page i of 77 - nrc.gov · engineering report no.-entergy a2-me-2003-001-1 rev. i page i of 77...

Engineering Report No.

-Entergy

A2-ME-2003-001-1 Rev. IPage I of 77

ENTERGY NUCLEAR SOUTHEngineering Report Coversheet

Engineering Report Title:

Aging Management Review of Nonsafety-related Systems and Components AffectingSafety-related Systems

Engineering Report Type:

New E Revision Z Deleted El Superceded 0

Applicable Site(s)

ANO 0 Echelon El GGNS I E RBS [E WF3 0

I.\Report Origin: ED

ElENS

VendorSafety-Related: El Yes

0E No

(6) Vendor Document No.w;rv

-r orI .-

Prepared by:

Verified/Reviewed by.

Approved by:

Stan N. Batch v /4sResponsible Engineer

Ted S. IVYDesi VerifiedrReviewer

21- a~

Date: I) 17/4!

Date: 1f/z,4

Date: /ii4@

Comments:El YesEl No

O YesED No

El YesO1 No

Attached:El YesO No

El YesZ No

El YesO NoResponsible Supervisor or

Responsible Central Engineering Manager(for multiple site reports only)

-... . ,,, t- -L., *. S -.t. -. - , , , , . ,- - . - ...... . . . . . ... .. ..... .. ... . . ... I..

!

ARKANSAS NUCLEAR ONE Pe LE-DOC TITLE: E-DOC NO. CHANGE NO.

CONFIGURATION CHECKLIST 5010.004-A 006.00-0

This Document Contains I Page(s)A2-ME-2003-001 -1

[ ~Note:The Configuration Checklist rnay rot be used Instead of a 50.59 Review when a 50.59 Review Is required by NMM U-101 orother governing procedures related to the affected documents.

Complete this form In accordance with the Instructions provided in Procedure 5010.004, Attachment 3. For additional Information,follow the "Configuration Checklisr link provided on EntergyNErs ANO Engineering home page.

AFFECTED? 'UCENSING DISPOSITION or BASIS FOR CONCLUSION0Yes' 0No2 Any of the followin This aging management review report has no Impact on

* Technical Specifications any current licensing basis documents, SER's, VSC,.Operating License QAPM or E plan. It documents the evaluation of aging

affects on components and the programs necessary to* Confirmatory Orders manage them for the period of extended operation If* Safety Analysis Report / SAR Figures granted by the NRC. No LRS seach is required since* Core Operating Umits Report the renewed license and amendment to the SAR that

, Fire Hazards Analysis documents this evaluation has yet to be approved.

* Tech Spec Bases* Technical Requirements Manual* NRC Safety Evaluation Reports* Ventilated Storage Cask Licensing

Documents* Quality Assurance Program Manual* Emergency Plan

'if 'Yes," a 10CFR50.59 Determination is required In accordance with NMM LIl101.aIf 'No:' the basis for this conclusion must be documented (e.g., LRS search criteria, LBD sectionstfigures reviewed, etc.)AFFECTED? DESIGNIOTHER *DISPOSITION (If applicable)OYes ZNo DrawingsIDRNs/DTS Database0Yes ZNo Component Database

]Yes MNo VendorTech Manuals /VTM DatabaseOYes O No Upper Level Documents (ULDs)OYes Z No Calculations / Code Stress Reports __X

EjYes 0 No Specifications]Yes 0No Engineering Reports

OYes 0No EQ DocumentationOYes ZNo Piping Class SummaryD3Yes gNo Fire Barrier Penetration Log

DYes (0No Cable, Raceway or Equipment Numbers (PDMS)[Yes S No ER Responses I Mods (in-progress only)

]Yes 0 No ProceduresDYes | No Engineering Standards

[Yes ZNo Component Labels[:]Yes 0No Fuse ListsOYes SNo Repetitive Task DatabaseOYes S No Preventive Maintenance Engineering Evaluations

and TasksOYes N No SimulatorOYes ZNo Training I System Training Manuals (STMs)DYes O No MMISOYes SNo Engineering ProgramsOYes ZNo Lubrication Manual

Completed By: Ted S. IvyW Date: 1117/03-

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. . . .

. . .-. - - .- -- * . II

Engineering Report No.

- lEntergy

A2-ME-2003-001-0 Rev. 0Page 1 of 77

ENTERGY NUCLEAR SOUTHEngineering Report Coversheet

Engineering Report Title:

Aging Management Review of Nonsafety-related Systems and Components AffectingSafety-related Systems

Engineering Report Type:

New 9 Revision n Deleted El Superceded E

Applicable Site(s)

ANO 9 Echelon El GGNS rl RBS El WF3 0l

Report Origin: 9DEl

ENSVendor

Safety-Related: El YesED No

(6) Vendor Document No.

Prepared by

Verified/Reviewed by.

Approved by:

Stan N. Batch S,49Responsible Engineer

Ted S. Ivy °

* Date: 7L4L3

Date: 7A/c3

Date::

Comments:El Yes9 No

90 YesE No

El YesZ No

Attached:El YesZ No

ED YesEl No

El Yes0 No

t.

DesiMVerifier/Reviewer

Responsible Supervisor oFResponsible Central Engineering Manager

(for multiple site revorts onlv)

Arkansas Nuclear One Unit 2License Renewal Project

CALC- A2-ME-2003-001-1 I

A:ing Manageg ent Review ofNonsafetv-relatedSvstems and Components

Affectiniz Safety-related Svstems

Revision 1

ANO-2 License Renewal ProjectAging Management Review of Nonsafety-related Systems and

Components Affecting Safety-related Systems

l

Engineering ReportA2-ME-2003-001-1

Revision IPage 3 of 77

Table of Contents

1.0

2.0

3.0

Introduction ......................................... . . . 71.1 Purpose .......................................... 7

1.2 Industry/NRC Guidance on 10 CFR 54.4(a)(2) Scope ..................................... . 8

Evaluation Criteria.......................................................................................................112.1 Mechanical Systems and Components that Meet the 54.4(a)(2)

Criteria for Leakage or Spray . ................................. 1

2.2 Mechanical Systems and Components that Meet the 54.4(a)(2)Criteria for Reasons Other than Leakage or Spray . . ...................... 12

Individual System Review........................................................................................143.1 Alternate AC Generator (AAC) . . ............................... 14

3.2 Auxiliary Building Heating and Ventilation (ABHV) . ...................................... 14

3.3 Auxiliary Building Sump (ABS) . ...................................... . 15

3.4 Chilled Water (AC) ......................................... 16

3.5 Auxiliary Cooling Water (ACW).............................................................................17

3.6 Admin. Building Heating and Ventilation (ADHV) . . ..................... 17

3.7 Auxiliary Steam (AS) ...................................... .. 17

3.8 Breathing Air (BA) ...................................... .. 18

3.9 Startup and Blowdown Demineralizers (BD) . . ........................ 18

3.10 Boron Management (BMS) ........................................ 19

3.11 Containment Spray (BS) ........................................ 19

3.12 Chemical Addition (CA) ......................................... 20

3.13 Component Cooling Water (CCW) . . .............................. 20

3.14 Control Element Drive Mechanisms (CEDM) . . ........................ 21

3.15 Carbon Dioxide (CO2/CRDX) . . ................................ 22

3.16 Containment Penetration Room Ventilation (CPV) . ..................................... . 22

3.17 Control Room Ventilation (CRV) . ...................................... . 22

3.18 Condensate (CS) ...................................... 22

3.19 Condensate Storage and Transfer (CT)...................................................................22

3.20 Chemical and Volume Control (CVCS) . . ........................... 23

3.21 Containment Vent Header (CVH) . . ............................ 24

3.22 Circulating Water (CW) .............................. .. 24

3.23 Drain Collection Header (DCH) . . ............................ 24

ANO-2 License Renewal Project A2-MEn200rgo1-1Aging Management Review of Nonsafety-related Systems and Re.is3on 1

Components Affecting Safety-related Systems Revis4of 7Page 4 of 77

3.24 Dry Fuel Storage (DFS) ................................ 25

3.25 Domestic Water (DW) ................................ 25

3.26 Diesel Fuel Services (ED) ............................... 25

3.27 Emergency Diesel Generator (EDG) ............................... 26

3.28 Emergency Feedwater (EFW) ............................... 26

3.29 Electro-Hydraulic Control System (EHC) ................................ 27

3.30 Extraction Steam (EX) ................................ . 27

3.31 Emergency Operations Facility ............................... 27

3.32 Fuel Handling (FH and FHS) ............................... 27

3.33 Fuel Oil (FO) ............................... 28

3.34 Fuel Pool Cooling and Purification (FP) ................................ 28

3.35 Fire Protection (Water) (FS) ............................. 28

3.36 Feedwater (EW) .............................. 29

3.37 Gas Collection Header (GCH)..................................................................................29

3.38 Generator Gas (GG) ............................. 30

3.39 Gland Steam / Exhaust Steam (GS) ............................. 30

3.40 Generator Seal Oil (GSO) ............................. 30

3.41 Gaseous Radwaste (GZ) ............................. 30

3.42 Hydrogen Supply (Generator) (112) ............................. 30

3.43 Halon System (HAL) .............................. ; 30

3.44 HeaterDrains (HD) .............................. 30

3.45 HydrogenPurge(HPA) ............................. 31

3.46 High Pressure Safety Injection (EPSI) ............................. 31

3.47 Isophase Bus Cooling ............................. 31

3.48 Instrument Air (IA) ............................. 31

3.49 Intake Structure (IS) ............................. 32

3.50 Low Level Radwaste Building ............................. 32

3.51 Lube Oil (LO) ............................. 32

3.52 Low Pressure Safety Injection (LPSI) ............................. 32

3.53 Low Level Radwaste Building Ventilation (LRBV).................................................32

3.54 Liquid Radwaste Management (LRW) ....................................... 33

3.55 Main Steam (MS)......................................................................................................333.56 Nitrogen Supply (N2) ...................................... 34

3.57 Neutralizing Tank (NT) ...................................... 34

I

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and Revision 1

Components Affecting Safety-related Systems Page 5 of 77I

3.58 Reactor Building Purge Air (PA) ......................... 34

3.59 Post Accident Sampling System (PASS) .35

3.60 Plant Heating (PH) .35

3.61 Plant Makeup (PMU) .36

3.62 Prinmary Sampling (PS) .36

3.63 Reactor Building (RB) .37

3.64 Reactor Building Heating and Ventilation (RBHV) . .37

3.65 Reactor Coolant Pump System (RCP) .38

3.66 Reactor Coolant System (RCS) .. 383.67 Radiation Monitoring System (RMS) .. 39

3.68 Reheat Steam (RS) .39

3.69 Resin Transfer (RT) .. 40

3.70 Radwaste Building (RWB) .. 403.71 Reactor Core System (R.X ...... A0

3.72 Regenerative Waste (R) .. 40

3.73 Service Air (SA) .413.74 Shutdown Cooling (SDC) .. 41

3.75 Security System (SEC) .42

3.76 Spent Fuel Pool (SFP) .. 42

3.77 Steam Generator Secondary/Blowdown (SGS) . .42

3.78 Sampling System (SS) .43

3.79 Sewage Treatment Plant (ST) .433.80 Startup Boiler (SU) .. 433.81 Service Water (SW) .44

3.82 Generator Stator Cooling (SWC). 44

3.83 Spent Resin (SZ) .44

3.84 Turbine Building Sump (TBS) .45

3.85 Turbine Building Ventilation (TBV) .45

3.86 Turbine Generator (TG) .463.87 Traveling Screen Wash (TS) .......................... 46

3.88 Ventilation System (VENT) .463.89 Condenser Vacuum System (VS) .46

3.90 Bolting .......................... 46



4.0 Demonstration that Aging Effects Are Managed.4.1 Water Chemistry Control Program ..................

4.2 Boric Acid Corrosion Prevention Program......

4.3 System Walkdown Program............................

4.4 Flow Accelerated Corrosion Program..............

4.5 Bolting and Torquing Activities ......................

4.6 Metal Fatigue TLAA........................................

5.0 Summary and Conclusions....................................

I............ ................ 48AO

.......................................................... 49AO I

I............................. T., I

I.............................. JV

. ...................... V........

. .................................. -X . J

................... ...- ,.,...-.-.......... 5152O.X Reters

Attachments1.2.3.4.

nces ........................................................................................................................

ISystem Scoping Results ....................... 53Aging Management Review Results..................................................56Review Logic Flowchart................................................................76Walkdown Summaries .............. 77

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-NE-2003-001-1

Components Affecting Safety-related Systems Page 7 of 77

1.0 Introduction

1.1 Purnose

This report is part of the aging management review for the integrated plant assessment performedto extend the operating license of Arkansas Nuclear One Unit 2 (ANO-2). This report addressesnonsafety-related systems or components (SCs) whose failure could prevent satisfactoryaccomplishment of a safety function due to their proximity. The concern is that age-relateddegradation of nonsafety-related SCs could adversely impact safety-related SCs through spatialinteraction. This encompasses seismic KI/I high energy, and moderatellow energy pipingsystems. The report demonstrates the effects of aging on nonsafety-related passive mechanicalcomponents are adequately managed so that the intended functions of safety-related SCs can bemaintained consistent with the current licensing basis as required by 10 CER 54.21(a)(3).Nonsafety-related structures that could adversely impact safety-related equipment were evaluatedin the structural aging management review reports and will not be discussed in this report. Foradditional information on the license renewal project overall scope and documentation, refer toengineering report LRPG-01, License Renewal Project Plan. (Ref. 2, 20)

The purpose of this engineering report is to demonstrate that the aging effects for passivemechanical components in nonsafety-related systems or nonsafety-related portions of safety-related systems (meeting scoping criterion 54.4(a)(2)) can be adequately managed for the periodof extended operation associated with license renewal. Section 2 reviews the 54.4(a)(2) criteriaand establishes a logic flowchart (Attachment 3) for the review of systems. Section 3 thencompletes the 54.4(a)(2) flowchart process for each mechanical system at ANO-2. For systemsthat contain components meeting the 54.4(a)(2) criteria, the aging effects requiring managementare identified. Section 4.0 then evaluates if existing programs and commitments adequatelymanage those effects identified in Section 3. The demonstration process is complete for thecomponent under review when either:

* The evaluation of existing programs demonstrates the aging effects requiring managementare adequately managed so that the intended function(s) are maintained consistent with thecurrent licensing bases for the period of extended operation, or;

* Action(s) are proposed to augment existing or create new programs to manage the identifiedeffects of aging.

Applicable aging effects were determined using EPRI report 1003056 Non-Class 1 MechanicalImplementation Guideline and Mechanical Tools, Revision 3. The EPRI report provides thegeneric bases for the identification of aging effects based on specific materials and environmentsand documents the confirmation of the validity of the aging effects through review of industryexperience. This aging management review report, in conjunction with EPRI report 1003056,documents the identification and evaluation of aging effects requiring management for thecomponents. (Ref. 1)

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2- 20034001-1

Components Affecting Safety-related Systems Revision 1

1.2 Industry/NRC Guidance on 10 CFR 54.4(a)(2) Scope

On March 15, 2002 the Nuclear Regulatory Commission (NRC) issued a letter to the NuclearEnergy Institute (NEI) (Reference 23) providing "Guidance on the Identification and Treatmentof Structures, Systems, and Components which Meet 10 CPR 54.4(a)(2)". In this letter the NRCdistinguished between two specific situations where nonsafety-related SSCs could affect thefunctions of safety-related SSCs. In the first situation, nonsafety-related SSCs are directlyconnected to safety-related SSCs (typicallypiping). (In this case, the scope of license renewalincludes the nonsafety-related piping and supports up to and including the first seismic anchorbeyond the safety/nonsafety interface.) In the second situation, nonsafety-related SSCs are notdirectly connected to safety-related SSCs but have the potential for spatial interaction. Therefore,nonsafety-related SSCs should be included in the scope of license renewal if, based onengineering judgment and operating experience, their failure has the potential to prevent theaccomplishment of a safety function performed by safety-related SSCs. For such SSCs that arenot directly connected to safety-related SSCs, the impact is the result of the spatial interactionbetween the SSCs.

Based on the license renewal rule and the guidance in Reference 23, components meeting thescoping criterion of 54.4(a)(2) will fall into the following areas.

1) Nonsafety-related (NSR) SSCs directly connected to safety-related (SR) SSCs(typically piping systems).2) NSR SSCs that are directly or not directly connected to SR SSCs but have thepotential for spatial interaction.

The following sections address the different modes of spatial interaction. Those interactions canoccur in the following forms:

• physical impact such as in a seismic event (Seismic f/1),• pipe whip, jet impingement, orharsh environmentresulting from a piping rupture, or* damage due to leakage or spray from nonsafety-related SSCs

Protective features (whip restraints, spray shields, supports, barriers, etc.) may be installed toprotect safety-related SSCs against spatial interaction with nonsafety-related SSCs. Suchprotective features credited in the plant design are included within the scope of license renewaland are subject to aging management review. Where those protective features provide adequateprotection, the nonsafety-related system itself is excluded from the scope of license renewal.These protective features are typically associated with a structure and are addressed in thestructural aging management reviews.

Physical Impact

This category concerns the potential spatial interaction of nonsafety-related SSCs fallingon or otherwise physically impacting safety-related SSCs such that safety functions maynot be accomplished.

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and -IEi20o 1-

Components Affecting Safety-related Systems PRe 9 of 77

All NSR supports for non-seismic or seismic II/I piping systems with a potential for spatialinteraction with safety-related SSCs are in the scope of license renewal per 54.4(a)(2) and subjectto aging management review.

Based on earthquake experience data (Ref. 25) that includes aged pipe, the following conclusionscan be drawn.

* NO experience data exists of welded steel pipe segments falling due to a strong motionearthquake.

* Falling of piping segments is extremely rare and only occurs when there is a failure of thesupports.

* These conclusions apply for new and aged pipe.

As long as the effects of aging on the supports for these piping systems are managed, falling ofpiping sections is not considered credible, and the piping section itself is NOT in scope for54.4(a)(2) due to the physical impact hazard. The effects of spray and leakage must beconsidered.

Missiles can be generated from internal or external events such as failure of rotating equipment.Inherent NSR features that protect safety-related equipment from missiles should be consideredwithin the scope of license renewal per 54.4(a)(2) and subject to aging management review.

The overhead-handling systems whose failure could result in damage to any system that couldprevent the accomplishment of a safety function meet the criteria of 54.4(a)(2) and should beconsidered within the scope of license renewal and subject to aging management review.

Pipe Whip. Jet Impingement. or Harsh Environments

Pipe whip, jet impingement, and harsh environment effects on safety-related equipment aretypically addressed in site-specific analyses of high and medium energy line breaks. Section3.6.1 of the ANO-2 SAR identifies those systems where the fluid temperature exceeds 200 OF orthe pressure exceeds 275 psig that were evaluated for pipe breaks.

If a HELB analysis assumes that a NSR piping system does not fail or assumes failure only atspecific locations, then that piping system should be within the scope of license renewal per54.4(a)(2) and subject to aging management review in order to provide reasonable assurance thatthose assumptions remain valid through the period of extended operation.

If required safety-related equipment is not protected from the effects of a high-energy line break(HELB), then the high energy piping is within the scope of license renewal and subject to agingmanagement review.

........ ........ J .. __ .......... .. _ . ..

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-Me 2003-001-1


Leakage. Spray. or Flooding

Moderate and low energy systems have the potential for spatial interactions of spray and leakage.Nonsafety-related systems and nonsafety-related portions of safety-related systems with thepotential for spray or leakage that could prevent safety-related SSCs from performing theirrequired safety function are considered in the scope of license renewal and subject to agingmanagement review.

Air and gas systems (non-liquid) systems are not a hazard to other plant equipment. Componentsthat do not contain liquids cannot adversely affect safety-related SSCs due to leakage or spray.Operating experience indicates that nonsafety-related systems containing only air or gas haveexperienced no failures due to aging that could impact the ability of safety-related equipment toperform required safety functions. There are no credible aging effects for these systems when theenvironment is a dry gas. These systems need not be considered in the scope of license renewalfor scoping criterion §54A(a)(2).

Nonsafety-related systems and nonsafety-related portions of safety-related systems containingsteam or liquid that are near safety-related equipment should be considered in scope for§54.4(a)(2). In light of §54.4(a)(2), the concern for these systems is the impact of a pressureboundary failure on safety-related systems. These failures could result in the nonsafety-relatedpiping spraying or leaking on safety-related equipment. Consideration of hypothetical failuresthat could result from system interdependencies that are not part of the CLB and that have notbeen previously experienced is not required. (Ref. 24) Failure resulting from long-termexposure to conditions resulting from a failed NSR SSC (such as leakage or spray) areconsidered hypothetical. Leakage from liquid-filled low-energy systems is detected duringroutine operator rounds or system Walkdown long before it could impact the performance ofsafety-related equipment. The leakage from these low-energy systems has typically resulted fromisolated pitting that is not indicative of the overall condition of the piping. Follow-up actionswould direct leakage away from equipment and therefore prevent its failure. Additionalevaluations of the condition of the piping would then be performed.

Walls, curbs, dikes, doors, etc., that provide flood barriers to SR SSCs, should be within thescope of license renewal per 54.4(a)(2).

Section 2 of this report will review the specific evaluation criteria used to satisfy this guidance.

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-MEv2003so01-1

Components Affecting Safety-related Systems Raevision 7

2.0 Evaluation Criteria

2.1 Mechanical Systems and Components that Meet the 54.4(a)(2) Criteria for Leakage orSpray

This section reviews the 54.4(a)(2) criteria and establishes a logic flowchart (see Attachment 3)for the review of mechanical systems. Attachment 1 to this aging management review reportprovides a listing of the ANO-2 mechanical systems as identified in the ANO-2 scoping report(Ref. 3). In order to identify nonsafety-related systems or nonsafety-related portions of safety-related systems with the potential for adverse spatial interaction with safety-related SCs(54.4(a)(2)), a review of each mechanical system was required.

The first step is to determine if the system only contains air or gas. For these systems a reviewof operating experience is required. The review confirms that there have been no failures ofair/gas systems that could have adversely impacted the ability of equipment to perform requiredsafety functions. If this is verified, then air systems do not require further aging managementreviews under 10 CFR 54.4(a)(2). A review of industry operating experience associated withnonsafety-related systems/components containing air/gas found four NRC documents. None ofthese documents described instances where nonsafety-related air/gas system leakage or rupturesadversely impacted safety-related equipment. These documents are: NRC Generic Letter 88-14andNRC InformationNotices 81-38, 87-28, and 99-01. (Ref. 13,14,15,16,20) The operatingexperience review that was performed for ANO-2 in report A2-EP-2002-003-0 (Ref. 4)confirmed that there have been no failures of air/gas systems that could have adversely impactedthe ability of equipment to perform required safety functions. Since this was verified, air or gassystems do not require further aging management reviews under 10 CFR 54.4(a)(2).

The second step is to determine if the system has components in a safety-related structure.Systems that only contain components in the turbine building, office buildings, warehouses, etc,cannot interact with safety-related components and the nonsafety-related system does not requireaging management review. The ANO-2 containment building, auxiliary building, intakestructures, and emergency diesel fuel oil storage vault are the primary seismic class 1 structuresat ANO-2 and contain the safety-related plant equipment. For further information on thestructures and their functions, see the ANO-2 scoping report 02-R-2008-01.

Those systems that contain liquid-filled nonsafety-related components inside of safety-relatedstructures require as a third step a component level evaluation to determine if there is a potentialfor spatial interaction with safety-related SSC from leakage, or spray. Nonsafety-relatedcomponents such as the ANO-2 spent fuel pool coolers are an example of components that are ina safety-related building, but could not spatially interact with safety-related components sincethey are in a separate room of the building.



See Attachment 3 for a graphic representation of the screening that is performed. For thosecomponents that meet all three criteria, an aging management review is performed on the passivemechanical components that identify the aging effects requiring management for the material andenvironment combinations. The passive mechanical components reviewed include piping,tubing, valve bodies, heat exchangers, orifices, pump casings, tanks, filter housings and otherpassive components.

2.2 Mechanical Systems and Components that Meet the 54.4(a)(2) Criteria for Reasons Otherthan Leakage or Spray

Nonsafety-related supports for non-seismic (including seismic M) piping systems and electricalconduit and cable trays with a potential for spatial interaction with safety-related SCs are withinthe scope of license renewal per 54.4(a)(2) and subject to aging management review. Thesesupports and components have been addressed in a commodity fashion within civil/structuralAMRs. As long as the effects of aging on the supports for piping systems are managed, fallingof piping sections is not considered credible, and the piping section itself is NOT in scope for54.4(a)(2) due to the physical impact hazard.

Missiles can be generated from internal or external events such as failure of rotating equipment.Inherent NSR features that protect safety-related equipment from missiles are within the scope oflicense renewal per 54.4(a)(2) and subject to aging management review. These features areaddressed in civil/structural AMRRs.

The overhead-handling systems whose failure could result in damage to a system that couldprevent the accomplishment of a safety function, are considered to meet 54.4(a)(2) and are withinthe scope of license renewal and subject to aging management review. These features areaddressed in civil/structuralAMRRs.

Walls, curbs, dikes, doors, etc., that provide flood barriers to safety-related SCs and are withinthe scope of license renewal per 54.4(a)(2) have been included as part of the building structureand evaluated in the civil/structuralAMR~s for that building.

2.3 Review of ANO-2 High Energy Line Breaks (HELBs)

In order to ensure the nonsafety-related portions of high energy lines were included in this54.4(a)(2) review, the ANO-2 SAR and associated site documentation was reviewed. SARSection 3.6, Protection Against Dynamic Effects Associated With The Postulated Rupture OfPiping, contains the review of high-energy line breaks for ANO-2. The SAR lists the systemsthat were evaluated for postulated pipe breaks and identifies that these analyses are described inmore detail in the ANO- Engineering Standard NES-13, Environmental Qualification-Environmental Service Conditions. (Ref. 11, 26)

Section 3.6.1 of the ANO-2 SAR identifies those systems where the fluid temperature exceeds

ANO-2 License Renewal Project En2Mge2ei34)R1p1Aging Management Review of Nonsafety-related Systems and Re20sion 1


200TF or the pressure exceeds 275 psig that were evaluated for pipe breaks. The followingsystems were included:

A. Inside containment1. Reactor coolant piping, including pressurizer surge line and spray line piping2. Chemical and volume control system (CVCS) letdown and makeup piping3. Safety injection system (SIS) piping (only the portions of this system normally

subjected to safety injection tank pressure)4. Main steam piping5. Steam generator blowdown piping6. Main feedwater piping7. Emergency feedwater piping8. Shutdown cooling piping from reactor coolant nozzle to the first isolation

valve

B. Outside containment1. Main steam piping (including extraction steam piping and steam supply piping

to the main feedwater pump turbine drivers and the emergency feedwaterpump turbine driver)

2. Main feedwater piping3. Steam generator blowdown piping4. CVCS letdown piping (from containment penetration to letdown heat

exchanger) and makeup piping (from charging pump discharge to containmentpenetration).

5. Emergency feedwater piping (from pump discharge to containmentpenetration)

The majority of these high energy lines are safety-related lines that are reviewed in the systemmechanical aging management review reports. During the review of the ANO-2 systems asdocumented in Section 3 of this report, these high energy systems as documented in NES-13were considered to ensure any components that are part of nonsafety-related high energy linesthat can effect safety-related equipment are included in this report. For additional information onthe high energy lines, see NES-13, Environmental Qualification- Environmental ServiceConditions. (Ref. 11,26) I

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Components Affecting Safety-related Systems ev14 of 77

3.0 Individual System Review

This section performs a review per the 54.4(a)(2) criteria for each mechanical system at ANO-2.The flowchart of Attachment 3 is followed and the basis for a system's review or exclusion ispresented for each system. For systems that contain passive mechanical components meeting the54.4(a)(2) criteria, EPRI report 1003056 is used to identify and evaluate aging effects requiringmanagement. Attachment 2 contains a listing of component types, their environments and theaging effects requiring management.

3.1 Alternate AC Generator (AAC)

The alternate AC generator provides power to the site during a loss of all unit AC power. Itresides in its own structure in the yard removed from safety-related equipment. There is no agingmanagement review required of the components in this system code for 54.4(a)(2) since theassociated passive mechanical components cannot impact safety-related equipment. (Ref. 5, 8)

3.2 AuxiliarvBuilding Heating and Ventilation (ABHV)

This system contains numerous heating and ventilation subsystems to provide heating andcooling of plant areas. The safety-related components in this system code are reviewed in theauxiliary building HVAC mechanical aging management review report 02-R-2005-17. Theair/gas containing portions of the system (ductwork, fan housings, etc) do not require agingmanagement review per 54.4(a)(2) since they only contain air. In this system code are nonsafety-related chilled water filled components in a ventilation room at elevation 404 of the auxiliarybuilding that do not have safety-related equipment near them and therefore do not require agingmanagement review for 54.4(a)(2). The unit heaters and cooling coils in this system code areradiator style heat exchangers with copper tubes with an internal environment of both raw andtreated water that require aging management review for 54.4(a)(2). There are some water-containing components included in this system code (containing chilled water, condensate drains,etc) with carbon steel piping, carbon steel valves (including cast iron), and tubing in treated waterthat require aging management review for 54.4(a)(2). There are some condensate drain valvesand piping in this system code that are constructed of copper alloy with an internal environmentof raw and untreated water that require aging management review per 54.4(a)(2). (Re. 5, 7, 8,21)

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces.Cracking is not an aging effect requiring management since an ammonia environment is notpresent. Loss of material due to pitting and crevice corrosion and selective leaching is an agingeffect requiring management for the external copper alloy surfaces since they can be wetted bycondensation (especially at the cooling coils).

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Loss of material from general corrosion, pitting corrosion, erosion, crevice corrosion, galvaniccorrosion, selective leaching (for gray cast iron) and MIC is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to general,pitting and crevice corrosion is an aging effect requiring management for the external carbonsteel surfaces since they can be wetted by condensation.

The temperature of the water in this system is below the threshold for fatigue.

3.3 AuxiliarvBuilding Sump (ABS)

The auxiliary building sump system provides piping and sumps to allow drainage for equipmentand areas. The auxiliary building sump (ABS) system is shown primarily on P&IDs in the M-2213 series, but the beginnings of individual equipment drain piping are shown on many systemP&IDs. The system contains piping, valves and pumps for equipment and floor drains in thecontainment, auxiliary building, and turbine building. There are a few safety-related componentsat the containment penetration that are reviewed in the penetration AMR. The nonsafety-relatedcomponents in the turbine building do not require further review since their failure cannot impactsafety-related equipment. The components that are imbedded in concrete do not require reviewsince a loss of pressure boundary for these components will not impact safety-related equipment.(Ref. 5, 7, 8)

There are stainless steel piping and valves, carbon steel piping and valves, and copper alloyvalves that require aging management review for 54.4(a)(2) in this system code. The internalenvironment for the floor drains is untreated water. Although some of the component drains mayhave an environment of treated water from the system they are draining, the environment isconservatively specified as untreated water for all components in this system. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel components internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the system temperatures are below the 140 OFthreshold for this effect. There are no aging effects requiring management for the externalstainless steel surfaces in an ambient air environment.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosionand MIC is an aging effect requiring management for the carbon steel components internalsurfaces. Loss of material is an aging effect requiringmanagement for the external carbon steelsurfaces in an ambient air environment.

Loss of material from pitting corrosion, crevice corrosion, selective leaching and MIC is an agingeffect requiring management for the copper alloy component internal surfaces. Cracking is notan aging effect requiring management since an ammonia environment is not present. Loss ofmaterial is not an aging effect requiring management for the external copper alloy surfaces in air.

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Components Affecting Safety-related Systems aev 1ion 7

The temperature of the water in this drain piping will be below the thresholds for fatigue sincethese are open to the atmosphere (and therefore cannot be above 212 OF).

3.4 Chilled Water (AC)

The chilled water system is shown primarily on P&lDs in the M-2222 series, but extends to otherP&IDs. The system provides chilled water to cooling units in the containment, auxiliarybuilding, the administration building and turbine building. The safety-related components in thissystem include the containment penetration components that are reviewed in the containmentpenetration engineering report 02-R-2005-06 and components in control room ventilation that arereviewed in the control room ventilation aging management report 02-R-2005-18. Thenonsafety-related components in structures that do not contain safety-related equipment such asthe turbine building and administrative building do not require further review since their failurecannot impact safety-related equipment. In this system code are nonsafety-related normal controlroom chiller units with water filled heat exchangers (2E-133A, B, 134A, B, 135A, B) in aventilation room at elevation 404 of auxiliary building that do not have safety-related equipmentnear them and therefore do not require aging management review for 54.4(a)(2). The nonsafety-related components in the containment and auxiliary buildings that require review for 54.4(a)(2)include copper alloy heat exchangers, carbon steel valves (including cast iron), carbon steelpiping, stainless steel piping, stainless steel thermowells and annubars, carbon steel filterhousings, carbon steel pump casings, carbon steel thermowells, copper alloy valves, copper andstainless steel tubing, and carbon steel tanks. The internal environment is treated water. (Ref. 5,7,8,19)

Loss of material from general, pitting, crevice, and galvanic corrosion, selective leaching (forgray cast iron) and MIC is an aging effect requiring management for the carbon steel componentinternal surfaces. Loss of material due to general, pitting and crevice corrosion is an aging effectrequiring management for the external carbon steel surfaces especially since they can be wettedby condensation.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces.Cracking is not an aging effect requiring management since an ammonia environment is notpresent. Loss of material due to pitting and crevice corrosion is an aging effect requiringmanagement for the external copper alloy surfaces since they can be wetted by condensation(especially at the heat exchangers) or experience wear.

Loss of material from pitting corrosion, crevice corrosion and WC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is notan aging effect requiring management since the system will operate below the 140 OF thresholdfor this effect. Loss of material is not an aging effect requiring management for the externalstainless steel surfaces due to the inherent corrosion resistance of stainless steel.

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The temperature of the water in this system is below the threshold for fatigue since this is a lowtemperature cooling water system.

3.5 AuxiliarM Cooling Water (ACW)

The system provides cooling water (raw lake water from the service water header) to componentsin the auxiliary building and turbine building. The auxiliary cooling water system is shownprimarily on P&IDs in the 2211 series, but extends to other system's P&IDs such as M-2221sheet 1 that shows the ACW supply to the HVAC units. The nonsafety-related components instructures that do not contain safety-related equipment such as the turbine building do not requirefurther review since their failure cannot impact safety-related equipment. The nonsafety-relatedcomponents in the auxiliary building that require aging management review for 54.4(a)(2)include copper alloy valves, carbon steel valves, carbon steel piping, carbon steel orifices, copperalloy tubing, and a glass level gage. The internal environment is raw water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,and NEC is an aging effect requiring management for the carbon steel component internalsurfaces. Loss of material due to general, pitting andecrevice corrosion is an aging effectrequiring management for the external carbon steel surfaces especially since they can be wettedby condensation.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces. Loss ofmaterial due to pitting and crevice corrosion is an aging effect requiring management for theexternal copper alloy surfaces since they can be wetted by condensation (especially at the heatexchangers).

There are no aging effects requiring management for glass.

The temperature of the water in this system is below the threshold for fatigue since this is a lowtemperature lake water cooling system.

3.6 Admin. Building Heating and Ventilation (ADHV)

This system is not does not require aging management review per 54.4(a)(2) since it onlycontains dry air or gas and is in the administration building where there are no safety-relatedcomponents. (Ref. 5, 8)

3.7 AuxiliarM Steam (AS)

The system provides low pressure steam to components in the auxiliary building and turbinebuilding. The auxiliary steam system is shown partially on P&ID 2202 sheet 3 and extends toother system's P&IDs. The nonsafety-related components in structures that do not containsafety-related equipment such as the turbine building do not require further review since theirfailure cannot impact safety-related equipment. Although some of these components such as the

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boric acid evaporators are no longer utilized, there are portions of this system that are not isolatedand therefore require aging management review for 54.4(a)(2). The nonsafety-relatedcomponents in the auxiliary building that require aging management review for 54A(a)(2)include carbon steel valves, carbon steel piping, carbon steel orifices, stainless steel tubing, andstainless steel valves. The internal environment is steam and treated water. (Ref. 5, 7, 8, 9)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion (including FAC) and MIC (in low temperature portions) is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management since the system will operate above the 1400F threshold forthis effect. Loss of material is not an aging effect requiring management for the externalstainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management since the system operates at atemperature above the threshold for fatigue.

3.8 Breathing Air (BA)

The breathing air system provides a reliable supply of dry, oil free, OSHA grade D qualitycompressed air for use in air-fed respirators. This system does not require aging managementreview per 54.4(a)(2) since it only contains dry air or gas. (Ref. 5, 8)

3.9 Startup and Blowdown Demineralizers (BD)

The startup and blowdown demineralizer system contains the steam generator blowdowncomponents starting at the steam generators and includes the demineralizers that treat theblowdown tank effluent. The blowdown tanks are shown on M-2206 sheet 2 and the blowdowndemineralizers are shown on M-2229. The safety-related components in the system are reviewedin the penetration aging management review report 02-R-2005-06. The nonsafety-relatedcomponents in structures that do not contain safety-related equipment such as the turbinebuilding do not require further review since their failure cannot impact safety-related equipment.The portions of the system in the auxiliary building that require aging management review for54.4(a)(2) include carbon steel and stainless steel piping, stainless steel tubing, carbon (includingcast iron) and stainless steel valves, carbon steel tanks, and carbon steel and stainless steelorifices, and carbon steel with stainless steel clad pump casings that are exposed to treated wateror steam (upstream and including the blowdown tank) at elevated temperatures. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion (includingFAC), galvanic corrosion and selective leaching (for gray cast iron) and MIC (in low temperature

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portions) is an aging effect requiring management for the carbon steel component internalsurfaces. Loss of material due to general corrosion is an aging effect requiring management forthe external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for portions of the system that are above the 140 OF threshold.Loss of material is not an aging effect requiring management for the external stainless steelsurfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management for the portions of the system thatoperate above the thresholds for fatigue.

3.10 Boron Management (BMS)

The boron management system consists of boric acid tanks, pumps and various piping and valvesto control the born concentration in the primary systems. The system includes boric acidevaporators that are no longer utilized. (Ref. 9) The safety-related components in the system arereviewed in the penetration aging management review report 02-R-2005-06. The majority of thesystem is shown on P&IDs M-2213 and M-2214-1, 2 but extend to other P&I]Ds. The portions ofthe system in the auxiliary building and containment that require aging management review for54.4(a)(2) includes stainless steel piping and valves, stainless steel pump casings, stainless steeltanks, stainless steel filter housings, stainless steel tubing and stainless steel orifices that areexposed to treated borated water. (Ref. 5, 7, 8, 9)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for portions of the system that are above 140 OF. Loss ofmaterial is not an aging effect requiring management for the external stainless steel surfaces dueto the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management for the portions of the system thatoperates at a temperature above the 270 OF threshold for fatigue.

3.11 Containment Sporav (BS)

The containment spray system consists primarily of safety-related components that underaccident conditions will spray the containment and that are reviewed in report 02-R-2005-03.Included in this system in the database are the sodium hydroxide (NaOH) tank and componentsthat are no longer safety-related but remain filled with NaOH. The NaOH tank is outdoors andseparated from safety-related equipment, but a small portion of the NaOH piping in the auxiliarybuilding requires aging management review per 54.4(a)(2). This piping, valves, and pump casingare stainless steel and exposed to treated water containing NaOH. There are nonsafety-relatedcomponents in the BS system that are not reviewed in report 02-R-2005-03 and are in the

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auxiliary building and require aging management review per 54.4(a)(2) including the RWT fillvent line valves, the RWT recirculation and test line drains and sample valves. This piping andvalves are constructed of stainless steel and contain treated borated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management for the borated water portions of the system since thesystem temperatures are expected to remain below the 140 °'F threshold for this effect. For theNaOH portions of the system, cracking is identified as an aging effect requiring managementsince the level of contaminants is high. Loss of material is not an aging effect requiringmanagement for the external stainless steel surfaces due to the inherent corrosion resistance ofstainless steel.

Cracking from fatigue is not an aging effect requiring management since the system operates attemperatures below the 270 OF threshold for fatigue.

3.12 Chemical Addition (CA)

This system injects chemicals in the various water systems at ANIO. Many system componentsare in the turbine building or in other yard structures that do not contain safety-related equipment.There are a few components in the intake structure, but these components contain very lowdiluted concentrations of chemicals that are also in the service water pump bays where theirfailure would not affect any safety-related equipment. A few components in the auxiliarybuilding require aging management review for 54A(a)(2). These small (3/8 inch) stainless steelpiping and valves feed ammonia or hydrazine to the emergency feedwater suction for chemicalcontrol and are shown on P&IDs M-2204 sheet 4 and M-2240 sheet 1. The stainless steel pipingand valves that require aging management review for 54.4(a)(2) contain hydrazine or ammonia(Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management due to the chemicals transported. Loss of material is not anaging effect requiring management for the external stainless steel surfaces due to the inherentcorrosion resistance of stainless steel.

Cracking from fatigue is not an aging effect requiring management since this system operates attemperatures below the threshold for fatigue.

3.13 Component Cooling Water (CCW)

This system provides cooling water to nonsafety-related components and is shown primarily onP&IDs M-2234 sheets 1 and 2. The safety-related components in the system at the containmentpenetration are reviewed in the containment penetration AMRR (02-R-2005-06). The norisafety-

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related components in areas that do not contain safety-related equipment such as the turbinebuilding and elevation 404 in the auxiliary building do not require further review since theirfailure cannot impact safety-related equipment. The CCW surge tanks are in this room andtherefore do not require a review. The nonsafety-related components in the containment andauxiliary building require aging management review per 54.4(a)(2). This includes aluminumvalves, carbon steel pipe, stainless steel pipe and tubing, carbon steel (including cast iron) valves,stainless steel valves, copper alloy valves, copper alloy tubing, carbon steel orifices with aninternal environment of treated water. (Ref. 5, 7, 8,19)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion, galvaniccorrosion, selective leaching (for gray cast iron) and MIC is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material from generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the system operates below the 140 OF threshold forthis effect. Loss of material is not an aging effect requiring management for the externalstainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces. Loss ofmaterial is not an aging effect requiring management for the external copper alloy surfaces due tothe inherent resistance of copper to corrosion in air.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MEC isan aging effect requiring management for the aluminum alloy component internal surfaces. Lossof material is not an aging effect requiring management for the external aluminum alloy surfacesdue to their inherent corrosion resistance.

Cracking from fatigue is not an aging effect requiring management since the system operates attemperatures below the threshold for fatigue.

3.14 Control Element Drive Mechanisms (CEDM)

This system is the electrical controls and the control rod drive mechanisms for the ANO-2control rods. The passive mechanical components are the control rod drive mechanisms that arereviewed for their RCS pressure boundary in the RCS aging management review report (02-R-2005-01). There are no passive mechanical nonsafety-related components that require agingmanagement review per 54.4(a)(2) in this system code. (Ref. 5, 8)



3.15 Carbon Dioxide (CO2/CRDX)

This system does not require aging management review per 54.4(a)(2) since it only contains dryair or gas. (Ref. 5, 8)

3.16 Containment Penetration Room Ventilation (CPV)

This system does not require aging management review per 54.4(a)(2) since it only contains dryair or gas. (ReL 5, 8)

3.17 Control Room Ventilation (CRV)

The control room ventilation system provides normal and emergency ventilation for the controlroom space. The safety-related components are reviewed as required under the control roomventilation aging management review report 02-R-2005-18. This system contains nonsafety-related components that provide normal cooling and heating to the control room. The majority ofthese nonsafety-related components do not require aging management review for 54.4(a)(2) sincethey only contain dry air. See P&ID M-2263 sheets 1 and 2 for details of this equipment. Thereare heating and cooling coils inside the ventilation unit supply housing that contain water, butthese are in an area that does not contain safety-related equipment and therefore do not requireaging management review per 54.4(a)(2). (Ref. 5, 7, 8, 19)

3.18 Condensate (CS)

The primary flow path for this system is from the condensate pumps that take the water from themain condenser and supply the low pressure feedwater heaters and main feedwater pumps tosupport secondary plant operation. These components are in the turbine building and a reviewper 54.4(a)(2) is not required for the components in the turbine building. A few nonsafety-related valves and piping in this system are in the auxiliary building and were intended to returncondensate from the boric acid evaporators to the main condenser. See P&ID M-2213 sheet 3 fordetails of this equipment. Since the boric acid evaporators are not used, there is no fluidcontained in these lines and this piping does not require a review for 54A(a)(2). As a result thereis no aging management review per 54.4(a)(2) required of the nonsafety-related components inthis system. (Ref. 5, 8, 9)

3.19 Condensate Storage and Transfer (CT)

This system includes the condensate storage tanks, the condensate transfer pumps, and pipingand valves to distribute water from the condensate storage throughout the plant. Componentsthat are outdoors and separated from safety-related equipment, or in the turbine building do notrequire aging management require review per 54.4(a)(2). See P&IDs M-212, M-2212 sheets 3and 4 and others such as M-2226 sheetl for details of this equipment. The nonsafety-relatedcomponents in the auxiliary building that require aging management review per 54.4(a)(2)

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include stainless steel piping, stainless steel tubing, stainless steel valves, copper alloy valves,and copper tubing with an internal environment of treated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is notan aging effect requiring management for the since the system temperatures are expected toremain below the 140 OF threshold for this effect. Loss of material is not an aging effectrequiring management for the external stainless steel surfaces due to the inherent corrosionresistance of stainless steel.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces. Loss ofmaterial is not an aging effect requiring management for the external copper alloy surfaces in anair environment due to the inherent corrosion resistance of copper.


3.20 Chemical and Volume Control (CVCS)

The purpose of the chemical and volume control system is to maintain reactor coolant system(RCS) inventory and control RCS chemistry. The CVCS system consists of four subsections;letdown, charging, boron addition and reactor makeup water. The system is shown primarily onM-2231 sheets 1 and 2. The majority of the CVCS system is reviewed in the RCS report 02-R-2005-01 or the CVCS aging management review report 02-R-2005-10. There are nonsafety-related components in the auxiliary building in this system code that are not reviewed in thesystem aging management review reports including stainless steel filter housings, a heatexchanger (2E-29), stainless steel tanks (ion exchangers), stainless steel valves, stainless steelpiping, stainless steel tubing, stainless steel thermowells that have an internal environment oftreated borated water. These components require review per 54.4(a)(2). (Ref 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operate above the 140 OFthreshold for this effect (upstream of the letdown heat exchanger). Loss of material is not anaging effect requiring management for the external stainless steel surfaces due to the inherentcorrosion resistance of stainless steel.

The letdown heat exchanger 2E-29 has stainless steel channel head with an internal environmentof treated borated water that will have the same aging effects as the stainless steel componentsabove. The carbon steel shell with an internal environment of treated water requires managementfor the aging effect of loss of material from the internal surface from general corrosion, pitting

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corrosion, crevice corrosion, erosion, MIC, and galvanic corrosion. Loss of material is an agingeffect requiring management for the external carbon steel surface of the shell. (Ref. 10)

Cracking from fatigue is an aging effect requiring management for components that operate attemperatures above the threshold for fatigue.

3.21 Containment Vent Header (CVM)

This system does not require aging management review per 54A(a)(2) since it is a vent headerthat normally only contains dry air or gas. (Ref. 5, 8)

3.22 Circulating Water (CW)

The circulating water system provides cooling water to the main condenser and almost all of theequipment is in the turbine building or outdoors away from safety-related equipment. In theauxiliary building, line 2-JBD-200 and vent valve (2CW-1005) shown on P&ID M-2209 sheet 1are used to drain the circulating water system to the service water discharge pipe. Therefore thisone section of pipe and valve require aging management review per 54.4(a)(2). This is a carbonsteel pipe and valve and contains raw water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, and MIC is an agingeffect requiring management for the carbon steel component internal surfaces. Loss of materialdue to erosion is not an aging effect requiring management since this segment of piping isnormally stagnant. Loss of material due to general corrosion is an aging effect requiringmanagement for the external carbon steel surfaces.


3.23 Drain Collection Header (DCH)

This system drains numerous components in the auxiliary building and is shown on variousP&IDs (2112-1, 2231-1, 2235-1, etc.). The system consists of stainless steel piping, stainlesssteel valves, stainless steel tubing, carbon steel valves, and carbon steel piping that require agingmanagement review per 54.4(a)(2) with an internal environment that is conservatively identifiedas untreated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is notan aging effect requiring management since the system contains fluid from low temperaturesources and is below the 140 OF threshold for this effect. Loss of material is not an aging effectrequiring management for the external stainless steel surfaces due to the inherent corrosionresistance of stainless steel.

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Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,and MIC is an aging effect requiring management for the carbon steel component internalsurfaces. Loss of material due to general corrosion is an aging effect requiring management forthe external carbon steel surfaces.

Cracking from fatigue is not an aging effect requiring management since the system operates at atemperature below the thresholds for fatigue.

3.24 Dry Fuel Storage (DFS)

The dry fuel storage system is controlled by a license separate from the ANO-2 operating license,and is not affected by the operating license renewal. For additional information, see report 02-R-2008-01, System and Structure Scoping Method and Results.

3.25 Domestic Water (DW)

The domestic water system supplies water for domestic use (drinking water, sinks, etc)throughout various plant buildings and is shown primarily on P&IDs M-2212 sheets I thru 5.The components in the auxiliary building requiring aging management review per 54.4(a)(2)include piping and valves (including the valves on safety showers). These components arecopper alloy (brass, bronze, copper, etc) and carbon steel (including cast iron) and have aninternal environment of treated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces.Crackdng is not an aging effect requiring management since an ammonia environment is notpresent. Loss of material is not an aging effect requiring management for the external copperalloy surfaces due to the inherent corrosion resistance of copper alloy to aging effects in air.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,selective leaching (for gray cast iron) and MIC is an aging effect requiring management for thecarbon steel component internal surfaces. Loss of material due to general corrosion is an agingeffect requiring management for the external carbon steel surfaces.

The temperature of the water in this system is below the threshold for fatigue.

3.26 Diesel Fuel Services (ED)

The passive nonsafety-related mechanical components in this system consist of only two valvesthat are enclosure drains (2ED-1008A, B). These are to be used if there is a fuel oil leak from theEDG day tanks and normally contain only air. This system does not require aging managementreview per 54.4(a)(2) since it only contains dry air. (Ref. 5, 8)

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3.27 Emergency Diesel Generator (EDG'

The emergency diesel generator system provides emergency onsite power, and therefore themajority of the system components are safety-related and reviewed in the EDG agingmanagement review engineering report 02-R-2005-09. There are nonsafety-related valves andfilter housings on the crankcase vacuum measurement instruments that are not safety-related andare therefore not reviewed in the EDG report. These lines are connected to the portion of thecrankcase which is at a vacuum and only contains air. Therefore this system does not requireaging management review per 54A(a)(2) since the nonsafety-related portions only contain dryair.

3.28 EmergencyFeedwater (EFW)

The emergency feedwater system supplies safety grade backup source of feedwater to the steamgenerators when main feedwater is not available. The majority of components are thereforereviewed in the emergency feedwater aging management review report 02-R-2005-21. Thenonsafety-related auxiliary feedwater pump (2P-75) is included in this system code, but the pumpand its associated supporting components (lube oil, etc) are in the turbine building and thereforedo not require aging management review per 54.4(a)(2). There are nonsafety-related componentssuch as on the emergency feedwater test line, flush line, condensate suction line, low pressureleakoff lines, turbine casing drains and steam supply traps on the auxiliary steam supply to theturbine as shown primarily on P&ID M-2212 sheet 4.that that are in the auxiliary building andrequire aging management review per 54.4(a)(2). This includes stainless steel piping, stainlesssteel tubing, stainless steel valves, stainless steel orifices, carbon steel piping, carbon steelvalves, and carbon steel filter housings exposed to internal environments of treated water orsteam. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operate above the 140 OFthreshold for this effect (steam components). Loss of material is not an aging effect requiringmanagement for the external stainless steel surfaces due to the inherent corrosion resistance ofstainless steel.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion and MIC is an aging effect requiring management for the carbon steel component internalsurfaces. Loss of material due to general corrosion is an aging effect requiring management forthe external carbon steel surfaces.

Cracking from fatigue is an aging effect requiring management for the high temperature (steam)portions of the system.

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Components Affecting Safety-related Systems gevision 1I

3.29 Electro-Hvdraulic Control System (EHC)

The purpose of electro-hydraulic control system is to provide control of the main turbine valvesto support electrical generation. The mechanical components include hydraulic pumps, filter,heat exchangers reservoirs, valves, and piping that provide the hydraulic control fluid for themain turbine valves. This system does not require aging management review for 54.4(a)(2) sincethe passive mechanical components for this system are in the turbine building and cannot affectsafety-related components. (Ref. 5, 8)

3.30 Extraction Steam (EX)

The extraction steam system supplies steam and condensate extracted from the turbine tosecondary plant components. This system does not require aging management review for54.4(a)(2) since the passive mechanical components for this system are in the turbine buildingand cannot affect safety-related components. (Ref. 5, 8)

3.31 Emergencv Operations Facility (EOF)

The purpose of emergency operations facility is an alternate location for the technical supportcenter and the operational support center if required by the activation of the site emergency plan.The building is .65 miles from the reactor buildings and serves as a training center during normalplant operation. The mechanical components in this system code include a backup dieselgenerator, HVAC components including heat exchangers, blowers, filters, etc. This system doesnot require aging management review for 54.4(a)(2) since the passive mechanical componentsfor this system are in the training building/EOF and cannot affect safety-related components.(Ref. 5, 8)

3.32 Fuel Handling (Ef and FHS)

The purpose of the fuel handling system (codes FH and HIS) is to provide the capability ofunderwater handling and transfer of spent fuel and control components removed from the reactorto the spent fuel pool, movement of fuel and control components within the reactor vessel andmovement of new fuel from the spent fuel pool to .the reactor. The system also provides thecapability of moving new fuel from shipping containers to new fuel storage or spent fuel storage.

The FHS system consists of the fuel handling equipment such as the fuel transfer tube, the spentfuel pool crane, upender assemblies, refueling machine, spent fuel machine, the new fuelelevator, and manual tools. The fuel transfer tube includes the blind flange for containmentintegrity which is a safety-related component and reviewed in the SFP aging management reviewreport 02-R-2005-07. There are hydraulic pumps for upenders and refueling machine operation,but these are not in operation during normal power operation and are in or near the pools and notadjacent to safety-related equipment that could be affected by water. This system does notrequire aging management review per 54.4(a)(2) since there are no nonsafety-related pressure

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boundary passive mechanical components in this system adjacent to safety-related equipment.(Ref. 5, 8)

3.33 Fuel Oil (TO)

This system provides diesel fuel as required for the emergency diesel generators, SBO diesel, anddiesel fire pump, auxiliary boiler, security diesel, etc. The safety-related components arereviewed in the fuel oil system aging management review report 02-R-2005-13. The few passivenonsafety-related mechanical components in areas containing safety-related equipment that arenot reviewed in the fuel oil aging management review report 02-R-2005-13 (such as the fueloverflow indicators and dirty fuel oil collection components) normally only contain dry air orgas, Therefore this system does not require aging management review per 54.4(a)(2). (Ref 5, 8)

3.34 Fuel Pool Cooling and Purification (FM)

The fuel pool cooling and purification system removes decay heat from the stored spent fuel andmaintains purity and optical clarity of the water in the spent fuel pools and the fuel transfer canal/ refueling canal. The system is shown on P&ID M-2235. The safety-related components arereviewed in the spent fuel pool cooling aging management review report 02-R-2005-07. TheSFP heat exchanger, filters, ion exchanger tank and pumps are in their own rooms and thereforetheir failure cannot impact safety-related components. There are nonsafety-related stainless steelpiping and valves that require review for 54.4(a)(2) with an internal environment of treatedwater. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MWC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the system operates from low temperature sourcesand is below the 140 OF threshold for this effect. Loss of material is not an aging effect requiringmanagement for the external stainless steel surfaces due to the inherent corrosion resistance ofstainless steel.


3.35 Fire Protection (Water) (ES)

The fire protection water system is reviewed in the fire protection aging management reviewreport 02-R-2005-08. The majority of the system is shown on M-2219 sheets 1 and 2. The fueloil components in this system code are reviewed in the fuel oil aging management review report02-R-2005-13. The portions of the system that are not reviewed in these reports and are instructures containing safety-related equipment require aging management review per 54.4(a)(2).This includes carbon steel (including cast iron) and copper alloy valves, carbon steel piping,stainless steel valves, copper alloy tubing and stainless steel tubing that contain raw water. (Ref.5,7,8)

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Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion, selective leaching (for gray cast iron) and MIC is an aging effect requiring managementfor the carbon steel component internal surfaces. Loss of material is an aging effect requiringmanagement for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the system operates from low temperature sourcesand is below the 140 OF threshold for this effect. Loss of material is not an aging effect requiringmanagement for the external stainless steel surfaces due to the inherent corrosion resistance ofstainless steel.

Loss of material from pitting corrosion, crevice corrosion, selective leaching and MIC is an agingeffect requiring management for the copper alloy component internal surfaces. Cracking fromIGA/SCC is not an aging effect requiring management since an ammonia environment is notpresent. Loss of material is not an aging effect requiring management for the external copperalloy surfaces due to the inherent corrosion resistance of copper alloys.

Cracking from fatigue is not an aging effect requiring management since the system operates at atemperature below the thresholds for fatigue.

3.36 Feedwater (FW)

The feedwater system provides feedwater to the steam generators during normal plant operation.The majority of the system is in the turbine building and therefore does not require a review for54.4(a)(2). The safety-related components are reviewed in report 02-R-2005-20. The nonsafety-related components in the auxiliary building that require aging management review per 54.4(a)(2)include carbon steel piping and valves with an environment of treated water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion (including FAC) and MIC (when at low temperature) is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Cracking from fatigue is an aging effect requiring management since the system operates attemperature above the threshold for fatigue.

3.37 Gas Collection Header (GCH)

This system is part of the gaseous radwaste system and collects the vent gas from systems asshown on P&ID M-2215 (and others). This system does not require aging management reviewper 54.4(a)(2) since it only contains dry air or gas. (Ref. 5, 8)

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3.38 Generator Gas (GG)

This system provides gasses for the main generator. This system does not require agingmanagement review for 54.4(a)(2) since it only contains dry air or gas and the passivemechanical components are only in the turbine building. (Ref. 5, 8)

3.39 Gland Steam / Exhaust Steam (GS)

The gland steam / exhaust steam system has components in the turbine building that supply glandsealing steam to the seals and condense the steam from the seals of the main turbine and mainfeed pump turbines. This system does not require aging management review per 54.4(a)(2) sincethere are no passive mechanical components in structures containing safety-related components.(Ref. 5, 8)

3.40 Generator Seal Oil (GSO)

This system maintains oil at the proper pressure to seal the main generator. This system does notrequire aging management review per 54.4(a)(2) since there are no passive mechanicalcomponents in structures containing safety-related components. (Ref. 5,8)

3.41 Gaseous Radwaste (GZ

This system collects, compresses, and stores waste gas. The majority of the system componentsdo not require a review per license renewal for 54.4(a)(2) since they only contain dry air or gas.The only passive mechanical components in this system that contain water are the compressorcoolers (2E-1OlA, B; 2E-102A, B; 2E-103A, B) that are not where their failure could impactsafety-related equipment. (see Attachment 4) Therefore, no AMR is required. (Ref. 5,8)

3.42 Hvdrogen Supply (Generator) (H2)

This system supplies the hydrogen to the main generator and other plant equipment such as thevolume control tank. This system does not require aging management review per license renewalfor 54.4(a)(2) since it only contains dry air or gas. (Ref. 5,8)

3.43 Halon System (HAL)

The Halon system is a standby fire system that will disperse Halon gas if a fire is detected. Theportions of this system required for fire protection are reviewed in the Halon aging managementreview report 02-R-2005-12. This system does not require aging management review per licenserenewal for 54.4(a)(2) since it only contains dry air or gas. (Ref. 5, 8)

3.44 Heater Drains (HD)

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Components Affecting Safety-related Systems Rev3sion 7

The heater drains system directs the water from the feedwater heaters to the appropriatecomponent for secondary plant feedwater heating. All passive mechanical components for thissystem are in the turbine building where their failure can not impact safety-related equipment.(Ref. 5, 8)

3.45 Hvdroen Purge (HPA)

This system includes the hydrogen purge and hydrogen sampling components. The safety-relatedcomponents in this system are reviewed in the hydrogen control system aging managementreview report 02-R-2005-05. The system does not require review per 54.4(a)(2) since it onlycontains dry air or gas. No aging management review of the nonsafety-related components isrequired for 54.4(a)(2). (Ref. 5, 8)

3.46 High Pressure Safety Injection (HPSI

The high pressure safety injection system is a part of the emergency core cooling system toprovide water following a LOCA and is shown primarily on P&ID M-2232. The safety-relatedcomponents of this system are reviewed in the ECCS aging management review report 02-R-2005-02. There are a few nonsafety-related valves that are not reviewed in report 02-R-2005-02like the drain pan valves and several small pressure points in normally isolated portions of thesystem. These few lines are normally dry and do not require a review for 54.4(a)(2). No AMRon the nonsafety-related components is required for 54.4(a)(2). (Ref. 5, 8)

3A7 Isophase Bus Cooling (IBC)

The isophase bus cooling system consists of the ducts and associated cooling fans for cooling theisophase bus that connects the main generator to the main transformer. The mechanicalcomponents are the cooling fans and ductwork that provide cooling to remove the heat generatedby the electrical conductors. This system does not require aging management review per licenserenewal for 54.4(a)(2) since it only contains dry air.

3.48 Instrument Air (IA)

The instrument air system provides control air to pneumatically-operated components. Thissystem does not require a review per 54.4(a)(2) since the components in buildings that containsafety-related equipment only contain dry air or gas. There are heat exchangers in this systemcode that contain water, but these are in the turbine building. No aging management review isrequired per 54A(a)(2). (Ref. 5, 8)



3.49 Intake Structure (IS)

There are some passive mechanical components in the system code IS. This is includes dampers,fans, and heat exchangers (electrical heaters). The safety-related passive components arereviewed in the service water aging management review report 02-R-2005-16. The nonsafety-related passive mechanical components only contain an internal environment of air, andtherefore do not require a review for per 54.4(a)(2). (Ref. 5, 8)

3.50 Low Level Radwaste Building (LLRB)

This system code contains mechanical components that support the equipment used in the lowlevel radwaste building. This system does not require a review per 54.4(a)(2) since the passivemechanical components are in a building that does not contain safety-related equipment.

3.51 Lube Oil (LQ)

This system provides lube oil for the main turbine and main feedwater pumps. The passivemechanical components for this system are in the turbine building, therefore aging managementreview is not required for 54.4(a)(2). (Ref. 5, 8)

3.52 Low Pressure Safety Injection (LPSI)

The low pressure safety injection system is a part of the emergency core cooling system whichprovides water for core cooling following a LOCA. The safety-related components of thissystem are reviewed in the ECCS aging management review report 02-R-2005-02. Thenonsafety-related piping and valves that are not reviewed in report 02-R-2005-02 such as on theseal leak off lines and the drain header require a review per 54.4(a)(2). These components arestainless steel valves and piping and have an internal environment of treated borated water. (Ref.5,7,8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions that operate above the 140 OF threshold forthis effect. Loss of material is not an aging effect requiring management for the externalstainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management for the portions of the system inthe 54.4(a)(2) scope that operate at a temperature above the 270 OF threshold for fatigue.

3.53 Low Level Radwaste Building Ventilation (LRBV)

This system provides heating and cooling to the low level radwaste building. This system doesnot require aging management review per 54.4(a)(2) since the system components are not in abuilding that contains safety-related equipment. (ReL 5, 8)

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3.54 Liquid Radwaste Management (LRW)

This system processes the liquid radioactive waste water and is shown mainly on the M-2213P&ID series. The system was designed with boric acid evaporators and waste concentrators, butthese are not used. (Ref. 9, 22) There are nonsafety-related components including stainless steelvalves, stainless steel piping, stainless steel orifices, stainless steel pump casings, stainless steelfilter housings, and stainless steel tanks that have an internal environment of treated anduntreated borated water which require aging management review per 54.4(a)(2). There are heatexchangers for the spared-in-place evaporators that have component cooling water supplied tothem, but these are now either normally isolated by valves or in locations that their failure cannotimpact safety-related equipment. (Ref. 5, 7, 8, 11)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the system is supplied from low temperature sourcesand is below the 140 OF threshold for this effect. Loss of material is not an aging effect requiringmanagement for the external stainless steel surfaces due to the inherent corrosion resistance ofstainless steel.

Cracking from fatigue is not an aging effect requiring management since the portions of thesystem in the 54.4(a)(2) scope operate at temperature below the threshold for fatigue.

3.55 Miscellaneous (MISC!

The purpose of the miscellaneous system is to provide a system code for site equipment thatneeds to be entered into the site database for work tracking, etc. but does not belong to anyexisting system. This includes some work cranes and hoists and the backup diesel generator forthe generation support building. These components do not require aging management review per54.4(a)(2) since there are no passive mechanical components in safety-related structures in thissystem code.

3.56 Meteorological Tower (MET)

The purpose of the meteorological tower system is to provide meteorological data to the site forboth normal operation and following an accidental release of radioactive material. The systemincludes a backup power generator that is a mechanical component. These components do notrequire aging management review per 54.4(a)(2) since there are no passive mechanicalcomponents in safety-related structures in this system code.

3.57 Main Steam (MS)

The main steam system supplies the steam from the steam generators to the main turbine andsecondary plant components and is shown primarily on the M-2202 series of drawings. The

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safety-related components are reviewed in the main steam system aging management reviewreport 02-R-2005-19. There are nonsafety-related passive mechanical that are not reviewed inreport 02-R-2005-19 that require aging management review per 54.4(a)(2) including carbon steelvalves, carbon steel piping, stainless steel tubing and stainless steel valves. The internalenvironment is steam or treated water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion (including FAC) and MIC (in low temperature portions) is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is anaging effect requiring management since the system operates above the 140 OF threshold for thiseffect. Loss of material is not an aging effect requiring management for the external stainlesssteel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management since the system operates attemperatures above the threshold for fatigue.

3.58 Nitrogen SUPlV (N2)

The nitrogen supply system provides dry nitrogen gas to site components. The safety-relatedcomponents that have a safety function related to the containment penetrations (mechanical andelectrical) are reviewed in the containment penetrations aging management review report (02-R-2005-06). This system does not require aging management review per 54.4(a)(2) since it onlycontains dry gas. (Ref. 5, 8)

3.59 Neutralizing Tank (NT)

This system neutralizes acidic water as necessary for water chemistry and allowable releases.The passive mechanical components are primarily in the turbine building except for a portion ofpiping that is blanked off. Since there are no passive mechanical components in areas that couldaffect the Unit 2 safety-related components, this system does not require aging managementreview per 54.4(a)(2). (Ref. 5, 8)

3.60 Reactor Building Purge Air (PA)

The reactor building purge air can be used to provide fresh air to the containment for personnelaccess such as prior to plant outages. The safety-related components are reviewed in thecontainment cooling system aging management review report 02-R-2005-04. This system doesnot require a review per 54.4(a)(2) since it only contains dry air. (Ref. 5, 8)

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3.61 Post Accident Sampling System (PASS)

This system was intended to be utilized to perform post accident sampling of the RCS and therecirculated water is shown primarily on M-2237 sheet 4. Many of the components are in thePASS building, and therefore do not require a review since they cannot impact safety-relatedcomponents. The passive mechanical nonsafety-related components in the auxiliary buildinginclude stainless steel piping, stainless steel pump casings, stainless steel heat exchanger(radiator type), stainless steel valves, and stainless steel tubing exposed to an environment ofuntreated borated water and treated borated water. The portions of the systems that areconnected to hot systems could experience elevated temperatures. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operates above the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect for the portions the system that operates at temperaturesabove the 270 OF threshold for fatigue.

3.62 Plant Heatin2 (PH)

The plant heating system provides hot water for area heating in various buildings at the ANO siteand is shown on the M-2220 series of drawings. This system includes safety-related componentsat the containment penetration that are reviewed in the containment penetrations agingmanagement review report 02-R-2005-06. The nonsafety-related passive mechanicalcomponents that require review for 54.4(a)(2) include carbon steel piping, carbon steel (includingcast iron) valves, carbon steel and stainless steel filter (strainer) housings, carbon steelthermowells, copper alloy piping and copper alloy valves with an internal environment of treatedwater. (The heat exchangers are in system ABHV.) (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion, selectiveleaching (on cast iron) and MIC (in low temperature portions) is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion, erosion, selective leaching and MIC isan aging effect requiring management for the copper alloy component internal surfaces. Loss ofmaterial is not an aging effect requiring management for the external copper alloy surfaces in airdue to the inherent corrosion resistance of copper.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is an

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aging effect requiring management for the portions of the system that operate above the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.


3.63 Plant Makeup (PMU)

The plant makeup system is a nonsafety-related system that provides demineralized water forplant use and is shown on the M-2212 series of drawings. There are no passive mechanicalcomponents in this system in areas that contain safety-related equipment, therefore this systemdoes not require aging management review per 54.4(a)(2). (Ref. 5, 8)

3.64 Primary Sampling (PS)

The primary sampling system collects samples from the RCS and auxiliary systems as shown onthe M-2237 series of drawings and brings them to a common location in the sample room in theauxiliary building for analysis. The system components that are part of the RCS pressureboundary are reviewed in the RCS aging management review report 02-R-2005-01. Thecomponents that are part of the ECCS pressure boundary are reviewed in the ECCS agingmanagement review report 02-R-2005-02. Components that are part of a containment isolationpressure boundary are included in the containment penetration aging management review report02-R-2005-06. The nonsafety-related passive mechanical components that require agingmanagement review per 54.4(a)(2) include stainless steel piping, stainless steel valves, carbonsteel with stainless steel clad filter housings, stainless steel pump casings, stainless steel tank(sample cylinder),carbon steel heat exchanger shell, carbon steel valves, and carbon steel pipingthat contain an internal environment of treated water and treated borated water. The heatexchanger shell is cooled by CCW, which is treated water. (Ref. 5,7,8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operates above the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion and MIC is an aging effect requiring management for the carbon steel internal surfaces.Loss of material due to general corrosion is an aging effect requiring management for theexternal carbon steel surfaces.

Cracking from fatigue is an aging effect requiring management for the portions of the system thatoperate at a temperature above the thresholds for fatigue.

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3.65 Reactor Building (RB)

In the ANO-2 component database there are passive mechanical components under the systemcode of reactor building (RB). The passive mechanical components are safety-related valves atsome of the penetrations and the penetrations themselves. These safety-related components arereviewed in containment penetration aging management review report 02-R-2005-06 and thecontainment building structural AMERR 02-R-2006-01. There are no additional nonsafety-relatedpassive mechanical components in this system code. Therefore, no aging management review isrequired per 54.4(a)(2).

3.66 Reactor Building Heating and Ventilation (RBHV)

The purpose of the reactor building heating and ventilation system is to provide cooling andheating to the containment building during power operation, plant shutdown or accidentconditions. The system provides cooling under accident conditions. The safety-relatedcomponents in the cooling system are reviewed in the containment cooling aging managementreview report 02-R-2005-04. The cooler housings will prevent a failure of the nonsafety-relatedcooling coils (2VCC-1A, B, C, D, shown on M-2222 sheet 2) from impacting safety-relatedequipment. The safety-related containment air cooler housings are reviewed in the containmentcooling aging management review report. The portions of the system that contain only air do notrequire review since they cannot affect safety-related components. (Ref. 5, 7, 8)

The radiator type area heaters (2VUH-46, 47, 48, 49, 50, 51,52, 53,-see M-2222 sheet 2) aresupplied by plant heating water if heating is required. The supply to these heaters is lockedclosed during normal plant operation and the penetration is drained. Therefore these componentsdo not require aging management review per 54.4(a)(2). (Ref. 6)

The CEDM shroud cooling coils (2VCC-16A, B, C, D, see M-2222 sheet 2) are supplied bychilled water and are internal to unit housings. The unit housings (2VSF-35A, B, C, D- see M-2261 sheet 1) are therefore included in this aging management review since the housings willprevent the coil failure from spraying on safety-related equipment. The housings are carbon steelwith an internal environment of air and condensation.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,and MIC is an aging effect requiring management for the carbon steel housing internal surfacesof the CEDM cooling units. Loss of material due to general corrosion is an aging effect requiringmanagement for the housing external carbon steel surfaces of the CEDM cooling units.

Cracking from fatigue is not an aging effect requiring management since the system operates attemperatures below the thresholds for fatigue.

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3.67 Reactor Coolant Pump System (RCP)

The purpose of the reactor coolant pump system is to provide the motive force to circulate thereactor coolant through the reactor coolant system. This system code includes the reactor coolantpumps that are safety-related and a part of the reactor coolant system Class 1 pressure boundary,the reactor coolant pump motors, the reactor coolant pump oil system components, and portionsof the reactor coolant pump oil leakage collection system. The system is shown primarily on M-2230 sheet 1, M-2233, and M-2238. The safety-related passive mechanical components of theRCS are reviewed in the RCS aging management review report 02-R-2005-01. The RCP lube oilleakage collection components that are required for 50.48 are reviewed in engineering report 02-R-2005-12. The nonsafety-related passive mechanical lube oil components do not require areview since they would not impact safety-related equipment other than the RCP and theirleakage would be collected by the oil leakage collection system. There are nonsafety-relatedstainless steel, piping and valves, and a filter housing in this system code primarily in the sealcavity vents and bleedoffs that have an internal environment of treated borated water and requirea review for 54.4(a)(2).

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operate above the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is not an aging effect requiring management since the portions of thesystem that require a review per 54.4(a)(2) operate at a temperature below the 270 OF thresholdfor fatigue of stainless steel.

3.68 Reactor Coolant System (RCS)

The purpose of the reactor coolant system is to circulate water in a closed cycle, removing heatfrom the reactor core and internals and transferring it to the steam generators. The safety-relatedcomponents of the RCS are reviewed in the RCS aging management review report 02-R-2005-01. The RCP lube oil collection components that are required for 50.48 are reviewed inengineering report 02-R-2005-12. The nonsafety-related RCS components that are not reviewedin the RCS aging management review report include the reactor coolant pump motors lube oilcomponents and motor coolers, the hot leg level instrumentation tubing and valves, and thequench tank and associated vent, drain, and supply equipment. Each of these subsystems arereviewed against the 54.4(a)(2) criteria below. (Ref. 5, 8)

The reactor coolant pump motor coolers are internal to the reactor coolant pump motors and theirfailure would not impact safety-related equipment. The lube oil system has a leakage collectionsystem reviewed in engineering report 02-R-2005-12 that would collect and store lube oilleakage and prevent impact to safety-related equipment. Therefore, these components do notrequire aging management review per 54.4(a)(2). (Re. 5, 8)

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The hot leg level instrumentation tubing and valves included in this system code require agingmanagement review per 54.4(a)(2). The quench tank and the associated passive mechanicalcomponents require aging management review per 54.4(a)(2). The hot leg instrumentation, thequench tank, the associated piping and valves are stainless steel and contain an internalenvironment of treated water and treated borated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operate above the 140 DFthreshold for this effect. (The quench tank can be heated during the creation of a bubble in thepressurizer.) Loss of material is not an aging effect requiring management for the externalstainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is not an aging effect requiring management since the portions of thesystem that require a review per 54.4(a)(2) operate at a temperature below the 270 OF stainlesssteel threshold for fatigue.

3.69 Radiological Dose Assessment Computer (RDAC)

The purpose of the radiological dose assessment computer system is to monitor variouspotentially radioactive ventilation systems such as the containment purge system for radioactivityand utilizes super particulate iodine and noble gas (SPING) monitors. This system is one of theradiation monitoring systems at ANO and has shared components between ANO-1 and ANO-2.There are nonsafety-related passive mechanical components in the database for this systemincluding blower casings, piping, valves, etc. However, these components only contain air andtherefore do not require a review per 54.4(a)(2).

3.70 Radiation Monitoring Svstem (RMS)

The purpose of the radiological monitoring system is to monitor various potentially radioactiveprocess systems. There are nonsafety-related passive mechanical components included in thedatabase for this system including blowers, piping, valves, filters etc. Many of these contain airsince they are sampling purge air or HVAC systems and therefore do not require a review for54.4(a)(2). There are no nonsafety-related passive mechanical components that contain water instructures that contain safety-related equipment. The radiation monitors themselves areconsidered instruments and the equipment is internal to cabinets so that leakage could not affectother components. Therefore no review of these components is required for 54.4(a)(2).

3.71 Reheat Steam (RS)

The reheat steam system supplies steam to the feedwater heaters for secondary plant condensateand feedwater heating. All passive mechanical components for this system are in the turbine



building where their failure cannot impact safety-related equipment. Therefore, no agingmanagement review is required per 54.4(a)(2). (Ref. 5, 8)

3.72 Resin Transfer (RT)

The resin transfer system transfers resin for the demineralizers and is shown primarily on the M-2213 series of drawings. The passive mechanical components in the system that require agingmanagement review per 54.4(a)(2) include stainless steel valves and piping that are exposed to aninternal environment of untreated water (water with resin) that may contain boron. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is notan aging effect requiring management since the system is expected to operate below the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is not an aging effect requiring management since the system operates attemperatures below the 270 OF stainless steel threshold for fatigue.

3.73 Radwaste Building (RWB)

In the ANO-2 component database there are passive mechanical components under the systemcode "Radwaste Building". These components are all in areas that do not contain safety-relatedequipment, therefore an aging management review of this system's components is not requiredper 54.4(a)(2).

3.74 Reactor Core Svstem ()

The RX system consists of the reactor core, the reactor control element assemblies including thepart length control element assemblies and the reactor internals consisting of the core supportstructure, the upper guide structure, and the incore instrumentation supporting structure. Allpressure boundary components of the RCS are reviewed in the RCS aging management reviewreport 02-R-2005-01. There are no nonsafety-related passive mechanical components in thissystem code. Therefore, no aging management review is required of this system per 54.4(a)(2).(Ref. 5, 8)

3.75 Regenerative Waste (RZ)

The regenerative waste system processes and regenerate the radioactive waste water for ANO-2.Many components are shown on the M-2226 series of drawings, but the system extends to otherP&IDs. A large portion of this system is not used and is not subject to aging managementreview. (Ref. 22) The passive mechanical components in the system that require agingmanagement review for 54.4(a)(2) include stainless steel valves, stainless steel pump casings,

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ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2ReSE 200301-1


stainless steel piping and tubing, stainless steel orifices, carbon steel piping and carbon steelvalves that will be conservatively considered to have an internal environment of untreated waterand untreated borated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGAISCC is notan aging effect requiring management since the system is expected to operate below the 1400Fthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion, galvaniccorrosion, and MIC is an aging effect requiring management for the carbon steel componentinternal surfaces. Loss of material due to general corrosion is an aging effect requiringmanagement for the external carbon steel surfaces.


3.76 Service Air (SA)

The service air system provides compressed air to plant components. This system does notrequire aging management review per 54.4(a)(2) since it only contains air in buildings thatcontain safety-related equipment. (There is a water-cooled heat exchanger in this system code,but it is in the turbine building.) (Ref. 5, 8)

3.77 Shutdown Cooling (SDC)

The shutdown cooling system is placed in service during plant cooldowns to remove decay heat.Some of the system components are also utilized for emergency core cooling. The safety-relatedcomponents of this system are reviewed in the ECCS aging management review report 02-R-2005-02. There are passive mechanical nonsafety-related components that are not reviewed inreport 02-R-2005-02 on some portions of the system such as the purification loop and thedischarge of some relief valves. The passive mechanical components that require agingmanagement review for 54.4(a)(2) are stainless steel valves and piping and have an internalenvironment of treated borated water. (Ref. 5, 7, 8)

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management since the system may operate during SDC operation abovethe 140&F threshold for this effect. Loss of material is not an aging effect requiring managementfor the external stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

*!

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Components Affecting Safety-related Systems Page 42 of 77Cracing rom atiue i an gingeffct rquirng mnagmentfor ompoent tha opeat at

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Cracking from fatigue is an aging effect requiring management for components that operate attemperature above the threshold for fatigue.

3.78 Security System (SEC)

The purpose of the security system is to provide industrial security for the plant site and consistsprimarily of doors, access hatches, camera, panels, readers, etc. The system contains submersiblesump pumps (P-206, 7, 8, 12, 13, 14) inside of security system electrical manholes in the yard (asshown on M-2225 sheet 1), but these components are not in areas where their failure could affectsafety-related equipment and therefore do not require aging management review per 54.4(a)(2).There is a security diesel fuel oil pump in this system code and some air conditioning units forsecurity areas, but these components are not in areas where their failure could affect safety-related equipment and therefore do not require aging management review per 54.4(a)(2). Inaddition, there are two small cabinet cooling air conditioning units in the auxiliary building, butthese do not contain liquids that could leak onto safety-related equipment. Therefore, this systemdoes not require aging management review per 54.4(a)(2). (Ref. 5,8)

3.79 Spent Fuel Pool (SFP)

This system code includes the spent fuel pool racks and one vent valve for the cask pit. Thepassive mechanical components (the valve and the associated piping) are reviewed in the SFPcooling system aging management review report 02-R-2005-07. Therefore, this system does nothave passive mechanical components that require aging management review per 54.4(a)(2).(Ref. 5, 8)

3.80 Steam Generator Secondary / Blowdown (SGS)

This system includes instruments for steam generator level and pressure as well as some of thecomponents in the steam generator blowdown system (see system BD for other blowdownsystem components). The safety-related steam generator instrumentation piping and valves arereviewed in the main steam and main feedwater aging management review reports 02-R-2005-19and 20. Some of the nonsafety-related components are in the turbine building and do not requireaging management review since their failure cannot affect safety-related equipment. Thenonsafety-related components in the steam generator secondary (SGS) system code that requireaging management review per 54.4(a)(2) are shown on M-2206 sheet 2 and include carbon steelvalves, carbon steel piping, and carbon steel filter housings with an internal environment oftreated water. (Ref. 5, 7,8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion (includingFAC in susceptible portions) and MIC (in low temperature portions) is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-MEi2003-001-1


Cracking from fatigue is an aging effect requiring management for the portions of the system thatoperate at temperatures above the threshold for fatigue.

3.81 Sampling System (SS)

The sampling system draws samples from various plant systems. Many components are shownon the M-2237 series of drawings, but the system extends to other P&lDs. The safety-relatedsystem components that are part of containment penetrations are reviewed in the containmentpenetrations aging management review report 02-R-2005-06. The nonsafety-related systemcomponents that are in structures that contain safety-related equipment and have an internalenvironment of liquid and therefore require aging management review per 54.4(a)(2) includestainless steel valves, stainless steel piping and tubing, stainless steel pump casings, heatexchangers with carbon steel shells, carbon steel valves, and carbon steel piping. The internalenvironment is treated water, and in some portions of the system it may be treated borated water.(Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion and MIC (in low temperature portions) is an aging effect requiring management for thecarbon steel component internal surfaces. Loss of material due to general corrosion is an agingeffect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is anaging effect requiring management for the portions of the system that operate above the 140 OFthreshold for this effect. Loss of material is not an aging effect requiring management for theexternal stainless steel surfaces due to the inherent corrosion resistance of stainless steel.

Cracking from fatigue is an aging effect requiring management for the portions of the system thatoperate at temperatures above the thresholds for fatigue.

3.82 Sewage Treatment Plant (STPJ

The sewage treatment plant system process the site wastewater. This system does not includeany passive mechanical components in areas that contain safety-related equipment. Therefore,this system does not require aging management review per 54.4(a)(2). (Ref. 5, 8)

3.83 Startup Boiler (SUI

The startup boiler provides steam when the plant is shutdown for various purposes. This systemdoes not include any passive mechanical components in areas that contain safety-relatedequipment. Therefore, this system does not require aging management review per 54.4(a)(2).(Ref. 5, 8)

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2RMEs2003i01-1


3.84 Service Water (SW)

The service water system provide cooling water from Lake Dardanelle or the emergency coolingpond to cool safety-related and nonsafety-related equipment and provides an emergency supplyof water to the emergency feedwater and the fuel pool systems. The safety-related componentsare reviewed in the service water aging management-review report 02-R-2005-16. Thenonsafety-related system components that are in structures that contain safety-related equipmentand have an internal environment of liquid include stainless steel valves, stainless steel orifices,stainless steel piping, stainless steel tubing, carbon steel valves, and carbon steel piping. Theinternal environment is raw water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, galvanic corrosion,erosion and MIC is an aging effect requiring management for the carbon steel component internalsurfaces. Loss of material due to general, pitting and crevice corrosion is an aging effectrequiring management for the external carbon steel surfaces due to the potential forcondensation.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the portions of the system in the 54.4(a)(2) reviewoperate below the 140 OF threshold for this effect. Loss of material due to pitting and crevicecorrosion is an aging effect requiring management for the external stainless steel surfaces due tothe potential for condensation.


3.85 Generator Stator Cooling (SWO)

The stator cooling water system provides cooling water for the main generator stator. Thissystem does not have any passive mechanical components in areas that contain safety-relatedequipment. Therefore, this system does not require aging management review per 54.4(a)(2).(Ref. 5,8)

3.86 Spent Resin (SZ)

This system contains components for the transfer of resin to and from the site demineralizers andis shown primarily on the M-2224 drawing. The system nonsafety-related passive mechanicalcomponents that are in structures that contains safety-related equipment and have an internalenvironment of liquid include stainless steel valves, stainless steel piping, stainless steel tubing,stainless steel filter housings, stainless steel pump casings, stainless steel tanks, carbon steel(including cast) valves, carbon steel piping, and carbon steel (including cast) pumps (some

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ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-MEv2003 001-1


carbon steel components are lined). The internal environment is conservatively considereduntreated water. (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion, galvaniccorrosion, selective leaching (for cast components) and MIC is an aging effect requiringmanagement for the carbon steel component internal surfaces. Loss of material due to generalcorrosion is an aging effect requiring management for the external carbon steel surfaces.

Loss of material from pitting corrosion, crevice corrosion and MIC is an aging effect requiringmanagement for the stainless steel component internal surfaces. Cracking from IGA/SCC is notan aging effect requiring management since the portions of the system in the 54.4(a)(2) reviewoperate below the 140 OF threshold for this effect. Loss of material is not an aging effectrequiring management for the external stainless steel surfaces due to the inherent corrosionresistance of stainless steel


3.87 Turbine Building Sump (TBS)

This system provides the floor drains for components in the turbine building and the EFW andEDG rooms. Although the majority of this system is in the turbine building, there are somenonsafety-related carbon steel (cast iron) drain piping, carbon steel (cast iron) valves included inthis system code in the safety-related areas with an internal environment of untreated water thatrequire a review for 54.4(a)(2). (Ref. 5, 7, 8)

Loss of material from general corrosion, pitting corrosion, crevice corrosion, erosion, selectiveleaching (for cast iron components) and MIC is an aging effect requiring management for thecarbon steel component internal surfaces. Loss of material due to general corrosion is an agingeffect requiring management for the external carbon steel surfaces.


3.88 Turbine Building Ventilation (TBV)

This system provides ventilation to the turbine building. This system does not require a reviewper 54.4(a)(2) since it only contains dry air in areas that contain safety-related equipment. Thereare some cooling and heating coils in this system code that contain water, but these water filledcomponents are in the turbine building and therefore cannot affect safety-related components.(Ref. 5, 8)

ANO.2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and -ev203-o 11


3.89 Turbine Generator (TG)

This system contains components that support the turbine generator that is in the turbinebuilding. This system does not require a review per 54.4(a)(2) since there are no passivemechanical components in areas containing safety-related equipment. (Ref. 5, 8)

3.90 Traveling Screen Wash (TS)

The traveling screen wash system for ANO-2 is the piping and valves from the Unit 1 spray washsystem that supplies spray water to the Unit 2 traveling water screens. This system does notrequire a review per 54.4(a)(2) since there are no passive mechanical components in areascontaining safety-related equipment that have the potential to adversely affect safety-relatedequipment. (Ref. 5, 8, 19)

3.91 Ventilation System (VENT)

This system code includes miscellaneous ventilation components such as the alternate ACbuilding ventilation, the administrative building ventilation, the penetration room ventilation, andventilation for many of the outbuildings on the site. The alternate AC building ventilationcomponents that are required for AAC diesel operation are reviewed as a part of the alternate ACaging management review report 02-R-2005-11. This system does not require a review per54.4(a)(2) since there are no passive mechanical components containing liquids in areascontaining safety-related equipment. (Ref. 5, 8)

3.92 Condenser Vacuum System (VS)

This system helps to initiate and maintain the vacuum on the main condenser in the turbinebuilding. The majority of the components including water cooled heat exchangers are in theturbine building and their failure cannot impact safety-related equipment. This system does notrequire a review per 54.4(a)(2) since there are no passive mechanical components containingliquids in areas containing safety-related equipment. (Ref. 5, 8)

3.93 Bolting

Pressure-retaining bolting in these systems maybe carbon steel or stainless steel. Forconservatism, loss of material is identified as an aging effect requiring management for carbonsteel bolting.

Stainless steel bolting will not experience general or pitting/crevice corrosion in a dryenvironment. Loss of material from pitting and crevice corrosion is identified as an aging effectrequiring management for stainless steel bolting if significant condensation can be present.



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Il

The components in these systems are not exposed to vibration such as from a diesel engine. Lossof material from boric acid corrosion of the carbon steel bolting is possible only when boric acidis present. Loss of pre-load or cracking from thermal effects is possible in systems where theoperating temperatures are high. Therefore, loss of mechanical closure integrity is an agingeffect requiring management for the bolted closures exposed to borated water or elevatedtemperatures.

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4.0 Demonstration that Aging Effects Are Managed

Section 2.0 described the method for determining the liquid/steam filled systems or portions ofsystems requiring a review per 54.4(a)(2) and the corresponding typical components that aresubject to aging management review. For those components, Section 3.0 documenteddetermination of possible aging effects requiring management. The aging management review iscompleted by demonstrating that existing programs, when continued into the period of extendedoperation, can manage the aging effects identified in Section 3.0. No further action is requiredfor license renewal when the evaluation of an existing program demonstrates that it is adequate tomanage the aging effect such that corrective action maybe taken prior to loss of the systemintended functions. Alternately, if existing programs cannot be shown to manage the agingeffects for the period of extended operation, then action is proposed to augment existing or createnew programs to manage the identified effects of aging.

Demonstration for the purposes of the aging management review is accomplished by establishinga clear relationship among:

1) the components under review,

2) the aging effects on these items caused by the material-environment-stress combinationswhich, if undetected, could result in the loss of the intended function such that thesystem could not perform its function(s) within the scope of license renewal in the periodof extended operation, and

3) the credited aging management programs whose actions serve to preserve the systemintended function(s) for the period of extended operation.

As documented in section 2.0, the systems requiring a review per 54.4 (a)(2) include thosenonsafety-related systems with the potential for spatial interactions that could prevent theaccomplishment of safety functions performed by safety-related systems. Passive long-livedcomponents performing an intended function within these systems are subject to agingmanagement review. A review of aging management programs for SCs subject to agingmanagement review for spatial interaction is provided below.

The results of the aging management review are that the following aging management programsare adequate to manage the effects of aging for systems requiring a review per 54.4(a)(2):

* Boric Acid Corrosion Prevention Program* Flow Accelerated Corrosion Program* System Walkdown Program* Water Chemistiy Control Program* Bolting and Torquing Activities

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ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and REvisio* 1

Components Affecting Safety-related Systems Re 49soon

If future operating experience indicates that the above programs are not adequate, then thecorrective action program will lead to appropriate program enhancements or additional programsin order to effectively manage the effects of aging.

Sections 4.1 through 4.5 discuss these programs and provide the clear relationship between thecomponent, the aging effect and the aging management program action(s) which preserve theintended function(s) for the period of extended operation. Section 4.6 discusses time-limitedaging analyses associated with 54.4(a)(2) systems. For a comprehensive review of the programscredited for the license renewal of ANO-2 and a demonstration of how these programs willmanage the aging effects, see engineering report A2-EP-2002-002, Evaluation of AgingManagement Programs.

4.1 Water Chemistry Control Proaram

Many of the systems have treated water as an environment where water chemistry is monitoredas a part of the Water Chemistry Control Program. The Water Chemistry Control Program isonly listed in Attachment 2 for the purpose of documenting that the program can aid in managingloss of material and cracking for systems containing treated water. The System WalkdownProgram is the aging management program that is primarily credited for managing loss ofmaterial and cracking in treated water systems. For additional information on the WaterChemistry Control Program, see engineering report A2-EP-2002-002, Evaluation of AgingManagement Programs.

42 Boric Acid Corrosion Prevention Program

The Boric Acid Corrosion Prevention Program was established to reduce leakage and corrosionfrom borated water. This program will manage the loss of material from boric acid corrosion ofthe bolting. This program is also credited with managing the aging effect of loss of mechanicalclosure integrity for bolted closures that may be exposed to borated water if leakage occurs. Foradditional information on the Boric Acid Corrosion Prevention Program, see engineering reportA2-EP-2002-002, Evaluation of Aging Management Programs.

4.3 System Walkdown Program

Operating experience indicates that routine walkdowns, in conjunction with a flow acceleratedcorrosion prevention program, provide reasonable assurance that leaks from nonsafety-relatedSCs do not progress to the point of impacting the ability of safety-related SCs to performrequired safety functions. The waLlcdowns performed under the System Walkdown Program willdetect leakage and spray from liquid-filled low-energy systems before it could impact theperformance of safety-related equipment. Follow-up actions will direct leakage away fromequipment and take corrective actions which will prevent failure. The System WalkdownProgram manages the aging effects of loss of material and cracking due to SCC/IGA for allcomponents, loss of mechanical closure integrity on bolted closures, and cracking due to thermal

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-ME2003-001-1


fatigue on components subjected to high temperatures. For additional information on the SystemWalkdown Program, see engineering report A2-EP-2002-002, Evaluation of Aging ManagementPrograms.

4.4 Flow Accelerated Corrosion Program

Industry operating experience has shown that age-related failures of nonsafety-related SCscontaining steam or liquid that could prevent safety-related components from accomplishing theirsafety function have only occurred as a result of flow accelerated corrosion (FAC). FACprograms manage loss of material due to FAC to prevent failures. The Flow AcceleratedCorrosion Program is credited with managing the loss of material from the componentssusceptible to FAC as identified on Attachment 2. For additional information on the FlowAccelerated Corrosion Program, see engineering report A2-EP-2002-002, Evaluation of AgingManagement Programs.

4.5 Bolting and Torguing Activities

Bolting and Torquing Activities are credited with preventing loss of mechanical closure integrityfor the bolted closures exposed to high temperatures. For additional information on Bolting andTorquing Activities, see engineering report A2-EP-2002-002, Evaluation of Aging ManagementPrograms.

4.6 Metal Fatigue TLAA

Engineering report A2-EP-2002-005 documents evaluation of components in systems thatrequire a review per 54.4(a)(1) or (a)(3) and are subject to metal fatigue. The evaluationsperformed in A2-EP-2002-005 are applicable to the additional nonsafety-related components thatcan affect safety-related SSC and are in these same systems since they are the same material andenvironment combinations.

The walkdowns performed as a part of the System Walkdown Program will manage cracking dueto fatigue on components in the systems that only require a review for 54.4(a)(2). The SystemWalkdown Program will detect leakage and spray from liquid filled low energy systems as aresult of cracking before it could impact the performance of safety-related equipment. Follow-upactions will direct leakage away from equipment and take corrective actions which will preventits failure. As a result a fatigue evaluation is not required for these components.

ANO-2 License Renewal Project Engineering ReportA2-ME-2003-001-1Aging Management Review of Nonsafety-related Systems and Revision 1


5.0 Summary and Conclusions

This report documents the review of systems at ANO-2 in order to determine which systemsrequire aging management review per 54.4(a)(2). The results of this review are documented inAttachment 1. Based on this scoping review, the systems with components requiring review for54.4(a)(2) were further evaluated in order to identify the aging effects for the components thatrequired a review. Section 4 then identified what aging management programs would managethe effect of aging that were identified. Attachment 2 contains the aging management reviewresults for the components types in the systems in scope for 54.4(a)(2). The following agingmanagement programs address the aging effects that require management for the nonsafety-related SC that can affect safety-related SC.

* Boric Acid Corrosion Prevention Program* Flow Accelerated Corrosion Program* System Walkdown Program* Water Chemistry Control* Bolting and Torquing Activities

For additional information on the programs credited for the license renewal of ANO-2, seeengineering report A2-EP-2002-002, Evaluation of Aging Management Programs.

In conclusion, the programs described in Section 4.0 will provide reasonable assurance that theeffects of aging on the ANO-2 passive mechanical nonsafety-related components will not causefailures could prevent safety-related SSCs from accomplishing required safety functionsconsistent with the current licensing basis throughout the period of extended operation.

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6.0 References

1. EPRI Report 1003056 Non-Class I Mechanical Implementation Guideline andMechanical Tools- Revision 3

2. Engineering report LRPG-01, License Renewal Project Plan3. Engineering report 02-R-2008-01, System and Structure Scoping Method and Results4. A2-EP-2002-003-0, Operating Experience Review5. Piping & Instrument Diagrams, M-2200 series6. Procedure 1106.017, Plant Heating7. ANO Piping Specification M-2555, Rev. 1, Unit 2 Piping Class Sheets8. ANO-2 WMS Component Database9. ANO-2 SAR 11.2.210. TD M387.0020, Instruction Manual for the Letdown Heat Exchanger11. NES-13, Environmental Qualification- Environmental Service Conditions12. Procedure 2104.028, Component Cooling Water System Operations13. NRC Generic Letter 88-14, Instrument Air System Supply Problems Affecting Safety-

Related Equipment14. NRC I.E. Notice 81-38, Potentially Significant Equipment Failures Resulting From

Contamination of Air-Operated Systems15. NRC I.E. Notice 87-28, Air Systems Problems at U.S. Light Water Reactors16. NRC I.E. Notice 99-01, Deterioration of High Efficiency Particulate Air Filters in a

Pressurized Water Reactor Containment Fan Cooler Unit17. NUREG 0800 Appendix C Rev. I, Plant Design for Protection Against Postulated Piping

Failures in Fluid Systems Outside Containment18. EPRI Report # TR-114881, Aging Effects for Structures and Structural Components

(Structural Tools), BWOG Generic License Renewal Program, BAW-2279P, 199719. Walkdown report for ANO-2 54.4(a)(2) waclkdowns (see Attachment 4)20. NEI Letter, to Dr. P.T. Kuo from Alan Nelson, February 24, 2003, Industry Guidance on

Revised 54.4 (a) 2 Scoping Criterion (Non-Safety Affecting Safety)21. Drawing M-2511 Sh. J-G100-1 Rev. 10, Instrument Piping Class Specification22. ULD-2-SYS-41, Rev. 2, ANO-2 Liquid and Gaseous Radwaste Systems23. Correspondence from Grimes (NRC) to Nelson (NEI), Guidance on the Identification

and Treatment of Structures, Systems, and Components which Meet 10 CFR 54.4(a)(2),dated March 15,2002

24. Correspondence from Grimes (NRC) to Nelson (NEI), License Renewal Issue: Scopingof Seismic II/I Piping Systems, dated December 3,2001.

25. NUREG CR-6239 Survey of Strong Motion Earthquake Effects on Thermal PowerPlants in California with Emphasis on Piping Systems

26. ANO-2 SAR, Amendment 17, Section 3.6, Protection Against Dynamic EffectsAssociated With The Postulated Rupture of Piping

, I



. Attachment 1- System Scoping Results

AAC Alternate AC Generator

ABHV Auxiliary Building Heating and Ventilation X

ABS Auxiliary Building Surnp X

AC Chilled Water X

ACW Auxiliary Cooling Water X

ADHV Administration Building Heating andVentilation

AS Auxiliary Steam . X

BA Breathing Air

BD Startup and Blowdown Demineralizers X

BMS Boron Management X

BS Containment Spray X

CA Chemical Addition X

CCW Component Cooling Water X

CED.M Control Element Drive Mechanisms

C02/CRDX Carbon Dioxide

CPV Containment Penetration Room Ventilation

CRV Control Room Ventilation

Cs Condensate

CT Condensate Storage and Transfer X

CVCS Chemical and Volume Control X

CVH Containment Vent Header

CW Circulating Water X

DCH Drain Collection Header X

DFS Dry Fuel Storage

DW Domestic Water X

ED Diesel Fuel Services

EDG EmergencyDiesel Generator

EFW Emergency Feedwater X

EHC Electro-Hydraulic Control

EOF Emergency Operations Facility

EX Extraction Steam

FH/FHS Fuel Handling

FO Fuel Oil

FP Fuel Pool Cooling and Purification X

FS Fire Protection (Water) X

'I

ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and A2-Me-200s001-1


Attachment 1- System Scoping Results

FW Feedwater X

GCH Gas Collection Header

GG Generator Gas

GS Gland Steam I Exhaust Steam

GSO Generator Seal Oil

GZ Gaseous Radwaste

H2 Hydrogen Supply (Generator)

HAL Halon System

HD Heater Drains

HPA Hydrogen Purge

HPSI High Pressure Safety Injection

LA Instrument Air

IBc Isophase Bus Cooling

IS Intake Structure

LLRB Low Level Radwaste Building

LO Lube Oil

LPSI LowPressure Safety Injection X

LRBV Low Level Radwaste Building Ventilation

LRW Liquid Radwaste Management X

MISC Miscellaneous

MET Meteorological Tower

MS Main Steam X

N2 Nitrogen Supply e

NT Neutraliing Tank

PA Reactor Building Purge Air

PASS Post Accident Sampling System X

PH Plant Heating X

PMU Plant Makeup

PS Primay Sampling X

RB Reactor Building

RBHV Reactor Building Heating and Ventilation X

RCP Reactor Coolant Pump X

RCS Reactor Coolant System X

RDAC Radiological Dose Assessment Computer

RMS Radiation Monitoring System



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- -Attachment 1- System Scoping Results I

RS Reheat Steam

RT Resin Transfer X

RWB Radwaste Building

RX Reactor Core System .

RZ Regenerative Waste X

SA Service Air _

SDC Shutdown Cooling X

SEC Security System

SFP Spent Fuel Pool

SGS Steam Generator Secondary / Blowdown X

SS Sampling System X

STP Sewage Treatrnent Plant

SU Startup Boiler

SW Service Water XSWC Generator Stator Cooling

SZ Spent Resin XTBS Turbine Building Sunip X

TBV Turbine Building Ventilation

TG Tubine GeneratorTS Traveling Screen Wash

VENT Ventilation System

VS Condenser Vacuum Systemr

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Aging Management Review of Nonsarety-related Systems and Components Affecting Safety-related Systems Revision 7Page 56 of 77

Attachment 2- Aging Management Review Results

Component Commodity Intended Function Material Environment Aging Effect ProgramlActivityG rouping _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _

bolting pressure boundary carbon steel air (ext) loss of material Boric Acid CorrosionSystem Walkdown

loss of mechanical closure Bolting and Torquing Activitiesintegrity

Boric Acid Corrosioncondensation (ext) loss of material System Walkdown

stainless steel air (ext) loss of mechanical closure Bolting and Torquing Activitiesintegrity_ _ _ _ _ _ _ _ _

none none____________________ ________ condensation (ext) loss Of material System Walkdown I

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Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision Irage 57 of 77


Component Commodity Intended Function Material Environment Aging Effect ProgramlActivityG ro u p in g_ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

filter housing pressure boundary stainless steel air (cxt) none nonetreated water (int) loss of material System Walkdown

Water Chemistry Controltreated borated water (int) loss ofrmaterial System Walkdown

__ Water Chernistry Controlloss of material System Walkdown

treated borated water Water Chemistry Control> 140 OF (int) cracking System Walkdown

____ _Water Chemistry Controluntreated water (int) loss of material System Walkdownuntreated water (int) loss of material System Walkdown

> 140 OF cracking System Walkdownuntreated borated water loss of material System Walkdown

> 140 0F (int) cracking System Walkdowncarbon steel air (ext) loss of material System Walkdown

condensation (ext) loss of material System Walkdowncrackdng - fatigue SystemrWalkdown

treated water or steam loss of material System Walkdown>220 0F (int) Water Chemistry Control

loss of material - erosion Flow Accelerated Corrosiontreated water (int) loss of material System Walkdown

Water Chemistry Control

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CompoGnot lommodty Intended Function Material Environment Aging Effect Program/Activityfilter housing pressure boundary copper alloy air none none

condensation loss of material System Walkdown. fesh raw water(int) loss of material System WalkdownII


Aging Management Rcview of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision IPage 59 of 77


Component Commodity Intended Function Material Environment Aging Effect Prograni/ActlvityG roup ing_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

heat exchanger pressure boundary stainless steel air (ext) none none(shell, channel head) loss of material System Walkdown

treated borated water Water Chemistry Control> 140 F(int) cracking SystemrWalkdown

Water Chemistry Controlloss of material System Walkdown

treated borated water Water Chemistry Control> 270 F(int) cracking System Walkdown

Water Chemistry Controlcracking-fatigue System Walkdownloss of material System Walkdown

treated water (int) Water Chemistry Control> 140 F(int) cracking System Walkdown

. Water Chemistry Controluntreated borated water of material System Walkdown

_ _ _ _ _ _ _ _ _ _(int) lossof___terial_______________

copper alloy air (ext) none nonecondensation (cxt) loss of material SystemWalkdowntreated water (int) loss of material System Walkdown

._ Water Chemistry Controlcarbon steel air (ext) loss of material SystemnWalkdown

treated water (int) loss of material System Walkdown___ Water Chemistry Control

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Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision IPage 60 of 77


Component Commodity Intended Function Material Environment Aging Effect ProgramlActivityG ro u p in g _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

heat exchanger (heating or pressure boundary copper alloy air (ext) none nonecooling coil when not condensation (ext) loss of material System Walkdownenclosed in a housing)

treated water (int) loss of material System WalkdownWater Chemistry Control

stainless steel loss of material System Walkdowntreated borated water Water Chemistry Control

> 140 F(int) cracking System Walkdown.__ _Water Chemistry Control

level glass gauge pressure boundary glass air (ext) none none_ _ fresh raw water (hint) none none

orifice pressure boundary carbon steel air (ext) loss of material System Walkdownfresh raw water (int) loss of material System Walkdowntreated water (int) loss of material System Walkdown

Water Chemistry Controlloss of material System Walkdown

treated water or steam Water Chemistry Control>220 TF (int) cracking (fatigue) System Walkdown

loss of material- erosion Flow Accelerated Corrosion

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Component Commodity Intended Function Material Environment Aging Effect Program/ActivityG rouping_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

orifice pressure boundary stainless steel air (ext) none nonefresh raw water (int) loss of material System Walkdown

treated water or steam loss of material System Walkdown>270 TF (int) Water Chemistry Control

cracking System WalkdownWater Chemistry Control

cracking (fatigue) System Walkdowntreated borated water loss of material System Walkdown

(int) Water Chemistry Controltreated borated water loss of material System Walkdown

>140 0F (int) Water Cheistry Controlcracking System Walkdown

a Watmr ChemWistry Controltreated water (int) loss of material SystemrWalkdown

. Water Chemistry Controluntreated water (int) loss of material SytmWalkdown

untreated borated water loss of material SystemWalkdown_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ h~~in t)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Engineering ReportANO-2 License Renewal Project A2-ME,2003-001-1


Attachmcnt 2- Aging Management Review Results

Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGrouping

piping pressure boundary carbon steel air (ext) loss of material System Walkdown

condensation (ext) loss of material SystemWalkdownfresh raw water (int) loss of mnaterial System Walkdown

cracking - fatigue System Walkdownsteam or treated water loss of material System Walkdown

>220 TF (int) Water Chemistry Controlloss of material - erosion Flow Accelerated Corrosion


untreated water (int) loss of material System Walkdown

copper alloy air (ext) none nonecondensation (ext) loss of material System Walkdowntreated water (int) loss of material SystemWalkdown

___ Water Chemistry Control

. untreated water (int) loss of material SystemWalkdownpiping pressure boundary stainless steel air (ext) none none

condensation (ext) loss of material Systern Walkdownfresh raw water (int) loss of material System Walkdown

cracking - fatigue System Walkdownsteam or treated clacking System Walkdown

watet>270 op (int) Water Chemistry Controlloss of material System Walkdown

____ Water Chemisy Control

Engineering ReportANO-2 License Renewal Project A2MAWE.2003-001-1

Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision Ij Page 63 of 77


Component Commodity Intended Function Material Environment Aging Effect ProgramlActlvityGrouping _

piping pressure boundary stainless steel treated water (int) loss of material System Walkdown__ Water Chemistry Control

loss of material System Walkdowntreated water (int) Water Chemistry Control

> 140 OF cracking SystemWalkdown. Water Chemistry Control

treated berated water loss of material SystemWalkdown(int) Water Chemistry Control

loss of material System Walkdowntreated borated water Water Chemistry Control

>140 'F (int) cracking System WalkdownWater Chernistry Control

loss of material System Walkdowntreated berated water Water Chemistry Control

>270 OF (int) cracking System WalkdownWater Chemistry Control

cracking-fatigue System Walkdownuntreated water (int) loss of material System Walkdown

untreated water cracking System Walkdown>140 F (int)loss of material System Walkdown

untreated borated water loss of material System Walkdown_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(in t) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGrouping_ _ _ _ _ _ _ _ _ _ _ _

piping pressure boundary stainless steel untreated borated water cracldng System Walkdown>140 F (int) loss of material System Walkdown

sodium hydroxide loss of material System Walkdowncracldng System Walkdown I

hydrazine or ammonia loss of material System Walkdown.cracking System Walkdown

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Component Commodity Intended Function Material Environment Aging Effect ProgramlActivityG ro u p in g_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

pump casing pressure boundary carbon steel air (ext) loss of matenal System Walkdown lfresh raw water (int) loss of material System WalkdownI

treated water (int) loss of material System Walkdown lWater Chermisty Control

untreated water (inot) loss of material SystetnWalkdown lair (ext) loss of material System Walkdown l

carbon steel w/stainless loss of material System Walkdown lclad on internal treated water (int) Water Chemistry Control

surface cracking (of cladding) System Walkdown l

. Water Chemistry Control

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Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGron Ing

pump casing pressure boundary stainless steel treated boratcd water loss of material System Walkdown(int) Water Chernistry Control

loss of material System Walkdowntreated borated water Water Chemistry Control

>140 TF (int) cracklng System WatkdownWater Chemistry Control

loss of material System Walkdowntreated borated water Water Chernistry Control

>270 TF (int) cracking- fatigue SystemWalkdowncracidng Water Chemistry Control

_SystemWalkdown

untreated borated water loss of material System Walkdown(bit) _ _ _ _ _ _ _ _ _

untreated borated water loss of material System Walkdown. >140 0° (int) cracking SystemrWahkdown

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Engineering ReportANO-2 License Renewal Project A2-NM 2003-001-1



Component Commodity Intended Function Material Environment Aging Effect Program/ActlvltyG rouping _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

pump casing pressure boundary stainless steel air (ext) none nonetreated water (int) loss of material System Walkdown

Water Chemistry Controlcracking System Walkdown

treated water Water Chemistry Control> 140 'F (int) loss of material System Walkdown

Water Chemistry Controltreated borated water loss of material System Walkdown

(int) Water Chemistry Controlcracking System Walkdown

treated borated water Water Chemistry Control> 140 OF (int) loss of material System Walkdown

PWater Chemistry Controluntreated water (int) loss of material SystemWalkdown

sodium hydroxide (int) loss of material System Walkdowncracking System Walkdown

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Component Commodity Intended Function Material Environment Aging Effect Program/Activity

tank pressure boundary carbon steel air (ext) loss of material System Walkdowntreated water (int) loss of material System Walkdown

Water Chemistry Controluntreated water (int) loss of material System Walkdown

steam or treated water loss of material System Walkdown> 220 0F (int) Water Chemistry Control

cracking- fatigue System Walkdowncarbon steel (coated) air (ext) loss of material System Walkdown

untreated borated water loss of material SystemWalkdown

stainless steel air (ext) none nonetreated water (int) loss of material System Walkdown


treated borated water Water Chemistry Control> 140 OF (int) loss of material Water Chemistry Control

System Walkdowntreated borated water loss of material Water Chemistr Control

(int) System Walkdownuntreated water (int) loss of material System Walkdown

untreated borated water loss of material System Walkdown_________________ _____________________________ (nt)___________________________________________




Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGrouping _ Intended ___

thennowell pressure boundary carbon steel air (ext) loss of material Systern Walkdownfresh raw water (int) loss of material System Walkdown

treated water (int) loss of material System Walkdown._ Water Chenistry Control

stainless steel air (ext) none nonefresh raw water (int) loss of material SystemrWalkdown


cracking System Walkdowntreated borated water Water Chernistry Control

> 140 TF (int) loss of material System WalkdownWater Chemistry Control

cracking- fatigue System Walkdowntreated borated water cracking Water Chenistry Control

> 270 TF (int) Sys em Walkdownloss of material System Walkdown

Water Cheemistry Control

. ~Engineering ReportANO-2 License Renewal Project E2-Mei2003 p01-1

Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Rovislon IPage 70 of 77 l


Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGrouping _ l

tubing pressure boundary copper alloy air (ext) none nonetreated water (int) loss of material System Walkdown

Water Chemistry Controluntreated water (int) loss of material SystemWalkdownfresh raw water (int) loss of material SystemWalkdown

stainless steel air (ext) none nonefresh raw water (hit) loss of material System Walkdown

cracking Water Chemistry Controltreated borated water System Walkdown

>270 0F (int) cracldng - fatigue System Walkdownloss of material SystemWallcdown

_ ._ Water Chemistry Controltreated water (int) loss of material SystemWalkdown

___ Water Chemistry Controlcracking System Walkdown

treated water Water Chemistry Control> 140 OF (int) loss of material System Walkdown


treated water or steam Water Chenistry Control>270 TF (int) cracking- fatigue SystemWalkdown

loss of material SystemWalkdown__ _Water Chemistry Control

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tubing pressure boundary stainless steel cracking SystemWalkdowntreated borated water _ Water Chemistry Control

> 140 OF (int) loss of material System WalkdownWater Chemistry Control

untreated water (nt) loss of material System Walkdownuntreated borated water loss of material System Walkdown

(uit) brewtrosfaeaSseWkwuntreated borated water cracking System Walkdown

> 140 OF (Oit) loss of material System Walkdown.untreated water cracking System Walkdown> 140 OF (int) loss of material System Walkdown

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Engineering ReportANO-2 License Renewal Project A2-ME2003-001-1



Component Commodity Intended Function Material | Environment Aging Effect Program/ActivityG rouping__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

valve pressure boundary carbon steel air (ext) loss of material SystemWalkdowncondensation (ext) loss of material System Walkdown

fresh raw water (it) loss of material System Walkdowncracking- fatigue SystemWalkdown

steam or treated water loss of material System Walkdown>220 TF (int) Water Chemistry Control

loss of material - erosion Flow Accelcrated Corrosiontreated water (int) loss of material SystemWalkdown

Water Chemistry Controluntreated water (int) loss of material System Walk-down

aluminum condensation (cxt) loss of material SystemWalkdowntreated water (int) loss of material System Walkdown

Water Chemistry Controlcopper alloy air (ext) none none

condensation (cxt) loss of material System Walkdownfresh raw water (int loss of material System Walkdowntreated water (int) loss of material System Walkdown

Water Chemistry Control. untreated water (int) loss of material System Walcdown

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Engineering ReportANO-2 License Renewal Project A2-12003001-1

Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision 7Page 73 of 77


Component Commodity Intended Function Material Environment Aging Effect Program/ActivityGrouping _

valve pressure boundary stainless steel air (ext) none nonecracking System Walkdown

treated borated water Water Chemistry Control>270 0F (int) cracking - fatigue System Walkdown

loss of material System WalkdownWater Chemistry Control


treated borated water loss of material System Walcdown(int) Water Chemistry Control

cracking System Walkdowntreated water Water Chemistry Control> 140 OF (int) loss of material System Walkdown


treated borated water Water Chemistry Control> 140 TF (int) loss of material System Walkdown

. _ Water Chemistry Control

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Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision IPage74 of 77



valve pressure boundary stainless steel cracking System Walkdowntreated water or steamr Water Chemistry Control

>270 TF (int) cracking - fatigue System Walkdownloss of material System Walkdown

Water Chemistry Controlfresh raw water (int) loss of material System Walkdownuntreated water (int) loss of rnaterial System Walkdown

untreated water cracing System Walkdown> 270 TF (int) crackdng - fatigue System Walkdown

loss of material System Walkdownuntreated borated water loss of material System Walkdown

(int)sodium hydroxide (int) loss of material System Walkdown

cracking System Walkdownhydrazine or armnonia loss of material SystemWalkdown

_ cracking System Walkdown

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Engineering ReportANO-2 License Renewal Project A2-ME-2003-001-1Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems Revision IPage 75 of 77

Attachment 2- Aging Management Review Results _

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ANO-2 License Renewal Project Engineering ReportAging Management Review of Nonsafety-related Systems and e2003-001-1Revision I


Attachment 3- Review Logic Flowchart

I Listing of ANO-2 Systems Per 02-R-2008-01,ANO-2 License Renewal Project Final System and Structure Scoping Report

Does the system contain only air -or gas? | YES

4NODoes the system have nonsafety-related

components In safety-related structures?

No further review requiredof the system

4YES

Can the system nonsafety-relatedcomponents spatially impact any safety-related components?

NO

NO

No further review requiredof the system

No further review required.of the system

4YESPerform an aging

management review of these54.4 A(2) components.

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ANO-2 License Renewal Project Eng2eerng ReportAging Management Review of Nonsafety-related Systems A iME o2003n01-1

and Components Affecting Safety-related Systems PaRe 77 of 77

Attachment 4 Walkdown Summaries

In order to determine the potential impact to safety-related equipment, the followingwalkdowns were completed:

3/28/03 Ted Ivy and Stan Batch walked down:* The ANO-2 intake structure and outside area and verified the screenwash piping,

chemical addition piping, chemical addition tanks, and intake structure floor drainpiping cannot affect the safety-related equipment in the intake structure. Thenonsafety-related vacuum breaker components are surrounded by spray shields sothey cannot impact safety-related equipment.

• The HVAC equipment room 2153 that contains the CCW tanks, the control roomventilation normal ventilation components including the chillers, etc. It wasverified that a failure in this room would not affect safety-related equipment.

* The main chiller room 2092 was walked down and verified not to contain anysafety-related equipment.

7/2/03 Ted Ivy and Stan Batch walked down:* Verified no SR components adjacent to NSR components in the PASS Building.* Verified the SFP heat exchanger, filters, ion exchanger tank and pumps are in

their own rooms.* Verified the Boric Acid evaporators themselves are not used and located in their

own rooms.* Verified waste gas compressor coolers (2E-10AB; 2E-102A, B; 2E-103A, B) are

not located adjacent to safety-related equipment. (They are located in rooms forthe compressors.)

* Verified 2VUC-21 (cooled by ACW) is in an electrical equipment area containingNSR equipment and its failure could not affect SR equipment

* Verified sample coolers 2E31 and 2E51 are in a hallway and their failure cannotaffect SR equipment

Verified bv n ate Date

Verified byD Date

. _ ...... .S_ . .