material chemical attack (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive OJ ground water/soil; i.e., pH > 5.5,

't chlorides < 500 ppm, or sulfates

<1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with ag g ressive groundwater/soil, and/or where the (f) concrete structural elements have (D experienced degradation, a plant (D specific AMP accounting for the 3 extent of the degradation experienced 0-

~ should be implemented to manage the concrete aging during the period

'"oo of extended operation.

U1 OAGI0000203_200

(f)

(D II CONTAINMENT STRUCTURES (D

B3.1 Mark III Steel Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.1-2 II.B3.1.2-e Concrete: Concrete Soil Cracks and Chapter XI.S6, "Structures Monitoring Yes, if not distortion due to Program" within the (C-36) Basemat increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-watering operation. system is relied upon II.B3.1-3 II.B3.1.2-a Concrete: Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, Yes, if porosity, Subsection IWL" concrete was (C-3D) Basemat permeability! not leaching of Accessible areas: constructed as calcium Inspections performed in accordance stated for hydroxide with IWL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that z confirms the in-place concrete was C constructed in accordance with the

0 m recommendations in ACI 2D1.2R.

Gl OAGI0000203_201

z II CONTAINMENT STRUCTURES C

0 B3.1 Mark III Steel Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.1-4 II.B312-g Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-50) Basemat, air - outdoor modulus! limits are concrete fill-in elevated The implementation of exceeded annulus temperature 10 CFR 50.55a and ASME Section

(>150°F general; XI, Subsection IVVL would not be able

>200°F local) to identify the reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted.

Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipment loads are su pported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

(f)

Higher temperatures than given (D above may be allowed in the concrete (D if tests and!or calculations are 3 provided to evaluate the reduction in 0-

~ strength and this reduction is applied to the design allowables.

'"oo U1 OAGI0000203_202

(f)

(D II CONTAINMENT STRUCTURES (D

B3.1 Mark III Steel Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.1-5 II.B3.1.2-c Concrete: Concrete Any Cracking due to Chapter XI.S2, "ASME Section XI, Yes, if expansion! Subsection IWL" concrete was (C-51) Basemat, reaction with not concrete fill-in aggregates Accessible Areas: constructed as annulus Inspections performed in accordance stated for with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas aggregates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227 -50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2RTherefore, if these conditions are satisfied, aging management is not necessary.

z C

0 m

Gl OAGI0000203_203

z II CONTAINMENT STRUCTURES C

0 B3.1 Mark III Steel Containments m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.1-6 II.B3.1.2-d Concrete: Concrete; Air - indoor Cracking, loss of Chapter XI.S2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Subsection IWL" specific if (C-43) Basemat; air - outdoor material environment i reinforcing (spalling, Accessible Areas: aggressive steel scaling)/ Inspections performed in accordance corrosion of with IWL will indicate the presence of embedded steel surface cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steel.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates

<1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have (f) experienced degradation, a plant (D specific AMP accounting for the (D extent of the degradation experienced 3 should be implemented to manage 0-

~ the concrete aging during the period of extended operation.

'"oo U1 OAGI0000203_204

(f)

(D II CONTAINMENT STRUCTURES (D

B3.1 Mark III Steel Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.1-7 II.B3.1.2-f Concrete: Concrete; Water - flowing Reduction in Chapter XI.S6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, scope of the subfoundation cracking, Erosion of cement from porous applicant's differential concrete subfoundations beneath structures settlement! containment base mats is described in monitoring erosion of porous IN 97-11. IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, then the OJ licensee is to ensure proper o functioning of the de-watering system through the period of extended operation.

II.B3.1-8 II.B3.1.1-a Steel elements: Steel Air - indoor Loss of material! Chapter XI.S1, "ASME Section XI, Yes, if uncontrolled or general, pitting, Subsection IWE" corrosion is (C-19) Drywell; torus; treated water and crevice significant for drywell corrosion For inaccessible areas (embedded inaccessible head; containment steel shell or liner), loss areas embedded of material due to corrosion is not shell significant if the following conditions and sand are satisfied:

z pocket C regions; Concrete meeting the specifications

0 m drywell of ACI 318 or 349 and the guidance Gl support skirt; of 201.2R was used for the torus ring containment concrete in contact with girder; the embedded containment shell or downcomers; liner. The concrete is monitored to ECCS ensure that it is free of penetrating OAGI0000203_205

z II CONTAINMENT STRUCTURES C

0 B3.1 Mark III Steel Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< suction cracks that provide a path for water header seepage to the surface of the containment shell or liner. The NOTE moisture barrier, at the junction where Inspection of the shell or liner becomes embedded, containment is subject to aging management supports is activities in accordance with ASME addressed by Section XI, Subsection IWE ASME requirements. Water ponding on the Section XI, containment concrete floor are not Subsection common and when detected are IWF (see cleaned up in a timely manner IIIB13)

OJ If any of the above conditions cannot

~ be satisfied, then a plant-specific o

aging management program for corrosion is necessary. No Chapter XIS4, "10 CFR Part 50, Appendix J" IIB3.1-9 IIB3.1.1-b Steel elements: Stainless Air - indoor Cracking! stress Chapter XIS1, "ASME Section XI, No steel uncontrolled corrosion Subsection IWE" and Chapter XIS4, (C-24) Suppression cracking "10 CFR Part 50, Appendix J" cham ber shell (interior surface)

(f)

(D (D

3 0-

~

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(f)

(D (D II CONTAINMENT STRUCTURES 3 83.2 Mark III Concrete Containments 0-

~

'"oo Structure and!or Aging Effect! Further U1 Item Link Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component 11.83.2-1 11.83.2.1-f Concrete Concrete Soil Cracks and Chapter XI.S6, "Structures Monitoring Yes, if not elements; All distortion due to Program" within the (C-06) increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-watering operation. system is relied upon z

C

0 m

Gl OAGI0000203_207

z II CONTAINMENT STRUCTURES C

0 B3.2 Mark III Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.2-2 II.B3.2.1-h Concrete: Concrete Air - indoor Reduction of Plant-specific aging management Yes, if uncontrolled or strength and program temperature (C-33) Dome; wall; air - outdoor modulus! limits are basemat elevated The implementation of 10 CFR 50.55a exceeded temperature and ASME Section XI, Subsection

(>150°F general; IWL would not be able to identify the

>200°F local) reduction of strength and modulus due to elevated temperature. Thus, for any portions of concrete containment that exceed specified temperature limits, further evaluations are warranted. Subsection CC-3400 of ASME Section III, Division 2, specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas, such as around penetrations, which are not allowed to exceed 200T If significant equipmen loads are supported by concrete at temperatures exceeding 150°F, an evaluation of the ability to withstand the postulated design loads is to be made.

Higher temperatures than given (f) above may be allowed in the concrete (D if tests and!or calculations are (D provided to evaluate the reduction in 3 strength and this reduction is applied 0-

~ to the design allowables.

'"oo U1 OAGI0000203_208

(f)

(D II CONTAINMENT STRUCTURES (D

B3.2 Mark III Concrete Containments 3

0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.2-3 II.B3.2.1-a Concrete: Concrete Air - outdoor Loss of material Chapter XI.S2, "ASME Section XI, Yes, for (spalling, scaling) Subsection IWL" inaccessible (C-29) Dome; wall; and cracking/ areas of basemat freeze-thaw Accessible areas: plants located Inspections performed in accordance in moderate to with IWL will indicate the presence of severe loss of material (spalling, scaling) and weathering surface cracking due to freeze-thaw. conditions Inaccessible Areas:

Evaluation is needed for plants that are located in moderate to severe weathering conditions (weathering index >100 day-inch/yr) (NUREG-1557). Documented evidence confirms that where the existing concrete had air content of 3% to 6%,

subsequent inspection did not exhibit degradation related to freeze-thaw Such inspections should be considered a part of the evaluation.

The weathering index for the conti nental US is shown in AST M C33-90, Fig 1.

z C

0 m

Gl OAGI0000203_209

z II CONTAINMENT STRUCTURES C

0 B3.2 Mark III Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.2-4 II.B3.2.1-d Concrete: Concrete Any Cracking due to Chapter XI.S2, "ASME Section XI, Yes, if expansion! Subsection IWL" concrete was (C-40) Dome; wall; reaction with not basemat aggregates Accessible Areas: constructed as Inspections performed in accordance stated for with IWL will indicate the presence of inaccessible surface cracking due to reaction with areas agg regates.

Inaccessible Areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227 -50 can demonstrate that those aggregates do not react within reinforced concrete.

For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_210

(f)

(D II CONTAINMENT STRUCTURES (D

B3.2 Mark III Concrete Containments 3

0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.2-5 II.B3.2.1-c Concrete: Concrete Ground Increase in Chapter XI.S2, "ASME Section XI, Yes, plant-water/soil or porosity and Subsection IWL" specific if (C-27) Dome; wall; air-indoor permeability, environment i basemat uncontrolled or cracking, loss of Accessible Areas: aggressive air-outdoor material Inspections performed in accordance (spalling, with IWL will indicate the presence of scaling)/ increase in porosity and permeability, aggressive surface cracking, or loss of material chemical attack (spalling, scaling) due to aggressive chemical attack.

Inaccessible Areas:

For plants with non-aggressive OJ ground water/soil; i.e., pH > 5.5,

~ chlorides < 500 ppm, or sulfates U1

<1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive z

C groundwater/soil, and/or where the

0 concrete structural elements have m

Gl experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

OAGI0000203_211

z II CONTAINMENT STRUCTURES C

0 B3.2 Mark III Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.2-6 II.B3.2.1-b Concrete: Concrete Water - flowing Increase in Chapter XI.S2, "ASME Section XI, Yes, if porosity, Subsection IWL" concrete was (C-32) Dome; wall; permeability! not basemat leaching of Accessible areas: constructed as calcium Inspections performed in accordance stated for hydroxide with IWL will indicate the presence of inaccessible increase in porosity, and permeability areas due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_212

(f)

(D II CONTAINMENT STRUCTURES (D

B3.2 Mark III Concrete Containments 3

0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 II.B3.2-7 II.B3.2.1-e Concrete: Concrete; Air - indoor Cracking, loss of Chapter XI.S2, "ASME Section XI, Yes, plant-steel uncontrolled or bond, and loss of Subsection IWL" specific if (C-42) Dome; wall; air - outdoor material environment i basemat; (spalling, Accessible Areas: aggressive reinforcing scaling)/ Inspections performed in accordance steel corrosion of with IWL will indicate the presence of embedded steel surface cracking, loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steel.

Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates

<1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the z

C concrete structural elements have

0 experienced degradation, a plant m

Gl specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

OAGI0000203_213

z II CONTAINMENT STRUCTURES C

0 B3.2 Mark III Concrete Containments m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< II.B3.2-8 II.B321-g Concrete: Concrete; Water - flowing Red uction in Chapter XI.S6, "Structures Monitoring Yes, if not porous foundation Program" within the (C-07) Foundation; concrete strength, scope of the subfoundatio cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment base mats is described in monitoring erosion of porous IN 97-11. IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, then the OJ licensee is to ensure proper

~ functioning of the de-watering system OJ through the period of extended operation.

II.B3.2-9 II.B3.2.2-a Steel Steel Air - indoor Loss of material! Chapter XI.S1, "ASME Section XI, Yes, if elements: uncontrolled general, pitting, Subsection IWE" corrosion is (C-09) and crevice significant for Liner; corrosion For inaccessible areas (embedded inaccessible Liner containment steel shell or liner), loss areas anchors; of material due to corrosion is not Integral significant if the following conditions attachments are satisfied:

1. Concrete meeting the requirements (f) of ACI 318 or 349 and the guidance of (D

201.2R was used for the containment (D concrete in contact with the 3 embedded containment shell or liner.

0-

~ 2. The concrete is monitored to

'"oo ensure that it is free of penetrating U1 OAGI0000203_214

(f)

(D II CONTAINMENT STRUCTURES (D

B3.2 Mark III Concrete Containments 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 cracks that provide a path for water seepage to the surface of the containment shell or liner.

3. The moisture barrier, at the junction where the shell or liner becomes embedded, is subject to aging management activities in accordance with ASME Section XI, Subsection IWE requirements.

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

~

CD If any of the above conditions cannot be satisfied, then a plant-specific aging management program for corrosion is necessary.

Chapter XIS4, "10 CFR Part 50, No Appendix J" IIB3.2-10 IIB3.2.2-b Steel Stainless Air - indoor Cracking! stress Chapter XIS1, "ASME Section XI, No elements: steel uncontrolled corrosion Subsection IWE" and Chapter XIS4, (C-24) cracking "10 CFR Part 50, Appendix J" z Suppression C chamber shell

0 m (interior Gl surface)

OAGI0000203_215

This Page Intentionally Left Blank NUREG-1801, Rev. 1 1183-20 September 2005 OAGI0000203_216

B4. COMMON COMPONENTS Systems, Structures, and Components This section addresses the common components of boiling water reactor (BWR) containments.

The common components include penetration sleeves and bellows; dissimilar metal welds; personnel airlock; equipment hatch; CRD hatch; seals, gaskets, and moisture barriers.

System Interfaces Functional interfaces include the primary containment heating and ventilation system (VII.F3),

containment isolation system (V.C), and standby gas treatment system (V. B). Physical interfaces exist with any structure, system, or component that either penetrates the containment wall, such as the main steam system (VIII.B2) and feedwater system (VIII.D2), or is supported by the containment structure. The containment structure basemat may provide support to the NSSS components and containment internal structures.

September 2005 II B4-1 NUREG-1801, Rev. 1 OAGI0000203_217

z II CONTAINMENT STRUCTURES C

0 B4 Common Components m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< ILB4-1 ILB4.1-a Penetration Steel; Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, No sleeves dissimilar uncontrolled general, pitting, Subsection IWE,"

(C-12) metal welds or air - outdoor and crevice corrosion (Note: IWE examination category E-F, surface examination of dissimilar metal welds, is recommended)

Chapter XLS4, "10 CFR Part 50, No Appendix J" OJ t

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_218

(f)

(D II CONTAINMENT STRUCTURES (D

B4 Common Components 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 ILB4-2 ILB4.1-d Penetration Stainless Air - indoor Crackingl stress Chapter XLS1, "ASME Section XI, Yes, detection sleeves; steel; uncontrolled or corrosion Subsection IWE" and Chapter XLS4, of aging (C-15) Penetration dissimilar air - outdoor cracking "10 CFR Part 50, Appendix J" effects is to bellows metal welds be evaluated Evaluation of 10 CFR 50.55a/ASME Section XI, Subsection IWE is augmented as follows:

(4) Detection of Aging Effects Transgranular Stress corrosion cracking (TGSCC) is a concern for dissimilar metal welds. In the case of bellows assemblies, SCC may cause OJ aging effects particularly if the material t is not shielded from a corrosive environment ASME Section XI, Subsection IWE covers inspection of these items under examination categories E-B, E-F, and E-P (10 CFR Part 50, Appendix J pressure tests).

10 CFR 50.55a identifies examination categories E-B and E-F as optional during the current term of operation.

For the extended period of operation, Examination Categories E-B & E-F, and additional appropriate examinations to z

C detect SCC in bellows assemblies and

0 dissimilar metal welds are warranted to rn Gl address this issue.

(10) Operating Experience:

0 IN 92-20 describes an instance of (D

containment bellows cracking, resulting in loss of leak tiqhtness.

OAGI0000203_219

z II CONTAINMENT STRUCTURES C

0 B4 Common Components m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< ILB4-3 ILB4.1-c Penetration Steel; Air - indoor Cracking! cyclic Chapter XLS1, "ASME Section XI, Yes, detection sleeves; stainless uncontrolled or loading Subsection IWE" and Chapter XLS4, of aging (C-14) Penetration steel; air - outdoor "10 CFR Part 50, Appendix J" effects is to bellows dissimilar (CLB fatigue be evaluated metal welds analysis does Evaluation of 10 CFR 50.55a!ASME not exist) Section XI, Subsection IWE is to be supplemented to consider the following:

(4) Detection of Aging Effects VT-3 visual inspection may not detect fine cracks.

ILB4-4 ILB4.1-b Penetration Steel; Air - indoor Cumulative Fatigue is a time-limited aging analysis Yes, sleeves; stainless uncontrolled or fatigue damage! (TLAA) to be evaluated for the period of TLAA OJ (C-13) Penetration steel; air - outdoor fatigue extended operation. See the Standard t bellows dissimilar Review Plan, Section 4.6, metal welds (Only if CLB "Containment Liner Plate and fatigue analysis Penetration Fatigue Analysis" for exists) acceptable methods for meeting the requirements of 10 CFR 5421(c)(1)

ILB4-5 ILB4.2-b Personnel Steel Air - indoor Loss of leak Chapter XLS4, "10 CFR Part 50, No airlock, uncontrolled tightness! Append ix J" and (C-17) equipment or air - outdoor mechanical wear hatch, CRD of locks, hinges Plant Technical Specifications hatch: and closure mechanisms Locks, (f) hinges, and (D

closure (D mechanisms 3

0-

~

'"oo U1 OAGI0000203_220

(f)

(D II CONTAINMENT STRUCTURES (D

B4 Common Components 3

0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 ILB4-6 ILB4.2-a Personnel Steel Air - indoor Loss of material! Chapter XLS1, "ASME Section XI, No airlock, uncontrolled or general, pitting, Subsection IWE,"

(C-16) equipment air - outdoor and crevice hatch, CRD corrosion Chapter XLS4, "10 CFR Part 50, No hatch Appendix J" ILB4-7 ILB4.3-a Seals, Elastomers, Air - indoor Loss of sealing; Chapter XLS1, "ASME Section XI, No gaskets, and rubber and uncontrolled or Leakage through Subsection IWE" (C-18) moisture other similar air - outdoor containment!

barriers materials deterioration of Leak tightness will be monitored by (caulking, seals, gaskets, 10 CFR Part 50, Appendix J Leak Rate flashing, and and moisture Tests for pressure boundary, seals and other barriers gaskets (including O-rings) sealants) (caulking, flashing, and other sealants) z C

0 m

Gl

0 (D

OAGI0000203_221

This Page Intentionally Left Blank NUREG-1801, Rev. 1 II B4-6 September 2005 OAGI0000203_222

CHAPTER III STRUCTURES AND COMPONENT SUPPORTS September 2005 III-i NUREG-1801, Rev. 1 OAGI0000203_223

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III-ii September 2005 OAGI0000203_224

STRUCTURES AND COMPONENT SUPPORTS Chapter III A: Safety Related and Other Structures Safety related structures are those structures defined pursuant to 10 CFR 54.4(a)(1) and the other structures are those defined pursuant to 10 CFR 54.4(a)(2) and 10 CFR 54.4(a)(3).

Structures in this section are organized into nine groups and are discussed separately under subheadings A1 through A9.

Chapter III B: Component Supports Component supports include supports for ASME piping and components; supports for cable trays, conduit, HVAC ducts, TubeTrack, instrument tubing, non-ASME piping and components; anchorage of racks, panels, cabinets, and enclosures for electrical equipment and instrumentation; supports for emergency diesel generator (EDG) and HVAC system components; and supports for platforms, pipe whip restraints, jet impingement shields, masonry walls, and other miscellaneous structures.

September 2005 III-iii NUREG-1801, Rev. 1 OAGI0000203_225

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III-iv September 2005 OAGI0000203_226

III.A SAFETY RELATED AND OTHER STRUCTURES A1. Group 1 Structures (BWR Reactor Bldg., PWR Shield Bldg., Control Rm.lBldg.)

A2. Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

A3. Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker Foundation, Electrical Enclosure)

A4. Group 4 Structures (Containment Internal Structures, excluding Refueling Canal)

A5. Group 5 Structures (Fuel Storage Facility, Refueling Canal)

A6. Group 6 Structures (Water-Control Structures)

A7. Group 7 Structures (Concrete Tanks and Missile Barriers)

A8. Group 8 Structures (Steel Tanks and Missile Barriers)

A9. Group 9 Structures (BWR Unit Vent Stack)

September 2005 IIIA-1 NUREG-1801, Rev. 1 OAGI0000203_227

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III A-2 September 2005 OAGI0000203_228

A1. GROUP 1 STRUCTURES (BWR REACTOR BLDG., PWR SHIELD BLDG., CONTROL RM.lBLDG.)

Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) reactor building, pressurized water reactor (PWR) shield building, and control room/building. For this group, the applicable structural elements are concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems or components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIA1-1 NUREG-1801, Rev. 1 OAGI0000203_229

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA1-1 IILA11-j Concrete: Reinforced Air - indoor Reduction of Plant-specific aging management Yes, if concrete uncontrolled strength and program temperature (T-10) All modulus! elevated limits are temperature For any concrete elements that exceed exceeded

(>150°F general; specified temperature limits, further

>200°F local) evaluations are warranted. Appendix A of ACI 349-85 specifies the concrete temperature limits for normal operation or any other long -term period. The temperatures shall not exceed 150°F except for local areas which are allowed to have increased temperatures not to exceed 200T (f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) 3 0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA1-2 III.A11-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking due concrete was to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

z C

0 m

Gl

0 (D

OAGI0000203_231

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA1-3 IILA1.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon for applicant's settlement control of settlement, then the licensee structures is to ensure proper functioning of the de- monitoring watering system through the period of program or a extended operation. de-wateri ng system is relied upon (f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) 3 0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA1-4 IILA11-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material (spalling, environment is exterior; scaling)/ corrosion Accessible Areas: aggressive foundation of embedded steel Inspections performed in accordance with the Structures Monitoring Program will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of em bedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the z

C concrete structural elements have

0 experienced degradation, a plant m

Gl specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete

0 aging during the period of extended (D

operation.

OAGI0000203_233

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) m Gl Structure Aging Effect/ Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA1-5 IIIA11-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < 500 environment is exterior; cracking, loss of ppm, or sulfates <1500 ppm, as a aggressive foundation material (spalling, minimum, consider scaling)/

aggressive (1) Examination of the exposed portions chemical attack of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_234

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) 3 0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA1-6 III.A11-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw areas of plants located in Inaccessible Areas: moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering index conditions

> 100 day-inch/yr) (NUREG-1557)

Documented evidence to confirm that existing concrete has air content of 3%

to 6% and water-to-cement ratio of 0.35-0,45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig 1 z

C

0 m

Gl

0 (D

OAGI0000203_235

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA1-7 IILA1.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, loss not above- and of strength! Accessible areas: constructed as below-grade; leaching of calcium Inspections performed in accordance stated for foundation hydroxide with the Structures Monitoring Program inaccessible will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA1-8 III.A11-i Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation foundation Program" within the (T-09) Foundation; Porous strength, cracking, scope of the subfoundation concrete differential Erosion of cement from porous concrete applicant's settlement! erosion subfoundations beneath containment structures of porous concrete basemats is described in NRC IN 97-11. monitoring subfoundation NRC IN 98-26 proposes Maintenance program or a Rule Structures Monitoring for managing de-wateri ng this aging effect, if applicable If a de- system is watering system is relied upon for relied upon control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

IILA1-9 IILA11-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material (spalling, scope of the above-grade scaling)! corrosion Accessible areas: applicant's exterior of embedded steel Inspections performed in accordance structures with the Structures Monitoring Program monitoring will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of z embedded steeL C

0 m

Gl

0 (D

OAGI0000203_237

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA1-10 III.A11-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material (spalling, Inspections performed in accordance structures scaling)! with Structures Monitoring Program will monitoring aggressive indicate the presence of increase in program chemical attack porosity and permeability, cracking, or loss of material (spalling, scaling) due to aggressive chemical attack.

IILA1-11 IILA1.3-a Masonry walls: Concrete Air - indoor Cracking due to Chapter XLS5, "Masonry Wall Program" No block uncontrolled or restraint shrinkage, (T-12) All air - outdoor creep, and aggressive environment o

IILA1-12 III.A12-a Steel Steel Air - indoor Loss of material! Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitoring and maintenance.

(f)

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A2. GROUP 2 STRUCTURES (BWR REACTOR BLDG. WITH STEEL SUPERSTRUCTURE)

Systems, Structures, and Components This section addresses the elements of boiling water reactor (BWR) reactor building with steel superstructure. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 III A2-1 NUREG-1801, Rev. 1 OAGI0000203_239

z III STRUCTURES AND COMPONENT SUPPORTS C A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

0 m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA2-1 IILA21-j Concrete: Reinforced Air - indoor Reduction of Plant-specific aging management Yes, if concrete uncontrolled strength and program temperature (T-10) All modulus! limits are elevated For any concrete elements that exceed exceeded temperature specified temperature limits, further

(>150°F general; evaluations are warranted. Appendix A

>200°F local) of ACI 349-85 specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas which are allowed to have increased temperatures not to exceed 200T (f)

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA2-2 IILA2.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

z C

0 m

Gl

0 (D

OAGI0000203_241

z III STRUCTURES AND COMPONENT SUPPORTS C A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

0 m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA2-3 IILA2.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon (f)

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A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA2-4 IILA2.1-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material environment i exterior; (spalling, Accessible Areas: aggressive foundation scaling)/ Inspections performed in accordance corrosion of with the Structures Monitoring Program embedded steel will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the z

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0 experienced degradation, a plant m

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0 concrete aging during the period of (D

< extended operation.

OAGI0000203_243

z III STRUCTURES AND COMPONENT SUPPORTS C A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

0 m

Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA2-5 IILA21-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material minimum, consider (spalling, scaling)/ (1) Examination of the exposed portions aggressive of the below-grade concrete, when chemical attack excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

(f)

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA2-6 IILA2.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions index> 100 day-inch/yr) (NUREG-1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water -to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig1 z

C

0 m

Gl

0 (D

OAGI0000203_245

z III STRUCTURES AND COMPONENT SUPPORTS C A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

0 m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA2-7 IILA2.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, los, not above- and of strength! Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

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A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA2-8 IILA2.1-i Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundatio concrete cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment base mats is described in monitoring erosion of porous NRC IN 97-11. NRC IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

IILA2-9 IILA2.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material scope of the above-grade (spalling, Accessible areas: applicant's exterior scaling)! Inspections performed in accordance structures corrosion of with the Structures Monitoring Program monitoring embedded steel will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of z embedded steeL C

0 m

Gl

0 (D

OAGI0000203_247

z III STRUCTURES AND COMPONENT SUPPORTS C A2 Group 2 Structures (BWR Reactor Bldg. with Steel Superstructure)

0 m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA2-10 IILA2.1-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material Inspections performed in accordance structures (spalling, with Structures Monitoring Program will monitoring scaling)! indicate the presence of increase in program aggressive porosity and permeability, cracking, or chemical attack loss of material (spalling, scaling) due to aggressive chemical attack.

IILA2-11 IILA2.3-a Masonry walls: Concrete Air - indoor Cracking due to Chapter XLS5, "Masonry Wall Program" No block uncontrolled or restraint (T-12) All air - outdoor shrinkage, creep, and aggressive environment IILA2-12 IILA2.2-a Steel Steel Air - indoor Loss of material! Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitoring and maintenance.

(f)

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A3. GROUP 3 STRUCTURES (AUXILIARY BLDG., DIESEL GENERATOR BLDG.,

RADWASTE BLDG., TURBINE BLDG., SWITCHGEAR RM., YARD STRUCTURES SUCH AS AFW PUMPHOUSE, UTILITY/PIPING TUNNELS, SECURITY/LIGHTING POLES, MANHOLES, DUCT BANKS; SBO STRUCTURES SUCH AS TRANSMISSION TOWERS, STARTUP TOWERS CIRCUIT BREAKER FOUNDATION, ELECTRICAL ENCLOSURE)

Systems, Structures, and Components This section addresses the elements of auxiliary building, diesel generator building, radwaste building, turbine building, switchgear room, yard structures, and station blackout (SBO) structures. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIA3-1 NUREG-1801, Rev. 1 OAGI0000203_249

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

Gl AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker foundation, Electrical Enclosure)

0 Structure (D Aging Effect! Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-1 IILA31-j Concrete: Reinforced Air - indoor Reduction of Plant-specific aging management Yes, if concrete uncontrolled strength and program temperature (T-10) All modulus/ limits are elevated For any concrete elements that exceed exceeded temperature specified temperature limits, further

(>150°F general; evaluations are warranted. Appendix A

>200°F local) of ACI 349-85 specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas which are allowed to have increased temperatures not to exceed 200T (f)

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-

~ Startup Towers Circuit Breaker foundation, Electrical Enclosure)

'"oo Structure U1 Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-2 IILA3.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not z

C necessary.

0 m

Gl

0 (D

OAGI0000203_251

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

Gl AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker foundation, Electrical Enclosure)

0 Structure (D Aging Effect! Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-3 IILA3.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon (f)

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3 0-

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-

~ Startup Towers Circuit Breaker foundation, Electrical Enclosure)

'"oo Structure U1 Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-4 IILA3.1-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material environment i exterior; (spalling, Accessible Areas: aggressive foundation scaling)/ Inspections performed in accordance corrosion of with the Structures Monitoring Program embedded steel will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

z C

0 For plants with aggressive m

Gl groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant

0 specific AMP accounting for the extent (D

of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

OAGI0000203_253

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

Gl AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker foundation, Electrical Enclosure)

0 Structure (D Aging Effect! Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-5 IILA31-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material minimum, consider (spalling, scaling)/ (1) Examination of the exposed aggressive portions of the below-grade concrete, chemical attack when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

(f)

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3 0-

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-

~ Startup Towers Circuit Breaker foundation, Electrical Enclosure)

'"oo Structure U1 Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-6 IILA3.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw. areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions index> 100 day-inch/yr) (NUREG-1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water-to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

z C The weathering index for the

0 continental US is shown in ASTM C33-m Gl 90, Fig1

0 (D

OAGI0000203_255

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

Gl AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker foundation, Electrical Enclosure)

0 Structure (D Aging Effect! Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-7 IILA3.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, loss not above- and of strength/ Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

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3 0-

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as 3 AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, 0-

~ Startup Towers Circuit Breaker foundation, Electrical Enclosure)

'"oo Structure U1 Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-8 IILA3.1-i Concrete: Reinforced Water - flowi ng Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundation concrete cracking, Erosion of cement from porous applicant's differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of porous NRC IN 97-11 NRC IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

IILA3-9 IILA3.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material scope of the above-grade (spalling, Accessi ble areas: applicant's exterior scaling)/ Inspections performed in accordance structures corrosion of with the Structures Monitoring Program monitoring embedded steel will indicate the presence of cracking, program z loss of bond, and loss of material C

0 (spalling, scaling) due to corrosion of m embedded steeL Gl

0 (D

OAGI0000203_257

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A3 Group 3 Structures (Auxiliary Bldg., Diesel Generator Bldg., Radwaste Bldg., Turbine Bldg., Switchgear Rm., Yard Structures such as m

Gl AFW Pumphouse, Utility/Piping Tunnels, Security/Lighting Poles, Manholes, Duct Banks; SBO Structures such as Transmission Towers, Startup Towers Circuit Breaker foundation, Electrical Enclosure)

0 Structure (D Aging Effect! Further

< Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA3-10 IILA3.1-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material Inspections performed in accordance structures (spalling, with Structures Monitoring Program will monitoring scaling)/ indicate the presence of increase in program aggressive porosity and permeability, cracking, or chemical attack loss of material (spalling, scaling) due to aggressive chemical attack.

IILA3-11 IILA3.3-a Masonry walls: Concrete Air - indoor Cracking due to Chapter XLS5, "Masonry Wall No block uncontrolled or restraint Program" (T-12) All air - outdoor shrinkage, creep, and aggressive environment IILA3-12 IILA3.2-a Steel Steel Air - indoor Loss of material/ Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitoring and maintenance.

(f)

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3 0-

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A4. GROUP 4 STRUCTURES (CONTAINMENT INTERNAL STRUCTURES, EXCLUDING REFUELING CANAL)

Systems, Structures, and Components This section addresses the elements of containment internal structures, excluding refueling canal. For this group, the applicable structural elements are identified: concrete and steel elements. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 111A4-1 NUREG-1801, Rev. 1 OAGI0000203_259

III STRUCTURES AND COMPONENT SUPPORTS z A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal)

C

0 m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component

0 IILA4-1 IILA4.1-c Concrete: Reinforced Air - indoor Reduction of Plant-specific aging management Yes, if (D

< concrete uncontrolled strength and program temperature (T-10) All modulus! limits are elevated For any concrete elements that exceed exceeded temperature specified temperature limits, further

(>150°F general; evaluations are warranted. Appendix A

>200°F local) of ACI 349-85 specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas which are allowed to have increased temperatures not to exceed 200T (f)

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA4-2 IILA4.1-b Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking due concrete was to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or AST M C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

z C

0 m

Gl

0 (D

OAGI0000203_261

III STRUCTURES AND COMPONENT SUPPORTS z A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal)

C

0 m

Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component

0 IILA4-3 IILA4.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not (D

< concrete uncontrolled or bond, and loss Program" within the (T-04) Interior and air - outdoor of material scope of the above-grade (spalling, Accessible areas: applicant's exterior scaling)! Inspections performed in accordance structures corrosion of with the Structures Monitoring Program monitoring em bedded steel will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steeL IILA4-4 IILA4.1-a Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material Inspections performed in accordance structures (spalling, with Structures Monitoring Program will monitoring scaling)! indicate the presence of increase in program aggressive porosity and permeability, cracking, or chemical attack loss of material (spalling, scaling) due to aggressive chemical attack.

IILA4-5 IILA4.2-a Steel Steel Air - indoor Loss of material! Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program (f) coating monitoring and maintenance.

(D Ll (0

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A4 Group 4 Structures (Containment Internal Structures, excluding Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA4-6 IILA4.2-b Steel Lubrite Air - indoor Lock-up! wear Chapter XLS3, "ASME Section XI, Yes, if not components: uncontrolled Subsection IWF" or within the (T-13) Chapter XLS6, "Structures Monitoring scope of Radial beam Program" Section XI, seats in IWFor BWR structures drywell; monitoring RPV support program shoes for PWRwith nozzle supports; Steam generator supports z

C

0 m

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0 (D

OAGI0000203_263

This Page Intentionally Left Blank NUREG-1801, Rev. 1 111A4-6 September 2005 OAGI0000203_264

A5. GROUP 5 STRUCTURES (FUEL STORAGE FACILITY, REFUELING CANAL)

Systems, Structures, and Components This section addresses the elements of the fuel storage facility and refueling canal. For this group, the applicable structural elements are identified: concrete, steel, and masonry walls. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIA5-1 NUREG-1801, Rev. 1 OAGI0000203_265

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA5-1 IILA51-j Concrete: Reinforced Air - indoor Reduction of Plant-specific aging management Yes, if concrete uncontrolled strength and program temperature (T-10) All modulus! limits are elevated For any concrete elements that exceed exceeded temperature specified temperature limits, further

(>150°F general; evaluations are warranted. Appendix A

>200°F local) of ACI 349-85 specifies the concrete temperature limits for normal operation or any other long-term period. The temperatures shall not exceed 150°F except for local areas which are allowed to have increased temperatures not to exceed 200°F.

(f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA5-2 IILA5.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

z C

0 m

Gl

0 (D

OAGI0000203_267

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA5-3 IILA5.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon (f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA5-4 IILA5.1-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material (spalling, environment i exterior; scaling)/ Accessible Areas: aggressive foundation corrosion of Inspections performed in accordance embedded steel with the Structures Monitoring Program will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive z

C groundwater/soil, and/or where the

0 concrete structural elements have m

Gl experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should

0 be implemented to manage the (D

concrete aging duri ng the period of extended operation.

OAGI0000203_269

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA5-5 IILA51-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material (spalling, minimum, consider scaling)/

aggressive (1) Examination of the exposed portions chemical attack of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_270

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA5-6 IILA5.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw. areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions index> 100 day-inch/yr) (NUREG-1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water-to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-z C 90, Fig1

0 m

Gl

0 (D

OAGI0000203_271

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA5-7 IILA5.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, loss not above- and of strength! Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

(f)

(D (D

3 0-

~

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(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA5-8 IILA5.1-i Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundatio concrete cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of porous NRC IN 97-11. NRC IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

IILA5-9 IILA5.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material (spalling, scope of the above-grade scaling)! Accessible areas: applicant's exterior corrosion of Inspections performed in accordance structures embedded steel with the Structures Monitoring Program monitoring will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of z embedded steeL C

0 m

Gl

0 (D

OAGI0000203_273

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A5 Group 5 Structures (Fuel Storage Facility, Refueling Canal) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA5-10 IILA5.1-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material (spalling, Inspections performed in accordance structures scaling)/ with Structures Monitoring Program will monitoring aggressive indicate the presence of increase in program chemical allack porosity and permeability, cracking, or loss of material (spalling, scaling) due to aggressive chemical allack.

IILA5-11 IILA5.3-a Masonry walls: Concrete Air - indoor Cracking due to Chapter XLS5, "Masonry Wall Program" No block uncontrolled or restraint (T-12) All air - outdoor shrinkage, creep, and aggressive environment IILA5-12 IILA5.2-a Steel Steel Air - indoor Loss of material/ Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitoring and maintenance.

IILA5-13 IILA5.2-b Steel Stainless Treated water Cracki ng/ stress Chapter XL M2, "Water Chemistry" and, No components: steel or treated corrosion (T-14) borated water cracking Monitoring of the spent fuel pool water Fuel pool Loss of level in accordance with technical (f)

(D liner material/pilling specifications and leakage from the (D

and crevice leak chase channels.

3 corrosion 0-

~

'"oo U1 OAGI0000203_274

A6. GROUP 6 STRUCTURES (WATER-CONTROL STRUCTURES)

Systems, Structures, and Components This section addresses the elements of water-control structures. For this group, the applicable structural elements are identified: concrete, steel, masonry walls, and earthen water-control structures. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIA6-1 NUREG-1801, Rev. 1 OAGI0000203_275

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and!or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< IIIA6-1 IIIA6.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XIS7, "Regulatory Guide Yes, plant-concrete uncontrolled or bond, and loss of 1.127, Inspection of Water-Control specific if (T-18) All air - outdoor material Structures Associated with Nuclear environment (spalling, Power Plants" or the FERC ! US Army is aggressive scaling)! Corp of Engineers dam inspections corrosion of and maintenance programs.

embedded steel Accessible areas:

As described in NUREG-1557, corrosion of exterior above-grade and interior embedded steel is not significant if the steel is not exposed to an aggressive environment (concrete pH <11.5 or chlorides >500 ppm) If such steel is exposed to an aggressive environment, corrosion is not significant if the concrete in which the steel is embedded has a low water-to-cement ratio (0.35-0.45), adequate air entrainment (3-6%), low permeability, and is designed in accordance with ACI 318-63 or ACI 349-85. Therefore, if these conditions are satisfied, aging management is not necessary.

Inaccessible areas:

For plants with non-aggressive ground (f) water!soil; i.e., pH > 5.5, chlorides <

(D 500 ppm, or su Ifates < 1500 ppm, as a (D minimum, consider (1) Examination of 3 the exposed portions of the below 0-

~ grade concrete, when excavated for any reason, and

'"oo U1 OAGI0000203_276

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and/or Aging Effect/ Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

z C

0 m

Gl

0 (D

OAGI0000203_277

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< IIIA6-2 IIIA6.1-c Concrete: Reinforced Any Cracking due to Chapter XIS7, "Regulatory Guide Yes, if concrete expansion/ 1.127, Inspection of Water-Control concrete was (T-17) All reaction with Structures Associated with Nuclear not aggregates Power Plants" or the FERC / US Army constructed Corp of Engineers dam inspections as stated for and maintenance programs. inaccessible areas Accessible Areas:

Inspections/evaluations performed in accordance with "Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" or the FERC / US Army Corp of Engineers dam inspections and maintenance programs will indicate the presence of expansion and cracking due to reaction with aggregates.

Inaccessible areas:

As described in NUREG-1557, investigations, tests, and petrographic examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially (f) reactive aggregates, aggregate-(D reinforced concrete reaction is not (D significant if the concrete was 3 constructed in accordance with ACI 0-

~ 201.2R Therefore, if these conditions are satisfied, aging management is not

'"oo necessary.

U1 OAGI0000203_278

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and/or Aging Effect/ Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IIIA6-3 IIIA6.1-e Concrete: Reinforced Ground Increase in Chapter XIS7, "Regulatory Guide Yes, plant-concrete water/soil porosity and 1.127, Inspection of Water-Control specific if (T-19) All permeability, Structures Associated with Nuclear environment cracking, loss of Power Plants" or the FERC / US Army is aggressive material Corp of Engineers dam inspections (spalling, and maintenance programs.

scaling)/

aggressive Accessible Areas:

chemical attack Inspections performed in accordance with "Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" or the FERC / US Army Corp of Engineers dam inspections and maintenance programs will indicate the presence of increase in porosity and permeability, cracking, or loss of material (spalling, scaling) due to aggressive chemical attack.

Inaccessible areas:

For plants with non-aggressive ground water/soil; i.e. pH > 5.5, chlorides <

500 ppm, or su Ifates < 1500 ppm, as a minimum, consider:

(1) Examination of the exposed z

C portions of the below grade concrete,

0 when excavated for any reason, and m

Gl (2) Periodic monitoring of below-grade water chemistry, including

0 consideration of potential seasonal (D

variations.

OAGI0000203_279

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

(f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_280

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and!or Aging Effect! Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA6-4 IILA6.1-f Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper monitoring functioning of the de-watering system program or a through the period of extended de-watering operation. system is relied upon z

C

0 m

Gl

0 (D

OAGI0000203_281

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< IIIA6-5 IIIA6.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XIS7, "Regulatory Guide Yes, for concrete (spalling, 1.127, Inspection of Water-Control inaccessible (T-15) Exterior above- scaling) and Structures Associated with Nuclear areas of and below- cracki ng/ freeze- Power Plants" or the FERC / US Army plants located grade; thaw Corp of Engineers dam inspections in moderate to foundation and maintenance programs. severe weathering Accessible Areas: conditions Inspections performed in accordance with Chapter XIS7, "Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" or the FERC / US Army Corp of Engineers dam inspections and maintenance programs will indicate the presence of loss of material (spalling, scaling) and cracking due to freeze-thaw Inaccessible Areas:

As described in NUREG-1557, freeze-thaw does not cause loss of material from rei nforced concrete in foundations, or in above- and below-grade exterior concrete, for plants located in a geographic region of negligible weathering conditions (f)

(weathering index <100 day-inch/yr)

(D Loss of material from such concrete is (D not significant at plants located in 3 areas in which weathering conditions 0-

~ are severe (weathering index >500 day-inch/yr) or moderate (100-500

'"oo dav-inch/vrl, provided that the concrete U1 OAGI0000203_282

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and!or Aging Effect! Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 mix design meets the air content (entrained air 3-6%) and water-to-cement ratio (035-045) specified in ACI 318-63 or ACI 349-85. Therefore, if these conditions are satisfied, aging management is not necessary.

The weathering index is defined in ASTM C33-90, Table 3, Footnote E.

Fig 1 of ASTM C33-90 illustrates the various weathering index regions throughout the US z

C

0 m

Gl

0 (D

OAGI0000203_283

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and/or Aging Effect/ Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< IIIA6-6 IIIA6.1-b Concrete: Reinforced Water- Increase in Chapter XIS7, "Regulatory Guide Yes, if concrete flowing porosity and 1.127, Inspection of Water-Control concrete was (T-16) Exterior above- permeability, Structures Associated with Nuclear not and below- loss of strength/ Power Plants" or the FERC / US Army constructed grade; leaching of Corp of Engineers dam inspections as stated for foundation; calcium and maintenance programs inaccessible interior slab hydroxide areas Accessible Areas:

Inspections performed in accordance with Chapter XIS7, "Regulatory Guide 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants" or the FERC / US Army Corp of Engineers dam inspections and maintenance programs will indicate the presence of increase in porosity and permeability, loss of strength/leaching of calcium hydroxide Inaccessible Areas:

As described in NUREG-1557, leaching of calcium hydroxide from reinforced concrete becomes significant only if the concrete is exposed to flowing water. Even if reinforced concrete is exposed to flowing water, such leaching is not (f) significant if the concrete is (D constructed to ensure that it is dense, (D well-cured, has low permeability, and 3 that cracking is well controlled.

0-

~ Cracking is controlled through proper arrangement and distribution of

'"oo reinforcinq bars. All of the above U1 OAGI0000203_284

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and!or Aging Effect! Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 characteristics are assured if the concrete was constructed with the guidance of ACI 201.2R-77. Therefore, if these conditions are satisfied, aging management is not necessary.

IILA6-7 IILA6.1-h Concrete: Reinforced Water- Loss of material! Chapter XLS7, "Regulatory Guide No concrete flowing abrasion; 1.127, Inspection of Water-Control (T-20) Exterior above- cavitation Structures Associated with Nuclear and below- Power Plants" or the FERC ! US Army grade; Corp of Engineers dam inspections foundation; and maintenance programs.

interior slab IILA6-8 IILA61-g Concrete: Reinforced Water- Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; flowing under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundation concrete cracking, Erosion of cement from porous applicant's differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of NRC IN 97-11 NRC IN 98-26 program or a porous concrete proposes Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of z erosion of cement from porous C

0 concrete subfoundations, the licensee m is to ensure proper functioning of the Gl de-watering system through the period of extended operation.

0 (D

OAGI0000203_285

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A6 Group 6 Structures (Water-Control Structures) m Gl Structure and!or Aging Effect! Further Item Link Material Environment Aging Management Program (AMP)

Component Mechanism Evaluation

0 (D

< IILA6-9 IILA6.4-a Earthen water- Various Water- Loss of material, Chapter XLS7, "Regulatory Guide No control flowing loss of form! 1.127, Inspection of Water-Control (T-22) structures: Water- erosion, Structures Associated with Nuclear standing settlement, Power Plants" or the FERC ! US Army Dams, sedimentation, Corp of Engineers dam inspections Embankments, frost action, and maintenance programs.

Reservoirs, waves, currents, Channels, su rface ru noff, Canals and seepage ponds IILA6-10 IILA6.3-a Masonry walls: Concrete Air - indoor Cracking due to Chapter XLS5, "Masonry Wall No block uncontrolled or restraint Program" (T-12) All air - outdoor shrinkage, creep, and aggressive environment IILA6-11 IILA6.2-a Metal Steel; Air - indoor Loss of material! Chapter XLS7, "Regulatory Guide No components: copper uncontrolled or general (steel 1.127, Inspection of Water-Control (T-21) alloys air - outdoor; only), pitting and Structures Associated with Nuclear All structu ral Water- crevice corrosion Power Plants" or the FERC ! US Army members flowing or Corp of Engineers dam inspections water- and maintenance programs.

standing If protective coatings are relied upon to manage the effects of aging, this AMP is to include provisions to address (f) protective coating monitoring and (D

maintenance.

(D 3

0-

~

'"oo U1 OAGI0000203_286

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A6 Group 6 Structures (Water-Control Structures) 3 0-

~

Structure and!or Aging Effect! Further

'"oo Item Link Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA6-12 IILA6. Seals, gaskets, Elastomers Various Loss of sealing! Chapter XLS6, "Structures Monitoring No and moisture such as deterioration of Program" (TP-7) barriers EPDM seals, gaskets, (caulking, rubber and moisture flashing, and barriers other sealants) (caulking, flashing, and other sealants) z C

0 m

Gl

0 (D

OAGI0000203_287

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III A6-14 September 2005 OAGI0000203_288

A7. GROUP 7 STRUCTURES (CONCRETE TANKS AND MISSILE BARRIERS)

Systems, Structures, and Components This section addresses the elements of concrete tanks and missile barriers. For this group, the applicable structural elements are identified: concrete and steel. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 III A7-1 NUREG-1801, Rev. 1 OAGI0000203_289

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A7 Group 7 Structures (Concrete Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA7-1 IILA7.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations pe rformed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

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A7 Group 7 Structures (Concrete Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA7-2 IILA7.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon z

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0 m

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OAGI0000203_291

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A7 Group 7 Structures (Concrete Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA7-3 IILA7.1-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material (spalling, environment i exterior; scaling)/ Accessible Areas: aggressive foundation corrosion of Inspections performed in accordance embedded steel with the Structures Monitoring Program will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the (f) concrete structural elements have (D experienced degradation, a plant (D specific AMP accounting for the extent 3 of the degradation expenenced should 0-

~ be implemented to manage the concrete aging during the period of

'"oo extended operation.

U1 OAGI0000203_292

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A7 Group 7 Structures (Concrete Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA7-4 IILA71-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material (spalling, minimum, consider scaling)/

aggressive (1) Examination of the exposed portions chemical attack of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

z C

0 m

Gl

0 (D

OAGI0000203_293

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A7 Group 7 Structures (Concrete Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA7-5 IILA7.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw. areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions index> 100 day-inch/yr) (NUREG-1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water-to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig1 (f)

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A7 Group 7 Structures (Concrete Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA7-6 IILA7.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, loss not above- and of strength! Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

z C

0 m

Gl

0 (D

OAGI0000203_295

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A7 Group 7 Structures (Concrete Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA7-7 IILA7.1-i Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundatio concrete cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment basemats is described in monitoring erosion of porous NRC IN 97-11. NRC IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

IILA7-8 IILA7.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material (spalling, scope of the above-grade scaling)! Accessible areas: applicant's exterior corrosion of Inspections performed in accordance structures embedded steel with the Structures Monitoring Program monitoring will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steeL (f)

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A7 Group 7 Structures (Concrete Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA7-9 IILA7.1-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material (spalling, Inspections performed in accordance structures scaling)/ with Structures Monitoring Program will monitoring aggressive indicate the presence of increase in program chemical allack porosity and permeability, cracking, or loss of material (spalling, scaling) due to aggressive chemical allack.

IILA7-10 IILA7.2-a Steel Steel Air - indoor Loss of material/ Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitori ng and maintenance.

IILA7-11 IILA7.2-b Steel Stainless Water- Cracki ng/ stress A plant-specific aging management Yes, plant-components: steel standing corrosion program is to be evaluated. specific (T-23) cracking Tank liner Loss of material/pilling and crevice corrosion z

C

0 m

Gl

0 (D

OAGI0000203_297

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III A7-10 September 2005 OAGI0000203_298

A8. GROUP 8 STRUCTURES (STEEL TANKS AND MISSILE BARRIERS)

Systems, Structures, and Components This section addresses the elements of steel tanks and missile barriers. For this group, the applicable structural elements are identified: concrete and steel. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIAS-1 NUREG-1S01, Rev. 1 OAGI0000203_299

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A8 Group 8 Structures (Steel Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA8-1 IILA8.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

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3 0-

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

AS Group S Structures (Steel Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILAS-2 IILAS.1-f Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-OS) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon z

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0 m

Gl

0 (D

OAGI0000203_301

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A8 Group 8 Structures (Steel Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA8-3 IILA8.1-d Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material (spalling, environment i exterior; scaling)/ Accessible Areas: aggressive foundation corrosion of Inspections performed in accordance embedded steel with the Structures Monitoring Program will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the (f) concrete structural elements have (D experienced degradation, a plant (D specific AMP accounting for the extent 3 of the degradation experienced should 0-

~ be implemented to manage the concrete aging during the period of

'"oo extended operation.

U1 OAGI0000203_302

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A8 Group 8 Structures (Steel Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA8-4 IILA8.1-e Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material (spalling, minimum, consider scaling)/

aggressive (1) Examination of the exposed portions chemical attack of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

z C

0 m

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0 (D

OAGI0000203_303

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A8 Group 8 Structures (Steel Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILA8-5 IILA8.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking/ scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw. areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions index> 100 day-inch/yr) (NUREG-1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water-to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig1 (f)

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3 0-

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A8 Group 8 Structures (Steel Tanks and Missile Barriers) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA8-6 IILA8.1-b Concrete: Reinforced Water - flowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, loss not above- and of strength! Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

z C

0 m

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z III STRUCTURES AND COMPONENT SUPPORTS C

0 AS Group S Structures (Steel Tanks and Missile Barriers) m Gl Structure Aging Effect! Further Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation

0 Component (D

< IILAS-7 IILAS1-g Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundatio concrete cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures selliement! containment basemats is described in monitoring erosion of porous NRC IN 97-11. NRC IN 9S-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-watering system through the period of extended operation.

III.AS-S IILAS.2-a Steel Steel Air - indoor Loss of material/ Chapter XLS6, "Structures Monitoring Yes, if not components: uncontrolled or corrosion Program" within the (T-11) air - outdoor scope of the All structural If protective coatings are relied upon to applicant's steel manage the effects of aging, the structures structures monitoring program is to monitoring include provisions to address protective program coating monitoring and maintenance.

IILAS-9 IILAS.2-b Steel Stainless Water- Cracki ng/ stress A plant-specific aging management Yes, plant-components: steel standing corrosion program is to be evaluated. specific (T-23) cracking (f)

(D Tank liner Loss of (D

material/pilling 3 and crevice 0-

~

corrosion

'"oo U1 OAGI0000203_306

A9. GROUP 9 STRUCTURES (8WR UNIT VENT STACK)

Systems, Structures, and Components This section addresses the elements of the boiling water reactor (8WR) unit vent stack. For this group, the applicable structural element is identified: concrete. The aging management review is presented for each applicable combination of structural element and aging effect.

System Interfaces Physical interfaces exist with any system or component that either penetrates the structure wall or is supported by the structure wall, floor, and roof. The direct interface is through the system or component supports that are anchored to the structure. Structures also protect housed systems and components from internal and external design basis events. In the case of tanks, there is a functional interface with the associated system. Water-control structures are integral parts of the systems that provide plant cooling water and residual heat removal.

September 2005 IIIA9-1 NUREG-1801, Rev. 1 OAGI0000203_307

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A9 Group 9 Structures (BWR Unit Vent Stack) m Gl Structure OJ Aging Effect/ Further o Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA9-1 IILA9.1-c Concrete: Reinforced Any Cracking due to Chapter XLS6, "Structures Monitoring Yes, if not concrete expansion/ Program" within the (T-03) All reaction with scope of the aggregates Accessible Areas: applicant's Inspections/evaluations performed in structures accordance with the Structures monitoring Monitoring Program will indicate the program or presence of expansion and cracking concrete was due to reaction with aggregates. not constructed as Inaccessible Areas: stated for As described in NUREG-1557, inaccessible investigations, tests, and petrographic areas.

examinations of aggregates performed in accordance with ASTM C295-54 or ASTM C227-50 can demonstrate that those aggregates do not react within reinforced concrete. For potentially reactive aggregates, aggregate-reinforced concrete reaction is not significant if the concrete was constructed in accordance with ACI 201.2R. Therefore, if these conditions are satisfied, aging management is not necessary.

(f)

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3 0-

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(D III STRUCTURES AND COMPONENT SUPPORTS (D

A9 Group 9 Structures (BWR Unit Vent Stack) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA9-2 IILA9.1-h Concrete: Reinforced Soil Cracks and Chapter XLS6, "Structures Monitoring Yes, if not concrete distortion due to Program" within the (T-08) All increased stress scope of the levels from If a de-watering system is relied upon applicant's settlement for control of settlement, then the structures licensee is to ensure proper functioning monitoring of the de-watering system through the program or a period of extended operation. de-watering system is relied upon z

C

0 m

Gl

0 (D

OAGI0000203_309

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A9 Group 9 Structures (BWR Unit Vent Stack) m Gl Structure OJ Aging Effect/ Further o Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA9-3 IILA9.1-e Concrete: Reinforced Ground Cracking, loss of Chapter XLS6, "Structures Monitorin g Yes, plant-concrete water/soil bond, and loss of Program" specific if (T-05) Below-grade material environment i exterior; (spalling, Accessible Areas: aggressive foundation scaling)/ Inspections performed in accordance corrosion of with the Structures Monitoring Program embedded steel will indicate the cracking, loss of bond, or loss of material (spalling, scaling) due to corrosion of embedded steeL Inaccessible Areas:

For plants with non-aggressive ground water/soil; i.e., pH > 5.5, chlorides <

500 ppm, or sulfates <1500 ppm, as a minimum, consider (1) Examination of the exposed portions of the below-grade concrete, when excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have (f) experienced degradation, a plant (D

specific AMP accounting for the extent (D of the degradation experienced should 3 be implemented to manage the 0-

~ concrete aging during the period of

'"oo extended operation.

U1 OAGI0000203_310

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A9 Group 9 Structures (BWR Unit Vent Stack) 3 0-

~ Structure Aging Effect/ Further

'"oo Item Link and/or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA9-4 IILA91-g Concrete: Reinforced Ground Increase in Inaccessible Areas: Yes, plant-concrete water/soil porosity and For plants with non-aggressive ground specific if (T-07) Below-grade permeability, water/soil; i.e., pH > 5.5, chlorides < environment i exterior; cracking, loss of 500 ppm, or sulfates <1500 ppm, as a aggressive foundation material minimum, consider (spalling, scaling)/ (1) Examination of the exposed portions aggressive of the below-grade concrete, when chemical attack excavated for any reason, and (2) Periodic monitoring of below-grade water chemistry, including consideration of potential seasonal variations.

For plants with aggressive groundwater/soil, and/or where the concrete structural elements have experienced degradation, a plant specific AMP accounting for the extent of the degradation experienced should be implemented to manage the concrete aging during the period of extended operation.

z C

0 m

Gl

0 (D

OAGI0000203_311

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A9 Group 9 Structures (BWR Unit Vent Stack) m Gl Structure OJ Aging Effect/ Further o Item Link and/or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA9-5 IILA9.1-a Concrete: Reinforced Air - outdoor Loss of material Chapter XLS6, "Structures Monitoring Yes, if not concrete (spalling, scaling) Program" within the (T-01) Exterior and cracking! scope of the above- and freeze-thaw Accessible Areas: applicant's below-grade; Inspections performed in accordance structures foundation with the Structures Monitoring Program monitoring will indicate the presence of loss of program or for material (spalling, scaling) and cracking inaccessible due to freeze-thaw areas of plants located Inaccessible Areas: in moderate to Evaluation is needed for plants that are severe located in moderate to severe weathering weathering conditions (weathering conditions

>> index> 100 day-inch/yr) (NUREG-

'P OJ 1557). Documented evidence to confirm that existing concrete has air content of 3% to 6% and water -to-cement ratio of 0.35-0.45, and subsequent inspections did not exhibit degradation related to freeze-thaw, should be considered a part of the evaluation.

The weathering index for the continental US is shown in ASTM C33-90, Fig1 (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_312

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A9 Group 9 Structures (BWR Unit Vent Stack) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA9-6 IILA9.1-b Concrete: Reinforced Water - ftowing Increase in Chapter XLS6, "Structures Monitoring Yes, if concrete porosity and Program" concrete was (T-02) Exterior permeability, los, not above- and of strength! Accessible areas: constructed as below-grade; leaching of Inspections performed in accordance stated for foundation calcium with the Structures Monitoring Program inaccessible hydroxide will indicate the presence of increase in areas porosity, and permeability due to leaching of calcium hydroxide.

Inaccessible Areas:

An aging management program is not necessary, even if reinforced concrete is exposed to flowing water, if there is documented evidence that confirms the in-place concrete was constructed in accordance with the recommendations in ACI 201.2R-77.

z C

0 m

Gl

0 (D

OAGI0000203_313

z III STRUCTURES AND COMPONENT SUPPORTS C

0 A9 Group 9 Structures (BWR Unit Vent Stack) m Gl Structure OJ Aging Effect! Further o Item Link and!or Material Environment Aging Management Program (AMP)

Mechanism Evaluation Component IILA9-7 IILA9.1-i Concrete: Reinforced Water - flowing Reduction in Chapter XLS6, "Structures Monitoring Yes, if not concrete; under foundation Program" within the (T-09) Foundation; Porous foundation strength, scope of the subfoundatio concrete cracking, Erosion of cement from porous applicant's n differential concrete subfoundations beneath structures settlement! containment base mats is described in monitoring erosion of porous NRC IN 97-11. NRC IN 98-26 proposes program or a concrete Maintenance Rule Structures de-watering subfoundation Monitoring for managing this aging system is effect, if applicable. If a de-watering relied upon system is relied upon for control of erosion of cement from porous concrete subfoundations, the licensee is to ensure proper functioning of the de-

>> watering system through the period of

'P OJ extended operation.

IILA9-8 IILA9.1-d Concrete: Reinforced Air - indoor Cracking, loss of Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or bond, and loss of Program" within the (T-04) Interior and air - outdoor material scope of the above-grade (spalling, Accessible areas: applicant's exterior scaling)! Inspections performed in accordance structures corrosion of with the Structures Monitoring Program monitoring embedded steel will indicate the presence of cracking, program loss of bond, and loss of material (spalling, scaling) due to corrosion of embedded steeL (f)

(D (D

3 0-

~

'"oo U1 OAGI0000203_314

(f)

(D III STRUCTURES AND COMPONENT SUPPORTS (D

A9 Group 9 Structures (BWR Unit Vent Stack) 3 0-

~ Structure Aging Effect! Further

'"oo Item Link and!or Component Material Environment Mechanism Aging Management Program (AMP)

Evaluation U1 IILA9-9 IILA9.1-f Concrete: Reinforced Air - indoor Increase in Chapter XLS6, "Structures Monitoring Yes, if not concrete uncontrolled or porosity and Program" within the (T-06) Interior and air - outdoor permeability, scope of the above-grade cracking, loss of Accessible Areas: applicant's exterior material Inspections performed in accordance structures (spalling, with Structures Monitoring Program will monitoring scaling)! indicate the presence of increase in program aggressive porosity and permeability, cracking, or chemical attack loss of material (spalling, scaling) due to aggressive chemical attack.

z C

0 m

Gl

0 (D

OAGI0000203_315

This Page Intentionally Left Blank NUREG-1801, Rev. 1 III A9-10 September 2005 OAGI0000203_316

111.8 COMPONENT SUPPORTS

81. Supports for ASME Piping and Components

82. Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components

83. Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation

84. Supports for Emergency Diesel Generator (EDG), HVAC System Components, and Other Miscellaneous Mechanical Equipment

85. Supports for Platforms, Pipe Whip Restraints, Jet Impingement Shields, Masonry Walls, and Other Miscellaneous Structures September 2005 III B-i NUREG-1801, Rev. 1 OAGI0000203_317

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81. SUPPORTS FOR ASME PIPING AND COMPONENTS 81.1 Class 1 81.2 Class 2 and 3 81.3 Class MC (8WR Containment Supports)

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81. SUPPORTS FOR ASME PIPING AND COMPONENTS Systems, Structures, and Components This section addresses supports and anchorage for ASME piping systems and components. It is subdivided into Class 1 (111.81.1), Class 2 and 3 (111.81.2), and Class MC (111.81.3). Applicable aging effects are identified and the aging management review is presented for each applicable combination of support component and aging effect.

System Interfaces Physical interfaces exist with the structure, system, or component being supported and with the building structural element to which the support is anchored. A primary function of supports is to provide anchorage of the supported element for internal and external design basis events, so that the supported element can perform its intended function.

September 2005 III B1-3 NUREG-1801, Rev. 1 OAGI0000203_321

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