ML20112B974

Rev 1 to Aging Mgt Review Rept for MFW Sys

ML20112B974
Person / Time
Site:	Calvert Cliffs
Issue date:	05/01/1996
From:	Doroshuk B, Hotchkiss M, Penn P BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20112B955	List: ML20112B954 ML20112B964 ML20112B970 ML20112B974 ML20112B979 ML20112B995 ML20112C003 ML20112C011 ML20112C020 ML20112C024 ML20112C036 ML20112C042
References
NUDOCS 9605240110
Download: ML20112B974 (100)

Text

. .- . .. - _ -. - - _________,_

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l Calvert Cliffs Nuclear Power Plant i

l License RenewalProject i

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i l Aging Management Review Report for the i -.

Main Feedwater System lO (045)

Revision 1 April,1996 1

Prepared by: .

Date: Y'N'Ob M. W. Hotchkiss Reviewed by: ./A M / Date: ~2N4 P. A. Penn Date: 5 8!%

Approved by: $ j n. w. De,esunk O

w= m unih7 P

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l Feedwater System Aging Management Review Report i d Table of Contents Page List of Tables ii j List of Effective Pages iii l

1.0 INTRODUCTION

1.1 Feedwater System Description 1-1 1.1.1 Feedwater System Description 1-1 1.1.2 Feedwater System Boundary 1-2 1.1.3 Feedwater Intended System Functions 1-2 l

1.2 Evaluation Methods 1-3 1

1.3 System-Specific Definitions 1-3 l l 1.4 System-Specific References 1-4 2.0 STRUCTURES AND COMPONENTS WITIllN TIIE SCOPE OF f

6 LICENSE RENEWAL 2.1 Component Level Scoping Methodology Overview 2-1 I l 2.2 Component Level Scoping Results 2-1 1 3.0 COMPONENT PRE-EVALUATION 3.1 Pre-evaluation Methodology Overview 3-1 3.2 Pre-evaluation Results 3-1 l 4.0 COMPONENT AGING MANAGEMENT REVIEW 4.1 Aging Management Review Methodology Overview 4-1 4.2 Age-Related Degradation Mechanisms 4-2 4.2.1 Potential ARDMs 4-2 4.2.2 Component Grouping 4-3 4.2.3 Plausible ARDMs 4-3 4.3 Methods to Manage the Effects of Aging 4-3 O

(j Appendix A Feedwater System Aging Management Review Results i Revision 1

t FeedwaterSystem Aging Management Review Report y/

List of Tables 1

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Table 1-1 System-Specific References 1-5 i

Table 2-1 Feedwater System Device Types Within The Scope Of 2-2 License Renewal Table 3-1 Feedwater System Intended System Function Disposition 3-2 Table 3-2 Summary of Feedwater System Device Types Requiring 3-3 Aging Management Review Table 4-1 Potential Age-Related Degradation Mechanisms (ARDMs) 4-5 Summary Table 4-2 Plausible Age-Related Degradation Mechanisms Summary 4-6 j O  !

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List of Effective Pages Page Revision Change Description All 0 Initial issue All 1 General update for CCNPP IPA Methodology, Revision 1, and revision to component pre-evaluation and aging management review I

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1.0 INTRODUCTION

1.1 Feedwater System Description This section describes the scope and boundaries of the Feedwater System as it was evaluated. Section 1.1.1 provides a brief synopsis of the system as described in existing plant documentation. System boundaries (as described in ES-032, Revision 0) are provided in Section 1.1.2 to clarify the extent of the Feedwater System considered in this evaluation. Section 1.1.3 is a detailed breakdown of the intended system functions within the scope oflicense renewal and is provided as the basis for the identification of components required to support those-intended functions.

1.1.1 Feedwater System Description The conceptual functional requirements of the Feedwater System are:

to transfer feedwater from the steam generator feed pump suction to the steam generators,

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to regulate the flow of feedwater to the steam generators and to -

maintain a constant water level in the steam generators, i 1

To heat the condensate received by the feed pumps,

. To provide a means for injecting chemicals into the steam generators from the chemical addition system.

The condensate booster pumps deliver the condensate to the two turbine-driven steam generator feed pumps through two parallel sets of three low pressure feedwater heaters. The steam generator feed pumps then pump the condensate through two parallel high pressure feedwater heaters to the steam generators.

The Feedwater System was determined to be within the scope oflicense renewal during the system level scoping process.

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l.1.2 Feedwater System Boundary j The Feedwater System is comprised of the following equipment:

4 Pumps turbine-driven centrifugal steam generator feed pumps (SGFP)

Valves minimum pump recirculation flow control feedwater regulating regulating valve bypass Pump seal water system Heat Exchanger High pressure feedwater heaters Piping Instrumentation (q') The Feedwater System interfaces with the following systems and components:

Condensate System Main Steam System Chemical Addition System Emergency Safety Features Actuation System Extraction Steam System Reactor Coolant System (Steam Generator) 1.1.3 Feedwater Intended System Functions ,

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. Send signals to ESFAS and provide SG isolation

. Provide containment overpressure protection

. Prevent reverse flow from SG via check valve closure

. Maintain functionality of electrical equipment as addressed by the EQ Program

. To maintain the pressure boundary of the system

. To provide information used to assess the plant and environs condition

- during and following an accident

/T j Cl . Provide SG level indication 1-2 Revision 1

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V To maintain electrical continuity and/or provide protection of the electrical system

. Provide signals to AFAS

. Provide signals to RPS

. Monitor steam generator level to support safe shutdown in the event of a postulated severe fire 1.2 Evaluation Methods Feedwater System components within the scope oflicense renewal were identified through the use of BGE procedure for Component Level Scoping of Systems. The results of the scoping process are discussed in Section 2.0 of this report.

Feedwater System components subject to aging management review for license renewal were determined using the BGE procedure for Component Pre-Evaluation to identify passive, long-lived components that must be p evaluated for management of the effects of age-related degradation. The V results of the Pre-evaluation process ars discussed in Section 3.0 of this repcrt.

All components subject to aging management review are evaluated for the effects of aging in accordance with the BGE procedure for Component Aging Management Review. This procedure is performed to determine  ;

plausible aging effects and the appropriate methods to manage those  ;

effects. The results of the Aging Management Review (AMR) process are I discussed in Section 4.0 of this report. l l

1 1.3 System-Specific Definitions l l

This section provides the definitions for any specific terms unique to the Feedwater component aging evaluation.

No terms unique to the Feedwater System were used. l l

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1.4 System-Specific References Several sources were used to determine potential and plausible ARDMs for the Feedwater evaluation. These sources include NRC Draft Regulatory Guide DG-1009, " Standard Format and Content of Tecimical Information for Applications to Renew Nuclear Power Plant Operating Licenses". Detailed drawings and other controlled documents related to the Feedwater System were utilized to verify materials, design configurations and location of components.

Table 1-1 lists the references utilized in the completion of the Feedwater System Aging Management Review for license renewal.

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Feedwater System Aging Management Review Report Table 1-1 System Specific References Document ID Document Title Revision llate ANSI B31.1; Power Piping Code 1967 ANSI B31.7; Nuclear Power Piping Code 1969 ASME Boiler and Pressure Vessel Code, 83S83 Section XI, Subsection IWV-2000 ASME Wear Control llandbook, Peterson and 1980 Winer CCNPP ASME Section XI Pump and Valve 1 Test Program, Second Ten Year interval CCNPP Integrated Plant Assessment 1 Methodology Component L-evel ITLR Screening Results for 1 the Feedwater System Corrosion and Corrosion Control- Uhlig and 3rd Edition 1985

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Revie Corrosion Engineering - Fontana & Greene 3rd Edition 1978 Mark's Standard liandbook for Mechanical 8th Edition Engineers - McGraw-Ilill I Metals Handbook - ASM; Volumes I and 13 9th Edition 1978 Pre-evaluation Results for the Main 1 Feedwater System (045)

System Level Scoping Results 4 10452052 Feedwater Check Valve Inspection Repetitive 11/10/95 Task 10452053 Feedwater Check Valve Inspection Repetitive 11/10/95 Task 12399-0002 Cast Steel 11orizontal and Vertical Tilting 12 Disk Check Valve Drawing 12399-0022S110001 Cast Steel llorizontal and Vertical Tilting 5 Disk Check Valve Drawing 12543 A-01 Feedwater Piping Isometric Drawing, Unit 1 13 12717-0002 Carbon Steel Pressure Seal Gate Valve L Drawing

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Table 1-1 System Specific References Document ID Document Title Revision Dalt 13547A-20 Feedwater Piping Isometric Drawing, Unit 2 6F 13547A-47 Feedwater Piping Isometric Drawing, Unit 2 4 13549A-26 Feedwater Piping Isometric Drawing, Unit 2 3 15587-0008 Vogt 3/4" Globe Valve Drawing 20 15587-0021 Vogt 3/4" Globe Valve Drawing 5 15587-0027 Vogt 1" Gate Valve Drawing 3 20452043 Feedwater Check Valve Inspection Repetitive 11/10/95 Task 20452044 Feedwater Check Valve Inspection Repetitive 11/10/95 Task 60702SII0004 Condensate and Feedwater System 28 Operations Drawing 62702SH0004 Condensate and Feedwater System 30

/O Operations Drawing V 6750-M-355 Eauipment Specification for Thermocouple, 15 k fD, and Thermowells 92702 Special Thermowell For Thermocouples and 3 j Test Wells Drawing i 92767 Piping Class Sheets 58 92771 Master Valve List 41 CE-NPSD-634-P Fatigue Monitoring Program For CCNPP 4/92 Units 1&2 CP-0217 Specifications And Surveillance - Secondary 5 System Chemistry Procedure DG-1009 Draft Reg. Guide - 1009, Standard Format Drall 12/90 and Content of Technical Information for Applications to Renew Nuclear Power Plants, Appendix A FSK-M P-1003 Root Valves for Level Transmitters Drawing 5 1Rl-011-785 S/G Feedwater Nozzle / Piping Thermal, Stratification Issue Report LCM-16 LCM Component Aging Management 4

/f\ Review Procedure N.)

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Document ID Document Title Revision Dale l l

LCM 96-044 BGE Memorandum,

Subject:

Age Related 2/15/96 1 Degradation Inspections, dated February 15, 1996, BMT to Distribution NP-2129 EPRI Report - Radiation Effects on Organic 11/81 Materials in Nuclear Plants NP-3944 EPRI Report - Erosion / Corrosion in Nuclear 4/85 Plant Steam Piping NP-5461 EPRI Report - Component Life Estimation: 1987 LWR Structural Materials Degradation )

Mechanisms ,

NP-5775 EPRI Report Environmental Effects on 4/88 I Components: Commentary for ASME Section III '

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N P-5985 EPRI Report - Boric Acid Corrosion of 1988 Carbon and Low Alloy Steel Pressure m) Boundaries NP-6815D EPRI Report - Detection and Control of MIC 1990 NUM ARC 90-07 PWR Reactor Coolant System License 5/92 Renewal Industry Report NUREG/CR-5379 Nuclear Plant Service Water System Aging 6/89, Degradation Assessment, Volume I and 2 10/92  ;

NUREG/CR-5419 Aging Assessment ofinstrument Air Systems 1/90 NUREG/CR-5643 Insights Gained from Aging Research 3/92 OI- 12 A- 1 Unit 1 Main Feedwater Operating Instructions 22 Ol-12A-2 Unit 2 Main Feedwater Operating Instructions 14 PT-0009-204 Qualification Maintenance Requirements 0 Sheet PT-0009-205 Qualification Maintenance Requirements O Sheet l TPR96-022 Technical Problem Report; Feedwater System 3/25/96 i

S/G Check Valve Thermal Fatigue TR-102204 EPRI Report - Service (Salt) Water System 4/93 Life Cycle Management Evaluation C

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l Feedwater System Aging Management Review Report Table 1-1 i System Specific References l Document ID Document Title Revision llate UFSAR Updated Final Safety Analysis Report; 18 Chapter 4 " Reactor Coolant and Associated '

Systems", Chapter 10 " Steam and Pow.:r Conversion Systems" VTM-D243-0001 Dresser Hancock Valves Technical Manual 0 l

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1 2.0 STRUCTURES AND COMPONENTS WITIIIN THE SCOPE OF LICENSE '

RENEWAL 2.1 Component Level Scoping Methodology Overview 1 The scoping of the Feedwater System components was performed in accordance with the process described in the Calvert Cliffs Nuclear Power Plant Integrated Plant Assessment Methodology as specified in the procedure for the component level scoping of systems. The purpose of component level scoping is to identify all system components that support the intended system functions identified in Section 1.1.3 for the Feedwater System. These are the components that are within the scope oflicense renewal. I 1

2.2 Component Level Scoping Results  !

A total of 20 device types in the Feedwater System were designated as within the scope oflicense renewal. These device types are listed in Table 2-1.

The portion of the Feedwater System within the scope oflicense renewal l

-, consists of piping, components, component supports, instrumentation, and cables for the section of the system from the feedwater isolation motor-

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'd operated valves to the steam generator feedwater nozzle and for steam generator secondary instrumentation.

Refer to the results of the Feedwater System Component Level Scoping for the list ofintended functions, the list of components within the scope of license renewal, and other scoping-re!ated details.

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Table 2-1 l

Feedwater System Device Types Within the Scope of License Renewal l Ilevice Type Device Description l

l -DB Class DB Piping l CKV Check Valve FU Fuse llS Handswitch IIV lland Valve 1/1 Current / Current Device l JL Power Lamp indicator l L1 Level Indicator l LR Level Recorder i LT Level Transmitter MOV Motor Operated Valve i PI Pressure Indicator i PT Pressure Transmitter l ,'

RY Relay l TE Temperature Element TY Temperature Device (Relay) l g X Transformer YX Power Supply -

ZL Position Indicating Lamp ZS Position Switch l

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Feedwater Sgtem Aging Management Review Report l V 3.0 COMPONENT PRE-EVALUATION 3.1 Pre-Evaluation Methodology Overview i

The component pre-evaluation procedure is used to determine which

! components are subject to an aging management review. This procedure is used to categorize intended system functions as active or passive, determine if the components supporting passive system functions are long-lived, and identify the set of components subject to aging management

. review.

The pre-evaluation also determines whether the components should be included in a commodity group AMR. or the system AMR.

, 3.2 Pre-Evaluation Results 1

Table 3-1 summarizes the disposition ofintended system functions for the Feedwater System as either active or passive. These functions are derived i from the system functions identified and documented during the

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Components supporting only active intended system functions (i.e., not I passive components) and those that are subject to replacement based on qualified life (i.e., not long-lived components) do not require an aging management review.

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Components that are evaluated as part of commodity evaluations are l

l addressed in separate AMRs. The Feedwater System components

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dispositioned as part of commodity evaluations include all component '

supports , all cables *, and all instrument devices that support passive functions (that are not subject to a replacement program).

l Table 3-2 summarizes the disposition of the device types identified in Table 2-1 as within the scope oflicense renewal for the Feedwater System.

Refer to the results of the Feedwater System Component Pre-evaluation i

for the list of components subject to AMR and other details.

Component supports and cables are not identified as feedwater system components in the feedwater (N system scoping results, but are generically included in the Component Supports and Cables Commodity AMRs, respectively.

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Table 3-1 Feedwater System Intended System Function Disposition Function Descrintion Function Passive?

Send signals to ESFAS and provide SG isolation No Provide containment overpressure protection No Prevent reverse flow from SG via check valve No closure Maintain functionality of electrical equipment as No addressed by the EQ Program Maintain the pressure boundary of the system Yes Provide information used to assess the plant and No

, environs condition during and following an accident V) Provide SG level indication

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No Maintain electrical continuity and/or provide Yes protection of the electrical system i Provide signals to AFAS No Provide signals to RPS No Monitor steam generator level to support safe No shutdown in the event of a postulated severe fire

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Feedwater System Aging Management Review Report Table 3-2 Summary of Feedwater System Device Types Requiring Aging Management Review Components Components Components Components Support Subject to Evaluated in Included in Device Passive Replacement Commodity Feedwater Type Device Descrintion Eimetion(s)? Program? AMR?

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-DB Class DB Piping YES NO NO YES CKV Check Valve YES NO NO YES FU Fuse NO NO NO NO IIS liandswitch NO NO NO NO IIV lland Valve YES NO PARTIAL PARTIAL 1/1 Current / Current NO NO NO NO Device JL Power Lamp NO NO NO NO Indicator LI Level Indicator NO NO NO NO LR Level RecoIder NO NO NO NO LT Level Transmitter YES PARTIAL PARTIAL NO MOV Motor Operated YES NO NO YES Valve Pl Pressure Indicator NO NO NO NO PT Pressure Transmitter YES PARTIAL PARTIAL NO RY Relay NO NO NO NO TE Temperature Element YES NO NO YES i TY Temperature Relay NO NO NO NO X Transformer NO NO NO NO l YX Power Supply NO NO NO NO l

ZL Position Indicating NO NO NO NO l Lamp ZS Position Switch NO NO NO NO  !

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V 4.0 COMPONENT AGING MANAGEMENT REVIEW 4.1 Aging Management Review Methodology Overview l The aging management review of Feedwater System components was performed l in accordance with the process described in the Calvert Cliffs Nuclear Power Plant Integrated Plant Assessment Methodology'as specified in the procedure for the component aging management review. This procedure requires the identification of plausible age related degradation mechanisms (ARDMs) for each component subject to aging management review, unless it can be demonstrated that the effects of aging can be managed without specifying ARDMs. The effects of the ARDMs on the ability of the components to support intended functions are identified and the ability of existing plant programs to adequately manage the effects of these ARDMs is evaluated.

The review accomplished the following:

. Determination of plausible component-ARDMs combinations:

74 (1) Identified potential age-related degradation mechanisms (ARDMs)

) for Feedwater System components.

(2) Grouped Feedwater System components based on device type and design / operating environment attributes. Sub-component groups were also determined when necessary based on design / operating environment attributes and supported component functions.

(3) Identified plausible age-related degradation mechanisms ARDMs for each component or sub-component based on:

Industry and plant information Material of construction Environmental service factors Intended functions

. Identification of methods to manage aging effects for plausible ARDMs and assessment of current plant programs to determine whether these aging l

effects are adequately managed. If current programs were not adequate to l manage aging effects, program modifications or new program requirements were identified.

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! b 4.2 Age-Related Degradation Mechanisms Feedwater System components were evaluated to identify plausible ARDMs for

which aging effects management activities are required to ensure that age related

! degradation does not affect the component intended function (s). The identification of plausible ARDMs was completed in accordance with the process

discussed below.

4.2.1 Potential ARDMs This step of the aging evaluation identifies ARDMs that are potentially detrimental to Feedwater System components. These potential ARDMs are determined on an equipment type (e.g., pipe, valve, instrument, element) basis.

An ARDM is considered potential if the evaluation concludes that the ARDM could occur in generic applications of the equipment throughout the plant. The equipment types for which ARDMs were evaluated are listed below.

Pipe Valve

, Element

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(") A list of potential component ARDMs was developed for each of the equipment types. The list was developed through review ofindustry documents. The l following are examples of sources of ARDM information:

Draft NRC Regulatory Guide DG-1009 NUMARC Industry Reports NRC NPAR Reports l EPRI Reports For each ARDM on the list, a determination was made whether it was applicable

, (i.e., potential) to the equipment type. The applicability of the ARDM was l determined on the basis of a generic component of the equipment type in service

in any system in the plant.

A summary of the potential ARDMs for each of the Feedwater System equipment types is provided in Table 4-1. The specific description of each potential ARDM is included on the Attachment 7s in Appendix A.

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" l 4.2.2 Component Grouping l Similar components are grouped together for evaluation efficiency. The age-related degradation evaluation results completed for a group are applicable to each l of the individual components within the group. Selection of grouping attributes I was accomplished through consideration of the component characteristics that l would most influence the age-related degradation that could occur. Typical grouping attributes utilized for the Feedwater System included material of construction, component specific function, and process environment. Where these '

attributes varied among the sub-components within a given component, a sub-group was developed to represent all similar sub-components of the parent group members. Typical sub-groups represented component pressure boundary parts and component internals. Component grouping is shown on Attachment 3s in Appendix A. Subcomponent breakdowns are shown on Attachment 4s in Appendix A.

4.2.3 Plausible ARDMs The list of potential ARDMs is utilized for a Feedwater System component-

.'. specific identification of plausible ARDMs. The plausibility determination is rw made through consideration of factors that influence component susceptibility to

(. / the ARDM. The ARDMs are assessed for plausibility on the basis of:

Material of construction Internal (process) environment External environment Operational conditions / effects Affect on the passive intended function The results of the component-specific ARDM plausibility evaluation are included in Attachment 5s and 6s in Appendix A. These results are summarized by component Device Type, in matrix form, in Table 4-2.

4.3 Methods to Manage the Effects of Aging The methods of managing the effects of plausible age related degradation mechanisms are determined in the final step of the aging management review process. These methods are compared to current plant programs and practices to l

determine whether aging effects are adequately managed for the period of extended operation, or whether program revisions or new programs are required.

Additionally, plant modifications may be considered as a method to manage aging

. effects.

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(1 Applicable aging effects management methods are determined through consideration of the specific plausible ARDM, component configuration (material of construction, geometry, service conditions, etc.), and relative significance of i the aging effects for the period of extended operation.

1 Site programs and processes associated with the Feedwater System were reviewed I to identify those that implemented the aging effects management methods determined to be necessary for the period of extended operation. These activities l

were reviewed with appropriate site program managers, system engineers, and  !

others to gain concurrence on the site programs and processes that will become commitments for plant license renewal. Similarly, modifications to current programs, and requirements for new programs, were identified and reviewed with the site to gain concurrence as these will also become commitments for plant i license renewal.

l Site programs, modifications to programs, and new programs are related to specific Feedwater System components and plausible ARDMs on Attachments 1,

. 2,8 and 10 in Appendix A.

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(' ) Attachment 1 in Appendix A provides a summary of Feedwater System

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components (by device type) subject to aging management review, applicable passive intended function (s), plausible ARDMs, and aging effects management l programs.

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Table 4-1 Potential Age-Related Degradation Mechanisms (ARDMs) Summary i

Feedwater System Equipment Types  !

Potential ARDMs Pigg Valve Element  !

Cavitation Erosion x x x Corrosion Fatigue x x x Creep / Shrinkage Crevice Corrosion x x x Dynamic Loadmg x x Erosion / Corrosion x x x Fatigue x x x Fouling x x x Galvanic Corrosion x x x General Corrosion x x x Hydrogen Damage x x x Intergranular Attack x x x Irradiation Embrittlement t' Microbiologically x x x

(._/ Influenced Corrosion (MIC)

Oxidation Particulate Wear Erosion x x x Pitting x x x Radiation Damage x x x Saline Water Attack x j Selective Leaching x x x I Stress Corrosion Cracking x x x Stress Relaxation Thermal Damage x x x Thermal Embrittlement x x x  !

Wear x x x - indicates that the ARDM is potentially detrin. ital to the equipment type l l

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U Table 4-2 Plausible Age-Related Degradation Mechanisms Summary Feedwater System Device Types Plausible ARDMs DB CKV llV MOV TE Cavitation Erosion Corrosion Fatigue x x Creep / Shrinkage Crevice Corrosion x x x x x Dynamic Loading Erosion / Corrosion x x x x Fatigue x x Fouling Galvanic Corrosion General Corrosion x x x x x ilydrogen Damage Intergranular Attack

., Irradiation

. Embrittlement

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, Microbiologically

(") Influenced Corrosion (MIC) -

Oxidation Particulate Wear Erosion Pitting x x x x x Radiation Damage Saline Water Attack Selective Leaching Stress Corrosion Cracking Stress Relaxation i Thermal Damage I Thennal Embrittlement Wear x - indicates that the ARDM is plausible for component (s) within the Device Type l

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!"'- Appendix A b Feedwater System Aging Management Review Results T.utal Pages Attachment 1, Aging Management Review Summary 1 Attachment 2, Description of Programs Which Manage the Effects of Aging 3 Equipment Type: ELEMENT Attachment 7, Potential ARDM List 11 Device Type: TE Attachment 3, Component Grouping Summary Sheet (045-TE-01) 1 Attachment 4, Sub-Component /Sub-Groupidentification 1 Attachment 5, ARDM Matrix 1 Attachment 6, Matrix Code List 3 Equipment Type: PIPE Attachment 7, Potential ARDM List 10 Device Type: -DB Attachment 3, Component Grouping Summary Sheet (045-DB-01) 1

, Attachment 3, Component Grouping Summary Sheet (045-DB-02) 1

[ Attachment 5, ARDM Matrix 1 Attachment 6, Matrix Code List 4 Equipment Type: VALVE Attachment 7, Potential ARDM List 10 Device Type: CKV Attachment 3, Component Grouping Summary Sheet (045-CKV-01) 1 Attachment 4, Sub-Component /Sub-Groupidentification 1 Attachment 5, ARDM Matrix 1 4 l

Attachment 6, Matrix Code List 4 Device Type: IIV Attachment 3, Component Grouping Summary Sheet (045-ilV-01) 2 Attachment 4, Sub-Component /Sub-Groupidentification 1 l Attachment 5, ARDM Matrix 1 l Attachment 6, Matrix Code List 3 l l l Attachment 3, Component Grouping Summary Sheet (045-ilV-02) i Attachment 4, Sub-Component /Sub-Groupidentification I

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Attachment 5, ARDM Matrix 1

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Appendix A Feedwater System Aging Management Review Results Total Pages Device Type: MOV Attachment 3, Component Grouping Summary Sheet (045-MOV-01) 1 Attachment 4, Sub-Component /Sub-Groupidentification 1

. Attachment 5, ARDM Matrix 1

. Attachment 6, Matrix Code List 4 Attachment 8, Development of Aging Management Alternatives 7 Attachment 10, Program / Activity (PA) Modifications I i

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Component Aging < anagement Review ATTACHMENT 1, AGING MANAGEMENT REVIEW

SUMMARY

System Name and No.: Main Feedwater (045)

Subcomponents/ .

Group Passive Intended Grouping Subgroups Not Plausible Managed by Existing Modifications New Program Desire Type ID Functions Attributes Subject to Aging ARDMs . Programs ID Needed . Needed --

Mgmt Review Mamtain system -Carbon Steel Material N/A Crevice Corrosion CP-0217 Yes - Age-Related

-Du 045-Oli-01 pressure boundary - Controlled environmer.t Pitting Degradation [nspection General Corrosion Program

- Water @ 435F

- Subject to thermal Erosion Corrosion MN-3-11 I CP-0217 stratification conditions Fatigue, Corrosion Fatigue Mon:toring Yes - Commitment 01 Fatigue Program (see Attachment 10)

CP-0217 Mamtam system -Carbon Steel Material N/A Crevice Corrosion CP-0217 Yes- Age-Related 045-Dit -02 pressure boundary - Controlled environment Pitting Degradation Inspection General Corrosion Program

- Water @ 435F Erosion Corrosion MN-3-11 i CP-0217 045-CKV-01 Maintam system -Carbon Steel Material 045-CKV-01C Crevice Corrosion CP-0217 Yes- Age-Related CKV pressure boundary - Controlled environment Disk, and other Pitting Degradation Inspection

- Water @ 435F non-pressure- General Corrosion Program retaining pa:ts Erosion Corrosion RepFasks 10452052, 10452053,20452043, and 20452044 CP-0217 l-atigue, Corrosion Fatigue Momtoring Yes - Commitment 01 Fatigue , Program (see Attachment 10)

CP-0217 ilV 045-ilV-01 Mamtain system -Carbon Steel Material 045-ilV-01D Crevice Corrosion CP-0217 Yes- Age-Related pressure boundary - Controlled environment Disk, and other Pitting Degradation Inspection

- WateriSteam up to 550F non-pressure- General Corrosion Program

- Normally open retaining parts 045-IIV-02 Mamtam system - Carbon Steel Material 045-IIV-01E Crevice Corrosion CP-0217 Yes - Age-Related pressure boundary - Controlled environment Non-pressure- Pitting Degradation Inspection

- Water @ 4;5F retaining intemal General Corrosion Program

-Norma;ly closed parts MOV 04 5-MOV-01 Maintain system - Carbon Steel Matenal 045-MOV-Ol E Crevice Corrosion CP-0217 Yes- Age-Related pressure boundary -Controlled environment Non-pressure- Pitting Degradation Inspection

- Water @ 435F retaining intemal General Corrosion Program

- Normally open parts Erosion Corrosion CP-0217 Yes- Age-Related Degradation Inspection Program a IL 045-I L-01 Maintam system -21/4Cr-lMo Material 045-1 E-OlB Crevice Corrosion CP-0217 Yes- Age-Related pressure boundary - Controlled ensironment Temperature Pitting Degradation Inspection Water @ 435F Flement General Corrosion Program Erosion Corrosion CP-0217 Yes - Age-Related Degradation Inspection Program Revision 1 Page1ofI Date: Apr.116,1996 I

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• n V Component Aging ..ianagernent Review O O ATTACilMENT 2, DESCRIPTION OF PROGRAMS WIIICII MANAGE TIIE EFFECTS OF AGING System Name and Number: Main Feedwater (045)

Program ID Portions oISystem Managed ARDMs Managed by Description of Program By This Program & Passive This Program Intended Function CP-0217, Chemistry Feedwater System piping, Corrosion Fatigue The Chemistry Control Program provides requirements and Specifications and valves and associated criteria for monitoring fluid system chemical parameters Surveillance - components from the feedwater Crevice Corrosion including impurity concentrations, conductivity, pH, and total Secondary Systems isolation MOVs to the S/G solids levels. The program provides for appropriate corrective nozzle, and S/G instrument Erosion Corrosion actions when out-of-specification conditions are encountered.

root isolation valves. The chemistry department procedure CP-0217 provides these Passive Intended Function: General Corrosion requirements as applicable to the Feedwater System fluid Provide the system pressure chemistry, retaining boundary. Pitting MN-3-111, Erosion Feedwater System piping from Erosion Corrosion The Erosion Corrosion Monitoring Program procedure (MN Corrosion Monitoring the feedwater isolation MOVs 111) provides details of the program scope (which includes the of Secondary Piping to the S/G nozzle. Feedwater System), criteria for classification of piping locations Passive Intended Function: based on susceptibility to erosion corrosion and past inspection Provide the system pressure results, scheduling ofinspections, and corrective actions when retaining boundary. adverse conditions are found or predicted. The determination of corrective action requirements are based on calculated minimum wall thickness requirements considering all design requirements for the piping.

l Revision 1 ,Page1of3 Date: April 9,1996

Component Agm.g mEnagement Revtew ATTACIIMENT 2, DESCRIPTION OF PROGRAMS WHICH MANAGE THE EFFECTS OF AGING System Name and Number Main Feedwater (045)

Program ID Portions of System Managed ARDMs Managed by Description of Program By This Program & Passive This Program ,

Intended Function ,

Age Related Feedwater System piping, Corrosion Fatigue The Age-Related Degradation Inspection (ARDI) Program is Degradation valves and associated intended to provide the additional assurance needed to conclude inspection Program components from the feedwater Crevice Corrosion that the effects of plausible aging are being effectively managed '

isolation MOVs to the S/G for the period of extended operation. A conceptual description of nozzle, and S/G instrument Erosion Corrosion the ARDI Program can be found in BGE memorandum LCM 96-root isolation valves. 044 dated Febmary 15,1996. For the Feedwater System, the Passive Intended Function: General Corrosion ARDI Program will be focussed on the effects of the plausible Provide the system pressure age-related degradation mechanisms and affected components retaining boundary. Pitting, identified in this AMR. He results ofimplementation of the ARDI Program are to be used to determine actions required to j ensure that the affected components continue to support the passive intended functions identified in the AMR throughout the t perioi of extended operation. '

CCNPP Fatigue Feedwater System piping Fatigue De CCNPP Fatigue Monitoring Program (FMP) tracks thermal Monitoring Program downstream of the S/G check fatigue usage by monitoring thennal cycles occuring at critical ,

valves to the S/G nozzle, and Corrosion Fatigue (bounding) locations in the plant for a specific scope of plant the S/G check valve bodies. systems / components. De Feedwater System is not currently '

Passive Intended Function: within the scope of the FMP. He affected piping and check Provide the system pressure valves of the Feedwater System are to be evaluated to determine retaining boundary. whether currently monitored locations within FMP scope -

adequately envelope fatigue effects for these components. He FMP is to be modified, as necessary, to include these components within the scope of the program in order to ensure that fatigue ,

effects are managed during the period of extended operation.

i Revision 1 Page 2 of 3 Date: April 9,1996

b Component Agingi Jiagement Review U

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ATTACIIMENT 2, DESCRIPTION OF PROGRAMS WIIICII MANAGE THE EFFECTS OF AGING System Name and Number: Main Feedwater (045)

Program ID Portions of System Managed ARDMs Managed by - Description of Program By This Program & Passive This Program Intended Function S/G Check Valves Feedwater System S/G check Erosion Coyosion These tasks provide instructions for the inspection and thickness Inspection for valves. measurement of the S/G check valve bodies in order to determine Erosion Corrosion - Passive Intended Function: the effects of erosion corrosion of the valves. Continued Repetitive Tasks Provide the system pressure performance of these tasks ensures that the effects of erosion 10452052,10452053, retaining bc mdary. corrosion are managed for these check valves during the period of 20452043,and extended operation.

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Revision 1 Page 3 of 3 Date: April 9,1996

Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST l System: Main Feedwater System (045) Equipment Type: ELEMENT l ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE l (YES/NO)

Cavitation Yes Localized material erosion caused by formation and collapse of vapor [6]

Erosion bubbles in close proximity to material surface. Requires fluid (liquid) flow and pressure variations which temporarily drop the liquid pressure l below the corresponding vapor pressure. Most materials are susceptible l to varying degrees depending upon the severity of the environmental l factors.

l Corrosion Yes Plant equipment operating in a corrosive environment subjected to cyclic [6]

l Fatigue (fatigue) loading may initiate cracks and/or fail sooner than expected l based on analysis of the corrosion and fatigue loadings applied separately. Fatigue-crack initiation and growth usually follows a l transgranular path, although there are some cases where intergranular i cracking has been observed. In some cases, crack initiation occurs by

fatigue and is subsequently dominated by corrosion advance. In other cases, a corrosion mechanism (SCC) can be responsible for crack formation below the fatigue threshold, and the fatigue mechanism can

accelerate the crack propagation. Corrosion-fatigue is a potentially active mechanism in both stainless steels as well as carbon and low alloy steels.

. Creep / No Not applicable to Equipment Type. The phenomenon results in [2]

, Shrinkage dimensional changes in metals at high temperatures and in concrete subject to long term dehydration. This ARDM is not applicable to this q) "

equipment type since proper component specification and design prevents this ARDM from occurring (i.e., system and component design standards adequately address this ARDM).

Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or [5]

Corrosion shielded areas. It is associated with a small volume of stagnant solution [6]

caused by holes, gasket surfaces, lap joints, crevices under bolt heads, [11]

surface deposits, designed crevices for attaching thermal sleeves to safe-ends, and integral weld backing rings or back-up bars. The crevice must be wide enough to permit liquid entry and narrow enough to maintain stagnant conditions, typically a few thousandths of an inch or I tess. Crevice corrosion is closely related to pitting corrosion and can initiate pits in many cases as well as leading to stress corrosion cracking.

In an oxidizing environment, a crevice can set up a differential aeration ,

cell to concentrate an acid solution within the crevice. Even in a reducing environment, alternate wetting and drying can concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.

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Revision i Page 1 of 11 Date: March 19,1996 I

Component Aging Management Review ATTAClIMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: ELEMENT ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) l Dynamic Yes j LWR components and structures are designed to accommodate loads that [5]

Loading .tre expected in service. Particular attention is given to 1:miting the [6]

effects of fatigue and significant plastic deformation or rupture.

Experience has shown that while expected loads have been properly treated, dynamic loads not explicitly considered during design have occurred in service causing material degradation and component failure.

Examples of unexpected dynamic loads are vibration, water hammer, and unstable fluid flow. Vibration dynamic loads are caused by the response of a component, system or structure to oscillating input. Possible sources ofinput energy include rotating equipment and fluid flow. The most serious situations arise when the input load synchronizes or nearly synchronizes with the natural frequency of the component, system, or structure. Examples of vibration-induced dynamic loading problems which have occurred in LWRs include PWR core barrel vibration, main coolant pump shaft cracking, pipe weld fatigue cracking, and steam generator and condenser tube failures. Tubes in heat exchangers tend to vibrate under the influence of crossflow velocities, possibly leading to

, tube or support damage. When the vibration amplitude is high enough, the tubes impact and experience thinning at mid-span; when lower, g frettirg damage can occur at support points. Although fatigue failure is a i t majer concern due to vibration loads, simple loss of function may also I occar in components such as bolting and valves. Flow-induced vibration I has been identified as the source of many safety relief valve (SRV) failures in high energy piping systems, causing leakage, chatter, premature pop-off, fretting, galling, fatigue and possible failure to operate when required. Water hammer loads are caused by hydraulic pressure wave effects associated with rapid changes in fluid flow. These changes may be initiated by rapid valve or pump action, particularly with large differential pressure across the valve or high fluid flow capacity through the pump. In other cases, water hammer may be caused by rapid condensation of steam or liquid flashing to steam followed by condensation with enough liquid in the system to transmit the pressure wave. Unanticipated water hammer loads have caused piping support faika-s, deformation of piping and internals, and valve and pump damage.

m Revision i Page 2 of I I Date: March 19,1996

l Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST t G System: Main Feedwater System (045) Equipment Type: ELEMENT ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Erosion Yes increased rate of attack on a metal because of the relative movement (4]

Corrosion between a corrosive fluid and the metal surface. Mechanical wear or [5]

abrasion can be involved, characterized by grooves, gullies, waves, holes [6]

and valleys on the metal surface. Erosion is a mechanical action of a Guid and/or particulate matter on a metal surface, without the inDuence of corrosion. Erosion corrosion failures can occur in a relatively short time and are sometimes unexpected, since corrosion tests are usually run under static conditions. All equipment exposed to moving Guids is vulnerable; in particular, piping (bends, tees, etc.), valves, pumps, propellers and impellers, heat exchanger tubing, turbine blades and wear plates are compcaents which have experienced erosion corrosion. This is a serious problem in steam piping, heater drain piping, reheaters, and moisture separators due to high velocity particle impingement. Erosion corrosion has occurred in high and low pressure preheater tubes, low pressure preheaters, evaporators and feedwater heaters. Inlet tube corrosion occurs in heat exchangers, due to the turbulence of Cow from the exchanger head into the smaller tubes, within the first few inches of the

., tube. Such corrosion has been especially evident in condenser tubes and

, feedwater heaters. The occurrence of erosion corrosion is highly dependent upon material of construction and the Guid now conditions.

O Carbon or low alloy steels are particularly susceptible when in contact with high velocity water (single or two phase) with turbulent now, low l oxygen and fluid pH < 93. Maximum erosion corrosion rates are expected in carbon steel at 130-140 C (single phase) and 180*C (two phase).

Fatigue Yes Fatigue damage results from prog:*ssive, localized structural change in [5]

materials subjected to fluctuating stresses and strains. Associated failures [6]

may occur at either high or low cycles in response to various kinds of [2]

loads (e.g., Mechanical or vibrational loads, thermal cycles, or pressure cycles). Fatigue cracks initiate and propagate in regions of stren concentration that intensify strain. The fatigue life of a component is a function of several variables such as stress level, stress state, cyclic wave form, fatigue environment, and the metallurgical condition of the material. Failure occurs when the endurance limit r. amber of cycles (for a given load amplitude) is exceeded. All materials are susceptible (with varying endurance limits) when subjected to cyclic loading. Vibration loads have also been the cause of recurring weld failures by the fatigue of small socket welds. Certain piping locations, such as charging lines, have been found to experience vibration conditions. In some cases these failures in pipe have been due to inadequately supported pipe or obturator induced vibratory loads.

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t U i evision 1 Page 3 of 11 Date: March 19,1996 l

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST C System: Main Feedwater System (045)

( Equipment Type: ELEMENT l ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Fouling Yes Unavoidable introduction of foreign substances that interact with and/or [8]

collect within system and components. Caused by failure or degradation [9]

! of upstream removal process equipment, long term buildup, low flow, [10]

stagnant flow, infrequent operation, and/or contaminated inlet flow.

Fouling refers to all deposits on system surfaces that increase resistance to fluid flow and/or heat transfer. Sources of fouling include the j following: (1) organic films of micro-organisms and their products l (microbial fouling)(2) deposits of macro-orsanisms such as mussels

(macrobial fouling)(3) inorganic deposits, including scales, silt, corrosion products and detritus. Scales result when solubility limits for a  ;

given species are exceeded. Deposits result when coolant-borne particles drop onto surfaces due to hydraulic factors. The deposits result in reduced -

flow of cooling water, reduced heat transfer, and increased corrosion. 1 Sediment deposits promote concentration cell corrosion and growth of  !

sulfur-reducing bacteria. The bacteria can cause severe pitting after one month of service. Piping systems designed for 30 years have had their projected life reduced to five years due to under-sediment corrosion.

i ., Galvanic Yes Accelerated corrosion caused by dissimilar metals in contact in a [11]

Corrosion conductive solution. Requires two dissimilar metals in physical or 3 electrical contact, developed potential (material dependent), and conducting solution.

General Yes Thinning (wastage) of a metal by chemical attack (dissolution) at the [6]

Corrosion surface of the metal by an aggressive environment. The consequences of [7]

the damage are loss ofload carrying cross-sectional area. General [2] l corrosion requires an aggressive environment and materials susceptible to i that environment. An important concern for PWRs is boric acid attack of carbon steels. Borated water has been observed to leak from piping, valves, storage tanks, etc., and fall on other carbon steel components and attack the component from the outside. Wastage is not a concern for austenitic stainless steel alloys.

l Revision 1 Page 4 of I I Date: March 19,1996

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Component Aging Management Review NITACIIMENT 7, POTENTIAL ARDM LIST 1 r~~

( System: Main Feedwater System (04M Equipment Type: ELEMENT ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) liydrol,In Yes Two forms of hydrogen attack relevant to light water reactor materials Damage

[5]

and conditions are hydrogen blistering and hydrogen embrittlement. [6] '

Both produce mechanical damage in the affected component. In each case, atomic hydrogen enters the metal, either as a result of a corrosion  !

reaction at the surface or by cathodic polarization which results in the evolution of hydrogen gas. In blistering, molecular hydrogen within the metal causes high pressure and local damage in the form of"Histered" ,

regions of the metal surface. Ilydrogen embrittlement affects ferritic and martensitic iron-based alloys, and results in low ductility intergranular -

cracking (similar to stiess corrosion cracking). The phenomenon of hydrogen cracking is usaally manifested as delayed cracking, at or near room temperature, after strt ss is applied. A certain critical stress, which may take the form of weld residual stress, is required to cause cracking.

Notches concentrate such nresses and tend to shorten the delay time for cracking. Cracking of welds due to hydrogen embrittlement ard hydrogen-induced cracking is a common concern. This cracking is more ,

of a problem in higher strength steels (yield strength >l20 ksi). I erritic

., and martensitic stainless steels, carbon steels, and other high strength alloys are susceptible. Austenitic stainless steels are relatively immune but could experience damage at sufficiently high hydrogen levels.

Intergranular Yes Intergranular Attack (IGA) is very similar to intergranular stress [5]

Attack corrosion cracking (IGSCC) except that stress is not required for IGA.

~

[6]

IG A is localized corrosion at or adjacent to grain boundaries, w ith [2]

relatively little corrosion of the material grains. It is caused by impurities [11]

in the grain boundaries, or the enrichment or depletion of alloying elements at grain boundaries, such as the depletion of chromium at austenitic stainless steel grain boundaries. A " sensitized" microstructure causes susceptibility to IGA. Whcn austenitic stainless steels are heated into or slow cooled through the temperature range of approximately 750 to 1500'F, chromium carbides can be formed, thus depleting the grain boundaries of chromium and decreasing their corrosion resistance, liigh chromium ferritic stainless steels, such as Type 430, also experience susceptibility to IGA. Nickel alloys such as alloy 600 experience IG A in the presence of certain sulfur environments at high temperatures (by forming low melting sulfur compounds at grain boundaries) or when austenitic stainless steel weld filler metal is inadvertently used on Ni-Cr-Fe alloys. Susceptibility to intergranular attack (sensitization) usually develops during thermal processing such as welding or heat treatments.

Revision i Page 5 of I1 Date: March 19,1996

l Component Aging Management Review NI'TACllMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: ELEMENT l

i ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Irradiation No Not applicable to Equipment Type. The ARDM results in a decrease in [5]

Embrittlement steel fracture toughness due to long-term exposure to a fast flux of [6]

l neutrons. liigh neutron fluence levels can lead to embrittlement of te j reactor pressure vessel core beltline, as well as certain reactor intemals and core support structures. Control of material composition to low levels of Cu and Ni (and perhaps P and Si, to some extent) is beneficial in some cases, such as the reactor pressure vessel ferritic steel. Core support

(

' structure peak fluences as high as 1.0E+21 (e > Imev) are reached in some cases and can embrittle the austenitic stainless steels and alloy 600 material in these components. PWRs experience fluences of between 9.0E+18 and about 4.0E+ 19 (e > Imev) at the vessel beltline inside

! surface. Safe-ends and piping outside the vessel are not expected to

! experience irradiation significant enough to cause problems. However, l the embrittlement eifects due to low flux irradiation are not well understood. This ARDM is not applicable to this equipment type since l

j element components in the systems under evaluation are not located in l

areas where the neutron llux is high enough to cause this ARDM to l ., occur.

' MIC Yes Accelerated corrosion of materials resulting from surface microbiological [5]

activity. Sulfate reducing bacteria, sulfur oxidizers, and iron oxidizing [6]

bacteria are most commonly associated with corrosion effects. Most [2]

often results in pitting followed by excessive deposition of corrosiotr products. Stagnant or low flow areas are most susceptible. Any system l that uses untreated water, or is buried, is particularly susceptible.

Consequences range from leakage to excessive differential pressure and l

j flow blockage. Essentially all systems and most commonly-used j materiais are susceptible. Temperatures from about 50*F to 120 F are l most conducive to MIC. Experience in virtually all large industries is j common. Nuclear experience is relatively new, but also widespread.

MIC is generally observed in service water applications utilizing raw untreated water. Sedimentation aggravates the problem.

Oxidation No Not applicable to Equipment Type. The ARDM results from a chemical [6]

reaction at the surface of a material when subjected to an oxidizing [11]

i environment. Oxidation occurs at any temperature. Electrical ,

components experience degradation related to oxidation and are considered separately. Oxidation generally is not considered a degradation mechanism in metals of fluid systems in mild environments )

since this mechanism serves to protect materials by formation of a i passive layer. Other corrosion mechanisms (e.g. Corrosion fatigue, ]

crevice corrosion, erosion corrosion, general corrosion and pitting) can l result from oxidation / reduction reactions under specific aggressive I

i

! mechanical and chemical environment and are addressed separately. It could be considered a degradation mechanism at high temperatures, where a more rapid reaction between metal and oxygen is likely to occur.

} These temperatures do not occur in power plant applications under evaluation. Therefore, oxidation is not considered a potential ARDM for j

element components.

l Revision i Page 6 of 1 I Date: March 19,1996 l

Component Aging Management Review ATTACilMENT 7, POTENTIAL ARDM LIST i System: Main Feedwater Systern (045) Equipment Type: ELEMENT ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Particulate Yes The loss of material caused by mechanical abrasion due to relative [6]

Wear Erosion motion between solution and material surface. Requires high velocity Guid, en' rained particles, turbulent Dow regions, flow direction change, and/or impingement. Most materials are susceptible to varying degrees depending upon the severity of the environmental factors.

Pitting Yes A form of localized attack with greater corrosion rates at some locations [5]

than at others. Pitting can be very insidious and destructive, with sudden [6]

failures in high pressure epplications (especially in tubes) occurring by [2]

perforation. This form of corrosion essentially produces " holes" of [11]

varying depth to diameter ratios in the steel. These pits are, in many cases,611ed with oxide debris, especially for ferritic materials such as carbon steel. Deep pitting is more common with passive metals, such as austenitic stainless steels, than with non- passive metals. Pits are generally elongated in the direction of gravity. In many cases, erosion corrosion, fretting corrosion, and crevice corrosion can also lead to pitting. Corrosion pitting is an anodic reaction which is an autocatalytic process. That is, the corrosion process within a pit produces conditions which stimulate the continuing activity of the pit. High concentrations of impurity anions such as chlorides and sulfates tend to concentrate in the i oxygen- depleted pit region, giving rise to a potentially concentrated I

Q aggressive solution in this zone. Pitting has been found on the outside diameter of tubes where sludge or tube trale was present. It can also 1

occur at locations of relatively stagnant coolant or water, such as in carbon steel pipes for service water lines, and at crevices in stainless

( steel, such as at the stainless steel cladding between reactor pressure I vessel closure Danges. Pitting can become passia in some metals such as aluminum.

l Radiation Yes Non-metallics are susceptible to degradation caused by gamma radiation. [3]

Damage

( Saline Water No Not applicable to Equipment Type. Saline Water Attack has resulted in [2]

! Attack the degradation of reinforced concrete structures. The degradation mechanism involves water seepage into the concrete resulting in a high chloride environment for the reinforcing bars. The reinforcing bars corrode resulting in expansion that leads to cracking and spalling of the l concrete. Saline water attack is of particular concern for structures that l are inaccessible for routine inspection, and piping or other fluid components embedded in concrete. This ARDM is not applicable to element components since elements are not constructed of nor typically installed in concrete.

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l Revision i Page 7 of I1 Date: March 19,1996

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST l l System: Main Feedwater System (045) Equipment Type: ELEMENT 1

ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) l Selective Yes The removal of one element from a solid alloy by corrosion processes.

i Leaching

[l1)

The most common example is the selective removal of zine in brass (12]

l l alloys (dezincification). Similar processes occur in other alloy systems in which aluminum, iron, cobalt, chromium, and other elements are removed. There are two types, layer-type and plug-type. Layer-type is a l uniform attack whereas plug-type is extremely localized leading to i

pitting. Overall dimensions do not change appreciably. If a piece of l equipment is covered by debris or surface deposits and/or not inspected

! closely, sudden unexpected failure may occur in high pressure applications due to the poor strength of the remaining material. Requires susceptible materials and corrosive environment. Materials particularly l susceptible include zinc, aluminum, carbon and nickel. Environmental conditions include high temperature, stagnant aqueous solution, and porous inorganic scale. Acidic solutions and oxygen aggravate the mechanism.

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!O Revision i Page 8 of 11 Date: March 19,1996 l

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST System: .. Main Feedwater System (045) Equipment Type: ELEMENT l

ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) l Stress Yes Selective corrosive attack along or across material grain boundaries. [5]

j Corrosion Four particular mechanisms are known to exist: (1) Intergranular [6]

l Cracking (IGSCC), between the material grain boundaries. (2) Transgranular [2]

l (TOSCC), across the material grains along certain crystallographic planes. (3) Irradiation Assisted (IASCC), between the material grains after an incubation neutron dose which sensitizes the material. (4)

Interdendritic (IDSCC), between the dendrite interfaces. SCC requires applied or residual tensile stress, susceptible materials (such as austenitic stainless steels, alloy 600, alloy x-750, SAE 4340, and ASTM A289), and oxygen and/or ionic species (e.g., Chlorides / sulfates).

Common sources of residual stress include thermal processing and stress risers created during surface finishing, fabrication, or assembly. The heat laput during welding can result in a localized sensitized region which is j susceptible to SCC. IGSCC is a concern in stainless steel piping

depending on material condition and process fluid chemistry and also is a

)

potential concern in valve internals (Pil steel). While operating  !

., experience with carbon steel piping shows no evidence of

, environmentally assisted cracking, laboratory studies do indicate a m susceptibility to SCC. Screening tests on SA106b and SA333GR6 indicate that severe combinations of cyclic applied stress and high -

temperature oxygenated water can result in environmentally enhanced cracking. TGSCC may be a concern in stainless steelif aggressive chemical species (caustics, halogens, sulfates, especially if coupled with the presence of oxygen) are present. TGSCC was thought to be inactive in low alloy steel, however, recent data suggests that the mechanism may operate. I ASCC is a potential concern only for reactor vessel internals and other stainless steel components, such as control rods, which are subject to very high neutron fluence levels. A fast neutron incubation i fluence of at least 1.0E+20 is generally required to sensitize the material.

IDSCC is a potential concern in stainless steel weld metal deposits based l

on microstructure and delta ferrite content. This mechanism is inactive in carbon and low alloy steel. Ammonia grooving in brass components can occur when the concentration of ammonia is greater than a few ppm. It is found :nost often in feedwater heaters that contain admiralty brass tubes and where morpholine, which breaks down into ammonia, is used to increase the pH of the condensate.

Stress Yes Stress Relaxation occurs under conditions of constant strain where part of [6]

Relaxation the elastic strain is replaced with plastic strain. A material loaded to an initial stress may experience a reduction in stress over time at high temperatures. Bolted connections are most vulnerable. Relaxation of stress on packing due to stretching of gland follower studs under elevated temperatures may cause packing leakage.

Thermal Yes Non-metallics are particularly susceptible with material dependent [6]

i p Damage temperature limits. [2]

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Revision 1 Page 9 of 1I Date: March 19,1996

i Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: ELEMENT ARDMS POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Thermal Yes Loss of material fracture toughness caused by thermally induced changes [6]

Embrittlement in the formation and distribution of alloying constituents. Requires high temperature 500*F to 700*F for metallic components. Ferrite containing stainless steels are susceptible as are materials with grain boundary segregation ofimpurities.

, Wear Yes Wear results from relative motion between two surfaces (adhesive wear), [1]

j from the influence of hard, abrasive particles (abrasive wear - see i

particulate erosion) or fluid stream (erosion), and from small, vibratory or sliding motions under the influence of a corrosive environment (fretting).

In addition to material loss from the above wear mechanisms, impeded relative motion between two surfaces held in intimate contact for extended periods may result from galling /self-welding. Motions may be linear, circular, or vibratcry in inert or corrosive environments. The most common result of w ear is damage to one or both surfaces involved in the contact. Wear most typically occurs in components which experience considerable relative motion such as valves and pumps, in components which are held under high loads with no motion for long periods (valves, l , flanges), or in clamped joints where relative motion is not intended but occurs due to a loss of clamping force (e.g., Tubes in supports, valve l stems in seats, springs against tubes). Wear may proceed at an ever-i increasing rate as worn surfaces moving past one another will often do so l with much higher contact stresses than the surfaces of the original geometry. Fretting is a wear phenomenon that occurs between tight-fitting surfaces subjected to a cyclic, relative motion of extremely small amplitude. Fretting is frequently accompanied by corrosion.

l Common sites for fretting are in joints that are bolted, keyed, pinned, press fit or riveted; in oscillating bearings, couplings, spindles, and seals; in press fits on shafts; and in universaljoints. Under fretting conditions, fatigue cracks may be initiated at stresses well below the endurance limit of nonfretted specimens.

l Revision 1 Page 10 of 1I Date: March 19,1996

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: ELEMENT Reference Lh1 Source Title

[1] ASME Wear Control Handbook, Peterson and Winer,1980

[2] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draft NRC Regulatory Guide No. DG-1009, December 1990

[3] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[4] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985

[5] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No.

NP 5461,1987

[6] Environmental Effects on Components: Commentary for ASME Section Ill, EPRI Report No. NP-5775, April 1988

[7] Boric Acid Corrosion of Carbon and Low Alloy Steel Pressure Boundary Materials, EPRI Report No. NP-5985,1988

[8] Nuclear Plant Service Water System Aging Degradation Assessment, NUREG/CR-5379, Volume I and 2, June 1989 and October 1992

[9] Aging Assessment ofinstrument Air Systems, NUREG/CR-5419, January 1990

[10] Insights Gained from Aging Research, NUREG/CR-5643, March 1992

[l1]

Corrosion Engineering, Fontana and Greene,1978

[12] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, O Third Edition,1985 m

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(G Revision i Page 11 of 11 Date: March 19,1996

I Component Aging Management Review ATTACIIMENT 3, COMPONENT GROUPING

SUMMARY

SHEET  ;

SYSTEM: Main Feedwater GROUP ID NUMBER: 045-TE-01 I GROUP ATTRIBUTES:

1. Device Type: TE

2. Vendor: NA

3. Model Number: NA 4.' Material: 21/4 Cr - 1 Mo Steel

5. Internal Environment: Controlled chemistry water at un to 435F

6. External Environment: Climate controlled atmospheric air (Auxiliary Bldg 3

7. Function: Maintain system oressure boundarv

8. Name Plate Data:

PARAMETER VALUE i System Temperature up to 435F System Pressure </= 1300 psig Material of Construction ASTM A182 - F22 (21/4 Ci - 1 Mo steel) i LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

Eauipment IQ Descrintion Equiement ID Descrintion ITE4516 11 FW S/G INL TEMP ELMNT ITE4517 - 12 FW S/G INL TEMP  ;

ELMNT '

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Component Agm.gwanagement Review ATTACIIMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION SYSTEM NUMBER- 045 SYSTEM NAME: Main Feedwater EQUIPMENT ID: NA GROUP ID: 045-TE-01 l: Subject to '-

Sub-Group ID Sub-Component!Name . . Manufacturer Material Model Number . Passive Intended Function (s) AMR (Replacement Pgm) (Source) (Source) ' (Source) ' (Source) - - (Y or N) 045-T E-01 A Thermow ett Bechtel 21/4 Cr - ASTM NA Maintain system pressure boundary Y A182,F22 (None) (92702) (92702) . (NA) (CLSR)

(6750 %1-355) (6750-M-355) 045-TE-01 B Thermocouple NA NA NA None (non pressure retaining) N (None) (NA) (NA) (NA) (NA) i L

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l Component Aging Management Review ATTACHMENT 5, ARDM MATRIX SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater i l EQUIPMENT TYPE: El.EMENT DEVICE TYPE: TE  !

GROUPID (if applicable): 045-TE-01 GROUP OR SUB GROUP ID ARDMs' 045-TE-01 A NA NA NA-CAVITATION EROSION 1 CORROSION FATIGUE 2 CREVICE CORROSION A DYNAMIC LOADING -3 l

EROSION CORROSION B FATIGUE 4  !

FOULING $ t GALVANIC CORROSION 6 GENERAL CORROSION C llYDROGEN DAMAGE 7 INTERGRANULAR ATTACK 8

. MIC 9 PARTICULATE WEAR EROSION 10 _

PlTTING A RADIATION DAMAGE II SELECTIVE LEACll!NG 12, STRESS CORROSION CRACKING 13 STRESS RELAXATION 14 TilERMAL DAMAGE I1 l TilERMAL EMBRITTLEMENT 15 WEAR 16

< O Revision 1 Page I of 1 Date: March 12,1996

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Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST

! (~~T SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater I ! ) EQUIPMENT TYPE: ELEMENT DEVICE TYPE: TE GROUP ID(if applicable): 045-TE-01 CODE DESCRIPTION SOURCE I The feedwater system fluid flow conditions, pressure and temperature do not result [5],[9]

, in cavitation at the thermowell. The flow is relatively steady and the pressure is

! much greater than the vapor pressure at system temperature. Therefore, cavitation erosion is not plausible.

2 Control of system chemistry results in limited corrosion, and fatigue is not [5]

plausible for the thermowells. Therefore, cortosion fatigue is not plausible.

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3 Normal service loads for the feedwater system do not result in significant vibration [1], [4J, or other dynamic loading conditions. The system pressure and flowrate are [5],[9],

i normally maintained steady. The stiffness of the thermowell eliminates How [13]

induced vibration. Based on these considerations, dynamic loading effects are not plausible.

4 The source of thermal cycling for the piping in which these thermowells are [5],[8],

l installed are plant start-ups/ shutdowns and secondary plant transients. Thermal [9],[13]

growth of the thermowell is unrestrained, therefore, no thermal stresses are created.

Additionally, vibrational effects are not ocurring (see 3. above). Based on these considerations, fatigue of the thermowell is not plausible.

5 Fouling does not affect the component function. The component mtended function [5],[10]

is to maintain the pressure boundary integrity only. Due to the control of feedwater

. chemistry, fouling (including contamination and sedimentation) is not expected.

Any fouling or sedimentation will not have an affect on the intended function.

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' p) 6 The thermowell material is Cr-Mo steel and the surrounding piping is carbon steel.

The feedwater system water chemistry is controlled to minimize conductivity. The

[6],[7],

[10], [13]

(d anodic material (carbon steel piping) surface area is large relative to the -

thermowell. Based on low conductivity electrolyte, and large anode surface area, the effects of galvanic corrosion are insignificant and will not affect the piping (or thermowell) intended function. Therefore, galvanic corrosion is not plausible.

7 The thermowell is not fabricated from the high strength steel susceptible to [5]

hydrogen embrittlement and cracking. Therefore, this ARDM is not plausible.

8 Carbon and low alloy steel material is not susceptible to intergranular attack. [5]

9 Microbiologically influenced corrosion is not plausible due to the chemical [5], [10]

conditions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through feedwater/ condensate chemistry control. Additionally, normal feedwater temperature is above 200F making MIC not possible.

10 Control of feedwater chemistry ensures essentially no particulate matter in the [10]

feedwater flowstream. Therefore, particulate wear erosion is not plausible.

1i The thermal damage and radiation damage ARDMs affect non-metallics only. [2],[5]

There are no non-metallic materials in these thermowells.

12 The Cr Mo steel material is not susceptible to selective teaching. Therefore, this [6],[1l}

ARDM is not plausible.

13 Control of feedwater chemistry (particularly oxygen concentration) prevents the [5],[10]

environment necessary for SCC of alloy steel material. Therefore, this ARDM is not plausible.

14 There are no prestressed parts to the thermowell assembly, therefore, stress [13]

relaxation is not plausible.

15 The feedwater system operating temperature of ~ 435F max. is not sullicient to [9],[12]

result in embrittlement. Thermal embrittlement oflow alloy steels requires

[]

D temperatures greater than 650F.

Revision ! Page1of3 Date: April 16,1996

Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST A SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: ELEMENT DEVICE TYPE: TE GROUP ID (if applicable): 045-TE-01 CODE DESCRIPTION SOURCE 16 There are no moving parts in the thermowell assembly. Therefore, wear is not [13]

plausible.

A Crevice corrosion and pitting can occur in areas of the thermowell assembly that [5],[6],

are not exposed to the general flowstream such as in the area of the half-coupling [10]

attachment to the main piping, and other crevices. These areas may comprise small localized volumes of stagnant solution for which fluid chemistry may deviate from bulk system chemistry. liigher concentrations ofimpurities may exist in these crevices due to out-of-specification system chemistry during shutdown conditions and due to the stagnant How conditions of the crevice. The resulting degradation is highly localized pits or cracks. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of crevice corrosion and pitting.

The effects of crevice corrosion and pitting can not be dismissed due to the potential for crevice locations and potentially high impurity conccntrations in the system during shutdown conditions. Management of the effects of crevice corrosion and pitting should consist of: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of thermowell applications (from components in this group or representative applications in other portions of the plant) to an inspection to determine the extent oflocalized degradation.

B Erosion corrosion is plausible due to high velocity, high energy fluid flow [3),[5],

conditions. The effects of erosion corrosion include potentiady rapid wall thinning [9], [10]

to the point of pressure boundary failure. The control of feedwater system fluid (v) chemistry limits the rate and the cf fects of erosion corrosion. The feedwater system is monitored routinely for the effects of erosion corrosion by the plant erosion corrosion monitoring program. l Management of the effects of erosion corrosion of the thermowell components j should consist of.1) maintaining the current system chemistry control program, l and 2) subjecting a representative sample of thermowell applications (from components in this group or representative applications in other portions of the {

plant) to an inspection to determine the extent of erosion corrosion.

C General corrosion of the thermowells is plausible due to exposure of components [5],[6],

to potentially corrosive medium during shutdown periods and, to a lesser extent, [7], [10]

during operation. The rate of general corrosion is low due to the chromium content of the alloy steel material, however, exposure to high oxygen concentrations during shutdown conditions could result in general corrosion. The effects of general corrosion is wall thinning over a relatively large area and could result in pressure boundary failure if extensive. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of general corrosion. Management of the effects of general corrosion should consist of: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of thermowell applications (from components in this group or representative applications in other portions of the plant) to an inspection to determine the extent of general corrosion (i.e., wall thinning).

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(d Resision i Page 2 of 3 Date: April 16,1996

Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST i

SYSTEM NUMBER: 045 SYSTEM NAME:

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EQUIPMENT TYPE: El EMENT DEVICE TYPE:

Main Feedwater TE GROUP ID (if applicabic):

045-TE-01 Reference List Source Title

[1] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draft NRC Regulatory Guide No. DG-1009, December 1990

[2] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[3] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985

[4] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No.

NP-5461,1987

[5] Environmental Effects on Components: Commentary for ASME Section Ill, EPRI Report No. NP-5775, April 1988

[6] Corrosion Engineering, Fontana and Greene,1978

[7] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, .

Third Edition,1985

[8] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System, Unit I

[9] UFSAR, Rev.18; Chapter 4 - Reactor Coolant and Associated Systems, Chapter 10 - Steam and l Power Conversion Systems

., [10] CP-217, Rev. 5; Chemistry Specifications and Surveillance - Secondary System

, [11] Marks' Standard Handbook for Mechanical Engineers,8th Edition, McGraw-Hill

[12] Metals llandbook,9th Edition, Volumes I and 13, ASM e

[13] Drawing 92702, Rev. 3; Special Thermowell for Thermocouples and Test Wells I

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Revision i Page 3 of 3 Date: April 16,1996

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l Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: PIPE ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Cavitation Yes Localized material erosion caused by formation and collapse of vapor [6]  ;

l Erosion bubbles in close proximity to material surface. Requires fluid (liquid) flow and pressure variations which temporarily drop the liquid pressure below i the corresponding vapor pressure. Most materials are susceptible to  ;

varying degrees depending upon the severity of the environmental factors. j i

l. Corrosion Yes Plant equipment operating in a corrosive environment subjected to cyclic [6]

l Fatigue (fatigue) loading may initiate cracks and/or fail sooner than expected i based on analysis of the corrosion and fatigue loadings applied separately. )

Fatigue-crack initiation and growth usually follows a transgranular path, I although there are some cases where intergranular cracking has been observed. In some cases, crack initiation occurs by fatigue and is subsequently dominated by corrosion advance. In other cases, a corrosion mechanism (SCC) can be responsible for crack formation below the i fatigue threshold, and the fatigue mechanism can accelerate the crack

propagation. Corrosion-fatigue is a potentially active mechanism in both

! stainless steels as well as carbon and low alloy steels.

1 s Creep / No Not applicable to Equipment Type. The phenomenon results in [2]

Shrinkage dimensional changes in metals at high temperatures and in concrete subject to long term dehydration. This ARUM is not applicable to this equipment type since proper piping system design prevents this ARDM i from occuring (i.e., piping design standards adequately address this  !

ARDM). I l

Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or I

[5]

Corrosion shielded areas. It is associated with a small volume of stagnant solution [6]

caused by holes, gasket surfaces, lap joints, crevices under bolt heads, [11]

surface deposits, designed crevices for attaching thermal sleeves to safe-ends, and integral weld backing rings or back-up bars. The crevice must be wide enough to permit liquid entry and narrow enough to maintain stagnant conditions, typically a few thousandths of an inch or less. Crevice corrosion is closely related to pitting con osion and can initiate pits in many cases as well as leading to stress corrosion cracking.

In an oxidizing environment, a crevice can set up a differential aeration cell to concentrate an acid solution within the crevice. Even in a reducing environment, alternate wetting and drying can concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.

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Revision I page1of10 Date: March 15,1996

Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: PIPE ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE t

(YES/NO)

Dynamic Yes LWR components and structures are designed to accommodate loads that [5]

Loading are expected in service. Particular attention is given to limiting the effects [6]

of fatigue and significant plastic deformation or rupture. Experience has shown that while expected loads have been properly treated, dynamic

loads not explicitly considered during design have occurred in service l causing material degradation and component failure. Examples of l

un:xpected dynamic loads are vibration, water hammer, and unstable fluid l flow. Vibration dynamic loads are caused by the response of a component, l system or structure to oscillating input. Possible sources ofinput energy include rotating equipment and fluid flow. De most serious situations

arise when the input load synchronizes or nearly synchronizes with the l

natural frequency of the component, system, or structure. Examples of l

vibration-induced dynamic loading problems which have occurred in l LWRs include PWR core barrel vibration, main coolant pump shaft

! cracking, pipe weld fatigue cracking, and steam generator and condenser j tube failures. Tubes in heat exchangers tend to vibrate under the influence of crossflow velocities, possibly leading to tube or support damage. When l '

the vibration amplitude is high enough, the tubes impact and experience thinning at mid-span; when lower, fretting damage can occur at support g points. Although fatigue failure is a major concern due to vibration loads, simple loss of function may also occur in components such as bolting and valves. Flow-intluced vibration has been identified as the source of many safety relief valve (SRV) failures in high energy piping systems, causing leakage, chatter, premature pop-off, fretting, galling, fatigue and possible failure to operate when required. Water hammer loads are caused by

hydraulic pres

.ure wave effects associated with rapid changes in fluid l flow. These changes may be initiated by rapid valve or pump action, l particularly with large differential pressure across the valve or high fluid

! flow capacity through the pump. In other cases, water hammer may be l caused by rapid condensation of steam or liquid flashing to steam followed l by condensation with enough liquid in the system to transmit the pressure wave. Unanticipated water hammer loads have caused piping support failures, deformation of piping and internals, and valve and pump damage.

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Revision i Page 2 of 10 Date: March !5,1996

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST N

j System: Main Feedwater System (045) Equipment Type: PIPE I

l ARDM DESCRIPTION / JUSTIFICATION SOURCE l (YES/NO)

Erosion Yes Increased rate of attack on a metal because of the relative movement [4]

Corrosion between a corrosive fluid and the metal surface. Mechanical wear or [5] 1 abrasion can be involved, characterized by grooves, gullies, waves, holes [6]

l and valleys on the metal surface. Erosion is a mechanical action of a fluid l and/or particulate matter on a metal surface, without the influence of

! corrosion. Erosion corrosion failures can occur in a relatively short time I and are sometimes unexpected, since conosion tests are usually run under  !

static conditions. All equipment exposed to moving fluids is vulnerable- i in particular, piping (bcnds, tees, etc.), valves, pumps, propellers and impellers, heat exchanger tubing, turbine blades and wear plates are components which have experienced erosion corrosion. This is a serious problem in steam piping, heater drain piping, reheaters, and moisture separators due to high velocity particle impingement. Erosion corrosion has occurred in high and low pressure preheater tubes, low pressure preheaters, evaporators and feedwater heaters. Inlet tube corrosion occurs in heat exchangers, due to the turbulence of flow from the exchanger head l into the smaller tubes, within the first few inches of the tube. Such corrosion has been especially evident in condenser tubes and feedwater

, heaters. The occurrence of erosion corrosion is highly dependent upon

! A material of construction and the fluid flow conditions. Carboa or low j alloy steels are particularly susceptible when in contact with high velocity

, water (single or two phase) with turbulent flow, low oxygen and fluid pH l

< 9.3. Maximum erosion corrosion rates are expected in carbon steel at 130-140 C (single phase) and 180*C (two phase).

Fatigue Yes Fatigue damage results from progressive, localized structural change in [5] i' materials subjected to fluctuating stresses and strains. Associated failures [6]

may occur at either high or low cycles in response to various kinds of [2]

loads (e.g., Mechanical or vibrational loads, thermal cycles, or pressure i

cycles). Fatigue cracks initiate and propagate in regions of stress I l concentration that intensify strain. The fatigue life of a component is a function of several variables such as stress level, stress state, cyclic wave form, fatigue environment, and the metallurgical condition of the material.

Failure occurs when the endurance limit number of cycles (for a given load amplitude)is exceeded. All materials are susceptible (with varying endurance limits) when subjected to cyclic loading. Vibration loads have also been the cause of recurring weld failures by the fatigue of small socket welds. Certain piping locations, such as charging lines, have been l found to experience vibration conditions. In some cases these failures in pipe have been due to inadequately supported pipe or obturator induced ,

vibratory loads. j l

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D Revision 1 Page 3 of 10 Date

March 15,1996

r Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST i System: Main Feedwater System (045) Equipment Type: PIPE ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Fouling Yes Unavoidable introduction of foreign substances that interact with and/or [8]

collect within system and components. Caused by failure or degradation [9]

of upstream removal process equipment, long term buildup, low flow, [10]

stagnant flow, infrequent operation, and/or contaminated inlet flow.

Fouling refers to all deposits on system surfaces that increase resistance to fluid flow and/or heat transfer. Sources of fouling include the following:

(1) organic films of micro-organisms and their products (microbial fouling)(2) deposits of macro-organisms such as mussels (macrobial fouling) (3) inorganic deposit:, including scales, silt, corrosion products and detritus. Scales result when solubility limits f( a given species are exceeded. Deposits result when coolant-borne part., les drop onto surfaces j due to hydraulic factors. The deposits result in reducs d flow of cooling water, reduced heat transfer, and increased co'rrosion. Sediment deposits promote concentration cell corrosion and growth of sulfur-reducing bacterit The bacteria can cause severe pitting after one month of service.

i Piping systems designed for 30 years have had their projected life reduced to five years due to under-sediment corrosion.

Galvanic Yes Accelerated corrosion caused by dissimilar metals in contact in a [I1]

j Corrosion conductive solution. Requires two dissimilar metals in physical or V) electrical contact, developed potential (material dependent), and conducting solution.

General Yes Thinning (wastage) of a metal by chemical attack (dissolution) at the [6] l Corrosion surface of the metal by an aggressive environment. The consequences of [7] i the damage are loss ofload carrying cross-sectional area. General [2]

corrosion requires an aggressive environment and materials susceptible to 4 that environment. An important concern for PWRs is boric acid attack of I carbon steels. Borated water has been observed to leak from piping, l

valves, storage tanks, etc., and fall on other carbon steel components and attack the component from the outside. Wastage is not a concern for austenitic stainless steel alloys.

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i Revision 1 Page 4 of 10 Date: March 15,1996

Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST

/~N d System:

Main Feedwater Svstem (045) Equipment Type: PIPE ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) l liydrogen Yes Two forms of hydrogen attack relevant to light water reactor materials and [5]

Damage conditions are hydrogen blistering and hydrogen embrittlement. Both [6]

produce mechanical damage in the affected component. In each case, atomic hydrogen enters the metal, either as a result of a corrosion reaction at the surface or by cathodic polarization which results in the evolution of hydrogen gas. In blistering, molecular hydrogen within the metal causes high pressure and local damage in the form of " blistered" regions of the metal surface. Hydrogen embrittlement affects ferritic and martensitic iron-based alloys, and results in low ductility intergranular cracking (similar to stress corrosion cracking). The phenomenon of hydrogen cracking is usually manifested as delayed cracking, at or near room temperature, after stress is applied. A certain critical stress, which may take the form of weld residual stress, is required to cause cracking.

Notches concentrate such stresses and tend to -honen the delay time for cracking Cracking of welds due to hydrogen embrittlement and hydrogen-induced cracking is a common concem. This cracking is more of a problem in higher strength steels (yield strength >l20 ksi). Ferritic

., and martensitic stainless steels, carbon steels, and other high strength

. alloys are susceptible. Austenitic stainless steels are relatively immune but could experience damage at sufficiently high hydrogen levels.

Intergranular Yes Intergranular Attack (IGA) 4 very similar to intergranular stress corrosion [5]

Attack cracking (IGSCC) except that stress is not required for IGA. IG A is [6]

localized corrosion at or adjacent to grain boundaries, with relatively little [2]

corrosion of the material grains. It is caused by impurities in the grain [11]

boundaries, or the enrichment or depletion of alloying elements at grain boundaries, such as the depletion of chromium at austenitic stainless steel .

grain boundaries. A " sensitized" microstructure causes susceptibility to IGA. When austenitic stainless steels are heated into or slow cooled through the temperature range of approximately 750 to 1500 F, chromium carbides can be formed, thus depleting the grain boundnies of chromium and decreasing their corrosion resistance. High chromium ferritic stainless steels, such as Type 430, also experience susceptibility to IGA. Nickel alloys such as alloy 600 experience IGA in the presence of certain sulfur environments at high temperatures (by forming low melting sulfur compounds at grain boundaries) or when austenitic stainless steel weld filler metal is inadvertently used on Ni-Cr-Fe alloys. Susceptibility to intergranular attack (sensitization) usually develops during thermal processing such as welding or heat treatments.

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Revision 1 Page 5 of 10 Date: March 15,1996 i

l Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST

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System: Main Feedwater System (049 Equipment Type: PIPE i

l ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Irradiation No Not epplicable to Equipment Type. The ARDM results in a decrease in [5]

Embrittlement steel fracture toughness due to leng-term exposure to a fast flux of [6]

neutrons. High netaron fluence levels can lead to embrittlement of the reactor pressure vessel core beltline, as well as certain reactor internals and

! core support structures. Control of material composition to low levels of Cu and Ni (and perhaps P and Si, to some extent) is beneficial in some cases, such as the reactor pressure vessel ferritic steel. Core support structure peak fluences as high as 1.0E+21 (e > Imev) are reached in some cases and can embrittle the austenitic stainless steels and alloy 600 material in these components. PWRs experience fluences of between 9.0E+18 and about 4.0E+19 (e > Imev) at the vessel beltline inside

surface. Safe-ends and piping outside the vessel are not expected to l experience irradiation siFnificant enough to cause problems. However, the l embrittlement effects due to low flux irradiation are not well understood.

l This ARDM is not applicable to this equipment type since piping l components are not located in areas where the neutron flux is high enough l to cause this ARDM to occur.

, MIC Yes Accelerated corrosion of materials resulting from surface microbiological [5J activity. Sulfate reducing bacteria, sulfur oxidizers, and iron oxidizing [6]

bacteria are most commonly associated with corrosion effects. Most often [2]

' results in pitting followed by excessive deposition of corrosion products.

Stagnant or low flow areas are most susceptible. Any system that uses l untreated water, or is buried, is particularly susceptible. Consequerces i range from leakage to excessive differential pressure and flow blockage.

Essentially all systems and most commonly-used materials are susceptible.

Temperatures from about 50*F to 120 F are most conducive to MIC.

I Experience in virtually all large industries is common. Nuclear experience l is relatively new, but also widespread. MIC is generally observed in

! service water applications utilizing raw untreated water. Sedimentation aggravates the problem.

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Oxidation No Not applicable to Equipment Type. The ARDM results from a chemical [6}

reaction at the surface of a material when subjected to an oxidizing [11]

environment. Oxidation occurs at any temperature. Electrical components experience degradation related to oxidation and are considered separately. Oxidation generally is not considered a degradation mechanism in metals of fluid systems in mild environments since this mechanism serves to protect materials by formation of a passive layer. Other corrosion mechanisms (e.g. Corrosion fatigue, crevice corrosion, erosion corrosion, general corrosion and pitting) can result from l

oxidation / reduction reactions under specific aggressive mechanical and

! chemical environment and are addressed separately. It could be

considered a degradation mechanism at high temperatures, where a more

, rapid reaction between metal and oxygen is likely to occur. These i temperatures do not occur in power plant applications under evaluation.

, Therefore, oxidation is not considered a potential ARDM for piping.

Revision 1 Page 6 of 10 Date: March 15,1996

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Component Aging Management Review ,

1 ATTACIIMENT 7, POTENTIAL ARDM LIST '

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[ System: Main Feedwater System (04M Equipment Type: PIPE ,

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ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO) 1 Particulate Yes The loss of material caused by mechanical abrasion due to relative motion [6] l Wear Erosion between solution and material surface. Requires high velocity fluid,  !

entrained particles, turbulent flow regions, flow direction change, and/or j impingement. Most materials are susceptible to varying degrees i l depending upon the senrity of the environmental factors.

j Pitting Yes A form oflocalized attack with greater corrosion rates at some loco..as [5] '

l than at others. Pitting can be very insidious and destructive, with sudden [6]

l failures in high pressure applications (especially in tubes) occurring by [2]

l perforation. This form of corrosion essentially produces " holes" of [11]

varying depth to diameter ratios in the steel. These pits are,in many cases, filled with oxide debris, especially for ferritic materials such as carbon i steel. Deep pitting is more common with passive metals, such as austenitic stainless steels, than with non- passive metals. Pits are generally elongated in the direction of gravity. In many cases, erosion corrosion, fretting corrosion, and crevice corrosion can also lead to pitting. Corrosion pitting is an anodic reaction which is an autocatalytic process. That is, the

., corrosion process within a pit produces conditions which stimulate the

, continuing activity of the pit. High concentrations ofimpurity anions such g' as chlorides and sulfates tend to concentrate in the oxygen- depleted pit i region, giving rise to a potentially concentrated aggressive solution in this zone. Pitting has been found on the outside diameter of tubes where sludge or tube scale was present. It can also occur at locations of relatively stagnant coolant or water, such as in carbon steel pipes for service water lines, and at crevices in stainless steel, such as at the stainless steel cladding between reactor pressure vessel closure flanges. Pitting can I

become passive in some metals such as aluminum.

Radiation Yes Non-metallics are susceptible to degradation caused by gamma radiation. [3]

Damage i Saline Water Yes Saline Water Attack has resulted in the degradation of reinforced concrete [2]

Attack structures. The degradation mechanism involves water seepage into the  :

concrete resulting in a high chloride environment for the reinforcing bars.

, The reinforcing bars corrode resulting in expansion that leads to cracking and spalling of the concrete. Saline water attack is of particular concern for structures that are inaccessible for routine inspection, and piping or other fluid compcnents embedded in concrete.

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l Revision i Page 7 of to Date: March 15,1996 l

Component Aging Management Review ATTACllMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: PIPE ARDM PONTIAI' DESCRIPTION / JUSTIFICATION SOURCE I (YES/NO) 1 Selective Yes The removal of one element from a solid alloy by corrosion processes. [I1]

Leaching The most common example is the selective removal of zine in brass alloys [12] )

(dezincification). Similar processes occur in other alloy systems in which aluminum, iron, cobalt, chromium, and other elements are removed.

There are two types, layer-type and plug-type. Layer-type is a uniform ,

attack whereas plug-type is extremely localized leading to pitting. Overall  !

dimensions do not change appreciably. If a piece of equipment is covered by debris or surface deposits and/or not inspected closely, sudden unexpected failure may occur in high pressure applications due to the poor strength of the remaining material. Requires susceptible materials and corrosive environment. Materials particularly susceptible include zinc, aluminum, carbon and nickel. Environmental conditions include high temperature, stagnant aqueous solution, and porous inorganic scale.

Acidic solutions and oxygen aggravate the mechanism.

Stress Yes Selective corrosive attack along or across material grain boundaries. Four [5]

Corrosion particular mechanisms are known to exist: (1) Intergranular (IGSCC), [6] t Cracking between the material grain boundaries. (2) Transgranular (TGSCC), [2]

across the material grains along certain crystallographic planes. (3)

A Irradiation Assisted (IASCC), between the material grains after an lj incubation neutron dose which sensitizes the material. (4) Interdendritic (IDSCC), between the dendrite interfaces. SCC requires applied or residual tensile stress, susceptible materials (such as austenitic stainless steels, alloy 600, alloy x-750, SAE 4340, and ASTM A289), and oxygen and'or ionic species (eg., Chlorides / sulfates).

Common sources of residual stress include thermal processing and stress risers created during surface finishing, fabrication, or assembly. The heat input during welding can result in a localized sensitized region which is susceptible to SCC. IGSCC is a concern in stainless steel piping depending on material condition and process fluid chemistry and also is a potential concern in valve internals (PII steel). While operating experience with i l carbon steel piping shows no evidence of environmentally assisted cracking, laboratory studies do indicate a susceptibility to SCC. Screening i tests on SA106b and SA333GR6 indicate that severe combinations of cyclic applied stress and high temperature oxygenated water can result in environmentally enhanced cracking. TGSCC may be a concern in stainless l steel if aggressive chemical species (caustics, halogens, sulfates, especially

! if coupled with the presence of oxygen) are present. TGSCC was thought to be inactive in low alloy steel, however, recent data suggests that the mechanism may operate. IASCC is a potential concern only for reactor vessel internals and other stainless steel components, such as control rods,

which are subject to very high neutron fluence levels. A fast neutron j incubation fluence of at least 1.0E+20 is generally required to sensitize the material.

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IDSCC is a potential concern in stainless steel weld metal deposits based on microstructure and delta ferrhe content. This mechanism is inactive in 1 l

l Revision 1 Page 8 of to Date: March I5,1996 l __

Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST System: . . Main Feedwater System (045) Equipment Type: PIPE ARDM POTENTIAL I)ESCRIPTION/ JUSTIFICATION SOURCE (YES/NO) carbon and low alloy steel. Ammonia grooving in brass components can occur when the concentration of ammonia is greater than a few ppm. It is found most often in feedwater heaters that contain admiralty brass tubes and where morpholine, which breaks down into ammonia, is used to increase the pli of the condensate.

Thermal Yes Non-metallics are particularly susceptible with material dependent [6]

Damage temperature limits.

[2]

Thermal Yes Loss of material fracture toughness caused by thermally induced changes (6]

Embrittlement in the formation and distribution of alloying constituents. Requires high temperature 500'F to 700'F for metallic components. Ferrite containing stainless steels are susceptible as are materials with grain boundary segregation ofimpurities.

Wear No Not applicable to equipment type. There are no moving parts in this [1]

equipment type.

4 O

Revision 1 Page 9 of 10 Date: March I5,1996

Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: PIPE Reference List Source Title

[1] ASME Wear Control llandbook, Peterson and Winer,1980

[2] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draft NRC Regulatory Guide No. DG 1009, December 1990

[3] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[4] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985

[5] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No.

NP-5461,1987

[6] Environmental Effects on Components: Commentary for ASME Section III, EPRI Report No. NP-5775, April 1988

[7] Boric Acid Corrosion of Carbon and Low Alloy Steel Pressure Boundary Materials, EPRI Report No. NP 5985,1988

[8] Nuclear Plant Service Water System Aging Degradation Assessment, NUREG/CR-5379, Volume 1 and 2, June 1989 and October 1992

[9] Aging Assessrnent ofInstrument Air Systems, NUREG/CR-5419, January 1990

[10] Insights Gained from Aging Research, NUREG/CR-5643, March 1992

'. [11] Corrosion Engineering, Fontana and Greene,1978

[12] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, )

A Third Edition,1985 j

Q Revision i Page 10 of 10 Date: March 15,1996

i Component Aging Management Review ATTACHMENT 3, COMPONENT GROUPING

SUMMARY

SHEET SYSTEM: Main Feedwater (045)

GROUP ID NUMBER: 045-DB-01 GROUP ATTRIBUTES: ,

1. Device Type: -DB I

2. Vendor: NA l

3. Model Number: NA

4. Material: Carbon Steel i

5. Internal Environment: Controlled chemistrv vater at 435F (normal oneration) I

6. External Environment: Climate controlled atmosnheric air (Containment Bldg 3 1

7. Function: Maintain system nressure boundarv  !

8. Name Plate Data:

PARAMETER VALUE l

System Temperature Variable from ambient (70F) when i

shutdown to 435F when operating (subject to thermal transient conditions due to thermal stratification near S/G nozzle at HSB, plant start-up

/ shutdown, and operational transients)

System Pressure </= 1300 psig Materials of Construction Carbon Steel-seamless ASTM A-106 piping, cast steel ASTM A-234 fittings (alternate material for 1-DBI-1018, 1019 piping and fittings: Cr-Mo per M600C)

Joints Butt welded, except socket welded for 2" and smaller branch lines 1

i LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

Eauinment ID Descrintion Eauinment ID Descrintion 1-DB1-1018 FW SYSTEM PIPING 2-DB1-2018 FW SYSTEM PIPING l-DBI-1019 FW SYSTEM PIPING 2-DBI-2019 FW SYSTEM PIPING r

k Revision i Page1ofI Date: March 15,1996

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Component Aging Management Review ATTACIIMENT 3, COMPONENT GROUPING

SUMMARY

SIIEET

! n SYSTEM: Main Feedwater(045)

GROUP ID NUMBER: 045-DB-02 GROUP ATTRIBUTES:

l 1. Device Type: -DB

2. Vendor: NA

3. Model Number: NA

4. Material: Carbon Steel

5. Internal Environment: Controlled chemistry water at 435F (normal operation)

6. External Environment: Climate controlled atmospheric air (Auxiliary Bldg.)

7. Function: Maintain system oressure boundarv

8. Name Plate Data:

PARAMETER VAIUE System Temperature Variable from ambient (70F) when shutdown to 435F when operating (subject to thermal transient conditions due to plant start-up /

shutdown and operational transients) '

System Pressure </= 1300 psig Materials of Construction Carbon Steel-seamless ASTM A-106 piping, cast steel ASTM A-234 fittings (alternate material for 1-DB3-

• 1001,-1002 piping and fittings: Cr-Mo per M600C)

~

Joints Butt welded, except socket welded for 2" and smaller branch lines LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

Equipment ID Descriotion Equinment ID Descriotion 1-DB3-100i FW SYSTEM PIPING 2-DP3-2001 FW SYSTEM PIPING l-DB3-1002 FW SYSTEM PIPING 2-DB3-2002 FW SYSTEM PIPING l

v Revision i Page1ofI Date: March 15,1996

Component Aging Management Review

ATTACHMENT 5, ARDM MATRIX f3 Q SYSTEM NUMBER

EQUIPMENT TYPE:

045 PIPE SYSTEM NAME:

DEVICE TYPE:

Main Feedwater

-DB i GROUP ID(if applicable): NA GROUP OR SUB GROUP ID ,

l ARDMs :. i0j5-DB 045-DB-02 NA- l NA-CAVITATION EROSION 1 1 i

CORROSION FATIGUE A 2 CREVICE CORROSION B B

, DYNAMIC LOADING 3 3 l.

! EROSION CORROSION C C FATIGUE D 4

FOULING 5 5 l

l GALVANIC CORROSION 6 6 GENERAL CORROSION E E ,

4 IlYDROGEN DAMAGE 7 7

. INTERGRAllULAR ATTACK B 8 MIC 9 9 PARTICULATE WEAR EROSION Id 10 PITTING B B RADI ATION DAMAGE 11 11 SALINE WATER ATTACK 12 12 SELECTIVE LEACllING 13 13 STRESS CORROSION CRACKING 14 14 l

THERMAL DAMAGE 11 11 TiiERMAL EMBRITTLEMENT 15 15 i

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Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST f- m SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater l

(') EQUIPMENT TYPE:

GROUP ID (if applicable):

PIPE NA DEVICE TYPE: -DB CODE DESCRIPTION SOURCE 1 The feedwater system fluid flow conditions, pressure and temperature do not result [5], [l 1]

in cavitation conditions in the piping. The flow is relatively steady and the pressure is much greater than the v por pressure at system temperature. Therefore, cavitation erosion is not plausible.

2 Control of system chemistry results in limited corrosicn, and thermal fatigue for [5]

this piping is conservatively bounded by design code requirements (see Code 4 below). Therefore, corrosion fatigue is not plausible.

3 Normal service loads for feedwater piping do not result in significant vibration or [1],[4],

other dynamic loading conditions. 'The system pressure is normally maintained [5],[10],

steady. The transient effects of abnormal conditions, such as water hammer, aie [11]

=

not considered routine and do not result in cumulative degradation of the piping.

Based on these considerations, the effects of dynamic loading are negligible and will not affect the piping function.

4 The feedwater piping components in this group are far removed from the S/G, and [5],[8],

are not subject to rapid thermal transient conditions associated with the S/G [9], [11],

feedwater nozzle / piping thermal stratification conditions. The source of thermal [12],[13],

cycling for the piping in this group is plant start-ups/ shutdowns and sccondary [19], [20] j plant transients. These thermal cycles are conservatively enveloped by the design i code requirements associated with this piping (ANSI B31.7/B31.1 rules for calculating allowable stress range for expansion stresses) which allow 7000 full

{

j temperature range cycles before applying additional stress limitations. The code O requirements conservatively envelope expected plant thermal transients through the V period of extended operation, therefore, thermal fatigue is not considered plausible ,

for this group of piping components. I 5 Fouling does not affect the component function. The component intended function [5], [ 16]

, is to maintain the pressure boundary integrity only. Due to the control of feedwater chemistry, fouling (including contamination and sedimentation) is not expected.

Any fouling or sedimentation will not have an affect on the intended function.

6 Piping material is all carbon steel (with potentially Cr-Mo steel also) and water [6], [16]

chemistry is controlled. Therefore, the required galvanic cell and electrolyte are not present, and galvanic corrosion is not plausible.

7 The piping is not fabricated from *he high strength steel susceptible to hydrogen [5]

embrittlement and cracking. Therefore, this ARDM is not plausible.  ;

8 Carbon steel material is not susceptible to intergranular attack. [5]

9 Microbiologically influenced corrosion is not plausible due to the chemical [5], [16]

conditions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through j feedwater/ condensate chemistry control. Additionally, normal feedwater temperature is above 200F making MIC not possible.

10 Control of feedwater chemistry ensures essentially no particulate matter in the [16]

feedwater flowstream. Therefore, particulate wear erosion is not plausible.

11 The thermal damage and radiation damage ARDMs affect non-metallics only. [2],[5]

There are no non-metallic materials in these piping groups.

12 The effects of sahne water attack. is potentially applicable only to piping in contact [l], [l 1]

with concrete and exposed to moisture (i.e., embedded pipe). There is no embedded pipe in these piping groups of components.

13 The carbon steel piping material is not susceptible to select 5 leaching. Therefore, [6], [ 17]

i this ARDM is not plausible.

V Revision ! Page 1 of 4 Date: April 16, '9%

1 Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST 73 SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater

, ! EQUIPMENT TYPE: PIPE DEVICE TYPE: -DB GROUP ID(if applicable): NA CODE DESCRIPTION SOURCE 14 Control of feedwater chemistry (particularly oxygen concentration) prevents the [5],[16]

environment necessary for SCC of carbon steel material. Therefore, this ARDM is not plausible.

15 The feedwater system operating temperature of- 435F max. is not suf ficient to [5],[11]

result in embrittlement. Thermal embrittlement ofplain carbon and low alloy steels requires temperatures greater than 650F A Corrosion fatigue is plausible due to the combination of fatigue and corrosion [5],[14],

mechanisms affecting this piping. It is characterized by accelerated crack [16],[18]

propagation at susceptible locations due to mechanism synergy's and can lead to component failure pric t to predicted failure due to corrosion or fatigue effects alone. Control of feedwater chemistry minimizes the corrosive effects of the fluid environment and monitoring the fatigue effects of thermal cycles provides

predictability of degradation. An evaluation of feedwater system piping thermal fatigue should be perfonned to easure that plant components that are currently monitored for the effects of fatigue are bounding for the feedwater piping.

Additionally, the system fluid chemistry should continue to be controlled to minimize conditions conducive to corrosion.

B Crevice corrosion and pitting can occur in areas of the piping system that are not [5j,[6],

exposed to the general flowstream such as areas oflack of.:omplete penetration in [16]

butt welds, clearances at socket weld fi+-ups, and other crevices. These areas may comprise small localized volumes of stagnant solution for which fluid chemistry I O

'V may deviate from bulk system chemistry. Higher concentrations ofimpurities may exist in these crevices due to out-of-specification system chemistry during shutdown conditions and due to the stagnant flow conditions of the crevice. The resulting degradation is highly localized pits or cracks. The control of j feedwater/ condensate system fluid chemistry significantly limits the effects of '

crevice corrosion and pitting. Additionally, controls over piping fit-up and

]

welding quality during construction :imit the locations of potential cresices in the i large bore piping. Most susceptible locations for crevices are the small bore branch

)

piping (drains and instrumentation taps) where socket welding creates potential crevices by design of the joint.

The effects of crevice corrosion and pitting can not be dismissed due to the potential for crevice locations and potentially high impurin ancentrations in the ,

system during shutdown conditions. Management of thi, Jfects of crevice l

corrosion and pitting should consist of: 1) maintenance of the current system j chemistry control program, and 2) subjecting a representative sample of piping locations (from piping in these groups or representative piping in other portions of '

the plant) to an inspection to determine the extent oflocalized degradation occurring in the feedwater piping.

C Erosion corrosion is plausible due to high velocity, high energy fluid flow [3J,[5J, conditions. The effects of erosion corrosion include potentially rapid pipe wall [11], [16) thinning to the point of pressure boundary failure. The control of feedw ater system fluid chemistry limits the rate and effects of erosion corrosion. The feedwater system is moaitored routinely for the effects of ercrion corrosion by the plant erosion corrosion monitoring program. The chemistry control program and the erosion corrosion monitoring program should be con inued through the period of extended operation in order to manage the effects of erosion corrosion.

C Resision I Page 2 of 4 l >.it e Apol 16.1996

Component Aging Management Review ATTACIIMENT 6 MATRIX CODE LIST SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: PIPE DEVICE TYPE: -DB GROUP ID(if applicabic); NA CODE DESCRIPTION D S O tJ R C E Fatigue due la thermal cycling of the feedwater piping in this group (low-cycle [5],[14],

fatigue) is plausible due to thermal stratification of the piping adjacent to the S/G

[15]

nozzle during hot stand-by and low power operating conditions. The resulting high number of thermal cycles to which the piping is subjected could result in fatigue damage accumulation to the point of crack initiation and propagation. An evaluation of feedwater system piping thermal fatigue should be performed to ensure that plant components that are currently monitored for the effects of fatigue are bounding for the feedwater piping.

E General corrosion of the feedwater system piping is plausible due to exposure of [5],[6],

carbon steel materials to corrosive medium during shutdown periods and, to a [7),[16]

lessor extent, during operation. The rate of general corrosion is low after the initial build-up of the protective corrosion film (magnetite). Exposure to high oxygen concentrations during shutdown and potential removal and re-creation of the corrosion film result in general corrosion. The effects of general corrosion is pipe wall thinning over a relatively large area and could result in pressure boundary failure if extensive. The control of feedwater/ condensate system fluid chemistry significantly limits the efTects of general corrosion. Management of the effects of general corrosion should consist of: 1) maintenance of the current system .)

t

~

• chemistry control program, and 2) subjecting a reprcsentative sample of piping

• locations (from piping in these groups or representative piping in other portions of the plant) to an inspection to determine the extent of general degradation occurring in the feedwater piping. Portions of the feedwater system piping inspected for the effects of erosion corrosion are thereby managed for the effects of general corrosion (i.e., wall thinning).

i 6

s e Revision i Page 3 of 4 Date: Apol 16,1996

.,,,,,r--~- - ' ^ ~ ~ ^ ' ' ' ^ " '

Component Aging Management Review ATTACliMENT 6, MATRIX CODE LIST SYSTEM NUMBER: '045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: PIPE DEVICE TYPE: -DB L V- . GROUP ID(if applicable): NA Reference IJ11 l

Source Title

! [1] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draft NRC Regulatory Guide No. DG-1009, December 1990

[2] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981 l

[3]_ Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP 3944,1985

-[4] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No.

j NP-5461,1987 l- [5] Environmental Effects on Components: Commentary for ASME Section III, EPRI Report No. NP-5775, April 1988

[6] Corrosion Engineering, Fontana and Greene,1978 l [7] Corrosion ar.d Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, l Third Edition,1985

[8] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System, Unit 1 l [9] Drawing 62702, Sheet 4. Rev. 30; Condensate and Feedwater System, Unit 2 l [10] OI-12A-1, Rev. 22/OI-12A-2, Rev.14; Feedwater System Operating Instructions

[11] UFSAR, Rev.18; Chapter 4 - Reactor Coolant and Associated Systems, Chapter 10 - Steam and

, Power Conversion Systems l [12] ANSI B31.1,1967; Power Piping Code

[13] ANSI B31.7,1969; Nuclear Power Piping Code

[14] CE-NPSD-634-P, April 1992; Fatigue Monitoring Program for CCNPP Units 1 and 2 -

[15] IRl-Ol l-785 ; S/G Feedwater Nozzle / Piping Thermal Stratification Issue Report

[16] CP-217, Rev. 5; Chemistry Specifications and Surveillance - Secondary System

[17] Marks' Standard llandbook for Mechanical Engineers,8th Edition, McGraw-Hill

[18] Metals llandbook,9th Edition, Volumes 1 and 13, ASM

[19] Drawing 12543A-01, Rev.13; Feedwater Piping Isometric, Unit I t

[20] . Drawing 13547A 20, Rev. 6F; 13547A-47, Rev 4; 13549A-26, Rev. 3; Feedwater Piping Isometric, Unit 2 f

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b Revision i Page 4 of 4 Date: April lo,1996 >

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Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST

(

( System: Main Feedwater System (045) Equipment Type: VALVE ARDM PONIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Cavitation Yes Localized material erosion caused by formation and collapse of vapor [7]

Erosion bubbles in close proximity to material surface. Requires fluid (liquid) flow and pressure variations which temporarily drop the liquid pressure below the corresponding vapor pressure. Most materials are susceptible to varying degrees depending upon the severity of the environmental factors.

Corrosion Yes Plant equipment operating in a corrosive environment subjected to cyclic [7]

Fatigue (fatigue) loading may initiate cracks and/or fail sooner than expected based on analysis of the corrosion and fatigue loadings applied separately.

Fatigue-crack initiation and growth usually follows a transgranular path, although there are some cases where intergranular cracking has been observed. In some cases, crack initiation occurs by fatigue and is subsequently dominated by corrosion advance. In other cases, a corrosion mechanism (SCC) can be responsible for crack formation below the fatigue threshold, and the fatigue mechanism can accelerate the crack propagation.

Corrosion-fatigue is a potentially active mechanism in both stainless steels as well as carbon and low alloy ster.ls.

.~

Creep / No Not applicable to Equipment Type. The phenomenon results in [2]

.O Shrinkage dimensional changes in metals at high temperatures and in concrete subject

(}

' to long term dehydration. This ARDM is not applicable to this equipment type since proper component specification and design prevents this ARDM from occuring (i.e., system and component design standards adequately address this ARDM).

Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or shielded [6]

Corrosion areas. It is associated with a small volume of stagnant solution caused by [7]

holes, gasket surfaces, lap joints, crevices under bolt heads, surface [12]

deposits, designed crevices for attaching thermal sleeves to safe-ends, and integral weld backing rings or back up bars. The crevice must be wide enough to permit liquid ei try and nanow enough to maintain stagnant conditions, typically a few thousandths of an inch or less. Crevice corrosion is closely related to pitting corrosion and can initiate pits in many cases as well as leading to tiress corrosion cracking. In an oxidizing environment, a crevice can iet up a differential aeration cell to concentrate an acid solution within the cwvice. Even in a reducing environment, alternate wetting and drymg ctn concentrate aggressive ionic species to cause pitting, crevice corrosiori, intergranular attack, or stress corrosion cracking.

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U,m Revision 1 Page 1 of 10 Date: March 15,1996 l

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Component Aging Management Review ATTACIIMENT 7, POTENTIAL ARDM LIST C System: Main Feedwater System (045) Equipment Type: VALVE I ARDM AL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Erosion Yes increased rate of attack on a metal because of the relative movement [5]

Corrosion between a corrosive fluid and the metal surface. Mechanical wear or [6]

abrasion can be insolved, characterized by grooves, gullie::, waves, holes [7]

and valleys on the metal surface. Erosion is a mechanical action of a fluid and/or particulate mattu on a metal surface, without the influence of corrosion. Erosion corrosion failures can occur in a relatively short time and are sometimes unexpected, since corrosion tests are usually run under static conditions. All equipment exposed to moving fluids is vulnerable; in particular, piping (bends, tees, etc.), valves, pumps, propellers and in pellers, heat exchanger tubing, turbine blades and wear plates are components which have experienced erosion corrosion. This is a serious problem in steam piping, heater drain piping, reheaters, and moisture l separators due to high velocity particle impingement. Erosion corrosion has occurred in high and low pressure preheater tube, low pressure preheaters, evaporators and feedwater heaters. Inlet tube corrosion occurs in heat exchangers, due to the turbulence of flow from the exchanger head into the smaller tubes, within the first few inches of the tube. Such corrosion has

., been especially evident in condemer tubes and feedwater heaters. The occurrence of erosion corrosion is highly dependent upon material of fN construction and the fluid flow conditions. Carbon or low alloy steels are particularly susceptible when in contact with high velocity water (single or two phase) with turbulent flow, low oxygen and fluid pH < 9.3. Maximum erosion corrosion rates are expected in carbon steel at 130-140 C (single phase) and 180 C (two phase).

Fatigue Yes Fatigue damage results from progressive, localized structural change in [6]

materials subjected to fluctuating stresses and strains. Associated failures [7]

may occur at either high or low cycles in response to various kinds ofloads [2]

(e.g., Mechanical or vibrational loads, thermal cycles, or pressure cycles).

Fatigue cracks initiate and propagate in regions of stress concentration that intensify strain. The fatigue life of a component is a function of several variables such as stress level, stress state, cyclic wave form, fatigue environment, and the metallurgical condition of the material. Failure occurs when the endurance limit number of cycles (for a given load amplitude) is exceeded. All materials are susceptible (with varying endurance limits) when subjected to cyclic loading. Vibration loads have also been the cause of recurring weld failures by the fatigue of small socket welds. Certain piping locations, such as charging lines, have been found to experience vibration conditions. In some cases these failures in pipe have been due to inadequately supported pipe or obturator induced vibratory loads.

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.b Revision i Page 2 of 10 I) ate: March 15,1996

Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST C System: Main Feedwater System (045) Equipment Type: VALVE ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (VES/NO)

Fouling Yes Unavoidable introduction of foreign substances that interact with and/or [9]

collect within system and components. Caused by failure or degradation of [10]

upstream removal process equipment, long term buildup, low flow, stagnant [11] ,

flow, infrequent operation, and/or contaminated inlet flow. Fouling refers to i all deposits on system surfaces that increase resistance to f'uid flow and/or  ;

, heat transfer. Sources of fouling include the following:(1) organic films of l micro-organisms and their products (microbial fouling)(2) deposits of j ~

macro-organisms such as mussels (macrobial fouling)(3) incrganic deposits, including scales, silt, corrosion products and detritus. Scales result J l 1 l when solubility limits for a given species are exceeded. Deposits result 1 j when coolant-borne particles drop onto surfaces due to hydraulic factors.

The deposits result in reduced flow of cooling water, reduced heat transfer, and increased corrosion. Sediment deposits promote concentration cell corrosion und growth of sulfur-reducing bacteria. The bacteria can cause severe pitting after one month of service. Piping systems designed for 30 years have had their projected life reduced to five years due to under-sediment corrosien.

.', Galvanic Yes Accelerated corrosion caused by dissimilar metals in contact in a [12]

Corrosion conductive solution. Requires two dissimilar metals in physical or electrical contact, developed potential (material dependent), and conducting solution.

./

General Yes Thinning (wastage) of a metal by chemical attack (dissolution) at the [7]

Corrosion surface of the raetal by an aggressive environment. The consequences of [8]

the damage are loss ofload carrying cross-sectional area. General corrosion [2]

requires an aggressive environment and materials susceptible to that environment. An important concern for PWRs is boric acid attack of carbon steels. Borated water has been observed to leak from piping, valves, storage tanks, etc., and fall on other carbon steel components and attack the component from the cutside. Wastage is not a concern for austenitic stainless steel alloys.

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Revision i Paa,e 3 of to Date: March 15.1996 s

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Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST i O System: Main Feedwater System (045) y/ Equipment Type: VALVE ARDM POTENTIAL DESCRIPTION /JUSTIGCATION SOURCE (YES/NO)

Hydrogen Yes Two forms of hydrogen attack relevant to light water reactor materials and [6]

Damage conditions are hydrogen blistering and hydrogen embrittlement. Both [7]

produce mechanical damage in the affected component. In each case, atomic hydrogen enters the metal, either as a result of a corrosion reaction at the surface or by cathodic polarization which results in the evolution of hydrogen gas. In blistering, molecular hydrogen within the metal causes high pressure and local damage in the form of " blistered" regions of the metal surface. Ilydrogen embrittlement affects ferritic and martensitic iron-based alloys, and results in low ductility intergranular cracking (similar to stress corrosion cracking). The phenomenon of hydrogen cracking is usually manifested as delayed cracking, at or near room temperature, aller  :

stress is applied. A certain critical stress, which may take the form of weld residual stress, is required to cause cracking. Notches concentrate such stresses and tend to shorten the delay time for cracking. Cracking of welds due to hydrogen embrittlement and hydrogen-induced cracking is a common concern. This cracking is more of a problem in higher strength steels (yield strength >l20 ksi). Ferritic and martensitic stainless steels,

., carbon steels, and other high strength alloys are susceptible. Austenitic

, stainless steds are relatively immune but could experience damage at sufGciently high hydrogen levels.

Intergranular Yes Intergranular Attack (IGA) is very similar to intergranular stress corrosion [6]

Attack cracking (IGSCC) except that stress is not required for IGA. IGA is [7]

localized corrosion at or adjacent to grain boundaries, with relatively little [2]

corrosion of the material grains. It is caused by impurities in the grain [12]

boundaries, or the enrichment or depletion of alloying elements at grain boundaries, such as the depletion of chromium at austenitic stainless steel grain boundaries. A " sensitized" microstructure causes susceptibility to IGA. When austenitic stainless steels are heated into or slow cooled through the temperature range of approximately 750 to 1500 F, chromium carbides can be formed, thus depleting the grain boundaries of chromium and decreasing their corrosion resistance. liigh chromium ferritic stainless steels, such as Type 430, also experience susceptibility to IGA. Nickel alloys such as alloy 600 experience IGA in the presence of certain sulfur environments at high temperatures (by forming low melting sulfur compounds at grain boundaries) or when austenitic stainless steel weld Gller metal is inadvertently used on Ni-Cr-Fe alloys. Susceptibility to intergranular attack (sensitization) usually develops during thermal processing such as welding or heat treatments.

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Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) VALVE Equipment Type:

TIAL ARDM DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Irradiation No Not applicable to Equipment Type. The ARDM results in a decrease in [6]

Embrittlement steel fracture toughness due to long-term exposure to a fast flux of neutrons. [7]

High neutron fluence levels can lead to embrittlement of the reactor pressure vessel core beltline, as well as certain reactor internals and core support structures. Control of material composition to low levels of Cu and Ni(and perhaps P and Si, to some extent) is beneficial in some cases, such as the reactor pressure vessel ferritic steel. Core support structure peak fluences as high as 1.0E+21 (e > Imev) are reached in some cases and can embrittle the austenitic stainless steels and alloy 600 material in these components. PWRs experience fluences of between 9.0E+18 and about 4.0E .9 (e > Imev) at the vessel beltline inside surface. Safe-ends and piping outside the vessel are not expected to experience irradiation significant enough to cause problems. However, the embrittlement effects due to low flux irradiation are not well understood. This ARDM is not applicable to this equipment type since valve components are not located in areas where the neutron flux is high enough to cause this ARDM to occur.

., MIC Yes . Accelerated corrosion of materials resulting from surface microbiological [6]

, activity. Sulfate reducing bacteria, sulfur oxidizers, and iron oxidizing [7]

p bacteria are most commonly associated with corrosion effects. Most often [2]

V results in pitting followed by excessive deposition of corrosion products.

Stagnant or low flow areas are most susceptible. Any system that uses untreated water, or is buried, is particularly susceptible. Consequences range from leakage to excessive differential pressure and flow blockage.

Essentially all systems and most commonly.used materials are susceptible.

Temperatures from about 50*F to 120'F are most conducive to MIC.

Experience in virtually all large industries is common. Nuclear experience is relatively new, but also widespread. MIC is generally observed in service water apphcations utilizing raw untreated water. Sedimentation aggravates the problem.

Oxidation No Not applicable to Equipment Type. The ARDM results from a Chemical [7]

reaction at the surface of a material when subjected to an oxidizing [12]

environment. Oxidation occurs at any temperature. Electrical components experience degradation related to oxidation and are considered separately.

Oxidation generally is not considered a deradation mechanism in metals of fluid systems in mild environments since this mechanism serves to protect materials by formation of a passive layer. Other corrosion mechanisms (e.g. Corrosion fatigue, cmvice corrosion, erosion corrosion, general corrosion and pitting) can result from oxidation / reduction reactions under specific aggressive mechanical and chemical environment and are addressed separately. It could be considered a degradation mechanism at high temperatures, w here a more rapid reaction between metal and oxygen is likely to occur. These temperatures do not occur in power plant appI; cations under evaluation. Therefore, oxidation is not considered a potential ARDM for valv: components.

Revision I l' age 5 of to Date: March 15,1996

l 4

l -i L Component Aging Management Review i

l ATTA CHMENT 7, POTENTIAL ARDM LIST

'( System: Main Feedwater System (045) Equipment Type: VALVE '

ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Particulate Yes The loss of material caused by mechanical abrasion due to relative motion [7]

Wear Erosion between solution and material surface. Requires high velocity fluid, i i

entrained particles, turbulent flow regions, flow direction change, and/or impingement. Most materials are susceptible to varying degrees depending upon the severity of the environmental factors. l Pitting Yes A form oflocalized attack with greater corrosion rates at some locations [6]

than at others. Pitting can be very insidious and destructive, with sudden [7] '

failures in high pressure applications (especially m tubes) occurring by [2]

perforation. This form of corrosion essentially produces " holes" of varying [12]

depth to diameter ratios in the steel. These pits are, in many cases, filled  !

with oxide debris, especially for ferritic materials such as ca bon steel.

Deep pitting is more common with passive metals, such as austenitic j stainless steels, than with non- passive metals. Pits are generally elongated in the direction of gravity. In many cases, erosion corrosion, fretting corrosion, and crevice corrosion can also lead to pitting. Corrosion pitting is )

an anodic reaction which is an autocatalytic process. That is, the corrosion l

, process within a pit produces conditions which stimulate the continuing )

activi:y of the pit. liigh concentrations ofimpurity anions such as chlorides l and sulfates tend to concentrate in the oxygen- depleted pit region, giving )

g rise to a potentially concentrated aggressive solution in this zone. Pitting j has been found on the outside diameter of tubes wheie sludge or tube scale was present, it can also occur at locations of relatively stagnant coolant or water, such as in carbon steel pipes for service water lines, and at crevices in stainless steel, such as at the stainless steel cladding between reacter pressure vessel closure flanges. Pitting can become passive in some metals such as aluminum.

Radiation Yes Non-metallics are susceptible to degradation caused by gamma radiation. [4]

Damage Saline Water No Not applicable to Equipment Type. Saline Water Attack has resulted in the [2]

Attack degradation of reinforced concrete structures. The degradation mechanism involves water seepage into the concrete resulting in a high chloride environment for the reinforcing bars. The reinforcing bars corrode resulting in expansion that leads to cracking and spalling of the concrete. Saline water attack is of particular concern for structures that are inaccessible for routine inspection, and piping or other fluid components embedded in concrete. This ARDM is not applicable to valve components since valves l are not constructed of nor typically installed in concrete.

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Revision i Page 6 of 10 Date: March 15.1996 l

Component Aging Management Review NfTACIIMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: VALVE ARDM POJENTIAL DESCRIPTION / JUSTIFICATION SOURCE (1 ES/NO)

Selective Yes The removal of one element from a solid alloy by corrosion processes. The [12]

Leaching most common example is the selective removal of zine in brass alloys [13]

(dezincification). Similar processes occur in other alloy systems in which aluminum, iron, cobalt, chromium, and other elements are removed. There are two types, layer-type and plug-type. Layer type is a uniform attack whereas plug-type is extremely localized leading to pitting. Overall dimensions do not change appreciably. If a piece of equipment is covered by debris or surface deposits and/or not inspected closely, sudden .

unexpected failure may occur in high pressure applications due to the poor l strength of the remaining material. Requires susceptible materials and I corrosive environment. Materials particularly susceptible include zinc, I aluminum, carbon and nickel. Environmental conditions include high )

temperature, stagnant aqueous solution, and porous inorganic scale. Acidic solutions and oxygen aggravate the mechanism.

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ATTACllMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: VALVE ARDM IAL DESCRIPTION / JUSTIFICATION SOURCE (YES/NO)

Stress Yes Selective corrosive attack along or across material grain boundaries. Four [6]

Corrosion particular mechanisms are known to exist: (1) Intergranular (IGSCC), [7]

Cracking between the material grain boundaries. (2) Transgranular (TGSCC), across [2]

the material grains along certain crystallographic planes. (3) Irradiation Assisted (IASCC), between the material grains after an incubation neutron dose which sensitizes the material. (4) Interdendritic (IDSCC), between the dendrite interfaces. SCC requires applied or residual tensile stress, susceptible materials (such as austenitic stainless steels, alloy 600, alloy x-750, SAE 4340, and ASTM A289), and oxygen and/or ionic species (eg.,

Chlorides / sulfates).

Common sources of residual stress include thermal processing and stress risers created during surface finishing, fabrication, or assembly. The heat input during welding can result in a localized sensitized region which is '

susceptible to SCC. IGSCC is a concern in stainless steel piping depending on material condition and process fluid chemistry and also is a potential concern in valve internals (PH steel). While operating experience with carbon steel piping shows no evidence of environmentally assisted cracking, laboratory studies do indicate a susceptibility to SCC. Screening tests on SA106b and SA333GR6 indicate that severe combinations of cyclic applied stress and high temperature oxygenated water can result in -

environmentally enhanced cracking. TGSCC may be a concern in stainless steel if aggressive chemical species (caustics, halogens, sulfates, especially if coupled with the presence of oxygen) are present. TGSCC was thought to be inactive in low alloy steel, however, recent data suggests that the mechanism may operate. IASCC is a potential concern only for reactor vessel internals and other stainless steel components, such as control rods, which are subject to very high neutron fluence levels. A fast neutron incubation fluence of at least 1.0E+20 is generally required to sensitize the 1 material.

IDSCC is a potential concern in stainless steel weld metal deposits based on microstructure and delta ferrite content. This mechanism is inactive in carbon and low alloy steel. Ammonia grooving in brass components can occur when the concentration of ammonia is greater than a few ppm. It is found most often in feedwater herers that contain admiralty brass tubes and where morpholine, which breaks down into ammonia, is used to increase the pli of the condensate.

Stress Yes Stress Rela),ation occurs under conditions of constant strain where part of [7]

Relaxation the clastic strain is replaced with plastic strain. A material loaded to an initial stress may experience a reduction in stress over time at high temperatures. Bolted connections are most vulnerable. Relaxation of stress j on packing due to stretching of gland follower studs under elevated temperatures may cause packing leakage.

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Revision i Page 8 of to Date: March 15,1996 t , _ .

l Component Aging Management Review ATTACilMENT 7, POTENTIAL ARDM LIST

! System: Main Feedwater System (045)

Equipment Type: VALVE l

ARDM POTENTIAL (YES/NO) DESCRIPTION / JUSTIFICATION SOURCE Thermal Yes Non-metallies are particularly susceptible with material dependent [7]

Damage temperature limits.

[2]

Thermal Yes Loss of material fracture toughness caused by thermally induced changes in [7]

Embrittlement the formation and distribution of alloying constituents. Requires high

! l temperature 500*F to 700'F for metalli:: components. Ferrite containing  !

stainless steels are susceptible as are materials with grain boundary '

segregation ofimpurities.

i Wear Yes Wear results from relative motion between two surfaces (adhesive wear), [1]

l from the influence of hard, abrasive particles (abrasive wear - see

i

' particulate erosion) or fluid stream (erosion), and from small, vibratory or  !

sliding motions under the influence of a corrosive environment (fretting).

l In addition to material loss from the above wear mechanisms, impeded '

relative motion between two surfaces held in intimate contact for extended periods may result from galling /self-welding. Motions may be linear, circular, or vibratory in inert or corrosive environments. The most common '

." result of wear is damage to one or both surfaces involved in the contact.

Wear most typically occurs in components which experience considerable relative motion such as valves and pumps, in components which are held under high loads with no motion for long periods (valves, flanges), or in clamped joints where relative motion is not intended but occurs due to a loss of clamping force (e.G., Tubes in supports, valve stems in seats, springs  !

against tubes). Wear may proceed at an ever-increasing rate as worn l

surfaces moving past one another will often do so with much higher contact  !

stresses than the surfaces of the original geometry. Fretting is a wear phenomenon that occurs between tight-fitting surfaces subjected to a cyclic, relative motion of extremely small amplitude. Fretting is frequently accompanied by corrosion. Common sites for fretting are in joints that are bclted, keyed, pinned, press fit or riveted; in oscillating bearings, r couplings, spindles, and seals; in press fits on shafts; and in universal joints. Under fretting conditions, fatigue cracks may be initiated at stresses well below the endurance limit of nonfretted specimens.

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Component Aging Management Review ATTACHMENT 7, POTENTIAL ARDM LIST System: Main Feedwater System (045) Equipment Type: VALVE Reference List Source Title

[1] ASME Wear Control liandbook, Peterson and Winer,1980 5

[2] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draft NRC Regulatory Guide No. DG.1009, December 1990

[3] Service (Salt) Water System Life Cycle Management Evaluation, EPRI Report No. TR-102204, April 1993

[4] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[5] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Repon No. NP-3944,1985

[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Repon No.

NP-5461,1987

[7] Environmental Effects on Components: Commentary for ASME Section 111, EPRI Report No. NP-

~

5775, April 1988

[8] Boric Acid Corrosion of Carbon and Low Alloy Steel Pressure Boundary Materials, EPRI Report No. NP-5985,1988

[9] Nuclear Plant Service Water System Aging Degradation Assessment, NUREG/CR-5379, Volume I and 2, June 1989 and October 1992

. [10] Aging Assessment ofInstrument Air Systems, NUREG/CR-5419, January D90

[11] Insights Gained from Aging Research, NUREG/CR-5643, March 1992

[12] Corrosion Engineering, Fontana and Greene,1978

)

[13] Corrosion and Corrosion Control, An introduction to Corrosion Science and Engineering, Uhlig, Third Edition,1985 .

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l Revision 1 Page lo of 10 Date: March 15,1996

Component Aging Management Review ATTACHMENT 3, COMPONENT GROUPING

SUMMARY

SHEET SYSTEM: Main Feedwater (0451 GROUP ID NUMBER: 045-CKV-01 GROUP ATTRIBUTES:

1. Device Type: CKV

2. Vendor: ROCKWEI I -EDWARD val.VES

3. Model Number: Fie. 970Y/Fie. 970(WCC)NTY

4. Material: Cast carbon Steel

5. Internal Environment: Controlled chemistry water at 435F (normal oneration)

6. External Environment: Climate controlled atmosnheric tir (Containment Buildine)

7. Function: Maintain system nressure boundarv

8. Name Plate Data:

PARAMETER VALUE System Temperature Variable from arnbient (70F) when shutdown to 435F when operating (subject to temperature cycles associated with plant start-up / ,

shutdown and operational transients)

System Pressure </= 1300 psig Materials of Construction BODY / COVER: Cast / Forged Carbon Steel- ASTM A216, Grade WCB or

' WCC/ ASTM A105 (alternate material for valves: Cr-Mo alloy steel- see

! /^% MCR 93-045-027-00 for details)

LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

Eauinment ID Descrintion Eauinment ID Descrintion ICKVFW-130 12 SG FW IIDR CKV 2CKVFW-130 22 SG FW HDR CKV ICKVFW-133 11 SG FW llDR CKV 2CKVFW-133 21 SG FW IIDR CKV i

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p A ("'N Component Agin agepient Review ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT ID: NA GROUP ID: 045-CKV-01 ESubject to' -

Sub-Group ID Sub-Component /Name Manufacturer Material ' Model Number -.: Passive latended Function (s) ; _fAMR-(Replacement Pgm) (Sourec) (Source) (Source) . (Source) - (Yorh)-

045-CKV-DIA Hody, Cover, Drain Ass'y Rockwell Carbon Steel, Fig. 970Y; Maintain system pressure boundary Y Forged or Cast Fig. 970(WCC)NTY (None) (NA) (12399-0002; (12399-0002; (CLSR) 12399- 12399-0022S110001) 0022S110001) 045-CKV-01B Pressure Seal Bolting Rockwell AISI 416 Fig. 970Y; Maintain system pressure boundary Y Stainless Steel; or Fig.970(WCC)NTY ASTM A193,Gr.

B7 At;oy Steel (None) (NA) (12399-0002; (12399-0002; (CLSR) 12399- 12399-0022S110001) 0022S110001) 045-CKV-01C Disk /sent,other non-pressure Rockwell Various NA None (Prevents reverse flow from S/G) N retaining parts (N4) (NA) (NA) (NA) (NA)

Revision 1 Page'I ofI Date: March 15,1996

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l Component Aging Management Review ATTACIIMENT 5, ARDM MATRIX 1

/ \

l

() SYSTEM NUMBER: 045 CALVE SYSTEM NAME: Main Feedwater CKV EQUIPMENT TYPE: DEVICE TYPE:

GROUP ID (if applicable): _, 045-CKV-01 GROUP OR SUB GROUP ID ARDMs 045-CKV-01 A 045-CKV-OlB (Body / Cover) (Bolting)

CAVITATION EROSION 1 16 CORROSION FATIGUE J 16 CREVICE CORROSION A 16 EROSION CORROS!ON B 16 FATIGUE K 17 FOULING 4 16 '

GALVANIC CORROSION 5 16 GENERAL CORROSION C 16 IIYDROGEN DAMAGE 6 16 INTERGRANULAR ATTACK 7 16

, MIC 8 16 l

Q PARTICULATE WEAR EROSION 9 16 PITTING A 16 RADI ATION DAMAGE 10 10 SELECTIVE LEACHING 11 16 STRESS CORROSION CRACKING 12 16 l

j STRESS RELAXATION 13 13 TIIERMAL DAMAGE 10 10 TilERMAL EMBRITTLEMENT 14 14 WEAR 15 15 l

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Revision 1 Page1 ofI Date: March 19,1996 j

Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST l SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE:- CKV l GROUP ID(if applicable): 045-CKV-01 l

l CODE DESCRIPTION SOURCE I

I The feedwater system fluid flow conditions, pressure and temperature do not result [5],[11] l in cavitation at these check valves. The flow is relatively steady and the pressure is  !

l much greater than the vapor pressure at system temperature. Therefore, cavitation l erosion is not plausible.

j 4 Fouling does not affect the component function. The component intended function [5],[16]

l is to maintain the pressure boundary integrity only. Due to the control of feedwater l chemistry, fouling (including contamination and sedimentation) is not expected.

( Any fouling or sedimentation will not have an affect on the intended function.

5 The check valve materials of construction are primarily carbon steel (with [6],[16]

potentially Cr-Mo steel also) and water chemistry is controlled to minimize conductivity. Therefore, the required galvanic cell and electrolyte are not present, and galvanic corrosion is not plausible.

6 The check valve is not fabricated from the high strength steel susceptible to [5]

hydrogen embrittlement and cracking. Therefore, this ARDM is not plausible.

l 7 Carbon steel material is not susceptible to intergranular attack. [5]

8 Microbiologically innuenced corrosion is not plausible due to the chemical [5],[16]

cond;tions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through feedwater/ condensate chemistry control. Additionally, r.ormal feedwater temperature is above 200F making MIC not possible.

9 Control of feedwater chemistry ensures essentially no particulate matter in the [16]

feedwater Dowstream. Therefore, particulate wear erosion is not plausible.

d 10 The thermal damage and radiation damage ARDMs affect non-metallies only.

There are no non-metallic pressure retaining materials in these check valves.

[2],[5]._

1I Carbon steel materials are not susceptible to selective leaching. Therefore, this [6],[l1j, ARDM is not plausible. [17]

i 12 Control of feedwater chemistry (particularly oxygen concentration) prevents the [5], [16]

environment necessary for SCC of carbon steel material Therefore, this ARDM is not p!ausible.

13 Stress relaxation requires constant strain at temperatures greater than 700F. The [5],[11]

maximum temperature to which the check valves are exposed is ~ 435F.

Therefore, stress relaxation of pressure seal bolting (or other pressure retaining parts) is not plausible.

14 The feedwater system operating temperature of ~ 435F max. is not sufficient to [11], [18]

result in thermal embrittlement. Thermal einbrittlement oflow carbon or alloy steels requires temperatures greater than 650F.

15 Surfaces of the check valves pressure retaining boundary subject to wear are hard- [14], [19]

faced with a corrosion resistant inlay to prevent degradation. Based on this protective surface treatment and limited relative motion of pressure retaining parts,

! wear is not plausible.

i 16 The check valve pressure seal botting is exposed to the containment atmosphere [5],[8),[9]

and is not exposed to the feedwater system fluid Howstream. This environment is not conducive to signincant corrosion of the stainless steel or alloy steel botting.

Therefore, the corrosion and erosion mechanisms are not plausible.

17 Bolting pre-load and cover-to-body joint design limit the effects of fatigue. [17]

Fatigue is not plausible for the pressure seal bolting.

Revision i PageIof4 Date: April 16,1996

Component Aging Management Review NITACIIMENT 6, MATRIX CODE LIST

[ SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater V' EQUIPMENT TYPE: VALVE DEVICE TYPE: CKV GROUP ID (if applicable): 045-CKV-01 CODE DESCRIPTION SOURCE A Crevice corrosion and pitting can occur in areas of the check valves that are not [5],[6],

exposed to the general flowstream such as at the valve cover-to-body interface, the [16]

valve body drain pipe, and other crevices. These areas may comprise small localized volumes of stagnant solution for which fluid chemistry may deviate from bulk system chemistry. Higher concentrations ofimpurities may exist in these crevices due to out-of-specification system chemistry during shutdown conditions and due to the stagnant flow conditions of the crevice. The resulting degradation is highly localized pits or cracks. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of crevice corrosion and pitting.

The effects of crevice corrosion and pitting can not be dismissed due to the potential for crevice locations and potentially high impurity concentrations in the system during shutdown conditions. Management of the effects of crevice corrosion and pitting should consist of: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of valves (from valves in this group or representative components in other portions of the plant) to an inspection to determine the extent oflocalized degradation occurring in the feedwater check valves.

B Erosion corrosion is plausible due to high velocity, high energy Guid How [3], [5),

conditions. The effects of erosion corrosion include potentially rapid component (11], [15], j

^*

wall thinning to the point of pressure boundary failure. The control of feedwater [16]

~

system Guid chemistry limits the rate and effects of erosion corrosion. The (i

V) feedwater system check valves have experienced valve body erosion in service, and are monitored periodically for the effects of erosion corrosion 1,y specific l

inspections during refueling outages. The chemistry control program and these inspections should be continued through the period of extended operation in order to manage the effects of erosion corrosion.

C General corrosion of the feedwater check valves is plausible due to exposure of the [5],[6],

carbon steel materials to corrosive medium during shutdown periods and, to a [7), [16]

lesser extent, during operation. The rate of general corrosion is low after ti e initial build-up of the protective corrosion film (magnetite). Exposure to high oxygen concentrations during shutdown and potential removal and re-creation of the corrosion filra result in general corrosion. The effect of general corrosion is component wall thinning over a relatively large area and could result in pressure boundary failure if extensive. The control of feedwater/ condensate system Guid chemistry significantly limits the efrects of general corrosion. Management of the effects of general corrosion should consist of: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of valves (from valves in this group or representative componants in other portions of the plant) to an inspection to determine the extent of general corrosion occurring in the feedwater check valves.

J The ARDM is plausible due to the combination of fatigue and corrosion [5]

mechanisms affecGng these valves. It is characterized by accelerated crack Note I propagation at susceptible locations due to mechanism synergies and can lead to component failure. Aging management recommendations include maintenance of system chemistry, and cycle counting in the fatigue - litoring program.

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Revision I l' age 2 of 4 Date: April 16,1996 .

1 Component Aging Management Review ,

ATTACHMENT 6, MATRIX CODE LIST O SYSTEM NUMilER: 045 SYSTEM NAME: _hiain Feedwater EQUIPMENT TYPE: VALVE "EVICE TYPE: CKV GROUP ID(ifapplicable): 045-CKV-01 CODE DESCRIPTION SOURCE K The ARDM is plausible due to thermal effects, mainly during reactor startup. It is [1], [4),

characterized by crack propagation at susceptible locations due to thermal cycling [5],[22] "

which could lead to component failure. The aging management recommendation is Note I cycle counting in the fatigue monitoring program.

Notes:

1. The evaluation results for fatigue, and corrosion fatigue, of these check valves i, unchanged from the results of the Feedwater System Evaluation Report, Revision 0. There is technicaljustification that fatigue, and thus corrosion fatigue, are not plausible for these valves and this is documented in Technical Problem Repot1(TPR)96-022. The aging evaluation results are unchanged here in order to be consistent with the 1.icense Renewal Application Technical Report for the Feedwater System.

Additionally, the conclusion that fatigue, and corrosion fatigue, are plausible is conservative from a nuclear safety standpoint. The effects of fatigue will be evaluated as part of the aging effects management program for the check valves (see Attachment 8/10).

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l Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST l

e SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater t . EQUIPMENT TYPE: VALVE DEVICE TYPE: CKV l GROUP ID(if applicable): 045-CKV-01 l

Reference Lht

! Source Title l

[1] Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses, Draf1 NRC Regulatory Guide No. DG-1009, December 1990 j [2]- Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[3] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985

[4] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No.'

NP-5461,1987

[5] Environmental Effects on Components: Commentary for ASME Section 111, EPRI Report No. NP 5775, April 1988 l~ [6] Corrosion Engineering, Fontana and Greene,1978 l [7] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineeri o, Uhlig, Third Edition,1985

[8] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System, Unit 1

[9] Drawing 62702, Sheet 4, Rev. 30; Condensate and Feedwater System, Unit 2 l

[10] OI-12A-1, Rev. 22/OI-12A-2, Rev.14; Feedwater System Operating Instructions

., [11] UFSAR, Rey,18; Chapter 4 - Reactor Coolant and Associated Systems, Chapter 10 - Steam and

, Power Conversion Systems >

[12] ANSI B31.1,1967; Power Piping Code j' [13] ANSI 331.731969; Nuclear Power Piping Code '

[14] Drawings 12399-02, Rev.12; 12399-22, sheet 1, Rev. 5; Fig. 970Y Check Valve Assembly

[15] Repetitive Tasks 10452052,10452053,20452043,20452044; Feedwater Check Valve inspections 1

[16] CP-217, Rev. 5; Chemistry Specifications and Surveillance - Secondary System

[17] Marks' Standard llandbook for Mechanical Engineers,8th Edition, McGraw-liill

[18] Metals llandbook,9th Edition, Volumes 1 and 13, ASM

! [19] ASME Wear Control llandbook, Peterson and Winer,1980

l. [20] Drawing 12543A-01, Rev.13; Feedwater Piping Isometric, Unit I

[21] Drawing 13547A-20, Rev. 6F; 13547A-47, Rev. 4; 13549A 26, Rev. 3; Feedwater Piping Isometric, ,

Unit 2

[22] CE-NPSD-634-P, April 1992; Fatigue Monitoring Program for CCNPP Units 1 and 2 i

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Component Aging Management Review ATTACHMENT 3, COMPONENT GROUPING

SUMMARY

SHEET SYSTEM: Main Feedwater (045)

GROUP ID NUMBER: 045-HV-01 GROUP ATTRIBUTES:

1. Device Type: HV

2. Vendor: Various

3. Model Number: Various 4, Material: Carbon Steel 5, Internal Environment: Controlled chemistry water / steam at un to 550F

6. External Environment: Climate controlled atmosoberic air (Containment Bldel

7. Function: Maintain system oressure boundarv

8. Name Plate Data:

i-PARAMETER YAL1JE System Temperature up to 550F l

System Pressure </= 1300 psig Material of Construction Cast or Forged Carbon Steel w/ CR 13 trim l Normal Operating Position Open Valve Type Globe (Mark # 110H,130)

_ LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

Eauioment ID Descrintion Eauinment IQ Descrintion lilVFW-1501 LT-ill3A ROOT 211VFW-1501 lil3A-LT & 1013A-PT ROOT 111VFW-1502 LT-1113 A ROOT 2ilVFW-1502 Ii13A LT & 1013-PT ROOT lilVFW-1503 LT-ill3A ROOT 2HVFW-1503 lil3 A-LT ROOT 1IIVFW-1504 LT-1113 A ROOT 2HVFW-1504 1113-LT ROOT lilVFW-1521 LT-l ll3B ROOT 211VFW-1521 Il05-LT,1113B-LT & 1013-1IIVFW-1522 LT-1113B ROOT 21IVFW-1522 1105-LT,1113B-LT & 1013B llIVFW-1523 LT-ill3B ROOT 2HVFW-1523 I l05-LT & lil3B-LT ROOT lilVFW-1524 LT-lll3B ROOT 2iiVFW-1524 Il05-LT & *. ll3B-LT ROOT llIVFW-1541 LT-ll 13C ROOT 211VFW-1541 Ill3C-LT ROOT lilVFW-1542 LT-1113C ROOT 211VFW-1542 1113C-LT ROOT liiVFW-1543 LT-ill3C ROOT 211VFW-1543 Ill3C-LT & 1013C-PT ROOT lilVFW-1544 LT-lll3C ROOT 21{VFW-1544 lil3C-LT & 1013C-PT ROOT

! lilVFW-1561 LT-ll l3D ROOT 2HVFW-1561 lill-LT, I!!3D-LT & 1013D lHVFW-1562 LT-lll3D ROOT 211VFW-1562 11 ll-LT, Ill3D-LT & 1013D

} lilVFW-1563 LT-1113D ROOT 211VFW-1563 lill-LT & lil3D-LT ROOT i tilVFW-1564 LT-1113D ROOT 211VFW-1564 11ll-LT & lil3D-LT ROOT h IIIVFW-1587 l-LT-lll4A ROOT VLV 2HVFW-1587 lil4 A-LT ROOT j lilVFW-1588 1-LT-lll4A ROOT VLV 211VFW-1588 lil4 A-LT ROOT

! IIIVFW-1596 1-LT-1114B ROOT VLV 211VFW-1596 1114B-LT ROOT lHVFW-1597 1-LT-1114B ROOT VLV 2ilVFW-1597 1114B-LT ROOT 5

s Revision 1 Page1 of2 Date: March 13,1996 l

Component Aging Minagement Review ATTACIIMENT 3, COMPONENT GROUPING

SUMMARY

SIIEET g] F.auinment ID Descriotion Eauioment ID Descriotion (j lilVFW-1601 LT-il23A ROOT 211VFW 1601 1023 A-PT & l l23A-LT ROOT lilVFW-1602 LT-Il23A ROOT 211VFW-1602 1023A-PT & ll23A LT ROOT lilVFW-1603 LT-ll23A ROOT 2ilVFW-1603 1123A-LT ROOT 1IIVFW-1604 LT-1123A ROOT 211VFW-1604 1123A LT ROOT lilVFW-1621 LT-1123B ROOT 2HVFW-1621 1023B-PT,1106-LT & 1123B 1IIVFW-1622 LT-1123B ROOT 211VFW-1622 1023B-PT,1106-LT & 1123B liiVFW-1623 LT-ll23B ROOT 211VFW-1623 Il06-LT & ll23B-LT ROOT ll1VFW 1624 LT-1123B ROOT 211VFW-1624 1106-LT & ll23B-LT ROOT ll1VFW-1641 LT-ll23C ROOT 2HVFW 1641 ll23C-LT ROOT lilVFW-1642 LT-1123C ROOT 211VFW-1642 1123C-LT ROOT I11VFW-1643 LT-1123C ROOT 2HVFW-1643 1023C-PT & 1123C-LT ROOT lHVFW-1644 LT-1123C ROOT 2HVFW-1644 1023C-PT & 1123C-LT P.OOT lilVFW-1661 LT-il23D ROOT 211VFW-1661 1023D PT 1121-LT & 1123D-1HVFW-1662 LT-1123D ROOT 211VFW-1662 1023D-PT,1121-LT & 1123D lilVFW-1663 LT-ll23D ROOT 211VFW-1663 1023C-PT & il23C-LT P.OOT lilVFW-1664 LT-1123D ROOT 211VFW-1664 1023C-PT & 1123C-LT ROOT IHVFW-1687 1-LT-1124A ROOT VLV 2HVFW-1697 ll24A-LT ROOT IHVFW-1688 1-LT 1124A ROOT VLV 2HVFW-1688 ll23-LT ROOT 1IIVFW-1696 1-LT-1124B ROOT VLV 211VFW-1696 1123B-LT ROOT

., lilVFW-1697 1-LT-il24B ROOT VLV 2HVFW-1697 Il24B-LT ROOT

, IHVFW-1705 1-LT-1114C ROOT VLV 211VFW 1705 1114C-LT ROOT

/~N 1IIVFW-1706 1-LT-1114C ROOT VLV 2ilVFW-1706 1114C-LT ROOT U lilVFW-1714 1-LT-1114D ROOT VLV 2HVFW-1714 1114D-LT ROOT liiVFW-1715 1-LT-lll4D ROOT VLV 211VFW-1715. Ill4D-LT ROOT IIIVFW-1805 1-LT-1124C ROOT VLV 211VFW-1805 1124C-LT ROOT lilVFW-1806 1-LT-1124C ROOT VLV 211VFW-1806 1124C-LT ROOT IIIVFW-1814 1-LT-1124D ROOT VLV 211VFW-1814 1123D-LT ROOT lilVFW-1815 1-LT-1124D ROOT VLV 2HVFW-1815 ll23D-L '. ROOT i

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G Revision i Page 2 of 2 Date: March 13,1996 I

Component Aging f4anagement Review 'f ATTACIIMENT 4, SUBCOMPONENT/SUH-GROUP IDENTIFICATION l SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater i

EQUIPMENT ID: NA GROUP ID: 045-HV-01  !

Seigeet to Sub-Group ID Sub-Component'Name Manufacturer 3faterial ModcI Number Passive Intended Function (s) . ~

AMR 1 (Replacement Pgm) (Source) (Source) (Source) (Source) (Y or N) ' . I Body. Bonnet Various Carbon Steel, Mark 11011,130 I 045-IIV-01 A Maintain system pressure boundary Y Forged or Cast

[

(None) (NA) (92771SH-GLB-1) (FSK-MP-1003) (CLSR)  ;

(VTM-D2404001) [

(15587-0008) ,

(15587-0021) 045-IIV-Ol B Stem Various 13% Chrome, Mark 11011,130 Maintain system pressure boundary Y ASTM A182,F6 or similar (None) (NA) (VTM-D2404001) (F5K-MP-1003) (CLSR)

(15587-0008) .,

(15587-0021) l 045-IIV-01C Body /Baanet Bolting (for Various Carbon or Alloy Mark 11011,130 Maintain system pressure boundary Y bolted bonnet valves) Steel (None) (N/A) (\TM-D240-0001) (FSK-MP-1003) (CISR) l (15587-0008)

(15587-0021) i 045-IIV-01D Disk.other non-pressure Various NA NA None (Normally open) N '-

retaining parts (NA) (NA) (NA) (NA) (NA)

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, Revision 1 Page1 ofI Date: March 19,1996

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Component Aging Management Review l ATTACHMENT 5, ARDM MATRIX l

SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater l EQUIPMENT TYPE: VALVE DEVICE TYPE: HV l GROUP ID (if applicable): 045-H V-01 l

l GROUP OR SUB GROUP ID ARDMs 045-HV-01 A 045-HV-Ol B . 045-HV-01C NA  !

~(Body / Bonnet) (Stem) . (Bolting)

CAVITATION EROSION 1 1 16 i CORROSION FATIGUE 2 2 16

! CREVICE CORROSION A 18 16 l

EROSION CORROSION 1 1 16 l FATIGUE 3 3 17 FOULING 4 4 16 GALVANIC CORROSION 5 5 16 GENERAL CORROSION B 18 16 1 >

l IlYDROGEN DAMAGE 6 6 16 INTERGRANULAR ATTACK 7 7 16 l

l MIC 8 8 16 1

PARTICULATE WEAR EROSION 9 9 16 PITTING A 18 16 ,

RADIATION DAMAGE 10 10 10 SELECTIVE LEACillNG 11 11 16 STRESS COR.ROSION CRACKING 12 12 16 I STRESS RELAXATION 13 13 13 TIIERMAL DAMAGE 10 10 10 TilERMAL EMBRITTLEMENT 14 14 14 l WEAR 15 15 15 l

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Revision 1 Page1ofI Date: March 11,1996

. _ - ~ - . - ~ _ , - . - . - _ _ _ - - - - . - . . _ _ - _ - - . . - __

Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE: HV GROUP ID (if applicable): 045-HV-01 CODE DESCRIPTION SOURCE 1 These valves are not in the feedwater system flow stream. Therefore, cavitation [2],[5],

erosion and erosion corrosion are not plausible. [61,[7] )

2 Control of system chemistry results in limited corrosion, and thermal fatigue is not [2] e plausible for these hand valves. Therefore, corrosion fatigue is not plausible. l 3 These hand valves are 3/4" and !" globe type valves that serve as instrumentation 12], [5],

root isolation valves off the steam generator secondary shell. These small valves [6],[7] ,

are not subject to significant alternating stress levels in response to temperature j cycles. Therefore, thermal fatigue is not considered plausible for these hand valves. [

4 Fouling does not affect the component function. The component intended function [2],[8]

is to maintain the pressure boundary integrity only. Due to the control of feedwater chemistry, fouling (including contamination and sedimentation) is not expected.  ;

l Any fouling or sedimentation will not have an affect on the intended function.

5 The hand valve materials of construction are carbon steel with chromium steel [3],[8]

trim. Feedwater system and steam generator water chemistry is controlled to i f

minimize fluid conductivity. Based on the relatively large anode (CS parts) surface area, and low conductivity electrolyte. galvanic corrosion is not plausible. ,

6 The valves are not fabricated from the high strength steel susceptible to hydrogen [2]

., embrittlement and cracking. Therefore, this ARDM is not plausible.

7 The carbon steel material of the valve body is not susceptible to intergranular [2],[4],[8]

attack. The chromium steel stem could be susceptible if sensitized, however, the stems are not welded and sensitization is unlikely. Also, the feedwater environment is not sufficiently oxidizing to result in significant IGA. Therefore, IGA is not plausible for the valve materials.

8 Microbiologically influenced corrosion is not plausible due to the chemical [2],[8]

conditions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through feedwater/ condensate chemistry control. Additionally, normal feedwater ,

temperature is above 200F making MIC not possible. j 9 Control of feedwater chemistry ensures essentially no particulate matter in the [8]

feedwater flowstream. Therefore, particulate wear erosion is not plau;ible. i 10 The thermal damage and radiation damage ARDMs affect non-metallics only. [1],[2]  ;

There are no non-metallic pressure retaining materials in these valves.

i1 Carbon and chromium steel materials are not susceptible to selective leaching. [3],[7],[9] l Therefore, this ARDM is not plausible. {

12 Control of feedwater chemistry (particularly oxygen concentration) prevents the [2],[8]  ;

environment necessary for SCC of carbon and alloy steel material. Therefore, this  !

ARDM is not plausible. ]

13 Stress relaxation requires constant strain at temperatures greater than 700F. The [2],[7]

maximum temperature to which these valves are exposed is - 550F. Therefore, stress relaxation of bonnet bolting (or other pressure retaining parts) is not j plausible.

14 The temperature to which these valves are exposed ( ~ 550F max.) is not sufficient [7], [10] ,

i to result in thermal embrittlement. Thermal embrittlement of low carbon or alloy ,

l steels requires temperatures greater than 650F.

15 There is typically no relative motion between pressure retainmg parts of these hand [11] l

]

j valves. Therefore, wear is not plausible.  !

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Component Aging Management Review l ATTACIIMENT 6, MATRIX CODE LIST l

i P SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater ,

! \ EQUIPMENT TYPE: VALVE DEVICE TYPE: HV  ;

I GROUP ID (if applicable): 045-HV-01 1 CODE DESCRIPTION SOURCE 16 The valve bonne' bolting is exposed to the containment atmosphere and is not [2],[5],[6] '

exposed to the feedwater system fluid flowstream. This environment is not conducive to significant corrosion of the carbon or alloy steel bolting. Therefore, j the corrosion and erosion mechanisms are not plausible.

17 Bolting pre-ioad limits the effects of fatigue. Fatigue is not plausible for the [9]

bonnet bolting.

18 The chromium content in the stem material results in resisitance to teneral [2],[4],[8]

corrosion, pitting and crevice corrosion, panicularly in the controlled chemistry feedwater environment. Additionally, limited pitting and corrosion of the stem (in the area of the packing, which is the most aggressive area for corrosion) would not affect the pressure boundary function of the sub-component. Therefore, general corrosion, pitting and crevice corrosion are not plausible for the vah e stem.

A Crevice corrosion and pitting can occur in areas of the hand valves that are not [2],[3],[8]

exposed to the general flowstream such as at the valve body-tnonnet interface,-

the valve body-to-seat ring interface, and other crevices. These areas may comprise small localized volumes of stagnant solution for which fluid chemistry may Jeviate from bulk system chemistry. liigher concentrations ofimpurities may I

exist in these crevices due to out-of-specification system chemistry during shutdown conditions and due to the stagnant flow conditions of the crevice. The resulting degradation is highly localized pits or cracks. The control of l feedwater/condensa:e system fluid chemistry significantly limits the effects of l l9 V

crevice corrosion and pitting.

The effects of crevice corrosion and pitting can not be dismissed due to the -

potential for crevice locations and potentially high impurity concentrations in the i

system during shutdown conditions. Management of the effects of crevice l corrosion and pitting should consist ot: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of valves (from valves in this group or representative components in other portions of the plant) to an inspection to determine the extent oflocalized degradation occurring in i the feedwater hand vt.lves.

B General corrosion of the feedwater hand valves is plausible due to exposure of the [2],[3],

carbon steel materials to a potentially corrosive medium during shutdown periods [4],[8]

and, to a lesser extent, during operation. The rate of general corrosion is low after j the initial build-up of the protective corrosion film (magnetite). Exposure to high oxygen concentratisns during shutdown can result in general corrosion. The effect of general corrosion is compon nt wall thinning over a relatively large area and could result in pressure boundary failure if extensive. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of general corrosion. Management of the effects of general corrosion should consist of: 1) maintenance of the current system chemistry control program, and 2) i subjecting a representative sample of valves (from valves in this group or l

l representative components in other portions of the plant) to an inspection to l l determine the extent of general corrosion occurring in the feedwater hand valves.

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Revision 1 Page 2 of 3 Date: March 19,1996

Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST

,Q SY5 ITEM NUM13ER: 045 SYSTEM NAME:

l Main Feedwater  !

EQUIPMENT TYPE: VALVE DEVICE TYPE: HV l GROUP ID(if applicable): 045-HV-01 Reference List Source Title

[1] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[2] Environmental Effects on Components: Commentary fo ASME Section Ill, EPRI Report No. NP-5775, April 1988

[3] Corrosion Engineering, Fontana and Greene,1978

[4] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, i lhird Edition,1985 l

[5] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System. Unit 1

[6] Drawing 62702, Sheet 4, Rev. 30; Condensate and Feedwater System, Unit 2 l

[7] UFSAR, Rev.18; Chapter 4 - Reactor Coolant and Associated Systems. Chapter 10 - Steam and '

Power Conversion Systerns

[8] CP-217, Rev. 5; Chemistry Specifications and Surveillance - Secondary System

[9] Marks' Standard 11andbook for Mechanical Engineers,8th Edition, McGraw-liill

[10] Metals llandbook,9th Edition, Volumes I and 13, ASM

[11] ASME Wear Control 11andbook, Peterson and Winer,1980

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Revision 1 Page 3 of 3 Date: March 19,1996

Component Aging Management Review ATTACilMENT 3, COMPONENT GROUPING

SUMMARY

SilEET ry SYSTEM: Main Feedwater (045)

GROUP ID NUMBER: 045-11V-02 GROUP ATTRIBUTES:

1. Device Type: IIV

2. Vendor: Various

3. Model Number: Various

4. Material: Carbon Steel

5. Internal Environment: Controlled chemistry water at un to 435F

6. External Environment: Climate controlled atmospheric air (Containment Bldg)

7. Function: Maintain system cressure boundarv

8. Name Plate Data:

PARAMETER VALUE System Temperature up to 435F System Pressure </= 1300 psig Normal Operating Position Closed Valve Type Gate (Mark # 7)

., LIST OF GROUPED COMPONENTS (EQUIPMENT ID):

(N Eauinment ID Descriptian Eauinment ID Description lilVFW-220 11 SG FW llDR DRAIN _ 211VFW-220 21 SG FW llDR DRAIN lilVFW-222 12 SG FW llDR DRAIN 2ilVFW-223 22 SG FW llDR DRAIN 1

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Component Aging %anagement Review v i ATTAC11 MENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater  ;

EQUIPMENT ID: NA GROUP ID: 045-HV-02 Subject to SulM;roup lD Sut Component /Name 31anufacturer Staterial Slodel Number Passite intended Function (s) A31R (Replacement Pgm) (Source) (Source) (Source) (Source) (V or N) 045-IIV-02A Body, Bonnet Various Carbon St[el, Stark 7 31aintain system pressure boundary Y j Forged or Cast (None) (NA) (92771Sil-GATF 1) '60702S110004) (CLSR)

(3T31-D243-0001) (62702S110004)  !

(15587-0027)  ;

045-IIV-02B Stem Various 13% Chrome. 31srk 7 31aintain system pressure boundary Y I AST31 A182 Gr. F6 or similar ,

(None) (NA) (VT31-D2410001) (60702SII0004) (CISR)

(15587-0027) (62782S110004) .

045-ilV-02C Itod 3 /Ilonnet flolting(for Various Carbon or Alloy alark 7 Staintain system pressure boundary Y bolted bonnet valves) Steel '

(None) (N/A) (VT31-D243-0001) (60702S110004) (CIER)

(155R7-0027) (62702SIIG004) a 045-IIV-02D Dnk and Seat Various 13% Chrome, Stark 7 31aintain system pressure boundary (SR to NSR Y' AST31 A182 Gr. F6 boundary) '

or similar 4

(None) (NA) (31 St-D2410001) (60702S110004) (Ct.SR)

(15537-0027) (62702S110004) 045-IIV-02E Other non-pressure retainin: Various NA NA None (Normally open) N ,

parts (NA) (NA) (NA) (NA) (NA) t Revision 1 ,Page1 ofI Date: March 19,1996

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Component Aging Management Review ATTACHMENT 5, ARDM MATRIX SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE: HV GROUP ID (if applicable): 045-H V-02 GROUP OR SUB GROUP ID :

, ARDMs 045-HV-02A : 045-HV-02B 045-HV-02C 045-HV-02D (Body / Bonnet) (Stem) L (Bolting) . - (Disk / Seat)'

CAVITATION EROSION 1 1 16 1 CORROSION FATIGUE 2 2 16 2 CREVICE CORROSION A 18 16 18 EROSION CORROSION 1 1 16 1 FATIGUE 3 3 17 3 FOULING 4 4 16 4 GALVANIC CORROSION 5 5 16 5 GENERAL CORROSION B 18 16 18 IlYDROGEN DAMAGE 6 6 16 6-INTERGRANULAR ATTACK 7 7 16 7 MIC 8 8 16 8 PARTICULATE WEAR EROSION 9 9 16 9 .

PITTING A 18 16 18 RADIATION DAMAGE 10 10 10 10 SELECTIVE LEAClllNG 11 11 16 11 STRESS CORROSION CRACKING 12 12 16 12 STRESS RELAXATION 13 13 13 13 TilERMAL DAMAGE 10 10 10 10 TilERMAL EMBRITTLEMENT 14 14 14 14 WEAR 15 15 15 15 l

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Revision 1 Page1 ofI Date: March 11,1996

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l Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST l

lO

' (/

SYSTEM NUM13ER:

EQUIPMENT TYPE:

045 VALVE SYSTEM NAME:

DEVICE TYPE:

Mam Feedwater HV GROUP ID(if applicable): 045-HV-02 l

I CODE DESCRIPTION SOURCE ,

l 1 These valves are not in the feedwater system flow stream. Therefore, cavitation [2],[5], I l erosion and erosion corrosion are not plausible. [61,[7] {

2 Control of system chemistry results in limited corrosion, and thermal fatigue is not [2]  ;

plausible for these hand valves. Therefore, corrosion fatigue is not plausible.  ;

l 3 These hand valves are 1" gate type valves that serve as drain isolation valves off [2],[5], l l

the main feedwater piping. These small valves are not subject to significant [6],[7] l alternating stress levels in response to temperature cycles. Therefore, thermal i fatigue is not considered plausible for these hand valves. l 4 Fouling does not affect the component function. The component intended function [2],[8] l l is to maintain the pressure boundary integrity only. Due to the control of feedwater chemistry, fouling (including contamination and sedimentation)is not expected.

Any fouling or sediment . tion will not have an affect on the intended function.

5 The hand valve materials of construction are carbon steel with chromium steel [3],[8]  !

trim. Feedwater system water chemistry is controlled to minimize fluid  !

conductivity. Based on the relatively large anode (CS parts) surface area, and low l l conductivity electrolyte, galvanic corrosion is not plausible.

6 The valves are not fabricated from the high strength steel susceptible to hydrogen [2] l embrittlement and cracking. Therefore, this ARDM is not plausibh.

-, 7 The carbon steel material of the valve body is not susceptible to intergranular [2],[4],[8]

, attack. The chromium steel trim could be susceptible if sensitized, however, the r' stem and disk are not welded and sensitization is unlikely. Also, the feedwater l

! environment is not sufficiently oxidizing to result in significant IGA. Therefore,

IGA is not plausible for the valve materials.

8 Microbiologically influenced corrosion is not plausible due to the chemical [2],[8]

conditions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through feedwater/ condensate chemistry control. Additionally, normal feedwater temperature is above 200F making MIC not possible.

9 Control of feedwater chemistry ensures essentiauy no particulate matter in the [8]

feedwater flowstream. Therefore particulate wear erosion is not plausible.

l 10 The thermal damage and radiation damage ARDMs affect non-metallics only. [1],[2]

There are no non-metallic pressure retaining materials in these valves.

I1 Carbon and chromium steel materials are not susceptible to selective leaching. [3],[7],[9]

Therefore, this ARDM is not plausible.

12 Control of feedwater chemistry (particularly oxygen concentration) prevents the [2],[8]

environment necessary for SCC of carbon and alloy steel material. Therefore, this ARDM is not plausible. 4 13 Stress relaxation requires constant strain at temperatures greater than 700F. The [2],[7] l maximum temperature to which these valves are exposed is - 435F. Therefore, stress relaxation of bonnet bolting (or other pressure retaining parts) is not l plausible.

14 The temperature to which these valves are exposed ( ~ 435F max.) is not sufficient [7], [10]

to result in thermal embrittlement. Thermal embrittlement oflow carbon or alloy steels requires temperatures greater than 650F.

15 There is typically no relative motion between pressure retaining parts of these hand [I1],[12]

valves. The valves are not operated (opened / closed) often and no significant p seating surface wear is expected. Therefore, wear is not plausible.

l Revision i Page 1 of 3 Date: March 19,1996 l

l 1

Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST

[^ SYSTEM NUMBER: 045 SYSTriM NAME: Main Feedwater l (~ EQUIPMENT TYPE: VALVE DEVICE TYPE: HV GROUP ID (if applicable): 045-HV-02 CODE DESCRIPTION SOURCE 16 The valve bonnet bolting is exposed to the containment atmosphere and is not l [2],[5],[6]

exposed to the feedwater system fluid flowstream. This environment is not conducive to significant corrosion of the carbon or alloy steel bolting. Therefore, the corrosion and erosion mechanisms are not plausible.

17 Bolting pre-load limits the efTects of fatigue. Fatigue is not plausible for the [9]

l bonnet bolting.

! 18 The chromium content in the trim material results in resisitance to general [2],[4],[8]

corrosion, pitting and crevice corrosion, particularly in the controlled chemistry l feedwater environment. Additionally, limited pitting and corrosion of the trim (in

! the area of the packing, which is the most aggressive area for corrosion) would not l affect the pressure boundary function of the sub-component. Therefore, general corrosion, pitting and crevice corrosion are not plausible for the valve trim.

l A Crevice corrosion and pitting can occur in areas of the hand valves that are not [2J,[3],[8]

exposed to the general flowstream such as at the valve body-to-bonnet interface, the valve body-to-seat ring interface, and other crevices. These areas may

( comprise small localized volumes of stagnant solution for w hich fluid chemistry l may deviate from bulk system chemistry. Higher concentrations ofimpurities may

! exist in these crevices due to out-of-specification system chemistry during shutdown conditions and due to the stagnant flow conditions of the crevice. The resulting degradation is highly localized pits or cracks. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of h

V crevice corrosion and pitting.

The effects of crevice corrosion and pitting can not be dismissed due to the potential for crevice locations and potentially high impurity concentrations in the system during shutdown conditions. Manacement of the effects of crevice l corrosion and pitting should consist of: 1) maintenance of the current system l l chemistry control program, and 2) subjecting a representative sample of vah es  !

j (from valves in this group or representative components in other portions of the l l plant) to an inspection to determine the extent oflocalized degradation occurring in  !

l the feedwater hand valves.

B General corrosion of the feedwater hand valves is plausible due to exposure of the (2),[3),

carbon steel materials to a potentially corrosive medium during shutdown periods [4].[8]

and, to a lesser extent, during operation. The rate of general corrosion is low after the initial build-up of the protective corrosion film (magnetite). Exposure to high j oxygen concentrations during shutdown can result in general corrosion. The effect i I

i of general corrosion is component wall thinning over a relatively large area and l

could result in pressure boundary failure if extensive. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of general corrosion. Management of the effects of general corrosion should consist of: 1) maintenance of the current system chernistry control program, and 2) subjecting a representative sample of valves (from valves in this group or l

representative components in other portions of the plant) to an inspection to l determine the extent of general corrosion occurring in the feedwater hand valves.

O Resision i Page 2 of 3 Date: March 19.1996 l

Component Aging Management Review l ATTACHMENT 6, MATRIX CODE LIST SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE: HV GROUP ID (if applicable): 045-HV-02 Reference List Source Title

{ [1] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November i

1981 I

[2] Environmental Effects on Components: Commentary for ASME Section Ill, EPRI Report No. NP-5775, April 1988

[3] Corrosion Engineering, Fontana and Greene,1978

[4] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, j i Third Edition,1985 l [5] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System. Unit !

l [6] Drawing 62702, Sheet 4, Rev. 30; Condensate and Feedwater System. Unit 2 l l

[7] UFSAR, Rev.18; Chapter 4 - Reactor Coolant and Associated Systems, Chapter 10 - Steam and Power Conversion Systems l [8] CP-217, Rev. 5; Chemistry Specifications and Surveillance Secondary System I l [9] Marks' Standard llandbook for Mechanical Engineers,8th Edition, McGraw-11ill  !

[10] Metals 11andbook,9th Edition, Volumes I and 13, ASM l [11] ASME Wear Control 11andbook, Peterson and Winer,1980 i

, [12] OI-12A-1, Rev. 22/OI-12A-2, Rev.14; Feedwater System Operating Instructions l .

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i Revision 1 Page 3 of 3 Date: March 19,1996 I

l Component Aging Management Review i ATTACilMENT 3, COMPONFNT GROUPING

SUMMARY

SIIEET o

SYSTEM: Main Feedwater (045) l GROUP ID NUMBER: 045-MOV-01 1 GROUP ATTRIBUTES:

l 1. Device Type: MOV ,

l 2. Vendor: Vetan  ;

l 3. Model Number: B20-2 ASPS-02TS I l 4. Material: Carbon Steel l 5. Internal Environment: Controlled chemistry water at un to 435F t I 6. External Environment: Climate controlled atmospheric air (Auxiliary Blde)  !

l 7. Function: Maintain system pIgssure boundarv )

8. Name Plate Data:

PARAMETER VALUE System Temperature Variable from ambient (70F) when j shutdown to-435F uhen operating l (subject to semperature cycles l associated with plant start-up /  !

I shutdow n and operational transients)

System Pressure </= 1300 psig Normal Operating Position Open Valve Type Motor Operated Gate l ,

,f

/3 '1 l

1 l %l 1

LIST OF G ROUPED COMPONENTS (EQUIPMENT ID):

Eauinment ID Descrintion Equipment ID Descrintion ,

j IMOV4516VLV i1 SG FW ISOL 2MOV4516VLY 21 SG fW ISOL i IMOV4517VLV 12 SG FW ISOL 2MOV4517VLV 22 SG FW ISOL l

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i I Revision i Pagei ofI Date: March 12,1996

r XITACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION n

Component Agingsmagement Review SYSTEM NUNIBER: 045 SYSTEM NAMIk Main Feedwater EQUIPMENT ID: NA GROUP ID: 045-MOV-01 Subject to Sul> Group ID Sub-ComponentNa me . Alanufacturer Material Stodel Number Passive Intended Function (s) 'AMR 1 Replacement Pgm) (Source) (Source) (Source) (Source) (Y or N) 045-310V-01 A Body. Bonnet Velan Carbon Steel w/ Fig. # B20-2A5PS- Maintain system pressure boundary Y Stellited near 2TS surfaces (None) (12717-0002) (12717-0002) (12717-0002) (CLSR) 045-3 TOV-OlB Stem Velan 410 SS Fig. # B20-2 ASPS- Maintain system pressure boundary Y 2TS (None) (12717-0002) (12717-0002) (12717 4 002) (CLSR) 045-310V-01C Wedge, Seat Ring Velan Carbon Steel w/ Fig. # B20-2 ASPS- Maintain system pressure boundary (SR to NSR Y Stellited near 2TS boundary) surfaces (None) (12717-0002) (12717-0002) (12717-0002) (CLSR) 045-310V DID Body / Bonnet Bolting Velan Carbon or Alloy Fig. # B20-2 ASPS- Slaintain system pressure boundary Y Stect 2TS (None) (12717-00G2) (12717-0002) (12717-0002) (CLSR) 045-310V-01E Non-pressure retaining parts Velan Various Fig # B20-2 ASPS- None (Non-pressure retaining) N 2TS (NA) (12717-0002) (12717-0002) (12717-0002) (NA) f 4

Revision 1 .Page1 ofI Date: March 12,1996

Component Aging Management Review ATTACIIMENT 5, ARDM MATRIX SYSTEM NUMBER: 045 SYSTEM NAME: Maia Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE: MOV GROUP ID(if applicable): 045-MOV-01 GROUP OR SUB GROUP ID .

ARDMs 045-MOV-01 A 045-MOV-OlB 045-MOV-01C 045-MOV-01D (Body / Cover) - (Stem) (Wedge, Seat) .- (Bolting) -

CAVITATION EROSION i - 1 1 16 CORROSION FATIGUE 2 2 2 16 I CREVICE CORROSION A A A 16 EROSION CORROSION B B B 16 FATIGUE 3 3 3 17 FOULING 4 4 4 16 G ALVANIC CORROSION 5 5 5 16 GENERAL CORROSION C C C 16 IlYDROGEN DAM AGE 6 6 6 16

,. INTERGRANULAR ATTACK 7 7 7 16 MIC 8 8 8 16 PARTICULATE WEAR EROSION 9 9 9 16

• PITTING A A A 16 RADIATION DAMAGE 10 10 10 10 SELECTIVE LEACillNG 11 11 11 16 STRESS CORROSION CRACKING 12 12 12 16 STRESS RELA) ATION 13 13 13 13 TIIERMAL DAN. \GE 10 10 10 10 TilERMAL EMBib "TLEMENT 14 14 14 14 WEAR 15 15 18 15 O

l Res tsion i PageIofI Date: March 12,1996 m

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Component Aging Management Review ATTACIIMENT 6, MATRIX CODE LIST Q SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater Q EQUIPMENT TYPE:

GROUP ID (if applicable):

VALVE 045-MOV-01 DEVICE TYPE: MOV CODE DESCRIPTION 1

SOURCE The feedwater system fluid 11( v conditions, pressure and temperature do not result [3],[8]

in cavitation at the feedwater icolation valves. The flow is relatively steady and the pressure is much greater than the vapor pressure at system temperature. Therefore, cavitation erosion is not plausible.

2 Control of system chemistry results in limited corrosion, and thermal fatigue is not [3]

plausible for these valves. Herefore, corrosion fatigue is not plausible.

3 The feedwater isolation valves are far removed from the S/G, and are not subject to [3),[6],

rapid thermal transient conditions associated with the S/G feedwater nozzle / piping [7],[8],

thermal stratification conditions. The sources of thermal cycling for the MOVs are [14],[15]

plant start-ups/ shutdowns and secondary plant transients. Thermal fatigue effects result from thermal expansion stresses due to temperature cycles and is primarily a I problem for piping systems. Based on the limited number of temperature cycles and relatively low thermal stresses developed in the valve body, thermal fatigue is not considered plausible for these valves.

4 Fouling does not affect the component function. The component intended function [3],[10]

is to maintain the pressure boundary integrity only. Due to the control of feedwater chemistry, fouling (including contamination and sedimentation) is not expected.

Any fouling or sedimentation will not have an affect on the intended function.

5 The valve materials of construction are carbon steel with a stainless steel stem. [4],[9],

Feedwater system water chemistry is controlled to minimize fluid conductivity. [10]

Based on the large anode (CS parts) surface area and low conductivity electrolyte,

((j'N palvanic corrosion is not plausible.

6 The valves (and subcomponeTits) are not fabricated from the high strength steel [3]

susceptible to hydrogen embrittlement and cracking. Therefore, this ARDM is not plausible.

7 Carbon steel and martensitic SS material are not susceptible to intergranular attack. l3]  ;

8 Mi.:robiologically innuenced corrosion is not plausible due to the chemical [3J, [10]

conditions and temperature of the working fluid in the system. The source for feedwater is demineralized water, and organic contaminants are avoided through feedwater/ condensate chemistry control. Additionally, normal feedwater temperature is above 200F making MIC not possible.

9 Control of feedwater chemistry ensures essentiahy no particulate matter in the [10]

feedwater Dowstream. Therefore, particulate wear erosion is not plausible.

10 The thermal damage and radiation damage ARDMs effect non-metallics only. [1],[3]

There are no non-metallic pressure retaining materials in these valves.

I1 Carbon and alloy steel materials are not susceptible to selective leaching. [4),[8],

Therefore, this ARDM is not plausible. {l11 12 Control of feedwater chemistry (particularly oxygen concentration) prevents the [3],[5], ,

environment necessary for SCC of carbon steel material. Also, the 410SS stem [10]  !

material is not in a highly stressed application. Therefore, this ARDM is not  !

plausible. ,

13 Stress relaxation requires constant strain at temperatures greater than 700F. The [3),[8] l maximum temperature to which the check valves are exposed is - 435F.

Therefore, stress relaxation of pressure seal bolting (or other pressure retaining j parts) is not plausible. I 14 The feedwater system operating temperature of ~ 435F max. is not sufficient to [8J,ll2J I g result in thermal embrittlement. Thermal embrittlement oflow carbon or alloy l steels requires temperatures greater than 650F.

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Resision i pageIof4 Date: April 16,1996  !

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Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST l

! []!

(,

SYSTEM NUMBER:

EQUIPMENT TYPE:

GROUP ID(if applicable):

045 VALVE SYSTEM NAME:

DEVICE TYPE:

Main Feedwater MOV 045-MOV-01 CODE DESCRIPTION SOURCE 15 Surfaces of the MOVs pressure retaining boundary that are subject to wear are l

I

[9],[13]

hard-faced with a wear and corrosion resistant material (Stellite #6) to prevent l degradation. Based on this protective surface treatment and limited relative motion of pressure retaining parts, wear is not plausible.

16 The valve pressure seal bolting is exposed to the auxiliary building atmosphere and [3],[6],[7]

is not exposed to the feedwater system fluid flowstream. This environment is not conducive to significant corrosion of the carbon or elloy steel bolting. Therefore, the corrosion and erosion mechanisms are not plausible.

17 Bolting pre-load and cover-to-body joint design limit the effects of fatigue. [11]

Fatigue is not plausible for the pressure seal bolting.

I8 Wear of the MOV seating surfaces can occur due to valve cycling. Excessive wear [9),[13J, can result in significant leakage through the valve seat. Ilowever, the valve seating [16),[17]

surfaces are hard-faced with Stellite #6 to minimize the effects of wear. In addition, these valves are classified as IST Category B (leakage through the seat is inconsequential to valve function) and, as such, are not subject to seat leakage testing requirements. Therefore, limited seating surface wear will not affect the function of the feedwater isolation valves, and wear is not a plausible ARDM.

A Crevice corrosion and pitting can occur in areas of the feedwater isolation valves [3],[4],

,* that are not exposed to the general flowstream such as at the valve cover-to-body [10]

interface, the valve body-to-seat ring interface, and other crevices. These areas may comprise small localized volumes of stagnant solution for which fluid

([)

chemistry may deviate from bulk system chemistry. Higher concentrations of impurities may exist in these crevices due to out-of-specification system chemistry 1

i during shutdown conditions and due to the stagnant flow conditions of the crevice. l The resulting degradation is highly localized pits or cracks. The control of feedwater/ condensate system fluid chemistry significantly limits the effects of crevice corrosion and pitting.

The effects of crevice corrosion and pitting can not be dismissed due to the potential for crevice locations and potentially high impurity concentrations in the system during shutdown conditions. Management of the effects of crevice corrosion and pitting should consist of: 1) maintenance of the current system chemistry control program, and 2) subjecting a representative sample of valves (from valves in this group or representative components in other portions of the plant) to an inspection to determine the extent oflocalized degradation occurring in the feedwater isolation valves.

B Erosion corrosion is plausible due to high velocity, high energy fluid flow [2],[3],

conditions. The effects of erosion corrosion include potentially rapid component [8], [10]

wall thinning to the point of pressure boundary failure. The control of feedwater system fluid chemistry limits the effects of erosion corrosion. Management of the effects of crosion corrosion should consist of: 1) n aintenance of the current system chemistry control program, and 2) subjecting a representative sample of the valves (from valves in this group or representative components in other portions of the plant) to an inspection to determine the extent of erosion corrosion occurring in the feedwater isolation valves.

l ln 1 l V Revision 1 Page 2 of 4 Date: April 16,1996

Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST N SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater EQUIPMENT TYPE: VALVE DEVICE TYPE: MOV GROUP ID(if applicable): 045-MOV-01 CODE DESCRIPTION SOURCE C General corrosian of the feedwater isolation valves is plausible due to exposure of [3],[4],

the carbon steel materials to potentially corrosive medium during shutdown periods [5], (10]

and, to a lesser extent, during operation. The rate of general corrosion is low after the initial build-up of the protective corrosion film (magnetite). Exposure to high oxygen concentrations during shutdown and potential removal and re-creation of the corrosior tik n result in general corrosion. The effect of general corrosion is componer*. wall '.hinning over a relatively large area and could result in pressure bounda<y failure if extensive. The control of feedwater/ condensate system fluid chemi.stry significantly limits the effects of general corrosion. Management of the efferts of general corrosion should consist of: 1) maintenance of the current sy.sem chemistry control program, and 2) subjecting a representative sample of vt Ives (from valves in this group or representative components in other portions of the plant) to an inspection to determine the extent of general corrosion occurring in the icedwater isolation valves.

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j Revision i Page 3 of 4 Date: April 16,1996 t

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Component Aging Management Review ATTACHMENT 6, MATRIX CODE LIST SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater

' EQUIPMENT TYPE: VALVE DEVICE TYPE: MOV GROUP ID(if applicable): 045-MOV-01 Reference List Source Title

[1] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, November 1981

[2] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985

[3] Environmental Effects on Components: Commentary for ASME Section III, EPRI Report No. NP- ,

5775, April 1988

[4] Corrosion Engineering, Fontana and Greene,1978

[5] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, Third Edition,1985

[6] Drawing 60702, Sheet 4, Rev. 28; Condensate and Feedwater System, Unit I t

[7] Drawing 62702, Sheet 4, Rev. 30; Condensate and Feedwater System, Unit 2 *

[8] UFSAR, Rev.18; Chapter 4 - Reactor Coolant and Associated Systems, Chapter 10 - Steam and Power Conversion Systems '

.[9] Drawing 12717-02, Rev. L; Pressure Seal Gate Valve Assembly

[10] CP-217, Rev,5; Chemistry Specifications and Surveillance - Secondary System

[11] Marks' Standard liandbook for Mechanical Engineers,8th Edition, McGraw-liill '

l ., [12] Metals llandbook,9th Edition, Volumes 1 and 13, ASM

, [13] ASME Wear Control llandbook, Peterson and Winer,1980

[14] Drawing 12543A-01, Rev.13; Feedwater Piping Isometric, Unit 1 ,

I.

.( [15] Drawing 13547A 20, Rev. 6F; 13547A-47. Rev. 4; 13549A-26, Rev. 3; Feedwater Piping Isometric, Unit 2

[16] ASME Boiler and Pressure Vessel Code,Section XI"Ruies for Inservice Inspection of Nuclear  !

Power Plant Components", Subsection IWV-2000; 1983 ed. w/ Summer '83 addenda

[17] CCNPP ASME Section XI Pump and Valve Test Program, Second Ten Year Interval, Revision 1 ,

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i N Revision 1 Page 4 of 4 Date: April 16,1996

O O Ccmpon;nt Aging 1%m Argement Review O

ATTACHMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater COMPONENTID: NA GROUP ID: 045-DB-01 1 _

2 .

3?

PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGMENT -

. FROM ALTERNATIVE CHOSEN !

ATTACllMENT 5 Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for

Pitting, General concentration of corrosive impurities (chlorides, Feedwater System components.

Corrosion, Corrosion sulfates, oxygen):

Fatigue CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation due to the effects of The occurrence of crevice corrosion, pitting and general corrosion are crevice corrosion, pitting, and general corrosion through expected to be limited and may not affect the intended function of the inspection of representative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of program) .

appropriate corrective action if significant corrosion is occuring.

Erosion Corrosion Monitor Feedwater System piping for the effects of An erosion corrosion monitoring program is effective in determining a erosion corrosion: rate of degradation and preventing erosion corrosion from affecting the MN-3-111, Erosion Corrosion Monitoring of component intended function.

Secondary Piping Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for concentration of corrosive impurities (chlorides, Feedwater System components, and limits the rate and effects of erosion sulfates, oxygen) and optimize fluid pH: . corrosion.

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Fatigue, Corrosion Monitor the effects of thermal fatigue: Tracking and monitoring the fatigue status of Feedwater System Fatigue CCNPP Fatigue Monitoring Program (with components will ensure that fatigue threshholds are not exceeded and modifications) that fatigue cracks are prevented or controlled. Through control of corrosion and monitoring of thermal fatigue effects, corrosion fatigue is also managed such that the efrects will not prevent the component intended function.

I Revision i Page 1 of 7 Date: April 11,1996

_ _ _ - _ - . - - _ _ _ - _ - _ _ _ _ _ _ _ - .__ _ - - - - - - ~ . - - - - - - - - - -. .- - -- - - _ _ - - _ -

n Comporent Agingbn:gement Rzwiew

- ATTACilMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES O i l ,

SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater .

COMPONENT ID: NA GROUP ID: 045-DB-02 1 2 3 PLAUSlHLE ARDM PLANT PROGRAM REASON FOR TIIE FORM OF AGING MANAGMENT i FROM ALTERNATIVE CHOSEN ATTACllMENT S I Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for Pitting, General concentration of corrosive impurities (chlorides, sulfates, Feedwater System components.

Corrosion oxygen):

• CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation due to the etTects of The occurrence of crevice corrosion, pitting and general corrosion are crevice corrosion, pitting, and general corrosien through expected to be limited and may not affect the intended function of the insnection of representative plant components prior to Feedwater System components due to the control of fluid chemistry. l the period of extended operations: Inspections of representative plant components will provide assurance r Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of  ;

program) appropriate corrective action if significant corrosion is occuring.

Erosion Corrosion Monitor Feedwater System piping for the effects of An erosion corrosion monitoring program is effective in determining a  :

erosion corrosion: rate of degradation and preventing erosion corrosion from affecting the MN-3-111, Erosion Corrosion Monitoring of component intended function. l Secondary Piping Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for  :

concentration of corrosive impurities (chlorides, sulfates, Feedwater System components, and limits the rate and efTects of erosion oxygen) and optimize fluid pH: corrosion. j CP-0217, Chemistry Specifications and Surveillance - [

Secondary Systems Revision 1 Page 2 of 7 Date: April 11,1996 i

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Compon:nt Aging .;tn:gcJnent Review ATTACllMENT 8. DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES i

SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater -

COMPONENT ID: NA GROUP ID: 045-CKV-01  !

I 2 3 <

PLAUSlHLE ARDM PLANT PROGRAM REASON FOR Tile FORM OF AGING MANAGMENT. j FROM ALTEPNATIVE CllOSEN -

ATTACIIMENT 5 Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for t Pitting, General concentration of corrosive impurities (chlorides, Feedwater System components.  !

Corrosion. Corrosion sulfates, oxygen): [

Fatigue CP-0217, Chemistry Specifications and Surveillance - t Secondary Systems i Determine the extent of degradation due to the effects of The occurrence of crevice corrosion, pitting and general corrosion are ,

crevice corrosion, pitting, and general corrosion through expected to be limited and may not afTect the intended function of the inspection of representative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance  ;

Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of I program) appropriate corrective action if significant corrosion is occuring. j Erosion Corrosion Monitor the Feedwater System S/G check valves for the An erosion corrosion monitoring program is effective in determining a i efTects of erosion corrosion: rate of degradation and preventing erosion corrosion from affecting the l Special Inspections of Feedwater IIcader Steam component intended function.

Generator Check Valves - Repetitive Tasks  ;

10452052,10452053,20452043, and 20452044 r Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for concentration of corrosive impurities (chlorides, Feedwater System components, and limits the rate and effects of erosion '

sulfates, oxygen) and optimize fluid pil: corrosion. j CP-0217, Chemistry Specifications and Surveillance -  ;

Secondary Systems  !

Fatigue, Corrosion Monitor the effects of thermal fatigue: Tracking and monitoring the fatigue status of Feedwater System ,

Fatigue CCNPP Fatigue Monitoring Program (with components will ensure that fatigue threshholds are not exceeded and modifications) that fatigue cracks are prevented or controlled. Through control of corrosion and monitoring of thermal fatigue efTects, corrosion fatigue is i also managed such that the effects will not prevent the component  !

intended function. l l

Resision 1 Page 3 of 7 Date: April 11,1996

f F)

Compoient Agu. mganzt R:v.iew ATTACIIMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES t

SYSTEM NUMBER- 045 SYSTEM NAME- Main Feedwater COMPONENTID: NA GROUP ID: 045-HV-01 1 2 -3 PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGMENT FROM ALTERNATIVE CHOSEN ,

ATTACilMENT 5 Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for Pitting, General concentration of corrosive impurities (chlorides, Feedwater System components.

Corrosion sulfates, oxygen):

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems i Determine the extent of degradation due to the effects of The occurrence of crevice corrosion, pitting and general corrosion are crevice corrosior: pitting, and general corrosion through expected to be limited and may not affect the intended function of the inspection of represer.tative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of program) appropriate corrective action if significant corrosion is occuring.

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Compone:t Aging _ Snagement Review O

ATTACilMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES SYSTEM NUMBER: 0 15 SYSTEM NAME: Main Feedwater COMPONENT ID: NA GROUP ID: 045-HV-02 1 2 3-PLAUSIHLE ARDM PLANT PROGRAM i REASON FOR THE FORM OF AGING MANAGMENT FROM ALTERNATIVE CHOSEN ATTACllMENT S Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for Pitting, General concentration of corrosive impurities (chlorides, Feedwater System components.

Corrosion sulfates, oxygen):

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Detennine the extent of degradation due to the effects of The occurrence of crevice corrosion, pitting and general corrosion are crevice corrosion, pitting, and general corrosien through expected to be limited and may not affect the intended function of the inspection of representative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of program) appropriate corrective action if significant corrosion is occuring.

Revision 1 Page 5 of 7 Date: April 11,1996

D \

Component AginkhiCgem:nt Review

/ ) '

ATTAClIMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater COMPONENT ID: NA GROUP ID: 045-MOV-01 t

i 2 3

• PLAUSillLE ARDM PLANT PROGRAM REASON FOR TIIE FORM OF AGING MANAGMENT FROM ALTERNATIVE CHOSEN ATTACllMENT 5 Crevice Corrosion, Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for Pitting, General concentration of corrosive impurities (chlorides, Feedwater System components.

Corrosion sulfates, oxygen):

CP-0217 Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation due to the effects of The occurrence of. crevice corrosion, pitting and general corrosion are crevice corrosion, pitting, and general corrosion through expected to be limited and may not affect the intended function of the inspection of representative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of program) appropriate corrective action if significant corrosion is occuring.

Erosion Corrosion Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for concentration of corrosive impurities (chlorides, Feedwater System components, and limits the rate and effects of erosion sulfates, oxygen) and optimize fluid pil: corrosion.

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation dee to the effects of The occurrence of erosion corrosion is expected to be limited and may erosion corrosion through inspection of representative not affect the intended function of the Feedwater System MOVs due to plant components prior to the period of extended the control of fluid chemistry and non-conducive flow geometry of the operations: valve. Inspections of representative plant components will provide Age-Related Degradation Inspection Program (new assurance that significant erosion corrosion is not occurring, or will result program) in initiation of appropriate corrective action if significant erosion corrosion is occuring.

Revision 1 Page 6 of 7 Date: April 11,1996

Om Compo:ent (m Aging.bn>igement Review U^

ATTACHMENT 8, DEVELOPMENT OF AGING MANAGEMENT ALTERNATIVES SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater COMPONENT ID: NA GROUP ID: 045-TE-01 1 2- 3-PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGMENT' FROM ALTERNATIVE CHOSEN ATTACIIMENT 5 Crevice Corrosion, Control system fluid chemistry in order to minimize t1e Control of fluid chemistry prevents a corrosive environment for Pitting. General Corrosion concentration of corrosive impurities (chlorides, Fcedwater System components.

sulfates, oxygen):

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation due to the effects of The occurrence of crevice corrosion, pitting and general corrosion are crevice corrosion, pitting, and general corrosion through expected to be limited and may not affect the intended function of the inspection of representative plant components prior to Feedwater System components due to the control of fluid chemistry.

the period of extended operations: Inspections of representative plant components will provide assurance Age-Related Degradation Inspection Program (new that significant corrosion is not occurring, or will result in initiation of program) appropriate corrective action if significant cotrosion is occuring.

Erosion Corrosion Control system fluid chemistry in order to minimize the Control of fluid chemistry prevents a corrosive environment for concentration of corrosive impurities (chlorides, Feedwater System components, and limits the rate and effects of erosion sulfates, oxygen) and optimize tiuid pil: corrosion.

CP-0217, Chemistry Specifications and Surveillance -

Secondary Systems Determine the extent of degradation due to the effects of The occurrence of erosion corrosion is expected to be limited and may erosion corrosion through inspection of representative not affect the intended function of the Feedwater System thermowells plant components prior to the period of extended due to the control of fluid chemistry and thermowell material of operations: construction. Inspections of representative plant components will Age-Related Degradation Inspection Program (new provide assurance that significant erosion corrosion is not occurring, or i program) will result in initiation of appropriate corrective action if significant  ;

erosion corrosion is occuring.

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Revision 1 Pay 7 of 7 Date: April 11,1996

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Component Agingh ragement Review ATTACHMENT 10, PROGRAM / ACTIVITY (PA) MODIFICATIONS SYSTEM NUMBER: 045 SYSTEM NAME: Main Feedwater  !

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PATFASK ID and . PRESENT DESCRIPTION - NEW/ REVISED 1 AFFECTED PORTION CORRECTIVE ACTION / RECOMMENDATION!

Age-Related Degradation New Program The ARDI Program must provide requirements for i inspection (ARDI) Program identification of representative plant components for inspection i based on the results of this aging management review, the inspection sample size, appropriate inspection techniques, and requirements for reporting of results and corrective actions.

Reference BGE Memorandum LCM 96-044, dated 2-15-96, for  !*

furtlier information.

CCNPP Fatigue Monitoring The FMP currently excludes the Main Feedwater System from An evaluation of the Feedwater System piping and components Program (FMP)- Scope of the scope of the program. (for which thermal fatigue is plausible) is required in order to program portion; determine whether current fatigue monitoring practice ,

Commitment 01 envelopes fatigue effects on Feedwater components. The FMP must be modified, as necessary, to monitor appropriate plant components such that the thermal fatigue effects of Feedwater components are bounded and managed.

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