ML20112B970
| ML20112B970 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/21/1996 |
| From: | Doroshuk B, Hatch T, Scoggin D BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20112B955 | List: |
| References | |
| NUDOCS 9605240109 | |
| Download: ML20112B970 (170) | |
Text
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O Calvert Cliffs NuclearPowerPlant License RenewalProject Aging Management Review Report for the Radiation Monitoring System (077/079)
Rc-ision 1 May,1996 Prepared by: Mb45 Date: 6/#/f4 j
'D. B. $coggin l Reviewed by: T9 Ath>-. Date: s/m/f a T. It Hatch Approved by: I Date: f/'tilfb
- 8. W. Doroshuk O
hDk AOOOK 05 317 P PDR
O Calvert Cliffs Nuclear PowerPlant License RenewalProject Aging Management Review Report for the O Area and Process Radiation Monitoring System _
(077/079)
Revision 1 May ,1996 O
Radiation Monitoring System Aging Management Review Report rh C Table of Contents E.*TS List of Tables ii List of Effective Pages iii
1.0 INTRODUCTION
1.1 Area and Process Radiation Monitoring System Description 1-1 l
l.1.1 Area and Process Radiation Monitoring System Description 1-1 1.1.2 Area and Process Radiation Monitoring System Boundary 1-1 1.1.3 Area and Process Radiation Monitoring Intended System Functions 1-2 1.2 Evaluation Methods 1-3 1.3 S) stem-Specific Definitions 1-3 1.4 System-Specific References 1-3 ,
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2.0 STRUCTURES AND COMPONENTS WITHIN THE SCOPE OF LICENSE RENEWAL 2.1 Component 1ael Scoping Methodology Oveniew 2-1 2.2 Componentlevel Scoping Results 2-1 0, _
3.0 COMPONENT PRE-EVALUATION
- 3. Pre-evaluation Methodology Oveniew 3-1 3.2 Pre-evaluation Results 3-1 4.0 COMPONENT AGING MANAGEMENT REVIEW 4.1 Aging Management Review Methodology Oveniew 4-1 4-1 l 4.2 Age-Related Deg adation Mechanisms 4.2.1 Potential ARDMs 4-2 4.2.2 Component Grouping 4-2 4.2.3 Plausible ARDMs 4-3 4.3 Methods to Manage the Effects of Aging 4-3 Appendix A Area and Process Radiation Monitoring System Aging Management Rmiew Results lO i Revision 1
Radiation Monitoring System Aging Management Review Report List of Tables
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Table 1-1 System-Specific References 1-4 Table 2-1 Area and Process Radiation Monitoring System Device Types 2-2 Within The Scope Of License Renewal Table 3-1 Area and Process Radiation Monitoring System Intended System 3-2 Function Disposition Table 3-2 Summary of Area and Process RMS Device Types Requiring Aging 3-3 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 0 .
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List of Effective Pages 1 \
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Description:
All 0 Initialissue All .I 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 Area and Process Radiation Monitoring System Description This section describes the scope and boundaries of the Area and Process Radiation Monitoring System (RMS) as it was evaluated. Section 1.1.1 provides a brief synopsis of the system as described in existing plant documentation. System boundaries are provided in Section 1.1.2 to clarify the extent of the Area and Process Radiation Monitoring System considered in this evaluation. Section 1.1.3 is a detailed breakdown of the intended system functions within the scope of license renewal and is provided as the basis for +he identification of components required to support those intended functions. ;
l 1.1.1 Area and Process Radiation Monitoring System Description )
l The purpose of the Area and Process Radiation Monitoring System is to warn l operating personnel of an increasing radiation level or abnormal radioactivity I concentration at selected points in the plant. This warning system may also indicate a system or component malfunction which needs operator action or it may perform automatic protective actions to correct and/or isolate an abnormal condition to prevent an uncontrolled release of radioactive material to the g environment. The Area and Process Radiation Monitoring System includes j
() _ various process radiation monitoring subsystems such as the plant main vent monitor, wide range gas monitor, contamment atmosphere monitor, waste gas discharge monitor, liquid waste processing discharge monitor, condensate air removal discharge monitor, Component Cooling Water System monitor, Service Water System monitor, steam generator blowdown tank discharge monitor, steam generator recovery radiation monitor, control room ventilation monitor, atmosphere monitors and main steam effluent radiation monitor. It also includes area radiation monitors in 29 areas plus six monitors in each contamment.
The Area and Process Radiation Monitoring System was determined to be within the scope oflicense renewal during the system level scoping process.
1.1.2 Area and Process Radiation Monitoring System Boundaries The Area and Process Radiation Monitoring System is comprised of the following equipment:
Pumps Several of the radiation monitor trains contain pumps which move the fluid being sampled.
Valves Provide contamment isolation and system alignment / isolation (control, check, hand, motor operated and solenoid valves).
I d Filters Filter air to protect downstream components.
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Instrumentation / Provides data to operators and automatic .
I elements systems Piping / tubing Provides flowpath and maintains pressure l
boundary. ,
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l The Area and Process Radiation Monitoring System interfaces with the following j systems and components- '
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Plant vent Contamment vent l
Component Cool.r2g System Service Water System Control Room HVAC System 1.1.3 Area and Process Radiation Monitoring Intended System Functions j l
. Provide contamment area radiation signal to ESFAS for containment isolation l I
and radiological release control
. Provide contamment high range radiation signal for containment environment monitoring and to isolate the contamment vent / hydrogen purge lines
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. Provide information to assess the environs and plant Eondition during and following an accident
. Maintain functionality of electrical equipment as addressed by the EQ Program
. Maintain the pressure boundary of the system
. Provide contamment isolation of the contamment atmosphere and purge air monitor sampling line
. Monitor and record wide range gaseous activity / release rate through the main plant vent and provide indications / alarms in the control room
. Monitor and record radiation levels indicative of effluent activity in the main steam lines and provide indications / alarms in the control room
. Provide testing capability and prevent spurious actuation of control room radiation monitoring circuitry
. Maintain electrical continuity and/or provide protection of the electrical system
. Provide seismic integrity and/or protection of SR components i
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Radiation Monitoring System Aging Management Review Report O f 1.2 Evaluation Methods Area and Process Radiation Monitoring System components within the scope of license 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.
Area and Process Radiation Monitoring 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 I I
must be evaluated for management of the effects of age-related degradation. He results of the Pre-evaluation process are discussed in Section 3.0 of this report.
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 i effects and the appropriate methods to manage those effects. The results of the Aging Management Review (AMR) process are discussed in Section 4.0 of this report.
1.3 System-Specific Definitions f'%
d This section provides the definitions for any specific terms unique to the Area and Process Radiation Monitoring component aging evaluation.
No terms unique to the Area and Process Radiation Monitoring System were used.
1.4 System-Specific References Several sources were used to determine potential and plausible ARDMs for the Area and Process Radiation Monitoring evaluation. These sources include NRC Draft Regulatory Guide DG-1009, " Standard Format and Content of Technical Information for Applications to Renew Nuclear Power Plant Operating Licenses".
Detailed drawings and other controlled documents related to the Area and Process Radiation Monitoring System were utilized to verify materials, design configurations and location of components.
Table 1-1 lists the references utilized in the completion of the Area and Process Radiation Monitoring System Aging Management Review for license renewal.
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I l Table 1-1 l System Specific References Document ID ' Document Title Revision Date l 12284-0026 P/L Temperature Probe Assembly 0 1981 12284-0028 Temperature Probe Assembly A 1981 60722-E SH0001 " Auxiliary Building Ventilation Systems" 32 1995 60738-E SH0001 " Area and Process Radiation Monitoring 45 1995 l
System" 60738-E SH0002 Operations Drawing " Area and Process 10 1995 Radiation Monitoring System" !
92767 SH HB-1 M-600 Piping Class Sheets for HB 54 1995 92769 SH HB-7 M-601 Piping Class Summary Sheets for 22 1995 HB-5 92771 SH0001 M-602 Master Valve List 41 1995 ASM ASM Specialty Handbook, Stainless Steels, -
1994 Davis ASME ASME Wear Control Handbook, Peterson -
1980 and Winer CLSR CCNPP Component Level Screening Results 01 1995 I
- System 077/079 CP-204 Specification and Surveillance Primary 4 1995 Systems CP-206 Specifications and Surveillance Component 2 1995 Cooling / Service Water System DG-1009 Standard Format and Content of Technical -
1990 Information for Applications to Renew i Nuclear Power Plant Operating Licenses, l Draft NRC Regulatory Guide ES-014 Summary of Ambient Environmental Service 0 1995 Conditions ii i
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Table 1-1 System Specific References Document ID Document Title Revision Date ES-024 10CFR50.49 Environmental Qualification 01 1996 Program ES-032 " Control of the Equipment Technical 0 1995 Databases (Nucleis - Master Equipment List and CCETS)"
FSK-MP-1262 Non-Nuclear HB & HB-65 Nuclear 14 1992 Containment Atmosphere Radiation Monitor i Line FSK-MP-3050 Containment Atmosphere Radiation Monitor 3 1991 Line Penetration Piping I-33 Maintenance Procedure, Thomas Air Pump 4 1995 Diaphragm Replacement Procedure IFI Standards " Fastener Standards", Industrial Fastener -
1988 Institute,6th Edition (pg. A-13)
IPM13101 Replace WRNGM Thomas Air Pump -
1993 Diaphragms LCM-16 " Component Aging Management Review", 4 1995 LCM Procedure I LCM-95-095 " Radiation Monitoring Systems Component -
3/21/95 Information", letter to J. Rycyna from M.
Hotchkiss LCM-95-112 " Boric Acid Corrosion", letter to file from J. -
3/29/95 Rycyna LCM-96-044 BGE memorandum,
Subject:
Age Related 2/15/96 Degradation Inspections, dated February 15, 1996, BMT to distribution LCM 96-133 "Cenversation with Bill Cartwright, Plant 5/17/96
! Engineering, to discuss minimum ambient i
temperature in East Piping Penetration l Rooms" O
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Table 1-1 System Specific References Document ID Document Title Revision Date LCM C-96-004 Circle Seal Controls vendor information file, - -
Circle Seal Controls, Inc.
LCM S-96-009 "RE-5417/5418 WRGM Sample Chamber -
1/31/96 Details" telecon to file, M. Hothchkiss/ P.
Newman LCM S-96-019 Seelscrews vendor information file, - -
Multiflex Seals 95-BGE-0086 Gilbert Commonwealth letter forwarding -
8/29/95 MIC Position Paper N/A CCNPP Pre-evaluation Results for the 01 1996 Radiation Monitoring System (077/079)
N/A CCNPP Aging Evaluation for System 011 00 1994 A N/A CCNPP Aging Evaluation for System 015 00 1994 f
NETD CCNPP NUCLEIS Database 1996 l
l N/A Corrosion and Corrosion Control, An -
1985 Introduction to Corrosion Science and Engineering, Uhlig, Third Edition N/A Corrosion Engineering, Fontana and Greene -
1978 N/A Introduction to Physical Metallurgy, Avner, - 1974
- Second Edition N/A Structural Materials in Nuclear Power -
1981 Systems l
l N/A The Structure and Properties of Materials, -
1964 Volume I; Moffatt, Pearsall, and Wulff N/A Materials Handbook; Brady and Clauser, - -
Thirteenth Edition N/A Mark's Standard Handbook for Mechanical - -
Engineers; Avallone and Baumeister, Ninth Edition 1-6 Revision 1 l
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Table 1-1 System Specific References Document ID , Document Title Revision Date N/A Thomas Industries,727 Series Single -
1990 Cylinder, Oil-less, Diaphragm Compressors, Bulletin / Data Sheets NP-2129 EPRI Report, Radiation Effects on Organic -
1981 Materials in Nuclear Plants NP-3784 EPRI Report, A Survey of the Literature on -
1984 Low-Alloy Steel Fastener Corrosion in PWR Power Plants NP-3944 EPRI Report, Erosion / Corrosion in Nuclear -
1985 Plant Steam Piping i NP-5461 EPRI Report, Component Life Estimation: -
1987 l LWR Structural Materials Degradation l Mechanisms )
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NP-5769 EPRI Report, Degradation and Failure of -
1988
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Bolting in Nuclear Power Plants _
NP-5775 EPRI Report, Environmental Effects on -
1988 Components: Commentary for ASME Section III NP-5985 Boric Acid Corrosion of Carbon and Low -
1988 Alloy Steel Pressure Boundary Materials, EPRI Report No. NP-5985 NUREG/CR-5379 Nuclear Plant Service Water System Aging Degradation Assessment
. Volume 1 -
1989
. Volume 2 -
1992 NUREG/CR-5419 Aging Assessment ofInstrument Air Systems -
1990 NUREG/CR-5643 Insights Gained from Aging Research -
1992 l
OERDB OER Database -
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Radiation Monitoring System Aging Management Review Report Table 1-1 System Specific References Document ID Document Title Revhlon Date O&MR-132 " Particulate and Gaseous Radioactivity -
1983 !
1 Monitoring System Failures Due to Excess Moisture", Operations and Maintenance ,
Reminder, INPO l l
01-15 Service Water System Operating Instruction, Unit 1 22 1994 i Unit 2 22 1994 01-16 Component Cooling System Operating Instruction, Unit 1 20 1993 l l
Unit 2 17 1993 01-35 Radiation Monitoring System 1024 1995 01- 48 Wide Range Noble Gas Monitor 7 1995 PIPEAMG Aging Management Guidelhie for - 1995 Commercial Nuclear Power Plants - Non-Reactor Coolant Pressure Boundary Piping and Tubing, Draft (v) -_.
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STP-M-571E-1 Local Leak Rate Test, Penetrations 15,16, 0 1991 18, 38, 59, 60, 61, 62, 64, Unit 1 ,
STP-M-571E-2 Local Leak Rate Test, Penetrations 15,16, 0 1991 18, 38, 59, 60, 61, 62, 64, Unit 2 STP-O-055-1 Containment Integrity Verification Mode 1- 33 1992 4, Unit 1 STP-O-055-2 Containment Integrity Verification Mode 1- 33 1992 4, Unit 2 TR-102204 EPRI Report, Service (Salt) Water System - 1993 Life Cycle Management Evaluation UFSAR Updated Final Safety Analysis Report 19 l
VOL-1 Metals Handbook, Volume 1 - Properties - 1978 l
' and Selection: Irons and Steels, Ninth Edition, ASM International
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I Radiation Monitoring System Aging Management Review Rep?rt Table 1-1 System Specific References Document ID Document Title Revision Date VOL-13 Metals Handbook, Volume 13 - Corrosion, -
1987 l Ninth Edition, ASM International VTM 12284-010 General Atomic - Wide Range Gas Monitor 21 1996 l
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(vD 2.0 STRUCTURES AND COMPONENTS WITIIIN TIIE SCOPE OF LICENSE RENEWAL 2.1 Component Level Scoping Methodology Overview The scoping of the Area and Process Radiation Monitoring 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. He purpose of component level scoping l is to identify all system components that support the intended system functions identified in Section 1.1.3 for the Area and Process Radiation Monitoring System.
These are the components that are within the scope oflicense renewal.
2.2 Component Level Scoping Results A total of 33 device types in the Area and Precess Radiation Monitoring System were designated as within the scope oflicense renewal. These device types are listed in Table 2-1.
The portion of the Area and Process Radiation Monitoring System within the scope oflicense renewal consists of piping, components, component supports, instrumentation, panels, and cables for the following sections of the system: control room ventilation radiation monitor; containment atmosphere, high range and area radiation monitors; service water and component cooling radiation monitors; main l d- steam effluent radiation monitors; and wide range noble gas monitors.
Refer to the results of the Area and Process Radiation Monitoring System Component l Level Scoping for the list ofintended functions, the list of components within the scope oflicense renewal, and other scoping-related details.
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Table 2-1 Area and Process Radiation Monitoring System Device Types Within the Scope of License Renewal Device Tvoe Device Description
-HB Piping,ilB AE Analyzer Element CKV Check Valve CV Control Valve (& Operators)
E/I Voltage / Current Device FE Flow Element FI Flow Indicator FIS Flow Indicator Switch FL Filter, FT Flow Transmitter FU Fuse HS Handswitch IIV Hand Valve JL Power Lamp Indicator M Motor q MOV Motor Operated Valve (& Operators)
PDT Differential Pressure Transmitter
'Q PI Pressure Indicator ,
PNL Panel PUMP Pump / Driver Assembly RE Radiation Element RI Radiation Indicator RIC Radiation Indicator Controller RP Radiation Test Point RR Radiation Recorder RY Relay SV Solenoid Valve TC Temperature Controller TE Temperature Element U Heater XI Eccentricity Indicator ZL Position Indicating Lamp ZS Position Switch l
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Radiation Monitoring System Aging Management Review Report 3.0 COMPONENT PRE-EVALUATION 3.1 Pre-Evaluation Methodology Overview He component pre-evaluation procedure is used to determine which components i
are subject to an aging management review. His procedure is used to categorize intended system functions as active or passive, determine if the components l supporting passive system functions are long-lived, and identify the set of i components subject to aging management review. l l
The pre-evaluation also determines whether the components should be included in j a commodity group AMR or the system AMR.
3.2 Pre-Evaluation Results Table 3-1 summarizes the dhpcation ofintended system functions for the Area ;
and Process Radiation Monitoring System (RMS) as either active or passive.
These functions are derived from the system functions identified and documented during the component level scoping process, which are listed in subsection 1.1.3.
n Components supporting only active intended system functions (i.e., not passive d 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.
Components that are evaluated as part of commodity evaluations are addressed in separate AMRs. The RMS components dispositioned as part of commodity evaluations include all component supports , all cables *, and instrument desices without isolation valves (that are not subject to a replacement program) that support passive functions.
Several components included in the RMS pre-evaluation were previously j evaluated in AMRs of other systems and are not included in the RMS AMR. The device types of these components are noted in Table 3-2.
Table 3-2 summarizes the disposition of the device types identified in Table 2-1 as l
within the scope oflicense renewal for the Area and Process Radiation Monitoring System.
Refer to the results of the Area and Process Radiation Monitoring System Component Pre-evaluation for the list of components subject to AMR and other i l '
details.
Component supports and cables are not identified as Area and Process Radiation Monitoring system components in the Area and Process Radiation Monitoring system scoping results, but are generically included in the f
Component Supports and Cables Commodity AMRs, respectively.
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U 1 Table 3-1 .
Area and Process Radiation Monitoring System Intended System Function Disposition Function ,
Function Descriotion Passive? j 1
Provide containment area radiation signal to ESFAS No for containment isolation and radiological release control Provide containment high range radiation signal for No ;
contamment environment monitoring and to isolate the ;
contamment vent / hydrogen purge lines Provide information to assess the environs and plant No condition during and following an accident Maintain functionality of electrical equipment as No addressed by the EQ Program Yes I Maintain the pressure boundary of the system Provide contamment isolation of the containment Yes atmosphere and purge air monitor sampling line i
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\ '# Monitor and record wide rang'e gaseous activity / release No rate through the main plant vent and provide indications / alarms in the control room :
Monitor and record radiation levels indicative of No l effluent activity in the main steam lines and provide I indications / alarms in the control room Provide testing capability / prevent spurious actuation of No I control room radiation monitoring circuitry Maintain electrical continuity and/or provide protection Yes of the electrical system Provide seismic integrity and/or protection of SR Yes components l
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l Radiation Monitoring System Aging Management Review Report O Table 3-2 Summary of RMS Device Types Requiring Aging Management Review Components Components Components Componentsin Componentsin Support Passive Subject to Evaluated in Other System Radiation Device Device Fametion(s)? Replacement Commodity AMR? Monitoring Troe Description Procram? Evaluation? AMR?
-IIB Piping class Yes No No No Yes IIB AE Analyzer No No No No No l Element CKV Check Valve Yes No No Yes Yes CV Control Valve No Yes Yes No No
(& OP)
E/I Voltage /
No No No No No Current Device FE Flow Element Yes No No No Yes
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FI Flow Indicator l Yes No No No Yes l FIS Flow Indicator Yes No Yes No No _
Switch FL Filter No Yes Yes No No FT Flow No No No No No Transmitter FU Fuse No No No No No IIS Ilandswitch No No No No No I HV IIand Valve Yes Yes No No Yes l JL Power Lamp No No No No No Indicator M Motor No No No No No MOV Motor No Yes Yes No No Operated Valve PDT Differential No Yes No Yes No
- Pressure Transmitter PI Pressure Yes No Yes No No Indicator I
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Table 3-2 (continued) l l Components Components Components Components in Componentsin i Support Passive Subject to Evaluated in Other System Radiation Device Device Function (s)? Replacement Commodity AMR7 Monitoring Tvoe Description Program? Evaluation? AMR7 PNL Panel (Wide Yes No Yes No No l Range Gas l
Monitor Skids)
PUMP Pump Yes Yes No Yes No RE Radiation Yes No No Yes Yes Element RI Radiation No No No No No Indicator
, RIC Radiation
' No No No No No Indicator 1
Controller j RP Radiation Test '
i Yes No No No Yes Point RR Radiation No No No No No j Recorder O RY Relay No No No No No 1
SV Solenoid Valve No No Yes No Yes i TC Temperature No No No No No Controller TE Temperature No No No No No Element U IIcater No No No No No l XI Eccentn ity No No No No No l Indicator i ZL Position No No No No No Indicating Lamp ZS Position No No No No No Switch o
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Radiation Monitoring System Aging Management Review Report k 4.0 COMPONENT AGING MANAGEMENT REVIEW 4.1 Aging Management Review Methodology Overview The aging management review of Area and Process Radiation Monitoring 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 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:
(1) Identified potential age-related degradation mechanisms (ARDMs) for Area and Process Radiation Monitoring System components.
(2) Grouped Area and Process Radiation Monitoring System components
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V based on device type and desigsloperating environment attributes. Sub-component groups were%o detennined 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 infonnation Material of construction
- Environmental service factors Intended functions e Identification of methods to manage aging effects for plausible ARDMs and l assessment of current plant programs to determine whether these aging effects are
- adequately managed. If current programs were not adequate to manage aging effects, l program modifications or new program requirements were identified.
4.2 Age-Related Degradation Mechanisms Area and Process Radiation Monitoring 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). 'Ihe V l 1
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, v 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 Area and Process Radiation Monitoring system components. These potential ARDMs are determined on an equipment type (e.g., pipe, valve, mstrument, 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 Indicator Filter A list of potential component ARDMs was developed for each of the equipment types.
The list was developed through review ofindustry documents. The following are examples of sources of ARDM information:
p Draft NRC Regulatory Guide DG-1009 V NLIMARC (NEI) Industry Reports l NRC NPAR 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 determined on the basis of a generic component of the equipment type in service in any system in the plant.
i A summary of the potential ARDMs for each of the Area and Process Radiation ~
Monitoring 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.
l 4.2.2 Component Grouping Similar components are grouped together for evaluation efficiency. The age-related degradation evaluations results completed for a group are applicable to each of the :
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! individual components within the group. Selection of grouping attributes was j
! accomplished through consideration of the component characteristics that would most i influence the age-related degradation that could occur. Typical grouping attributes utilized for the Area and Process Radiation Monitoring 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 ;
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V l 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. j 4.2.3 Plausible ARDMs l
He list of potential ARDMs is utilized for a Area and Process Radiation Monitoring I System component-specific identification of plausible ARDMs. He plausibility determination is 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 l
External environment !
l Operational conditions / effects Affect on the passive intended function ,
l The results of the component-specific ARDM plausibility evaluation are included in )
i Attachment 5s and 6s in Appendix A. Ecse results are summarized by component Device i Type, in matrix fonn,in Table 4-2. l
. 4.3 Methods to Manage the Effects of Aging He 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 determine whether aging effects are l adequately managed for the period of extended operation, or whether program revisions or l
new programs are required. Additionally, plant modifications may be considered as a 1 method to manage aging effects. l
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I Applicable aging effects management methods are determined through consideration of the l l specific plausible ARDM, component configuration (material of construction, geometry, service conditions, etc.), and relative significance of the aging effects for the period of extended operation.
l Site programs and processes associated with the Area and Process Radiation Monitoring system were reviewed to identify those that implemented the aging effects management !
l methods determined to be necessary for the period of extended operation. These activities 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 license renewal.
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Radiation Monitoring System Aging Management Review Report O Site programs, modifications to programs, and new programs are related to specific Area and Process Radiation Monitoring system components and plausible ARDMs on Attachments 1,2, 8 and 10 in Appendix A.
l Attachment 1 in Appendix A provides a summary of Area and Process Radiation Monitoring System components (by device type) subject to aging management review, applicable passive intended function (s), plausible ARDMs, and aging effects management Programs.
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O kJ Table 4-1 Potential Age-Related Degradation Mechanisms (ARDMs) Summary Area and Process Radiation Monitoring System Equipment Types Potential ARDMs Eing Valve Eiltst Indicator Element Cavitation Erosion x x x x x Corrosion Fatigue x x x x x Creep / Shrinkage l Crevice Corrosion x x x x x Erosion / Corrosion x x x x x Fatigue x x x x x Fouling x x x x x Galvanic Corrosion x x x x x General Corrosion x x x x x Hydrogen Damage x x x x x Intergranular Attack x x x x x Irradiation Embrittlement Microbiologically Influenced x x x x x i
Comaion (MIC) g Oxidation t,j Particulate Wear Erosion . x. x x x x Patting x x x~ x x Radiation Damage x x x x x Rubber Degradation x x x x x Saline Water Attack x Selective leaching x x x x x Stress Corrosion Cracking x x x x x Stress Relaxation x x x x x hermal Damage x x x x x nermal Embrittlement x x x x x Wear x x x x x l
x - indicates that the ARDM is potentially deimental to the equipment type i
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(3 1 Table 4 2 Plausible Age-Related Degradation Mechanisms Summary Area and Process Radiation Monitoring System Device Types Plausible -HB CKV CV FE FI FL HV MOV RE RP SV ARDMs Cavitation Erosion Corrosion Fatigue Crevice x x Corrosion Erosion Corrosion Fatigue Fouling Galvanic Corrosion _
General x x Corrosion i Hydrogen i Damage l Intergrannular 1 Attack (V Particulate
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Wear Erosion Pi k g x x Radiation Damage
)
Rubber l Degradation l Saline Water l Attack l Selective I Leaching Stress Corrosion Cracking Stress Relaxation Dermal Damage Hermal Embrittlement Wear x x - indicates that the ARDM is plausible for component (s) within the Device Type O
V 4-6 Revision 1
Radiation Monitoring System Aging Management Review Report Appendix A
(^N Area and Process Radiation Monitoring System Aging Management Review Results i V l
l Attachment 1, Aging Management Review Summary Attachment 2, Description of Programs Which Manage the EfI cts of Aging Attachment 8, Development of Aging Management Alternatives I l
Attachment 10, Program / Activity (PA) Modifications l Equipment Type: ELEMENT Attachment 7, Potential ARDM List l
Device Type: FE Attachment 3, Component Grouping Sununary Sheet (077-FE-01)
Attachment 4, Sub-Component / Subgroup Identification Attachment 5, ARDM Matrix Attacluner.t 6, Matnx Code List Device Type: IE Attachment 3, Component Grouping Summary Sheet (077-RE-01)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix l
Attachment 6, Matrix Code List g
j
(_,) Attachment 3, Component Grouping Summary Sheet (077-RE-02)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List i Attachment 3, Component Grouping Sununary Sheet (077-RE-03)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List l Equipment Type: INDICATOR Attachment 7, Potential ARDM List Device Type: FI Attachment 3, Component Grouping Sumnary Sheet (077-FI-01)
Attachment 4, Sub-Component /Sub-Group Identification l Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Attachment 3, Component Grouping Summary Sheet (077-F1-02)
Attachment 4, SubComponent/Sub-Group Identification Attachment 5, ARDM Matrix V Attachment 6, Matnx Code List l
A-1 Revision !
l
Radiation Monitoring System Aging Management Review Report Appendix A A Area and Process Radiation Monitoring System Aging Management Review Results V
Equipment Type: Fil!!ER Attachment 7, Potential ARDM List Device Type: FL Attachment 3, Component Grouping Summary Sheet (077-FL-01)
Attaclunent 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attaciunent 6, Matrix Code List Equipment T>pe: PIPE Attachment 7, Potential ARDM List Device Type: -IIB Attachment 3, Component Grouping Sununary Sheet (077-IIB-01)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment o, Matrix Code List g Attaclunent 3, Component Grouping Summary Sheet (077-RP-01)
Attachment 4, Sub-Component /Sub-Grot'p Identification Attachment 5, ARDM Matrix Attaclunent 6, Matrix Code List Equipment Type: VALVE Attachment 7, Potential ARDM List Device Type: CKV l At'achment 3, Component Grouping Summary Sheet (077-CKV-01)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Device Type: CV Attachment 3, Component Grouping Summary Sheet (077-CV-01)
Attachment 4, Sub-Component /Sub-Group Identification Attaciunent 5, ARDM Matrix Attachment 6, Matrix Code List A-2 Revision 1
Radiation Monitoring System Aging Management Review Report Appendix A
(] Area and Process Radiation Monitoring System Aging Management Review Results V
Device Type: IIV Attachment 3, Component Grouping Summary Sheet (077-IIV-01)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Attachment 3, Component Grouping Summary Sheet (077-IIV-02)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Attachment 3, Component Grouping Summary Sheet (077-IIV43)
Attachment 4, Sut<omponent/Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Attachment 3, Component Grouping Summary Sheet (077-liv-04)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix d Attachment 6, Matrix Code List Device Type: MOV Attachment 3, Component Grouping Summary Sheet (077-MOV-01)
Attachment 4 Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Attaclunent 3, Component Grouping Summary Sheet (077-MOV-02)
Attachment 4, Sut<omponent/Sut@oup Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List Device Type: SV Attachment 3, Component Grouping Summary Sheet (077-SV-01)
Attachment 4, Sub-Component /Sub-Group Identification Attachment 5, ARDM Matrix Attachment 6, Matrix Code List V(3 A-3 Revision 1
Component Ating Manageme eview Summary (Revision 1)
Sy; tem Number: 077/079 Attachment 1 Syltem Name: Area and Process Radiation Monitoring Page 1 of 3 Date: May 21,1996 Subcomponents/
Subgroups Not Meneged by Group Passive Intended Grouping Subject to Aging Pleusitde Emieting . Medficatione L New Program Device Functions - Attributes Mgt Review ARDMs~ Programs ID Needed Need Type ID Maintain Press HB Pipe None Crevice Corrosion - None NA Yes
-HB 077-HB-01 Bndry Integrity Pipe / Fittings / Welds (internaf)
General Corrosion - Age Related Pipe / Fittings / Welds Degradation (internal) Inspection Pitting - Program Pipe / Fittings / Welds (internal) 077-CKV-01 Maintain Press Check Valves Internals None NA NA NA CKV Bndry integrity 077-CKV-01 B i
07 7-CV-01 Cont isolation CVs None Wear - STP M-571-E-1 and NA NA CV Flug & Seat STP M-571-E-2 FE 07 7-F E-01 Maintain Press FEs Nozzle None NA NA NA Bndry Integnty 077-FE-01 B FI 077-F1-01 Maintain Press Brooks instrument Float None NA NA NA Bndry Integrity Model 1305 077-F1-01 C Roat Stops 077-FI-010 Shield 077-Fi-01 F 07 7-F1-02 Maintain Press Brooks instrument Float None NA NA NA Bndry integrity Model 1355 077-F1-02C Float Stops 077-F1-02D Shield 077-FI-02F FL 077-FL-01 Maintain Press Filters Internals None NA NA NA Bndry Integrity 077-FL-01 B HV 077-HV-01 Maintain Press Jamesbury Model Non-Press Bndry None NA NA NA Bndry integrity 21-3600-PP-3, Parts Plant Vent Gases 077-HV-01 D
Component Aging Managomen eview Summary (Revision 1)
Syztem Number: 077/079 Attachment 1 Syttem Name: Area and Process Radiation Monitoring Page 2 of 3 Date: May 21,1996 ;
subcomponents/
Subgroups Not - Managed by - .
Group ~ Possive Intended . Grouping Subject to Aging - Pe=% Enleting MoeBReedens New Pmgram Device ID Functions Attributes Mgt Review 'ARDMs Programs ID . Needed ' Need -
Type 077-HV-02 Cont Isolation Mark 130, None Crevice Corrosion - None NA Yes Containment Body / Stem / Disk / Seat Atmosphere General Corrosion - Age Related Body Degradation Prtting - Inspection Body / Stem / Disk / Seat Program 077-HV-03 Maintain Press Mark 19. Disk & Seat None NA NA NA Bndry Integrity Control Room 077-HV-03E Atmosphere 077-HV-04 Maintain Press Mark 19, None Crevice Corrosion - CP-206 NA Yes Bnory Integrity Cornp Cooling Body / Stem / Disk / Seat and Service General Corrosion - Age Related i Water Body Degradation Pitting - Inspection Body / Stem / Disk / Seat Program MOV 07 7-MOV-01 Maintain Press Marpac Model Ball and Seat None NA NA NA Bndry integrity SS-B325 077-MOV-01 D 077-MOV-02 Maintain Press Circle Seal Model None None NA NA NA Bndry integrity 9562T-4CC PUMP 077-PUMP-01 Pumps in this group are now disposhioned in System 077/079 Pre-evaluation Results and have been removed from Aging Management Review 07 7-PUMP-02 Pumps in this group are now dispositioned in System 077/079 Pre-evaluation Results and have been removeJ from Aging Management Review RE 07 7-RE-01 Maintain Press General Atomic None None i NA NA NA Bndry Integrity Model RD-52-61 07 7-RE-02 Mamtsin Press General Atomic None None NA NA NA Bndry Integrity Model RD-72-01 077-RE-03 Maintain Press General Atomic None None NA NA NA Bndry Integrity Model RD-72-02 RP 077-RP-01 Maintain Press RPs Supporting ? None NA NA NA Bndry Integrity Members 077-RP-01B
__ - - _ - _ a . . - . - . - - . . - - , - ~ - ~ - - - _ _ _ _ _ - . - - - , _ - . _ _ __ - _ _ - - _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ - _
Component Aging Man eview Summary (Revision 1)
Sy tem Number: 077/079 Attachment 1 System Name: Area and Process Radiation Monitoring Page 3 of 3 Date: May 21,1996 Subcomponeritsl :
Subyoups Not - Meneged by 1 Device : Group Passive intended Grouping Subject to Aging N==84 Enleting MedMcedono { New Propam
- Type. Functions Attributes Mgt Review ARDMs Programs D Needed F Nood .:
.ID SV 077-SV-01 Maintain Press SVs Internals None NA NA NA Bndry integrity 077-SV-01D k
RM1. DOC
_.._.._.___m__ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _
O Component Aging Management Review Summary O O D:scription of Programs Which Manage the Effects of Aging (Revision 1) Date: May 21,1996 Sy , tem Number: 077/079 Attachment 2 System Name: Area and Process Radiation Monitoring Page 1 of 1 y l Portions of System Managed Byg , _ .
e y, s y '?% W r -e s s
{^
h
'g' 2 DescriptionofPtegram
~
ProgramIDf SIlds M & Passive (ARDMsManaged QMProgram .
s -
,e MS W
~ ~
s ~ -"
XIntended Function -
Age Related CS pipes and HVs Crevice Corrosion Inspections will be conducted to confirm that the mitigation Degradation - 077-HB-01* General Corrosion programs are effective in preventing or mitigating the aging effects Inspection - 077-HV O2** Pitting which they were designed to control. He scope of such inspections Program would typically be a representative sample of the population of SRW and CC valve internal components of concern. Where practical and prudent, the sample surfaces would be biased to focus on bounding of leading components. If
- 077-HV-04* these inspections reveal little or no degradation, the conclusion could be reached thtt the mitigation programs are sufficient to Maintain Pressure Boundary manage the effects of aging during the period of extended Integrity
- operations. Significant degradation would trigger action under the existing corrective action program and the need for additional Maintain Containment Isolation ** mspections would be evaluated. The inspection techniques would need to be capable of detectmg the effects of Crevice Corrosion, General Corrosion, and Pitting. Acceptance criteria for these mspections would be consistent with current practices which account for the components
- abiliti:s to perform intended functions in accordance with the CLB.
CP-206 SRW and CC valve internal Crevice Corrosion Re chemistry control program provides requirements and criteria surfaces General Corrosion for monitoring system fluid chemical parameters including pH,
- 077-HV-04 Pitting hydrazme concentration, impurity concentrations, dissolved oxygen, and suspended solids. He program provides for appropriate Maintain Pressure Boundary corrective actions if parameters exceed action levels.
Integrity STP M-571E-1 Cont Isolation valve plugs & seats Wear He Imcal Leak Rate Testing of Containment Penetrations as STP M-571E-2 - 077-CV-01 required by 10CFR50 Appendix J provides assurance of seat / disk leak tightness.
Maintain Containment Isolation RM2. DOC
_ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _____ _ ___._________.______._____________.____.._____.____________m
O O O Development of Aging Management Altern;tives (nevision 1) nate: s/21/96 SYSTEM NUMBER- 077 /079 SYSTEM NAME: Area and Process Radiation Monitoring COMPONENT ID: NA GROUP ID: 077-HB-01, 077-HV-02 j
1 2 3-PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGEMENT.-
FROM ALTERNATIVE CHOSEN - !
ATTACHMENT 5 Age Related Degradation Program (new program) 5 The occurrence of crevice corrosion, general corrosion and pitting is Crevice Corrosion General Corrosion expected to be limited and may not affect the intended function of the RMS Pitting components due to the air internal emironment of the components which would result in e minimal amount of moisture. Inspections of representatiw: ,
plant components will provide assurance that significant corrosion is not occurring, or will result in appropriate corrective action if significant corrosion is occurring.
t i
l Attachment 8 Page 1 of 3
n l (d d Development of Aging M:n:gim:nt Altern:tives (Revision 1) Date: s/21/96 077 /079 SYSTEhk NAME: Area and Process Radiation Monitoring SYSTEM NUMBER-COMPONENT ID: NA GROUPID: 077-CV-01 1 2 .3 PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGEMENT FROM ALTERNATIVE CHOSENn A'ITACHMENT 5 Wear Local Leak Rate Testing of Containment Penetrations Wear of the seating surfaces of the containment penetration control nhts in in accordance with the requirements of 10CFR50, the Containment Atmosphere Radiation Monitor System can occur due to App. J. This testing requirement is implemented on valve operation and is managed by periodic leak testing. Leak testing the the Containment Atmosphere Radiation Monitor penetration components per the requirements of 10CFR50, App. J prmides penetration components by STP M-571E-1 and STP assuranceofseat/diskleaktightness. STPM-571E-1(2),"LLRTof M-571E-2," Local Leak Rate Test, Penetrations 15 Penetrations 15,16, . ." performs the App. J Type C leak rate test of the (Purge Air Monitor),16, ..(Unit Heaters)" penetration. This test is performed on a refueling outage fiq&,,cy.
Attachment 8 Page 2 of 3
O O O Development of Aging Management Alternatives (Resision 1) Date: s/21/96 SYSEM NUMBER- 077 / 079 SYSTEM NAME: Area and Process Radiation Monitoring COMPONENTID: NA GROUPID: 077-HV-04 1 2' .3:
PLAUSIBLE ARDM PLANT PROGRAM REASON FOR THE FORM OF AGING MANAGEMENT i
- FROM . ALTERNATIVE CHOSEN ATTACHMENT 5 Crevice Corrosion Chemistry Control and Monitoring for the Senice Corrosion of the Senice Water and Component Cooling Radiation Monitor General Corrosion Water and Component Cooling systems. The isolation valve pressure boundary is plausible due to the senice fluid (water).
Pitting program is implemented by CP-206," Specifications Control of senice fluid chemistry prmides an emironment which mimmazes and Suntillance of Component Cooling /Senice the effects of corrosion. Corrosion is not expected to present a significant Water" challenge to the pressure boundary function of the components due to treated and controlled chemistry internal emironment.
Crevice Corrosion Age Related Degradation Program (new program) The occurrence of cresice corrosion, general corrosion and pitting is GeneralCorrosion expected to be limited and may not affect the intended function of the RMS Pitting components due to the control of Component Cooling and Senice Water chemistry, inspections of representative plant components will prmide assurance that significant corrosion is not occurnng, or will result in appropriate corrective action if significant corrosion is occurring.
Attachment 8 Page 3 of 3
component Agin :nrg ment R:vi:w LCM-16 Revision 4 i
Development of Aging Management AlternatiVOS (Revision 11 Date: 5/21/96 SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring PA/TASKID and PRESENT DESCRIPTION - 'NEW/ REVISED AFFEC1t,J PORTION . CORRECTIVE ACTION /RECOMMENDATIONi Age Related Degradation N/A The ARDI program must provide requirements for identification of representative Inspection (ARDI) Program plant components for inspection based on the results of this aging management review, including the inspection sample size, appropriate sample techniques, and requirements for reporting of results and ccrrective actions. See BGE memorandum LCM-96-044, dated 2-15-% for funher information.
t Attachment 10 Page 1 of 1
i POTENTIAL ARDM LIST (R vi:l:n 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 1 cf 10 Equipment Type: ELEMENT March 27,1996 v ,
l l
I ARDM POTENTIAL DESCRIPTION /JUSTlFICATION SOURCE Cavitation Yes Localized material erosion caused by formation and collapse of [7] ,
i Erosion vapor bubbles in close proximity to material surface. Requires fluid l (liquid) flow and pressure variations which temporarily drop the l liquid pressure below the corresponding vapor pressure. Most t
materials are susceptible to varying degrees depending upon the l severity of the environmental factors.
l Corrosion Yes Plant equipment operating in a corrosive environment subjected to [7] ,
i
! Fatigue cyclic (fatigue) loading may initiate cracks and/or fail sooner than expected based on analysis of the corrosion and fatigue loadings applied separately. Fatigue-crack initiatica and growth usually l follows a transgranular path, although there are some cases l 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 l propagation. Corrosion-fatigue is a potentially active mechanism in both stainless steels as well as carbon and low alloy steels.
i Creep / No Not applicable to Equipment Type. The phenomenon results in [2]
l Shrinkage dimensional changes in metals at high temperatures and in l l concrete subject to long term dehydration. This ARDM is not ~~
l applicable to this equipment type since proper component l I
specification and design prevents this ARDM from occurring (i.e.,
system and component design standards adequately address this l ARDM).
l Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or [6]
Corrosion shielded areas. It is associated with a small volume of stagnant [7]
solution caused by holes, gasket surfaces, lap joints, crevices [12] )
under bolt heads, surface deposits, designed crevices for attaching thermal sleeves to safe-ends, and integral weld backing I 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 corrosion and can initiate pits in many .
cases as well as leading to stress corrosion cracking. In an j oxidizing environment, a crevice can set up a differential aeration l cell to concentrate an acid solution within the crevice. Even in a reducing environment, alternate wetting and drying can j concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.
l O
\
j POTENTIAL ARDM LIST (R:.visi:n 1) l System Number: (077/079) Attachment 7 l System Name: Area & Process Radiation Monitoring Page 2 of 10 l _ Equipment Type: ELEMENT March 27,1996 i
w Erosion Yes increased rate of attack on a metal because of the relative [5]
Corrosion movement between a corrosive fluid and the metal surface. [6]
Mechanical wear or abrasion can be involved, characterized by [7]
l grooves, gullies, waves, holes and valleys on the metal surface. )
I Erosion is a mechanical action of a fluid and/or particulate matter 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 i vulnerable; in particular, piping (bends, tees, etc.), Valves, pumps, l 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 t particle impingement. Erosion corrosion has occurred in high and low pressure preheater tubes, low pressure preheaters, l
I evaporators and feedwater heaters. Inlet tube corrosion occurs in heat exchangers, due to the turbulence of flow from the exchanger l head into the smaller tubes, within the first few inches of the tube.
l Such corrosion has been especially evident in condenser tubes i
and feedwater heaters. The occurrence of erosion corrosion is highly dependent upon material of construction and the fluid flow conditions. Carbon or low alloy steels are particularly susceptible q g when in contact with high velocity water (single or two phase)-with - - - - -- -
! turbulent flow, low oxygen and fluid pH < 9.3. Maximum erosion I l
corrosion rates are expected in carbon steel at 130-140*C (single l phase) and 180*C (two phase).
i i
l F&tigue Yes Fatigue damage results from progressive, localized structural [6]
change in materials subjected to fluctuating stresses and strains. [7]
l Associated failures may occur at either high or low cycles in [2]
response to various kinds of loads (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 l 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 l to experience vibration conditions. In some cases these failures in pipe have been due to inadequately supported pipe or obturator 1 induced vibratory loads.
l
f I
l POTENTIAL ARDM LIST (Revision 1) l System Number: (077/079) Attachment 7 I l System Name: Area & Process Radiation Monitoring Page 3 of 10 I ELEMENT March 27,1996 ImEquipment Type:
C)
Fouling Yes Unavoidable introduction of foreign substances that interact with [9]
! and/or collect within system and components. Caused by failure [10]
l or degradation of upstream removal process equipment, long term [11]
l buildup, low flow, 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 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 j increased corrosion. Sediment deposits promote concentration l 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 l reduced to five years due to under-sediment corrosion.
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 l
conducting solution.
l General Yes Thinning (wastage) of a metal by chemical attack (dissolution) at -
[7]
Corrosion the surface of the metal by an aggressive environment. The [8]
consequences of the damage are loss of load carrying [2]
cross-sectional area. General corrosion requires an aggressive environment and materials susceptible to that environment. An important concem 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 concem for austenitic stainless steel alloys.
l l
POTENTIAL ARDM LIST (R: vision 1)
Sy tem Number: (077/079) Attachment 7
, System Name: Area & Process Radiation Monitoring Page 4 of 10
_ Equipment Type: ELEMENT iviarch 27,1996 Hyc'rogen Yes Two forms of hydrogen attack relevant to light water reactor [6]
l Dimage materials and conditions are hydrogen blistering and hydrogen [7]
I embrittlement. 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 blisturing, molecular hydrogen within the metal causes high pressure and local damage in the form of " blistered" regions of the metal surface. Hydrogen embrittlement affects femtic and martensitic iron-based alloys, and results in low ductility l 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 shorten 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 >120 ksi). Ferritic and martensitic stainless steels, carbon steels, and other hi;h strength alloys are susceptible. Austenitic stainless steels are relatively immune but could erperience damage at sufficiently high hydrogen levels.
Int:rgranular Yes Intergranutar Attack (IGA) isvery similar to intergranular stress - [6]
Attack corrosion cracking (IGSCC) except that stress is not required for [7]
IGA. IGA is localized corrosion at or adjacent to grain boundaries, [2]
with relatively little corrosion of the material grains. It is caused by [12]
impurities in the grain houndaries, 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 l 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. 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 environrrents at high temperatures (by forming low melting sulfur compounds at grain boundaries) or when austenitic stainless steel weto filler metalis inadvertently used on Ni-Cr-Fe alloys. Susceptibility to intergranular attack (sensitization) usually develops dunng thermal processing such as v elding or heat treatments.
Irradiation No Not applicable to Equipment Type. The ARDM results in a [6]
Embrittlement decrease in steel fracture toughness due to long-term exposure to [7]
a fast flux of neutrons. This ARDM is not applicable to this equipment type since element components in the systems under evaluation are not located in areas where the neutron flux is high enough to cause this ARDM to occur.
l
~
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 l Sy: tem Name: Area & Process Radiation Monitoring Page 6 of 10 l
_ Equipment Type: ELEMENT March 27,1996 l
I l MlC Yes Accelerated corrosion of materials resulting from surface [6]
microbiological activity. Sulfate reducing bacteria, sulfur oxidizers, [7]
and Iron oxidizing bacteria are most commonly associated with [2]
l corrosion effects. Most often results in pitting followed by excessive deposition of corrosion products. Stagnant or low flow areas are most susceptible. Any system that uses untreated water, c-is buried, is particularly susceptible. Consequences range ft;m 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 alllarge industries is 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 [7]
chemical reaction at the surface of a material when subjected to [12]
I an oxidizing environment. Oxidation occurs at any temperature.
Electrical components experience degradation related to oxidation and are considered separately. Oxidation genera!!y 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 .
I 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 temperatures do not occur in power plant applications under evaluation. Therefore, oxidation is l not considered a potential ARDM for element components.
Perticulate Yes The loss of material caused by mechanical abrasion due to [7]
relative motion between solution and material surface. Requires Wear Erosion high velocity fluid, 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.
I 1
l
POTENTIAL ARDM LIST (Revisi:n 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 6 of 10 gEquipment Type: ELEMENT March 27,1996 V
Pitting Yes A form of localized attack with greater corrosion rates at some [6]
locations than at others. Pitting can be very insidious and [7]
destructive, with sudden failures in high pressure applications [2]
(especially in tubes) occurring by perforation. This form of [12]
corrosion essentially produces " holes" of 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 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 as chlorides and sulfates tend to concentrate in the oxygen- depleted pit region, i 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 become passive in
{
some metals such as aluminum.
Radiation Yes Non-metallics are susceptible to degradation caused by gamma [4]
Damage radiation.
Rubber Yes Rubber can be used in specific applications of this device type. [3]
l Degradation Long term exposure of rubber to water will result in water absorption and swelling, blistering, hardening, and eventual cracking. When utilized as a protective lining, moisture permeation of the rubber produces blisters beneath the lining and initiates corrosion of the lined surface.
l Saline Water No Not applicable to Equipment Type. Saline Water Attack has [2]
Attack resulted in the degradation of reinforced concrete structures. The i degradation mechanism involves water seepage into the concrete l
resulting in a high chloride environment for the reinforcing bars.
l The reinforcing bars corrode resulting in expansion that leads to i
cracking and spalling of the concrete. 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 element components since elements are not constructed of nor typically installed in concrete.
O 1
POTENTIAL ARDM LIST (R: vision 1)
System Number: (077/079) Attachment 7 Sy: tem Name: Area & Process Radiation Monitoring Page 7 of 10 l
_ Equipment Type: ELEMENT March 27,1996 1 l
Selective Yes The removal of one element from a solid alloy by corrosion [12]
Leaching processes. The most common example is the selective removal of [13]
zinc in brass 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 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. l Environmental conditions include high temperature, stagnant aqueous solution, and porous inorganic scale. Acidic solutions and oxygen aggravate the mechanism.
Str;ss Yes Selective corrosive attack along or across material grain [6]
C:rrosion boundaries. Four particular mechanisms are known to exist: (1) [7]
Cracking Intergranular (IGSCC), between the material grain boundaries. (2) [2]
Transgranular (TGl.,CC), across the material grains along certain [12]
crystallographic planes. (3) Irradiation Assisted (IASCC), between [13]
the material grains after an incubation neutron dose which sensitizes the material. (4) Interdendritic (IDSCC), between the l{
g 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 I and/or ionic species (e.g., Chlorides / sulfates).
)
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POTENTIAL ARDM LIST (R2 vision 1)
System Number: (077/079) Attachment 7 ;
System Name: Area & Process Radiation Monitoring Page 8 of10 Mquipment Type: ELEMENT - March 27,1996 Stress Yes Common sources of residual stress include thermal processing Corrosion (Cont'd) and stress risem created during surface finishing, fabrication, or Cracking assembly. The leat input during welding can result in a localized (Continued) sensitized regio,1 which is susceptible to SCC. IGSCC is a concem l in stainless steel piping depending on material conaition and process fluid chemistry and also is a potential concem in valve intemals (PH steel). SCC of low alloy steel and carbon steel is not considered a credible aging mechanism for typical conditions
. encountered in a nuclear power plant. TGSCC may be a concem 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 l may operate. lASCC is a potential concem only for reactor vessel intemals 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 material.
l IDSCC is a potential concem 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 j g 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 tu6es and where morpholine, l
which breaks down into ammonia, is used to increase the pH of l the condensate.
Stress Yes Stress Relaxation occprs under conditions of constant strain [7]
l R11axation where part of the elastic strain is replaced with plastic strain. A i materialloaood to an initial stress may experience a reduction in i 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 [7]
Dimage temperature limits. [2]
Thermal Yes Loss of material fracture toughness caused by tnermally induced [7]
Embrittlement changes 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 of impurities.
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NTIAL ARDM LIST (R;visi:n 1)
Sy: tem Number: (077/079) Attachment 7 I System Name: Area & Process Radiation Monitoring Page 9 of 10
_ Equipment Type: ELEMENT March 27,1996 Wear Yes Wear results from relative motion between two surfaces (adhesive [1]
wear), from the influence of herd, abrasive particles (abrasive wear - see 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 l 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 wom 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 q g corrosion. 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 j initiated at stresses well below the endurance limit of nonfretted specimens.
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POTENTIAL ARDM LIST (R: vision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 10 of 10
_ Equipment Type: ELEMENT March 27,1996 Attachment 7 Reference List i
Source Title
[1] ASME Wear Control Handbook, Peterson and Winer,1980
[2] Standard Format and Content of TechnicalInformation 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 Report No. NP-3944,1985
[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No. NP-5461,1987
[7] Environmental Effects on Components: Commentary for ASME Section lil, 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 1 and 2, June 1989 and October 1992
,,,_s[10) Aging Assessment of Instrument Air Systems, NUREG/CR-5419, January 1990
{'j11] 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 l
l Winwons Fde RM7ELEM DOC a
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f- COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: ELEMENT Page 1 of 1 Device Type: FE March 29,1996 Group ID: 077-FE-01 l
Device Type: Flow Element Vendor: General Atomics Model Number: 03679060-014 Materia!: Stainless Steel Internal Environment: Air External Environment: Air Function (s): Maintain System Pressure Boundary Integrity Name Plate Data:
l List of Grouped Components:
1FE5415A 1RE Low Range Sample Flow f3 d
1FE5415B 2FE5415A 1RE High Range Sample Flow 2RE Low Range Sample Flow 2FE5415B 2RE High Range Sample Flow 1
I l
l WinWbrd File RM3FE01. DOC l
- O
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revisio21)
SYSTEM NUMBER- 077/079 SYSTEM NAME: Area & Process Radiation GROUP ID: 077-FE-01 Date: March 27,1996 EQUIPMENTID: NA
. Seblect te l
- Sub-Group ID Sub-Component /Name - . Manufacturer . . Material : : Model Number.'. Passive Intended Function (s).; "AMR1
' (Replacement Pge) z (Source) - (Soutre) . (Source) ' (Soaree) - T (Y er N) --
077-FE-01 A Tebe Assembly General Atomics Stainless Steel 03679060-014 Maintain system pressure boundary Y (None) OTM 12284-010 OTM 12284-010 OTM 12284-010 (CLSR)
Section 6, p.24 Section 6,p.24 Section 6, p.24 Appendix, pp.118- Appendix, pp.II8- Appendix, pp.I18-141) 141) 141) 077-FE-01B Nozzle General Atomics Stainless Steel 93679060-014 None (Provide flour to element) N (None) OTM 12284-010 GTM 12284-010 OTM 12284-010 (CLSR)
Section 6,p.24 Section 6, p.24 Section 6, p.24 Appendix, pp.118- Appendix, pp.118- Appendix, pp.118-141) 141) 141) 077-FE-OlC Transducer General Atomics Stainless Steel 03679060-814 Maintain system pressure boundary Y (None) OTM 12284-010 GTM 12284-010 GTM 12284-010 (CLSR)
Section 6, p.24 Section 6, p.24 Section 6,p.24 .
Aprendix, pp.118- Appendix, pp.II8-Appendix, ppf I8-141) 141) 141) t Page 1of1
ARDM MATRIX (Revision 1)
System: Aren & Process Radiation Monitoring (077/079) Attachment 5 I Equipment Type: ELEMENT Page1 of1 '
Device Type: FE March 29,1996 l Group ID: 077-FE-01 l
ARDM 077-FE- 077-FE-OlA OIC l Tube Transducer Assembly Cavitation Erosion 02 02 Corrosion Fatigue 12 12 Crevice Corrosion 06 06 Erosion Corrosion 21 21 Fatigue 12 12 Fouling 15 15 Galvanic Corrosion 07 07 General Corrosion 01.3 01.3 Hydrogen Damage 03 03 Intergranular Attack 22 22 MIC 15 15 Particulate Wear 17 17 Erosion Pitting 06 06 p lladiation Damage 01.3
() Rubber Degradation 01.3 01.3 - 01.3 l
Selective Leaching 01.3 01.3 Stress 18 18 Corrosion Cracking Stress Relaxation 04 04 l
Thermal Damage 01.3 01.3 Thermal 04 04 j Embrittlement I Wear 16 16 I
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Compon:nt Aging Man:gtm nt Rsvisw LCM-16 Revision 4 Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: FE EQUIPMENT TYPE: ELEMENT GROUP ID: 077-FE-01 Date: 4/11/96 I
,TCODEI .
I. DESC. R. IPT. ION !.: !![
.800R CE.!
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 I
CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM-
)
01.3 STAINLESS STEEL I l I
! '02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 I THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ;
ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 ;
HYDROGEN DAMAGE REQUIRES SURFACE CORROSION ,
WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN
. THAT ENTERS THE GRAIN STRUCTURE.0F THE METAL. .THE . . ._. _. . ,
PROCESS FLUlD DOES NOT CREATE THE REQUIRED CORROSION SITES.
1 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 l ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 l
ENSURE THIS ARDM IS NOT PLAUSIBLE. ES-024 l 06. PROCESS FLUID CHEMISTRY AND MOISTURE DO NOT ATTACll 7 l PERPETUATE THE ARDM. INPO OPERATIONS AND O/l-35 ,
MAINTENANCE REMINDER O&MR-132 DESCRIBES INPO OPERATIONAL FAILURES OF RAD MONITORING SYSTEMS O&MR-132 j' DUE TO EXCESS MOISTURE. CCNPP RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO l THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504).
l HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT !
EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF l MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE W AGING MECHANISMS. l t
I
! Attachment 6 j Page 1 of 3
l 4
i i ComponInt Aging Mrnagsmsnt Rsvisw LCM-16 )
l Revision 4 I
! )
, lCODEh $ DESCRIPTION $ . (SOURCE i 4
07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 )
NOT PERPETUATE THE ARDM. THE ELEMENT IS MADE OF O/l-35 :
MATERIALS WITH LOW POTENTIAL DIFFERENCES AND THE j ONLY MOISTURE RESULTS FROM A LIMITED AMOUNT OF i CONDENSATION.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 !
PERPETUATE THE ARDM. THE SYSTEM MAINTAINS A 12284-010 l RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES I MAKING THIS ARDM NOT PLAUSIBLE. I 15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY- FROM THE VENT GASES, MICROBES AND AIRBORNE PARTICLES. PLANT EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS i SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE i TO LIMITED AMOUNT OF CONDENSATION.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE NOT IN RELATIVE MOTION AGAINST O rHER SUB-COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738SH.2 THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE .
CONDITIONING SKID PREVENT SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. l THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT ,
HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS FROM A LIMITED AMOUNT OF CONDENSATION.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
O Attachment 6 Page 2 of 3
Compon:nt Aging Manag:m:nt Revi:w LCM-16 Revision 4
- CODE.l ' DESCRIPTION 1 SOURCE 22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT PLAUSlBLE SINCE THE ONLY MOISTURE RESULTS FROM A LIMITED AMOUNT OF CONDENSATION.
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l Attachment 6 Page 3 of 3 1
l
I COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation E titoring (077/079) Attachment 3 i Equipment Type: ELEMENT Page 1 of 1 Device Type: RE May 15,1996 Group ID: 077-RE-01 Device Type: Radiation Element Vendor: General Atomics Model Number: RD-52-61 Material: SS Internal Environment: Air External Environment: Air Function (s): Maintain System Pressure Boundary Integrity Name Plate Data:
1 List of Grouped Components: I
'OV 1RE5416 RE Wide Rang,e Effluent _ Radiation, Monitor, __
l 2RE5416 RE Wide Range Effluentiladiation Monitor WinWord Fue RM3RE01 DOC
)
ATTACHMENT ,SUBCOMPONENT/SUB-GROUPIDENTIFICA110N(Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME Area & Process Radiation Monitoring GROUPID: 077-RE 101 Date: May 15,1996 EQUIPMENTID: NA Subject to (
Sul> Group ID Sub-Component'Name 1 Manufacturer i Material : . Model Number i Passive Intended Function (s) - i AMR h .
. (Replacement Pge) -- : (Source) - (Source) - (Source) l (Source)% i (YorN) /
General Atomics 304 SS RD-5241 Maintain systesa pressure boundary Y 077-RE-OlA Sample Chamber (None) OTM 12284410) OTM 12284410 (VTM 12284410 "CLSR)
Appendix p.6) pp.1-15,6-47)
Cover General Atomics 304 SS RD-5241 Maintale system pressere boundary Y i 077-RE-OlB 4
(None) OTM 12284410) OTM 12184-010 OTM 12284-010 (CIER)
Appendix p.6) pp.1-15,6-47)
Photomultiplier Tube General Atomics SS RD-5241 Maintain system pressure boundary Y 077-RE-01C (None) OTM 12284410) 'OTM 12284410 OTM 12284-010 (CIER)
Appendix p.6) pp.1-15,6-47)
Inlet / Outlet Tube General Atomics SS RD-5241 Maintain system pressure boundary Y 077-RE-01D (None) OTM 12284-010) OTM 12284-010 GTM 12284410 (CISR)
Appendix p.6) pp.1-15,6-47)
SealScrews General Atomics SS ' RD-5241 Maintain system pressere boundary Y 077-RE-01E (None) OTM 12284-010) (VTM 12284-010 OTM 12284-010 (CIER)
- p. 6-5 & L.CM pp.1-15,6-47)
File S-96-Ot9) 077-RE-OlF Flange Screws General Atomics GAlloy/SS - RD-5241 Maintain system pressure boundary Y (None) OTM 12284-010) (None) OTM 12284-010 (CLSR) pp.1-15,6-47)
Page1ofI
ARDM MATRIX (Revision 1)
, System: Ares & Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: ELEMENT Page 1 of1 Device Type: RE May 15,1996
- Group ID: 077-RE-01 ARDM 077-RE- 077.RE- 077-RE- 077-RE- 077-RE- 077-RE-OlA OlB OIC OID ole OlF -
Sample Cover PM Tube Inlet / outlet Seal Screws Flange Chamber Tube Screws Cavitation Erosion 02 02 02 02 02 19 i Corrosion Fatigue 12 12 12 12 12 12 l Crevice Corrosion 06 06 06 06 % 19 Erosion Corrosion 21 21 21 21 21 19 Fatigue 12 12 12 12 12 12 Fouling 15 15 15 15 15 19 Galvanic Corrosion 07 07 07 07 07 07 General Corrosion 01.3 01.3 01.3 01.3 01.3 19 l Hydrogen Damage 03 03 03 03 03 03 Intergranular Attack 22 22 22 22 22 22 MIC 15 15 15 15 15 19 Particulate Wear 17 17 17 17 17 19 I Erosion Pitting 06 06 06 06 06 19 Radiation Damage 01.3 01.3 01.3 01.3 01.3 . 01.2 ,
Rubber Degradation 01.3 01.3 01.3 - 01.3 01.3 01.2 Selective Leaching 01.3 01.3 01.3 01.3 01.3 01.2 Stress 18 18 18 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 04 04 04 Thermal Damage 01.3 01.3 01.3 01.3 01.3 01.2 i Thermal 04 04 04 04 04 04 l Embrittlement j' Wear 16 i 16 16 16 16 16 l
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Compon:nt Aging ManagsmInt R::visw LCM-16 Revision 4 Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION l' MONITORING DEVICE TYPE: RE EQUIPMENT TYPE: ELEMENT GROUP ID: 077-RE-01 Date: 5/15/96 l
f DESCRIPTIONi :
~
ICODEM $SOORDEi$ ;
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
, 01.2 CARBON STEEL / ALLOY / STAINLESS STEEL l 01.3 STAINLESS STEEL i 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 '
l THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY l ASSOCIATED WITH THIS ARDM. l I
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 p
d HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 WHICH CREATES A SOURCE OF MONO-ATOMIC liYDROGEN__ _ _FONTANA. _
THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE ' 60738 SH2 l PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 l I
CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE.
l MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW ,
j YlELD STRENGTHS OF TYPICAL 300 SERIES STAINLESS STEELS AND TYPICAL STEEL BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
L l
Attachment 6 l Page 1 of 4 l
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Compon;nt Aging Man:g:m:nt R;vi:;w LCM-16 Revision 4
/~'T b CODE DESCRIPTION ' SOURCE -
06 PROCESG FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. THE ELEMENT PRESSURE O/l-35 BOUNDARY PARTS ARE MADE OF MATERIALS WITH LOW 12284-010 POTENTIAL DIFFERENCES. THE FLANGE SCREWS ES-014 (UNSPECIFIED MATERIAL) ARE NOT SEPARATED FROM THE 304 SS SAMPLE CHAMBER, BUT GALVANIC CORROSION
~'S (V WILL BE MINIMAL DUE TO LACK OF AN ELECTROLYTE (THE ONLY MOISTURE RESULTS FROM A LIMITED-AMOUNT OF CONDENSATION). THE SCREWS EXPOSED TO AN EXTERNAL AIR ENVIRONMENT ONLY AND ARE NOT EXPOSED TO PROCESS AIR.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 i PERPETUATE THE ARDM. THE SYSTEM MAINTAINS 12284-010 RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES ES-014 i I
MAKING THIS ARDM NOT PLAUSIBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 '
FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/1-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 GASES, MICROBEG AND AIRBORNE PARTICLES. PLANT MO 2199402189 EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT l BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE l TO LIMITED AMOUNT OF CONDENSATION WHICH IS REMOVED BY FILTRATION.
b i Attachment 6 Page 2 of 4
1 Compon:nt Aging Mantgtmtnt Rsview LCM-16 i Revision 4 CODE' IDESCRIPTIONs 1 <
(SOURCEy 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE 12284-010 NOT IN RELATIVE MOTION AGAINST OTHER SUB-COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, 60738SH.2 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH.7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 12284-010 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT 60738 SH.2 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF AVNER WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS FONTANA 60722 SH1 O INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN CONCENIRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN ASM NP-5461 TYPICAL 300 SERIES STAINLESS STEELS. THE LOW YlELD STRENGTHS OF TYPICAL 300 SERIES SS AND TYPICAL STEEL BOLTING MATERIALS MAKE THE MATERIALS LESS SUSCEPTIBLE TO THE ARDM, 19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 i ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT ES-014 l EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ,
ARDM NON-PLAUSIBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
O Attachment 6 Page 3 of 4
Compon:nt Aging Mantg::m:nt R:visw LCM-16 ;
Revision 4 l
O . CODE DESCRIPTIONi ? SOURCE-22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 PLAUSlBLE SINCE THE ONLY MOISTURE RESULTS FROM A 60738 SH.2 '
LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS VOL-13 REMOVED BY FILTRATION, AND THE AIR ENVIRONMENT IS AVNER NOT THE AGGRESSIVE ENVIRONMENT NECESSARY FOR THE FONTANA ARDM. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 60722 SH1 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ;
ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN TYPICAL 300 SERIES STAINLESS STEELS AND TYPICAL STEEL BOLTING MATERIALS.
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Attachment 6 I
Page 4 of 4
e COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: ELEMENT Page 1 of 1 Device Type: RE May 13,1996 Group ID: 077-RE-02 l
Device Type: Radiation Element Vendor: General Atomics Model Number: RD-72-01 304 SS, Steel, Anodized Aluminum, Cadmium-Plated Steel i Material:
internal Environment: Air Ext:~.at Environment: Air Furistion(s): Maintain System Pressure Boundary Integrity Name Plate Data:
List of Grouped Components: l
.1RE5417 RE Wide Range Effluent Radiation Monitor ,
2RE5417 RE Wide Range Effluent. Radiation Monitor l
WinWord Fde RM3RE02 DOC
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ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revi= ion I) l i
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring GROUP ID: 077-RE-02 Date: May 15,1996 EQUIPMENTID: NA i
Su W to SulM;roup lD Sul<omponent/Name Manufacturer . Material Model Number Passive latended Function (s) . ?AMR' (Replacement Pge) - (Source) ~ ' (Source) (Source) ' ~ (Source) -
(Y er N) '
077-RE-02A Chamber llousing General Atomics 304 SS RD-72-01 Maintain system pressere boundary Y (None) OTM 12284-010) (LCM File S OTM 12284-010 (CLSR) 009) { pp.6-62,6-25) 077-RE-02B Tubing Chamber General Atomics 304 SS RD-72-01 Maintain system pressure boundary Y (None) OTM 12284-010) (LCM File S OTM 12284410 (CLSR) 009) pp.6-62,6-25)
Tubing General Atomics 304 SS RD-7241 Malatain system pressure boundary Y 077-RE-02C f I
(None) OTM 12284-010) '(LCM File S (Vill 12284410 (CLSR) 009) i pp.6-62,6-25) 077-RE-02D Detector End Cover Screws General Atomics Cadmium-PlatN RD-7241 Maintain system pressure boundary Y Steel !
1
'None) OTM 12284-010) OTM 12284410 GTM 12284410 (CLSR)
- p. 6-62D) I pp.6-62,6-25) 077-RE-02E Tubing Chamber Screws General Atomics Steel ' RD-7241 Maintain system pressure boundary Y I
(None) OTM 12284410) OTM 12284410 GTM 12284-010 (CLSR)
- p. 6-62D) pp.6-62,6-25) 077-RE-02F Detector Cover General Atomies 304 SS RD-72-01 Maletnin structuralintegrity Y (None) OTM 12284-010) (LCM File S OTM 12284-010 (CLSR) 009) pp.6-62,6-25) 077-RE-02G End Cover General Atomics Anodized RD-7241 Maintain structuralintegrity Y Aluminum (None) OTM 12284-010) OTM 12284-010 GTM 12284410 (CLSR)
- p. 6-42A) pp.6-62,6-25)
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ARDM MATRIX (Revision 1)
System: Ares & Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: ELEMENT Page1 of1 Device Type: RE May 15,1996 Group ID: 077-RE-02 l
l ARDM 077.RE- 077-RE- 077-RE- 077 RE- 077-RE- 077-RE. 077-RE- 1 02A 02B 02C 02D 02E 02F 020 l Chamber Tubing Tubing Detector Tubing Detector End Cover l Ilousing Chamber End Cover Chamber Cover 1 Screws Screws Cavitation Erosion 02 02 02 19 19 19 19 l Corrosion Fatigue 12 12 12 12 12 12 12 Crevice Corrosion 06 06 06 19 19 19 19 I
Erosion Corrosion 21 21 21 19 19 19 19 Fatigue 12 12 12 12 12 12 12 Foulirig 15 15 15 19 19 19 19 Galvanic Corrosion 07 07 07 07 07 07 07 General Corrosion 01.3 01.3 01.3 01.1 19 01.3 01.4 Hydrogen Damage 03 03 03 19 19 19 19 Intergranular Attack 22 22 22 22 22 22 22 MIC 15 15 15 19 19 19 19 Particulate Wear 17 17 17 19 19 19 19 i
Erosion Pitting 06 06 06 19 19 19 19 Radiation Damage 01.3 01.3 01.3 01.1 01.1 01.3 01.4 Rubber Degradation 01.3 01.3 01.3 01.1 01.1 01.3 01.4 Selective Leaching 01.3 01.3 01.3 01.1 01.1 01.3 19 Stress 18 18 18 18 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 04 04 04 04 Thermal Damage 01.3 01.3 01.3 01.1 01.1 01.3 01.4 Thermal 04 04 04 04 04 04 04 Embrittlement
\Vear 16 16 16 16 16 16 16 i
\
WinWord File RMSRE02 DOC l
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Componrnt Aging Mtnrgsmant Rsview LCM-16 Revision 4 O M tri C o Li *<a i i '>
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: RE EQUIPMENT TYPE: ELEMENT GROUP ID: 077 RE-02 Date: 5/15/96 CODE .l L DESCRIPTIONj iSOURCE[
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.1 STEEL 01.3 STAINLESS STEEL 01.4 ALUMINUM O2 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 O HYDROGEN DAMAGE REQUIRES SURFACE CORROSION WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN VOL-13 FONTANA THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE 60738 SH2 PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 12284-010 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF TYPICAL 300 SERIES STAINLESS STEELS AND TYPICAL STEEL BOLTING MATERIAL IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING. THE LOW YlELD STRENGTH OF ALUMINUM USED IN THE END COVER LESSENS ITS SUSCEPTIBILITY TO HYDROGEN CRACKING. SINCE BLISTERING OF ALUMINUM TYPICALLY OCCURS ONLY DURING MELTING OR HEAT TREATMENT (MANUFACTURING), ANOMOLIES WOULD BE DISCOVERED EARLIER IN COMPONENT LIFE DURING TUBE DISASSEMBLY.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 O ^aou oeea^Ti"o Te=eea^Tuaes 'ess Tsa" soo e ENSU9E THIS ARDM IS NOT PLAUSIBLE.
es-o' 4 I
Attachment 6 l Page 1 of 4 I I
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1 Componsnt Aging Manzgtmrnt Rsvisw LCM-16 l Revision 4 CODEY >
z DESCRIPTION 0 4SOURCEj 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE l SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED
( PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION l l
l lS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED l AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT ;
FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION AND ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THE ARDM. ELEMENT PRESSURE BOUNDARY IS O/l-35 OF UNIFORM MATERIAL OF CONSTRUCTION. THE 12284-010 ANODIZED ALUMINUM END COVER IS NOT SEPARATED ES-014 l
FROM THE CADMlUM-PLATED STEEL SCREWS AND THE 304 LCM S-96-009
- SS DETECTOR COVER, AND THE 304 SS CHAMBER AND UHLIG l.'
TUBING HOUSINGS ARE NOT. SEPARATED.FROM STEEL _
l SCREWS, BUT GALVANIC CORROSION WILT:BE MINIMAL ,
l DUE TO LACK OF AN ELECTROLYTE (THE ONLY MOISTURE l RESULTS FROM A LIMITED AMOUNT OF CONDENSATION). l l 12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 i PERPETUATE THE ARDM. THE SYSTEM MAINTAINS 12284-010 l l RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES ES-014 ;
! MAKING THIS ARDM NOT PLAUSIBLE.
~
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 l GASES, MICROBES AND AIRBORNE PARTICLES. PLANT MO 2199402189 :
EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS !
SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE I l
PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT )
BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION WHICH IS REMOVED BY FILTRATION.
l l 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7
! THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE 12284-010
!O
[
"oT is ae'^Tive uoTio" ^o^i"ST oTsea sue.
COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
Attachment 6 Page 2 of 4
Comoontnt Aging Mtnagsmint Rsvisw LCM-16 Revision 4 iCODEI ? DESCRIPTIONI ?SOURCEi 17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY lS SUFFICIENT TO CARRY PARTICLES, 60738SH.2 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 12284-010 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT 60738 SH.2 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION WHICH IS AVNER REMOVED BY FILTRATION. FLOW FROM SYSTEMS INTO Tt IE FONTANA PLANT VENT IS NOT EXPECTED TO CONTAIN 60722 SH1 CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS ASM WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 304 NP-5461 SERIES STAINLESS STEEL TUBING AND CHAMBERS. THE ES-014 LOW YlELD STRENGTH OF 304 SS MAKES IT LESS SUSCEPTIBLE TO THE ARDM. THE PARTS NOT EXPOSED TO O. PROCESS AIR ARE EXPOSED ONLY TO AN AIR _
ENVIRONMENT WHICH IS NOT CONDUCIVE TO THIS ARDM.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT ES-014 EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSlBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 .
NOT PERPETUATE THE ARDM.
O Attachment 6 Page 3 of 4
Compontnt Aging Managtment Rsvisw LCM-16
. Revision 4
- CODE' . DESCRIPTION! : SOURCE-22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A 60738 SH.2
, LIMITED AMOUNT OF CONDENSATION WHICH IS REMOVED VOL-13 BY FILTRATION, AND THE AIR ENVIRONMENT IS NOT THE AVNER AGGRESSIVE ENVIRONMENT NECESSARY FOR THE ARDM. FONTANA !
FLOW FROM SYSTEMS INTO THE PLANT VENT IS NOT 60722 SH1 EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ES-014 ARDM TO BE PLAUSIBLE IN TYPICAL 300 SERIES STAINLESS STEELS. THE PARTS NOT EXPOSED TO PROCESS AIR ARE EXPOSED ONLY TO AN AIR ENVIRONMENT WHICH IS NOT l
CONDUCIVE TO THIS ARDM.
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Attachment 6 Page 4 of 4
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1) lO l System: Area & Process Radiation Monitoring (077/079) Attachment 3 l Equipment Type: ELEMENT Page 1 of 1 ;
l Device Type: RE May 13,1996 j
! Group ID: 077-RE-03 Device Type: Radiation Element Vendor: General Atomics Model Number: RD-72-02 Material: 304 SS, Stainless Steel, Fiberglass internal Environment: Air !
External Environment: Air Function (s): Maintain System Pressure Boundary Integrity Name Plate Data:
l l
l List of Grouped Components:
1 1RE5418 _
RE Wide Range Effluent Radiation Monitor 2RE5418 RE Wide Range Effluent Radiation Monitor f
r WnWord Fde RM3RE03 DOC
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O O O NITACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision I)
SYSTEM NUMBER- 077/079 SYSTEM NAME Area & Process Radiation Monitoring EQUIPMENTID: NA GROUPID: 077-RE Date: May 15,1996 i
M OD [
! Sub-Group ID . SeK - , -:Wamet ~: M aserneturer ; Material j-- . Modet Nember . Paulve latended Ftimetime(s) .. . AMR f
~
.. (Replacement Pge) (Source) i (Source) (Source) -
(Searte)i .' (Y er N)[
l
! 077 RE43A Chamber General Atomics 364 SS RD-72-82 Maintale system pressere i " , Y (None) OTM 12284410) (LCM File S-E (LCM File S-96-409, (CIER) 009) \TM 12284419 p.6-25) 077-RE438 Tobing General Atomics 384 SS RD-7242 Maletale system pressure boundary Y i
(None) OTM 12284419) (LCM File S-E (LCM File S-96-009, (CLSR)
. 009) VTM II284410 I p.6-25) 977-RE43C Cover General Atomics . 304 SS RD-72-82 Maletale structuralintegrity Y l
(None) OTM 12284410) (LCM File S (LCM File S-96409, (CLSR) 009) . , VTM 12284410 p.6-25) 077-RE43D Spacers General Atomics Fiberglass . RD-72-02 Malmente structuralintegrity Y (None) (VTM 12284410) (LCM File S-% (LCM File S-96-409, (CLSR) 009) VTM 12284410 p.6-25)
~
977-RE43E Bolts General Atomics - SS/ Alley /CS RD-7242 Meistate syntesa pressere boundary Y (Nome; OTM 12284410) (None) (LCM File S-96-009, (CESR)
\TM 12284414 p.6-25) h a
m Page1of1
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i ARDM MATRIX (Revision 1) :
System: Area & Process Radiation Monitoring (077/079) Attachment 5 - l Equipment Type: ELEMENT PageI ofI Device Type: RE May 15,1996 I
Group ID: 077-RE-03 l
l ARDM 077-RE- 077-RE- 077-RE- 077-RE- 077-RE-L 03A 03B 03C 03D 03E l Chamber TubinC Cover Spacers Ibits Cavitation Erosion 02 02 02 02 19 Corrosion Fatigue 12 12 12 01.5 12 Crevice Corrosion 06 06 06 01.5 19
(. Erosion Corrosion 21 21 21 19 19
[ Fatigue 12 12 12 12 12 Fouling 15 15 15 19 19 Galvanic Corrosion 07 07 07 01.5 07 -
General Corrosion 01.3 01.3 01.3 01.5 19 Hydrogen Damage 03 03 03 01.5 19 Intergranular Attack 22 22 22 01.5 19 MIC 15 15 15 19 19 l Particulate Wear 17 17 17 19 19 l Erosion Pitting 06 06 06 01.5 '
19 Radiation Damage 01.3 01.3 01.3 20 01.1 V Rubber Degradation 01.3 01.3 01.3 01.5 01.1 Selective Leaching 01.3 01.3 013 01.5 01.1 Stress 18 18 18 01.5 19 Corrosion Cracking Stress Relaxation 04 04 04 04 04 Thermal Damage 01.3 01.3 01.3 04 01.1 Thermal 04 04 04 04 04 Embrittlement Wear 16 16 16 16 16 Wrmord Fue RM5RE03 Doc
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l l Compon:nt Aging Managsment Revisw LCM-16
( Revision 4 l
~
Matrix Code List (Revision il i
SYSTEM NUMBER: .077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING l
DEVICE TYPE: RE EQUIPMENT TYPE: ELEMENT GROUP ID: 077-RE-03 Date: 5/15/96
~
iCODE[ [ DESCRIPTION 3 l SOOR'CE:;
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.1 STEEL l 01.3- STAINLESS STEEL f
01.5 FIBERGLASS l 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 I THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY
- ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 O- HYDROGEN DAMAGE. REQUIRES SURFACE _ CORROSION - __ _ ._VOL .13 . . _
WHICH CREATES A SOURCE OF MGNO-ATOMIC HYDROGEN FONTANA l THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE 60738 SH2 l PROCESS FLUID DOES NOT CREATF THE REQUIRED 60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER GASES. ' FLOW FROM SYSTEMS INTO THE PLANT VENT IS LCM S-96-OO9 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF 12284-010 ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ASM ARDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW I YlELD STRENGTH OF TYPICAL 300 SERIES STAINLESS I
STEELS AND TYPICAL STEEL BOLTING MATERIAL IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE. MAXIMUM DESIGN 12284-010
- OPERATING TEMPERATURE OF 130 F FOR THE WIDE RANGE GAS MONITORS ENSURES THE FIBERGLASS SPACERS ARE j
NOT EXPOSED TO HIGH TEMPERATURES.
iO Attachment G Page 1 of 4
Componznt Aging Man::gsmant Rsvisw LCM-16 Revision 4 CODEF i DESCRIPTION i: ' SOURCE' i 06 ~
PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132
- MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK i VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM l ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE l SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED I l PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION AND ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THE ARDM. ELEMENT PRESSURE BOUNDARY IS O/l-35 OF UNIFORM MATERIAL OF CONSTRUCTION. THE BOLTS LCM S-96-OO9 (UNSPECIFIED MATERIAL) ARE NOT SEPARATED FROM THE ES-014 304 SS COVER AND CHAMBER, BUT GALVANIC CORROSION 12284-010 l
WILL BE MINIMAL DUE TO LACK OF AN ELECTROLYTE AS THE BOLTS ARE NOT EXPOSED TO PROCESS FLUID AND THE l
EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE. SYSTEM MAINTAINS A LCM S-96-OO9 RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES ES-014 i MAKING THIS ARDM NOT PLAUSIBLE. 12284-010 15 ARDMS DO NOT SIGNIFICANTLY AFFEQT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT LCM S-96-OO9 GASES, MICROBES AND AIRBORNE PARTICLES. PLANT MO 2199402189 EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS 12284-010 SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS REMOVED BY FILTRATION, 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE LCM S-96-OO9 NOT IN RELATIVE MOTION AGAINST OTHER SUB- 12284-010
- COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
l Attachment 6 Page 2 of 4
l l
Compontnt Aging Manag: ment Rsvisw LCM-16 Revision 4 CODEi ' DESCRIPTIONi iSOURCE7 17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, 60738SH.2 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS FILTRATION OF AIR ON THE SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANr EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. LCM S-96-009 THIS ARDM IS NOT PLAUStBLE SINCE THE SYSTEM IS NOT 12284-010 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS 60738 SH.2 FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF VOL-13 WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS AVNER ;
INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN FONTANA j CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS 60722 SH1 l WHICH WOULD CAUSE THE ARDM TO BE PLAUStBLE IN 304 ASM SERIES STAINLESS STEELS. THE LOW YlELD STRENGTil OF NP-5461 THIS MATERIAL MAKES IT LESS SUSCEPTIBLE TO THE ARDM.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT ES-014 EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSIBLE. THE EXTERNAL ENVIRONMENT IS ;
NOT NORMALLY HARSH. I I
O Attachment 6 Page 3 of 4
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Compon:nt Aging Man:g:m:nt Rsvisw LCM-16 l Revision 4 l
CODE- J DESCRIPTION L ISOURCE4 20 MATERIAL, PROCESS FLUID (PLANT VENT GASES),- AND ATTACH 7 ENVIRONMENT DO NOT PERPETUATE ARDM. HIGH RANGE LCM S-96-OO9 DETECTORS ARE DESIGNED FOR RADIATION HARDNESS OF O/l-48 1.0E7 RADS AND ARE DESIGNED TO OPERATE DURING AND 12284-010 AFTER AN EVENT. BY DESIGN, THE HIGH RANGE DETECTOR ES-014 l WOULD OPERATE ONLY DURING AND AFTER AN EVENT l WHEN RADIATION CONCENTRATIONS REACH 4000 pCi/cc.
FIBERGLASS SPACERS TYPICALLY ARE NOT EXPOSED TO RADIATION LEVELS IN PLANT VENT GASES WHICH APPROACH THE RAD HARDNESS THRESHOLD. THE I DETECTORS ARE ENCASED IN A 6-INCH THICK LEAD SHIELD i WHICH PROTECTS EXTERNALLY AGAINST HIGH j ENVIRONMENTAL RADIATION LEVELS, BUT THE LOCA DOSE RATE FOR ROOMS 524 AND 526 IS 1.54E2 RADS, WELL BELOW THE RAD HARDNESS THRESHOLD FOR THE DETECTOR. THE INTERNAL CHECKSOURCE DOES NOT PERPETUATE THE ARDM AS IT IS NORMALLY NOT ALIGNED WITH THE RE, AND IS THEREFORE SHIELDED BY THE LEAD CASING.
- 21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM. ,---
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT LCM S-96-009 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A' 60738 SH.2 !
LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS VOL-13 )
REMOVED BY FILTRATION, AND THE AIR ENVIRONMENT IS AVNER ;
NOT THE AGGRESSIVE ENVIRONMENT NECESSARY FOR THE FONTANA ARDM. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 60722 SH1 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 304 SERIES STAINLESS STEELS.
- 0 t
Attachment 6 Page 4 of 4
I POTENTIAL ARDM LIST (R:vi:isn 1)
Sy: tem Number: (077/079) Attachment 7 Sy: tem Name: Area & Process Radiation Monitoring Page 1 of 10
_ Equipment Type: INDCTR May 14,1996 l ARDM POTENTIAL DESCRIPTION /JUSTlFICATION SOURCE Cavitation Yes Localized material erosion caused by formation and collapse of [7] !
Erosion vapor 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 j severity of the environmental factors.
Corrosion Yes Plant equipment operating in a corrosive environment subjected to [7]
Fatigue cyclic (fatigue) loading may initiate cracks and/or fail sooner than expected based on analysis of the corrosion and fatigue loadings applied separately. Fatigue-crack Mitiation and growth usually follows a transgranular path, although there are some cases where intergranular cracking has been observed, in some cases, l 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 i threshold, and the fatigue mechanism can accelerate the crack j 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 l l l concrete subjecyo long term _ dehydration. This ARD_M is not .
applicable to this equipment type since proper component ;
specification and design prevents this ARDM from occurring (i.e., i system and component design standards adequately address this ARDM).
l Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or [6]
l Corrosion shielded areas. It is associated with a small volume of stagnant [7]
l solution caused by holes, gasket surfaces, lap joints, crevices [12] l under bolt heads, surface deposits, designed crevices for !
l attaching thermal sleeves to safe-ends, and integral weld backing rings or back-up bars. -The crevice must be wide enough to permit l 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 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 l cell to concentrate an acid solution within the crevice. Even in a l reducing environment, altemate wetting and drying can l concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.
lO
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.. - . - . - - - - - . - - - . - - _ . _ . . - . . . - - - . -- - ~_.
I i
POTENTIAL ARDM LIST (R: vision 1) -
] Sy: tem Number: (077/079) Attachment 7 3 Sy tom Name: Area & Process Radiation Monitoring Page 2 of10
- _ Equipment Type
- INDCTR May 14,1996 4
, Erosion Yes increased rate of attack on a metal because of the relative [5] l j Corrosion movement between a corrosive fluid and the metal surface.
[6]
L Mechanical wear or abrasion can be involved, characterized by [7]
grooves, gullies, waves, holes and valleys on the metal surface.
{ Erosion is a mechanical action of a fluid and/or particulate matter l 4 on a metal surface, without the influence of corrosion. Erosion
!i 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 l j vulnerable; in particular, piping (bends, tees, etc.), Valves, pumps, 4
propellers and impellers, heat exchanger tubing, turt>ine blades l j and wear plates are components which have experienced erosion - )
- corrosion. This is a serious problem in steam piping, heater drain l j piping, reheaters, and moisture separators due to high velocity i
- particle impingement. Erosion corrosion has occurred in high and i
~
low pressure preheater tubes, low pressure preheaters, i 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 th6 tube.
! Such corrosion has been especially evident in condenser tubes and feedwater heaters. The occurrence of erosion corrosion ic j highly dependent upon material of construction and the fluid flow
- q g conditions. Carbon or low alloy steels are particularly susceptible i -
when in contact with high velocity water (single or two phase) with ,
j turbulent flow, low oxygen and fluid pH % 9.3. Maximum erosion corrosion rates are expected in carbon steel at 130-140*C (single i phase) and 180*C (two phase).
Fatigue Yes Fatigue damage results from progressive, localized structural [6]
! change in materials subjected to fluctuating stresses and strains. [7]
l Associated failures may occur at either high or low cycles in (2)
~
response to various kinds of loads (e.g., Mechanical or vibrational
- loads, thermal cycles, or pressure cycles). Fatigue cracks initiate j 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 1
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 e,anditions. In some cases these failures in pipe I. ave been due to inadequately supported pipe or obturator induced vibratory loads.
O
1 POTENTIAL ARDM LIST (Revision 1) '
. System Number: (077/079) Attachment 7 i
System Name: Area & Process Radiation Monitoring Page 3 of10
_ Equipment Type: INDCTR May 14,1996 Fouling Yes Unavoidable introduction of foreign substances that interact with [9] l and/or collect within system and components. Caused by failure [10] i or degradation of upstream removal process equipment, long term [11]
- buildup, low flow, 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 i micro-organisms and their products (microbial fouling) (2) j deposits of macro-organisms such as mussels (macrobial fouling) l 4 (3) inorganic deposits, including scales, silt, corros!on products l and detritus. Scales result when solubility limits for a given species are exceeded. Deposits result when coolant-bome 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 1
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.
Galvanic Yes Accelerated corroslori 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 [7]
Corrosion the surface of the metal by an aggressive environment. The [8]
consequences of the damage are loss ofload carrying [2]
cross-sectional area. General corrosion requires an aggressive environment and mate. rials susceptible to that environment. An important concem 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 1 attack the component from the outside. Wastage is not a concem i for austenitic stainless steel alloys.
4 O
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 4 of 10
_ Equipment Type: INDCTR May 14,1996 Hydrogen Yes Two forms of hydrogen attack relevant to light water reactor [6]
Dimage materials and conditions are hydrogen blistering and hydrogen [7]
embrittlement. 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 whici, 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 rocm 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 shorten 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 >120 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 (lGA) is very similar to intergranular stress -
(6]- --
Attack corrosion cracking (IGSCC) except that stress is not required for [7]
IGA. IGA is localized corrosion at or adjacent to grain boundaries, [2]
with relatively little corrosion of the material grains. It is caused by [12]
impurities in the grain boundaries, or the enrichment or depletion [14]
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. 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. IGA is generally not a concem in atmospheric exposures and is most commonly documented to occur in fluid systems.
Irradiation No Not applicable to Equipment Type. The ARDM results in a [6]
Embrittlement decrease in steel fracture toughness duo to long-term exposure to [7]
a fast flux of neutrons. This ARDM is not applicable to this l I equipment type since indicator components in the systems under
- evaluation are not located in areas where the neutron flux is high enough to cause this ARDM to occur.
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring PageSof10
_ Equipment Type: INDCTR May 14,1996 MIC Yes Accelerated corrosion of materials resulting from surface [6] l microbiological activity. Sulfate reducing bacteria, sulfur oxidizers, [7]
and iron oxidizing bacteria are most commonly associated with [2]
corrosion effects. Most often results in pitting followed by ,
l 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 virtua!!y all large industries is 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 [7]
chemical reaction at the surface of a material when subjected to [12]
an oxidizing environment. Oxidation occurs at any temperature.
Electrical components experience degradation related to oxidation l 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 l q g materials by formation of a passive layer. Other corrosion i mechanisms (e.g. Corrosion fatigue, crevice 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, 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 indicator components.
Particulate Yes The loss of material caused by mechanical abrasion due to [7]
Wear Erosion relative motion between solution and material surface. Requires high velocity fluid, 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.
( 2 Y-l
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 6 of 10
_ Equipment Type: INDCTR May 14,1996 Pitting Yes A form of localized attack with greater corrosion rates at some [6]
locations than at others. Pitting can be very insidious and [7]
destructive, with sudden failures in high pressure applications [2]
(especially in tubes) occurring by perforation. This form of [12] '
corrosion essentially produces " holes" of 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 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 as chlorides and sulfates tend to concentrate in the oxygen- depleted pit region, giving rise to a potentially concentrated aggressive solution in thjs 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 q g pressure vessel closure flanges. Pitting can become passive in some metals such as aluminum.- ~-- - - - - - - - - - -
Rrdiation Yes Non-metallies are susceptible to degradation caused by gamma [4]
D: mage radiation.
Rubber Yes Rubber can be used in specific applications of this device type. [3] ]
Degradation Long term exposure of rubber to water will result in water absorption and swelling, blistering, hardening, and eventual cracking. When utilized as a protective lining, moisture permeation of the rubber produces blisters beneath the lining and initiates corrosion of the lined surface.
! l l S line Water No Not applicable to Equipment Type. Saline Water Attack has [2]
Attack resulted in 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 concrete. Of particular concern for l
structures that are inaccessible for routine inspection, and piping or other fluid components embedded in concrete. This ARDM is 1 l
not applicable to indicator components since indicators are not l
I constructed of nor typically installed in concrete.
l
POTENTIAL ARDM LIST (R;v!sion 1)
System Number: (077/079) Attachment 7 System Name: Ares & Process Radiation Monitoring Page 7 of 10
, Equipment Type: INDCTR May 14,1996 Selective Yes The removal of one element from a solid alloy by corrosion [12]
Leaching processes. The most common example is the selective removal of [13]
zine in brass alloys (dezincification). Similar processes occur in l
other alloy systems in which aluminum, iron, cobalt, chromium, l and other elements are removed. There are two types, layer-type i and plug-type. Layer-type is a uniform attack whereas plug-type is j 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 i the poor strength of the remaining material. Requires susceptible l materials and corrosive environment. Materials particularly j susceptible include zinc, aluminum, carbon and nickel.
l Environmental conditions include high temperature, stagnant '
aqueous solution, and porous inorganic scale. Acidic solutions and oxygen aggravate the mechanism.
l Stress Yes Selective corrosive attack along or across material grain [6]
Corrosion boundaries. Four particular mechanisms are known to exist (1) [7]
Cracking intergranular (IGSCC), between the material grain boundaries. (2) [2]
I Transgranular (TGSCC), across the material grains along certain [12]
crystallographic planes. (3) Irradiation Assisted (IASCC), between [13]
the material grains after an incubation neutron dose which [15]
sensitizes the material. (4) Interdendritic (IDSCC), between the I- -
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).
l 1
t ;
1 I
i O
POTENTIAL ARDM LIST (Revisi:n 1)
System Number: (077/079) Attachment 7 l System Name: Area & Process Radiation Monitoring Page 8 of10
_ Equipment Type: INDCTR May 14,1996 Stress Yes Common sources of residual stress include thermal processing Corrosion (Cont'd) and stress risers created during surface finishing, fabrication, or Cracking assembly. The heat input during welding can result in a localized (Continued) senskized 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 concem in valve internals (PH steet). SCC of low alloy steel and carbon steel is not considered a credible aging mechanism for typical conditions encountered in a nuclear power plant. TGSCC may be a concern in low alloy and stainless steelif aggressive chemical species (caustics, halogens, sulfates, especially if coupled with the presence of oxygen) are present, lASCC 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 material.
IDSCC is a potential concem 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 g is greater than a few ppm. It is found most often in feedwater
{
heaters that contain admiralty brass tubes and where morphotine,
~
which breaks down into ammonia, is used to increase the pH of the condensate.
Stress Yes Stress Relaxation occurs under conditions of constant strain [7]
R laxation where part of 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 [7] i D mage temperature limits. [2]
Thermal Yes Loss of material fracture toughness caused by thermally induced [7]
Embrittlement changes in the formation and distribution of alloying constituents.
Requires high temperature 500*F to 700*F for metallic l components. Ferrite containing stainless steels are susceptible as are materials with grain boundary segregation of impurities.
- O l
l _ _ _
- . - .-. . _-. .._.- - - . . - ._- - ~ .. - .. - - -. . - _ . . -
l r
POTENTIAL ARDM LIST (R:visi:n 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 9 of10
_ Equipment Type: INDCTR May 14,1996 .
l Wear Yes Wear results from relative motion between two surfaces (adhesive [1]
l wear), from the influence of hard, abrasive particles (abrasive wear - see particulate erosion) or fluid stream (erosion), and from small, vibratory or sliding motions under the influence of a corrosive environment (fretting). In addition to mater,ai toss 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 esats, springs against tubes). Wear may proceed at an ever- increasing rate as wom 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 bolted, keyed, pinned, press fit or riveted; in.escillating-bearings, -
coupiings, 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 j
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l . .- .-. .. -- . --. . _ . _ -
l Sy: tem Number: POTENTIAL ARDM LIST (Revision 1)
(077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 10 of 10 Equipment Type: INDCTR
- May 14,1996 1
Attachment 7 Reference List 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] Service (Salt) Water System Life Cycle Management Evaluation, EPRI Report No. TR-102204, April 1993 ,
l
[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 Report No. NP-3944,1985
[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No. NP-5461,1987
[7] Environmental Effects on Components: Commentary for ASME Section lil, EPRI Report l 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 1 and 2, June 1989 and October 1992
[10] Aging Assessment of Instrument Air Systems, NUREG/CR-5419, January 1990 Insights Gained from Aging Research, NUREG/CR-5643, March 1992 G[11](12] Corrosion Engineering, Fontana and Greene,1978 _
[13] Corrosion and Corrosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, Third Edition,1985
[14] ASM Specialty Handbook, Stainless Steels, Davis,1994
[15] A Survey of the Literature on Low-Alloy Steel Fastener Corrosion in PWR Power Plants, !
EPRI-NP-3784,1984 WnnWord Fde RM7WDCT DOC i
I COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
O System: Area & Process Radiation Monitoring (077/079) Attachment 3 l
)
Equipment Type: INDCTR Page 1 of 1 i Device Type: FI May 14,1996 ;
Group ID: 077-FI-01 Device Type: Flow Indicator Vendor: Brooks Instrument Model Number: 1305 Material: Stainless Steel, Aluminum, Borosilicate Glass Internal Environment: Air External Environment: Air Function (s): Maintain System Pressure Boundary integrity Name Plate Data:
List of Grouped Components:
1Fl5415A 1RE Low Range Sample Flow Indicator 2Fl5415A 2RE Low Range Sampia. Flow Indicator l
l i
)
wnward rile RM3F101 DOC O
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision I) <
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-FI-01 Date: May 15,1996 Bobleetle :
Sub-Grvey ID SeMemposent/Neene .Mesafecturer . Meterialf ModelNumber i Fendve latended Footese(s) -'
fAMR
' (Repiecement pge) . (Source) -- (Source) - (Source) c + (Source) . (Oar N) :-
977-FI41A Metering Tube Brooks Instrument Borosilicate Glass 1305 Size 8 Meistole system pressure boundary Y (None) OTM 12284418 OTM 12284-019 OTM 12284-814 (ClJiR)
Section 6 pp. 43-52) Appendix pp. 80- Section 6 pp. 43-52 RI) & Appendin p.84) 077-FI41B End Fittin8s Brooks Instrument 316 Steintess Steel 1305 Sire 8 Meistein system pressere boundary Y (None) OTM 12284418 GTM 12284419 OTM 12284-010 (CLSR)
Section 6 pp. 43-52) Appendin pg.89- Section 6 pp. 43-52 8I & NETD) & Appendis y84) 877-FI-elC Float Brooks Instrument 316 Steinless Steel 1305 Size 8 None (Frevide indienties) N (None) (VDI 12284410 GTM 12284-010, OTM 12284410 (CLSE)
. Section 6 pp.43-52) Appendix pp. 88- Secties 6 pp. 43-52 8I) & Appendis p.84) 977-F14tD Float Stops Brooks Instrument 316 Steinless Steel 1305 Sise 8 Nome (Provide indleetles) N (None) OTM 12284410 GTM 12284414 (VIM 12284410 (CLSR)
Section 6 pp. 43-52) Appendis pp. 80- Sectice 6 pp. 43-52
- 51) & Appeediu p.84) 977-FI-9tE Side Plates Broolts Instrument Amedised 1305 Size 8 Frevide structurallategrity Y Alumiseen (None) (VIM 12284419 OTM 12284410 (VDI 12284410 (CLSR)
Section 6 pp. 43-52) Appendis pp. SS- Section 6 pp. 43-52 SI) & Appendis p.84) 877-FI4t F Shield Brooks Instrument Flestic 1395 Sise 8 None (Provideledicotten) N (None) OTM 12284419 (VTM 12284419 (VTM 12284419 (CLSR)
Sectnes 6 pp. 43-52) Appendix pIk 80- Section 6 pp. 43-52 SI) & Appendis p.84) 077-FI-elG Side Plate Screws Brooks Instrument 8-18 Steiniew Steet 1305 Frevide structend lategrity Y (None) OTW 12284410 (VTM 12284419 OTM 12284410 (CLSR)
Sectice 6 pp.43-52) Appendix pp.SS- Section 6 pp. 43-52 RI) & Appendix p.84)
, Page1ofI
ARDM MATRIX (Revision 1) l ! System: Area & Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: INDCTR Page1 ofI Device Type: FI May 15,1996 Group ID: 077-FI-01 ARDM 077-F1- 077 F1- 077-FI- 077-F1-l OlA OlB ole OlG :
Metering End Side Plates Side Plate l
Tube Fittings Screws Cavitation hrosion 02 02 19 19
)
Corrosion Fatigue 01.5 12 12 12 l
Crevice Corrosion 01.5 06 19 19 :
Erosion Corrosion 21 21 19 19 Fatigue 12 12 12 12 Fouling 15 15 19 19 Galvanic Corrosion 07 07 07 07 General Corrosion 01.5 01.3 01.4 01.3 l Hydrogen Damage 01.5 03 19 19 l Intergranular Attack 01.5 22 22 22 i MIC 15 15 19 19 i Particulate Wear 17 17 19 19 l Erosion Pittmg l q 01.5 06 19 19 Q Radiation Damage Rubber Degradation 20 01.5 01.3 01.3 01.4
- 01.4 01.3 01.3 l
Selective Leaching 01.5 01.3 01.4 01.3 j Stress 01.5 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 04 Thermal Damage 05 01.3 01.4 01.3 Thermal 04 04 04 04 Embrittlement Wear 16 16 16 16 WinWbrd File RM5F101 DOC i
l CompanInt Aging Mantg; ment Rsvisw LCM-16 Revision 4 Matrix Code List (Revision 1) l SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: FI EQUIPMENT TYPE: INDCTR l
GROUP ID: 077-FI-01 Date: 5/15/96
- ' CODE) DESCRIPTION
- SOURCE!
l t 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 l OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS STEEL 01.4 ALUMINUM 01.5 BOROSILICATE GLASS O2 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
> 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMA.GE REQUIRES SURFACE CORROSION VOL-13 i WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN FONTANA THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE 60738 SH2 l
PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 l CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER l GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM i NOT EXPECTED TO CONTAIN CONCENTRATIONS OF l ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE l ASDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STREliGTH OF 316 STAINLESS STEELS IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
l 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSlBLE FOR METALLICS MOFFATT
! AND GLASS. BOROSILICATE GLASS HAS A LOW BRADY l COEFFICIENT OF THERMAL EXPANSION, AS WELL AS HIGH AVALLONE
, TEMPERATURE AND THERMAL SHOCK RESISTANCE CAPABILITIES.
I
- O Attachment 6 Page 1 of 4
r-i l
Compon:nt Aging Mantg: ment R:visw LCM-16 Revision 4 o
Y ' CODE -DESCRIPTION SOURCE 05 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE ARDM. MOFFATT BOROSILICATE GLASS HAS A LOW COEFFICIENT OF BRADY THERMAL EXPANSION, AS WELL AS HIGH TEMPERATURE AVALLONE AND THERMAL SHOCK RESISTANCE CAPABILITIES. ARDM ES-014 IS NOT PLAUStBLE BECAUSE OF LOW PROCESS FLUID AND AMBIENT TEMPERATURES.
06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7
! ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRI6ES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 l
RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS l
lNTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK
! VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO l 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM l ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE l SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED l PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION l lS ASSURED IN ACCORDANCE WITH O/1-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT l q FROM THESE AGING MECHANISMS. .
O 07 MATERIAL SELECTION AND ENVIRONMENT DO NOT ATTACH 7 l PERPETUATE THE ARDM. THE STAINLESS STEEL END O/l-35 f FITTINGS AND SCREWS ARE NOT SEPARATED FROM THE 12284-010 l ANODIZED ALUMINUM SIDE PLATES, BUT GALVANIC ES-014 CORROSION WILL BE MINIMAL DUE TO LACK OF AN ELECTROLYTE (COMPONENT EXTERNAL SURFACES l EXPOSED ONLY TO AIR WITH MAXIMUM DESIGN RELATIVE HUMIDITY OF 90%).
l 12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM MAINTAINS A 12284-010 RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES ES-014
! MAKING THIS ARDM NOT PLAUSIBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 GASES, MICROBES AND AIRBORNE PARTICLES. PLANT MO 2199402189 EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH l]
IS REMOVED BY FILTRATION.
Attachment 6 Page 2 of 4 l
Componsnt Aging Manrg msnt Ravicw LCM-16 Revision 4
! CODES DESCRIPTION / . fSOURCEi 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE 12284-010 l NOT IN RELATIVE MOTION AGAINST OTHER SUB- l COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE. j 17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, 60738SH.2 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES 12284-010 :
WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE l SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 60738 SH.2 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT ES-014 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 i FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF AVNER WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS FONTANA ,
INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN 60722 SH1 O CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSlBLE IN 316 ASM NP-5461 STAINLESS STEELS (SIDE PLATES AND SCREWS EXPOSED 12284-010 ONLY TO NORMAL AMBIENT AIR). THE LOW YlELD STRENGTHS OF THESE MATElllALS MAKE THEM LESS SUSCEPTIBLE TO THE ARDM.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT ES-014 EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ,
ARDM NON-PLAUSlBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
l O i Attachment 6 Page 3 of 4 i
I Componnnt Aging Manzgsmtnt R:visw LCM-16 Revision 4 i
- CODE DESCRIP. TION SOURCE 3 -
I 20 COMPONENT ENVIRC NMENT AND PROCESS FLUID (PLANT ATTACH 7 I VENT GASES) DO NOT PERPETUATE ARDM. THE LOCA ES-014 DOSE RATE FOR ROOM 524 AND 526 IS 1.54E2 RADS. THIS NP-2129 IS WELL BELOW THE THRESHOLD DOSE RATES OF 1.OE4 O/l-48 RADS, WHERE OPTICAL PROPERTIES OF SOME GLASS 12284-010 CHANGES, AND 1.OE6 RADS, WHERE FRAGILITY OF SOME GLASS INCREASES.
BY DESIGN, THE LOW RANGE INDICATOR OPERATES ONLY BEFORE AN EVENT (WHEN RADIATION CONCENTRATIONS IN l PLANT VENT GASES ARE LESS THAN 4000 pCi/cc). THE COMPONENT WAS EVALUATED BY THE VENDOR FOR RADIATION HARDNESS, DURING WHICH METALLICS AND CERAMICS WERE SHOWN TO INCUR UT'LE DAMAGE BELOW 1.OE6 RADS. ALL COMPONENTS WERE SHOWN TO !
OPERATE AT THE SPECIFIED INTEGRATED DOSE OF 5.OE5 I
RADS.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 i AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 60738 SH.2 '
PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A VOL-13 LIMITED AMOUNT OF CONDEN.SATION, MOST OF WHICH IS ES-014 REMOVED BY FILTRATION, AND THE AIR ENVIRONMENT IS AVNER NOT THE AGGRESSIVE ENVIRONMENT NECESSARY FOR THE FONTANA :
ARDM. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 60722 SH1 l NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE 12284-010 .
ARDM TO BE PLAUSlBLE IN 316 STAINLESS STEELS (SIDE PLATES AND SCREWS ARE EXPOSED ONLY TO NORMAL AMBIENT AIR).
1 l
l l
l O Attachment 6 Page 4 of 4
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1) l' O System: Area & Process Radiation Morsitoring (GT7/079) Attachment 3 l Equipment Type: INDCTR Page 1 of1 i Device Type: FI May 14,1996 l Group ID: 077-Fl 02 Device Type: Flow Indicator Vendor: Brooks Instrument Model Number: 1355 Sho-Rate 150 ;
Material: Stainless Stsel, Borosilicate Glass, Aluminum Intomal Environment: Air ;
Extemal Environment: Air j i
Function (s): Maintain System Pressure Boundary Integrity I
Name Plate Data:
l List of Grouped Components:
l 1Fl5415B _
1RE High Range Sample Flow Indic.ator _ _
2F15415B 2RE High Range Sample Flow Indicator l
1 l
i WlnWord Fde RM3FC2 DOC I
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-FI-02 Date: May 15,1996 i .
i Subject to
'Sub.Gromp lD - Sub-Component!Name Manufacturer Meterial . Medet Namber. Passive latended Function (s)1 '
AMR' (Replacement Pge) (Source) - (Source) (Source) (Seeree): 1(Y or N) i 077-F1-02A Metering Tube Brooks Instrument Borosilicate Glau 1355 She-Rate 150 Maintain system pressure boundary Y l
(None) OTM 12284410 GTM 12284-010 GTM 12284410 (CLSR)
Section 6 pp. 43-52) Appendix pp.90- Section 6 pp. 43-52) 91) 077-F142B End Fittings Brooks Instrument 316 Stainless Steel 1355 Sho-Rate 150 Maintain system pressure boundary Y (Noge) OTM 12284-010 OTM 12284fl0 G T M 12284-010 (CLSR)
Section 6 pp. 43-52) p.6-48 & Appendix Section 6 pp. 43-52) pp. 90-91) 077-FI-02C Rost Brooks Instrument 316 Stainless Steel 1355 She-Rate 150 None(Provideindication) N (None) OTM 12284-010 OTM 12284-010 (VTM 12284-010 (CLSR)
Section 6 pp. 43-52) Appendix pp.90- Section 6 pp. 43-52)
- 91) ,
077-F1-02D Host Stops Brooks Instrument Teflon 1355 Sho-Rate 150 None(Provide indication) N (None) OTM 12284410 GTM 12284-010 GTM 12284410 (ClER) l Section 6 pp. 43-52) Appendix pp.90- Section 6 pp. 43-52) 91) 077-F1-02E Side Plates Brooks Instrument Anodized 1355 Sho-Rate 150 Provide structuralintegrity Y Aluminum (None) (VTM 12284-010 OTM 12284-010 OTM 12284-010 (CLSR) s Section 6 pp. 43-52) p.4-7 & Appendix Section 6 pp.43-52) pp. 90-91) 077-FI-02F Shield Brooks Instrument Plastic 1355 Sho-Rate 150 None (Provide indication) N (None) (\TM 12284410 OTM 12284-010 (VTM 12284-010 (CESR)
Section 6 pp. 43-52) Appendix pp.90- Section 6 pp. 43-52) 91) 077-F1-02G Side Plate Screws Brooks Instrument Stainless Steel 1355 Sho-Rate 150 Provide structuralintegrity Y (None) OTM 12284410 OTM 12284-010 (\TM 12284410 (CIER)
Section 6 pp. 43-52) Appendix pp.87- Section 6 pp. 43-52) 88)
- Page1ofI
ARDM MATRIX (Revision 1) l
( System: Area & Process Radiation Monitoring (077/079) Attachment 5 !
Equipment Type: INDCTR Page1of1 Device Type: FI May 15,1996 Group ID- 077-FI-02 ARDM 077-FI- 077-FI- 077-F1- 077-FI-02A 02B 02E 02G Metering End Side Plates Side Plate Tube Fittings Screws Cavitation Erosion 02 02 19 19 Corrosion Fatigue 01.5 12 12 12 )
Crevice Corrosion 01.5 06 19 19 l Erosion Corrosion 21 21 19 19 l Fatigue 12 12 12 12
)
Fouling 15 15 19 19 i Galvanic Corrosion 07 07 07 07 General Corrosion 01.5 01.3 01.4 01.3 Hydrogen Damage 01.5 03 19 19 Intergranular Attack 01.5 22 22 22 MIC 15 15 19 19 Particulate Wear 17 17 19 19 Erosion g Pitting 01.5 06 19 19 ,
._ Radiation Damage 20 01.3 01.4 01.3 ,
- Rubber Degradation 01.5 01.3 - 01.4 01.3 Selective Leaching 01.5 01.3 01.4 01.3 l
Stress 01.5 18 18 18 l Corrosion Cracking l
Stress Relaxation 04 04 04 04 l Thermal Damage 05 01.3 01.4 01.3 l Thermal 04 04 04 04 j Embrittlement Wear 16 16 16 16 I
W Fde RM5F02 DOC
. O t
t
Compon:nt Aging Man:g m:nt R2 view LCM-16 Revision 4 O trix c e 'i * <a i i 'i l SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: FI EQUIPMENT TYPE: INDCTR GROUP ID: 077-FI-02 Date: 5/15/96 CODE DESCRIPTIONI iSOURCE?
! 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7
! OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS STEEL 01.4 ALUMINUM 01.5 BOROSILICATE GLASS O2 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 l THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
I e 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7
- J HYDROGEN DAMA.GE REQUIRES SURFACE CORROSION VOL-13 l 'NHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN FONTANA THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE 60738 SH2 PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 CORROSION SITES. THE PROC.ESS FLUID IS PLANT VENT AVNER GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM NOT EXPECTED TO CONTAIN CONCENTRATIONS OF
- ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE I ARDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF 316 STAINLESS STEELS IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR l HYDROGEN CRACKING. ,
04 PROCESS FLUIT3 TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE FOR METALLICS MOFFATT l AND GLASS. BOROSILICATE GLASS HAS A LOW BRADY l
COEFFICIENT OF THERMAL EXPANSION, AS WELL AS HIGH AVALLONE TEMPERATURE AND THERMAL SHOCK RESISTANCE CAPABILITIES.
O l Attachment 6 Page 1 of 4
ComponInt Aging M:nagtmrnt Rsvi3w LCM-16 Revision 4 1 O
V COD 5 ~ DESCRIPTIONi :SOURCEI 05 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE ARDM. MOFFATT BOROSILICATE GLASS HAS A LOW COEFFICIENT OF BRADY THERMAL EXPANSION, AS WELL AS HIGH TEMPERATURE AVALLONE AND THERMAL SHOCK RESISTANCE CAPABILITIES. ARDM ES-014 IS NOT PLAUSIBLE BECAUSE OF LOW PROCESS FLUID AND AMBIENT TEMPERATURES.
06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING AllGNED TO THE MAIN PLANT VENT (MO 2199407504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINECH THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HA3 NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION AND ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THE ARDM. THE STAINLESS STEEL END O/l-35 FITTINGS AND SCREWS ARE NOT SEPARATED FROM THE 12284-010 ANODIZED ALUMINUM SIDE PLATES, BUT GALVANIC ES-014 CORROSION WILL BE MINIMAL DUE TO LACK OF AN ELECTROLYTE (COMPONENT EXTERNAL SURFACES EXPOSED ONLY TO AIR WITH MAXIMUM DESIGN RELATIVE 1 HUMIDITY OF 90%).
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM MAINTAINS A 12284-010 RELATIVELY LOW STEADY PRESSURE AND TEMPERATURES ES-014 MAKING THIS ARDM NOT PLAUSIBLE.
l 15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 GASES, MICROBES AND AIRBORNE PARTICLES. PLANT MO 2199402189 EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS REMOVED BY FILTRATION.
Attachment 6 Page 2 of 4
Comp:ntnt Aging Manag:m:nt R5vi:w LCM-16
, Revision 4 1 l
LCODE; )bESCRIPTIONf 1 SOURCE: j i 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE ELEMENT PRESSURE BOUNDARY SUBCOMPONENTS ARE 12284-010 NOT IN RELATIVE MOTION AGAINST OTHER SUB-COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 !
AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, 60738SH.2 l HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES 12284-010 '
WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE l SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANT !
EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 60738 SH.2 I
THIS ARDM IS NOT PLAUSlBLE SINCE THE SYSTEM IS NOT VOL-13 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS ES-014 FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF AVNER WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS FONTANA INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN 60722 SH1 O- CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS ASM WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 316 NP-5461 STAINLESS STEELS (SIDE PLATES AND SCREWS EXPOSED 12284-010 ONLY TO NORMAL AMBIENT AIR). THE LOW YlELD STRENGTH OF THIS MATERIAL MAKE IT LESS SUSCEPTIBLE TO THE ARDM.
. 19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT ES-014 EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSIBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
l Attachment 6 Page 3 of 4
i 3
Compon:nt Aging Man:gtmsnt Rsvisw LCM-16 Revision 4 r
I CODE" 1 DESCRIPTION : ; SOURCE 20 COMPONENT ENVIRONMENT AND PROCESS FLUID (PLANT ATTACH 7 VENT GASES) DO NOT PERPETUATE ARDM. THE LOCA ES-014 DOSE RATE FOR ROOMS 524 AND 526 IS 1.54E2 RADS. NP-2129 THIS IS WELL BELOW THE THRESHOLD DOSE RATES OF O/l-48
! 1.0E4 RADS, WHERE OPTICAL PROPERTIES OF SOME GLASS 12284-010 CHANGES, AND 1.0E6 RADS, WHERE FRAGILITY OF SOME GLASS INCREASES.
BY DESIGN, THE MID/HIGH RANGE INDICATOR WOULD l OPERATE ONLY DURING AND AFTER AN EVENT WHEN l RADIATION CONCENTRATIONS IN PLANT VENT GASES l l REACH 4000 pCi/cc. THE COMPONENT WAS EVALUATED BY !
THE VENDOR FOR RADIATION HARDNESS, DURING WHICH METALLICS AND CERAMICS WERE SHOWN TO INCUR LITTLE DAMAGE BELOW 1.0E6 RADS. ALL COMPONENTS WERE SHOWN TO OPERATE AT THE SPECIF!ED INTEGRATED DOSE i OF 5.OE5 RADS. .
l 21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 l NOT PERPETUATE THE ARDM. j l
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE. ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 60738 SH.2 1 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A VOL-13 l LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS ES-014 l
REMOVED BY FILTRATION, AND THE AIR ENVIRONMENT IS AVNER
! NOT THE AGGRESSIVE ENVIRONMENT NECESSARY FOR THE FONTANA l
ARDM. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 60722 SH1 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE 12284-010 l ARDM TO BE PLAUSIBLE IN 316 STAINLESS STEELS (SIDE PLATES AND SCREWS ARE EXPOSED ONLY TO NORMAL AMBIENT AIR).
l i
l O
Attachment 6 Page 4 of 4
,- .- . . . . - - . - - ~ . . - - - -. .
POTENTIAL ARDM LIST (R; vision 1)
Sy; tem Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 1 of10 quipment Type: FILTER May 10,1996 ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE Civitation Yes Localized material erosion caused by formation and collapse of [7]
Erosion vapor 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 [7]
Fatigue cyclic (fatigue) loading may initiate cracks and/or fait 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 steels.
. Creep / No Not applicable to Equipment _ Type. This 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 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 [6]
Corrosion shielded areas. It is associated with a small volume of stagnant [7]
solution caused by holes, gasket surfaces, lap joints, crevices [12]
under bolt heads, 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 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, attemate wetting and drying can concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.
O
POTENTIAL ARDM LIST (R; vision 1) l System Number: (077/079) Attachment 7 i System Name: Area & Process Radiation Monitoring Page 2 of10
_ Equipment Type: FILTER May 10,1996 Erosion Yes increased rate of attack on a metal because of the relative [5]
Corrosion movement between a corrosive fluid and the metal surface. [6]
Mechanical wear or abrasion can be involved, characterized by [7]
grooves, gullies, waves, holes and valleys on the metal surface.
Erosion is a mechanical action of a fluid and/or particulate matter 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 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 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 fluid flow conditions. Carbon or low alloy steels are particularly susceptible l )
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 [6]
change in materials subjected to fluctuating stresses and strains. [7]
Associated failures may occur at either high or low cycles in [2]
response to various kinds of loads (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 materisis 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.
O O
l l POTENTIAL ARDM LIST (R; vision 1) l System Number: (077/079) Attachment 7 !
System Name: Area & Process Radiation Monitoring Page 3 of10
_ Equipment Type: FILTER May 10,1996 l
Fouling Yes Unavoidable introduction of foreign substances that interact with [9] !
and/or collect within system and components. Caused by failure [10]
or degradation of upstream removal process equipment, long term [11]
buildup, low flow, stagnant flow, infrequent operation, and/or i 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 deposits, including scales, silt, corrosion products and detritus. Scales result when solubility limits for a given species are exceeded. Deposits result when coolant-bome particles drop onto surfaces dt.e to hydraulic factors. The deposits result in reduced flow of cocling water, reduced heat transfer, and increased corrosion. 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.
1 Gilvanic 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 q g -
conducting solution,.
I General Yes Thinning (wastage) of a metal by chemical attack (dissolution) at [7]
Corrosion the surface of the metal by an aggressive environment. The [8]
consequences of the damage are loss of load carrying [2]
cross-sectional area. General corrosion requires an aggressive environment and materials susceptible to that environment. An important concem for PWRs is boric acid attack of carbon steels.
Berated 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 concem for austenitic stainless steel alloys.
l
POTENTIAL ARDM LIST (R ; vision 1)
System Number: (077/079) Attachment 7 Area & Process Radiation Monitoring Page 4 of10
_Sy; tem Name:
Equipment Type: FILTER . May 10,1996 Hydrogen Yes Two forms of hydrogen attack relevant to light water reactor [6]
D: mage materials and conditions are hydrogen blistering and hydrogen [7]
embrittlement. 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 j 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 shorten 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 >120 ksi). Ferritic and martensitic stainless steels, cart >on 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 [6]
Attack corrosion cracking (IGSCC) except that stress is not required for [7]
IGA. lGA is localized corrosion at or adjacent to grain boundaries,
[2]
with relatively little corrosion of the material grains. It is e.aused by [12]
impurities in the grain boundaries, or the enrichment or copletion [14)-
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. 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 i
metalis inadvertently used on Ni-Cr-Fe alloys. Susceptibility to l
intergranular attack (sensitization) usually develops during thermal processing such as welding or heat treatments. IGA is generally not a concem in atmospheric exposures and is most commonly documented to occur in fluid systems.
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T(RNsion 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 5 of 10
_ Equipment Type: FILTER May 10,1996 Irradiation No Not applicable to Equipment Type. This ARDM results in a [6]
Embrittlement decrease in steel fracture toughness due to long-term exposure to [7]
a fast flux of neutrons. This ARDM is not applicable to this equipment type since filter 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 [6]
microbiological activity. Sulfate reducing bacteria, sulfur oxidizers, [7]
and iron oxidizing bacteria are most commonly associated with [2]
corrosion effects. Most often 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 l 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 ,
alse wide' spread. MIC is generally observed in service water I appucations utilizing raw untreated water. Sedimentation l aggravates the problem. l Oxidation -
No Not applicable to Equipment Type. The ARDM results from a [7]
chemical reaction at the surface of a msterial when subjected to [12) an oxidizing 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 l mild environments since this mechanism serves to protect l materials by formation of a passive layer. Other corrosion mechanisms (e.g. Corrosion fatigue, crevice corrosion, erosion l 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, where a more rapid reaction between metal and oxygen is likely to occur. These temperatures do not occur in power p! ant applications under evaluation. Therefore, oxidation is not considered a potential ARDM for filter components.
Particulate Yes The loss of material caused by mechanical abrasion due to [7]
Wear Erosion relative motion between solution and material surface. Requires high velocity fluid, entrained particles, turbulent flow regions, flow direction change, and/or impingement. Most mderials are susceptible to varying degrees depending upon the severity of the environmental factors.
POTENTIAL ARDM LIST (R . vision 1)
System Number: (077/079) Attachment 7 Sy; tem Name: Area & Process Radiation Monitoring Page 6 of 10 quipment Type: FILTER May 10,1996 Pitting Yes A form of localized attack with greater corrosion rates at some [6]
locations than at others. Pitting can be very insidious and [7]
destructive, with sudden failures in high pressure applications [2]
(especially in tubes) occurring by perforation. This form of [12]
corrosion essentially produces " holes" of 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 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 l 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 oxygen- depleted pit region, l giving rise to a potentially concentrated aggressive solution in this !
zone. Pitting has been found on the outside diameter of tubes l where sludge or tube scale was present. It can also occur at 1 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 i j ) pressure vessel closure flanges. Pitting can become passive in
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some metals such as aluminum.- ;
Radiation Yes Non-metallics are susceptible to degradation caused by gamma [4]
Dimage radiation.
Rubber Yes Rubber can be used in specific applications of this device td ~ [3]
Degradation Long term exposure of rubber to water will result in water absorption and swelling, blistering, hardening, and eventual cracking. When utilized as a protective lining, moisture permeation of the rubber produces blisters beneath the lining and initiates corrosion of the lined surface.
Silirie Water No Not applicable to Equipment Type. Saline Water Attack has [2]
Attack resulted in 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 concrete. 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 filter components since filters are not constructed of nor typically installed in concrete.
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.- - - - - - .- ..- - -..- . - -. -_ - - - -.. ~ . ~- .
POTENTIAL ARDM LIST (R;visi:n 1)
System Number: (077/079) Attachment 7 l
System Name: Area & Process Radiation Monitoring Page 7 of 10
! 8quipment Type: FILTER May 10,1996 ;
Selective Yes The removal of one element from a solid alloy by corrosion [12]
IAaching processes. The most common example is the selective removal of [13] 7 zinc in brass 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 l and plug-type. Layer-type is a uniform attack whereas plug-type is ,
! extremely localized leading to pitting. Overall dimensions do not l change appreciably, if a piece of equipment is covered by debris ;
l i or surface deposits and/or not inspected closely, sudden unexpected failure may occur in high pressure applications due to l the poor strength of the remaining material. Requires susceptible l
materials and corrosive environment. Materials particularly l susceptible include zinc, aluminum, carbon and nickel. J Environmental conditions include high temperature, stagnant ;
aqueous solution, and porous inorganic scale. Acidic solutions l and oxygen aggravate the mechanism. l Stress Yes Selective corrosive attack along or across material grain [6]
! Corrosion boundaries. Four particular mechanisms are known to exist- (1) [7]
Cracking intergranular (IGSCC), between the material grain boundaries. (2) [2] i Transgranular (TGSCC), across the material grains along certain [12]
crystallographic planes. (3) Irradiation Assisted (IASCC), between [13]
the material grains after an incubation neutron dose which
! { ) -
sensitizes the meterial. (4) Interdendritic (IDSCC), between the -- - -
- dendrite interfaces. SCC requires applied or residual tensile l stress, susceptible materials (such as austenitic stainless steels, i alloy 600, alloy x-750, SAE 4340, and ASTM A289), and oxygen l and/or ionic species (e.g., Chlorides / sulfates).
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l POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 l System Name: Area & Process Radiation Monitoring Page 8 of 10 l Equipment Type: FILTER May 10,1996 Stress Yes Common sources of residual stress include thermal processing Corrosion (Cont'd) and stress risers created during surface finishing, fabrication, or Cracking assembly. The heat input during welding can result in a localized (Continued) sensitized region which is susceptible to SCC. IGSCC is a concem ,
in stainless steel piping depending on material condition and ;
process fluid chemistry and also is a potential concem in valve intemals (PH steel). SCC of low alloy steel and carbon steelis not considered a credible aging mechanism for typical conditions encountered in a nuclear power plant. TGSCC may be a concern in low alloy and stainless steelif aggressive chemical species (caustics, halogens, sulfates, especially if coupled with the presence of oxygen) are present. IASCC is a potential concem .
only for reactor vessel intemals and other stainless steel l 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 material.
IDSCC is a potential concem in stainless steel weld metal deposits based on microstructure and delta ferrite content. This mechanism i
is inactive in carbon and low alloy steel. Ammonia grooving in brass components can occur when the concentration of ammonia l l is greater than a few ppm. It is found most often in feedwater
~
heaters that contain admiralty brass tubes and where morpholine,' I which breaks down into ammonia, is used to increase the pH of the condensate.
Stress Yes Stress Relaxation occurs under conditions of constant strain [7]
Relaxation where part of 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 l packing leakage. i Thermal Yes Non-metallics are particularly susceptible with material dependent [7]
Damage temperature limits. [2] ;
Thermal Yes Loss of material fracture toughness caused by thermally induced [7]
Embrittlement changes 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 of impurities.
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4 POTENTIAL ARDM LIST (R; vision 1)
System Number: (077/079) Attachment 7 I
System Name: Area & Process Radiation Monitoring Page 9 of 10
_ Equipment Type: FILTER May 10,1996 Wear Yes Wear results from relative motion between two surfaces (adhesive [1]
wear), from the influence of hard, abrasive particles (abrasive wear - see 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 vibratory in inert or corrosive environments. The most common result of wear is damage to one or both surfaces involved in the l 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 wom 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 cyc;ic, relative motion of extremely sma!! amplitude. Fretting is frequently accompanied by t
p corrosion. 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 l specimens.
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I WI*I'"II System Number: (077/079) Attachment 7 System Name: Ares & Process Radiation Monitoring Page 10 of10
_ Equipment Type: FILTER May 10,1996 Attachment 7 Reference List Source Title
[1] AGME Wear Control Handbook, Peterson and Winer,1980
[2] Standard Format and Content of Technical Information for Applications fa 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 Report No. NP-3944,1985
[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No. NP-5461,1987
[7] Environmental Effects on Components: Commentary for ASME Section lil, EPRI Report i 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, i Volume 1 and 2 June 1989 and October 1992 p(10] Aging Assessment of Instrument Air Systems, NUREG/CR-5419, January 1990
\j[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
[14] ASM Specialty Handbook, Stainless Steels, Davis,1994 1
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COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 l
)
Equipment Type: FILTER Page 1 of 1 ;
Device Type: FL April 11,1996 i Group ID: 077-FL-01 '
Device Type: Filter j Vendor:
Model Number:
Material: l Intemal Environment:
External Environment:
Function (s): Maintain System Pressure Boundary integrity l Other Parameters: l i
i List of Grouped Components:
1FL5416A WRGM Filter Assembly Low Range
~
! 1FL54168 WRGM Filter Assemblylow Range l 1FL5416G1 WRGM Filter Assembly Low Range 1FL5418C WRGM Filter Assembly Mid/High Range 1FL5418D WRGM Filter Assembly Mid/High Range
! 1FL5418G2 WRGM Filter Assembly Mid/High Range
! 1FL5483 Filter Assembly WRGM Mid/High Range Pump 2FL5416A WRGM Filter Assembly Low Range 2FL5416B WRGM Filter Assembly Low Range
- 2FL5416G1 WRGM Filter Assembly Low Range l
2FL5418C WRGM Filter Assembly Mid/High Range 2FL5418D WRGM Filter Assembly Mid/High Range 2FL5418G2 WRGM Filter Assembly Mid/High Range l Filter Assembly WRGM Mid/High Range Pump 2FL5483 l
l Winword Fde RM3FLD1 DOC l
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ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER- 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-FL-01 Date: AprilI1,1996 7
. ., . .' . Seldect to -
Sub-Group ID - SetKomponent/Name .. . Masefacturer . : Modet Neuber . ~ Material - :' Passiveleeended Feettise(s)i f.AMRx (Replacement Pge) ' -- (Source) : (Searce): (Searce) -- (Searte) ; -
=(YerN)H 077-F1 OlA HOUSING GENERAL P/N 03661121- STAINLESS STEEL MAINTAIN PRESSURE BOUNDARY Y i ATOMIC 001.2,3 INTEGRITY [
(NONE) (12284-010) (LCM Q) (LCM 95-095) (CLSR) 077-FI 01g INTERNALS GENERAL N/A N/A NONE. NO LR INTENDED FUNCTION. N ATOMIC COMPONENT IN LR SCOPE FOR PRESSURE BOUNDARY ONLY.
(N/A) (1228 M 10) (CIER) 6 Y
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I Page1ofI
ARDM MATRIX (Revision 1)
System: Area and Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: FILTER Page1ofI Device Type: FL April 11,1996 l Group ID: 077-fir 01 ARDM 077 FL-01 A Housing Cavitation Erosion 02 Corrosion Fatigue 12 Crevice Corrosion 06 Erosion Corrosion 21 Fatigue 12 Fouling 15 Galvanic Corrosion 07 General Corrosion 01.3 Hydrogen Damage 03 Intergranular Attack 22 MIC 15 j Particulate Wear Erosion 17 i Pitting 06 l
Radiation Damage 01.3 Rubber Degradation 01.3 j
. Selective Leaching 01.3 l O\ -
Stress -
Corrosion Cracking
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18 Stress Relaxation 04 Thermal Damage 01.3 Thermal Embrittlement 04 Wear 16 l
VAnWord File SF5FLO1 DOC v
Componsnt Aging M:nagem:nt Revi:w LCM-16 i Revision 4 l
Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITOR!NG DEVICE TYPE: FL EQUIPMENT TYPE: FILTER GROUP ID: 077-FL-01 Date: 5/10/96 j CODE- ' DESCRIPTION? iSOURCE) ,
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 '
OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY 60738 SH2 ASSOCIATED WITH THIS ARDM. l 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 l WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN FONTANA l THAT ENTERS THE GRAIN STRUCTURE OF THE METAL.. THE. .60738 SH2.
PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER I GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE. j MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF TYPICAL 300 SERIES STAINLESS STEELS IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 l ENSURE THIS ARDM IS NOT PLAUSlBLE.
l lO Attachment 6 Page 1 of 3
l Compontnt Aging Management Review LCM-16 Revision 4 1
!VO
! CODE:
- -- f DESCR.IPTIONY SOURCE-l 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 1 i
ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 l MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 l RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS l lNTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK l
VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM :
ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE l SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE' AGING MECHANISMS.
1 07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. FILTER PRESSURE O/l-35 BOUNDARY IS OF UNIFORM MATERIAL OF CONSTRUCTION LCM 95-095
, AND THE ONLY MOISTURE RESULTS FROM A LIMITED 12284-010 l AMOUNT OF CONDENSATION.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM MAINTAINS A 12284-010 RELATIVELY LOW STEADY PRESSURE, FLOW, AND 60738 SH2 TEMPERATURES MAKING THIS ARDM NOT PLAUSIBLE. ES-014 15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/1-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT GASES, MICROBES AND AIRBORNE PARTICLES. PLANT EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS t SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MtC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE FILTER PRESSURE BOUNDARY SUBCOMPONENTS ARE 12284-010 NOT IN RELATIVE MOTION AGAINST OTHER SUB-COMPONENTS MAKING THIS ARDM NOT PLAUSIBLE.
i lO Attachment 6 Page 2 of 3
i l Compon:nt Aging Managemtnt R5vi:w LCM-16 Revision 4 CODE- ' DESCRIPTION ' SOURCE i
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 l AIR VELOCITY SLOWS INSIDE THE LARGER VOLUME OF THE 60738 SH.2 FILTER HOUSING. THE PROCESS FLUID IS PLANT VENT LCM 95-095 GASES AND IS NOT THE AGGRESSIVE ENVIRONMENT 12284-010 NEEDED TO ERODE THE EROSION RESISTANT STAINLESS 1 STEEL COMPONENTS, MAKING THIS ARDM NOT PLAUSIBLE.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ;
ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES, AND AN APPROPRIATE ENVIRONMENT. 60738 SH.2 THIS ARDM IS NOT PLAUSlBLE SINCE THE SYSTEM IS NOT VOL-13 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS AVNER FROM A LIMITED AMOUNT OF CONDENSATION. FLOW FONTANA FROM SYSTEMS INTO THE PLANT VENT IS NOT EXPECTED 60722 SH1 TO CONTAIN CONCENTRATIONS OF ATMOSPHERIC ASM CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE NP-5461 PLAUSIBLE IN TYPICAL 300 SERIES STAINLESS STEELS. THE l LOW YlELD STRENGTH OF 300 SERIES SS MAKES THE MATERIAL LESS SUSCEPTIBLE TO THE ARDM.
l 21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 l h3 NOT PERPETUATE THE ARDM.
22 ENVIRONMENT DOES NOT PERPETUATE THE ARDM. THIS ATTACH 7 l ARDM REQUIRES A SUSCEPTIBLE MATERIAL AND AN O/l-35 )
l APPROPRIATE ENVIRONMENT.. THIS ARDM IS NOT 60738 SH.2
! PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A VOL-13 LIMITED Als10UNT OF CONDENSATION, AND THE AIR AVNER l ENVIRONMENT IS NOT THE AGGRESSIVE ENVIRONMENT FONTANA
! NECESSARY FOR THE ARDM. FLOW FROM SYSTEMS INTO 60722 SH1 l THE PLANT VENT IS NOT EXPECTED TO CONTAIN ASM CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN l TYPICAL 300 SERIES STAINLESS STEELS.
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Attachment 6 Page 3 of 3
POTENTIAL ARDM LIST (R:visi:n 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 1 of10 Equipment Type: PIPE May 9,1996
/ \
V ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE Cavitation Yes Localized material erosion caused by formation and collapse of [7]
Erosion vapor 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 [7]
Fatigue cyclic (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 steels.
Od Creep /
Shrinkage No Not applicable to Equipm'ent Type. The phenomenon results in dimensional changes in metals at high temperatures and in
[2]
concrete subject to long term dehydration. This ARDM is not applicable to this equipment type since proper piping system design prevents this ARDM from occurring (i.e., piping design standards adequately address this ARDM).
Crevice Yes Crevice corrosion is intense, localized corrosion within crevices or [6]
Corrosion shielded areas. It is associated with a small volume of stagnant [7]
solution caused by holes, gasket surfaces, lap joints, crevices [12]
under bolt heads, 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 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.
l 1
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 l System Name: Area & Process Radiation Monitoring Page 2 of 10 Equipment Type: PIPE May 9,1996 V
Erosion Yes increased rate of attack on a metal because of the relative [5]
Corrosion movement between a corrosive fluid and the metal surface. [6]
Mechanical wear or abrasion can be involved, characterized by [7]
grooves, gullies, waves, holes and valleys on the metal surface.
Erosion is a mechanical action of a fluid and/or particulate matter 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 l under static conditions. All equipment exposed to moving fluids is
! vulnerable; in particular, piping (bends, tees, etc.), Valves, pumps, I
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 l 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 l 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 condenser tubes and feedwater heaters. The occurrence of erosion corrosion is highly dependent upon material of construction and the fluid flow l (3 conditions. Carbon or low alloy steels are particularly susceptible l () 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).
l Fatigue Yes Fatigue damage results from progressive, localized structural [6]
l change in materials subjected to fluctuating stresses and strains. [7]
l Associated failures may occur at either high or low cycles in [2]
response to various kinds of loads (e.g., Mechanical or vibrational ,
j ,
loads, thermal cycles, or pressure cycles). Fatigue cracks initiate l l and propagate in regions of stress concentration that intensify j strain. The fatigue life of a component is a function of several I variables such as stress level, stress state, cyclic wave form, j 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.
I Certain piping locations, such as charging lines, have been found l 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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POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Ares & Process Radiation Monitoring Page 3 of10 Equipment Type: PIPE May 9,1996 Fouling Yes Unavoidable introduction of foreign substances that interact with [9]
and/or collect within system and components. Caused by failure [10]
or degradation of upstream removal process equipment, long term [11]
buildup, low flow, stagnant flow, infrequent operation, and/or i contaminated inlet flow. Fouling refers to all deposds on system i 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 deposits, including scales, silt, corrosion products l and detritus. Scales result when solubility limits for a given species
! are exceeded Deposits result when coolant-borne particles drop l onto surfaces due to hydraulic factors. The deposits result in
! reduced flow of cooling water, reduced heat transfer, and l increased corrosion. Sediment deposits promote concentration
- cell corrosion and growth of sulfur-reducing bacteria. The bacteria j 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.
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 [7]
Corrosion the surface of the metal by an aggressive environment. The [8]
consequences of the damage are loss of load carrying [2]
cross-sectional area. General corrosion requires an aggressive environment and materials susceptible to that environment. An important concem 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 concem for austenitic stainless steel alloys.
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M UST (ReviMon 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 4 of 10 Equipment Type: PIPE May 9,1996 Hydrogen Yes Two forms of hydrogen attack relevant to light water reactor [6]
Damage materials and conditions are hydrogen blistering and hydrogen [7]
embrittlement. 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" 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 shorten 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 >120 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) is very sirnilar to intergranular stress [6]
Attack corrosion cracking (IGSCC) except that stress is not required for [7]
IGA. IGA is localized corrosion at or adjacent to grain boundaries, [2]
with relatively little corrosion of the material grains. It is caused by [12]
impurities in the grain boundaries, or the enrichment or depletion [14]
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. 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. IGA is generally not a concem in atmospheric exposures and is most commonly documented to occur in fluid systems.
)
I i
POTENTIAL ARDM LIST (R; vision 1)
System Number: (077/079) Attachment 7 i
System Name: Area & Process Radiation Monitoring Page5of10 l Equipment Type: PIPE May 9,1996 l $.
w-Irradiation No Not applicable to Equipment Type. The ARDM results in a [6]
Embrittlement decrease in steel fracture toughness due to long-term exposure to [7]
a fast flux of neutrons. This ARDM is not applicable to this equipment type since piping components are not located in areas 1 where the neutron flu is high enough to cause this ARDM to l occur. l MIC Yes Accelerated corrosion of materials resulting from surface [6]
microbiological activity. Sulfate reducing bacteria, sulfur oxidizers, [7] l and iron oxidizing bacteria are most commonly associated with [2]
corrosion effects. Most often 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 applications utilizing raw untreated water. Sedimentation aggravates the problem, fV) Oxidation - No Not applicable to Equipment Type. tie ARDM results from a [7]
chemical reaction at the surface of a mArial when subjected to [12]
an oxidizing environment. Oxidation oc'.;urs 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 I mechanisms (e.g. Corrosion fatigue, crevice corrosion, erosion corrosion, general corrosion and pitting) can result from ,
oxidation / reduction reactions under specific aggressive l 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 i power plant applications under evaluation. Therefore, oxidation is i not considered a potential ARDM for piping.
Particulate Yes The loss of material caused by mechanical abrasion due to [7]
Wear Erosion relative motion between solution and material surface. Requires high velocity fluid, 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.
3
- (V
POTENTIAL ARD3 LIST (R: vision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 6 of10 EquipmentType: PIPE May 9,1996 O
Pitting Yes A form of localized attack with greater corrosion rates at some [6]
locations than at others. Pitting can be very insidious and [7]-
destructive, with sudden failures in high pressure applications [2]
(especially in tubes) occurring by perforation This form of [12]
corrosion essentially produces " holes" of varying depth to diameter ratios in the steel. These pits are, in many cases, filled with oxide debris, especially for femtic 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 oxygen- depleted pit region, giving rise to a potentially concentrated aggressive :,olui'on in this zone. Pitting has been found on the outside d%neter 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 foc service water lines, and at crevices in stainless steel, such as at i.5e stainless steel cladding between reactor O- pressure vessel closue flanges. Pitting can become passive in some metals such as aluminum.-
Radiation Yes Non-metallics are susceptible to degradation caused by gamma [4]
Damage radiation. ;
Rubber Yes Rubber can be used in specific applications of this device type. [3]
Degradation Long term exposure of rubber to water will result in water absorption and swelling, blistering, hardening, and eventual cracking. When utilized as a protective lining, moisture permeation of the rubber produces blisters beneath the lining and initiates corrosion of the lined surface.
Saline Water Yes Saline Water Attack has resulted in the degradation of reinforced [2]
Attack 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. Of particular concern for structures that are inaccessible for routine inspection, and piping or other fluid components embedded in concrete.
O
POTENTIAL ARDM LIST (R vision 1)
System Number:
~
(077/079) Attachment 7 System Name: Area & Pmcess Radiation Monitoring Page 7 of10 Equipment Type: PIPE May 9,1996 Selective Yes The removal of one element from a solid alloy by corrosion [12]
Leaching processes. The most common example is the selective removal of [13]
zinc in brass 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 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 l t
or surface deposits and/or not inspected closely, sudden l unexpected failure may occur in high pressure applications due to i the poor strength of the remaining material. Requires susceptible i 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 i and oxygen aggravate the mechanism.
1 l
l Stress Yes Selective corrosive attack along or across material grain [6]
Corrosion boundaries. Four particular mechanisms are known to exist (1) [7] '
Cracking Ir.iergranular (IGSCC), between the material grain boundaries. (2) [2]
Transgranular (TGSCC), across the material grains along certain [12] ,
crystallographic planes. (3) Irradiation Assisted (IASCC), between [13] l O -
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 specie,s (e.g., Chlorides / sulfates).
1 f . .
!O
I l
l l POTENTIAL ARDM LIST (R:visi:n 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 8 of10 Equipment Type: PlPE May 9,1996 V
Stress Yes Common sources of residual stress include thermal processing Corrosion (Cont'd) and stress risers created during surface finishing, fabrication, or Crackhg assembly. The heat input during welding can result in a localized (Continued) sensitized region which is susceptible to SCC. IGSCC is a concem in stainless steel piping depending on material condition and process fluid chemistry and also is a potential concem in valve intemals (PH steel). SCC of low alloy steel and carbon steel is not considered a credible aging mechanism for typical conditions encountered in a nuclear power plant. TGSCC may be a concem
- in low alloy and stainless steelif aggressive chemical species
! (caustics, halogens, sulfates, especially if coupled with the l presence of oxygen) are present. IASCC is a potential concern I only for reactor vessel intemals and other stainless steel components, such as control rods, which are subject to very high i
neutron fluence levels. A fast neutron incubation fluence of at least 1.0E+20 is generally required to sensitize the material.
IDSCC is a potential concem in stainless steel weld metal deposits l based on microstructure and delta ferrite content. This mechanism Is inactive in carbon and low alloy steel. Ammonia grooving in l
l 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 pH of the condensate.
l Stress Yes Stress Relaxation occurs under conditions of constant strain [7]
Relaxation where part of the elastic strain is replaced with plastic strain. A material loaded to an initial stress may experience a reduction in l stress over time at high temperatures. Bolted connections are l
most vulnerable. Relaxation of stress on packing due to stretching l of gland follower studs under elevated temperatures may cause packing leakage.
, Thermal Yes Non-metallics are particularly susceptible with material dependent [7]
! Damage temperature limits. [2]
Thermal Yes Loss of material fracture toughness caused by thermally induced [7]
Embrittlement changes 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.
t O
(
l POTENTIAL ARDM LIST (R;visi:n 1)
System Number: (077/079) Attachment 7 System Name: Area 2 Process Radiation Monitoring Page 9 of10 Equipment Type: PIPE May 9,1996 V
l Wear Yes Wear results from relative motion between two surfaces (adhesive [1]
l wear), from the influence of hard, abrasive particles (abrasive l wear - see particulate erosion) or fluid stream (erosion), and fmm l
small, vibratory or sliding motions under the influence of a corrosive environment (fretting). In addition to materialloss 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 i 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 I
clamping force (e.g., Tubes in supports, valve stems in seats, springs against tubes). Wear may proceed at an ever-Increasing i rate as wom surfaces moving past one another will often do so l with much higher contact stresses than the surfaces of the original I 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 I corrosion. Common sites for fretting are in joints that are bolted,
(
L 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
- V
m-. _a_A POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 10 of10 Equipment Type: PIPE May 9,1996 ,
O Attachment 7 Reference List 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] 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 Report No. NP-3944,1985
[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI Report No. NP-ti461,1987
[7] Environmental Effects on Components: Commentary for ASME Section Ill, 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 1 and 2, June 1989 and October 1992 f, [10] Aging Assessment of instrument Air Systems, NUREGICR-5419, January 1990 Q [11]
[12]
insights Gained from Aging Resea.rch, . NUREG/CR-5643, March 1992 Corrosion Engineering, Fontana and Greene,1978 -
j
[13] Corrosion and Corrosion Control, An introduction to Corrosion Science and Engineering, Uhlig, Third Edition,1985
[14] ASM Specialty Handbook, Stainless Steels, Davis,1994 l
l l
O %AnWtrd Fde RM7 PIPE DOC
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
O System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: PIPE Page 1 of 1 Device Type: -HB April 12,1996 Group ID: 077-HB-01 Device Type: Pipe Line with Piping Code HB Vendor:
Model Number:
Material:
Intemal Environment: ,
Extemal Environment.
Function (s): Maintain System Pressure Boundary integrity .
Other Parameters: ,
l List of Grouped Components:
1-HB65-CARM5291 Pipe Spool between 1CV5291 & 1CV5292 2-HB65-CARM5291 ' Pipe ~ Spool between 2CV5291 & 2CV5292 -
1
s gg
(/ V ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER- 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUPID: 077-IIB-01 Date: May 10,19%
- Subject to Sub-GrouplD - Sub-Component!Name Manufacturer . : Model_ Number: Material ~
Passive Intended Functiem(s); AMRi (Replacemest Pge) . (Source) .- (Sourec) .' (Source) . (Source) ' (Y or N) 077-IIB-01A PIPE N/A N/A A-106 GR B, SMLS MAINTAIN PRESSURE BOUNDARY Y CARBON STEEL INTEGRITY (NONE) (N/A) (N/A) (92767) (CISR) 077-IIB- 01B FITTINGS N/A N/A FORGED: A-181 MAINTtlN PRESSURE BOLWDARY Y INTEGRTIY (NONE) (N/A) (N/A) (92767) (CESR) 077-IIB-01C WELDS N/A N/A CS WELD MAINTAIN PRESSURE BOUNDARY y MATERIAL INTEGRITY (NONE) (N/A) (N/A) (TYPICAL) (CISR)
Page1 of1
l l
l l
ARDM MATRIX (Revision 1)
O. System:
Equipment Type:
Area and Process Radiation Monitoring (077/079)
PIPE Attachment 5 Page1 of1 Device Type: -H B April 12,1996 Group ID: 077-HB-01 ARDM 077 HB- 077 HB- 077-HB- 1 OlA OlB OIC l Pipe Fittings Welds Cavitation Erosion 02 02 02 l Corrosion Fatigue 12 12 12 Crevice Corrosion A A A Erosion Corrosion 02 02 02 Fatigue 12 12 12 Fouling 06 06 06 ,
Galvanic Corrosion 07 07 07 .
General Corrosion A A A .
l Hydrogen Damage 03 03 03 Intergranular Attack 01.1 01.1 01.1 MIC 06 06 06 Panticulat Wear Erosion 15 15 15 Pitting A A A Radiation Damage 01.1 01.1 01.1
- Rubber Degradation 01.1 01.1 01.1 Saline Water *ttack 18 18 18 Selective Leaching 01.1 01.1 01.1 Sness 01.1 01.1 01.1 Corrosion Cracking Stress Relaxation 04 04 04 Thermal Damage 01.1 01.1 01.1 Thermal Embrittlement 04 04 04 Wear 16 16 16 t
i 4
m m rii.nus.seoi. ooc l
l
Comp::ntnt Aging Mantgsmsnt Rsvi:;w LCM-16 i Revision 4 i
Matrix Code List (Revision 1) l SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION l MONITORING i
DEVICE TYPE: -HB EQUIPMENT TYPE: PIPE l
GROUP ID: 077-HB-01 Date: 5/10/96 CODEj (DESCRIPTION [ <
,. y , 50URdEj l 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 ,
i CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
1 01.1 CARBON STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 l HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-1 l WHICH CREATES A SOURCE OF MONOATOMIC HYDROGEN VOL-13 0 -- Ta^T e Teas Tae.oa^ia sraUcTURe OF THe METAL.1He PROCESS FLUID DOES NOT CREATE THE REQUIRED FONTANA 60738 SH1 CORROSION SITES. THE PROCESS FLUID IS CONTAINMENT l ATMOSPHERE. Ti!5. NORMAL HYDROGEN CONCENTRATION l lS NOT SUFFICIENT TO MAKE THIS ARDM PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF PIPING MILD CARBON STEELS IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
06 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. THE ATTACH 7 FLUID IS AIR WITH THE POTENTIAL FOR SOME HUMIDITY.
HUMIDITY DOES NOT SUBJECT THE COMPONENTS TO THE AGGRESSIVE ENVIRONMENT NORMALLY ASSOCIATED WITH i
THE ARDM.
l l
!O v Attachment 6 Page 1 of 2
Compontnt Aging Mantggmznt Rsvisw LCM-16 Revision 4 l
fCODEI
)DESdRIP'lldlU $800RCEi 07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. MATERIALS USED 92767 THROUGHOUT THE SYSTEM GENERALLY HAVE LOW O/l-35 POTENTIAL DIFFERENCES AND, WHERE APPROPRIATE, ARE LCM-96-133 SEPARATED BY APPROPRIATE TRANSITION MATERIALS. THE COMPONENTS ARE ONLY EXPOSED TO HUMID AIR, WITH NO EXPECTED CONDENSATION.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM MAINTAINS ES-014 RELATIVELY LOW STEADY PRESSURE, FLOW, AND O/l-35 TEMPERATURES MAKING THIS ARDM NOT PLAUSIBLE.
15 ARDM NOT SIGNIFICANTLY AFFECT COMPONENT FUNCTION. ATTACH 7 THE AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, O/l-35 HOWEVER, THE LIMITED SOURCE OF IMPlNGEMENT PARTICLES (CARBON PIPE CORROSION PARTICLES) WILL NOT LEAD TO SIGNIFICANT EROSION OF THE PIPE WALL.
16 WEAR IS NOT A PLAUSIBLE ARDM SINCE THE ATTACH 7 n SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY
,Q RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUSCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NOT RELATIVE MOTION.
18 COMPONENT MATERIAL AND ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THE ARDM: UFSAR FIG.5-10
- 1) COMPONENT IS NOT BURIED IN EARTH, CONCRETE, OR OTHER POROUS MATERIAL SUCH THAT EXTERIOR ENVIRONMENT DOES NOT PERPETUATE THE ARDM.
A THE ARDM IS PLAUSIBLE BECAUSE CARBON STEEL ATTACH 7 MATERIAL OF CONSTRUCTION IS EXPOSED TO POTENTIALLY NP-3784 WARM HUMID AIR. THERE ARE TWO GENERAL POSSIBLE NP-5769 EFFECTS: A UNIFORM CORROSION OF THE INTERNAL NP-5985 SURFACES OF THE PIPE CAUSING WALL THINNING, AND LOCALIZED ATTACK RESULTING IN PITS AND CRACK INITIATION - MOST LIKELY AT LOW POINTS IN THE PIPE AND IN CREVICES BETWEEN SOCKET WELDED FITTINGS AND PIPE.
AGING MANAGEMENT RECOMMENDATIONS:
(1) INCLUDE THE COMPONENTS IN THE AGE RELATED O DEGRADATION INSPECTION PROGRAM.
Attachment 6 Page 2 of 2
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: PIPE Page 1 of 1 Device Type: RP March 13,1996 Group ID: 077-RP 01 Device Type: Radiation Test Point Vendor:
Model Number:
Material: Stainless steel pipe / tube isokinetic nozzle (Ref. 60738 sh 2)
Intemal Environment:
Extemal Environment:
Function (s): Maintain System Pressure Boundary integrity Other Parameters:
List of Grouped Components:
1RP6905 1 HVAC/A Plant Vent Radiation Monitoring RP 2RP6905 .2 HVAC/A Plant Vent Radiation Monitoring RP WhiWord Fue RM3RP01. DOC O
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring GROUPID: 077-RP-01 Date: May 10,1996 EQUIPMENTID: NA ISebject to':c Sat 4roup ID - _- Sub.Compoucat/Name ' s Masefacturer ; Modet Namber5 '. Material . " Passive Intended Function (s) .. . . .': AMR :
(Replacement Pge) : . (Source) ' . (Source); (Soune) , (Source) < . (Y or N) -
077-RP-0IA TUBES GENERAL N/A STAINLESS STEEL MAINTAIN PRESSURE BOUNDARY Y ATOMIC INTEGRITY (NONE) (60738SH0002) (CLSR)
SUPPORTING MEMBERS GENERAL N/A N/A NONE. NO LR INTENDED FUNCTION. N 077-RP-01B ATOMIC COMPONENT IN LR SCOPE FOR PRESSURE BOUNDARY ONLY.
(N/A) (CLSR)
I e
e Page1of1
l l
l l g ARDM MATRIX (Revision 1)
Q System:
Equipment Type:
Area and Process Radiation Monitoring (077/079)
PIPE -
Attachment 5 Page1 of1 Device Type: RP March 13,1996 Group ID: 077-RP-01 l
ARDM 077-RP-OlA Tubes Cavitation Erosion 02
! Corrosion I atigue 12 Crevice Corrosion 06 Erosion Corrosion 21 Fatigue 12 Fouling 15 l Galvanic Corrosion 07 General Corrosion 01.3 i
Hydrogen Damage 03 l Intergranular Attack 22 MIC 15 Particulate Wear Erosion 17 Pitting 06 Radiation Damage 01.3 Rubber Degradation 01.3 l
b Saline Water Attack 19 -
Selective Leaching 01.3 Stress 18 Corrosion Cracking Stress Relaxation 04 Thermal Damage 01.3 Thermal Embrittlement 04 Wear 16 I
l l
l WinWord Fite $F6RP01. DOC iO
Compontnt Aging Managtmtnt Revisw LCM-16 Revision 4 Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: PIPE EQUIPMENT TYPE: PlPE GROUP ID: 077-RP-01 Date: 5/10/96 (CODE 2 lDESCRIPTIONi. : SOURCES 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL ATTACH 7 OF CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS O2 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LlOUlDS NORMALLY ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 WHICH CREATES A SOURCE OF MONOATOMIC HYDROGEN FONTANA THAT ENTERS THE GRAIN STRUCTURE OF THE METAL THE. 6.0738_ SH2. _.
PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF TYPICAL 300 SERIES TUBING ~
STAINLESS STEELS IS BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
I O
Attachment 6 Page 1 of 3
Component Aging Managsmant Rsvisw LCM-16 ,
Revision 4
- CODE: [DESCRIPTIONi a [SOURCEi 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 -
ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 3 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK :
VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED :
PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. MATERIALS USED O/l-35 THROUGHOUT THE SYSTEM GENERALLY HAVE LOW POTENTIAL DIFFERENCES AND, WHERE APPROPRIATE, ARE SEPARATED BY APPROPRIATE TRANSITION MATERIALS.
THIS CONDITION IN CONJUNCTION WITH A GENERAL LACK O OF AN ELECTROLYTE (CONDENSAIlON)IO COMPLETETHE GALVANIC CIRCUlT MAKES THIS ARDM NOT. PLAUSIBLE.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE. SYSTEM SAMPLES PLANT 60722 SH1 VENT GASES AT ATMOSPHERIC PRESSURES AND 60738 SH2 TEMPERATURES, AND MAINTAINS A RELATIVELY LOW STEADY PRESSURE, FLOW, AND TEMPERATURES MAKING THIS ARDM NOT PLAUStBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT MO 2199402189 l GASES, AND AIRBORNE PARTICLES AND MICROBES. PLANT l EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS I SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION.
O .
Attachment 6 Page 2 of 3 i
i I
\
Compon:nt Aging Managtmtnt R5visw LCM-16 Revision 4
-0 ! CODES ,
^
' DESCRIPTIONi ,
p.8OURCE) 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSIBLE ARDM SINCE THE SUB-COMPONENTS ARE DESIGNED TO ELIMINATE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUB-COMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUB-COMPONENTS OR THEY ARE RESTRAINED SUCH THAT I
THERE IS NOT RELATIVE MOTION.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, 60738 SH2 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS.
18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 60722 SH1 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT AVNER HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION. FLOW FONTANA FROM SYSTEMS INTO THE PLANT VENT IS NOT EXPECTED 60738 SH2 !
-O' _ .- TO CONTAlhLCONCENTRATIO.NS OF. ATMOSPHERIC . ASM .j CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN TYPICAL 300 SERIES TUBING STAINLESS STEELS.
19 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 )
ARDM. COMPONENT IS MOUNTED IN THE VENT STACK AND 60722 SH1 NOT BURIED IN EARTH, CONCRETE, OR OTHER POROUS MATERIAL SUCH THAT EXTERIOR ENVIRONMENT DOES NOT PERPETUATE THE ARDM. ,
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 60722 SH1 PLAUSlBLE SINCE THE ONLY MOISTURE RESULTS FROM A AVNER LIMITED AMOUNT OF CONDENSATION. FLOW FROM VOL-13 SYSTEMS INTO THE PLANT VENT IS NOT EXPECTED TO FONTANA CONTAIN CONCENTRATIONS OF ATMOSPHERIC 60738 SH2
) CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE ASM PLAUSlBLE IN TYPICAL 300 SERIES TUBING STAINLESS O STEELS.
Attachment 6 Page 3 of 3
POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 1 of 10 Jquipment Type: VALVE May 15,1996 ARDM POTENTIAL DESCRIPTION / JUSTIFICATION SOURCE Cavitation Yes Localized material erosion caused by formation and collapse of [7]
Erosion vapor 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 [7]
Fatigue cyclic (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 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 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, loca!! zed corrosion within crevices or [6]
Corrosion shielded areas. It is associated with a small volume of stagnant [7]
solutiors caused by holes, gasket surfaces, lap joints, crevices [12]
under bolt heads, 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 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 cari concentrate aggressive ionic species to cause pitting, crevice corrosion, intergranular attack, or stress corrosion cracking.
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1 POTENTIAL ARDM LIST (Revision 1)
System Number: (077 M g Attachment 7 System Name: Area & Process Radiation Monitoring Page 2 of10 "quipment Type: VALVE May 15,1996 Erosion Yes increased rate of attack on a metal because of the relative [5] !
Corrosion movement between a corrosive fluid and the metal surface. [6] l i Mechanical wear or abrasion can be involved, characterized by (7) j grooves, gullies, waves, holes and valleys on the metal surface. ;
Erosion is a mechanical schon of a fluid and/or par 1iculate matter ;
I on a metal surface, without the influence of corrosen. Erosion !
corrosion failures can occur in a relatnrely short time and are l
j sometimes unexpected, since corrosen tests are usually run i under static conditions. All equipment exposed to moving fluids is i vulnerable; in particular, piping (bends, tees, etc.), Valves, pumps, l propellers and impellers, heat exchanger tubing, turbine blades j and wear plates are components which have experienced erosion ;
corrosion. This is a serious problem in steam piping, heater drain l 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 i heat exchangers, due to the turbulence of flow from the exchanger ;
head into the smaller tubes, within the first few inches of the tube. I Such corrosion has been especially evident in condenser tubes i and feedwater heaters. The occurrence of erosion corrosion is i highly dependent upon material of construebon 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 j
i 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).
l Fatigue Yes Fatigue damage results from progressive, localized structural [6]
change in materials subjected to fluctuating stresses and strains. [7]
Associated failures may occur at either high or low cycles in [2]
response to various kinds of loads (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. j Certain piping locations, such as charging lines, have been found i to experience vibration conditions. In some cases these failures in 4 pipe have been due to inadequately supported pipe or obturator induced vibratory loads.
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POTENTIAL ARDM LIST (Revision 1) l System Number: ' (077/079) .
Attachment 7 l ' System Name: Area & Process Radiation Monitoring Page 3 of10
_ Equipment Type: VALVE May 15,1996 Fouting Yes Unavoidable introduction of foreign substances that interact with [9]
and/or collect within system and components. Caused by failure [10]
or degradation of upstream removal process equipment, long term [11]
l buildup, low flow, 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 j micro-organisms and their products (microbial fouling) (2) l deposits of macro-organisms 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 i
reduced flow of cooling water, reduced heat transfer, and increased corrosion. Sediment deposits promote concentration
- cell corrosion and growth of sulfur-reducing bacteria. The bacteria l can cause severe pitting after one month of service. Piping l systems designed for 30 years have had their projected life l reduced to five years due to under-sediment corrosion.
l l Grivanic Yes Accelerated corrosion caused by dissimilar metals in contact in a [12]
! Corrosion conductive solution. Requires two dissimilar metals in physical or electncal contact, developed potential (material dependent), and l l -
conducting solution, _
l Gsneral Yes Thinning (wastage) of a metal by chemical attack (dissolution) at [7]
l Corrosion - the surface of the metal by an aggressive environment. The [8]
l consequences of the damage are loss of load carrying [2]
i cross-sectional area. General corrosion 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 I attack the component from the outside. Wastage is not a concern for austenitic stainless steel alloys.
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POTENTIAL ARDM LIST (R; vision 1)
System Number: (077/079) Attachment 7 i System Name: Area & Process Radiation Monitoring Page 4 of10 pquipmentType: VALVE May 16,1996
^
i- Hydrogen Yes Two forms of hydrogen attack relevant to light water reactor [6]
l D: mage materials and conditions are hydrogen blistering and hydrogen [7] I embrittlement. Both produce mechanical damage in the affected .
component. In each case, atomic hydrogen enters the metal, i i either as a result of a corrosion reaction at the surface or by l l cathodic polarization which results in the evolution of hydrogen l l gas. In blistering, molecular hydrogen within the metal causes high pressure and local damage in the form of " blistered" regions l l of the metal surface. Hydrogen embrittlement affects ferritic and I l 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 tempe ature, after stress is l applied. A certain critical stress, which may take the form of weld l
residual stress, is required to cause cracking. _ Notches concentrate such stresses and tend to shorten the delay time for l 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 >120 l
ksi). Ferritic and martensitic stainless steels, carbon steels, and
- other high strength alloys are susceptible. Austenitic stainless l steels are relatively immune but could experience damage at
.q g sufficiently high hydrogen levels.
Inttrgranular Yes Intergranular Attack (IGA) is very similar to intergranular stren [6]
Attack corrosion cracking (IGSCC) except that stress is not required for [7]
IGA. IGA is localized corrosion at or adjacent to grain boundaries, [2]
with relatively little corrosion of the material grains. It is caused by [12]
impurities in the grain boundaries, or the enrichment or depletion [14) 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 -
I carbides can be formed, thus depleting the grain boundaries of l chromium and decreasing their corrosion resistance. High chromium ferritic stainless steels, such at 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 metalis inadvertently used on Ni-Cr-Fe alloys. Susceptibility to intergranular attack (sensitization) usually develops during thermal processing such as welding or heat treatments. IGA is generally ,
j not a concem in atmospheric exposures and is most commonly l l
documented to occur in fluid systems.
-____m __a -air-- p- a mw I7? Tm T- --pyJM + - Mr T M -
47
l POTENTIAL ARDM LIST (R:visi:n 1) l System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 5 of 10
. Equipment Type: VALVE May 15,1996 l
trradiation No Not applicable to Equipment Type. The ARDM results in a [6]
l Embrittlement decrease in steel fracture toughness due to long-term exposure to [7]
a fast flux of neutrons. 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 materia ls resulting from surface [6]
microbiological activity. Sulfate reducing bacteria, sulfur oxidizers, [7]
and iron oxidizing bacteria are most commonly associated with [2]
corrosion effects. Most often 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 applications utilizing raw untreated water. Sedimentation aggravates the problem. l Oxidation No Not applicable to Equipment Type. The ARDM results from a [7]
Chemical reaction at the surface of a triaterial when subjected to [12] ,
an oxidizing environment. Oxidation occurs at any temperature. l 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 i 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 temperatures do not occur in power plant applications under evaluation. Therefore, oxidation is not considered a potential ARDM for valve components.
Particulate Yes The loss of material caused by mechanical abrasion due to [7]
Wear Erosion relative motion between solution and material surface. Requires high velocity fluid, entrained particles, turbulent flow regions, flow direction change, and/or impingement. Most matenals are susceptible to varying degrees depending upon the severity of the l
envitonmental factors.
L ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 6 of 10
_ Equipment Type: VALVE May 15,1996 Pitting Yes A form of localized attack with greater corrosion rates at some [6]
locations than at others. Pitting can be very insidious and [7]
destructive, with sudden failures in high pressure applications [2]
(especially in tubes) occurring by perforation. This form of [12) corrosion essentially produces " holes" of 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 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 a'1 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 as chlorides and sulfates tend to concentrate in the oxygen- depleted pit region, giving rise to a potentially concentrated aggressive solution in this zone. Pitting has been found on the outside diarmter 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 q , 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 [4]
Damage radiation.
Rubber Yes Rubber can be used in specific applications of this device type. [3]
Degradation Long term exposure of rubber to water will result in water absorption and swelling, blistering, hardening, and eventual cracking. When utilized as a protective lining, moisture permeation of the rubber produces blisters beneath the lining and initiates corrosion of the lined surface.
Saline Water No Not applicable to Equipment Type. Saline Water Attack has [2]
Attack resulted in the degradation of reinforced concrete structures. The ,
degradation mechanism involves water seepage into the concrete l 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. Of particular concern for structures that are inaccessible for routine inspection, and piping or other fluid cornponents embedded in concrete. This ARDM is not applicable to valve components since valves are not constructed of nor typically installed in concrete.
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l POTENTIAL ARDM LIST (R: vision 1)
System Number: (077/079) Attachment 7 I System Name: Area & Process Radiation Monitoring Page 7 of10 l Equipment Type: VALVE May 15,1996 Selective Yes The removal of ono element from a solid alloy by corrosion [12]
Lcaching processes. The most common example is the selective removal of [13]
zine in brass 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 uniform attack whereas plug-type is i
extremely localized leading to pitting. Overall dimensions do not l
change appreciably. If a piece of equipment is covered by debris l or surface deposits and/or not inspected closely, sudden i unexpected failure may occur in high pressure applications due to
( the poor strength of the remaining material. Requires susceptible i materials and corrosive environment. Materials particularly susceptible include zinc, aluminum, carbon and nickel.
Environmental conditions include high temperature, stagnant ;
I aqueous solution, and porous inorganic scale. Acidic solutions and oxygen aggravate the mechanism. j Stress Yes Selective corrosive attack along or across material grain [6]
l Corrosion boundaries. Four particular mechanisms are known to exist: (1) [7]
Cracking Intergranular (IGSCC), between the material grain boundaries. (2) [2]
Transgranular (TGSCC), across the material grains along certain [12]
crystallographic planes. (3) Irradiation Assisted (IASCC), between [13]
the material grains after an incubation neutron dose which
{ -
sensitizes the material. (4) interdendritic (IDSO6), between the dendrite interfaces. SCC requires appli~ed 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).
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POTENTIAL ARDM LIST (R; vision 1)
System Number: (077/079) Attachment 7 l System Name: Area & Process Radiation Monitoring Page 8 of 10 Equipment Type: VALVE May 15,1996 l
l Stress Yes Common sources of residual stress include thermal processing Corrosion (Cont'd) and stress risers created during surface finishing, fabrication, or Cracking assembly. The heat input during welding can result in a localized l (Continued) sensitized region which is susceptible to SCC. IGSCC is a concern l in stainless steel piping depending on material condition and process fluid chemistry and also is a potential concem in valve l internals (PH steel). SCC of low alloy steel and carbon steelis not I
considered a credible aging mechanism for typical conditions encountered in a nuclear power plant. TGSCC may be a concem in low al!oy and stainless steelif aggressive chemical species (caustics, halogens, sulfates, especially if coupled with the presence of oxygen) are present. IASCC is a potential concem l only for reactor vessel intemals and other stainless steel
- components, such as control rods, which are subject to very high l neutron fluence levels. A fast neutron incubation fluence of at least
! 1.0E+20 is generally required to sensitize the material.
1 IDSCC is a potential concern in stainless steel weld metal deposits based on microstructure and delta ferrite content. This mechanism j is inactive in carbon and low alloy steel. Ammonia grooving in l brass components can occur when the concentration of ammonia is greater than a few ppm. It is found most often in feedwater (l
l l
heaters that containWdmiratty brass tubes and where morphol!ne,~
I which breaks down into ammonia, is used to increase the pH of the condensate.
Stress Yes Stress Relaxation occurs under conditions of constant strain [7]
R; laxation where part of 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 l packing leakage.
Thermal Yes Non-metallics are particularly susceptible with material dependent [7]
l Dimage temperature limits. [2]
Thermal Yes Loss of material fracture toughness caused by thermally induced [7]
I Embrittlement changes 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 of impurities.
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l l POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) Attachment 7 System Name: Area & Process Radiation Monitoring Page 9 of 10
, Jquipment Type: VALVE May 15,1996 Wear Yes Wear results from relative motion between two surfaces (adhesive [1]
wear), from the influence of hard, abrasive particles (abrasive wear- see particulate erosion) or fluld stream (erosion), and from l small, vibratory or sliding motions under the influence of a
- corrosive environment (fretting). In addition to materialloss from the ebove wear mechanisms, impeded relative motion between two surfaces held in intimate contact for extended periods may l
result from galling /self-welding. Motions may be linear, circular, or l 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, l springs against tubes). Wear may proceed at an ever-increasing rate as wom 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 f extremely small amplitude. Fretting is frequently accompanied by l corrosion. Common sites for fretting are in joints that are bolted, g g i -
keyed, pinned, press fit or riveted; in oscillating bearings, -
couplings, spindles, and seals; in prest 'its on shafts; and in universaljoints. Under fretting conditions, fatigue cracks may be i initiated at stresses well below the endurance limit of nonfretted l specimens.
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POTENTIAL ARDM LIST (Revision 1)
System Number: (077/079) _
Attachment 7 :
Sy tem Name:. Area & Process Radiation Monitoring Page 10 of10 ^
_ Equipment Type: VALVE- May 15,1996 Attachment 7 Reference List ;
Source Title
[1] ASME Wear Control Handbook, Peterson and Winer,1980 i
[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-l 102204, April 1993 l
' [4] Radiation Effects on Organic Materials in Nuclear Plants, EPRI Report No. NP-2129, t November 1981
[5] Erosion / Corrosion in Nuclear Plant Steam Piping, EPRI Report No. NP-3944,1985 t
[6] Component Life Estimation: LWR Structural Materials Degradation Mechanisms, EPRI .
Report No. NP-5461,1987 l
[7] Environmental Effects on Components: Commentary for ASME Section 111, EPRI Report .
l No. NP-5775, April 1988
[8] Boric Acid Corrosion of Carbon and Low Alloy Steel Pressure Boundary Materials, EPRI l Report No. NP-5985,1988 :
I
[9] Nuclear Plant Service Water System Aging Degradation Assessment, NUREG/CR-5379, l Volume 1 and 2, June 1989 and October 1992 n[10] Aging Assessment of Instrument Air Systems, NUREG/CR-5419, January 1990 insights Gained from Aging Research, NUREG/CR-5643, March _1992 , ,
[12] Corrosion Engineering, Fontana and Greene,1978 l Q((11] _
13] Corrosion and Conosion Control, An Introduction to Corrosion Science and Engineering, Uhlig, Third Edition,1985
[14] ASM Specialty Handbook, Stainless Steels, Davis,1994 4
FNs RM7 VALVE DOC r
-a. a
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: CKV April 15,1996 j Group ID: 077-CKV-01 Device Type: Check \!alve Vendor:
Model Number:
Material:
Internal Environment:
l Extemal Environment:
Function (s): Maintain System Pressure Boundary Integrity Other Parameters:
List of Grouped Components:
1CKVRE-5416P RE Low Range Outlet CKV 1CKVRE-5418P RE Mid-High Outlet CKV_ ~ '
2CKVRE-5416P RE Low Range Outlet CKV 2CKVRE-5418P RE Mid-High Outlet CKV l
i WrWWord Fde RM3CKV01 DOC
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O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-CKV-01 Date: May 16,1996
- Sableet to1 Sub-Group ID SuMomponent/Name Manufacturer Model Nember . . Material: Passive Intended Function (s) ;.
': .iAMR2 (Replacement Pgm) - (Source) ' . (Source) (Source) (Seeece)' 2 (YorN)1 077-CKV-01 A BODY NUPhD SS-4CP2-1/3 316 SS MAINTAIN PRESSURE BOUNDARY Y INTEGRITY (NONE) OTM 12284-310 (VTM 12284-010 GTM 12284-010 (CLSR)
Section 6 pp. 4448) Section 6 pp. 44-48) Appendix pp.94-96, LCM File 95-095) 077-CKV-01B INTERNALS NUPRO SS-4CP2-1/3 316 SS NONE. NO LR INI' ENDED FUNCIlON. N COMPONENT IN LR SCOPE FOR PRESSURE BOUNDARY ONLY.
(N/A) OTM 12284-010 (\TM 12284-010 GTM 12284-010 (CLSR)
Section 6 pp. 44-48) Section 6 pp. 44-48) Appendix pp.94 96)
<e Page1 of1
l I
ARDM MATRIX (Revision 1)
System: Ares & Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: VALVE Page1 ofI Device Type: CKV April 15,1996 !
Group ID: 077-CKV-01 l l
ARDM 077-CKV-01A Body Cavitation Erosion 02 l Corrosion Fatigue 12 Crevice Corrosion 06 Erosion Corrosion 21 i Fatigt.e 12 1 l
Fouling 15 f
Galvatic Corrosion 07 General Corrosion 01.3 Hydrogen Damage 03 Intergranular Attack 22 MIC 15 i Particulate Wear 17 i Erosion
' Pitting 06 s Radiation Damage _ .01.3 . ._._ . _ _ -_. _
Rubber Degradation 013 Selective Leaching 01.3 Stress 18 l I
Corrosion Cracking t
Stress Relaxation 04
! Thermal Damage 01.3 Thermal 04 )
Embrittlement I Wear 16 l
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WinWord Fde RMSCKV01. Doc l
\
Compon:nt Aging Manrg:m:nt R virtw LCM-16 Revision 4
(T Matrix Code List (Revision 1)
(,/
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: CKV EQUIPMENT TYPE: VALVE GROUP ID: 077-CKV-01 Date: 5/16/96 CODE DESCRIPT'l ON ' SOURCE 1
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 (3 WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN FONTANA
, (,) - THAT ErJTERS THE GRAIN STRUCTURE OF THE METAL. THE 60738 SH2 ,_
PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM l NOT EXPECTED TO CONTAIN CONCENTRATIONS OF l ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE.
l MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTH OF 316 STAINLESS STEEL IS BELOW THE THRESHOLD OF 120 KS! TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
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Attachment S Page 1 of 3 i
Componint Aging Managtm:nt Review LCM 16 Revision 4 1
CODEL : D':SCRIPTION'
-SOURCEL l
l 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCF REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 i I
RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION DO NOT PERPETUATE THE ARDM THE ATTACH 7 VALVE IS MADE OF UNIFORM MATERIALS. O/l-35 12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND 12284-010 p TEMPERATUPES ARE LOW AND RELATIVELY STEADY ES-014 V MAKING THIS ARDM NOT PLAUSIBLE. ,,,
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COM' PONENT ATTACH 7 I FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 GASES, MICROBES AND AIRBORNE PARTICLES. PLANT MO 2199402189 EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS l SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE l
PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE l
TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH l lS REMOVED BY FILTRATION.
! 1G NORMAL OPERATIONAL CYCLES DO NOT PERPETUATE THE ATTACH 7 ARDM. ALTHOUGH RELATIVE MOTION EXISTS, WEAR IS NOT 12284-010 A PLAUSlBLE ARDM SINCE THE VALVE DOES NOT NORMALLY O/l-48 OPERATE AT A HIGH CYCLE RATE AND METAL TO METAL FORCES OF VALVE SUBCOMPONENTS ARE LOW, RESULTING i IN INSIGNIFICANT WEAR OF PRESSURE BOUNDARY SUBCOMPONENTS.
Attachment 6 Page 2 of 3
1 l
Compontnt Aging Mrnag:m:nt Rsvi;w LCM-16 Revision 4 l
C) CODE DESCRIPTION : SOURCE-l 17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738 SH.2 ;
THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT l LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE l I
CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 12284-010 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT 60738 SH.2 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 !
FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF AVNER ;
WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS FONTANA )
INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN 60722 SH1 CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS ASM WHICH WOULD CAUSE THE ARDM TO BE PLAUStBLE IN 316 NP-5461 STAINLESS STEEL. THE LOW YlELD STRENGTH OF 316 SG MAKES THE MATERIAL LESS SUSCEPTIBLE TO THE ARDM.
U,m 21 PROCESS FLUID (AIR) AND MATERIAL SELECTj_ON (SS) DO ATTACH 7 l NOT PERPETUATE THE ARDM. -
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES,A SUSCEPTIBLE MATERIAL O/l-35 l AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 PLAUStBLE SINCE THE ONLY MOISTURE RESULTS FROM A 60738 SH.2 LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS VOL-13 REMOVED BY FILTRATION, AND THE AIR ENVIRONMENT IS AVNER NOT THE AGGRESSIVE ENVIRONMENT NECESSARY FOR THE FONTANA ARDM. FLOW FROM SYSTEMS INTO THE PLANT VENT IS 60722 SH1 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 316 STAINI.ESS STEEL.
l
,n.
L)
Attachment 6 l Page 3 of 3 l
l
I COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
O System: Area & Process Radiation Monitoring (077/079) Attachment 3 l
l Equipment Type: VALVE Page 1 of 1 l Device Type: CV April 15,1996 1 Group ID: 077-CV 01 l ,
I Device Type:
Control Valve
! Vendor:
Model Number:
Material:
Internal Environment:
External Environment:
Function (s): Maintain Containment Isolation Other Parameters:
List of Grouped Components:
i 1CV5291 Containment Atmosphere Sample Isolation Valve O' 1CV5292 Containment Atroosphere Sample Isolation Valve 2CV5291 Containment Atmosphere Sample isolation Valve ,
- 2CV5292 Containment Atmosphere Sample isolation Valve I
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O O O ATTACIIMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-CV-01 Date: May 16,1996 Subject to Sel4reep ID SulFCompoacat/Name Manufacturer Model Number Material Passite latended Fametion(s) . AMR (Replacement Pge) (Source) (Sourec) (Source) (Source) (YorN) 077-CV-CI A BODY / BONNET MIASONEILAN 38-20521 STAINLESS STEEL MAINTAIN CONTAINMENT ISOLATION Y INT INC (316)
(NONE) (NUCLEIS/BOMID (NUCLEIS/BOMID (NUCLEIS/BOMID (CLSR) 349) 349) 349) 077-CV-Ol B STEM 3IASONEllAN 38-20521 STAINLESS STEEL MAINTAIN CONTAINMENT ISOLATION Y INT INC - (316)
(NONE) (NUCLEIS/BOMID (N1'CLEIS/BOMID (NUCLEIS/BOMID (CLSli) 349) 349) 349) 077-CV-0IC STUDS / NUTS SIASONEllAN 38-20521 ALLOY STEEL. IIT MAINTAIN CONTAINMENT ISOLATION Y INT INC '
(NONE) (NUCLEIS/BOMID (NUCLEIS/BOMID (NUCLEIS/BOMID (CESR) 349) 349) 349) 077-CV-01D PLUG AND SEAT MASONEllAN 38-20521 STAINLESS STEEL MAINTAIN CONTAINMENT ISOLATION Y INT INC (316)
(NONE) (NUCLEIS/BOMID (NUCLEIS/BOMID (NUCLEIS/BOMID (CISR) 349) 349) 349)
Page1ofI
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ARDM MATRIX (Revision 1)
- System
- Area & Process Radiation Monitoring (077/79) Attachment 5
\ Equipment Type: VALVE Page1ofI Device Type: CV April 15,1996 Group ID: 077-CV-01 ARDM 077-CV- 077-CV- 077-CV- 077-CV-OlA OlB OIC OID l Body / Bonnet Stem Studs / Nuts Plug & Seat Cavitation Erosion 02 02 19 02 Corrosion Fatigue 12 12 12 12 Crevice Corrosion 06 06 06 06 Erosion Corrosion 21 21 19 21 Fatigue 12 12 12 12 Fouling 15 15 19 15 Galvanic Corrosion 07 07 07 07 General Corrosion 01.3 01.3 01.3 01.3 Hydrogen Damage 03 03 03 03 Intergranular Attack 22 22 01.3 22 MIC 15 15 19 15
! Particulate Wear Erosion 17 17 19 17 Pitting 06 06 06 06 .
Radiation Damage 01.3 01.3 01.3 01.3 >
( Rubber Degradation 01.3 01.3 01.3 01.3 j i ( Selective Leaching 01.3 01.3 01.3 01.3 l Stress 18 18 18 18 Corrosion Cracking l Stress Relaxation 04 04 04 04 Thermal Damage 01.3 01.3 01.3 01.3 Thermal Embrittlement 04 04 04 04 Wear 16 20 16 P 1
I WinWord Fde RMSCV0tDOC
Componsnt Aging M:n gsmant Ravisw LCM-16 l Revision 4 l
1 Matrix Code List (Revision 1) j SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING I
DEVICE TYPE: CV' EQUIPMENT TYPE: VALVE GROUP ID: 077-CV-01 Date: 5/10/96 t
CODE DESCRIPTION SOURCE l
l 01 MATERIAL IS NOT APPLICABLE TO THE ARDM MATERIAL OF ATTACH 7 l CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM: ;
i l l 01.3 ALLOY / STAINLESS STEEL 1 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY l ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 l
HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-1 i WHICH CREATES A SOURCE OF MONOATOMIC HYDROGEN VOL-13 ,
l THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE FONTANA PROCESS FLUID DOES NOT CREATE THE REQUIRED ES-014 CORROSION SITES. THE PROCESS FLUID IS CONTAINMENT 60738 SH1 l ATMOSPHERE. THE NORMAL HYDROGEN CONCENTRATION CH-1-100 l
lS NOT SUFFICIENT TO MAKE THIS ARDM PLAUSIBLE. NP-5769 MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW l YlELD STRENGTHS OF 316 STAINLESS STEELS AND TYPICAL BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120
- KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
l I
THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM
, PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED
! BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULI:lDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL l
CONTAINMENT MAXIMUM TEMPERATU'iE OF120 F, NORMAL l AMBIENT TEMPERATURES IN THE EAST SIPING PENETRATION ROCMS OF 140 F, AND DRYING EFFECTS 0.5 WA9MER TEMPERATURES, HYDROGEN DAMAGE DUE TO MC,LY
{ DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 1 of 4
Compon:nt Aging Management Review LCM-16 l Revision 4 CODE DESCRIPTION SOURCE l
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 l ENSURE THIS ARDM IS NOT PLAUSIBLE. I 06 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. THE ATTACH 7 :
l FLUID IS AIR WITH THE POTENTIAL FOR SOME HUMIDITY. O/l-35 l OCCASIONAL HUMIDITY DOES NOT SUBJECT THE LCM 95-112 COMPONENTS TO THE AGGRESSIVE ENVIRONMENT LCM 96-133 NORMALLY ASSOCIATED WITH THE ARDM.
! 07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. THE VALVE IS MADE OF O/l-35 l l MATERIALS WITH LOW POTENTIAL DIFFERENCES AND THE I COMPONENTS ARE ONLY EXPOSED TO OCCASIONAL l HUMIDITY WITH NO EXPECTED CONDENSATION.
l 12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 i i
PERPETUATE THE ARDM. THE SYSTEM PRESSURES, FLOW, ES-014 )
, AND TEMPERATURES ARE LOW AND RELATIVELY STEADY O/l-35 MAKING THIS ARDM NOT PLAUStBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 l FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE WARM
, CONTAINMENT GASES, MICROBES AND AIRBORNE !
PARTICLES. FOULING DOES NOT AFFECT THE PRESSURE l
BOUNDARY FUNCTION. MIC WILL NOT OCCUR AS THE ENVIRONMENT IS ONLY HUMID AIR, WITH NO STANDING l WATER.
I- 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUStBLE ARDM SINCE THE M120-0001 l SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY l RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THAT THEY ARE NOT ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 PART!CULATE WEAR EROSION IS NOT SIGNIFICANT. THE ATTACH 7 AIR VELOCITY IS SUFFICIENT TO CARRY PARTICLES, O/l-35 HOWEVER, THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE VALVE MATERIALS.
O V
Attachment 6 Page 2 of 4
Component Aging Managemtnt Rsview LCM 16 Revision 4 CODE' DESCRIPTION SOURCE -
18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. ES-014 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT FSK-MP-1262 HIGHLY STRESSED AND THE COMPONENTS ARE ONLY FSK-MP-3050 EXPOSED TO HUMID AIR WITH NO EXPECTED CH-1-100 CONDENSATION. NP-5769 VOL-13 THE EXTERNAL ENVIRONMENT (AIR) IS NOT EXPECTED TO AVNER CONTAIN SUFFICIENT ATMOSPHERIC CONTAMINANTS TO FONTANA MAKE THIS ARDM PLAUSIBLE IN 316 STAINLESS STEEL AND ASM TYPICAL ALLOY STEEL. THE LOW YlELD STRENGTHS OF NP-5461 THESE MATERIALS MAKES THEM LESS SUSCEPTIBLE TO THE ARDM.
MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL CONTAINMENT MAXIMUM TEMPERATURE OF120*F, NORMAL AMBIENT TEMPERATURES IN THE EAST PIPING PENETRATION ROOMS OF 140 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, SCC DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSIBLE.
20 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION. VALVE OPERATION RESULTS IN M120-0001
- ITEM / PACKING CONTACT IN RELATIVE MOTION AND POTENTIALLY ABRASIVE WEAR. WEAR OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
O Attachment 6 Page 3 of 4 I
I
Componsnt Aging Managsmsnt Rsvisw LCM-16 Revision 4 CODE DESCRIPTION SOURCE 22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7
. ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT ES-014 PLAUSIBLE SINCE THE PROCESS FLUID IS HUMID AIR WITH CH-1 -100 NO EXPECTED CONDENSATION, AND THE EXTERNAL NP-5769 )
ENVIRONMENT (AIR) IS NOT EXPECTED TO CONTAIN VOL-13 l SUFFICIENT ATMOSPHERIC CONTAMINANTS TO MAKE THIS AVNER ARDM PLAUSIBLE IN 316 STAINLESS STEEL AND TYPICAL FONTANA ALLOY STEEL. ASM NP-5461 MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY i PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL CONTAINMENT MAXIMUM TEMPERATURE OF120 F, NORMAL AMBIENT TEMPERATURES IN THE EAST PIPING PENETRATION ROOMS OF 140 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, IGA DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
P THIS ARDM IS PLAUSIBLE SINCE VALVE PLUG AND SEAT ATTACH 7 WEAR OCCUR WHEN THE VALVE IS OPERATED. THE LEAK TIGHTNESS OF THE VALVE WILL DECREASE WITH TIME AND THE FREQUENCY OF OPERATION. THIS ARDM CAN BE MANAGED BY A PROGRAM WHICH PERFORMS REGULAR LEAK TESTS.
O Attachment 6 Page 4 of 4
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 2 Device Type: HV April 15,1996 Group ID: 077-HV 01 Device Type: Hand Valve Vendor: Jamesbury Model Number: 1/4 and 1/2-21-5600-PP-3 Material:
Internal Environment: Plant Vent Gases External Environment:
Function (s): Maintain System Pressure Boundary Integrity
- Other Parameters:
1 i List of Grouped Components:
'. 1HVRE-5416-A Low Range Inletisolation - -
1HVRE-5416-B ' Filter "B" Inlet Isolation .
l 1HVRE-5416-C Filter "B" Inlet Disconnect' l 1HVRE-5416-D Filter"B" Outlet Disconnect 1HVRE-5416-E Filter"B" Outlet isolation l 1HVRE-5416-F Filter"A" Inlet Isolation l 1HVRE-5416-G Filter"A" Inlet Disconnect 1HVRE-5416-H Filter "A" Outlet Disconnect l
l 1HVRE-5416-J Filter"A" Outlet Isolation 1HVRE-5416-K Grab 1 Inlet isolation 1HVRE-5416-L Grab 1 Inlet Disconnect i 1HVRE-5416-M Grab 1 Outlet Disconnect 1HVRE-5416-N Grab 1 Outlet isolation 1HVRE-5416-Q Low Range Outlet isolation 1HVRE-5418-A Mid-High inlet isolation 1HVRE-5418-B Filter"D" Inlet Isolation 1HVRE-5418-C Filter"D" Inlet Disconnect 1HVRE-5418-D Filter "D" Outlet Disconnect 1HVRE-5418-E Filter "D" Outlet Isolation 1HVRE-5418-F Filter"C" inlet isolation 1HVRE-5418-G Filter "C" Inlet Disconnect 1HVRE-5418-H Fi'ter "C" Outlet Disconnect 1HVRE-5418-J Filter "C" Outlet isolation 1HVRE-5418-K Grab 2 Inlet isolation
- 1HVRE-5418-L Grab 2 Inlet Disconnect
- 1HVRE-5418-M Grab 2 Outlet Disconnect 1HVRE-5418-N Grab 2 Outlet isolation
l l
l n COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
U System: Area & Process Radiation Monitoring (077/079) Attachment 3 i
Equipment Type: VALVE Page 2 of 2 Device Type: HV April 15,1996 Group ID: 077-HV 01 l
l 1HVRE-5418-Q Mid-High Outlet isolation 2HVRE-5416-A Low Range inlet isolation 2HVRE-5416-B Filter"B" Inlet isolation 2HVRE-5416-C Filter"B" Inlet Disconnect 2HVRE-5416-D Filter"B" Outlet Disconnect l 2HVRE-5416-E Filter"B" Outlet Isolation 2HVRE-5416-F Filter"A" Inlet Isolation 2HVRE-5416-G Filter"A" Inlet Disconnect 2HVRE-5416-H Filter"A" Outlet Disconnect 2HVRE-5416-J Filter"A" Outlet isolation 2HVRE-5416-K Grab 1 Inlet isolation 2HVRE-5416-L Grab 1 Inlet Disconnect 2HVRE-5416-M Grab 1 Outlet Disconnect 2HVRE-5416-N Grab 1 Outlet isolation 2HVRE-5416-Q Low Range Outlet isolation 2HVRE-5418-A Mid-High inlet Isolation 2HVRE-5418-B Filter"D" Inlet isolation b
O 2HVRE-5418-C Filter"D" Inlet Disconnect 2HVRE-5418-D -
- Filter"D" Outlet Disconnect -
2HVRE-5418-E Filter"D" Outlet isolation 1 2HVRE-5418-F Filter"C" Inlet Isolation 2HVRE-5418-G Filter"C" Inlet Disconnect l 2HVRE-5418-H Filter"C" Outlet Disconnect 2HVRE-5418-J Filter "C" Outlet isolation 2HVRE-5418-K Grab 2 Inlet isolation 2HVRE-5418-L Grab 2 Inlet Disconnect 2HVRE-5418-M Grab 2 Outlet Disconnect 2HVRE-5418-N Grab 2 Outlet isolation 2HVRE-5418-Q Mid-High Outlet Isolation
)MnWord Fde RM3HV01 DOC l
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O O O ATTACHMENT 4, SUBCOMPONENT/5UB-GROUP IDENTIFICATION (Revision 1) i SYSTEM NUMBER- 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUPID: 077-HV-01 Date: May 16,1996 i c3 -6 Sablect to y
- SaI>GroupID SutKomponent/Name - Manufacturer ModelNumber ' . Material PassiveIstended Functiem(s) L AMR' (Replacement Pge) ' i (Source) (Searce) . L (Seeree) - (Seerre) ! ' (Y er N) 077-IIV-OlA BODY JAMESBURY 1/4 OR 1/2-21-3600- STAINLESS STEEL MAINTAIN PRESSURE BOUNDARY Y PP-3 (TYPE 316) INTEGRITY (NONE) (12284410 Section (12284410 Section (12284410 Section 6 (CLSR) 6 pp. 25-35 & 48) 6 pp. 25-35 & 48) pp. 25-35 & 48) 077-IIV-01B STDI JAMESBURY 1/4 OR 1/2-21-3600- STAINLESS STEEL MAINTAIN PRESSURE BOUNDARY Y PP-3 (316) INTEGRTIY (NONE) (12284-010 Section (12284-010 Section (12284-010 Sectice 6 (CLSR) 6 pp. 25-35 & 48) 6 pp. 25-35 & 48) pp. 25-35 & 48) 077-IIV-01C BOLTS AND NUTS JAMESBURY 1/4 OR 1/2-21-3600* STAINLESS STEEL MAINTAIN PRESSURE BOUNDARY Y PP-3 (300 SERIES) INTEGRITY (NONE) (12284-010 Section (12284-010 Section (12284-010 Section 6 (CESR) 6 pp. 25-35 & 48) 6 pp. 25-35 & 48) pp. 25-35 & 48) 077-IIV-01D NON-PRFSSURE JAMESBURY 1/4 OR 1/2-21-3600- N/A NONE. NO LR INTENDED FUNCTION. N BOUNDARY PARTS PF-3 COMPONENT IN LR SCOPE FOR PRESSURE BOUNDARY ON1Y.
(NONE) (12284-010 Section (12284-010 S$ tion (N/A) (CLSR) 1 <
6 pp.25-35 & 48) 6 pp. 25-35 & 48)
I a
Page1of1
1 l
l ARDM MATRIX (Revision 1) i System: Ares & Process Radiation Monitoring (877/079) Attachment 5 !
Equipment Type: VALVE Page 1 ofI Device Type: HV May 16,1996 ,
Group ID: 077-HV-01 i ARDM 077-HV- 077-HV- 077-HV-OlA OlB OIC Body Stem Bolt / Nut Cavitation Erosion 02 02 19 Corrosion Fatigue 12 12 12 Crevice Corrosion 06 06 19 Erosion Corrosion 21 21 19 Fatigue 12 12 12 Fouling 15 15 19 Galvanic Corrosion 07 07 07 General Corrosion 01.3 01.3 01.3 Hydrogen Damage 03 03 19 Intergranular Attack 22 22 22 i MIC 15 15 19 Particulate Wear 17 19 19 Erosion l Pitting 06 06 19 l p Radiation Damage 01.3 01.3 01.3 ,
l Rubber Degradation - 01.3 -- 01.3 - 01.3 Selective Leaching 01.3 013 01.3 Stress 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 Thermal Damage 01.3 01.3 01.3 Thermal 04 04 04 Embrittlement Wear 16 14 16 l
l I
Winword File RM5HW1 doc O
Componsnt Aging Minigtm:nt Rsvisw LCM-16 Revision 4 6
Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: HV EQUIPMENT TYPE: VALVE GROUP ID: 077-HV-01 Date: 5/16/H !
~
CODE) (DESCRIPTION) L {SOORCEh' 4
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 :
CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM: l 01.3 STAINLESS STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. - ATTACli 7 !
I THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY ASSOCIATED WITH THIS ARDM.
6 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 i WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN FONTANA !
O ..THAT ENTERS THE GRAIN STRUCTURE OF THE. METAL...THE_ .
PROCESS FLUID DOES NOT CREATE THE REQUIRED
. 60738 SH2 .
60722 SH1 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT AVNER '
GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS ASM NOT EXPECTED TO CONTAIN CONCENTRATIONS OF 12284-010 ;
ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE CH-1-100 i ARDM TO BE PLAUSIBLE. NP-5769 i MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW :
YlELD STRENGTH OF 300 SERIES STAINLESS STEELS IS ~
BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY ,
FOR HYDROGEN CRACKING.
THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS i SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (>150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN THE MAXIMUM AMBIENT DESIGN TEMPERATURE OF120 F, MAXIMUM FLUID DESIGN TEMPERATURES OF 130 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 1 of 4
Compon:nt Aging Man:g:m:nt R:vi2w LCM-16 Revision 4 CODE i DESCRIPTION L SOURCE 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. METALLIC SUBCOMPONENTS ARE NOT SisBJECTED ES-014 TO TEMPERATURES APPROACHING OR IN EXCESS OF 500 F.
06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 I ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS j INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO i 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION i IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
l 07 MATERIAL SELECTION / SEPARATION DOES NOT PERPETUATE ATTACH 7 THE ARDM. THE VALVE IS MADE OF MATERIALS WITH LOW O/l-35 y p() POTENTIAL DIFFERENCES AND THE ONLY. MOISTURE. _. . . _ ~ . .
RESULTS FROM A LIMITED AMOUNT OF CONDENSATION.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND 12284-010 TEMPERATURES ARE LOW AND RELATIVELY STEADY ES-014 MAKING THIS ARDM NOT PLAUSlBLE.
14 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION AND IS NOT CONSIDERED PLAUSIBLE. 12284-010 VALVE OPERATION RESULTS IN STEM / PACKING CONTACT IN RELATIVE MOTION AND POTENTIALLY ABRASIVE WEAR.
l BALL VALVE DESIGN RESULTS IN MINIMAL STEM WEAR. IF i
PACKINGS LEAK, IT WILL BE MINOR (MINIMAL IMPACT ON INTENDED FUNCTION) AND DETECTABLE DURING VALVE l OPERATION / INSPECTION. i l
l l
f3 i b
Attachment 6 Page 2 of 4 l l
i Compon:nt Aging M:n:gim:nt RLvisw LCM-16 Revision 4 v CODE: TSOURCEj (DESCRIPTION L 15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT MO 2199402189 GASES, AIRBORNE PARTICLES AND MICROBES. PLANT EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSIBLE ARDM SINCE THE SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT l ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE l RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7
- VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738 SH.2 THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT 12284-010 l w LEAD TO SIGNIFICANT EROSION OF.THE EROSION RESISTANT.
MATERIALS.
l 18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES. A SUSCEPTIBLE MATERIAL, O/l-35 j TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 60722 SH1 THIS ARDM iS NOT PLAUStBLE SINCE THE SYSTEM IS NOT AVNER I HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION. FLOW FONTANA l FROM SYSTEMS INTO THE PLANT VENT IS NOT EXPECTED 60738 SH2 TO CONTAIN CONCENTRATIONS OF ATMOSPHERIC ASM CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE CH-1-100 '
l PLAUSIBLE IN TYPICAL 300 SERIES STAINLESS STEELS. THE NP-5769 LOW YlELD STRENGTH OF TYPICAL 300 SERIES STAINLESS STEELS MAKES THE ARDM NOT PLAUStBLE.
1 MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (>150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN THE MAXIMUM AMBIENT DESIGN TEMPERATURE OF120 F, MAXIMUM FLUID DESIGN TEMPERATURES OF 130 F, AND (q) 4 DRYING EFFECTS OF WARMER TEMPERATURES, SCC DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 3 of 4
Compontnt Aging Manigsmant Rsvisw LCM-16 Revision 4 CODEt
, TDESCRIPTIONI :: SOURCEi 19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUSCOMPONENTS TYPICALLY ARE NOT EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSlBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 60722 SH1 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A AVNER LIMITED AMOUNT OF CONDENSATION. FLOW FROM VOL-13 SVSTEMS INTO THE PLANT VENT IS NOT EXPECTED TO FONTANA CONTAIN CONCENTRATIONS OF ATMOSPHERIC 60738 SH2 CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE ASM PLAUSIBLE IN TYPICAL 300 SERIES STAINLESS STEELS. CH-1-100 NP-5769 MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS O.- SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN THE MAXIMUM AMBIENT DESIGN TEMPERATURE OF120 F, MAXIMUM FLUID DESIGN TEMPERATURES OF 130 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, IGA DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
I Attachment 6 Page 4 of 4
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1) l O System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: HV April 15,1996 Group 10: 077-HV-02 Device Type: Hand Valve Vendor:
Model Number:
Material:
Internal Environment: Containment Atmosphere External Environment:
Function (s): Maintain Containment Isolation Other Parameters: Mark 130 List of Grouped Components:
i 1HVRE-102 Containment RMS Test Connector isolation Valve
~
~ Containment RMS Test Connector Isolation Valve ~
f l
I
% Flie RM. yy2y g O
- O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER- 077/079 SYSTEM NAME Area & Process Radiation Monitoring EQUIPMENTID: NA GROUP ID: 077-HV-02 Date: May 17,1996 Sahltet to Sub-Group ID . . Sat <omponent/Name Manufacturer . . Model Number - i . Material : Passive Imeesded Feuctase(s)( LAMR-L (Replacement Pge) - : (Somree) 0 - (Sonne) . (Source) - (See ce) - (y orN) >-
077-IIV-02A BODY / BONNET N/A MARK 130 CAST A216 GR MAINTAIN CONTAINMENT ISOLATION y WCB OR FORGED A105 GR 11 CARBON STEEL (NONE) (N/A) (6073hSH0001) (92771) (CLSR)
STEM N/A MARK 130 ALLOY STEEL MAINTAIN CONTAINMENT ISOLATION y 077-HV-02B (NONE) (N/A) (60738SH0001) (NONE) (CIER)
BOLTS N/A MARK 130 ALLOY /CS MAINTAIN CONTAINMENT ISOLATION y 077-IIV-02C (NONE) (N/A) (607385H0001) (NONE) (CIER)
NITIS N/A MARK 130 ALLOY /CS MAINTAIN CONTAINMENT ISOLATION y 077-IIV-02D (NONE) (N/A) (60738SH0001) (NONE) (CLSR) 077-IIV-02E DISK & SEAT N/A MARK 130 ALLOY MAINTAIN CONTAINMENT ISOLATION Y STEEI/ STELLITE (NONE) (N/A) (607385H0001) (NONE/92771) (CIER) i Page1ofI
g ARDM MATRIX (Revision 1) t System: Area & Process Radiation Monitoring (07709) Attachment 5
- Equipment Type: VALVE Page1 of1 Device Type: HV May 20,1996 Group ID: 077-HV-02 ARDM 077-HV- 077-HV- 077-HV- 077-HV- 077-HV-02A 02B 02C 02D 02E Body / Bonnet Stem Bolts Nuts Disk & Seat Cavitation Erosion 02 02 19 19 02 Corrosion Fatigue 12 12 12 12 12 Crevice Corrosion G G 19 19 G Erosion Corrosion 02 02 19 19 02 Fatigue 12 12 12 12 12 Fouling 15 15 19 19 15 Galvanic Corrosion 07 07 07 07 07 General Corrosion G 01.3 19 19 01.3
( Hydrogen Damage 03 03 03 03 03 i Intergranular Attack 01.1 22 22 22 22 B41C 06 06 19 19 06 Particulate Wear Erosion 20 20 19 19 20 Pitting G G 19 19 G j Radiation Damage 01.1 01.3 01.2 01.2 01.3 l D Rubber Degradation 01.1 01.3 01.2 01.2 01.3
- h Selective Leaching Stress 01.1 - .
01.1 01.3 18
-- -. 012 - -
18 al2 18 01.3 18 l
Corrosion Cracking
! Stress Relaxation 04 04 04 04 04 Thermal Damage 01.1 01.3 01.2 01.2 01.3 Thermal Embrittlement 04 04 04 04 04
\Vear 16 21 16 16 17 i
i
)
I
% Word Fde RM5HV01 DOC 5
O i
i l
Ccmpon:nt Aging MInag:msnt Rsvi:w LCM-16 Revision 4 j
Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING l DEVICE TYPE: HV EQUIPMENT TYPE: VALVE i
GROUP ID: 077-HV-02 Date: 5/20/96 CODE (DESCIUPTIONj y iSOURCEf l
01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.1 CARBON STEEL 01.2 CARBON STEEL / ALLOY 01.3 ALLOY / STAINLESS STEEL 02 PROCESS FLUID TYPE DCES NOT PERPETUATE THE ARDM. ATTACH 7 '
THE PROCESS FLUID IS AIR, NOT THE LIQUIDS NORMALLY l
ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES. SURFACE CORROSION VOL-1 .
WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN VOL-13 THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE FONTANA PROCESS FLUID DOES NOT CREATE THE REQUIRED 60738 SH1 CORROSION SITES. THE PROCESS FLUID IS CONTAINMENT CH-1-100 ATMOSPHERE. THE NORMAL HYDROGEN CONCENTRATION NP-5769 IS NOT SUFFICIENT TO MAKE THIS ARDM PLAUSIBLE. AVNER ASM MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTHS OF TYPICAL CARBON STEELS AND BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN ;
SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED l
BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS i REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO l 1
DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL CONTAINMENT MAXIMUM TEMPERATURE OF120 F, NORMAL i AMBIENT TEMPERATURES IN THE EAST PIPING PENETRATION ROOMS OF 140 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 1 of 4
I Componznt Aging Mzntg:msnt Rsvisw LCM-16 Revision 4
- SOORCEi sCODE/ [ DESCRIPTION!
04 PROCESS FL UlD TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 l ARDM. OPfMTING TEMPERATURES LESS THAN 500 F ES-014 l ENSURE TK ARDM IS NOT PLAUSIBLE.
06 PROCESS F UlD AND MOISTURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE FLUID IS AIR WITH THE POTENTIAL FOR SOME ES-014 HUMIDITY. OCCASSIONAL HUMIDITY DOES NOT SUBJECT THE COMPONENTS TO THE AGGRESSIVE ENVIRONMENT NORMALLY ASSOCIATED WITH THE ARDM.
l I 07 PROCESS FLUID (AIR WITH SOME HUMIDITY) DOES NOT ATTACH 7 PERPETUATE THE ARDM. THE GENERAL LACK OF O/l-35 >
ELECTROLYTE TO COMPLETE A GALVANIC CIRCUlT MAKES ES-014 l THIS ARDM NOT PLAUSIBLE.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 l ES-014 PERPETUATE THE ARDM THE SYSTEM PRESSURES AND l TEMPERATURES ARE LOW AND RELATIVELY STEADY Oll-35 MAKING THIS ARDM NOT PLAUS!BLE.
I 15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 l FUNCTION._ FOULING MAY OCCUR TO A LIMITED.. EXTENT ._ _ . O/l-35 l DUE TO HUMIDITY IN THE WARM CONTAINMENT GASES AND AIRBORNE PARTICLES. THE VALVES ARE OPERATED INFREQUENTLY, MINIMlZING THE POSSIBILITY OF THIS l ARDM. FOULING DOES NOT D,lRECTLY AFFECT THE PRESSURE BOUNDARY FUNCTION.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSIBLE ARDM SINCE THE SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY ,
RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 THE ARDM IS NOT Pl.AUSIBLE. COBALT ALLOYS SUCH AS ASME STELLITE HAVE EXCELLENT WEAR RESISTANCE. O-055-1/2 ADDITIONALLY, THE VALVES ARE OPERATED ONLY TO TEST M-571 E-1/2 THE CONTAINMENT ISOLATION CONTROL VALVES FOR LEAKAGE AND ARE NORMALLY LOCKED SHUT.
l l
l O ,
i Attachment 6 Page 2 of 4
Compon:nt Aging Minagtm:nt Rsvisw LCM-16 Revision 4
- CODE L lDESCRIPHONF iSOURCE6 18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35
! TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. FSK-MP-1262 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT FSK-MP-3050 HIGHLY STRESSED AND THE PROCESS FLUID IS HUMID AIR. CH-1-100 NP-5769 l THE EXTERNAL ENVIRONMENT (AIR) IS NOT EXPECTEO TO VOL-13 CONTAIN SUFFICIENT ATMOSPHERIC CONTAMINANTS TO AVNER MAKE THIS ARDM PLAUSIBLE IN TYPICAL CARBON STEELS FONTANA AND BOLTING MATERIALS. THE LOW YlELD STRENGTHS OF ASM THESE MATERIALS MAKES THEM LESS SUSCEPTIBLE TO THE NP-5461 ARDM.
i MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY I PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS ,
REQUIRE MOISTURE AND TEMPERATURE (> 150'F) TO !
DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL l CONTAINMENT MAXIMUM TEMPERATURE OF120 F, NORMAL l l AMBIENT TEMPERATURES IN THE EAST PIPING PENETRATION l l ROOMS OF 140 F, AND DRYING EFFECTS OF WARMER l
, - TEMPERATURES, SCC DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSlBLE. THE EXTERNAL ENVIRONMENT IS NOT I
NORMALLY HARSH.
20 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY lS SUFFICIENT TO CARRY PARTICLES, HOWEVER, O/l-35 THE LIMITED SOURCE OF AIRBORNE PARTICLES AND INFREQUENT OPERATION WILL NOT LEAD TO SIGNIFICANT EROSION OF THE VALVE MATERIALS.
21 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION. VALVE OPERATION MAY RESULT IN i STEM / PACKING CONTACT IN RELATIVE MOTION. BUT THE INFREQUENT OPERATION OF THE VALVE REDUCES THE j OCCURRANCE OF THE ARDM TO A MINIMUM . WEAR OF l PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE l BOUNDARY SUBCOMPONENTS.
Attachment 6 Page 3 of 4 i
i Compon:nt Aging Mznagsmant Rsvisw- LCM-16 Revision 4 .
ECODEi (DESCRIErlONi; ISOURCEj 21 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION. VALVE OPERATION MAY RESULT IN STEM / PACKING CONTACT IN RELATIVE MOTION, BUT THE :
l lNFREQUENT OPERATION OF THE VALVE REDUCES THE ,
1 OCCURRANCE OF THE ARDM TO A MINIMUM . WEAR OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS.
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 ,
l AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT ES-014 PLAUSIBLE SINCE THE PROCESS FLUID iS ONLY HUMID AIR, CH-1-100 AND THE ENVIRONMENT (AIR) IS NOT EXPECTED TO . NP-5769 ,
CONTAIN SUFFICIENT ATMOSPHERIC CONTAMINANTS TO VOL-13 MAKE THIS ARDM PLAUSIBLE IN TYPICAL ALLOY STEEL AND AVNER BOLTING MATERIAL. FONTANA ASM MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY NP-5461 PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS p REQUIRE MOISTURE AND TEMPERATURE (> 150'F) TO V DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN NORMAL CONTAINMENT MAXIMUM TEMPERATURE OF120*F, NORMAL AMBIENT TEMPERATURES IN THE EAST PIPING PENETRATION ROOMS OF 140 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, IGA DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
4 G THE ARDM IS PLAUSIBLE BECAUSE STEEL MATERIALS OF ATTACH 7 CONSTRUCTION ARE EXPOSED TO HUMID AIR. THERE ARE LCM 96-133 TWO GENERAL POSSIBLE EFFECTS; A UNIFORM CORROSION OF THE INTERNAL SURFACES OF THE VALVE CAUSING BODY WALL THINNING, AND LOCALIZED ATTACK RESULTING IN PITS AND CRACK INITIATION - MOST LIKELY AT CREVICES IN THE BODY / BONNET JOINT, STEM TO BONNET / PACKING AREA, AND AT THE VALVE SEAT AREA.
AGING MANAGEMENT RECOMMENDATIONS INCLUDE:
1 (1) INCLUDE THE COMPONENTS IN THE AGE RELATED DEGRADATION INSPECTION PROGRAM.
l l
O Attachment 6 Page 4 of 4
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: HV April 15,1996 Group ID: 077-HV 03 Device Type: Hand Valve Vendor:
Model Number:
Material:
Internal Environment: Control Room Atmosphere External Environment:
Function (s): Maintain System Pressure Boundary integrity Other Parameters: Mark 19 List of Grouped Components:
0HVRE-5350-H Control Room Radiation Monitor inlet
~
OHVRE-5350-1 Control Room Radiation Monitor inlet OHVRE-5350-L Control Room Radiation Monitor Outlet ,
i VAnWord Fue RM3HYD3 DOC O
/~N O J U ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring GROUPID: 077-HV-03 Date: May 17,1996 EQUIPMENTID: NA Subject to i Masefecturer ModelNumber . 1
. Meterial PassiveIntended Fasetles(s) L . ? AMR -;
Sub-GroupID SubCompoucat/Name -
- (Repiecement Pge) - (Soerce) ' (Source) . (Source) (Source) ~ ; (Yer N)i 1
077-IIV-03A BODY / BONNET N/A MARK 19 CAST A216 GR MAINTAIN PRE 5L%RE BOUNDARY Y WCB OR FORGED INTEGRITY A105 GR H CARBON STEEL (NONE) (N/A) (60738SH0001) (92771) (CLSR)
STEM N/A MARK 19 ALLOY STEEL MAINTAIN PRESSURE BOUNDARY Y 077-IIV-03B INTEGRITY (NONE) (N/A) (60738SH0001) (NOST) (CISR) 077-IIV-03C BOLTS N/A MARK 19 ALLOY /CS MAINTAIN PRESSLRE BOUNDARY Y INTEGRIN' (NONE) (N/A) (607385H0001) (NONE) (CESR) 077-HV-03p NUTS N/A MARK 19 ALLOYK3 MAINTAIN PRESSURE BOUNDARY Y INTEGRIN' (NONE) (N/A) (60738SH0001) (NONE) (CLSR) 077-IIV 03E DISK & SEAT N/A MARK 130 ALLOY NONE. NO LR INTENDED FUNCTION. N STEEI1 STELLITE COMPONENT IN LR SCOPE FOR OR SS PRESSURE BOUNDARY ONLY.
(NONE) (N/A) (607385H0001) (NONE/92771) (CLSR)
Page1ofI
1 ARDM MATRIX (Revision 1)
System: Ares & Process Radiation Monitoring (077/79) Attachment 5 Equipment Type: VALVE PageI of1 Device Type: HV May 20,1996 Group ID: 077-HV-03
)
l I
ARDM 077 HV- 077 HV- 077-HV- 077-HV- 1 03A 03B 03C 03C Body / Bonnet Stem Bolts Nuts Cavitation Erosion 02 02 19 19 Corrosion Fatigue 12 12 12 12 Crevice Corrosion 06 06 06 06 Erosion Corrosion 02 02 19 19 )
Fatigue 12 12 12 12 l l
Fouling 06 06 19 19 Galvanic Corrosion 07 07 07 07 General Corrosion 06 01.3 06 06 Hydrogen Damage 03 03 03 03 Intergranular Attack 01.1 22 22 22 MIC 06 06 19 19 l
Particulate Wear Erosion 15 15 19 19 Pitting 06 06 06 06 Radiation Damage 01.1 01.3 01.2 01.2 l C
V Rubber Degradation Selective Leaching 01.1 01.1 01.3 01.3 01.2 01.2 01.2 01.2 y j
Stress 01.1 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 04 Thermal Damage 01.1 01.3 01.2 01.2 Thermal Embrittlement 04 04 04 04 Wear 16 17 16 16 Winword Filo RM5&WO3 DOC f
L/
Comp::n nt Aging Man:g:msnt Rsvisw LCM-16 Revision 4 Matrix Code List (Revision 1)
SYGTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: HV EQUIPMENT TYPE: VALVE GROUP ID: 077-HV-03 Date: 5/21/96 l l
~
"CODEI ,
[DESCRIPTIONU ' [50URC'Ek ~
t 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
l 01.1 CARBON STEEL 01.2 CARBON STEEL / ALLOY 01.3 ALLOY / STAINLESS STEEL l 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 ,
THE PROCESS FLUID IS AIR, NOT THE LIQUID 3 NORMALLY l ASSOCIATED WITH THIS ARDM.
t
! 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 l HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-1 f I
WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN VOL-13 THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE FONTANA PROCESS FLUID DOES NOT CREATE THE REQUIRED 60738 SH1 CORROSION SITES. THE PROCESS FLUID IS CONTROL ROOM CH-1-100 HVAC AIR. THE NORMAL HYDROGEN CONCENTRATION IS NP-5769 NOT SUFFICIENT TO MAKE THIS ARDM PLAUSIBLE. AVNER ASM MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW
, YlELD STRENGTHS OF TYPICAL CARBON STEELS AND ~
l BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS i SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS j l
REQUIRE MOISTURE AND TEMPERATURE (>150 F) TO
)
DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MILD l CONDITIONS INSIDE THE CONTROL ROOM, NORMAL j AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST
- ROOM OF 110*F MAXIMUM, AND THE DRYING EFFECTS OF
! WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 1 of 4
Compon:nt Aging Managtment Rsvisw LCM-16 j Revision 4 '
. CODE (DESCRIPTIONi ' ,
ISddRCEI 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
06 THE PROCESS FLUID AND EXTERNAL ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THIS ARDM. THE CONTROL ROOM LCM 95-112 ATMOSPHERE IS CONDITIONED (REDUCED HUMIDITY AND UFSAR 9.8.2.3 FILTERED). THE FOULING AND HUMIDITY EFFECTS ARE THEREFORE INSIGNIFICANT. THE VALVE PRESSURE BOUNDARY FUNCTION FOR THE VERY LOW SYSTEM PRESSURES WILL NOT BE AFFECTED.
BORIC AClD CORROSION OF THIS SYSTEM IS ALSO NOT CONSIDERED PLAUSlBLE AS THE PROCESS FLUID IS NOT BORATED WATER.
07 PROCESS FLUID (HVAC AIR WITH LOW HUMIDITY) DOES NOT ATTACH 7 )
PERPETUATE THE ARDM. THE GENERAL LACK OF. O/l-35 l' ELECTROLYTE TO COMPLETE A GALVANIC CIRCUlT MAKES ES-014 THIS ARDM NOT PLAUSIBLE. I O ,2 Service LOADING.AMeLiTUDeS,FReOUENCieS D.O NOT PERPETUATE THE ARDM. THE SYSTEM PRES.SURES AND ATTACH 7 ES-014 TEMPERATURES ARE LOW AND RELATIVELY STEADY O/l-35 MAKING THIS ARDM NOT PLAUSIBLE.
15 PARTICULATE WEAR EROSION'DOES NOT SIGNIFICANTLY ATTACH 7 AFFECT COMPONENT FUNCTION. THE AIR VELOCITY IS O/l-35 l SUFFICIENT TO CARRY PARTICLES, HOWEVER, THE LIMITED UFSAR 9.8.2.3 J SOURCE OF AIRBCRNE PART!CLES WILL NOT LEAD TO ,
SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSIBLE ARDM SINCE THE SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 i INTENDED FUNCTION. VALVE OPERATION RESULTS IN STEM / PACKING CONTACT IN RELATIVE MOTION, BUT WEAR l Q OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS.
Attachment 6 Page 2 of 4
. . - - . - . _ _ - ~ . _ _ _ _ _ - . ... .- . - . _ _ - _
Compon nt Aging Manag:mant RsviLw LCM-16 Revision 4
-l CODE ? fDESCRIPTIONI . ISOURdEI 18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTlBLE MATERIAL, O/l 35 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. FSK-MP-2028 !
THIS ARDM iS NOT PLAUSlBLE SINCE THE SYSTEM IS NOT CH-1-100 HIGHLY STRESSED AND THE PROCESS FLUID IS HVAC AIR ES-014 WITH LOW HUMIDITY. NP-5769 l VOL-13 :
THE EXTERNAL ENVIRONMENT (AIR) IS NOT EXPECTED TO AVNER l CONTAIN SUFFICIENT ATMOSPHERIC CONTAMINANTS TO FONTANA MAKE THIS ARDM PLAUSIBLE IN TYPICAL CARBON STEELS ASM AND BOLTING MATERIALS. THE LOW YlELD STRENGTHS OF NP-5461 l THESE MATERIALS MAKES THEM LESS SUSCEPTIBLE TO THE ARDM.
l MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY )
PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFlDE LUBRICANTS 1 REQUIRE MOISTURE AND TEMPERATURE (>150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MILD I CONDITIONS INSIDE THE CONTROL ROOM, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOM OF 110*F MAXIMUM AND u DRYING EFFECTS OF WARMER TEMPERATURES, SCC DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 i ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT l l
EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM l NON-PLAUSIBLE.
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Componnnt Aging Managtmrnt R3vi:w LCM-16 Revision 4
^
CDDET LDESCRIPTIONl 5SdORCE; 22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT FSK-MP-2028 PLAUSlBLE SINCE THE PROCESS FLUID IS HVAC AIR WITH CH-1-100 LOW HUMIDITY. ES-014 NP-5769 MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY VOL-13 PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS AVNER SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS FONTANA REQUIRE MOISTURE AND TEMPERATURE (> 150'F) TO ASM DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MILD NP-5461 CONDITIONS INSIDE THE CONTROL ROOM, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOM OF 110*F MAXIMUM, AND DRYING EFFECTS OF WARMER TEMPERATURES, IGA DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
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Attachment 6 ,
Page 4 of 4
i COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: HV April 15,1996 Group ID: 077-HV-04
}.
, Device Type: Hand Valve Vendor:
Model Number:
Material:
Internal Environment: Component Cooling / Service Water i
External Environment:
, Function (s): Maintain System Pressure Boundary Integrity Maintain isolation Boundary Other Parameters: Mark 19 n List of Grouped Components:
U 1HVRE-1595-H SRW RMS Inlet -
1HVRE-1595-J 1-FIS-1595 Bypass 1HVRE-1595-M 1-FIS-1595 Outlet isolation 1HVRE-3819-K PRM CC Radiation Monitoring Unit i HV 2HVRE-1595-H SRW RMS Inlet 2HVRE-1595-J 2-FIS-1595 Bypass 2HVRE-1595-M 2-FIS-1595 Outlet Isolation 2HVRE-3819-K PRM CC Radiation Monitoring Unit 2 HV WinWord Fee RM3HV04 DOC
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision I)
SYSTEM NUMBER- 077/079 SYSTEM NAME: Area & Process Radiation Monitoring EQUIPMENTID: NA GROUPID: 077-HV-04 Date: May20,1996
~
Sebject to T-Sub.GroupID ; .: SebComposent/Name < Manufacturer . ModelNumber 3 Material PasiveIntended Fumetlee(s) . VAMR ::
. (Replacement Pge)~ . (Source) . > (Source).; 4(Source) _ (Seeree) .. (Y er N)L i
077-IIV44A BODY / BONNET N/A MARK 19 CAST A216 GR MAINTAIN PRESSURE BOUNDARY y WCB OR FORGED INTEGRITY A195 GR H CARBON STEEL (NONE) (N/A) (607385H0001) (92771) (CLSR)
~
STEM N/A MARK 19 ALLOY STEEL MAINTAIN FRESSURE BOUNDARY y INTEGRITY f 077.IIV-04B (NONE) (N/A) (607385H0001) (NOST) (CLSR) .
077-IIV-04C BOLTS N/A MARK 19 ALLOY /CS MAINTAIN PRESSURE BOUNDARY Y INTEGRTlY i (NONE) (N/A) (60738SH0001) (NONE) (CLSR) <
077-IIV-04D NUIS N/A MARK 19 ALLOY /CS MAINTAIN PRESS.JRE BOUNDARY y INTEGRITY (NONE) (N/A) (687385H0001) (NONE) (CLSR) 077-IIV-04E DISK & SEAT N/A MARK 130 ALLOY MAINTAIN PRESSURE BOUNDARY y STEEIJSTELLITE INTEGRITY. ISOLATION ETNCTION.
(NONE) (N/A) (60738SH0001) (NONE/92771) (CLSR)
PageIofI
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l ARDM MATRIX (Revision 1)
System: Ares & Process Radiation Monitoring (077/79) Attachment 5 w Equpment Type: VALVE Page1 ofI Device Type: HV May 20,1996 Group ID: 077-HV-04 l
! ARDM 077-HV- 077-HV- 077 HV- 077 HV- 077-H V-l 04A 04B 04C 04D 04E l Body / Bonnet Stem Bolts Nuts Disk / Seat Cavitation Erosion 02 02 19 19 02 Corrosion Fatigue 12 12 12 12 12 Crevice Corrosion G G 19 19 G Erosion Corrosion 02 02 19 19 02 Fatigue 12 12 12 12 12 Fouling 06 06 19 19 19
, Galvanic Corrosion 07 07 07 07 07 l General Corrosion G 01.3 19 19 01.3 Hydrogen Damage 03 03 03 03 03 l Intergranular Attack 01.1 06 01.2 01.2 06 MIC 06 06 19 19 06 Particulate Wear Erosion 15 15 19 19 15 Pitting G G 19 19 G
! Radiation Damage 01.1 01.3 01.2 01.2 01.3
. Rubber Degradation 01.1 01.3 O!.2 01.2 01.3 Selective teaching 01.1 01.3 .01.2 01.2 01.3
! Stress 01.1 18 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 04 04 Thermal Damage 01.1 01.3 01.2 01.2 01.3 Thermal Embrittlement 04 04 04 04 04 Wear 16 17 16 16 17 1 l
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MAnWord Fde RMSHV04 DOC
Compon:nt Aging Management Rsvi::w LCM-16 Revision 4 Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: HV EQUIPMENT TYPE: VALVE l
GROUP ID: 077-HV-04 Date: 5/20/96 l
CODE' : DESCRIPTION.~ SOURCE 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.1 CARBON STEEL 01.2 ALLOY / CARBON STEEL 01.3 ALLOY / STAINLESS STEEL l
02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS NOT THE TYPE NORMALLY O/135 ASSOCIATED WITH THIS ARDM (HIGH VELOCITY AND/OR RAPID PRESSURE VARIATIONS). ,
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I Componsnt Aging Managemtnt Revisw LCM-16 Revision 4
- CODET LDESCRIPTION ? 5 SOURCE.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 l HYDROGEN DAMAGE REQUIRES SURFACE CORROSION CP-206 WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN VOL-1 l THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE VOL-13 PROCESS FLUID DOES NOT CREATE THE REQUIRED FONTANA CORROSION SITES. THE PROCESS FLUIDS ARE COMPONENT 60738 SH1 COOLING WATER AND SERVICE WATER, WHICH ARE CH-1-100 l
TREATED UNDER STRICT ADMINISTRATIVE CONTROLS TO NP-5769 LIMIT HYDRAZINE. THE NORMAL HYDROGEN AVNER CONCENTRATION IS NOT SUFFICIENT TO MAKE THIS ARDM ASM PLAUSIBLE.
i MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW l YlELD STRENGTHS OF TYPICAL CARBON STEELS AND l BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
l THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM PLAUSIBLE. ONLY LUBRICANTS WITHIN STRICT
^""'"'"'"^""'"'"'"^""""""'"""""
(J_ PROCEDURE TO BE USED ON RESTRICTED SYSTEMS SUCH _
AS CCW/SRW. SINCE CHEMICAL CONTROL OF THESE SYSTEMS MUST BE PERFORMED TO PROTECT THEM i
AGAINST CHEMICAL ATTACK, HYDROGEN DAMAGE DUE TO l LUBRICANTS IS NOT A CONCE.RN.
l 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7
! ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014
< ENSURE THIS ARDM IS NOT PLAUSIBLE.
06 THE PROCESS FLUID CHEMISTRY DOES NOT PERPETUATE ATTACH 7 THIS ARDM. THE COMPONENT COOLING AND SERVICE CP-206 )
WATER SYSTEMS ARE CLOSED SYSTEMS WITH TREATED 95-BGE-0086 WATER UNDER STRICT ADMINISTRATIVE CONTROLS TO LIMIT CHLORIDES, SUSPENDED SOLIDS AND DISSOLVED OXYGEN.
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Attachment 6 Page 2 of 5
Compontnt Aging Manag::msnt Rsvisw LCM-16 Revision 4 h idODEi
- LDE8dRIPTIOM TSOURCEE ~
07 THE ARDM DOES NOT SIGNIFICANTLY IMPACT THE ATTACH 7 PRESSURE BOUNDARY FUNCTION OF THE SUBCOMPONENTS. CP-206 THERE MAY BE SIGNIFICANT GALVANIC COUPLES BETWEEN OERDB VARIOUS SUBCOMPONENT MATERIALS, HOWEVER: PIPE AMG VOL-13
- 1) THE CHEMISTRY CONTROL OF THE SYSTEM FLUID RESULTS IN VERY LOW (PPB) LEVELS OF DISSOLVED OXYGEN AND CHLORIDES, GREATLY REDUCING RATES AND EFFECTS OF ANY GALVANIC CORROSION WHICH MIGHT OCCUR.
- 2) THE RATIO OF THE WETTED CARBON STEEL AREA TO THE CATHODIC MATERIALS WETTED AREAS IS LARGE, LIMITING THE EFFECTS ON THE CARBON STEEL PB SUBCOMPONENTS.
- 3) GALVANIC CORROSION IN CLOSED LOOP COOLING SYSTEM COMPONENTS HAS NOT BEEN IDENTIFIED AS AN ISSUE AT CCNPP OR IN THE INDUSTRY GENERICALLY.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND O/l-15 TEMPERATURES ARE LOW AND RELATIVELY STEADY O/l-16 O M^xiNG THiS ^RDM NOT eLauS'Ble. _
15 PARTICULATE WEAR EROSION DOES NOT SIGNIFICANTLY ATTACH 7 AFFECT COMPONENT FUNCTION. THE WATER VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, THE LIMITED
~
SOURCE OF PARTICLES IN THiS CLOSED / TREATED WATER SYSTEM WILL NOT LEAD TO SIGNIFICANT EROSION OF THE VALVE MATERIALS.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 '
WEAR IS NOT A PLAUSlBLE ARDM SINCE THE SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION. VALVE OPERATION RESULTS IN STEM / PACKING CONTACT IN RELATIVE MOTION AND POTENTIALLY ABRASIVE WEAR. WEAR OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS. THE DISC / SEAT WEAR DUE TO PERIODIC OPERATION IS CONSIDERED MINIMAL AND WILL NOT AFFECT THE SYSTEM INTENDED FUNCTION.
Attachment 6 Page 3 of 5
1 i
i' Compon:nt Aging Managsmant Ravisw LCM-16 i Revision 4
, CODE 0 '
$.DESCRIP. TIDN ? ISDURCES 3
l 18 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, CP-206 TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 95-BGE-0086
- THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT CH-1-100 HIGHLY STRESSED AND THE COMPONENT COOLING AND ES-014 SERVICE WATER SYSTEMS ARE CLOSED SYSTEMS WITH NP-5769 TREATED WATER UNDER STRICT ADMINISTRATIVE VOL-13 i CONTROLS TO LIMIT CHLORIDES, SUSPENDED SOLIDS AND AVNER' DISSOLVED OXYGEN. ONLY LUBRICANTS WITHIN STRICT FONTANA
- ADMINISTRATIVE CONTROLS ARE PERMITTED BY ASM i
PROCEDURE TO BE USED ON RESTRICTED SYSTEMS SUCH NP-5461
- AS CCW/SRW. SINCE CHEMICAL CONTROL OF THESE
- SYSTEMS MUST BE PERFORMED TO PROTECT THEM i AGAINST CHEMICAL ATTACK, SCC DUE TO LUBRICANTS IS NOT A CONCERN.
. THE EXTERNAL ENVIRONMENT (AIR) IS NOT EXPECTED TO CONTAIN SUFFICIENT ATMOSPHERIC CONTAMINANTS TO
, MAKE THIS ARDM PLAUSlBLE IN TYPICAL CARBON STEELS 3
AND BOLTING MATERIALS. THE LOW YlELD STRENGTHS OF THESE MATERIALS MAKES THEM LESS SUSCEPTIBLE TO THE ARDM.
{ ,_
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7
", ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT l EXPOSED TO THE PROCESS FL.UID WHICH MAKES THE ARDM NON-PLAUSIBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
~
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- Page 4 of 5
Compontnt Aging Manag ment Rsvisw LCM-16 Revision 4 r~
(,)/
.. i-DESCRIPTION SOURCE
- CODE-G THE ARDM IS PLAUSIBLE BECAUSE STEEL MATERIALS OF ATTACH 7 CONSTRUCTION ARE EXPOSED TO THE PROCESS FLUID DURING STAGNANT CONDITIONS. THERE ARE SEVERAL POSSIBLE EFFECTS. A UNIFORM CORROSION OF THE INTERNAL SURFACES OF THE VALVE CAUSING BODY WALL THINNING. LOCALIZED ATTACK RESULTING IN PITS AND CRACK INITIATION - MOST LIKELY AT CREVICES IN THE BODY / BONNET JOINT, STEM TO BONNET / PACKING AREA, AND AT THE VALVE SEAT AREA.
AGING MANAGEMENT RECOMMENDATIONS INCLUDE:
(1) MAINTAINING THE WATER CHEMISTRY CONTROLS WHICH MINIMlZE THE REQUIRED CONDITIONS FOR THEIR OCCURRENCE.
(2) INCLUDE THE COMPONENTS IN THE AGE RELATED DEGRADATION INSPECTION PROGRAM.
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Attachment 6 Page 5 of 5
COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: MOV May 20,1996 Group ID: 077-MOV-01 Device Type: Motor Operated Valve Vendor: Marpac Model Number: 1/2-SS-B325 Material:
Internal Environment:
External Environment:
Function (s): Maintain System Pressure Boundary Integrity Other Parameters:
List of Grouped Components:
1MOV5415AVLV RE Low Range Sample PP Suction 2MOV5415AVLV RE Low Range Sample PP Suction 1
l WinWbrd File RM3MOV01 DOC O
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Robion 1)
SYSTEM NUMBER- 077/079 SYSTEM NAME- Area & Process Radiation Monitoring EQUIPMENTID: NA GROUPID: 077-MOV-01 Date: May20,1996 Seldect to :
Set ><;roup ID - Seldomponent/Name Manufacturer Modet Neuber - Material Pasuve latended Fametion(s) fAMR5 (Replacement Pge) (Source) . (Searee) (Souru) . (Searte) 1 : (Y er N) -
077-MOV41A BODY ASV END MARPAC t/2-SS-B3254-EX- FORGED MAINTAIN FRESSURE BOUNDARY y ADAFTORS OS STAINLESS STEEL INTEGRTW (12284410 Section (12284419 Section (12284418 Appendix (CISR)
(NONE) 6 pp.43-52) 6 pp. 43-52) pp. 27-34)
STEM MARPAC 1/2-SS-B3254-EX- STAINLESS STEEL MAINTAIN PRESSLRE BOUNDARY y 077-MOV4iB 98 (316) INTEGRTIY (12284-010 Section (12284410 Section (12284419 Appendix (CLSR)
(NONE) ,
6 pp. 43-52) 6 pp. 43-52) pp. 27-34)
BOLTS / NUTS MARPAC I/2-SS-R3254-EX- CARBON STEEL MAINTAIN PRESSURE BOUNDARY y 077-MOV-01C 98 GR8 INTEGRTW (12284-010 Section (12284410 Section (12284-010 Appendix (CLSR) ,
(NONE) 6 pp.43-52) 6 pp 43-52) pp. 27-34) 077-MOV-01D BALL AND SEAT MARPAC 1/2-SS-R325J-EX- N/A NONE. NO LR INTENDED FUNCTION. N 08 LNNENT IN LR SCOPE FOR PRESSURE BOUNDARY ONLY.
(NONE) (12284410 Section (12284416 S$ tion (N/A) (CLSR) 6 pp.43-52) 6 pp. 43-52) a Page1of1
A ARDM MATRIX (Revision 1)
O System:
Equipment Type:
Area & Process Radiation Monitoring (077/079)
VALVE Attachment 5 Page1of1 Device Type: MOV May 20,1996 Group ID: 077-MOV-01 ARDM 077 077- 077 MOV- MOV- MOV-OIA OlB OIC Body Stem Bolt / Nut Cavitation Erosion 02 02 19 l Corrosion Fatigue 12 12 12 i
l Crevice Corrosion 06 05 19 l Erosion Corrosion 21 21 19
! Fatigue 12 12 12 i Fouling 15 15 19 Galvanic Corrosion 07 07 07 GeneralCorrosion 01.3 01.3 19 l
Ilydrogen Damage 03 03 19 Intergranular Attack 22 22 01.1 MIC 15 15 19 Particulate Wear 17 19 19 Erosion l
\ Pitting 06 06 19
{d Radiation Damage Rubber Degradation 01.3 01.3 01.3 013 01.1 01.1 Selective Leaching 01.3 01.3 01.1 l Suess 18 18 01.1 Corrosion Cracking Stress Relaxation 04 04 04 Thermal Damage 01.3 01.3 01.1 Hermal 04 04 04 Embrittlement l Wear 16 20 16 Wr1 Word Fde RM5MOV01 DOC
Compontnt Aging M:nagIm:nt Rsvi:w LCM-16 l Revision 4 Matrix Code List (Revision il SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: MOV EQUIPMENT TYPE: VALVE GROUP ID: 077-MOV-01 Date: 5/21/96 LCODEI (DESCRIPTION $ JSOURCE) 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.1 CARBON STEEL 01.3 STAINLESS STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID IS NOT THE TYPE NORMALLY ASSOCIATED WITH THIS ARDM.
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Compan:nt Aging Mtn:gtm:nt Rsvi;w LCM-16 Revision 4
' CODE iDESCRIPT'ON4 l ESOURCEl 03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN ES-014 THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE FONTANA PROCESS FLUID DOES NOT CREATE THE REQUIRED 60738 SH2 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT 60722 SH1 l GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS CH-1-100 i NOT EXPECTED TO CONTAIN CONCENTRATIONS OF NP-5769 ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THIS AVNER j l ARDM TO BE PLAUSIBLE. ASM I MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTHS OF 316 AND TYPICAL FORGED STAINLESS STEELS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM PLAUSlBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS q SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS m V REQUIRE MOISTURE AND. TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120 F, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYIN.G EFFECTS OF WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUStBLE.
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Attachment 6 Page 2 of 5
Componsnt Aging Mantgtmint Rsvisw LCM-16 Revision 4 O 1060t 16ESe,B,uONt 1S6oROE; 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 PROCESS FLUID (AIR WITH SOME MOISTURE) DOES NOT ATTACH 7 PERPETUATE THE ARDM. MOST OF THE MOISTURE IS O/l-35 FILTERED OUT OF THE PROCESS FLUID. THE CARBON STEEL ES-014 BOLTS AND NUTS ARE IN CONTACT WITH THE STAINLESS 12284-010 STEEL BODY AND END FITTINGS, BUT THE GENERAL LACK OF ELECTROLYTE TO COMPLETE A GALVANIC CIRCUlT MAKES O THIS ARDM NOT PLAUSIBLE.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND 12284-010 TEMPERATURES ARE LOW AND RELATIVELY STEADY MAKING THIS ARDM NOT PLAUSlBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY (MOST OF WHICH IS .
FILTERED FROM THE PROCESS FLUID) FROM THE VENT GASES, MICROBES AND AIRBORNE PARTICLES. PLANT EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION.
16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSlBLE ARDM SINCE THE 12284-010 SUBCOMPONENTS ARE DESIGNED TO ELIMINATE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUBCOMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUBCOMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
Attachment 6 Page 3 of 5 i
Compontnt Aging Managtmsnt Rsvisw LCM-16 Revision 4 ICDDE$ y[ , g g;[6ESCN@dN!? 2SOURCEj l
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738SH.2 THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT :
LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT l MATERIALS. FILTRATION OF AIR ON THE SAMPLE l CONDITIONING SKID PREVENT SIGNIFICANT EFFECT FROM THIS AGING MECHANISM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 l TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 12284-010 1 THIS ARDM IS NOT PLAUSIBLE SINCE THE SYSTEM IS NOT 60738 SH.2 l HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF ES-014 ;
WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS AVNER l lNTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN FONTANA CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS 60722 SH.1 ,
WHICH WOULD CAUSE THE ARDM TO BE PLAUSlBLE IN 316 ASM AND FORGED STAINLESS STEELS. THE LOW YlELD NP-5461 STRENGTH OF THESE MATERIALS MAKE THEM LESS CH-1-100 ;
SUSCEPTIBLE TO THE ARDM. NP-5769 1 THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT CONTAMINANTS OR PRESSURE TO MAKE THIS ,
ARDM PLAUSlBLE. MOLY DISULFIDE LUBRICANTS ARE l PERMITTED BY PROCEDURE TO BE USED ON NON- l l RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY l DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120 F, NORMAL AMBIENT TEMPERATURES ,
IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUBCOMPONENTS TYPICALLY ARE NOT EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSlBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
lO Attachment 6 Page 4 of 5
._ _.._. _ .m . _ . . - . _ - _ _ _ . _ _ . . _ _ . . . _ _ . _ _ _ -. _ __ .- _ ._ .. _ _._
Componsnt Aging MInagsmant Revisw LCM-16 Revision 4
'^ '
[ CODE! <
lDENCRIPTION ! ,
~' SOURCE 3 20 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 lNTENDED FUNCTION. VALVE OPERATION RESULTS IN 12284-010 STEM / PACKING CONTACT IN RELATIVE MOTION AND POTENTIALLY ABRASIVE WEAR. BALL VALVE DESIGN RESULTS IN MINIMAL STEM WEAR. WEAR OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS.
21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 NOT PERPETUATE THE ARDM.
l f
l 22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 l AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A 60738 SH.2 LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS VOL-13 REMOVED BY FILTRATION, FLOW FROM SYSTEMS INTO THE ES-014 PLANT VENT IS NOT EXPECTED TO CONTAIN AVNER CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS FONTANA WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 316 60722 SH.1 l p AND FORGED STAINLESS STEELS. ASM v- . _NP.-5461 THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN CH-1-100 SUFFICIENT CONTAMINANTS OR PRESSURE TO MAKE THIS NP-5769 ARDM PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS AMS. HOWEVER, MOLY l DISULFIDE LUBRICANTS REQUIRE MOISTURE AND l TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN
! SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120 F, NORMAL AMBIENT TEMPERATURES ,
IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYING EFFECTS OF WARMER TEMPERATURES. HYDROGEN l DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A l CONCERN.
4 iO Attachment 6 Page 5 of 5
i COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
O System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of1 ,
Device Type: MOV May 21,1996 l Group ID: 077-MOV-02 l Device Type: Motor Operated Valve l Vendor: Circle Seal Model Number: 9562T-4CC l Material:
Internal Environment: j External Environment: l Function (s): Maintain System Pressure Boundary integrity Other Parameters:
l l
l l
List of Grouped Components:
1MOV5415BVLV RE High Range Sample PP Suction
~
2MOV5415BVLV ~ ~RE High Range Sample PP Suction l
l WinWord Fde RM3MOV02 DOC O
ATTACHMENT 4,5UBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision I)
SYSTEM NUMBER: 077/079 SYSTEM NAME Area & Process Radiation Monitoring GROUPID: 077-MOV-02 Date: May21,1996 EQUIPMENTID: NA l
. Sehket W Sub-Group ID Sub-Component /Name . Mansfacterer .. ModeI Nember Material _ : Passive 1stended Fuee6ee(s) - .AMR-(Replacement Pge) - .(Source)- (Searce) - (Source) (Source) ' . (Y or N) 077-RfOV-02A BODY AND PLUG CIRCLE SEAL 9562T-4CC STAINLESS STEEL MAISTAIN PRESSURE EDUSDARY y INTEGRITY (NONE) (12284-010 Section (12284-410 Sectwo (12284-010 Section 6 (CLSR) 6 pp. 43-52) 6 pp.43-52) pp. 43-52, LCM Flie C-96-804) ,
Page1of1
l i
1 ARDM MATRIX (Revision 1) l System: Ares & Process Radiation Monitoring (077/079) Attachment 5 )
l Equipment Type: VALVE Page1of1 Device Type: MOV April 15,1996 Group ID: 077-MOV-02 ARDM 077-MOV. ,
02A Body i Cavitation Erosion 02 l Corrosion Fatigue 12 j Crevice Corrosion 06 l Erosion Corrosion 21 Fatigue 12 I
Fouling 15 Galvanic Corrosion 07 GeneralCorrosion 01.3 Hydrogen Damage 03 Intergranular Attack 22 MIC 15 Particulate Wear 17 Erosion p)
(
Pitting Radiation Damage _
06 01.3 _ . _ . . . _ _ _ .i Rubber Degradation 01:3 Selective Leaching 01.3 Suess 18 Corrosion Cracking Stress Relaxation 04 Thermal Damage 01.3 Thermal 04 Embrittlement Wear 20 WinWurd File RM5MOVD2 DOC v
Comp:n:nt Aging Managsment Review LCM-16 Revision 4 Matrix Code List (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: MOV EQUIPMENT TYPE: VALVE GROUP ID: 077-MOV-02 Date: 5/21/96
~
CODE- 2 DESCRIPTIONI. ISOURCEi 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM:
01.3 STAINLESS STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESE Fl UID IS NOT THE TYPE NORMALLY ASSOCIATED WITH THIS ARDM.
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 HYDROGEN DAMAGE REQUIRES SURFACE CORROSION VOL-13 p/
(_
WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN THAT ENTERS T.HE GRAIN STRUCTURE OF THE METAL. THE FONTANA 60738 SH2 PROCESS FLUID DOES NOT CREATE THE REQUIRED 60722 SH1 I CORROSION SITES. THE PROCESS FLUID IS PLANT VENT LCM C-96-004 GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS AVNER NOT EXPECTED TO CONTAIN CONCENTRATIONS OF ASM ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THIS ,
ARDM TO BE PLAUSIBLE.
MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW YlELD STRENGTHS OF 300 GERIES STAINLESS STEELS ARE ,
BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN CRACKING.
04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUSIBLE.
- O Attachment 6 Page 1 of 3 i
Comp:nznt Aging Minigtmznt R:visw LCM-16 Revision 4
[ CODE) 7 iDE8 @ * ,
% ' iSOUR'CET 06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER O/l-35 O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 -
, MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402504 RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS 4 INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l 35. THE LIMITED AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS.
07 MATERIAL SELECTION / SEPARATION AND ENVIRONMENT DO ATTACH 7 NOT PERPETUATE THE ARDM. THE VALVE IS MADE OF O/l-35 MATERIALS WITH LOW POTENTIAL DIFFERENCES AND THE 12284-010 ONLY MOISTURE RESULTS FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS REMOVED BY
/~~N FILTRATION.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH 7 PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND 12284-010 TEMPERATURES ARE LOW AND RELATIVELY STEADY MAKING THIS ARDM NOT PLAUSIBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 l FUNCTION. FOULING AND MIC MAY OCCUR TO A LIMITED O/l-35 EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT 12284-010 GASES, MICROBES AND AIRBORNE PARTICLES. PLANT ,
EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS l SYSTEM. HOWEVER, FOULING DOES NOT AFFECT THE !
PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS REMOVED BY FILTRATION.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738SH.2 THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE '
CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM O THIS AGING MECHANISM.
Attachment 6 Page 2 of 3
! Compon2nt Aging Mansg2 mint Rsvi:w LCM-16 Revision 4 (CODE? LDESCRIPT10NI TSOURCE) l 18 STRESSES AND ENVIRONMENT 00 NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 '
- TENSILE STRESSES AND AN APPROPRIATE ENVIRONMENT. 12284-010 l THIS ARDM IS NOT PLAUSIBLE SIM,E THE SYSTEM IS NOT LCM C-96-004 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS 60738 SH.2 l
FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF VOL-13 l WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS AVNER INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN FONTANA 60722 SH.1 CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 300 ASM l SERIES STAINLESS STEELS. THE LOW YlELD STRENGTH OF NP-5461 l THESE MATERIALS MAKE THEM LESS SUSCEPTIBLE TO THE ARDM.
20 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7
! INTENDED FUNCTION. VALVE OPERATION RESULTS IN 12284-010 STEM / PACKING CONTACT IN RELATIVE MOTION AND LCM C-96-004 POTENTIALLY ABRASlVE WEAR. VALVE DESIGN RESULTS IN MINIMAL STEM WEAR. WEAR OF PACKING WILL NOT RESULT IN LEAKAGE OF PRESSURE BOUNDARY SUBCOMPONENTS.
> O- _- . _ _ .
ATTACH 7 21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO l NOT PERPETUATE THE ARDM.
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 l ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A LCM C-96-004 LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS 60738 SH.2 REMOVED BY FILTRATION. FLOW FROM SYSTEMS INTO THE VOL-13 PLANT VENT IS NOT EXPECTED TO CONTAIN AVNER CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS FONTANA WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 300 60722 SH.1 SERIES STAINLESS STEELS. ASM I
l i
O l Attachment 6 Page 3 of 3
1 g COMPONENT GROUPING
SUMMARY
SHEET (Revision 1)
System: Area & Process Radiation Monitoring (077/079) Attachment 3 Equipment Type: VALVE Page 1 of 1 Device Type: SV April 15,1996 Group ID: 077-SV-01 Device Type: Solenoid Valve Vendor: ASCO Model Number: HB-0262-A153, HB-8262-A231, HB-8211-C87, HTX-82 li-B-30 Material:
Internal Environment:
External Environment:
Function (s): Maintain System Pressure Boundary integrity Other Parameters:
List of Grouped Components:
1SV5415A 1 RE Filter Outlet Isolation SV 1SV54158 1 RE Filter Outlet Isolation SV 1SV5416A 1 RE Filter Outlet Isolation SV 1SV54168 1 RE Filter Outlet isolation SV 1SV5417A 1 RE Filter Outlet Isolation SV 1SV5417B 1 RE Filter Outlet isolation SV iSV5418A 1 RE Sample Detection Skid inlet SV 1SV5418B 1 RE Sample Detection Skid Isolation SV 1SV5419A 1 RE Sample Detection Skid Purge SV iSV54198 1 RE Sample Detection Skid Purge SV 2SV5415A 2 RE Filter Outlet isolation SV 2SV5415B 2 RE Filter Outlet isolation SV 2SV5416A 2 RE Filter Outlet isolation SV 2SV5416B 2 RE Filter Outlet isolation SV 2SV5417A 2 RE Filter Outlet isolation SV 2SV5417B 2 RE Filter Outlet isolation SV 2SV5418A 2 RE Sample Detection Skid inlet SV 2SV5418B 2 RE Sample Detection Skid inlet SV 2SV5419A 2 RE Sample Detection Skid Purge SV 2SV5419B 2 RE Sample Detection Skid Purge SV wnwwo re.Russvoi ooc l0
O O O ATTACHMENT 4, SUBCOMPONENT/SUB-GROUP IDENTIFICATION (Revision 1)
SYSTEM NUMBER: 077/079 SYSTEM NAME: Area & Process Radiation Monitoring GROUPID: 077-SV-01 Date: May21,1996 EQUIPMENTID: NA Sahiett em; Sub-GroupID SACompoecet/Name - Masefacturer ; . ModeINomber 7 - Maserial -' Passivelesended Fencelse(s) E JAMR3
- (Replacemeet Pge) - e (Source) . (Seerce) : (Source) (Seerte) : (Y se N) -
077-SV41A BODY ASCO 8211,8262 STAINLESS STEEL MAINTAIN FRES$URE BOUNDARY Y (300 SERIES) ISTEGRITY (12284-010 Section (12284410 Section (12284410 Appendix (CLSR)
(NONE) 6 pp. 25-35,43-52) 6 pp.25-35,43-52) pp. I8-26) 077-SV-01B CORE "IUBE ASCO 821I,8262 STAINLESS STEEL MAINTAIN FRESSURE BOUNDARY Y (305) INIIGRITY (12284410 Section (12284410 Section (12284410 Appendix (CLSR)
(NONE) 6 pp. 25-35,43-52) 6 pp. 25-35,43-52) pp. I8-26)
ASCO 8211,8262 ALLOY /SS STEEL MAINTAIN FRESSURE BOUNDARY y 077-SV4tC BOLTS INTEGRITY (NONE) (12284410 Section (12284410 Section (NONE) (CISR) 6 pp.25-35,43-52) 6 pp.2545,43-52)
INTERNAIS ASCO 8211,8262 STAINLESS STEEL NONE. NO LR INITNDED FUNCTION- N 077-SV-0lD COMPONENT IN LR SCOPE FOR PRESSURE BOUNDARY ONLY.
f12284-010 Secti on (12284-010 Section (12284410 Appendix (CISR)
(NONE) 6 pp. 25-35. 43-52) 6 pp. 25-35,43-52) pp. I8-26)
Page1of1
ARDM MATRIX (Revision 1)
System: Ares & Process Radiation Monitoring (077/079) Attachment 5 Equipment Type: VALVE Page1ofI Device Type: SV May 21,1996 Group ID: 077-SV-61 ARDM 077-SV- 077-SV- 077-SV-OlA OlB OIC Body Core Tube Bolts Cavitation Erosion 02 02 19 Corrosion Fetigue 12 12 12 Crevice Corrosion 06 06 19 Erosion Corrosion 21 21 19 Fatigue 12 12 12 Fouling 15 15 19 Galvanic Corrosion 07 07 07 GeneralCorrosion 01.3 01.3 19 flydrogen Damage 03 03 19 Intergranular Attack 22 22 01.3 MIC 15 15 19 Particulate Wear 17 17 19 Erosion Pitting 06 06 19 Radiation Damage 01.3 01.3 01.3
'N Rubber Degradation 01.3 01.3 01.3 Selective Leaching 01.3 01:3 01.3 Stress 18 18 18 Corrosion Cracking Stress Relaxation 04 04 04 Thermal Damage 01.3 01.3 01.3 Thermal 04 04 04 j Embrittlement Wear 16 20 16 i
WinWord File RMSSV01 doc O
l i
I
i l l
Compon:nt Aging ManagtmInt Revisw LCM-16 Revision 4 O M ti Ceo Li t<Revi i ,i SYSTEM NUMBER: 077/079 SYSTEM NAME: AREA & PROCESS RADIATION MONITORING DEVICE TYPE: SV EQUIPMENT TYPE: VALVE l
l GROUP ID: 077-SV-01 Date: 5/21/96 i l
? CODE .' DESCRIPTION . - SOORCEl j 01 MATERIAL IS NOT APPLICABLE TO THE ARDM. MATERIAL OF ATTACH 7 j CONSTRUCTION IS NOT SUSCEPTIBLE TO THIS ARDM: l l 01.3 STAINLESS STEEL / ALLOY STEEL 02 PROCESS FLUID TYPE DOES NOT PERPETUATE THE ARDM. ATTACH 7 THE PROCESS FLUID (AIR) IS NOT THE TYPE NORMALLY ASSOCIATED 'NITH THIS ARDM. l i
lO l
i l
i t
i i
l l
l 1 ,
Attachment 6 Page 1 of 5
_. ._m . _ _ _ _ _ ___ _ . ___ .. __ -_ ___ ___ _ _ . _
Compontnt Aging Managtmant Rsvisw LCM-16 Revision 4
__ CODE ~ " DESCRIPTION lSOURCE4 '
03 PROCESS FLUID DOES NOT PERPETUATE THE ARDM. ATTACH 7 l HYDROGEN DAMAGE REQUIRES SURFACE CORROSlON VOL-1 l WHICH CREATES A SOURCE OF MONO-ATOMIC HYDROGEN VOL-13 THAT ENTERS THE GRAIN STRUCTURE OF THE METAL. THE FONTANA -
PROCESS FLUID DOES NOT CREATE THE REQUIRED 60738 SH2 CORROSION SITES. THE PROCESS FLUID IS PLANT VENT 60722 SH1 GASES. FLOW FROM SYSTEMS INTO THE PLANT VENT IS CH-1-100 NOT EXPECTED TO CONTAIN CONCENTRATIONS OF NP-5769 ATMOSPHERIC CONTAMINANTS WHICH WOULD CAUSE THIS AVNER l ARDM TO BE PLAUSIBLE. ASM )
l MATERIALS DO NOT PERPETUATE THE ARDM. THE LOW :
l YlELD STRENGTHS OF 300 SERIES STAINLESS STEELS AND i TYPICAL BOLTING MATERIALS ARE BELOW THE THRESHOLD OF 120 KSI TYPICALLY NECESSARY FOR HYDROGEN
, CRACKING.
l l l THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN l l SUFFICIENT HYDROGEN OR PRESSURE TO MAKE THIS ARDM l PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED l BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS.RMS.. HOWEVER, MOLY DISULFIDE.LUBRIQANTS f ,
l REQUIRE MOISTURE AND TEMPERATURE (> 150*F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120*F, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYING EFFECTS OF WARMER l
TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
l 04 PROCESS FLUID TEMPERATURE DOES NOT PERPETUATE THE ATTACH 7 '
l ARDM. OPERATING TEMPERATURES LESS THAN 500 F ES-014 ENSURE THIS ARDM IS NOT PLAUStBLE. .
i l l
l l
!O Attachment 6 Page 2 of 5
~. -.- . - _ . . .-- - - - - - . . . - . -
i Compon:nt Aging Mantgsmant Rsvisw LCM-16 Revision 4 :
'CODET + , IDESCRIPTIONE ,
- ISOURCEf~!
06 PROCESS FLUID AND MOISTURE DO NOT PERPETUATE THE ATTACH 7 l ARDM. INPO OPERATIONS AND MAINTENANCE REMINDER- O/l-35 ;
O&MR-132 DESCRIBES OPERATIONAL FAILURES OF RAD INPO O&MR-132 MONITORING SYSTEMS DUE TO EXCESS MOISTURE. CCNPP MO 2199402.504 ;
RECENT HISTORY SHOWS ONE CASE WHERE WATER WAS INTRODUCED TO THE SYSTEM DUE TO BLOWDOWN TANK ,
VENT BEING ALIGNED TO THE MAIN PLANT VENT (MO i 2199402504). HOWEVER, PER INPUT FROM THE SYSTEM '
ENGINEER THIS IS NOT A COMMON OCCURRENCE. THE SYSTEM HAS NOT EXPERIENCED THE MOISTURE RELATED '
PROBLEMS DESCRIBED IN O&MR-132. SYSTEM OPERATION IS ASSURED IN ACCORDANCE WITH O/l-35. THE LIMITED l AMOUNT OF MOISTURE PREVENTS SIGNIFICANT EFFECT FROM THESE AGING MECHANISMS. !
07 MATERIAL SELECTION AND ENVIRONMENT DO NOT ATTACH 7 PERPETUATE THE ARDM. THE ALLOY STEEL BOLTS AND ES-014 NUTS ARE IN CONTACT WITH THE STAINLESS STEEL BODY, 12284-010 ,
BUT THE GENERAL LACK OF ELECTROLYTE TO COMPLETE A ['
GALVANIC CIRCUlT MAKES THIS ARDM NOT PLAUSIBLE.
12 SERVICE LOADING AMPLITUDES / FREQUENCIES DO NOT ATTACH .J. . . . _
PERPETUATE THE ARDM. THE SYSTEM PRESSURES AND 12284-010 TEMPERATURES ARE LOW AND RELATIVELY STEADY MAKING THIS ARDM NOT PLAUSIBLE.
15 ARDMS DO NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 FUNCTION. THE FOLLOWING RECOGNIZES THAT PARTS ON O/l-35 THE CORE SIDE OF THE DIAPHRAGM ARE ONLY SUBJECTED 12284-010 TO PROCESS FLUID ENVIRONMENTS IF A LEAK DEVELOPS IN THE NON-PRESSURE BOUNDARY DIAPHRAGM. .
FOULING AND MIC MAY OCCUR TO A LIMITED EXTENT DUE TO CONDENSED HUMIDITY FROM THE VENT GASES, MICROBES AND AIRBORNE PARTICLES. PLANT EXPERIENCE HAS SHOWN FOULING HAS OCCURRED IN THIS SYSTEM. l HOWEVER, FOULING DOES NOT AFFECT THE PRESSURE BOUNDARY FUNCTION. MIC ACTIVITY WILL NOT BE SIGNIFICANT TO PRESSURE BOUNDARY FUNCTION DUE TO LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS REMOVED BY FILTRATION.
l O
Attachment 6 Page 3 of 5
Componsnt Aging Managsment Rsvisw LCM-16 Revision 4 lCODEI
[ DESCRIPTION _ y [SDURCE 16 COMPONENT DESIGN DOES NOT PERPETUATE THE ARDM. ATTACH 7 WEAR IS NOT A PLAUSlBLE ARDM SINCE THE SUB- 12284-010 COMPONENTS ARE DESIGNED TO MINIMlZE ANY RELATIVE MOTION BETWEEN THE PARTS. THE SUB-COMPONENTS ARE DESIGNED SO THEY ARE NOT ADJACENT TO OTHER SUB-COMPONENTS OR THEY ARE RESTRAINED SUCH THAT THERE IS NO RELATIVE MOTION.
17 PARTICULATE WEAR EROSION IS NOT SIGNIFICANT. THE AIR ATTACH 7 VELOCITY IS SUFFICIENT TO CARRY PARTICLES, HOWEVER, 60738 SH.2 THE LIMITED SOURCE OF AIRBORNE PARTICLES WILL NOT 12284-010 LEAD TO SIGNIFICANT EROSION OF THE EROSION RESISTANT MATERIALS. FILTRATION OF AIR ON THE SAMPLE CONDITIONING SKID PREVENTS SIGNIFICANT EFFECT FROM THIS AGING MECHANISM. PARTS ON THE CORE SIDE OF THE DIAPHRAGM ARE ONLY SUBJECTED TO PROCESS FLUID ENVIRONMENTS IF A LEAK DEVELOPS IN THE NON-PRESSURE BOUNDARY DIAPHRAGM.
18 STRESSES AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL, O/l-35 O TENSILE ST.RESSES AND- AN APPROPRIATE ENVIRONMENT.
THIS ARDM IS NOT PLAUSlBLE SINCE THE SYSTEM IS NOT 12284-010 60738 SH.2 HIGHLY STRESSED AND THE ONLY MOISTURE RESULTS VOL-13 FROM A LIMITED AMOUNT OF CONDENSATION, MOST OF ES-014 WHICH IS REMOVED BY FILTRATION. FLOW FROM SYSTEMS AVNER INTO THE PLANT VENT IS NOT EXPECTED TO CONTAIN FONTANA CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS 60722 SH.1 WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE !N 300 ASM SERIES STAINLESS STEELS AND TYPICAL BOLTING NP-5461 MATERIALS. THE LOW YlELD STRENGTHS OF THESE CH-1-100 ,
MATERIALS MAKE THEM LESS SUSCEPTIBLE TO THE ARDM. NP-5769 THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN SUFFICIENT CONTAMINANTS OR PRESSURE TO MAKE THIS ARDM PLAUStBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON-RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUlHE MOISTURE AND TEMPERATURE (> 150*F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120 F, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, HYDROGEN O DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
Attachment 6 Page 4 of 5
Compontnt Aging Mrnagtmtnt Rsvizw . LCM-16 Revision 4
' ' [SOORCE) ,
LCODEj ,
' DESCRIPTIOf 19 COMPONENT ENVIRONMENT DOES NOT PERPETUATE THE ATTACH 7 ARDM. THE SUB-COMPONENTS TYPICALLY ARE NOT l EXPOSED TO THE PROCESS FLUID WHICH MAKES THE ARDM NON-PLAUSIBLE. THE EXTERNAL ENVIRONMENT IS NOT NORMALLY HARSH.
l 20 WEAR DOES NOT SIGNIFICANTLY AFFECT COMPONENT ATTACH 7 INTENDED FUNCTION. VALVE OPERATION RESULTS IN CORE 12284-010 AND CORE TUBE RELATIVE MOTION AND POTENTIALLY ABRASIVE WEAR. HOWEVER, SOLENOID VALVE DESIGN l
MAGNETICALLY CENTERS THE CORE IN THE CORE TUBE,
, RESULTING IN INSIGNIFICANT WEAR. .
! 21 PROCESS FLUID (AIR) AND MATERIAL SELECTION (SS) DO ATTACH 7 l NOT PERPETUATE THE ARDM. .
22 MATERIAL AND ENVIRONMENT DO NOT PERPETUATE THE ATTACH 7 ARDM. THIS ARDM REQUIRES A SUSCEPTIBLE MATERIAL O/l-35 AND AN APPROPRIATE ENVIRONMENT. THIS ARDM IS NOT 12284-010 i PLAUSIBLE SINCE THE ONLY MOISTURE RESULTS FROM A' 60738 SH.2 LIMITED AMOUNT OF CONDENSATION, MOST OF WHICH IS VOL-13
--- REMOVED BY FILTRATION. FLOW FROM SYSTEMS INTO THE ES-014 PLANT VENT IS NOT EXPECTED TO CONTAIN. AVNER CONCENTRATIONS OF ATMOSPHERIC CONTAMINANTS FONTANA WHICH WOULD CAUSE THE ARDM TO BE PLAUSIBLE IN 300 60722 SH.1 SERIES STAINLESS STEELS. ASM NP-5461 THE EXTERNAL ENVIRONMENT (AIR) DOES NOT CONTAIN CH-1-100 SUFFICIENT CONTAMINANTS OR PRESSURE TO MAKE THIS NP-5769 ARDM PLAUSIBLE. MOLY DISULFIDE LUBRICANTS ARE PERMITTED BY PROCEDURE TO BE USED ON NON- f RESTRICTED SYSTEMS SUCH AS RMS. HOWEVER, MOLY DISULFIDE LUBRICANTS REQUIRE MOISTURE AND TEMPERATURE (> 150 F) TO DECOMPOSE INTO HYDROGEN SULFIDE. GIVEN MAXIMUM WRGM SKID DESIGN TEMPERATURE OF 120 F, NORMAL AMBIENT TEMPERATURES IN THE MAIN PLANT EXHAUST ROOMS OF 110 F, AND DRYING EFFECTS OF WARMER TEMPERATURES, HYDROGEN DAMAGE DUE TO MOLY DISULFIDE LUBRICANTS IS NOT A CONCERN.
l O
Attachment 6 Page 5 of 5