ML12088A481
| ML12088A481 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/28/2012 |
| From: | Entergy Nuclear Operations |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| Shared Package | |
| ML12088A474 | List: |
| References | |
| RAS 22105, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR | |
| Download: ML12088A481 (192) | |
Text
ENT00122B Submitted: March 28, 2012 Table A.1 Gall Report for NPAR Reports Page 968 Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL Eft ect ot Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item PS S&T Req.,
13 PSTS Req.
Loss of rod drive mechanism cooling Not stated None stated PS S&T Req.,
Improve leakage monitoring [2]
5-13 14 capacity leading to inoperable CRDM or PSTS Req.
rod drops.
Loss of rod drive mechanism cooling Not stated None stated PS S&T Req.,
Improve leakage monitoring [2]
5-13 15 capacity leading to inoperable CRDM or PSTS Req.
rod drops.
Loss of rod drive mechanism cooling Not stated None stated PS S&T Req.,
Improve leakage monitoring [2]
5-13 16 capacity leading to inoperable CRDM or PSTS Req.
rod drops.
Clad cracking and wash out of the poison. Occasional None stated PS S&T Req.,
Rod exposure tracking; Increased 5-14 17 PS TS Req.
visual inspection [2]
Cracking of the tube wall.
Rare None stated PSS&T Req.,
Component design modification [2]
5-14 18 PS TS Req.
Cracking of the guide causing rod drops.
Rare None stated PSS&T Req.,
None given 5-14 19 PS TS Req.
Housing cracks causing primary coolant Rare None stated PS S&T Req.,
Improved leakage monitoring; 5-14 20 leakage (SBLOCA) and jamming of the PS TS Req.
Improved visual inspection [2]
drive mechanism.
PSS&TReq.,
21 PS TS Req.
Loss of valve function and primary coolant Occasional None stated PS S&T Req.,
Improved leakage monitoring; 5-14 22 leakage.
PSTS Req.
Improved visual inspection [2]
Failure of these sub-components will lead Rare None stated PS S&T Req.,
None stated 5-14 23 to dropping or locking of the control rod PSTS Req.
assembly.
Cracking of the leadscrew will cause a Rare None stated PS S&T Req.,
Periodic wear measurements [2]
5-14 24 dropped or immovable control rod.
PSTS Req.
PS S&T Req.,
25 PSTSReq.
PS S&T Req.,
26 PS TS Req.
PS S&T Req.,
27 PS TS Req.
PSS&T Req.,
28 PS TS Req.
PSS&TReq.,
29 PSTS Req.
PSS&T Req.,
30 PS TS Req.
Table A.1 Gall Report for NPAR Reports Page 97A Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL 1St e/C b
M t. I M
f t
ARD h'
ARD ff ts tem :iysem Structur omp Su component a erla s anu ac urer mec amsm eec 31 Babcock & Wilcox CRDM Cooling Centrifugal Pumps Not stated B&W CORR/BA Loss of material (B&W) Control Rod System Drive System 32 Babcock & Wilcox CRDM Cooling Heat Exchangers Not stated B&W CORR/BA Loss of material (B&W) Control Rod System Drive System 33 Babcock & Wilcox CRDM Cooling Surge Tank Not stated B&W CORR/BA Loss of material (B&W) Control Rod System Drive System Document: NUREG/CR-5807, Improvements in Motor Operated Gate Valve Designs and Prediction Models for Nuclear Power Plant Systems Reviewed by:
Ken E. Kasza, ANL Item System Structure/Comp Subcomponent Materials Manufacturer h
ARD mec anism AR D effects 1 Various Motor operated gate This report does not valves provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Document: NUREG/CR-5848, Recordkeeping Needs to Mitigate the Impact of Aging Degradation Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Multiple Multiple This report does not provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Document: NUREG/CR-5870, Results of LWR Snubber Aging Research Reviewed by:
Steve U. Choi, ANL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 PWR and BWR Mechanical Lead screw, thrust Not stated Not stated VIBR (high-Loosening, wear cooling and snubbers bearing, capstan amplitude) emergency cooling spring, pins, and systems attachment lugs 2 PWR and BWR Mechanical Fasteners, clevis Not stated Not stated VIBR (Iow-Loosening, wear cooling and snubbers pins, and amplitude) emergency cooling attachments systems 3 PWR and BWR Mechanical Lubricants Not stated Not stated ELE-TEMP Chemical or physical cooling and snubbers degradation emergency cooling systems 4 PWR and BWR Mechanical capstan and Not stated Not stated CORR Loss of material; cooling and snubbers capstan spring corrosion product emergency cooling buildup systems
Table A.1 Gall Report tor NPAR Reports Page 978 Document: NUREGlCR*5783, BNL-NUREG*52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL Effect ot Aging on Component Function Contrib to Failure Rej)_orted progs Rel.progs Report Recommendations.
Page No. Item Loss of cooling leading to inoperable Rare None stated PSS&T Req.,
None stated 31 CRDM.
PSTS Req.
Loss of cooling leading to inoperable Rare None stated PS S&T Req.,
None stated 32 CRDM.
PS TS Req.
Loss of cooling leading to inoperable Rare None stated PSS&T Req.,
None stated 33 CRDM.
PSTS Req.
Document: NUREG/CR-5807, Improvements in Motor Operated Gate Valve Designs and Prediction Models for Nuclear Power Plant Systems Reviewed by:
Ken E. Kasza, ANL E
t F
b R I R
tR d ti P
ffect 0 Aging on Component unction Contri to Failure Reported progs e.progs epor ecommen a ons age N It em
- o.
1 Document: NUREG/CR-5848, Recordkeeping Needs to Mitigate the Impact of Aging Degradation Reviewed by:
Dwight R. Diercks, ANL Effect ot Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. Item 1
Document: NUREG/CR*5870, Results of LWR Snubber Aging Research Reviewed by:
Steve U. Choi, ANL Eff t t A.
C F
'b t F'I R
ed eco,glng on omponent unction Contrl 0
al ure
~ort progs RI e.progs R
rtR epo d ti ecommen a ons P age No lte m High-amplitude vibration can result in Not stated Not discussed in ASMESecXI Monitor service-life to include 17,19 1
localized fretting and wear of mating report ISTD determination of snubber failure or parts. It can also result in an increase in degradation causes, operating drag force, an increase in mechanical environment, managing snubbers in clearances, jamming, and/or an increase severe enVironments, augmented in the acceleration threshold.
surveillance, trending degradation parameters & testing. [2]
Low-amplitude vibration can lead to Not stated Not discussed in ASMESecXI Monitor service-life to include 17,19 2
loosening of fasteners and, in combination report ISTD determination of snubber failure or with the weight of the snubber, can cause degradation causes, operating wear of clevis pins and attachments, enVironment, managing snubbers in resulting in elongated attachment holes, severe enVironments, augmented and can cause internal wear.
surveillance, trending degradation parameters & testing. [2]
Solidification of lubricants increases Not stated Not discussed in ASMESecXI Monitor service-life to include 17,19 3
friction and results in an increase in drag report ISTD determination of snubber failure or force.
degradation causes, operating environment, managing snubbers in severe enVironments, augmented surveillance, trending degradation parameters & testing. [2f lntemal corrosion can lead to increasing Not stated Not discussed in ASME Sec XI Monitor service-life to include 17,19 4
drag force, jamming, and/or a decrease in report ISTD determination of snubber failure or the snubber's acceleration threshold as a degradation causes, operating result of a buildup of rust.
environment, managing snubbers in severe enVironments, augmented surveillance, trending degradation parameters & testing. [2]
Table A.1 Gall Report for NPAR Reports Page 98A Document: NUREG/CR-5870, Results of LWR Snubber Aging Research Reviewed by:
Steve U. Choi, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 5 PWR and BWR Hydraulic snubbers Seals Not stated Not stated ELE-TEMP Chemical or physical cooling and degradation emergency cooling systems 6 PWR and BWR Hydraulic snubbers Plastic hydraulic Not stated Not stated ELE-TEMP Chemical or physical cooling and reservoirs degradation emergency cooling systems 7 PWR and BWR Hydraulic snubbers Control valve Not stated Not stated CORR Loss of material; cooling and corrosion product emergency cooling buildup systems 8 PWR and BWR Hydraulic snubbers Control valve Not stated Not stated VIBR Loosening, wear cooling and emergency cooling systems 9 PWR and BWR Hydraulic snubbers Threaded fasteners, Not stated Not stated VIBR Loosening, wear cooling and clevis pins, emergency cooling attachment holes systems 10 PWRand BWR Hydraulic snubbers Hydraulic fluid Not stated Not stated VIBR Gelation cooling and emergency cooling systems Document: NUREG/CR-5944, A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry Reviewed by:
Ken E. Kasza, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Reactor flow control Check valves Hinge pinlbushings Not stated Not stated CORR;WEAR Loss of material, attrition 2 Reactor flow control Check valves Disk stud Not stated Not stated FAT; VIBR Cumulative fatigue damage 3 Reactor flow control Check valves Hinge arm Not stated Not stated FAT; VIBR Cumulative fatigue damage 4 Reactor flow control Check valves Seat Not stated Not stated CORR;ERO Loss of material 5 Reactor flow control Check valves Valve body Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 988 Document: NUREG/CR-5870, Results of LWR Snubber Aging Research Reviewed by:
Steve U. Choi, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. Item Seal leaks would result in loss of fluid Not stated Not discussed in ASMESecXI Monitor service-life to include 3,11 5
from the snubber.
report ISrD determination of snubber failure or degradation causes, operating environment, managing snubbers in severe environments, augmented surveillance, trending degradation parameters & testing. [2]
Elevated temperature can lead to Not stated Not discussed in ASME Sec XI Monitor service-life to include 3,11 6
deformation of plastic hydraulic reservoirs.
report ISrD determination of snubber failure or degradation causes, operating environment, managing snubbers in severe environments, augmented surveillance, trending degradation parameters & testing. [2]
Internal corrosion resulting in the Not stated Not discussed in ASME Sec XI Monitor service-fife to include 3,11 7
generation of corrosion products can report ISTD determination of snubber failure or cause a malfunction of the snubber degradation causes, operating control Valve.
environment, managing snubbers in severe environments, augmented surveillance, trending degradation parameters & testing. [2J Wear due to high-amplitude vibration can Not stated Not discussed in ASMESecXI Monitor service-life to include 3,12 8
result in particle generation, potentially report ISrD determination of snubber failure or affecting control valve performance.
degradation causes, operating environment, managing snubbers in severe enVironments, augmented surveillance, trending degradation parameters & testing. [2]
High-or low-amplitude vibration can result Not stated Not discussed in ASMESecXI Monitor service-life to include 3,12,J.6 9
in loosening of threaded fasteners and/or report ISTD determination of snubber failure or wear or deformation of clevis pins and degradation causes, operating attachment holes.
environment, managing snubbers in severe enVironments, augmented surveillance, trending degradation parameters & testing. [2]
Extreme high-amplitude vibration can Not stated Not discussed in ASMESecXI Monitor service-life to include 3,12,J.2 10 result in gelated, blackened hydraulic report ISTD determination of snubber failure or fluid.
degradation causes, operating environment, managing snubbers in severe environments, augmented surveillance, trending degradation parameters & testing. [2]
Document: NUREG/CR-5944, A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry RevieWed by:
Ken E. Kasza, ANL E
R ffect of Aging on Component Function Contrib to Failure Reported progs el.progs Report Recommendations Page No. Item Corrosion and wear of hinge pins and Rare ASME Working*
ASMESecXI Not stated 10,21 1
bushings can cause valve to open or Group on Check IWV close sluggishly or not move, resulting in Valves (OM 22) leakage or reduced flow.
Fatigue due to flow impact and vibration Occasional ASME Working ASMESecXI Not stated 7,17 2
can cause misalignment of valve disk and Group on Check IWV seat, resulting in leakage.
Valves (OM 22)
Fatigue due to flow impact and vibration Occasional ASME Working ASMESecXI Not stated 7,17 3
can cause misalignment of valve disk and Group on Check IWV seat, resulting in leakage.
Valves (OM 22)
Erosion and/or corrosion causes valve to Moderate ASME Working ASME Sec XI Not stated 7,21,32 4
seat improperly, resulting in minor or Group on Check IWV major fluid leakage. The impact depends Valves (OM 22) on where valve is located in plant, and can lead to important safety related events.
This degradation is prevalent in large Values.
Degradation of a body penetration, such Moderate ASME Working ASMESecXI Not stated 10 5
as packing or a valve stem, due to wear Group on Check IWB,IWV interferes with proper valve functioning Valves (OM 22) and causes possible leakage.
Table A.1 Gall Report for NPAR Reports Page 99A Document: NUREG/CR-6001, Aging Assessment of BWR Standby Uquid Control Systems Reviewed by:
Ken E. Kasza, ANL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 Standby liquid Relief valves Not delineated Not stated Not stated WEAR Attrition control in BWR 2 Standby liquid Relief valves Not delineated Not stated Not stated CQRR Loss of material; control in BWR corrosion product buildup 3 Standby liquid Relief valves Not delineated Not stated Not stated CONTAM Buildup of deposits control in BWR 4 Standby liquid Accumulators Not delineated Not stated Not stated Not stated Nitrogen blanket control in BWR pressure reduction 5 Standby liquid Pumps Not delineated Not stated Not stated Not stated Aging degradation of control in BWR packing, seals and internal valves 6 Standby liquid Instrumentation Not delineated Not stated Not stated Not stated Impaired ability to control in BWR monitor system Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I Reviewed by:
Dwight R. Diercks, ANL Item S.ystem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Air-treatment system HEPA filters Rltering media Glass fiber filter Not stated PART Increased pressure
'paper," possibly drop with organic additions 2 Air-treatment system HEPA filters Rltering media Glass fiber filter Not stated MOIST Increased pressure
'paper,' possibly drop and reduced with organic strength additions 3 Air-treatment system HEPA filters Rltering media Glass fiber filter Not stated ENVIR Physical degradation
'paper,' possibly with organic additions 4 Air-treatment system HEPA filters Frames and Aluminum and other Not stated CORR Loss of material separators metals 5 Air-treatment system HEPA filters Sealants, gaskets, Unidentified organic Not stated ELE-TEMP; ENVIR Chemical and and water repellents materials physical degradation 6 Air-treatment system Air treatment system Adsorber medium Activated charcoal Not stated WEATH Loss of capacity adsorbers (carbon) 7 Air-treatment system Air treatment system Adsorber medium Activated charcoal Not stated ENVIR Chemical and adsorbers (carbon) physical degradation
Table A.1 Gall Report for NPAR Reports Page 998 Document: NUREG/CR-6001, Aging Assessment of BWR Standby Uquid Control Systems Reviewed by:
Ken E. Kasza, ANL Effect of Aging on Component Function Contrib to Failure Rej!orted progs Rel.progs Report Recommendations Page No. Item Wear can cause valve setpoint to drift.
Moderate Not discussed in ASMESecXI Not stated 6, 13, 14, 1
Higher value results in a loss of system report IWV 23 overpressure protection; a decrease could reduce the rate of boron injection effecting reactivity control.
Improper concentrations of boric acid Occasional Not discussed in ASME Sec XI Not stated 6, 13, 14, 2
causes corrosion of valve internals and report IWV 23 reduced valve function.
Buildup of sodium pentaborate Occasional Not discussed in ASMESecXI Not stated 13,14 3
precipitates on valve internals causes report IWV Changes in valve opening characteristics and injection of borate.
loss of nitrogen pressure is caused by Not stated Not discussed in ASMESecXI Not stated 13,14 4
valve wear and failure of gas bladder.
report IWV However the accumulators would stay intact and still would pass flow in times of Critical need.
Degradation could prevent pumps from Occasional Not discussed in ASMESecXI Not stated 13,14,23 S
operating within technical specifications report IWP and change borate injection Characteristics.
Instrumentation required to monitor the Occasional Not discussed in 10CFRSO.49 Not stated 13,14 6
system, such as component status lights, report tank level sensors, temperature, pressure and flow gauges, are subject to aging but are not stated to be necessary for system operation during critical need.
Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I Reviewed by:
Dwight R. Diercks, ANL Eff t fA*
C F
- b F*I eco,g,"g on omponent unction Contrl to al ure Reported progs Rel.progs Report Recommendations Page No. tem Dust pickup increase the pressure drop Frequent ASME N509-1989; PS S&T Req.,
Monitor pressure drop across filter 4.1,5.1, 1
across the filter. Dust pickup can also ASME NS1D-RG 1.140, RG and change filter as required. [2]
6.1 reduce the effectiveness of organic 1989;NRC RG 1.S2 1.S2 materials added for strengthening and and RG 1.140 water repellency.
Moisture incorporation into the filter Frequent ASME NS09-1989; PSS&T Req.,
Not stated 4.1,7.4 2
medium causes increased pressure drop ASME NS1D-RG 1.140, RG and reduced filter strength, and structural 1989;NRC RG 1.S2 1.S2 failure of the filter can occur even under and RG 1.140 design flow rates.
Prolonged exposure to air containing Occasional ASME NS09-1989; PS S&T Req.,
Not stated 4.1 3
normal concentrations of oxygen and ASME NS1D-RG 1.140, RG oxides of nitrogen can cause 1989;NRC RG 1.52 1.52 embrittlement of the filter media material, and RG 1.140 resulting in possible leakage and loss of
. filtration.
Corrosive attack of metallic components Occasional ASME NS09-1989; PSS&TReq.,
Not stated 4.1, S.2 4
in HEPA filters exposed to aggressive ASME NS1D-RG 1.140, RG environments can cause structural failure 1989;NRC RG 1.S2 1.S2 and consequent leakage and loss of and RG 1.140 filtration.
Heat and radiation are reported to cause Occasional ASME NS09-1989; PS S&T Req.,
Not stated 4.1, S.2 S
aging and deterioration of face gaskets, ASME NS1D-RG 1.140, RG adhesives, sealants, and water repellents.
1989;NRC RG 1.S2 1.S2 resulting in filter leakage and loss of and RG 1.140 effective filtration.
Airborne moisture, contaminants, and Frequent ASME NS1D-1989; PSS&TReq.,
Not stated 4.2, S.2 6
pollutants are readily absorbed by carbon NRC RG 1.S2 and RG 1.140, RG bed adsorbers, thereby depleting RG 1.140 1.S2 adsorbent capacity and reducing efficiency.
Oxidation of the. carbon adsorbent Occasional ASME NS10-1989; PSS&TReq.,
Not stated 4.2 7
medium has been found to deplete NRC RG 1.S2 and RG 1.140, RG adsorbent capacity and reduce efficiency.
RG 1.140 1.S2
Table A.1 Gall Report for NPAR Reports Page 100A Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp Subcomponent Materials M anu acturer ARD h
mec amsm ARD H ts eec 8 Air-treatment system Air treatment system Unidentified Stainless steel Not stated CORR; CORR/PIT Loss of material adsorbers stainless steel components Document: NUREG/CR-6043, Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants Reviewed by:
Dwight R. Diercks, ANL Item S S M
- I M
f t
.ystem Structure/Comp ubcomponent aterlas anu ac urer ARD h
mec amsm ARD H ts eec 1 Heating, ventilating Centrifugal chiller Compressor seals Non-ferrous metals Not stated WEAR Attrition and air conditioning or carbon and (HVAC) elastomers 2 Heating, ventilating, Centrifugal chiller Compressor motor Not stated Not stated WEAR Attrition and air conditioning bearings (HVAC) 3 Heating, ventilating, Centrifugal chiller Compressor motor Not stated Not stated ELE-TEMP Chemical and and air conditioning physical degradation (HVAC) 4 Heating, ventilating, Centrifugal chiller Condenser and Carbon steel plate; Carrier, Trane, and CORR; CORR/PIT; Loss of material and and air conditioning evaporator/cooler Cu or Cu-10% Ni York CORRIMIC corrosion product (HVAC) heat exchangers tubing buildup 5 Heating, ventilating, Centrifugal chiller Condenser and Carbon steel plate; Carrier, Trane, and VIBR Loosening and air conditioning evaporator/cooler Cu or Cu-10% Ni York (HVAC) heat exchangers tubing 6 Heating, ventilating, Centrifugal chiller Refrigerant lines Cu or Cu-10% Ni Not stated FAT; VIBR Cumulative fatigue and air conditioning tubing damage; loosening (HVAC) 7 Heating, ventilating, Condenser cooling Piping and tubing Not stated Carrier, Trane, and CORR Loss of material and and air conditioning water system York corrosion product (HVAC) buildup 8 Heating, ventilating, Condenser cooling Piping and tubing Not stated Carrier, Trane, and FAT Cumulative fatigue and air conditioning water system York damage (HVAC) 9 Heating, ventilating, Lubrication system Tubing and other Not stated Carrier, Trane, and FAT Cumulative fatigue and air conditioning components York damage (HVAC) 10 Heating, ventilating, Lubrication system Lubricant Hydrocarbon Not stated CORR; WEAR Loss of material; and air conditioning attrition (HVAC) 11 Heating, ventilating, Control system Misc. small Not stated Carrier, Trane, and FAT Cumulative fatigue and air conditioning components York damage (HVAC) 12 Heating, ventilating, Control system Float valve bearings Not stated Carrier, Trane, and CORR; Loss of material; and air conditioning and pivots York CORRIIGSCC crack initiation and (HVAC) growth
Table A.1 Gall Report for NPAR Reports Page 1008 Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs RI e.progs R eport R ecommen d ti a ons P age o.
em N
It Relatively rapid galvanic corrosion and Occasional ASME N51(}'1989; PS S&TReq.,
Not stated 4.3 8
severe pitting can occur in stainless steel NRC RG 1.52 and RG 1.140, RG adsorber components in contact with wet RG 1.140 1.52 carbon, resulting in loss of integrity and effectiveness by the adsorber assembly.
Document: NUREG/CR-6043, Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Re"progs Report R d.
ecommen ations p age o.
em N
It Components are subject to time-Occasional Not discussed in PS S&T Req.
Periodically (3 to 10 years) overhaul 31,33, 1
dependent wear and ultimate failure, report and inspect all wearing parts, with C.3 resulting in loss of refrigerant through interval based on shortest material leakage.
life.~
Components are subject to time-Occasional Not discussed in PS S&T Req.
Periodically (3 to 10 years) overhaul 26,31, 2
dependent wear, resulting in loss of report and inspect all wearing parts, with 32, C.3 bearing function and motor failure.
interval based on shortest material life. [4)
Motor insulation and internal electrical Occasional Not discussed in PSS&TReq.,
Heat scan with infrared temperature-31,33, 3
components are subject to thermal report RG 1.32, RG.
sensing instruments. [4) 0.2,0.3 breakdown, resulting in motor failure.
1.140 Corrosion failures associated with Frequent Not discussed in PS S&T Req.
Control water quality supplied to the 26,27, 4
moisture ingress into the refrigerant in report condenser and evaporator; 28,30, refrigerant systems can lead to leakage periodically examine tubes and Clean 31,32, and loss of refrigerant. Others include of necessary. [4) 33,39, heat exchanger tube fouling and plugging, C.2,D.5, crevice corrosion at tube sheets, and bio-E.2, E.4 fouling.
Loosening of bolts by vibration has been Occasional Not discussed in PS S&T Req.
Periodically perform vibration 31,0.3 5
observed to cause component failure.
report analysis. [4]
Leakage of refrigerant lines apparently Occasional Not discussed in PS S&TReq.
Periodically perform vibration 31,33, 6
caused by vibrational fatigue or loosening report analysis. [4)
C.2, C.3, can lead to loss of refrigerant and system C.4,D.7, failure.
E.2 System components are subject to Frequent Not discussed in PS S&T Req.
Control water quality supplied to the 31,33, 7
corrosion, fouling, and plugging if good report condenser and evaporator; C.2, C.3, water chemistry is not maintained, periodically examine tubes and clean C.4,D.7, resulting in system failure.
of necessary. [4)
E.2 Vibrational fatigue failure of cooling Occasional Not discussed in PSS&TReq.
Periodically perform vibration 29,31, 8
system piping has been reported, report analysis. [4]
0.2 resulting in cooling water leakage and possible system failure.
Lubrication system leaks apparently Occasional Not discussed in PS S&T Req.
Periodically perform vibration 31,31, 9
caused by vibrational fatigue have been report analysis; routinely analyze lubrication C.2,D.2, reported, and such leaks can lead to loss oil to ensure correct chemistry. [4]
0.4, E.2, of lubricant and compressor and pump E.3 bearing failure.
Leakage from corrosion can cause Moderate Not discussed in PSS&TReq.
Routinely analyze lubrication oil to 30,32, 10 contamination of lubrication system by report ensure correct chemistry. [4]
E.2, E.5 acids, leading to accelerated wear and Ultimate failure of compressor and pump bearings.
Small control system components such Frequent Not discussed in PSS&TReq.
Periodically perform vibration 29,30, 11 as timers, cam switches, relays, terminal report analysis; annually service and test 31,33, and wire connectors, and lamp bulbs are components to ensure reliability. [4]
0.6, E.2, subject to mechanical fatigue-related E.3, E.6 failures due to vibration.
Corrosive attack of bearings and pivots in Rare Not discussed in PSS&TReq.
Routinely analyze refrigerant to 31,33, 12 float valves due to water ingress into the report ensure correct chemistry. [4]
C.2,C.3, refrigerant can lead to failure. IGSCC of a C.4,D.3 valve ball float in Waterford Unit 3 has also been observed.
Table A.1 Gall Report for NPAR Reports Page 101A Document: NUREG/CR-6048, Pressurized-Water Reactor Internals Aging Degradation Study, Phase 1 Reviewed by:
Ali Erdemir, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Reactor internals Lower core support Thermal shield Type 304 SS Westinghouse.
VIBR Crack initiation and structure growth 2 Reactor internals Lower core support Thermal shield radial Type304SS Westinghouse.
VIBR Crack initiation and structure limiter pin growth 3 Reactor internals Lower core support Thermal shield Type304SS Westinghouse VIBR Crack initiation and structure flexure support growth system 4 Reactor internals Lower core support Thermal shield Type304SS Combustion VIBR; WEAR Crack initiation and structure Engineering growth; attrition 5 Reactor internals Lower core support Hold-down ring Type304SS Combustion VIBR; WEAR Crack initiation and structure Engineering growth; attrition 6 Reactor internals Lower core support Fuel rods Type304SS Westinghouse VIBR Crack initiation and structure growth 7 Reactor internals Lower core support Thermal shield Alloy A-286 Babcock & Wilcox CORRIIGSCC Crack initiation and structure support bolts growth 8 Reactor internals Lower core support Barrel-to-core Alloy A-286 Babcock & Wilcox CORRIIGSCC Crack initiation and structure support shield bolts growth 9 Reactor internals Core barrel Baffle bolts Inconel X-750 Westinghouse CORRIIGSCC Crack initiation and growth 10 Reactor internals Upper core support Control rod guide Inconel X-750 Westinghouse CORRIIGSCC Crack initiation and structure tube support pins growth 11 Reactor internals In-core.
Aux thimbles and Types 304 and 316 Westinghouse VIBR, WEAR Crack initiation and instrumentation guide tube SS growth, attrition support structure 12 Reactor internals In-core Surveillance Type304SS Babcock & Wilcox VIBR, WEAR Crack initiation and instrumentation specimen holder growth, attrition support structure tube Document: ORNUNRC/LTR-91/25, Throttled Valve Cavitation and Erosion Reviewed by:
Ken E. Kasza, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 Component cooling Valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material water body/seat/plug SS, cast iron, carbor steel I
Table A.1 Gall Report for NPAR Reports Page 1018 Document: NUREG/CR-6048, Pressurized-Water Reactor Intemals Aging Degradation Study, Phase 1 ReViewed by:
Ali Erdemir, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Vibration of thermal shield in a shell mode Not stated ASME B&PV Code, ASMESecXI Not stated 38 1
caused some of the shell segments to Section XI IWB&Assoc.
come into contact with the core barrel.
NRCGC The repeated impact loadings caused failures in the core barrel support bolts and also damaged the thermal shield.
Row-induced vibration caused radial Not stated ASME B&PV Code, ASMESecXI Not stated 38 2
limiter pins to come into contact with the Section XI IWB & Assoc.
sides of the keyway in the core barrel, NRCGC eventually leading to cracking of the fillet welds between pins and thermal shield.
The top mounted flexure support system Not stated ASME B&PV Code, ASMESecXI Not stated 38 3
failed due to high-cycle fatigue caused by Section XI IWB & Assoc.
small-amplitude flow-induced vibration of NRCGC the thermal shield.
Pump-generated pressure pulsations Not stated ASME B&PV Code, ASME Sec XI Not stated 38 4
caused excessive wear damage and lossSection XI IWB & Assoc.
of some support and positioning pins.
NRCGC Lugs welded to the core barrel were also damaged. In one unit the damaged lugs caused a through-the-wall crack in the core barrel.
Row-induced vibration caused excessive Not stated ASME B&PV Code, ASMESecXI Use 403 SS, increase hold-down 38 5
mechanical wear in the hold-down ring of Section XI IWB & Assoc.
spring force. [4) a CE unit due to the insufficient levels of NRCGC hold-down spring force.
Baffle plate water-jetting due to pressure Not stated ASME B&PV Code, ASMESecXI Change design, modify downward 38-39 6
differential set fuel rods into whirling Section XI IWB&Assoc.
bypass flow to an upward bypass motions and excessive vibrations, which NRCGC flow scheme [4) eventually led to cladding degradation and failures.
High tensile stresses due to preloads and Not stated Not discussed in ASMESecXI Change design, reduce tensile 40 7
poor design in the shank region of bolts report IWB & Assoc.
stress level, change material to X-led to the development of IGSCC at the NRCGC 750 [1) bolt-head-to-bolt shank transition area.
As a result, some bolts were lost and others became loose.
Overtorquing on bolts and hot-head Not stated Not discussed in ASMESecXI Reduce torque to bolts, change fab-41 8
manufacturing process were the most report IWB& Assoc.
rication practice, use bolts made by probable cause of IGSCC in a number of NRCGC machining [1) bolts that join core barrel to core support shield.
Routine inspections detected signs of Not stated Not discussed in ASME Sec XI Use austenitic stainless steel bolts 42 9
cracks in core baffle bolts, and the report IWB&Assoc.
[4) failures were attributed to IGSCC possibly NRCGC due to sensitization of the Inconel X-750 bolts.
Crevice conditions, improper heat Not stated NRC Information ASMESecXI Solution heat treat at a higher 41 10 treatment, and overtorquing of nuts during Notice 82-29 IWB&Assoc.
temper-ature, increase pin size, installation of the support pins may have NRCGC reduce preloads during installation.
contributed to IGSCC.
(4)
Fretting and mechanical wear resulted in Not stated NRC Information ASMESecXI Move thinned segments away from 43 11 thinning and eventual leakage of the Notice 87-44 IWB & Assoc.
the vibrating region. Use thicker-thimble and guide tubes. Flow-induced NRCGC walled tubes [4]
vibration was identified as the leading contributor to fretting and wear.
Row induced vibration due to pump-Not stated Not discussed in ASMESecXI Change stiffness of tubes [4) 43 12 generated pressure pulsations caused report IWB & Assoc.
excessive wear on tubes.
NRCGC Document: ORNUNRC/LTR-91125, Throttled Valve Cavitation and Erosion Reviewed by:
Ken E. Kasza, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Valves used under throttied service can Occasional Not discussed in ASMESecXI More carefully select valve type, trim 3,4,8, 1
experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18 material. For butterfly type valves, wall
&Suppl.
operating conditions [4) thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Table A.1 Gall Report for NPAR Reports Page 102A Document: ORNUNRCILTR-91/25, Throttled Valve Cavitation and Erosion Reviewed by:
Ken E. Kasza, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 2 Condensate/feedwat Valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material er body/seat/plug SS, cast iron, carbor steel 3 Chemical volume Valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material and control body/seat/plug SS, cast iron, carbor steel 4 Service water Valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material body/seat/plug SS, cast iron, carbon steel 5 Main steam Valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material body/seat/plug SS, cast iron, carbor steel 6 Residual heat Globe valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material removal body/seat/plug SS, cast iron, carbor steel 7 Residual heat Butterfly valve Internals:
316 SS, stellite over Not stated ERO/CAV Loss of material removal body/seatlplug SS, cast iron, carbon steel Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers Reviewed by:
Steve U. Choi, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 All systems in ECCS pump room Fan V-Cord (cotton, rayon, Not stated VISR Loosening; crack general and RHR coolers Belts/Sheaves synthetic, steel) initiation and growth system in particular fiber, rubber/steel 2 All systems in ECCS pump room Fan V-Cord (cotton, rayon, Not stated WEAR Attrition general and RHR coolers Belts/Sheaves synthetic, steel) system in particular fiber, rubber/steel 3 All systems in ECCS pump room Motor-and fan-Steel, brass, bronze, Not stated WEAR Attrition general and RHR coolers bearings grease, lube oil system in particular 4 All systems in ECCS pump room Motor-and fan-Steel, brass, bronze, Not stated CORR Loss of general and RHR coolers bearings grease, lube oil material;corrosion system in particular product buildup
Table A.1 Gall Report for NPAR Reports Page 1028 Document: ORNUNRC/LTR-91/25, Throttled Valve Cavitation and Erosion Reviewed by:
Ken E. Kasza, ANL E
A ffect of 'ging on Component Function Contrib to Failure Reported progs RI e.p!~aS R eport R d.
ecommen ations P age N It
- o.
em Valves used under throttled service can Moderate Not discussed in ASME Sec XI More carefully select valve type, trim 3,4,8, 2
experience cavitation, which can remove report IWV, GL89-10 and materials appropriate for 10,18 material. For butterfly type valves, wall
&Suppl.
operating conditions [4]
thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Valves used under throttled service can Occasional Not discussed in ASME Sec XI More carefully select valve type, trim 3,4,8, 3
experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10, 18 material. For butterfly type valves, wall
&Suppl.
operating conditions [4]
thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Valves used under throttled service can Moderate Not discussed in ASMESecXI More carefully select valve type, trim 3,4,8, 4
experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18 material. For butterfly type valves, wall
&Suppl.
operating conditions [4]
thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Valves used under throttled service can Occasional Not discussed in ASMESecXI More carefully select valve type, trim 3,4,8, 5
experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10, 18 material. For butterfly type valves, wall
&Suppl.
operating conditions [4]
thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Valves used under throttled service can Occasional Not discussed in ASMESecXI More carefully select valve type, trim 3,4,8, 6
experience cavitation, which can remove report IWB,IWV,GL and materials appropriate for 10,12, material. For butterfly type valves, wall 89-10 & Suppl. operating conditions [4]
13, 18 thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Valves used under throttled service can Moderate Not discussed in ASME Sec XI More carefully select valve type, trim 3,4,8, 7
experience cavitation, which can remove report IWB,IWV, GL and materials appropriate for 10,12, material. For butterfly type valves, wall 89-10 & Suppl. operating conditions [4]
13, 18 thinning can occur in adjacent downstream pipe. Cavitation can cause vibration damage.
Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers RevieWed by:
Steve U. Choi, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated.
Frequent Not discussed in PS S&TReq.
Follow mfg. recommendations for 2.4,5.3 1
report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use strip heaters to control humidity. [4]
Not stated.
Not stated Not discussed in PSS&T Follow mfg. recommendations for 5.4 2
report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies. use [4]
Not stated.
Frequent Not discussed in PS S&TReq.,
Follow mfg. recommendations for 2.4,5.4 3
report RG 1.32 installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PS S&T Req.,. Follow mfg. recommendations for 6.5 4
report RG 1.32 installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Table A.1 Gall Report for NPAR Reports Page 103A Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers Reviewed by:
Steve U. Choi, ANL Item System Structur eI Sb M*I M
Comp u component aterlas anu acturer ARD mec h amsm ARD ff ts eec 5 All systems in ECCS pump room Couplings/fans Not Not stated VISR Loosening; crack general and RHR coolers stated/Galvanized, initiation and growth system in particular carbon and stainless steel, aluminum 6 All systems in ECCS pump room Cooling coils Copper, copper-Not stated VISR Loosening; crack general and RHR coolers nickel, aluminum initiation and growth system in particular 7 All systems in ECCS pump room Cooling coils Copper, copper-Not stated CORR Loss of general and RHR coolers nickel, aluminum material;corrosion system in particular product buildup 8 All systems in ECCS pump room Fan motors Copper, steel, silicon Not stated VISR Loosening; crack general and RHR coolers steel, aluminum, initiation and growth system in particular insulating materials, cast iron, brass, mica, plastics, graphite, cable, seals and gaskets 9 All systems in ECCS pump room Fan motors Copper, steel, silicon Not stated ELE-TEMP Degradation general and RHR coolers steel, aluminum, system in particular insulating materials, cast iron, brass, mica, plastics, graphite, cable, seals and gaskets 10 All systems in ECCS pump room Fan motor mounting Not stated Not stated CORR Loss of general and RHR coolers bolts, lead material;corrosion system in particular connection, conduit product buildup boxes, housing enclosures Document: PNL-6287, Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation Reviewed by:
Steve U. Choi, ANL Item System StructurelComp b
Su component Materials Manufacturer ARD mechanism ARDeffects 1 Diesel Generator Various This report does not provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Document: PNL-7516, Emergency Diesel Generator Technical Specifications Study Results Reviewed by:
Steve U. Choi, ANL I tem System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Diesel Generator Various This report does not provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Table A.1 Gall Report tor NPAR Reports Page 1038 Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers Reviewed by:
Steve U. Choi, ANL Effect of Aging on Component Function Contrib to Failure Reported progs R
R el.prog_s eport R d ti ecommen a ons P age N It
- o.
em Not stated.
Not stated Not discussed in PS S&T Req.
Follow mfg. recommendations for 2.4,6.1-5 report installation, surveillance, and 6.3 maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PS S&T Req.
Follow mfg. recommendations for 2.4,6.3 6
report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly.
check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PS S&T Req.
Follow mfg. recommendations for 6.6 7
report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PSS&T Req.,
Follow mfg. recommendations for 2.4,6.1 8
report RG 1.32 installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PS S&TReq.
Follow mfg. recommendations for 6.4 9
report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Not stated.
Not stated Not discussed in PS S&TReq.
Follow mfg. recommendations for 6.5 10 report installation, surveillance, and maintenance, add vibration isolation mounts, use acoustic and temp.
monitoring techniques, regularly check vibration amplitudes and frequencies, use [4]
Document: PNL-6287, Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation Reviewed by:
Steve U. Choi, ANL E
f*
R R
R ffect 0 Agl'!!t on Comllonent Function Contrib to Failure Reported progs el~~s e~ort d.
ecommen ations P age N o. tem 1
Document: PNL-7516, Emergency Diesel Generator Technical Specifications Study Results RevieWed by:
Steve U. Choi, ANL E ffect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item 1
Table A.1 Gall Report for NPAR Reports Page 104A Document: PNL-7823, Maintenance Practices to Manage Aging: A Review of Several Technologies Reviewed by:
Ken E. Kasza, ANL Item System Structure/Comp Subcom~onent Materials Manufacturer ARDmec amsm AR e ects h
D ff 1 Reactor All major This report does not components provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL Item S1stem S
e/
Sb M
- 1 tructur Comp u com~onent aterla s Manufacturer ARD mechanism ARDeffects 1 Containment Metal containment Drywell base Not stated Not stated CORR Loss of material 2 Containment Metal containment Drywell base Not stated Not stated CORR/CREV Loss of material 3 Containment Metal containment Drywell base Not stated Not stated CORRIMIC Loss of material 4 Containment Metal containment Embedded shell Not stated Not stated CORR/CREV Loss of material 5 Containment Metal containment Embedded shell Not stated Not stated CORR/PIT Loss of material 6 Containment Metal containment Embedded shell Not stated Not stated CORR Loss of material 7 Containment Metal containment Bellows Stainless steel Not stated CORR/IGSCC Crack initiation and growth 8 Containment Metal containment Bellows Stainless steel Not stated CO RRITGSCC Crack initiation and growth 9 Containment Metal containment Suppression pool Not stated Not stated CORR Loss of material 10 Containment Metal containment Suppression pool Not stated Not stated CORRIMIC Loss of material 11 Containment Metal containment Suppression pool Not stated Not stated CORR/PIT Loss of material 12 Containment Metal containment Dissimilar metal Not stated Not stated CORR Loss of material welds 13 Containment Reinforced concrete Reinforcing bars Not stated Not stated CORR Loss of material containment 14 Containment Reinforced concrete Suppression pool Steel Not stated CORR Loss of material containment liner
Table A.1 Gall Report for NPAR Reports Page 1048 Document: PNL-7823, Maintenance Practices to Manage Aging: A Review of Several Technologies Reviewed by:
Ken E. Kasza, ANL Eff R I eet of Aging on Component Function Contrib to Failure Reported progs e.progs R
rtR epo d.
ecommen ations P age N lte
- o.
m 1
Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL Effeet of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Leakage of radioactive gases.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 17 1
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 17 2
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 17 3
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Loss of structural integrity.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 17 4
Sect. III and XI IWE&
refurbishent, and replacement on a 1 OCFR50 App. timely basis. [4)
J Loss of structural integrity.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 17 5
Sect. III and XI IWE&
refurbishent, and replacement on a 1 OCFR50 App. timely basis. [4)
J Loss of structural integrity.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 17 6
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Frequent ASME B&PV Code ASMESecXI Effective application of mainteance, 17 7
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. (4)
J Leakage of radioactive gases.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 17 8
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 17 9
Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. (4)
J Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 17 10 Sect. III and XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 17 11 Sect. JII and XI IWE&
refurbishent, and replacement on a 1 OCFR50 App. timely basis. [4)
J Leakage of radioactive gases.
Frequent ASME B&PV Code ASMESecXI Effective application of mainteance, 18 12 Sect. JIIand XI IWE&
refurbishent, and replacement on a 10CFR50 App. timely baSis. [4)
J Loss of structural integrity.
Infrequent ASME B&PV Code ASMESecXI Effective application of mainteance, 18 13 Sect. III and XI IWL refurbishent, and replacement on a
. timely basis. [4)
Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 18 14 Sect. III and XI IWL&
refurbishent, and replacement on a 10CFR50 App. timely basis. [4)
J
Table A.1 Gall Report for NPAR Reports Page 105A Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL I
S eI b
M M
f tu tem System tructur Co"!p_
Su component aterlals anu ac rer ARD h
mee amsm ARD ff ts eee 15 Containment Reinforced concrete Suppression pool Steel Not stated CORRIMIC Loss of material containment liner 16 Containment Prestressed Posttensioning Not stated Not stated CORR Loss of material concrete system anchor containment 17 Containment Prestressed Posttensioning wire Not stated Not stated CORR/PIT Loss of material concrete or strand containment 18 Containment Prestressed Posttensioning wire Not stated Not stated CORRIMIC Loss of material concrete or strand containment 19 Containment Prestressed Suppression pool Steel Not stated CORR Loss of material concrete liner containment 20 Containment Prestressed Suppression pool Steel Not stated CORRIMIC Loss of material concrete liner containment 21 Containment Prestressed Drywall liner Steel Not stated CORR Loss of material concrete containment 22 Containment Prestressed Reinforcing bar Not stated Not stated CORR Loss of material concrete containment 23 Containment Prestressed and Uner over wall dome Steel Not stated CORR Loss of material reinforced concrete and base slab 24 BWR cooling Reactor pressure Nozzles Not stated Not stated CORR/IGSCC Crack initiation and system vessel growth 25 BWRcooling Recirculation piping Weld heat-affected Not stated Not stated CORR/IGSCC Crack initiation and system zones growth 26 BWR cooling Feedwater and main Near fittings and Not stated Not stated CORR Loss of material system steam lines discontinuities 27 BWR cooling Feedwater and main Near fittings and Not stated Not stated ERO/CORR Loss of material system steam lines discontinuities 28 BWR cooling Control rod drive Pressure housing &
Not stated Not stated CORR/IGSCC Crack initiation and system mechanisms stub tube growth 29 BWR cooling Reactor internals Attachment welds Not stated Not stated CORR/IGSCC Crack initiation and system growth 30 BWR cooling Reactor internals Jet pumps Not stated Not stated CORR/IGSCC Crack initiation and system growth 31 PWR cooling Reactor pressure Vessel flange and Not stated Not stated FAT Cumulative fatigue system vessel studs damage 32 PWR cooling Recirculation steam Hot-leg tubes and U-Not stated Not stated CORR/IGSCC Crack initiation and system generator tubes bends growth 33 PWR cooling Recirculation steam Cold-leg side in Not stated Not stated CORR/PIT Loss of material system generator tubes sludge pile 34 PWRcooling Recirculation steam Tubing 0.0. above Not stated Not stated CORR/UA Loss of material system generator tubes tube sheet 35 PWR cooling Once-through steam Steam generator Not stated Babcock & Wilcox ERO/CORR Loss of material system generators tubes
Table A.1 Gall Report for NPAR Reports Page 1058 Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 18 15 Sect. III and XI IWL&
returbishen~ and replacement on a 10CFR50 App. timely basis. [4]
J Reduction of load-carrying capacity.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 18 16 Sect. III and XI.
IWL refurbishen~ and replacement on a timely basis. [4]
Reduction of load-carrying capacity.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 18 17 Sect. III and XI IWL&
refurbishen~ and replacement on a 10CFR50 App. timely basis. [4]
J Reduction of load-carrying capacity.
Infrequent ASME B&PV Code ASMESecXI Effective application of mainteance, 18 18 Sect. III and XI IWL refurbishen~ and replacement on a timely basis. [4]
Leakage of radioactive gases.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 19 19 Sect. III and XI IWL&
returbishent, and replacement on a 10CFR50 App. timely basis. [4]
J Leakage of radioactive gases.
Occasional ASME B&PV Code ASME Sec XI Effective application of mainteance, 19 20 Sect. III and XI IWL&
refurbishen~ and replacement on a 10CFR50 App. timely basis. [4]
J Leakage of radioactive gases.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 19 21 Sect. III and XI IWL&
returbishen~ and replacement on a 10CFR50 App. timely basis. [4]
J Loss of structural integrity.
Infrequent ASME B&PV Code ASMESecXI Effective application of mainteance, 19 22 Sect. III and XI IWL returbishen~ and replacement on a timely basis. [4]
Leakage of radioactive gases and Infrequent ASME B&PV Code ASMESecXI Effective application of mainteance, 19-20 23 interaction of liner and concrete.
Sect. III and XI IWL&
returbishen~ and replacement on a 10CFR50 App. timely basis. [4]
J Ductile overload leading to leakage.
Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 21 24 Seclill and XI IWB returbishen~ and replacement on a timely basis. [4]
Cracking and leakage.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 21 25 Sect. III and XI IWB returbishen~ and replacement on a timely basis. [4]
Cracking, large deformations, rupture, Frequent ASME B&PV Code ASMESecXI Effective application of mainteance, 21 26 and leakage.
SecllllandXI IWB returbishen~ and replacement on a timely basis. [4]
Cracking, large deformations, rupture, Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 21 27 and leakage.
Sect. III and XI IWB returbishen~ and replacement on a timely basis. [4]
Cracking leading to leakage.
Occasional ASME B&PV Code ASME Sec XI Effective application of mainteance, 21 28 Sect. III and XI IWB returbishen~ and replacement on a timely basis. [4]
Crack growth progressing into reactor Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 21 29 vessel.
Sect. III and XI IWB returbishen~ and replacement on a timely basis. [4]
Loss of adequate core flow.
Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 22 30 Sect. III and XI IWB refurbishen~ and replacement on a timely basis. [4]
EVentual ductile overload failure.
Moderate ASME B&PV Code ASMESec III & Effective application of mainteance, 23 31 Sect. III and XI XIIWB returbishent, and replacement on a timely basis. [4]
Possible eventual cracking.
Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 23 32 Sect. III and XI IWB& PS TS returbishen~ and replacement on a Req.
timely basis. [4J Possible eventual perforation, resulting in Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 23 33 leakage.
Sect. III and XI IWB& PSTS returbishent, and replacement on a Req.
timely basis. [4]
Tube thinning, possibly leading to Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 23 34 penetration and leakage.
Sect. III and XI IWB& PS TS returbishent, and replacement on a Req.
timely basis. [4]
Tube thinning, possibly leading to Frequent ASME B&PV Code ASMESecXI Effective application of mainteance, 24 35 penetration and leakage.
Sect. III and XI IWB& PS TS returbishent, and replacement on a Req.
timely baSIS. [4]
Table A.1 Gall Report for NPAR Reports Page 106A Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL Item System Structure/Com~
b Su component M t. I aenas M
f tu anu ac rer ARD h
mec amsm ARD ff ts eec 36 PWR cooling Pressurizer sleeve Heater sheaths Not stated Not stated CORR/SCC Crack initiation and system growth 37 PWR cooling Pressurizer sleeve Heater sheaths Not stated Not stated WEAR Attrition system 38 PWR cooling Pressurizer sleeve Manway bolts Not stated Not stated CORR/SCC Crack initiation and system growth 39 PWR cooling Reactor internals Thermal shield, Not stated Not stated FAT Cumulative fatigue system bolts, core barrel, damage and core support structure 40 PWR cooling Reactor internals Thermal shield, Not stated Not stated CORRIIGSCC Crack initiation and system bolts, core barrel, growth and core support structure 41 PWR cooling Reactor internals Thermal shield, Not stated Not stated EMBRIIR Loss of fracture system bolts, core barrel, toughness and core support structure 42 PWR cooling Reactor internals Thermal shield, Not stated Not stated EMBRITE Loss of fracture system bolts, core barrel, toughness and core support structure 43 PWR cooling Feedwater piping Piping and nozzle Not stated Not stated ERa/CaRR Loss of material system and nozzle inside containment 44 PWR cooling Feedwater piping Piping and nozzle Not stated Not stated FAT Cumulative fatigue system and nozzle inside containment damage Document: PNL-SA-20219, ASME Subsection ISTD Recommendations based upon NPAR Snubber Aging Research Results Reviewed by:
Steve U. Choi, ANL Item System Structure/Com p Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 Piping Snubber This report does not provide specific detailed information on age-related degradation processes for specific nuclear components or systems.
Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL Item System Structure/Comp Subcomponent Materials ManUfacturer ARD mechanism ARDeffects 1 Combustion Control Element Control Elements Clad-Inconel 625 CE WEAR; CORR/SCC Attrition; Crack Engineering (eE)
Assemblies initiation and growth Control Rod Drive System 2 Combustion Control Element Fuel Assembly Zircaloy-4 CE WEAR Attrition Engineering (eE)
Assemblies Guide Tubes Control Rod Drive System 3 Combustion Control Element Upper Guide Stainless Steel CE WEAR; EMBRIIR; Attrition; Loss of Engineering (CE)
Assemblies Structure-Spider FAT fracture toughness; Control Rod Drive Cumulative fatigue System damage 4 Combustion Control Element Motor Housing 403 Stainless Steel CE EMBR; CaRR; FAT Loss of fracture Engineering (eE)
Drive Mechanisms Assembly Ni-Cr-Fe alloy toughness; Loss of Control Rod Drive (CEDM) material; Cumulative System fatigue damage 5 Combustion Control Element Motor Assembly-High Cobalt Alloy CE WEAR; FAT; Attrition; Cumulative Engineering (CE)
Drive Mechanisms Latches, Unks and CONTAM fatigue damage; Control Rod Drive (CEDM)
Pins Buildup of deposits System
Table A.1 Gall Report for NPAR Reports Page 1068 Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants Reviewed by:
John W. Holland, ANL Effect of Agin_g_ on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem Cracking leading to leakage.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 24 36 Sect. III and XI IWB refurbishent and replacement on a timely basis. [4J Metal loss leading to leakage.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 24 37 Sect. III and XI IWB refurbishent and replacement on a timely basis. [4]
Solt breakage leading to leakage.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 24 38 Sect. III and XI IWB refurbishent and replacement on a timely basis. [4)
Broken bolts, cracks, and loose parts.
Frequent ASME B&PV Code ASMESec III & Effective application of mainteance, 24 39 Sect. III and XI XIIWB refurbishent and replacement on a timely basis. [4)
Broken bolts, cracks, and loose parts.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 24 40 Sect. III and XI IWB refurbishent and replacement on a timely basis. [4]
Broken bolts, cracks, and loose parts.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 24 41 Sect. III and XI IWB refurbishent, and replacement on a timely basis. [4]
Broken bolts, cracks, and loose parts.
Infrequent ASME B&PV Code ASMESecXI Effective application of mainteance, 24 42 Sect. III and XI IWB refurbishent and replacement on a timely basis. [4]
Rupture caused by water pressure.
Moderate ASME B&PV Code ASMESecXI Effective application of mainteance, 24 43 Sect. III and XI
& PS S&T refurbishent and replacement on a Req.
timely basis. [4]
Leakage through fatigue cracks.
Occasional ASME B&PV Code ASMESecXI Effective application of mainteance, 24 44 Sect. III and XI
& PSS&T refurbishent and replacement on a Req.
timely basis. [4)
Document: PNL-SA-20219, ASME Subsection ISTD Recommendations based upon NPAR Snubber Aging Research Results Reviewed by:
Steve U. Choi, ANL E
fA*
F FRed RI R
rtR d
ffecto Igmg on Component unction Contribto ailure eport progs el.progs epo ecommen ations P
N It age o.
em 1
Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL E ffect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Cilad cracking and wash out of the poison. Occasional None stated ASME Sec XI None given 1
IWB& PS Tech Spec.
Req.
Cracking of the tube wall.
Frequent None stated ASMESecXI None given 2
IWB& PS Tech Spec.
Req.
Cracking of the guide causing rod drops.
Rare None stated ASMESecXI None given 3
IWB& PS Tech Spec.
Req.
Housing cracking leads to primary coolant Frequent None stated ASME Sec XI None given 4
leakage (SBLOCA) and jamming of the IWB& PS drive mechanism.
Tech Spec.
Req.
Failure of these sub-components will lead Rare None stated ASMESecXI None given 5
to dropping or lOCking of the control IWB& PS element Tech Spec.
Req.
Table A.1 Gall Reportfor NPAR Reports Page 107A Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL Item System StructureJComp Subcomponent Materials Manu acturer ARD h
mec amsm ARD ff ts eec 6 Combustion Control Element Upper Pressure Type 316 Stainless CE EMBR; CaRR; FAT Loss of fracture Engineering (CE)
Drive Mechanisms Housing Assembly toughness; Loss of Control Rod Drive (CEDM) material; Loss of System fracture toughness 7 Combustion Control Element Extension Shaft Type 304 Stainless, CE WEAR; FAT; Attrition; Loss of Engineering (CE)
Drive Mechanisms Chromium plated CORR/SCC fracture toughness; Control Rod Drive (CEDM)
Crack initiation and System growth 8 Combustion Control Element Vent Valves Type 440 Stainless CE CaRR; FAT; Corrosion product Engineering (CE)
Drive Mechanisms Steel, Type 316 WEAR; EMBRITE buildup; Cumulative Control Rod Drive (CEDM)
Stainless Steel Seat fatigue damage; System Attrition; Loss of fracture toughness 9 Combustion Control Element Coil Stack Assembly Copper wire CE CaRR; WEAR Loss of material; Engineering (CE)
Drive Mechanisms
- Coils insulated with high Attrition Control Rod Drive (CEDM) temperature enamel System vacuum impregnated with high temperature vamish 10 Combustion CEDM Control Control Element Not stated CE These components Engineering (CE)
Systems Drive Control are referred to INEL Control Rod Drive System and Control for review.
System Power Programmer 11 Combustion CEDM Control Rack and Pinion Not stated CE These components Engineering (CE)
Systems Control System are referred to INEL Control Rod Drive for review.
System 12 Combustion CEA Rod Position Reed Switch Not stated CE These components Engineering (CE)
Indication Position Transmitter are referred to INEL Control Rod Drive Assembly for review.
System 13 Combustion CEA Rod Position Pulse Count Position Not stated CE These components Engineering (CE)
Indication Indication System are referred to INEL Control Rod Drive for review.
System 14 Combustion CEDM Cooling Fans Not stated CE Not stated Not stated Engineering (CE)
System Control Rod Drive System 15 Combustion CEDM Cooling Cooling Shroud Sheet metal CE CORR/BA Loss of material Engineering (CE)
System Control Rod Drive System 16 Combustion CEDM Cooling Instrumentation Not stated CE Not stated Not stated Engineering (CE)
System Control Rod Drive System 17 Babcock & Wilcox Control Rod Control Rod Type 304 Stainless B&W CORR/SCC; WEAR Crack initiation and (B&W) Control Rod Assemblies Cladding growth; Attrition Drive System 18 Babcock & Wilcox Control Rod Fuel Assembly Zircaloy-4 B&W WEAR Attrition (B&W) Control Rod Assemblies Guide Tubes Drive System 19 Babcock & Wilcox Control Rod Upper Internal GradeCF3M B&W CORR/SCC; Crack initiation and (B&W) Control Rod Assemblies Brazement Stainless WEAR; EMBRIIR; growth; Attrition; Drive System Assemblies-Spider FAT Loss of fracture toughness; Cumulative fatigue damage 20 Babcock & Wilcox Control Rod Drive Motor Tube Low alloy steel clad B&W EMBRITE; CaRR; Loss of fracture (B&W) Control Rod. Mechanisms with Inconel or Type FAT toughness; Loss of Drive System (CRDM) 403 stainless material; Cumulative fatigue damage
Table A.1 Gall Report for NPAR Reports Page 1078 Document: TR*3270, 9-90, An Operational Assessment of the Combustion Engineering'and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L. Binder, ANL Effect of Aging on Com~onent Function Contrib to Failure Reported proCis Rel.progs Report Recommendations Page No. Item Housing cracking leads to primary coolant Frequent None stated ASME Sec XI None given 6
leakage (SBLOCA) and jamming of the IWB& PS drive mechanism.
Tech Spec.
Req.
Shaft cracking will lead to locking of the Occasional None stated ASMESecXI None given 7
mechanical operation.
IWB&PS Tech Spec.
Req.
Loss of valve function and primary coolant Rare None stated ASMESecXI None given 8
leakage.
IWB& PS Tech Spec.
Req.
Loss of coil function will lead to dropped, Rare None stated ASMESecXI None given 9
slipped or immovable control elements.
IWB& PS Tech Spec.
Req.
Referred to INEL for review.
Rare 10 None given 11 Rare 12 13 Loss of rod drive mechanism cooling Not stated None stated ASMESecXI None given 14 capacity leading to inoperable CRDM or and PSTech rod drops.
Spec. Req.
Loss of rod drive mechanism cooling Not stated None stated ASMESecXI None given 15 capacity leading to inoperable CRDM or and PSTech rod drops.
Spec. Req.
Loss of rod drive mechanism cooling Not stated None stated If Class 1E None given 16 capacity leading to inoperable CRDM or 10CFR 50.49 rod drops.
otherwise PS S&TReq.
Clad cracking and wash out of the poison. Occasional None stated ASMESecXI None given 17 IWBand PS Tech Spec.
Req.
CraCking of the tube wall.
Rare None stated ASME Sec XI None given 18 IWB&PS Tech Spec.
Req.
Cracking of the guide causing rod drops.
Rare None stated ASME Sec XI None given 19 IWB&PS Tech Spec.
Req.
Housing cracks causing primary coolant Rare None stated ASMESecXI None given 20 leakage (SBLOCA) and jamming of the IWB&PS drive mechanism.
Tech Spec.
Req.
Table A.1 Gall Report for NPAR Reports Page 108A Document: TR*3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives Reviewed by:
Jeffrey L Binder, ANL Item System StructureiComp Subcomponent Materials Manufacturer A Dmee amsm R
h A RD ff e eets 21 Babcock & Wilcox Control Rod Drive Stator Coils Copper Wire, Dow B&W Referred to INEL for (8&W) Control Rod Mechanisms Corning 997 review.
Drive System (CRDM)
Varnish, Kapton, Nomex, Silicone Rubber 22 Babcock & Wilcox Control Rod Drive Vent Valve O*rings Stainless Steel B&W CORR; WEAR; Corrosion product (8&W) Control Rod Mechanisms FAT; EMBRfTE buildup; Attrition; Drive System (CRDM)
Cumulative fatigue damage; Loss of fracture toughness 23 Babcock & Wilcox Control Rod Drive Rotor Assembly*
Stellite Ni*Cr*Fe B&W WEAR; FAT; Attrition; Cumulative (8&W) Control Rod Mechanisms roller nuts, segment Alloy, Type 403 CONTAM fatigue damage; Drive System (CRDM) arms, springs Stainless Steel Buildup of deposits 24 Babcock & Wilcox Control Rod Drive Leadscrew 17-4 PH Stainless B&W WEAR; FAT; Attrition; Cumulative (8&W) Control Rod Mechanisms Steel CORR/SCC fatigue damage; Drive System (CRDM)
Crack initiation and growth; 25 Babcock & Wilcox CRDM Power and Power Supplies Not stated B&W Referred to INEL for (8&W) Control Rod Control Systems review.
Drive System 26 Babcock & Wilcox CRDM Power and Programmers Not stated B&W Referred to INEL for (8&W) Control Rod Control Systems review.
Drive System 27 Babcock & Wilcox CRDM Power and Trip Breakers Not stated B&W Referred to INEL for (8&W) Control Rod Control Systems review.
Drive System 28 Babcock & Wilcox CRDM Power and Programmer Drive Not stated B&W Referred to INEL for (8&W) Control Rod Control Systems Motors review.
Drive System 29 Babcock & Wilcox CRA Rod Position Absolute Position Not stated B&W Referred to INEL for (8&W) Control Rod Indication Indication System review.
Drive System 30 Babcock & Wilcox CRA Rod Position Relative Rod Not stated B&W Referred to INEL for (8&W) Control Rod Indication Position Indication review.
Drive System 31 Babcock & Wilcox CRDM Cooling Centrifugal Pumps Not stated B&W CORR/BA Loss of material (8&W) Control Rod System Drive System 32 Babcock & Wilcox CRDM Cooling Heat Exchangers Not stated B&W CORR/BA Loss of material (8&W) Control Rod System Drive System 33 Babcock & Wilcox CRDM Cooling Surge Tank Not stated B&W CORR/BA Loss of material (8& W) Control Rod System Drive System
Table A.1 Gall Report for NPAR Reports Page 1088 Document: TR*3270, 9*90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives ReViewed by:
Jeffrey L. Binder, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem 21 Loss of valve function and primary coolant Occasional None stated ASMESecXI None given 22 leakage.
IWB& PS Tech Spec.
Req.
Failure of these sub-components will lead Rare None stated ASMESecXI None given 23 to dropping or locking of the control rod IWB& PS assembly.
Tech Spec.
Req.
Cracking of the leadscrew will cause a Rare None stated ASMESecXI None given 24 dropped or immovable control rod.
IWB&PS Tech Spec.
Req.
25 26 27 28 29 30 Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 31 CRDM.
IWB& PS Tech Spec.
Req.
Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 32 CRDM.
IWB&PS Tech Spec.
Req.
Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 33 CRDM.
IWB&PS Tech Spec.
Req.
Table A.1 Gall Report for NRC Generic Letters Page 1A Document: GL Letters, NRC Generic Letters, 1989-1994 Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp S b u component M
. I aterlas M
f tu anu ac rer ARD h
mee amsm ARD ff e eets 1 Cooling System Feedwater piping Not stated Carbon steel Not stated ERO/CORR Wall thinning 2 Cooling System Feedwater piping Nozzles Not stated General Electric Co, FATfTHERM Cumulative fatigue damage 3 Cooling System Steam generator and Supports Not stated Not stated EMBR/IR Loss of fracture coolant pump toughness 4 Cooling System BWRprimary Not stated Type 304 stainless General Electric Co. CORR/IGSCC Crack initiation and system piping steel growth 5 Cooling System Piping, heat Not stated Various Not stated BIO Buildup of deposits exchangers, and other components 6 Containment system Reactor pressure Not stated Not stated Not stated EMBR/IR Loss of fracture vessel toughness
Table A.1 Gall Report for NRC Generic Letters Page 18 Document: GL Letters, NRC Generic Letters, 1989-1994 Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Erosion/corrosion caused by high-velocity Moderate NUREG-1344 Implement long-term erosion-89-08 1
flow of water through piping has caused corrosion monitoring programs. [4]
several incidents of piping failure or wall thinning below ASME Code a1lowables.
Fluctuations in water temperature within Frequent NUREG-0619 Not stated 89-21, p.
2 BWR vessel in nozzle region produces 5
high-cycle fatigue and resulting crack initiation and growth in nozzles.
Fracture toughness of support materials Not stated NUREG-0577 Maintain minimum temperature 89-21, pp.
3 may be inadequate, creating the potential above fracture transition 6
for fracture or lamellar tearing in service.
temperature; replace supports it necessary [4]
The gradual buildup of macroscopic Frequent NUREG/CR-5210; Implement surveillance and control 89-13; 89-4 biological fouling organisms (e.g., blue NUREG/CR-5234 program outlined in Generic Letter 13,Suppl.
mussels, American oysters, Zebra 89-13[4]
1 mussels, and Asiatic clams) inhibits coolant flow, ultimately resulting in flow rates below technical speCifications.
Combination of residual or service Formerly frequent NUREG-D313 Follow recommendations in 89-21, p.
5 stresses, sensitization from welding, and NUREG-0313. [4]
11 oxygenated cooling water can cause IGSCC of piping, resulting in leakage.
Neutron irradiation over extended time Not stated NUREG-Follow NUREG-0744 methods for 89-21, pp.
6 periods can cause embrittlement of the 0744;ASTM E-evaluating Charpy upper shelf 5-6,16; reactor pressure vessel material, 185;Reg. Guide impact strength. [4]
92-01, particularly near the beltline, resulting in 1.99, Rev. 2 Rev. 1 loss of impact resistance and possible failure in a severe pressurized overcool evenl
Table A.1 Gall Report for Information Notices Page 1A Document: IN&B 1989, 1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL Item System StructurelComp Subcomponent Materials Manufacturer AR D h
mee amsm A RD ff e eets 1 Cooling system Valves Carbon steel valve Carbon steel Not stated ERO/CAV Loss of material bodies 2 Cooling system Coolant pump Pump shaft A-286 Byron Jackson FAT Cumulative fatigue damage 3 Cooling system Coolant pump Ring surrounding Not stated Byron Jackson Not stated Not stated bearing housing 4 Cooling system Steam generator Tubing mechanical Inconel600 Westinghouse CORR/PWSCC Crack initiation and plugs growth 5 Cooling system Steam generator Tubing mechanical Inconel600 Babcock & Wilcox CORR/PWSCC Crack initiation and plugs growth 6 Cooling system Steam lines Atmospheric dump Not stated Control CONTAM Loss of desired valves Components, Inc.
surface properties 7 (Various water Pumps Impeller, bushings, Brass bushings; Not stated ERO/CAV; VIBR Loss of material; systems) and other intemal other materials not physical damage components stated.
8 Electrical control Electrical cable Neoprene Not stated ELE-TEMP Chemical and system insulation chloroprene and physical degradation other organic polymers 9 Turbine High-press. steam 14-in. piping Carbon steel Not stated ERO/CORR Wall thinning extraction line 10 Containment system Containment Steel shell (Carbon?) steel Not stated CORR/BA Loss of material structure Document: IN&B 1990,1990 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL ISS elC Sb tem ;ystem tructur omp u componen t M
- I aterla s M
f tu anu ac rer ARD h
mee anlsm ARD ff ts eee 1 Service water Check valve Swing arm 17-4 PH stain-less Borg-Wamer CORR/SCC Crack initiation and system steel, H1100 heat growth treatment 2 Service water Motor-operated Valve seat Not stated BIF/General Signal ENVIR Physical degradation system butterfly valve Corp.
3 Service water Piping and heat Valve seat Not stated Not stated CONTAM Buildup of deposits system exchangers
Table A.1 Gall Report for Information Notices Page 18 Document: IN&B 1989, 1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to F.,
al ure Reported progs RI e.progs R
rtR epo ecommen d ti a ons P age N o. tern Significant localized wall thinning of 16-Not stated Not discussed in Not stated 89-01 1
and 24-in. valve bodies apparently caused report by cavitation can lead to rupture.
Abrupt dacoupling of pump shaft and Not stated Not discussed in Use improved vibration monitoring 89-15 2
impeller probably caused by shaft fracture report system to detect growing cracks in or failure of cap screws and drive pins, shaft [2]
resulting in pump failure. Root cause is undetermined, but possibly fatigue.
Failure of attachment weld was repaired Not stated Not discussed in Repair with full-penetration welds 89-20 3
by fillet welds that failed four years later, report and realignment of ring. [2J resulting in pump failure and loose parts in the recirculation loop.
Intergranular cracking, apparently Not stated Not discussed in Replace plugs from suspect heats 0 89-33; 4
associated with improper heat treatment report material; discontinue use of Bull. 89-andlor susceptible heats of material, can Westinghouse plugs. [4]
01,89-01, cause mechanical tube plugs to loosen, Suppl. 1 8 leak, and sometimes be forcibly ejected,
- 2.
causing additional tube damage.
Intergranular cracking, apparently Not stated NRC Bull. 89-01 Conduct eddy current inspections of 89-65 5
associated with intragranular carbides and installed plugs. [4]
relatively little intergranular precipitation improper heat treatment and susceptible heats of material, could lead to possible plug failure.
Foreign particles from steamlines lodge in Not stated Not discussed in Design modifications have been 89-38 6
valve clearance areas and on sealing report implemented by the manufacturer [1]
surfaces, resulting in leakage past valve plug piston ring and consequent valve malfunctioning.
Repeated operation of the pumps at 60%
Not stated Not discussed in Avoid sustained operation of pumps 89-08 7
or less of their design flow resulted in report at low flow rates [4]
slow deterioration of internal components, causing eventual loss of pump function.
Prolonged exposure of electrical cable Not stated NRC Temporary Provide better containment cooling tc 89-30 8
insulation to temperatures above their Instruction 2515/98 maintain temperatures below the EO environmental qualification (EO) design temperature [4J temperature, e.g., in reactor containment, can lead to insulation breakdown and failure.
Abrupt change in 1.0. at nozzle-to-pipe Not stated NRC BUll. 87-01 Not stated 89-53 9
connection apparently causes flow turbulence, leading to accelerated erosion-corrosion of adjacent piping.
Boric acid leaking from instrument line Not stated 10CFR50, Appendix Containment in-service inspection 89-79; 89-10 compression fittings condenses on the J
for wall thinning by corrosion [4]
79, Suppl.
outer surface of the containment steel 1
shell, resulting in general and pitting corrosion.
Document: IN&B 1990,1990 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Effect of Agil!g on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Preexisting casting defects, including Not stated Aerospace Materials Replace with parts from another 90-03 1
porosity, hot cracks, and weld repairs, Spec. 5398A and vendor; inspect parts for flaws plus improper heat treatment, resulted in Mil. Spec. MIL-H-before installation. [4]
propagating cracks in the high chloride 6875 service water that caused fracture and loss of function.
Valve seat material hardens with time Not stated GL89-10 Set open torque switch to maximum 90-21 2
under service conditions, causing value; test and inspect valves. [4]
increase in coefficient of friction and possible failure of valve to open.
AccumUlation of silt and corrosion Not stated 10CFR50, Append.
Cleaning of contamination and 90-39 3
products in piping reduced emergency AandB adjustments in flow distribution [4]
water flows to levels below deSign basis conditions.
Table A.1 Gall Report fot Information Notices Page 2A Document: IN&B 1990,1990 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System StructurelComp Subcomponent Materials M anu acturer ARC h.
mec an Ism ARC ff ts eec 4 Service water Containment air Tubes Not stated Not stated CONTAM Buildup of deposits system coolers 5 Service water Service water lines Check valves Not stated Not stated CONTAM Buildup of deposits system 6 Service water Piping Not stated Not stated CORR; CORRIMIC Loss of material; system corrosion product buildup 7 Cooling system Steam generator Upper shell-to-Not stated Westinghouse and CORR; Loss of material; transition cone girth Combustion FATITHERM cumulative fatigue welds Engineering damage 8 Cooling system Steam generator Tubes Not stated Westinghouse and CORRfSCC Crack initiation and Combustion growth Engineering 9 Cooling system Pressurizer Pressurizer heater Inconel600 Not stated CORRfPWSCC Crack initiation and thermal sleeves growth 10 Cooling system Coolant pumps Bolts fastening A453, Gr. 660 (Alloy Not stated, but CORR/IGSCC Crack initiation and turning vanes A-286) similar to growth Westinghouse design 11 Pressure vessel Pressure vessel Weld cladding and Not stated Not stated CORRfSCC Crack initiation and upper head base-metal heat-growth affected zone Document: IN&B 1991, 1991 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARC mechanism ARC effects 1 Cooling system Moisture separator 6-inch, schedule 40 Garbon steel Not stated EROfCORR Wall thinning drain piping 2 Cooling system Feedwater regulating 6-inch piping Carbon steel Not stated ERO/CORR Wall thinning valve bypass line 3 Cooling system Low-pressure drain Piping Garbon steel Not stated EROfCORR Wall thinning system 4 Cooling system Row-measuring-Orifice flange Garbon steel Not stated EROfCORR Wall thinning orifice 5 Cooling system Moisture separator 8-inch elbow Carbon steel Not stated EROfCORR Wall thinning reheater 6 Cooling system Steam generators Feedwater Carbon steel Combustion FATITHERM;EROf Cumulative fatigue distribution feedring Engineering CORR damage; wall piping thinning
Table A.1 Gall Report for Information Notices Page 2B Document: IN&B 1990,1990 NRC Information Notices RevieWed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Buildup of.silt and corrosion products in Not stated 10CFR50, Append.
Remove deposits (4) 90-39 4
containment air cooler tubes reduced AandB service water flow rates to unacceptable levels.
Buildup of silt in emergency water service Not stated 10CFR50, Append.
Remove deposits (4) 90-39 5
line check valve could have prevented AandB system trom functioning.
Acidic well water and MIC have resulted Not stated 10CFR50, Append.
Chemically clean system and/or 90-39 6
in a corrosion pitting rate of 24 mils per AandB replace pipe (4) year in the affected components.
Corrosion fatigue from thermal cycling, Not stated Not discussed in Perfonn more frequent inspections 90-04 7
dissolved oxygen in feedwater, and Cu report of affected region. (4) alloys in feedwater system result in crack initiation at surface corrosion pits and subsequent crack growth into girth welds.
Secondary side-initiated cracking of Not stated Not discussed in Plug leaking tubes; develop 90-49 8
steam generator tubes, typically in the report improved NDE techniques to detect expansion transition near the tubesheet or cracks (4) at the support plate, has resulted in leaking cracks in several PWRs.
Residual stresses from reaming or roll Not stated Not discussed in Implement augmented inspection 90-10 9
joining plus a susceptible Inconel 600 report program. (4) microstructure and the PWR coolant environment lead to PWSCC and leakage.
Alloy A-286 is subject to IGSCC at peak Not stated B&WOwner's Discontinue the use of Alloy A-286 90-68 10 stresses> 100 ksi, depending upon Cr Group Report BAW-as a reactor structural material. (4) content, fabrication practice, and 1842 environment The present failures occurred in foreign reactors and threatened coolant pump function.
Grinding residual stresses, low delta-Not stated General Electric Co.
PT of back-clad region for surface 90-29 11 ferrite content, and high dissolved-oxygen RICSIL No. 050 cracks and enhanced UT for in the coolant induce interdendritic SCC subsurface cracks. (4) of weld cladding, and resulting cracks propagate into underlying base metal, possibly threatening structural integrity.
Document: IN&B 1991, 1991 NRC Information Notices RevieWed by:
Dwight R. Diercks, ANL Eff t fA' C
F ti C
tr'b t F 'I eco,gmg on omponent unc on on I 0
al ure R rted epo progs RI el.progs R
rtR epo d ti ecommen a ons P age N lte
- o.
m High-velocity turbulent flow of water Not stated Not discussed in System found to be susceptible by 91-18 1
through piping caused wall thinning by report EPRI CHEC code and should have erosiOn/corrosion and resulted in pipe been inspected (4) rupture and actuation of fire-protection deluge system.
High-velocity turbulent flow of water Not stated Not discussed in Failed piping replaced (4) 91-18 2
through piping caused wall thinning by report erosion/corrosion and resulted in steam leak and repair outage.
High-velocity turbulent flow of water Not stated Not discussed in Failed piping temporarily replaced 91-18 3
through piping caused wall thinning by report with A106, Gr. B; permanent erosion/corrosion and resulted in piping replacement to be A335-P22. (4) rupture.
High-velocity turbulent flow of water Not stated Not discussed in Failed flanges temporarily replaced 91-18 4
through piping caused wall thinning by report with same material; more-resistant erosion/corrosion and resulted in flange material being considered for rupture.
permanent replacement [4)
High-velocity turbulent flow of water Not stated Not discussed in System found to be susceptible by 91-18, 5
through piping caused wall thinning by report CHECMATE code and should have Suppl. 1 erosiOn/corrosion and resulted in elbow been inspected (4) rupture and actuation of fire-protection del~e system.
CraCking and wall thinning resulted in Not stated Not discussed in Component redesigned for 91-19 6
component failure and introduction of report increased strength and erosion loose parts into secondary side of steam resistance. (4) generator.
Table A.1 Gall Report for Information Notices Page 3A Document: IN&B 1991,1991 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System Str S b ucturelComp u component M t. I a erla s M
f t
anu ac urer ARC mec h amsm ARC ff ts eec 7 Cooling system Stearn generators Tubing Not stated Mitsubishi (based on FAT Cumulative fatigue Westinghouse damage design) 8 Cooling system Steam generators Tubing Not stated Combustion Not stated Not stated Engineering 9 Cooling system Stearn generators Tubing Not stated Babcock & Wilcox FAT Cumulative fatigue damage 10 Cooling system Hnch accumulator Nozzle-to-pipe weld Not stated Not stated FAT; VIBR Cumulative fatigue fill line damage; crack initiation and growth 11 Cooling system Condensate storage Diaphragm Not stated Goodyear Co.; Lorel ENVIR Chemical or physical tanks Corp.
degradation Document: IN&B 1992,1992 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System S tructurelComp Subcomponent Materials M anu acturer h
ARC mec anism A RC ff e ects 1 Cooling system Stearn generators 4-inch, schedule 80 A 1 06B carbon steel Westinghouse ERO/CORR Wall thinning feedwater piping 2 Cooling system Primary coolant loop Reducing tee riser Not stated Not stated ERO/CORR Wall thinning 3 Cooling system Pressurizer power-Valve stems SA 564, Type 630, Rockwell EMBRITE Loss of fracture operated relief valve~
H900-H1150 (17-4 International (now toughness PH) stainless steel Edward Valve Co.)
4 Emergency Manual gate valves Valve bodies CF8M cast stainless Not stated FAT Cumulative fatigue condenser system steel damage 5 Reactor internal Core shroud support Welded access hole Inconel 600 with General Electric CORR/IGSCC Crack initiation and support structure plate Inconel 82 or 182 growth weld filler metal Document: IN&B 1993, 1993 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System StructurelComp Subcomponent Materials Manufacturer ARC mechanism ARC effects 1 Emergency Core Residual heat Thrust bearing Not stated Ingersoll-Rand WEAR Attrition Cooling system remOVal pump 2 Emergency Core Residual heat Discharge check Not stated Copes-Vulcan FAT Cumulative fatigue Cooling system removal pump valve lock wire damage 3 Emergency Core Residual heat Discharge check Stainless steel Pacific Valve VIBR Loosening Cooling system removal pump valve disk and locking device; other Engineering hanger assembly parts not stated
Table A.1 Gall Report for Information Notices Page 38 Document: IN&B 1991,1991 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Eft F
°b F*I eet of Agi'lg on Component unction Contrl to al ure R eport ed progs RI el.progs R
rtR epo d ti eeommen a ons P age N It
- o.
em High-cycle fatigue failure of steam Not stated Not discussed in Incorrect insertion of aritivibration 91-43 7
generator tube at uppermost support plate report corrected [4]
resulted in excessive primary-to-secondary leak rate.
Cracking of steam generator tube at U-Not stated NRC Bull. 88-02, Not stated 91-43 8
bend at a location where flow conditions Fig. 1 permit contaminants to be deposited on the tube surface resulted in excessive primary-te-secondary leak rate.
Tube cracking at lower face of upper Not stated NRC Bull. 88-02, Not stated 91-43 9
tubesheet resulted in excessive primary-Fig. 1 to-secondary leak rate.
Two ruptures of the nozzle-to-pipe weld in Not stated Not discussed in Revise operation procedures [4]
91-50 10 the accumulator fill line during filling were report caused by flow-induced vibration and resulted in spillage of coolant.
Long-term deterioration of diaphragms in Not stated Not discussed in Replace diaphragms after 9 years or 91-82 11 contact with their service environment report more frequently if indicated by results in the development of holes and inspections. [4]
tears, with consequent leaks and possible clogging of eqUipment.
Document: IN&B 1992,1992 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Eft eet of Aging on Component Function Contrib to Failure Reported progs Re~rogs Rep~rt R d.
eeommen ations P age N o. tem High-velocity flow of water through piping Not stated Not discussed in Redesign piping to reduce flow 92-07 1
caused wall thinning by erosion/corrosion report velocity. [4]
and necessitated the replacement of 90 feet of piping for which the wall thickness was at or near the minimum allowable.
High-velocity flow of water through Not stated NRC Bull. 87-01; Not stated 92-35 2
reducing tee riser caused wall thinning by NRC GL89-08 erosion/corrosion and necessitated com-ponent replacement because wall thick-ness was near the minimum allowable.
Valve stems are subject to secondary Not stated Not discussed in Not stated 92-60 3
aging after several thousand hours at 600 report F, resulting in increased susceptibility to fracture when subjected to excessive torgue from power actuator.
Fatigue (possibly thermal) resulted in Not stated Not discussed in Not stated 92-50 4
leaking cracks in at least one gate valve report and partially through-wall cracks in several other valves.
Apparent IGSCC of welds joining access Not stated GE SIL No. 462, Perform periodic visual and UT 92-57 5
hole covers to shroud support plates Suppl. 3 examinations of region; repair resulted in circumferential cracking in procedures being developed [4]
weld region, with some cracks possibly propagating into the adjacent base metal.
Document: IN&B 1993, 1993 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Eftect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Thrust load during normal operation Not stated Not discussed in Redesign pump to reduce bearing 93-08 1
exceeded design value, resulting in report load; replace periodically. [4]
abnormally high wear of bearing and failure after approx. eight fuel cycles.
Inadequate disk nut torquing allowed nut Not stated Not discussed in Replace lock wire with 1/B-in. cotter 93-16 2
to rotate back and forth. Resulting cyclic report pin [4]
loading caused high-cycle fatigue failure of lock wire, loss of disk nut and washer, and check valve failure.
Inadequate capscrew torquing, missing Not stated Not discussed in Revise maintenance procedure to 93-16 3
capscrews, and improper reuse of locking report ensure correct installation. [4]
device results in capscrew loosening, loss of disk and hanger assembly, and check valve failure.
Table A.1 Gall Report for Information Notices Page 4A Document: IN&B 1993,1993 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL It S
t S
e/C S b em sysem tructur omp u com~onen M t. I a erlas M
f tu anu ac rer ARD mec h amsm ARD ff ts eec 4 Emergency Core Residual heat Coolant pump Not stated Not stated CLOG Blockage of flow Cooling system removal pump strainers and passages containment sump screens 5 Emergency Core High-pressure Steam exhaust Stainless steel Black Sivalls &
Not stated Not stated Cooling system coolant injection rupture disk Bryson, Inc.
pump 6 Cooling system Steam generators Feedwater piping Not stated Westinghouse and FATITHERM Cumulative fatigue Combustion damage Engineering 7 Cooling system Piping Feedwater piping Carbon steel Not stated ERO/CORR Wall thinning and other components 8 Cooling system Turbine-driven Turbine stop valve Not stated Not stated CONTAM Loss of lubricant feedwater pumps properties 9 Cooling system Motor-operated gate Valve yoke Case carbon steel Walworth FAT Cumulative fatigue and globe valves damage 10 Cooling system Jet pump Hold-clown beam Not stated General Electric Co. CORR/IGSCC; FAT Crack initiation and growth; cumulative fatigue damage 11 Spent fuel storage Spent fuel storage Boraflex neutron Polymer base with Brand Industrial ENVIR Physical degradation system racks absorbing material silica filler and Services, Inc.
neutron absorber (boron?)
12 Reactor internals Core shroud Beltline region welds Stainless steel General Electric Co. CORR/IGSCC Crack initiation and growth 13 Reactor internals Fuel rods Fuel rod cladding Zircaloy Westinghouse, WEAR/FRET Attrition Siemens, General Electric Co.
Document: IN&B 1994,1994 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Electrical generating Turbines Turbine blades Not stated General Electric Co. FAT Cumulative fatigue system damage 2 Electrical generating Turbine low auto Plunger rod, stainless steel and Not stated CORR Corrosion product system stop oil pressure bushing, and case aluminum buildup switch 3 Cooling system Steam generator Kinetically weld-Inconel600 Babcock & Wilcox CORR/PWSCC Crack initiation and repaired tubes growth
Table A.1 Gall Report for Information Notices Page 4B Document: IN&B 1993,1993 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Eft fA' F
F ecto I9Inq on Component unction Contrib to,ailure Reported progs R el.progs Report Recommendations P aqe N o. tem Foreign debris can block emergency core Not stated Not discussed in Remove debris [4]
93*34 and 4
cooling screens and sumps, resulting in report 93*34, possible reduced emergency core cooling Suppl. 1 in and accident situation, Rupture disk failed unexpectedly after 20 Not stated Not discussed in Replace 20*year*old rupture disks 93*67 5
years of service, resulting in personal report with new ones, [4]
injUries. Cause of failure is unclear, but vendor speculated that an unspecified aging process may have caused the strength to degrade.
Thermal stratification in feedwater lines, Frequent NUREG/CR-0691 Reduce severity of thermal cycles.
93*20 6
particularly during cold, low-flow
[4J conditions, leads to rapid thermal fatigue loading, resulting in cracking and leakage.
Erosion/corrosion has been observed to Frequent ASME Section XI, Develop improved inspection and 93-21 7
cause excessive wall thinning and IWA 4100 and 4300 repair procedures in accordance possible piping failure in numerous plants.
with ASME Section XI. [4J Inspection and repair procedures are often inadequate.
Gradual buildup of contaminants in the Not stated Not discussed in Flush oil system [4J 93-48 8
control oil for the stop valve on the report turbine-driven feed water pump caused the valve to stick open when the main turbine tripped, resulting in overfill of the pressure vessel.
Preexisting defects, component design, Not stated Not discussed in Weld repair cracks; torque bolts 93-97 9
and insufficient bolt torque can lead to the report sufficiently when reinstalling yokes.
initiation and growth of fatigue cracks that
[4J could cause eventual component failure.
IGSCC that initiated at a machined radius Not stated Not discussed in Replace beams of similar design if in 93-101 10 propagated over -80% of the cross-report service for more than 8 years. [4]
sectional area. The resulting loss of preload apparently led to fatigue crack growth and eventual component failure.
Surveillance coupons of Boraflex tested Not stated EPRI TR-101986 Not stated 93-70 11 after five years had degraded substantially. Similar degradation of the Boraflex used in the high-density spent fuel storage racks would result in loss of subcriticality margin in the pool.
IGSCC in the HAZ of core shroud circum-Not stated GE RICSIL 054, Add stiffening braces to the top 93-79 12 ferential welds near the beltline resulted in Rev. 1 portion of the shroud. [4) axial cracking that may compromise the structural integrity of the shroud.
Debris-induced fretting and grid-te-rod Not stated Not discussed in Install vibration damping; redesign 93-82 13 flow-induced vibrational fretting can lead report core to reduce vibration. [4) to cladding perforation and fuel rod failure.
Document: IN&B 1994,1994 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Torsional excitation of the turbine-Not stated Not discussed in Not stated 94-01 1
generator shaft from an electrical system report disturbance causes vibration, resulting in separation of turbine blades by high-cycle fatigue.
Apparent galvanic corrosion between the Not stated Not discussed in Not stated 94-11 2
SS plunger rod and the remaining AI parts report caused corrosion product buildup and switch malfunction, resulting in an erroneous signal to the control computer and turbine overspeed.
Tubes repaired with kinetically welded Not stated Not discussed in Not stated; problem still under 94-05 3
sleeves may be susceptible to PWSCC report investigation [4) adjacent to the sleeve because of residual stresses introduced, despite the post-weld heat treatment. Result is tube leakage.
Table A.1 Gall Report for Information Notices Page SA Document: IN&B 1994, 1994 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp Subcomponent
. I Materlas M anu acturer A RDmechamsm ARDeffects 4 Cooling system Main steam isolation Guide ribs Not stated Atwood & Morrill WEAR Attrition valve Co., Inc.
5 Cooling system Standby service Bolts and Carbon steel Not stated CaRR Loss of material water pump lockwashers in shaft coupling assemblies 6 Cooling system Pipe snubbers Internal lubricant Hydrocarbon grease Pacific Scientific ELE-TEMP Chemical and physical degradation 7 Emergency core Air dampers and Elastomer seals Buna-N Not stated ELE-TEMP Chemical and cooling system solenoid valves physical degradation 8 Emergency core Shutdown cooling Sealing surfaces of Stellite Anchor-Darling RESID; Crack initiation; cooling system suction isolation valve disk and slide FATITHERM cumulative fatigue valves seat ring damage 9 Emergency core High-pressure Torque switch drive AISI1070 carbon Umitorque EMBR; ENVIR Loss of fracture cooling system coolant injection pinion gear roll pin steel toughness; chemical motor-operated valve and physical degradation 10 Emergency core High head safety Pump casing Carbon steel clad Dresser Industries, Not stated; Crack initiation and cooling system injection pump with stainless steel Pacific Pump CORR/BA growth; loss of Division material 11 Reactor internals Core shroud Core plate support Stainless steel General Electric CORR/IGSCC Crack initiation and ring weldment Company growth
Table A.1 Gall Report for Information Notices Page 58 Document: IN&B 1994,1994 NRC Information Notices Reviewed by:
Dwight R. Diercks, ANL Effect of Aging on Component Function Contrib to Failure Reported progs ReJ.progs Report Recommendations Page No. Item Improper clearances between valve Not stated NRC Inspect. Rept.
Install anti-rotation modification from 94-08 4
poppet and body can cause excessive 50-458/93-18 manufacturer [4]
wear of guide ribs, resulting in failure of valve to close properly.
Extensive general corrosion of the bolts Not stated Not discusses in Rebuild pumps; modify testing 94-45 5
and lockwashers in the pump shaft report procedure to detect internal changes coupling assemblies caused shifting of before severe damage occurs. [4]
intemal parts and damage to impellers and bowls, resulting in degraded vibration performance.
Prolonged exposure to temperatures of 38 Common Not discussed in Replace failed snubbers; develop 94-48 6
to 93 deg. C caused the internal lubricant report criteria for service life program. [4]
grease to bake and dl)' ou~ resulting in insufficient drag resistance during testing.
Prolonged exposure to elevated temper-Not stated Not discussed in Replace affected components with 94-06 7
arures causes the Buna-N elastomer seal report qualified replacements. [4]
material to break down, resulting in leak-age of the nitrogen supply for the auto-matic depressurization valves and possible failure of these valves in a LOCA situation.
High residual stresses from inadequate Not stated Not discussed in Not stated 94-30 8
stress relief or thermal fatigue led to the report initiation and growth of cracks in the sealing surfaces of the valves, resulting in excessive valve leakage.
Brittleness of roll pin material, possibly Not stated Not discussed in Replace with larger diameter pin 94*49 9
combined with hardening of grease in report fabricated of Type 416 stainless drive mechanism in one case, caused steel for better ductility and impact shear fracture of pin under load, resulting resistance. [4]
in failure of valve.
Cracking of the stainless steel cladding Not stated Pacific Pump Perform field inspections deSCribed 94-63 10 from an unidentified cause leads to Bulletin 037-0-0104-in Pacific Pump Bulletin 037-0-0104 exposure of the underlying carbon steel, 0
O. [4]
which corrodes relatively rapidly in contact with boric acid in the coolant.
IGSCC in and near the HAZ of the Not stated GE RICSIL 054, Safety implications under 94-42 11 outside circumference of the core plate Rev. 1 investigation by NRC. [4]
support ring weldment resulted in a 360 circum-ferential crack with a max. depth of -2.13 cm in two different reactors.
Table A.1 Gall Report for Licensee Event Reports Page 1A Document: LER's, Ucensee Event Reports (LERs)
Reviewed by:
Ma and K. E. Kasza, ANL It S
Str tue/C S b em :i}'stem uc r omp u componen t M t. I a erla s M
f tu anuac rer ARD h
mec amsm ARD ff ts eec 1 Control Rod Drive Scram Solenoid Pilo t Pressure and Rubber Automatic Switch ELE-TEMP Hardening, cracking Valves Exhaust Diaphragms Company 2 Control rod drive Scram solenoid pilot Diaphragm Buna-N General Electric EMBR Loss of fracture valves toughness 3 Containment Personal Airlock Door Shaft Seal Not stated Not stated WEAR Attrition Range Bolts 4 Containment Main Steam Isolation Seat Surfaces, Not stated Not stated WEAR, RATCH Attrition, change in Valves Actuator Spring dimension 5 Containment Vent Valve Seal Nitrile Elastomer Atwood and Morrill WEATH Loss of capacity Co.
6 Containment H2I02 gas analyzer Analyzer pump Not stated Teledyne Not stated Not stated diaphragm 7 Penetration Inboard Containmen Boot Seal Not stated Not stated ENVIR Chemical or physical Pressurization Purge Exhaust degradation System Valves 8 Condenser System Low Pressure Exhaust Boot Seal Fabric Reinforced Uniroyal FAT Cumulative Fatigue Turbines Rubber Damage 9 Feedwater Check Valve Seal Rubber (Parker Not stated ELE-TEMP/ERO Physical E692) degradation, loss of material 10 Hot Leg Loop Isolation Valve Valve Stem 17 4PH Stainless Not stated CORR/SCC Crack initiation and Steel (ASTM A 56M growth Type 630) 11 Auxiliary Feedwater Pump Pneumatic Different Pressure Not stated Not stated EDS (setpoint drift)
Loss of function Speed Control Loop Transmitter 12 Emergency diesel Fuel oil injector Injector screw Not stated Nordberg Not stated Not stated generator pump 13 Spent fuel pool Charcoal absorber Seal on bypass Rubber Johnson Controls Not stated Not stated exhaust ventilation damper blade edge 14 Spent fuel pool Charcoal absorber Damper blades Not stated Johnson Controls Not stated Not stated exhaust ventilation 15 Fail-safe 2 way solenoid valve Seal O-ring Not stated Versa Product Co.
FAT Cumulative fatigue accumulator damage 16 Power system Steam generator Tube Not stated Combustion CORRIIGSCC Crack initiation and Engineering System-growth 80
Table A.1 Gall Report for Licensee Event Reports Page 18 Document: LER's, Ucensee Event Reports (LERs)
Reviewed by:
Ma and K. E. Kasza, ANL Effect of Aging on Component Function Contrib to Failure Reported pro(Js Rel.pro(Js Report Recommendations Page No. Item Control rod failed to scram due to Frequent Not discussed in PSTS Req.
Use of new diaphragm material [2]
94-005-01 1
degradation of pilot valve elastomers report (hardening, cracking and permanent set) caused by high temperature produced by the energized solenoid coils.
Control air leakage through degraded Not applicable Not discussed in PSTSReq.
Not stated 94-005-00 2
solenoid diaphragms rendered valve report inoperable and failure to scram a control rod resulted.
Excessive force to support shaft bearing Moderate Not discussed in 10CFR50 App. Including inspection of the shaft seal 92-026-00 3
and increased use of the airlock caused report J & PS TS gasket bolts in plant maintenance the shaft seal flange to loosen and move Req.
and inspection [4]
away from its seating, resulting in test pressure drop below criteria of containment airlock leakage test.
During local leak rate testing, the leak rate, Frequent Not discussed in PS TS Req.
Replace springs on regular basis [4] 92-013-01 4
limit was exceeded due to degraded valve report seal seat surfaces (misalignment of the poppet seat caused by wear of the guide ribs.)
Leakage of rubber seal attributed to Not stated Not discussed in PS TS Req.
The failed seal was replaced and the 89-005-00 5
weather checking on exposed surface and report leak rate met acceptance cri teria.
storage causing unacceptable leakage in To prevent recurrence, both shelf life an Appendix J Type B leakrate test.
and durometer testing requirements shall be considered in the I procurement documents [4J Incorrect readings of oxygen Not applicable Not discussed in PS TS Req.
Not stated 92-009-00 6
concentration because of air leak into report analyzer.
Environmental aging of seal material Not stated Not discussed in ASMESecXI Not stated 93-001-00 7
caused leakage of PPS exceeding report
& PS TS Req.
allowable rate. Seating area was cleaned and the leakage stopped.
Loss of condenser vacuum due to fatigue Moderate Not discussed in PSTS Req.
Replace entire boot seal rather than 92-010-00 8
failure of the north low pressure turbine report performing local repair [2]
eXhaust boot seal (a fabric reinforced rubber expansion joint), causing an automatic turbine trip and reactor trip.
Leakage of rubber seal due to thermal Frequent Not discussed in ASMESecXI Replace the soft seal material 86-017-01 9
aging and erosive wear, causing report IWV& PSTS (Parker E692) with a new material excessive leak rate of the check valves, Req.
more resistive to thermal aging and erosive wear than the original [4]
Crack due to tensile stress on the stem Infrequent Not discussed in ASMESecXI To minimize the in service stresses, 86-008-01 10 and entrapped water propagated through report IWV& PSTS the valves will be soft back seated the valve stem diameter, resulting in the Req.
during plant heatup and hard back valve gate being in a partially closed seated only when operating position.
temperature is reached [4]
Inoperability of the pump pneumatic Not stated Not discussed in PSTS Req.
Record turbine steam bowl 89-016-0:;;
11 speed control loop due to leaking bellows, report pressures, including the speed setpoint drift, limited pump speed and control loop. In the preventive discharge pressure below that needed to maintenance/calibration program at inject water into the steam generators initial plant startup, perform periodic under some accident conditions.
full flow test [4]
Emergency diesel generator not operable Not applicable Not discussed in PSTS Req.
Not stated 92-009-00 12 to allow fixing of injector pump.
report Over time the rubber seals lose pliability Not applicable Not discussed in PS TS Req.
Not stated 92-008-00 13 and allow leakage in the ventilation report system.
Bent damper blades prevented sealing Not applicable Not discussed in PS TS Req.
Not stated 92-008-OC 14 and caused leakage in the ventilation report system.
Deterioration of O-ring caused control air Not applicable Not discussed in PS TS Req.
Not stated 93-005-00 15 leakage and failure of solenoid to meet report specs.
Rupture of tube causes leakage leading to Not applicable Steam Generator ASMESecXI Not stated 93-001-0:;;
16 low pressurizer level and pressure Task Force formed IWB& PSTS causing reactor trip and radiation in Req.
secondary system.
Table A.1 Gall Report for Licensee Event Reports Page 2A Document: LER's, Ucensee Event Reports (LERs)
Reviewed by:
Maand K. Kasza, ANL Item System S
e/C S b tructur omp u component Materials Manufacturer ARD mechanism ARDeffects 17 Main steam line Isoiation valve (globe Seat Not stated Atwood and Morrill CORR/PIT Local loss of materia valve)
Company Inc.
18 Main steam line Isolation valve (globe Seat Not stated Atwood and Morrill CREEP Change in valve)
Company Inc.
dimension 19 Essential cooling Traveling screen Flexible coupling Elastomeric Rexnord ENVIR Chemical or physical water filter degradation 20 Not stated High Pressure Auto Stop Oil Une Not stated Not stated RESID/FAT Crack initiation, Turbine Stop Valve cumulative fatigue damage 21 Penetration Inboard Containmen Seal Seat Not stated Not stated ENVIR Chemical or Physica Pressurization Purge Exhaust Degradation System Valves 22 Emergency Power Diesel Generator Fuel Oil Not stated Not stated OX Buildup of Deposit System 23 Emergency Power Diesel Generator Fuel Oil Not stated Not stated OX Buildup of Deposit System 24 Containment Spray Heading Piping Spray Nozzle Piping: Carbon Steel Not stated CLOG Blockage of flow System passages 25 Fire Protection 3-hour Fire-rated Penetration Fire Seal Silicone Foam Not stated Improper Loss of Function Barriers installation/lack of inspection rqmt.
26 Steam Generator Air-operated Valve Actuator Rubber Not stated ENVIR Physical Blowdown OuUet Isolation Valve Rubber Diaphragm Degradation 27 Not stated Main Condenser Expansion Joint Rubber Not stated ENVIR Physical Degradation 28 Not stated Turbine Low Pressure Rubber Uniroyal FAT Cumulative Fatigue Exhaust Boot Seal Damage 29 Emergency Cooling Motor-operated Not stated Not stated Not stated Improper Switch Loss of Function System and Valves Setting Containment Spray System 30 Primary Containmen Isolation Valves, O-rings, Seat Rings, Ethylene-propylene, Various ENVIRIWEAR Physical Isolation System Reactor Vessel Gaskets Rubber Degradation, Attritior Stabilizer Hatch 31 Containment Electric Penetration Seals Polyurethane Bunker Ramo Hydrolysis Physical Penetration Assemblies Degradation, Attritior
Table A.1 Gall Report for Licensee Event Reports Page 28 Document: LER's, Ucensee Event Reports (LERs)
Reviewed by:
Ma and K. Kasza, ANL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Technical specifications for leakage limits Moderate Not discussed in ASMESecXI Not stated 93-003-17 on valves is exceeded.
report
& PS TS Req.
01; 003-02 Technical specification for leakage limits Infrequent Not discussed in ASMESecXI Not stated 93-003-01 18 on valves is exceeded.
report
& PSS&T Req.
Aging of elastomeric couplings resulted in Not applicable Not discussed in PSs&TReq.
Not stated 93-010-00 19 their cracking and failure of traveling report screen filter to operate.
Turbine stop valve closure due to auto Rare Not stated PS S&T Req.
Perform visual inspection of the 89-011-00 20 stop oil line weld leak resulted in a manual accessible welds, measure vibration reactor trip and a manual safety injection.
of the auto stop oil line during plant The weld failure was due to inadequate startup [4) field installation (overlapping welds) and fatigue.
Environmental aging of seal material Not stated Not stated PS S&TReq.
Not stated 93-013-01 21 caused leakage of PPS exceeding allowable rate. Seating area was cleaned and the leakage stopped.
Oxidation of fuel oil due to a high Infrequent Not stated RG 1.9, RG Periodic replace ment of the fuel oil 89-001-00 22 concentration of insolubles clogging the 1.108 & PS TS and use of a higher grade diesel fuel sample filter, causing inoperability of Req.
oil which has a longer shelf life [4]
diesel generator.
Oxidation of fuel oil due to a high Infrequent Not stated RG 1.9, RG Periodic replacement of the fuel oil 89-001-01 23 concentration of insolubles clogging the 1.108 & PS TS and use of a higher grade diesel fuel sample filter, causing inoperability of Req.
oil which has a longer shelf life. Add diesel generator.
a biocide, a dispersant and a stabilizer to extend the shelf life. [4]
Nozzle blockage due to accumUlation of Frequent Not stated PS S&TReq.
Replacement of the CSS nozzles 90-021-00 24 the deteriorated coating of the CSS piping
& PSTS Req.
with clog resistant nozzles [4]
inner surface could block the CSS flow.
Gaps, tears, or splits due to improper Frequent Not stated PS S&T Req.
Use a different type of foam and 90-002-00 25 installation and lack of inspection different installation techniques [4]
requirements were found in the seals.
Propagation of a fire across boundary would affect the plant safe shutdown.
Failure of rubber diaphragm resulting in Not stated Not stated ASMESecXI Not stated 92-001-00 26 air leakage and failure of the valve IWV& PSS&T closure.
Req.
The air leakage through the torn Infrequent Not stated PS S&T Req.
Periodic replacement of the 92-003-00 27 expansion joint rubber belt caused low
& PSTS Req.
expansion joints [2]
vacuum in the main condenser and subsequent manual reactor and main turbine trip.
Failure of the north low pressure turbine Not stated Not stated PSs&TReq.
Not stated 92-007-00 28 boot seal due to fatigue caused condenser low vacuum and subsequent automatic reactor and turbine trip.
Isolation valves were not capable of full Frequent GL89-10 ASME Reconfigure and test the MOVs to 92-006-00 29 closure under design basis conditions due satisfy the GL89 10 criteria [4]
to improper drive gear sets and torque switch settings.
Brittle and broken O-ring seals of the Frequent Not stated 10CFR50 App. Periodic replacement of the O-rings 88-014-00 30 reactor vessel stabilizer hatch indicated J
[4]
that the ethylene propylene (EP) material is generally unable to resist harsh environments. O-rings made of silicone rubber were in good condition.
Degradation of seal material, Frequent Not stated PS S&T Req Use a more durable material, 91-011-02 31 polyurethane, due to hydrolysis would ethylene propylene rubber; install a allow moisture intrusion into the electrical silicone rubber O-ring as a backup penetration assembly during a LOCA seal; upgrade the nitrogen supply event, potentially resulting in discontinuity system to safety-grade system [4) of off-site power.
Table A.l Gall Report for NRC Bulletins Page lA Document: BL 89-01,1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL It S
em :iystem Structure/Comp Subcomponent Materials M anufacturer AR D h
mec anlsm R
ff A De ects 1 Cooling system Steam generator Tubing mechanical Inoonel600 Westinghouse CORR/PWSCC Crack initiation and plugs growth Document: BL 89-02,1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Residual heat-swing check valve Retaining block stud Type 410 stainless Anchor Darling CORR/SCC Crack initiation and removal system (bolt) steel (A193, Gr B6, growth Type 410 55)
Table A.1 Gall Report for NRC Bulletins Page 18 Document: BL 89-01, 1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL
'J Effect of Aging on Component Function Contrlb to Fal ure Reported progs Re.~ogs R eport R d
ecommen ations P89_e N o. Item Intergranular cracking, apparently Not stated Not discussed in Replace plugs from suspect heats 0 89-33; 1
associated with improper heat treatment report material; discontinue use of Bull. 89-and/or susceptible heats of material, can Westinghouse plugs. [4]
01,89-01, cause mechanical tube plugs to loosen, Suppl. 1 8 leak, and sometimes be forcibly ejected,
- 2.
causing additional tube damage.
Document: BL 89-02, 1989 NRC Information Notices and Bulletins Reviewed by:
Dwight R. Diercks, ANL Effect of ~ginR on Component Function Contrib to FaIlure Reported progs Rel.~rogs R eport R d
ecommen ations Page No. Item Susceptibility to SCC was apparently Not stated ASME SA193-B6 Inspect bolts for cracks; replace BL89-02 1
enhanced by improper heat treatment defective bolts with bolts having Rc (hardness too high), coupled with hardness <=26. [4]
presence of borated water. Resulting cracking led to bolt fracture.
A.2 Electrical Components and Systems NUREG/CR-6490
Table A.2 Gall Report for NPAR Reports Page 1A Document: BNL A-327Q-11-85, Seismic Endurance Tests of Naturally Aged Small Electric Motors Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Electric Motors Terminal Boxes Not stated Not stated CORR Improper sealing of J
the cover gaskets 2
Electric Motors Stator Winding Not stated Not stated Not stated Break down of varnish and insulation 3
Electric Motors All Other Not stated Not stated Not stated Not stated Components Document: BN L A-3270-3-86, Testing Program For The Monitoring of Degradation in a Continuous Duty 460 volt Class 'B', 10 hp Electric Motor Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Electric Motor Dielectrics Organic insulation Not stated ELETEMP MOIST-Insultion degradation (Insulation) materials EL RAD, VIBR, causes leakage CURSTR, VOLSTR, through the CONTAM insulation 2
Electric Motor Bearings Not stated Not stated Not stated Ballor roller surface defects cause vibration 3
Electric Motor Cage (Rotor)
Not stated Not stated Not stated Damaged or defective cage 4
Electric Motor Stator Steel, Copper, Not stated THERM-CY, FAT Stress caused by Organic insulation differences in thermal expansion rates Document: CHAPTER 24 CABLES, Aging and Ufe Extension of Major Ught Water Reactor Components Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Non-Shielded Single Polymers, Rubber, Not stated ELETEMP, MOIST-Jacket embrittlement
& Multi-Conductor Sicicon, Copper, EL, OXIDAT, & RAD & cracking, Jacketed Kapton propagating thru insulation 2
Shielded Pair Multi-Polymers, Rubber, Not stated ELETEMP, MOIST-Jacket & cracking-Conductor Jacketed Silicon & Copper EL, OXIDAT, & RAD moisture diffuses through jacket and condo 3
Connections - Non-Not stated Not stated ELETEMP&
Moisture diffuses Sealed MOIST-EL into cables and connection internals 4
Connections -
Polymers Not stated ELETEMP, RAD, &
Seals not hermetic Compression Sealed VIBR 5
Cables, Halogination Polymers Not stated ELETEMP, RAD, &
Electrolytes that of Filled Polymers MOIST-EL increase leakage or losses 6
Mineral Insulated Not stated Not stated THERMO-CY &
Open hermetic seals Cable VIBR 7
Terminal Strips Not stated Not stated CONTAM Increase leakage or losses Document: Letter ReportliNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL I
S tem iystem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Battery Chargers Circuit Breakers Contacts, Coil, Not stated Not stated WEAR & LOSLUB Bearing wear &
and Inverters Unkages, & Case solidification of lubrication 2 Battery Chargers Circuit Breakers Contacts, Coil, Not stated Not stated FAT,OXIDAT Metal fatigue, and Inverters Unkages, & Case embrittiement &
cracking of insulation 3 Battery Chargers Circuit Breakers Contacts, Coil, Not stated Not stated OXIDAT & WEAR Oxidation and pitting and Inverters Unkages, & Case of contact surtaces
Table A.2 Gall Report for NPAR Reports Page 18 Document: BNL A-3270-11-85, Seismic Endurance Tests of Naturally Aged Small Electric Motors Reviewed by:
Jerry Edson, INEL Eftect of Agil!g on Component Function Contrib to Failure Reported. progs Rel.progs Report Recommendations Page No. Item Leakage of moisture into the box could
\\ Not stated Not discussed in No specific Not stated 3,4 1
leao to termination corrosionand report program overheating which could cause degraded performance or failure to operate Excessive leakage current and decreased Not stated Not discussed in No specific Not stated 4
2 performance or failure to operate report program Not stated Not stated Not discussed in No specific Not stated A-6 3
report program Document: BNL A-3270-3-86, Testing Program For The Monitoring of Degradation in a Continuous Duty 460 volt Class "B", 10 hp Electric Motor Reviewed by:
Jerry Edson, INEL Eft
- 1 R I R
rt Rd*
P N
lte ect of Aging on Component Function Contrib to Fal ure Reported progs e~ogs epo ecommen ations age o.
m Leakage through the insulation causes Not stated Not discussed in IEEE 334-1974 Not stated 1,3,12 1
imbalances between phases, phases with report Section 14 below normal current, and overheating in phases with above normal current.
Results in decreased output.
Increased friction and reduced output Not stated Not discussed in IEEE 334-1974 Not stated 3, 15 2
report Section 14 Decreased speed or torque Not stated Not discussed in IEEE 334-1974 Not stated 15 3
report Section 14 Additional aging stress to the windings Not stated Not discussed in IEEE 334-1974 Not stated 3
4 report Section 14 Document: CHAPTER 24 CABLES, Aging and Ufe Extension of Major Ught Water Reactor Components ReViewed by:
E. W. Roberts, INEL Eft fA*
F F.
R I R
ecto,gmg on Component unction Contrib to allure Reported progs el.progs eport R d.
ecommen ations p age N o. tem Circuit ground or short Frequent Umited No specific Utilities (1) monitor temp/rad 845,848,8 1
program determine hot spots, (2) perform 54,863, &
periodic inspections, & (3) don't 865 disturb cables [4]
Circuit opens, grounds, total loss of Frequent Umited No specific Utilities adopt improved failure 845,848,8 2
function program analysis & recording [4]
54,863, 865 Circuit opens, grounds, total loss of Not stated Not discussed in No specific Not stated 845,848,8 3
function report program 63,865 During DBE moisture enters through Not stated Not discussed in No specific Not stated 845,848,8 4
connection, contacts corride, circuit report program 50,863, &
grounds or shorts 865 Disable function during dbe Not stated Not discussed in No specific Not stated 845,848,8 5
report program 63, &865 DBE-excessive leakage disables cable Not stated Not discussed in No specific Not stated 845,848,8 6
report program 51, &865 DBE-excessive leakage disables cable Not stated Not discussed in No specific Not stated 833,845,8 7
report program 48, &865 Document: Letter ReportllNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM ReViewed by:
L. C. Meyer, INEL Eft t fA*
C F
C*b F i R I
R d
P N
eco 'gmg on omponent unction ontrl to a lure R~orted progs e~rogs Report ecommen ations
~e o. tem Failure to operate Occasional Not discussed in Vendor specific Not stated 4-18 1
report program, Tech.
Spec. surveil.
Fails to open - trip coil force becomes less Occasional Not discussed in Vendor specific Not stated 4-18 2
than spring force.
report program, Tech.
Spec. surveil.
Fails to open - loss of continuity across Rare Not discussed in Vendor specific Not stated 4-18 3
contacts.
report program, Tech.
Spec. surveil.
Table A.2 Gall Report for NPAR Reports Page 2A Document: Letter ReportllNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL Item System S
b M
. I M
ARD h'
ARD ff ts tructureiComp SU component aterla s anu acturer mec amsm eec 4 Battery Chargers Fuse Not stated Not stated FAT Metal fatigue and Inverters 5 Battery Chargers Fuse Not stated Not stated ELE-TEMP Melting of link and Inverters 6 Battery Chargers Relay Contacts Not stated Not stated OXIDAT & WEAR Oxidation & pitting 0 and Inverters contact surfaces 7 Battery Chargers Relay Coil Not stated Not stated CORR Electromechanical and Inverters action causing corrosion of fine wires.
8 Battery Chargers Electrolytic Not stated Not stated ELETEMP Over heating by and Inverters Capacitors internal stresses causes loss of electrolyte 9 Battery Chargers Electrolytic Not stated Not stated -
VIS Failure of leads and Inverters Capacitors 10 Battery Chargers Oil Filled Capacitors Not stated Not stated ELETEMP Over heating forrns and Inverters gasses and dielectric breakdown 11 Battery Chargers Oil Filled Capacitors Not stated Not stated VIS Failure of leads and Inverters 12 Battery Chargers Transformer Wire Not stated Not stated THERM-CY&
Cracking of and Inverters ELETEMP insulation 13 Battery Chargers Transformer Wire Not stated Not stated LOTEMP Cracking of moisture and Inverters seals 14 Battery Chargers Transformer Wire Not stated Not stated VOLSTR Insulaton material and Inverters deterioration 15 Battery Chargers Transformer Wire Not stated Not stated VIS & ELETEMP Fracture of and Inverters connecting wires and changes in shunting.
16 Battery Chargers Silicon Controlled Not stated Not stated VOLSTR &
Transients resulting and Inverters Rectifier CURSTR in over voltage &
current &
overheating 17 Battery Chargers Resistor Not stated Not stated VIS Lead fails and Inverters 18 Battery Chargers Resistor Not stated Not stated ELETEMP Decrease in and Inverters resistance values as temperature increases 19 Battery Chargers Printed Circuit Not stated Not stated THERM-CY Cracking of input and Inverters Boards lines 20 Battery Chargers Printed Circuit Not stated Not stated CORR Loss of material and Inverters Boards 21 Battery Chargers Printed Circuit Not stated Not stated VIS Loose or open and Inverters Boards connection 22 Battery Chargers Surge Suppressor Not stated Not stated VOLSTR OR Semiconductor and Inverters CURSTR barrier breakdown due to overheating.
23 Battery Chargers Connectors Not stated Not stated FAT & VIS Fatigue of wires at and Inverters terminals -
24 Battery Chargers Meters Not stated Not stated CONTAM Dirt on movement and Inverters and increase in bearing friction 25 Battery Chargers Meters Coil Insulation Not stated Not stated ELETEMP Coil insulation and Inverters degrades causing shorting 26 Battery Chargers Meters Contacts Not stated Not stated WEAR & CORR Contacts pitting or and Inverters corrosion 27 Cable Insulation Not stated Not stated ELETEMP, RAD, & Loss of dielectric MOIST-EL properties &
changes in structure
Table A.2 Gall Report for NPAR Reports Page 28 Document: Letter ReportllNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.proQs Report Recommendations Page No. Item Fails open due to equipment load cycling Occasional Not discussed in Vendor specific Not stated 4-18 4
report program, Tech.
Spec. surveil.
Fails open due to heat generated by Rare Not discussed in Vendor specific Not stated 4-18 5
surrounding components.
report program, Tech.
Spec. surveil.
Contacts open - loss of continuity across Rare Not discussed in Tech. Spec.
Not stated 4-18 6
contacts report surveillance Open circuit of coil - loss of continuity Rare Not discussed in Vendor specific Not stated 4*18 7
through coil wires.
report program Loss of capacitance and degraded Occasional Not discussed in Vendor specific Not stated 4-18 8
system operation.
report program Open circuit Rare Not discussed in Vendor specific Not stated 4-18 9
report program Loss of capacitance Occasional Not discussed in Vendor specific Not stated 4-18 10 report program Open circuit Rare Not discussed in Vendor specific Not stated 4-18 11 report iproqram Short circuit - turn to tum or to ground Occasi,onal Not discussed in Vendor specific Not stated 4-19 12 report iproqram Short circuit - turn to tum or to ground Occasional Not discussed in Vendor specific Not stated 4-19 13 report program Short circuit - turn to tum or to ground Occasional Not discussed in Vendor specific Not stated 4-19 14 report program Change in inductance Rare Not discussed in Vendor specific Not stated 4-19 15 report program Short or open circuit Occasional Not discussed in Vendor specific Not stated 4-19 16 report program Open circuit Rare Not discussed in Vendor specific Not stated 4-19 17 report program Change in resistance value and degraded Rare Not discussed in Vendor specific Not stated 4-19 18 circuit operation.
report program Change in output Rare Not discussed in Vendor specific Not stated 4-19 19 report program Open circuit at terminals or within printed Rare Not discussed in Vendor specific Not stated 4-19 20 circuit board.
report program Change in output Occasional Not discussed in Vendor specific Not stated 4-19 21 report program Short circuit Rare Not discussed in Vendor specific Not stated 4-19 22 report program Open or short circuit Occasional Not discussed in Vendor specific Not stated 4-19 23 report program No response (stuck)
Occasional Not discussed in Vendor specific Not stated 4-19 24 report program No response from meter Rare Not discussed in Vendor specific Not stated 4-19 25 report program Fails to open or close Occasional Not discussed in Vendor specific Not stated 4-19 26 report program Cracks when flexed & loss of flexibility, Rare Not discussed in No specific Not stated 3-33 27 loss of imperviousness, failure frequently report program coupled with presence of moisture or water.
Table A.2 Gall Report for NPAR Reports Page 3A Document: Letter ReportllNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL ISS eJ S b M
. I M
ARD tem :iystem tructur Comp u component ate rIa s anu acturer mechanIsm ARDeffects 28 Cable Insulation Not stated Not stated ELETEMP, RAD, &
Loss of dielectric MOIST-EL properties &
changes in structure 29 Cable Insulation Not stated Not stated ELETEMP, RAD, &
Loss of dielectric MOIST-EL properties &
changes in structure 30 (Pressure Force Balance Type Force Bar & Unkage Not stated Not stated WEAR & VIB Wear of pivot points Transmitters) 31 (Pressure Force Balance Type Force Motor Not stated Not stated VOLSTR ELETEMP Insulation failure &
Transmitters)
(Feedback Coil) coil burnout 32 (Pressure Force Balance Type Amplifier Not stated Not stated THER-CY &
Shorting or opening Transmitters)
VOLSTR of electronic components 33 (Pressure Force Balance Type Housing Seals Not stated Not stated ELETEMP, RAD, Compresive set or Transmitters)
OR EMBR cracking 34 (Pressure Force Balance Type Diaphragm Not stated Not stated CORR Perforation of Transmitters) diaphragm from corrosion 35 (Pressure Force Balance Type Diaphragm Seal Not stated Not stated Not stated Seal deterioration Transmitters) from decomposition 36 (Pressure Capicitance Type Sensing Cell Not stated Not stated Not stated Perforation in cell Transmitters)
Transmitters allowing leakage of fluid 37 (Pressure Capicitance Type Terminal Cover Plate Not stated Not stated EMBR, ELETEMP, Embrittlement and Transmitters)
Transmitters Seal
&RAD seal cracking 38 (Pressure Capicitance Type Electronics Not stated Not stated OXIDAT&
Circuit continuity los Transmitters)
Transmitters CONTAM and bridging of circuits 39 (Pressure Capicitance Type Electronics Not stated Not stated VOLSTR &
Shorting or opening Transmitters)
Transmitters ELETEMP of component 40 (Pressure Capicitance Type Sensing Cell Not stated Not stated ELETEMP OR RAD Chemical changes ir Transmitters)
Transmitters fill-oil 41 (Pressure Capicitance Type Electronics Not stated Not stated RAD, ELETEMP, Change in Transmitters)
Transmitters OR VOLSTR component parameters
Table A.2 Gall Report for NPAR Reports Page 38 Document: Letter ReportiiNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Cracks when flexed & loss of flexibility, Rare Not discussed in No specific Not stated 3*34 28 loss of imperviousness, failure frequenUy report program coupled with presence of moisture or water.
Cracks when flexed & loss of flexibility, Rare Not discussed in No specific Not stated 3*34 29 loss of imperviousness, failure frequenUy report program coupled with presence of moisture or water. Adverse changes in insulation resistance may cause attenuation of signals.
Failure to operate - decrased accuracy or Occasional Not discussed in RG 1.118, Not stated 4-43 30 complete failure. Zero shift may result report IEEE 338*
from bent components causing 1987,ISA transmitter failure to operate as required.
67.06, Tech
~ec Failure to operate - loss of output Rare Not discussed in RG 1.118, Not stated 4*43 31 report IEEE 338*
1987,ISA 67.06, Tech Spec Failure to operate* may fail high, low, lose Occasional Not discussed in RG 1.118, Not stated 4-43 32 accuracy, or fail with steady output.
report IEEE 338*
1987,ISA 67.06, Tech Spec Failure to operate - inability of seal to Occasional Not discussed in RG 1.118, Not stated 4*43 33 provide moisture and pressure barrier report IEEE 338*
results in failure of electronics due to 1987,ISA shorting and corrosion from ingress of 67.06, Tech environmental contaminants.
Spec Failure to operate as required - zero shift Occasional Not discussed in RG 1.118,IEEE Not stated 4*43 34 or leakage through diaphram causing report 338-1987,ISA variable instrument drift as pressures 67.06,10 CFR across diapharam equalize 50.49 Failure to operate as required* leakage Occasional Not discussed in RG 1.118, Not stated.
4-43 35 through diaphram causing variable report IEEE 338*
instrument drift as pressures across 1987,ISA diapharam equalize 67.06, Tech Spec Failure to operate or loss of accuracy or Rare Not discussed in RG 1.118, Not stated 4-44 36 drift report IEEE 338*
1987,ISA 67.06, Bu190-01 Failure to operate - inability to provide Rare Not discussed in RG 1.118,IEEE Not stated 4-44 37 moisture and pressure boundary resulting report 338-1987,ISA in loss of electronics due to ingress of 67.06,10 CFR environmental contaminants 50.49 Failure to operate or loss of signal or Occasional Not discussed in RG 1.118, Not stated 4-44 38 sporadic operation report IEEE 338*
1987,ISA 67.06, Tech Spec Failure to operate - loss of output, may fail Occasional Not discussed in RG 1.118, Not stated 4-44 39 high or low.
report IEEE 338-1987,ISA 67.06, Tech Spec Failure to operate as required such as Rare Not discussed in RG 1.118, Not stated 4-45 40 zero shift, reduced accuracy, or changes report IEEE 338-in response time.
1987,ISA 67.06, IN 95-20 Failure to operate as required - loss of Occasional Not discussed in RG 1.118, Not stated 4-45 41 accuracy, drift, or zero shift.
report IEEE 338-1987,ISA 67.06, Tech Spec
Table A.2 Gall Report for NPAR Reports Page 4A Document: Letter ReportllNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL 1St eJC S b M t. I M
f t
ARD h*
ARD ff ts tem
.ys em Structur omp u component a erlas anu ac urer mec an Ism eec 42 (Pressure Strain Gage Type Strain Gage Not stated Not stated Not stated Loss of continuity in Transmitters) bridge circuit related to aging 43 (Pressure Strain Gage Type Seals Not stated Not stated CONTAM, EMBR, Embrittlenent or Transmitters)
ELETEMP,OR cracking RAD 44 (Pressure Strain Gage Type Potentiometer Not stated Not stated CORR & ELETEMP Corrodes open due Transmitters) to thermal stress 45 (Pressure Strain Gage Type Electric Module Not stated Not stated Not stated Component Transmitters) deterioration or change in parameters 46 (Pressure Strain Gage Type Bourdon Tube Not stated Not stated CORR Perforation of tube Transmitters) allowing leaks to transmitter housing Document: NISTIR 4485, Annotated Bibliography - Diagnostic Methods and Measurement Approached to Detect Incipient Defects Due to Aging of cables Reviewed by:
L. C. Meyer, INEL 1St eJ S b M
. I M
f t
ARD h*
ARD ff ts tem sys em Structur Comp u component aterla s anu ac urer mec amsm eec 1
Cable Not stated Not stated Not stated Not stated Not stated Document: NISTIR 4487, Detection of incipient Defects in cables by Partial Discharge Signal Analysis Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Cable Insulation Not stated Not stated MOIST-EL, Defects develop
- OXIDAT, from these ELETEMP, & RAD mechanisms Document: NISTIR 4787, The Use of lime-Domain Dielectric Spectroscopy to Evaluate the Lifetime of Nuclear Power Station Cables Reviewed by:
Jerry Edson, INEL 1St ARD h'
tem.ys em StructureJComp Subcomponent Materials Manu acturer mec amsm ARD ff e ects 1
Electrical Cable Jacket Vinyl Not stated Not stated Not stated 2
Electrical Cable Insulation PE, XLPE, XLPO Not stated ELETEMP & RAD Chemical reactions, crosslinking, ionization 3
Electrical Cable Insulation PE, XLPE, XLPO Not stated ELETEMP Chemical reactions, COMBINED WITH crosslinking, RAD ionization Document: NUREG-1377 R3, NRC Research Program on Plant Aging: Listing and Summaries of Reports Issued Through July 1992 Reviewed by:
Jerry Edson, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Listing and NOT Summaries of 123 SPECIFICALLY NPAR Reports ADDRESSED IN THE REPORT
Table A.2 Gall Report for NPAR Reports Page 48 Document: Letter ReportiiNEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported E'rogs Rel.progs Report Recommendations Page No. Item Failure to operate - loss of output.
Rare Not discussed in RG 1.118, Not stated 4-45 42 report IEEE 338-1987,ISA 67.06, Tech Spec Failure to operate - inability to provide Occasional Not discussed in RG 1.118,IEEE Not stated 4-45 43 moisture and pressure barrier leading to report 338-1987,ISA failure of electronics due to contamination.
67.06,10 CFR 50.49 Failure to operate - fails over range, wire-Occasional Not discussed in RG 1.118, Not stated 4-45 44 wound potentiometer corrosion of resistive report IEEE 338-elements leads to failure 1987,ISA 67.06, Tech Spec Failure to operate or loss of full output Occasional Not discussed in RG 1.118, Not stated 4-45 45 report IEEE 338-1987,ISA 67.06, Tech Spec Failure to operate as required - drift, Rare Not discussed in RG 1.118, Not stated 4-45 46 contamination of transmitter intemals, and report IEEE 338-failure to respond 1987,ISA 67.06, Tech Spec Document: NISTIR 4485, Annotated Bibliography - Diagnostic Methods and Measurement Approached to Detect Incipient Defects Due to Aging of Cables Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations..
Page No. Item This is a collection of 156 reveiwed Not stated Not discussed in No specific Not stated NA 1
abstracts of reports and papers related to report program cable aging and defect assessment covering the 1970-1986 period. An additional list of 850 citations was compiled from references given in the reveiwed papers.
Document: NISTIR 4487, Detection of Incipient Defects in Cables by Partial Discharge Signal Analysis Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item The defects will degrade insulating Occasional Not discussed in No specific Six recommendations each for 1 and 120 1
properties of cable insulation.
report program partial discharge research and hardware development. Three for software. [4]
Document: NISTIR 4787, The Use of "Time-Domain Dielectric Spectroscopy to Evaluate the Ufetime of Nuclear Power Station Cables Reviewed by:
Jerry Edson, INEL Eff t fA' b
F'I R
ed R I R
R d ti eco \\gmg on Component Function Contri to al ure eport progs e.progs eport ecommen a ons P age N o. tem Not stated Not stated Not discussed in No specific Not stated 15 1
report program Embrittlement, softening, loss of Not stated Not discussed in No specific Not stated 1,2,4,7, 2
elongation and reduced dielectric strength report program 8,15,17, could cause failure to accurately transmit 22-38 voltage or current.
Embrittlement, softening, loss of Not stated Not discussed in No specific Not stated 1,2,4,7, 3
elongation and reduced dielectric strength report program 8,15,17, could cause failure to accurately transmit 22-38 voltage or current.
Document: NUREG-1377 R3, NRC Research Program on Plant Aging: Usting and Summaries of Reports Issued Through July 1992 RevieWed by:
Jerry Edson, INEL Eff t fA' F
C'b F'I R
rted R I R
Rd' eco \\gmg on Component unction ontrl to al ure epo progs e.progs eport ecommen ations P age N o. tem The purpose of the report is to present a Not discussed in the No specific Not stated 1
listing and summaries of 123 NP AR report program reports. Specific aging effects and recommendations are addressed by the individual reports.
Table A.2 Gall Report for NPAR Reports Page SA Document: NUREG/CP-0100, Proceedings of the Intemational Nuclear Aging Symposium, Session 3 Reviewed by:
L. C. Meyer, INEL IS e/C Sb Mt*.
M ftu tem )ystem Structur omp u component a erlas anu ac rer ARD h
mec amsm ARD ff ts eec 17 Resistance Not stated Not stated THERM-CY Conductive Temperature compounds become Devices insulative 18 Electrical Wiring Insulation Kapton (Aeromatic Not stated MOIST-EL & ELE-Insulation cracking polymide)
TEMP and loss of mechanical properties 19 Pressure Force Balance Type Not stated Foxboro CONTAM & FRZ-Blockage of sensing Transducers Sensors THAW lines 20 Pressure Not stated Not stated Rosemount CONTAM & FRZ-Blockage of sensing Transducers THAW lines 21 Micro Processor &
ICDIE Silicon, Silicon oxide Not stated
- CONTAM, Contamination ICs
& interfaces VOTSTR,CURSTR causes shorts, V & I stresses cause burnout 22 Micro Processor &
ICDIE Metalization Not stated CORR Corrosion from ICs adjacent materials 23 Micro Processor &
Not stated FAT, CORR, VIB, & Corr from adjacent ICs container and glass CONTAM materials, vib cause!
seals fat, contam shorts 24 Diesel Generator Not stated Not stated Not stated Not stated WEAR & LOSLUB Wear from lack of lubrication during fast starts 25 Cable Insulation EPR,CSPE,&
Four vendors listed RAD, ELETEMP, &
Insulation XLPE MOIST-EL degradation from all three mechanisms Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeling (Electrical Parts)
Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 14 Auxiliary Feedwater Not stated Not stated Not stated Not stated System 15 Auxiliary Feedwater Cable Various cable Seven vendors RADAND Not stated System materials Identified ELETEMP 16 Auxiliary Feedwater Steam Generator Tubes Not stated Westinghouse FAT, EROS, CORR Primary water stress System corrosion cracking (PWSCC) 17 Auxiliary Feedwater Circuit Breakers Not stated Not stated Not stated Not stated System 18 Auxiliary Feedwater Turbine Driven Not stated Not stated Not stated Not stated System Pump 19 Auxiliary Feedwater Compressors Not stated Not stated WEAR, CONTAM, Set point drift, System
& VIB degraded parts, &
loose connections 20 Auxiliary Feedwater Dryers Not stated Not stated CORR & CONTAM Blockage, deterialion System of components 21 Auxiliary Feedwater Valve Not stated Not stated WEAR, CONTAM, Set point drift, System AND CORR fracture/cracking, component deterioration
Table A.2 Gall Report for NPAR Reports Page 58 Document: NUREG/CP-0100, Proceedings of the International Nuclear Aging Symposium, Session 3 RevieWed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Never-seez usd in thermal wells lose Not stated Reg Guides 1.118 Reg Guides Not stated 363-366 17 conductivity with age and effects and 1.105 1.118 and response time of RTD.
1.105 Cracking can result in contamination Occasional Not discussed in No specific Not stated 130-131 18 intrusion and improper output.
report program Partial or full blockage of sensing lines Not stated IEEE-Std 338, Reg IEEE 338, Reg Not stated 137-139 19 effects the transducer response time.
Guide 1.118, & ISA Guide 1.118, Std 67.06 ISA67.06 Partial or full blockage of sensing lines Not stated IEEE-Std 338, Reg IEEE 338, Reg Not stated 138-139 20 effects the transducer response time.
Guide 1.118, & ISA Guide 1.118, Std 67.06 ISA67.06 Contamination enters by cracks or from Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 21 MFG process and if moved by handling program emerge, their aging sensitivity shoulc can short gate elements, voltage and be addressed. [2]
current spikes may overstress leads or connections weakened by manufacturing process or chemical reactions of materials used in IC.
Metalization may fail because of corrosion Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 22 from adjacent materials program emerge, their aging sensitivity shoulc be addressed. [2]
Vibration may crack glass seals allowing Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 23 contamination to enter case, corr from program emerge, their aging sensitivity shoulc moisture entering cracked seals or be addressed. [2]
adjacent materials, contamination left from mfg process or entering through seal cracks may cause component shorting.
Decreases reliable life of diesels Not stated Not discussed in IEEE 387-1984 Not stated 153-157 24 report Section 7.5, IEEE 749-1983 The report is not an aging evaluation, but Not stated IEEE Std-74 & IEEE No specific Not stated 158-166 25 only describes long term tests to STD-383-1974 program determine the amount of insulation degratation from radiation, elevated temperature, pwr atmospheres, and inerted BWR atmospheres.
Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item This report develops an aging risk Not stated Not discussed in No specific Not stated 3n-398 14 assesment methodology using the aPWR report program AFW system to demonstrate method This report covered loca testing of aged Not stated Not discussed in No specific Not stated 399-410 15 cables. Aging information provided in report program other Satldia reports on cable agin~
PWSCC damages steam tubes at three Rare Not discussed in No specific Not stated 411-431 16 locations; roll transition regions, U-bends, report program and tube dents. Leaks at these locations can lead to shuting down the reactor.
This report covers NPAR phase 2 tasks Not stated NPAR No specific Not stated 433-437 17 related to resolving technical safety issues program This report only provides an overview and Not stated Not discussed in No specific Comprehensive testing of 439-451 18 identifies the turbine driven pump as report program components and i&c. [2]
historically having the most failures with the turbine i&clgovernor control system having half of these failures. Does not have specific aging data.
Degraded operation or failure Occasional Not discussed in No specific Not stated 453-471 19 report program Failure or degraded operation Occasional Not discussed in No specific Not stated 453-471 20 report program Failure to operate, failure to open or Occasional Not discussed in No specific Not stated 453-471 21 close, or degraded operation report program
Table A.2 Gall Report for NPAR Reports Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)
Reviewed by:
L C. Meyer, INEL I
S Str tu elC S b M t
. I M
tem >ystem uc r omp u componen a erlas anu acturer 22 Auxiliary Feedwater Diesel Generator Not stated Not stated System 23 Auxiliary Feedwater Circuit Breakers Not stated Not stated Not stated System 24 Auxiliary Feedwater Not stated Not stated Not stated Not stated System 25 Auxiliary Feedwater Not stated Not stated Not stated Not stated System Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits Reviewed by:
L C. Meyer, INEL Item System StructureiComp b
Su component Materials Manufacturer 1 Pressurizer Heater Cable Conductor NO.6 AWG, single Okonite Feeder Circuit copper conductor 2 Pressurizer Heater Cable Insulation 1/16IN. thick oil Okonite Feeder Circuit base 3 Pressurizer Heater Cable Jacket 1/32-IN. black Okonite Feeder Circuit neoprene 4 Pressurizer Heater Cable Conductor NO.10 AWG Not stated Main Feeder Circuit Copper 5 Pressurizer Heater Cable Insulation Silicon rubber with Not stated Main Feeder Circuit glass braid 6 Pressurizer Heater Cable Jacket Silicon rubber Not stated Main Feeder Circuit 7 Instrumentation and Heater, MOV, and Stop Joint, Splices, Not stated Not stated Control RTD Circuits and Terminals 8 Rod Control Position Cable 33 Conductor, NO.
Copper Okonite Indicator Cables 16 AWG, Stranded Wire 9 Rod Control Position Cable Insulation Oil base insulation Okonite Indicator Cables 10 Rod Control Position Cable Jacket Neoprene Okonite Indicator Cables 11 Resistance Cable Insulation NO. 18 AWG, tinned Not stated Temperature copper stranded.
Detector Circuits spiral wrapped and shielded with a chrome vinyl jacket 12 Resistance RTDs Sensing Element Platinum Leeds and Northrup Temperature Detector Circuits 13 Resistance Terminals and Stop Not stated Not stated Not stated Temperature Joints Detector Circuits 14 Nuclear RG-149U Cables Insulation NO. 18 AWG Not stated Instrumentation copper center conductor and polyethylene insulation 15 Motor Operated Umit Switches Contacts Not stated Not stated Valves 16 Motor Operated Cable Not stated Not stated Not stated Valves 17 Motor Operated Motor Not stated Not stated Not stated Valves Page 6A ARD h
i mec ansm ARD ff ts eec Not stated Not stated Not stated Not stated Not stated Not stated Not stated Not stated ARD mechanism ARDeffects CORR Increased loop resistance Not stated Low insulation resistance Not stated Not stated CORR Not stated OXIDAT Degraded insulation resistance Not stated Not stated MOIST-EL AND Loss of material, and CORR corrosion product buildup Not stated Not stated Not stated Not stated Not stated Not stated Not stated Not stated Not stated Not stated CORRAND Increase in MOIST-EL resistance, open circuit, and film on terminals Not stated Not stated CORR Material buildup on contacts Not stated Not stated Not stated Not stated
Table A.2 Gall Report for NPAR Reports Page 68 Document: NUREG/Cp*0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)
Reviewed by:
L. C. Meyer, INEL Eftect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page o.
em N
It Failure to start Occasional Not discussed in IEEE 387-1984 Not stated 473*495 22 report Section 7.5, IEEE 749-1983 Failure to transfer Occasional Not discussed in IEEE 741-1986 Not stated 473-495 23 report Section 7 This report only covers the use of N PAR Not stated Not discussed in N/A Not stated 497*407 24 results in inspection activities. Aging report summaries are covered in other npar reports This report covers a methOdology for Not stated Not discussed in N/A Not stated 509-529 25 managing aging in nuclear power plants report Document: NUREG/CR*3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits Reviewed by:
L. C. Meyer, INEL Eft fA' C
ecto,gmg on omponent Function Contrib to Failure Reported progs Rel.progs d
Report Recommen ations P age N It
- o.
em
, The effect was a small decrease in Rare Plant specific No specific Keep moisture out [2J 5,6, & 7 1
available wattage to heaters maintenance program Degraded heater oeration, one circuit Rare Plant specific No specific Keep moisture out of cables [2J 5,6,7, &
2 failed because of low insulation resistance maintenance program 21 Not stated Rare Not discussed in No specific Not stated 6
3 report I program Marginal operation Rare Not discussed in No specific Not stated 6
4 report I program Marginal operation of heaters Rare Not discussed in No specific Not stated 6
5 report program Not stated Rare Not discussed in No specific Not stated 6
6 report program Nonenvironmentaly sealed splices and Occasional Not discussed in No specific Periodic plant maintenance to clean 7and21 7
terminals presents vulnerable areas for report program terminals and check seals and to oxidation, corrosion, dust, and moisture use ECCAD to check circuits before contamination to set in.
failure [2]
None Rare Not discussed in No specific Not stated 7,8,and 8
report program 21 None Rare Not discussed in No specific Not stated 7,8,and 9
report program 21 None Rare Not discussed in No specific Not stated 7,8,and 10 report program 21 None Rare Not discussed in No specific Not stated 7,8,and 11 report program 21 One circuit shorted to ground at the Rare Not discussed in ANSI/IEEE Not stated 8,9,and 12 instrument end report 338*1987 21 Circuits had higher than expected loop Occasional Not discussed in No specific Not stated 9,10, and 13 resistance, four circuits had a series report program 21 resistance occuring at the stop joints, resistance problem also observed at termination points in the control room, one circuit was shorted to ground at the instrument end None Rare Not discussed in ANSI N42.4*
Not stated 12.13, 14 report 1971 and 21 Insulation resistance exceeded the Rare Not discussed in Vendor Not stated 12,20, 15 standard recommended minimum, report specific, GL and 21 although not serious enough to alter the 89*10, intended limit switch function NUREG-1352 None Rare Not discussed in No specific Not stated 12,20, 16 report program and 21 None except two movs located outside, Rare Not discussed in Vendor Not stated 12,20, 17 exposed to weather were inoperable.
report specific, GL and 21 89-10, NUREG-1352
Table A.2 Gall Report for NPAR Reports Page 7A Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits Reviewed by:
L. C. Meyer, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism ARD effects 18 Motor Operated Not stated Not stated Not stated WEA TH Not stated Valves Document: NU RE G/CR-4156, Operating Experience and Aging-Seismic Assessment of Electric Motors Reviewed by:
L. C. Meyer, INEL ISS e/C Sb M*I M
f t
tem
.ystem tructur omp u component aterlas anu ac urer ARD h
i mec ansm ARD ff ts eec 1
3 Phase Induction & Stator - Conductors Copper Not stated VIB, THERM, AND Loosening of Synchronous Motors and Structural SHRINK laminations and Components locking devices 2
3 Phase Induction & Stator - Insulation Mica, glass, resins, Not stated THERM, OXIDAT, Degraded dielectric Synchronous Motors enamels, mylars, MOIST-EL, AND properties & tensile figer, vamish, and RAD strength, brittle nonhygroscopic materials 3
3 Phase Induction & Rotor - Contuctors Copper Not stated VIB& THERM Rotor embalance, Synchronous Motors and Structural loose parts, and Components overheating 4
3 Phase Induction & Rotor - Insulating Mica, glass, resins, Not stated CURSTR, THERM, Insulation damage, Synchronous Motors Materials enamels, mylars, RAD, AND MOIST-winding short, fiber, vamish, and EL overheating of rotor non hygroscopic coils marteials 5
3 Phase Induction & Rotor - Commutator Mica, copper, Not stated WEAR, FAT, DIRT, Brush wearout, Synchronous Motors and Brushes carbon, and steel in CONTAM,AND relaxed spring, oil spring mechanism OXIDAT deposits, & loose contact 6
3 Phase Induction & Bearings Steel, brass, and Not stated VIB, THERM, Material attrition, Synchronous Motors bronze
- WEAR, cracking of bearings CONTAMIN, AND scoring of surface LOSLUBE 7
3 Phase Induction & Bolts, Ranges, and Steel, cast iron, Not stated VIB, CORR, FAT, Sheared bolts, Synchronous Motors Housing brass, and copper THERM,AND cracked flanges or MECHSTR housing, overheated frame 8
3 Phase Induction & Seals and Gaskets Polymers Not stated THERM, VIB, AND Cracking, shrinking, Synchronous Motors RAD leaking of oil or water, embrittlement 9
3 Phase Induction & MOV's Break Coils Copper Not stated THERM, CORR, Corrosion product Synchronous Motors CURSTR buildup, current overload,&
misoperation 10 3 Phase Induction & Conduit Box, Leads, Copper Not stated VIB AND CORR, Leak, poor electrical Synchronous Motors and Connections CONTAM, MOIST-contact, loose leads, EL improper seals 11 3 Phase Induction & Motor See sub-Not stated WEAR, THERM, Misaligned parts, Synchronous Motors components VIB, CURSTR, burned out motor, &
RAD, FAT, AND disengaged motor MOIST-EL Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant~
Reviewed by:
Jerry Edson,INEL It S
t Str tu e/C S b M t - I M
f t
ARD h*
ARD ff ts em.ys em uc r omp u componen a erlas anu ac urer mec anlsm eec 1
Motor Operated Gearbox - Gears Not stated ElM, Umitorque, WEAR Not stated Valve Rotork
Table A.2 Gall Report for NPAR Reports Page 78 Document: NUREG/CR-4156, Operating Experience and Aging-Seismic Assessment of Electric Motors Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 8-2,2-15, 1
report Section 14 operational readiness acceptance and 4-23 criteria, in-situ testing and monitoring programs [2]
Degraded operation or failure to function Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, S-2,2-15, 2
report Section 14 operational readiness acceptance
&4-23 criteria, in-situ testing and monitoring programs [2]
Frame distortion, shift in rotor center of Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, S-2,2-20, 3
gravity, insuficient cooling, winding short report Section 14 operational readiness acceptance 4-23 short or overheating of rotor coils leading criteria, in-situ testing and monitorin~
to burnt motor and failure to function.
programs [2]
Excess current due to aging from many Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15, S-2, 4
starts, cage winding failure due to jogging, report Section 14 operational readiness acceptance 4-24 over heating of rotor coils leading to burnt criteria, in-situ testing and monitoring motor, winding shorts, insulation programs [2]
shrinkage results in decreased output or failure to function.
Loose brush connection, dirt & foreign Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-22, S-2, 5
particles, wear out of carbon brushes, report Section 14 operational readiness acceptance 4-25 relaxed spring load in the brush holder criteria, in-situ testing and monitorin~
mechanisms, dirt! moisture on programs [2]
commutator and oxidation effects results in decreased output or failure to function.
Seized bearings, and overheating, Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15,4-6 excessive vibration could cause fracture report Section 14 operational readiness acceptance 22,4-23, and bearing scoring, corrosion due to criteria, in-situ testing and monitorin~ 4-25,4-exposure to air.
programs [2]
26, and 4-27 Failure to function or degraded operation OCCCASIONAL Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15,4-7 report Section 14 operational readiness acceptance 24,4-25, Criteria, iri-situ testing and monitorin~ 4-25,4-programs [2]
27, and 4-28 Decreased output or *failure to function.
Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 5-15 & 4-8 report Section 14 operational readiness acceptance 28 criteria, in-situ testing and monitorin~
programs [2]
Burning of motor windings, jamming of Rare Not discussed in Vendor Preventive maintenance programms, 5-15 & 4-9 break coil, overload the motor drawing report specific, GL operational readiness acceptance 28 large currents into the windings results in 89-10, criteria, in-situ testing and monitorin~
failure to operate.
NUREG-1352 programs [2]
Degraded insulation, shorts, or open Occasional Not discussed in No specific Preventive maintenance programms, 4-28 10 circuits result in decreased output or report program operational readiness acceptance failure to function.
criteria, in-situ testing and monitoring programs [2]
Bumed or dead motor, disengaged motor, Rare Not discussed in IEEE 334-1974 Preventive maintenance programms, 4-29 11
& overcurrent results in decreased output report Section 14 operational readiness acceptance or failure to function.
criteria, in-situ testing and monitoring programs [2]
Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant~
Reviewed by:
Jerry Edson, INEL Eff t A"
F C
F "I ec of 'glng on Component unction ontrib to al ure Reported progs Rel.progs Report Recommendations Page No. Item Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 1
as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
Table A.2 Gall Report for NPAR Reports Page 8A Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Planl Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 2
Motor Operated Gearbox -Fasteners Not stated ElM, Limitorque, Not stated Fastener loosening Valve Rotork 3
Motor Operated Gearbox - Stem Nut Not stated ElM, Limitorque, WEAR Not stated Valve Rotork 4
Motor Operated Gearbox - Drive Not stated ElM, Limitorque, WEAR Not stated Valve Sleeve Rotork 5
Motor Operated Gearbox - Bearings Not stated ElM, Limitorque, WEAR Not stated Valve Rotork 6
Motor Operated Gearbox - Luberican Not stated ElM, Limitorque, Not stated Hardening Valve Rotork 7
Motor Operated Gearbox - Shaft Not stated ElM, Limitorque, WEAR, MECHSTR Tapering of the shaf1 Valve Rotork 8
Motor Operated Gearbox - Clutch Not stated ElM, Limitorque, WEAR Not stated Valve Rotork 9
Motor Operated Gearbox - Spring Not stated ElM, Limitorque, Not stated Response change Valve Pack and Torque Rotork Switch 10 Motor Operated Gearbox - Stem Not stated ElM, Limitorque, Not stated Loosening Valve Lock Nut Rotork 11 Motor Operated Gearbox - Seal Not stated ElM, Limitorque, WEAR Deterioration Valve Rotork 12 Motor Operated Motor Not stated ElM, Limitorque, CORR, WEAR Not stated Valve Rotork 13 Motor Operated Motor Not stated ElM, Limitorque, ELETEMP Break down of Valve Rotork insulation 14 Motor Operated Switches - Contacts Not stated ElM, Limitorque, CORR, CORR/PIT Not stated Valve Rotork 15 Motor Operated Switches - Insulation Not stated ElM, Limitorque, ELETEMP Insulation Valve Rotork breakdown 16 Motor Operated Switches - Grease Not stated ElM, Limitorque, Not stated Hamening Valve Rotork 17 Motor Operated Switches - Gear and Not stated ElM, Limitorque, WEAR Not stated Valve Cam Rotork 18 Motor Operated Switches - Fastener Not stated ElM, Limitorque, Not stated Loosening Valve Rotork
Table A.2 Gall Report for NPAR Reports Page 88 Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant!
Reviewed by:
Jerry Edson, INEL Effect of ~9ing on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. Item Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 2
as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 3
as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 4
as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 5
as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 6
as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 7
as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 8
as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 9
as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 10 as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Leakage of lubricant out from gearbox or Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 11 leakage of contaminants into the gear box report specific, GL should be performed. Good records 72,167 resulting in failure to open or close or 89-10, should be maintained [4]
failure to operate as required NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 12 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 13 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 14 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 15 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 16 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 17 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to opEln or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 18 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
Table A.2 Gall Report for NPAR Reports Page 9A Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plan!
Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 19 Motor Operated Valves - Operator Not stated Anchor Darling, WEAR, CORR Not stated Valve Velan, ET 20 Motor Operated Valves - Yoke Not stated Anchor Darling, WEAR Not stated Valve Bushing Velan, ET 21 Motor Operated Valves - Valve Stem Not stated Anchor Darling, WEAR, MECHSTR Tapering of the shaft Valve Velan, ET 22 Motor Operated Valves - Fasteners Not stated Anchor Darling, Not stated Loosening Valve Velan, ET 23 Motor Operated Valves - Valve Seat Not stated Anchor Darling, WEAR, CORR Not stated Valve Velan, ET 24 Motor Operated Valves - Bonnet Seal Not stated Anchor Darling, Not stated Deterioration Valve Velan, ET 25 Motor Operated Valves - Stem Not stated Anchor Darling, Not stated Deterioration Valve Packing Velan, ET Document: NUREG/CR-4257, Inspection, Surveillance, and Monitoring of Electrical Equipment Inside Containment of Nuclear Power Plants - With Applications tol Reviewed by:
L. C. Meyer, INEL Item System Structur e/
Sb M
ff Comp u component aterials Manufacturer ARD mechanism ARDe ects 1
Cable 600 V, 4 kV, and 13 Cross-linked Not stated THERM, RAD, Chemical changes, kV Power Cable polyethylene (XLPE)
CHEM,AND dielectric Insulation MOIST-EL degradation, &
cracks 2
Cable 600 V, 4 kV, and 13 Ethylene propylene Not stated THERM, RAD, Chemical changes, kV Power Cable CHEM,AND dielectric Insulation MOIST-EL degradation, &
cracks 3
Cable 600 V, 4 kV, and 13 Polyvinyl chloride Not stated THERM, RAD, Radiation kV Power Cable (PVC)
CHEM, AND deterioration, Insulation MOIST-EL dielectric degradation, &
cracks 4
Cable Cable Sheathing and Chlorosulfonated Not stated THERM,RAD,&
Radiation Jacket polyethylene (CSP)
CHEM.
deterioration, and Kapton dielectric degradation, &
cracks 5
Cable Control Cable Cross-linked Not stated THERM,RAD,&
Radiation polyethylene (XLPE)
CHEM.
deterioration, dielectric degradation, &
cracks 6
Cable Coaxial Cable Cross-linked Not stated THERM,RAD,&
Radiation polyethylene (XLPE)
CHEM.
deterioration, dielectric degradation, &
cracks 7
Cable Mineral Insulation Not stated Not stated RAD& VIB Wear Metal Jacket Cable
Table A.2 Gall Report for NPAR Reports Page 98 Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plantl Reviewed by:
Jerry Edson, INEL E
A' RI R
R dti P
Nit ffeet of 'gmg on Com~onent Function Contrib to Failure Reported progs e.progs eport eeommen a ons age o.
em Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 19 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 20 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 21 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 22 operate as required report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 23 operate as required report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
NUREG-1352 Leakage Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 24 report specific, GL should be performed. Good records 72,167 89-10, should be maintained [4]
NUREG-1352 Leakage Not stated Not discussed in Vendor Accurate and consistent mov testing 5-12,15, 25 report specific, GL should be performed. Good records 72, 167 89-10, should be maintained [4]
. NUREG-1352 Document: NUREG/CR-4257, Inspection, Surveillance, and Monitoring of Electrical Equipment Inside Containment of Nuclear Power Plants - With Applications to I Reviewed by:
L C. Meyer, INEL Eff fA' C
Rd' P
N It eeto 'gmg on omponent Function Contrib to Failure Reported progs Rel.progs Report eeommen ations age o.
em Chemical changes in polymer resulting Rare Not discussed in No specific Testing to be based on safety 26,38,40, 1
from aging, loss of dielectric generally report program importance, determine root cause of &53 occurs after deterioration of mechanical failures, remove samples after 5 to properties, treeing may cause rapid 10 years for tests [4]
breakdown of dielectric capabilities. loss of flexibility, can't withstand voltage stress Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26,38,40, 2
deterioration of mechanical properties, report program importance, determine root cause of &53 treeing may cause rapid breakdown of failures, remove samples after 5 to dielectric capabilities. loss of flexibility, 10 years for tests [4]
can't with stand voltage stress Subject to deterioration from radiation, Rare Not discussed in No specific Testing to be based on safety 26,38,40, 3
loss of dielectric generally occurs after report program importance, determine root cause of &53 deterioration of mechanical properties.
failures, remove samples after 5 to 1 0 years for tests [4]
Major failure modes for sheathing are loss Rare Not discussed in No specific Testing to be based on safety 26,38,40, 4
of flexibility and imperviousness. teflon report program importance, kapton not
&53 glue fails at low radiaton doses resulting recommended for applications in inability to protect conductor insulation.
subject to radiation doses> 0.01 mrad [4]
Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26,39, 5
deterioration of mechanical properties, report program importance, determine root cause of 40, &53 loss of flexibility, loss of imperviousness, failures, remove samples after 5 to aging similar to power cable. Results in 10 years for tests [4]
failure to properly transmit voltage or current.
Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26,39, 6
deterioration of mechanical properties, report program importance, determine root cause of 40, &53 loss of flexibility, loss of imperviousness, failures, remove samples after 5 to aging similar to power cable. Results in 10 years for tests [4]
failure to properly transmit voltage or current.
Conductor wear through insulation due to Rare Not discussed in No specific Testing to be based on safety 26,30, 7
bending or vibration. Results in ffailure to report program importance, determine root cause of ransmit voltage or current.
failures. [4]
Table A.2 Ga" Report for NPAR Reports Page 10A Document: NUREG/CR-4257 V2, Inspection, Surveillance, and Monitoring of Electrical Equipment in Nuclear Power Plants - Pressure Transmitters Reviewed by:
L. C. Meyer, INEL Item S eJ Sb M
~ystem Structur Comp u component aterials Manufacturer ARD mechanism ARD effects 1
Force Balance Type Force Balance Bar & 316 stainless steel The Foxboro VIB AND WEAR Wear, failure to Transmitter Unkage Company operate, bending component, zero shift 2
Force Balance Type Feedback Coil Copper The Foxboro
- THERM, Burnout Transmitter Company 3
Force Balance Type Amplifier Carbon resistors, The Foxboro THERM, RAD, Degradation of Transmitter transistors, OP Company VOLSTR insulation, insulation amps, capacitors &
breakdown, & crack~
diodes 4
Force Balance Type Housing Seals Viton The Foxboro THERM, RAD, &
Embrittlement, Transmitter Company CONTAM cracking, and inability to seal 5
Force Balance Type Diaphragm Capsule 316 stainless steel The Foxboro CORR Leakage or Transmitter Company perforation 6
Force Balance Type Diaphragm Seal 316 stainless steel The Foxboro THERMOR RAD Inability to maintain Transmitter Company pressure barrier, variable instrument 7
Capacitance Type Sensing Cell 316 stainless steel Rosemount THERM AND RAD Leakage, rupture, oil Transmitter breakdown, or perforation 8
Capacitance Type Terminal Cover Seal Ethylene propylene Rosemount THERM AND RAD Embrittlement and Transmitter cracking 9
Capacitance Type Electronics Cover Ethylene propylene Rosemount THERM AND RAD Embrittlement and Transmitter Seal cracking 10 Capacitance Type Electronics Parts -
Not stated Rosemount OXIDAT, THERM, Degradation of Transmitter MiscSmall AND VOLSTR insulation, arcing, Components shorts and open circuits 11 Strain Gage Type Strain Gage Resistive material ITIBarton VIB Loss of continuity or Instruments open resistor 12 Strain Gage Type Housing Seal Ethylene propylene ITIBarton THERM AND RAD Embrittlement or Instruments cracking 13 Strain Gage Type Potentiometer Phenolic body, nylon ITIBarton CORR AND Corrosion material rotor, and slider Instruments THERM buildup lubricant loss 14 Strain Gage Type Electric Module Carbon resistor, ITIBarton VIB, THERM, OR Component transistors, Instruments RAD deterioration or operational amplifier, change in capacitors, and component diodes parameters.
15 Strain Gage Type Bourdon Tube Haynes alloy NO 25 ITT Barton CORR Contamination build Instruments up and material loss.
Table A.2 Gall Report for NPAR Reports Page 10B Document: NUREG/CR-4257 V2, Inspection, Surveillance, and Monitoring of Electrical Equipment in Nuclear Power Plants - Pressure Transmitters Reviewed by:
L. C. Meyer, JNEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Wear of pivot pOints, decreased accuracy, Rare Not discussed in IEEE 338-1987 Not stated 9,18 &21 1
complete failure, zero shift, bending of report components in level system, Loss of output Rare Not discussed in IEEE 338-1987 Not stated 9,18 &21 2
report Shorting or opening of electronic Occasional Not discussed in IEEE 338-1987 Not stated 9,18&21 3
components, loss of accuracy, drift, zero report shift, loss of signal, may fail high or low, lose accuracy, or fail with steady output.
Inability of seal to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,18&21 4
pressure barrier, ingress of environmental report contaminants, and loss of pressure barrier results in transmitter drift or failure to respond.
Perforation of diaphragm from corrosion Rare Not discussed in IEEE 338-1987 Not stated 9,18 &21 5
or flaw, variable instrument drift as report pressures across diaphragm equalize, and leakage through diaphragm, permanent deformation of diaphragm, and zero shift.
Variable instrument drift as pressures Rare Not discussed in IEEE 338-1987 Not stated 9,18 &21 6
across diaphragm equalize, and inablitity report to maintain pressure barrier.
Leakage of cell fluid through diaphragm, Rare Not discussed in Enhanced Not stated 9,11,19 7
loss of accuracy and drift, rupture allows report Surveillance -
&21 equalization of forces on diaphragm, GL90-01 drastic change in sensing cell Suppl. 1 characteristics, oil breakdown due to thermal or radiation stress.
Inability of seal to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,11,19 8
pressure boundary, cracking due to report
&21 thermal or radiation stresses, and loss of electronics due to ingress of environmental contaminants. Results in transmitter drift or failure to respond.
Inability of seal to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,11,19 9
pressure boundary, cracking due to report
&21 thermal or radiation stresses, and loss of electronics due to ingress of environmental contaminants. Results in transmitter drift or failure to respond.
Loss of Signal, sporadic operation, Occasional Not discussed in IEEE 338-1987 Not stated 9, 11, 19 10 shorting or opening of components, report
&21 oxidation of contacts, bridging of circuits.
Loss of continuity in bridge circuit, loss of Occasional Not discussed in IEEE 338-1987 Not stated 6,7,20&
11 outpu~ loss of response to input pressure, report 22 and failure of instrument.
Inability to provide moisture and pressure Occasional Not discussed in 10 CFR 50.49 Not stated 6,7,20&
12 barrier, failure of electronics due to report 22 contamination. Results in instrument drift or failure to respond.
Corrosion of resistive elements in Occasional Not discussed in IEEE 338-1987 Not stated 6,7,20&
13 potentiometer, wirewound potentiometer report 22 corrodes open due to thermal stress and corrosive lubricant, fails over range, and loss of span adjustment.
Loss of full output, calibration shift, Occasional Not discussed in IEEE 338-1987 Not stated 6,7,20&
14 component parameters change.
report 22 Permanent deformation of tube, zero shift, Occasional Not discussed in IEEE 338-1987 Not stated 6,7,20&
15 leaks in bourdon tube to transmitter report 22 housing, perforatioon due to corrosion, drift of transmitter, failure of transmitter to respond.
Table A.2 Gall Report for NPAR Reports Page 11A Document: NUREG/CR*4457, Aging of Class 1E Batteries in Safety Systems of Nuclear Power Plants Reviewed by:
Jerry Edson, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Batteries - General GNB/Gould, Exide, C&D 2
Batteries Grids Lead-calcium alloy GNB/Gould, Exide, ELETEMP Plate growth, loss of C&D contact with active material 3
Batteries Active Material Lead, lead dioxide GNB/Gould, Exide, GAS, CONTAM Dislodging or C&D shedding of active material from the grid 4
Batteries Separators Rubber/glass mat, GNB/Gould, Exide, ELETEMP Decreased electrical polyethelene sheets C&D insulation 5
Batteries Electrolyte Sulfuric acid and GNB/Gould, Exide, CONTAM Chemical reactions, water C&D hydolysis 6
Batteries Vents Fused Alumina GNB/Gould, Exide, MECHSTR Vent breaks allowing C&D contamination to enter 7
Batteries Top Conductors Lead-calcium alloy GNB/Gould, Exide, ELETEMP, CORR, Low electrolyte level C&D EMBR causes corrosion and embritUement 8
Batteries Terminals Lead-calcium alloy, GNB/Gould, Exide, CORR/OX, CORR Poor electrical lead-calcium with C&D contact with external copper insert busses 9
Batteries Container and Cover Polycarbonate, GNB/Gould, Exide,
- MECHSTR, Oxidation of the lead styrene acrylonitrile, C&D CORR/OX causes plate growth acrylo butadiene styrene Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters Reviewed by:
Jerry Edson, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Chargers and General Inverters 2
Chargers and Circuit Breakers Not stated PCP, Elgar CONTAM, WEAR, Increased friction, Inverters EMBR, FAT, binding, loss of CORR/PIT, continuity LOSLUB
- 3 Chargers and Fuse Not stated PCP, Elgar FAT, ELETEMP Metal fatigue and Inverters melting of the fuse material 4
Chargers and Relay Not stated PCP, Elgar CORA/PIT, CORA Loss of continuity Inverters across contacts and thru coil 5
Chargers and 8ectrolytic Not stated PCP, Elgar ELETEMP, VIBR Loss of electrolyte, Inverters Capacitors failure of leads 6
Chargers and Oil Filled Capacitors Not stated PCP, Elgar ELETEMP, VIBR Dielectric Inverters breakdown, failure 0 leads 7
Chargers and Magnetics Copper, polyamide PCP, Elgar
- ELETEMP, Cracking/degr. of Inverters (Transformer, polymer, mylar tape, THERM-CY, VIBR, insulation and seals, Inductor) ferite steel LOTEMP, VOLSTR wire fracture 8
Chargers and Silicon Controlled Not stated PCP, Elgar
- ELETEMP, Over heating due to Inverters Rectifier VOLSTR,CURSTR transients
Table A.2 Gall Report for NPAR Reports Page 118 Document: NUREG/CR-4457, Aging of Class 1E Batteries in Safety Systems of Nuclear Power Plants Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported prOQS Rel.proQs Report Recommendations P~geNo. Item Not discussed in N/A A Phase 2 study of seismic 31 1
report vulnerability and advanced surveillance methods for identying seismic vulnerability [1]
Increased temp. from overcharging, ac Frequent IEEE 450, RG 1.129 IEEE 450, RG Not stated 8, 12, 13, 2
ripple, and the environment accelerates 1.129 14,24-26, oxidation. Poor electrical contact and 32,33 breaking of the container with subsequent loss of electrolyte results in reduced capacity or failure Gassing caused by overcharging or Occasional IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 3
contamination introduced into the 1.129 14,24-26, electrolyte deteriorates the active material 32,33 resulting in reduced capacity Decreased electrical insulation resulting in Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8, 12, 13, 4
internal shorts and failure of the battery 1.129 14,24-26, 32,33 Chemical reactions and hydrolysis causes Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 5
loss of electrolyte and loss of sulfuric acid 1.129 14,24-26, resulting in reduced battery capacity 32,33 Contaminates in the electrolyte result in Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8, 12, 13, 6
reduced capacity 1.129 14,24-26, 32,33 EmbrittJed top conductors are susceptible Occasional IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 7
to breaking and causes loss of capacity 1.129 14,24-26, 32,33 Poor electrical contact results in loss of Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12, 13, 8
capacity and may result in total battery 1.129 14,24-26, failure 32,33 Plate growth and handling stresses Frequent IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 9
results in cracked containers which allow 1.129 14,24-26, electrolyte to escape resulting in reduced 32,33 capacity or total failure Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Not discussed in N/A A comprehensive PM and testing 6-7 1
report program supported by personnel training should be implemented.
Procedures are needed [2]
Failure to operate, fails open Occasional IEEE-650, NEMA ANSIIIEEE Not stated 4-25,4-2 PE 5, IEC 146-2, 741-1986 27,5-4 IEEE-944 Section 7.3 thru 5-9 Fuse fails open. Failure to operate Occasional IEEE-650, NEMA ANSI/IEEE Pursue fuse failures due to thermal 4-25,4-3 PE 5, IEC 146-2, 741-1986 fatigue [2]
27,5-4 IEEE-944 Section 7.3 thru 5-9, 6-7 Contacts open, open ciruit of the coil, and Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-4 relay fails to operate PE 5, IEC 146-2, specific, NEMA 27,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Loss of capacitance and open circuit Frequent IEEE-650, NEMA Vendor Not stated 4-25,4-5 resulting in improper output or failure to PE 5, IEC 146-2,.
specific, NEMA 27,5-4 operate IEEE-944 PE 5, IEC 142-thru 5-9 2
Loss of capacitance and open circuit Frequent IEEE-650, NEMA Vendor Not stated 4-25,4-6 resulting in improper output or failure to PE 5, IEC 146-2, specific, NEMA 27,5-4 operate IEEE-944 PE 5, IEC 142-thru 5-9 2
Short circuits (tum to turn or to ground)or Occasional IEEE-650, NEMA Vendor Not stated 2-19,4-7 change in inductuance resulting in PE 5, IEC 146-2, specific, NEMA 25,4-28, improper output.
5-4 thru 5-2 9
Short or open circuit resulting in improper Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-8 or no output PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Table A.2 Gall Report for NPAR Reports Page 12A Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters Reviewed by:
Jerry Edson, INEL 1St Str tu e/C S b tem
.ys em uc r omp u component Materials Manufacturer ARD mechanism ARDeffects 9
Chargers and Resistors Not stated PCP, Elgar ELETEMP, VIBR Lead fails, decrease Inverters in resistance 10 Chargers and Printed Circuit Not stated PCP, Elgar THERM-CY, CORR, Cracking of circuit Inverters Boards VIBR lines, openlloose at terminals 11 Chargers and Surge Suppressors Not stated PCP, Elgar
- ELETEMP, Semiconductor Inverters VOLSTR, CURSTR barrier breakdown 12 Chargers and Connectors Not stated PCP, Elgar FAT Wire breaks Inverters 13 Chargers and Meters Not stated PCP, Elgar
- CONTAM, Increase in bearing Inverters ELETEMP friction, coil degrades 14 Chargers and Switches Not stated PCP, Elgar CORR, CORR/PIT Loss of continuity Inverters across contacts 15 Chargers and Potentiometer Not stated PCP, Elgar ELETEMP Loss of continuity Inverters across wiper arm and coil Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions Reviewed by:
L. C. Meyer, INEL Item S t
Str e/C Sb M
-I M
,ys em uctur omp u componen atena s anu acturer ARD mec h amsm ARD ff ts eec 1
Protective, Auxiliary, Relay Steel, aluminum, GE & Westinghouse THERM Shape changes for and Control Relays lexan, and phenolic lexan, no effect for steel, aI., or phnol.
2 Protective, Auxiliary, Coil Wire, Spools, & polyamide-imide Not stated THERM & VOLSTR Thermally caused and Control Relays Coatings insulated wire, failures, open copper magnet wire, circuits, and shorts and nylon bobbins 3
Protective, Auxiliary, Coil Spools Nylon, Zytel & lexan Not stated THERM Thermally caused and Control Relays failures 4
Protective, Auxiliary, Coil Coating Polyester tape, fiber Not stated THERM Thermally caused and Control Relays glass tape, & varnish failures 5
Protective, Auxiliary, Contact Carriers Phenolic, Zytel, Not stated THERM Nylon may change in and Control Relays delrin, & nylon shape 6
Protective, Auxiliary, Contacts Silver alloy Not stated WEAR, CHEM Oxidation when and Control Relays exosed to air &
material attrition 7
Protective, Auxiliary, Lead Wires Copper Not stated VIB Loose terminals and Control Relays 8
Protective, Auxiliary, Coil Lead Wire Teflon, silicon Not stated THERM& RAD Slow aging effects, and Control Relays Insulation rubber, and Tefzel degradation in insulation
Table A.2 Gall Report for NPAR Reports Page 128 Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Open circuits, change in resistance Rare IEEE-650, NEMA Vendor Not stated 4-25,4-9 values resulting in improper or no output PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Change in output of the chargerlinverter Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-10 PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Short ciruit within the surge arrestor and Rare IEEE-650, NEMA Vendor Not stated 4-25,4-11 failure to operate PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Fatigue caused by installation stress Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-12 causes wires to break resulting in open or PE 5, IEC 146-2, specific, NEMA 28,5-4 short circuits and failure to operate IEEE-944 PE 5, IEC 142-thru 5-9 2
No or improper response from the meter Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-13 PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Switch failes open or closed Occasional IEEE-650, NEMA Vendor Not stated 4-25,4-14 PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Thermal degradation results in open or Frequent IEEE-650, NEMA Vendor Not stated 4-25,4-15 short circuit and improper output PE 5, IEC 146-2, specific, NEMA 28,5-4 IEEE-944 PE 5, IEC 142-thru 5-9 2
Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs RI e.progs R eport R d.
ecommen ations P age N lte
- o.
m Binding of control relays, have been noted Rare Not discussed in Protection:
Perform root cause failure 28,29, 1
for continuously energized compact relays report IEEE 741, evaluation, develop test method for 35,and with plastic cases resulting in improper IEEE 338 thermally induced failure cause, see 160 operation or failure to operate report for more rec. [2]
The higher temperatures associated with Rare Not discussed in Protection:
Perform root cause failure 28,29, 2
continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35,and failures of relay coils and bobbins IEEE 338 thermally induced failure cause, see 160 resulting in improper operation or failure to report for more rec. [2]
operate.
The higher temperatures associated with Rare Not discussed in Protection:
Perform root cause failure 28,29, 3
continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35,and failures of relay bobbins resulting in relay IEEE 338 thermally induced failure cause, see 160 having improper operation or failure to report for more rec. [2]
operate.
The higher temperatures associated with Rare Not discussed in Protection:
Perform root cause failure 28,29, 4
continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35,and failures of relay coils (assumed it includes IEEE 338 thermally induced failure cause, see 160 coatings) resulting in improper operation report for more rec. [2]
or failure of relay.
Change in shape due to thermal aging Rare Not discussed in Protection:
Perform root cause failure 28,29, 5
can cause binding or improper contact report IEEE 741, evaluation, develop test method for 35,and mating resulting in improper operation or IEEE 338 thermally induced failure cause, see 160 failure of relay.
report for more rec. [2]
Wear due to use and testing resulting in Rare Not discussed in Protection:
Perform root cause failure 28,29, 6
failure to make proper contact.
report IEEE 741, evaluation, develop test method for 35,and IEEE 338 thermally induced failure cause, see 160 report for more rec. [2]
Loose terminations can cause ohmic Rare Not discussed in Protection:
Perform root cause failure 28,29, 7
heating and bumout report IEEE 741, evaluation, develop test method for 35,and IEEE 338 thermally induced failure cause, see 160 report for more rec. [2]
Improper operation or failure to operate.
Rare Not discussed in Protection:
Perform root cause failure 28,29, 8
report IEEE 741, evaluation, develop test method for 35,and IEEE 338 thermally induced failure cause, see 160 report for more rec. [2]
Table A.2 Gall Report for NPAR Reports Page 13A Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions Reviewed by:
L. C. Meyer, INEL Item System Structur eI b
t M
Com~
Su cOIllPonen aterials Manu acturer ARD mec h.
anlsm ARD ff ts eec 9
Protective, Auxiliary, Slip Motor Rotor Aluminum disc &
Not stated CONTAM Metalic iron based and Control Relays stainless steel shaft particles can prevent operation 10 lime Delay Relays Case Steel, Lexan, and Not stated THERM Shape changes for phenolic lexan & phenolic 11 lime Delay Relays timing Motor Magent wire with Not stated THERM Same as other formal varnish insulation varnish 12 lime Delay Relays Relay Silver Not stated WEAR Wear with use 13 lime Delay Relays Relay Delrin, Zytel, Not stated THERM Oxidation of contactl phenolic, & nylon.
14
'Time Delay Relays Cams Delrin & metal Not stated THERM& WEAR Delrin may change shape, metal may wear 15
'Time Delay Relays liming Circuits Resistance and Not stated Not stated Not stated capacitance networks with solid state components 16 lime Delay Relays liming Diaphragm Silicon rubber Not stated THERM Material may take a (Applies to set if not exercised Pneumatic Relay periodically.
Only) 17 Solid State Relays Solid state Not stated Not stated THERM, RAD, Insulation Components - SCRs VOLSTR, CURSTR, degradation from
& TRIAC
& VIB.
therm & rad, fatique from vib.
18 Molded Case Circuit Contacts, Trip Not stated GE, Westinghouse, THERM, ELECT, Material vaporized, Breakers Device, Spring, and
& Gould MECH, & ENV.
annealing bimetal, Case wear, friction & fat 19 Metal-Clad Circuit Housing, Doors, Steel, electroplated GE, Westinghouse, CURSTR, VIB, FAT, Loose parts, Breakers Frame &
steel, & cast bronze & Gould
&CORR.
component failure, Mechanisms stiffening of joints.
20 Metal-Clad Circuit Mechanisms Molybenium disulfide Not stated LOSLUBAND Dryoutand Breakers Lubricants
& petroleum-based THERM hardening of grease lubricants 21 Metal-Clad Circuit Contacts Silver Alloy on GE, Westinghouse, CURSTR, WEAR, Loss of material, Breakers copper base
& Gould THERM,AND wear, and CONTAM contamination 22 Metal-Clad Circuit Insulating Materials Polyester, glass GE, Westinghouse, THERM, EMBR, Contamination, loss Breakers for Power Path fiber-filled epoxy
& Gould AND VOLSTR of dielectric resin, & phenolic properties, & leakage path 23 Safety Injection Relays See relay See relay material GE & Agastat VOLSTR, THERM, Thermal stress, coil Subcomponent descriptions VIB, AND WEAR burnout, set point Descriptions drift, & con. wear 24 Safety Injection Circuit Breakers Molded Case and See CBdetaii GE, Westinghouse, ELECT, THERM, Loss of material, Metal-Clad Circuit descriptions
& Gould VIB, WEAR, & ENV corr, & arcing Breakers evaporation of contacts
Table A.2 Gall Report for NPAR Reports Page 13B Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations P ~eNo. tem Metalic iron based particles can lodge Rare Not discussed in lEE 741-1986 Perform root cause failure 28,29, 9
between the disc and magnet preventing report Section 7, evaluation, develop test method for 35,and operation.
IEEE 338-1987 thermally induced failure cause, see 160 report for more rec. [2J Some rare instances of case shape Rare Not discussed in Safety related:
Perform root cause failure 28,30, 10 changes resulting in binding of contacts report IEEE 741, evaluation, develop test method for 35, &36.
resulting in failure to operate.
IEEE 338 thermally induced failure cause, see report for more rec. [2]
Insulaton failure may cause shorts and Rare Not discussed in Safety related:
Not stated 30,35, &
11 failure to provide timing delay function.
report IEEE 741,
- 36.
IEEE 338 Contacts wear with cycling and making Rare Not discussed in Safety related:
Not stated 30, &35 12
. and breaking load resulting in failure to report IEEE 741, make proper contact.
IEEE 338 Failure to make proper contact.
Rare Not discussed in Safety related:
Not stated 30, &35 13 report IEEE 741, IEEE 338 Carns may wear and high temperature Rare Not discussed in Safety related:
Not stated 30, &35 14 may deform delrin cams resulting in report IEEE 741, degraded o~ration or relay failure.
IEEE 338 Not stated Rare Not discussed in Safety related:
Not stated 30 15 report IEEE 741, IEEE 338 The first operation of relay after a long Rare Not discussed in Safety related:
Not stated 30&36 16 period will have an improper time delay.
report IEEE 741, IEEE 338 Breakdown of insulation, ohmic heating Occasional Not discussed in Safety related:
Not stated 26,27, 17 lead to insulation and component failure, report IEEE 741, 28, &30.
vib. may loosen sockets/pins causing IEEE 338 opens, shorts resulting relay failure.
Damage contacts & arc chute materials, Occasional Not discussed in Safety related:
Replace after two nuisance trips, 78,83, 18 annealed bimetal strips causes nuisance report IEEE 741.
develop diagnostic techniques for 91,97,99, trips, vaporized material deposits on Others: No early detection of component 113, and insulation, loose connections, leakage specific failures. [2]
163 paths, component failure, hardening of lubricants, stiffening of joints, & loss of operability.
Freezing of joints, increased friction, &
Rare Not discussed in Safety related:
Inspection and cleaning after each 85,98, 19 loss of operability report IEEE 741.
interruption of a major fault. [2]
99,100,&
Others: No 163 specific Evaporation of petrolium based grease Occasional Not discussed in Vendor specific Inspection and cleaning after each 85,98, 20 may leave a nonlubricating soap base &
report programs interruption of a major fault. [2]
99,100,&
high temperatures may cause harding of 163 lubricants resulting in loss of operability.
Failure to operate as required.
Occasional Not discussed in Vendor specific Inspection and cleaning after each 85,98, 21 report programs interruption of a major fault. [2]
99,100, 101, &
163.
Failure to provide insulation results in Occasional Not discussed in Vendor specific Inspection and cleaning after each 85,98, 22 circuit failure.
report programs interruption of a major fault. [2]
99,100, 101, &
163.
Coil failures, binding, and electrical Occasional Not discussed in lEE 741-1986 Desirable to have incipient failure 142,159, 23 component failures increase with age.
report Section 7, detection technique to detect both
& 160 Protection relays may also fail due to drift IEEE 338-1987 old and new failure modes [2]
Loss of operability.
Occasional Plant maintenance IEEE 741-1986 Dagnostic techniques should be 142,161, 24 Section 7 developed for use with physical 162, &
inspections to determine condition of 163.
circuit breakers. [2]
Table A.2 Gall Report for NPAR Reports Page 14A Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 Reactor Protection Pressure Seals Ethylene propylene Not stated THERM, RAD, Leaks System Transmitter MOIST-EL 2 Reactor Protection Pressure Fill-Oil Silicon Not stated THERM& RAD Oil degradation System Transmitter 3 Reactor Protection Pressure Electronic Epoxy glass Not stated THERM, RAD, Drift and System Transmitter Components laminate, seats, &
MOIST-EL subcomponent insulation materials degradation 4 Reactor Protection Pressure Piping & Valves Stainless steel Not stated CORR Blockage, leaks System Transmitter 5 Reactor Protection Pressure Valve Packing Not stated Not stated WEAR Leaks System Transmitter 6 Reactor Protection Strain Gage Bourdon Tube, EDPM, Nylon, Not stated RAD, THERM, Resistance change, System Pressure Transduce Electronic copper, tefzel, &
MOIST-EL, &
tube blockage, and Components, Seals steel CONTAM shunting
& Wire 7 Reactor Protection Pressure Switch Bellows, Switch Copper Not stated THERM, MOIST-Wear, tube System Contacts, Seals &
EL, CONTAM, blockage, and Wire WEAR contact resistance change 8 Reactor Protection Resistance Sensing Wire, Platinum, aluminum Not stated RAD, THERM, AND Resistance change System Temperature Device Insulator & Sheath oxide powder, and MOIST-EL and shunting inconel X750 or stainless steel sheath 9 Reactor Protection Nuclear Instrument Nuclear Sensitive Not stated Not stated THERMAL-CY AND Degrades sensor, System Ion Chamber MOIST-EL low resistance, and erratic o.utput 10 Reactor Protection Electronic Modules Various Electronic Not stated Not stated FAT & VIB Loss of fatigue System Components resistance 11 Reactor Protection Relays Coils and Contacts Not stated Not stated WEAR, CONTAM, Contacts wear, System CORR,AND foreign material build CURSTR up causes short ckt.
12 Reactor Protection Scram Breakers Contacts, Under Not stated Westinghouse WEAR Contact wear, pin System Volatge & Shunt Trip binding in uv Attachments attachent, lack of lubricant 13 Reactor Protection Control Cable Conductor
- 16 AWG copper Not stated CORR, MOIST-EL, Mechanical damage System except nuclear RAD, & WEAR
& corrosion on instruments sue terminations RG11/CU Coax 14 Reactor Protection Control Cable Insulation Cross linked Not stated MOIST-EL, RAD, & Mechanical damage, System polyethylene and WEAR insulaton polyethylene degradation, and low ir
Table A.2 Gall Report for NPAR Reports Page 148 Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Seal failure allows leaks leading to Occasional Not discussed in IEEE 338-Not stated 15,18, 1
transmitter drift and moisture intrusion.
report 1987, RG 61,65, &
1.118,ISA 69 67.06, Tech Spec Degradation or loss of fill-oil causes Rare Not discussed in IEEE 338-Not stated 18, & 62 2
transmitter drift and signal variance from report 1987, RG other channels.
1.118,ISA 67.06, Tech Spec Components are subject to drift of zero &
Occasional Not discussed in IEEE 338-Not stated 18,65,&
3 span set points, and ultimate failure, report 1987, RG 70 resulting in loss of data channel.
1.118,ISA 67.06, Tech Spec Blockage causes degraded channel Occasional Not discussed in IEEE 338-Not stated 17, 19,28, 4
operation, components are subject to report 1987, RG 42, &69 loss of calibration, resulting in loss of data 1.118,ISA channel.
67.06, Tech Spec Components are subject to loss of Occasional Not discussed in IEEE 338-Not stated 65 5
calibration, resulting in loss of data report 1987, RG channel.
1.118,ISA 67.06, Tech Spec Sensing element resistance change due Occasional Not discussed in IEEE 338-Not stated 15,17, 6
to radiation, seal failure allows moisture to report 1987, RG 48, &69 get into connectors that lead to shunting 1.118,ISA signal, foreign material blocks sensing 67.06, Tech tube.
Spec Wear leads to switch failure, seal failure Occasional Not discussed in IEEE 338-Not stated 17,34, 7
allows moisture to get into connectors that report 1987, RG 37,49,&
lead to shunting signal, foreign material 1.118,ISA 65 blocks sensing tube.
67.06, Tech Spec Sensing element resistance change due Rare Not discussed in IEEE 338-Not stated 17.19, 8
to radiation, seal failure allows moisture to report 1987, RG 27,32,&
get into sensor and moisture causes 1.118,ISA 70 shunting of signal.
67.06, Tech Spec Transmitter becomes noisy or erratic, also Rare Not discussed in IEEE 338-Not stated 19,20, 9
low insulation resistance (few problems report 1987, RG 27,33, reported).
1.118,ISA 65, &66 67.06, Tech Spec Small system components such as Occasional Not discussed in IEEE 338-Not stated 27,29-33, 10 transistors, capacitors, logic elements, report 1987, RG 35-37,42-terminals and wire connectors are subject 1.118,ISA 45,47-49, to mechanical fatigue-related failures due 67.06, Tech 65, &70 to vibration, most failures are catastropic Spec with unknown cause.
Sticking armature, open or short circuits Occasional Not discussed in IEEE 338-Not stated 11,13,8-11 in the coil of the electromagnet, and report 1987, RG 7, & C-3 contact degradation causes failure to 1.118,ISA function.
67.06, Tech Spec Increased friction, nicking of latch Occasional Not discussed in IEEE 338-Not stated 66,70, 12 surfaces caused by repeated opeations, report 1987, RG and binding and friction causes degraded 1.118,ISA Appendix operation or failure to operate.
67.06, Tech B
Spec Increase in series resistance and loose Rare Not discussed in No specific Further research is needed to 20,21, 13 connections cause failure to accurately report program determine if improved maintenance 23,48, &
conduct current.
and new predictive techniques are 70 needed. [4]
Decreased insulation resistance damage Rare Not discussed in No specific Further research is needed to 20,21, 14 due to handling will accelerate aging and report program determine if improved maintenance 23,48, &
result in cable failing to accurately and new predictive techniques are 70 transmit voltage and current.
needed. [4]
Table A.2 Gall Report for NPAR Reports Page 15A Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems Reviewed by:
L. C. Meyer, INEL Item S.ystem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 15 Reactor Protection Control Cable Jacket Neoprene and Not stated CORR, MOIST-EL, Loss of material, System galvanized steel RAD, EMBR, &
attrition, and except nuclear cable WEAR insulation had PVC and degradation galvanized steel 16 Reactor Protection Cable Penetrations Assembly, Seals, SS, brass, Not stated CORR, MOIST-EL, Loss of material, System Cable, Connectors, elastomer, insul.
&RAD insulation
& Inert Gas Mall, polysulfone, degradation, loss of polyolefin, gold fill gass plated copper 17 Reactor Protection Transmitters, See components B&W CORR, RAD, VIB, See components System Electronic Modules, CURSTR, THERM, Cables, Breakers
&CONTAM Document: NUREG/CR-4747 V1, An Aging Failure Survey of LWR Safety Systems and Components Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1 Four Systems Not stated Not stated Not stated Covered (Same as Volume 2)
Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Item S e/
b M
M A
h
.ystem Structur Com~
Su component aterials anufacturer RDmec anism ARD effects 1 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated CONTAM Buildup of deposits pystem 2 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated WEAR Attrition System 3 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated VIBR Loosening System 4 Auxiliary Feedwater Flow Controllers Not stated Not stated Not stated CLOG Row blockage System 5 Auxiliary Feedwater Flow Controllers Not stated Not stated Not stated Not stated Lossofpertormance System 6 Auxiliary Feedwater. Flow Controllers Not stated Not stated Not stated Not stated Drift, contact failure, System module failure, or elect. failure 7 Auxiliary Feedwater Row Control Not stated Not stated Not stated WEAR Attrition System Recorders 8 Auxiliary Feedwater Flow Control Not stated Not stated Not stated Not stated Loss of performance System Recorders 9 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated CONTAM Buildup of deposites System causing erroneous/erratic signals 10 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated Not stated Out of calibration, System drift, or module faul~
Table A.2 Gall Report for NPAR Reports Page 1SB Document: NUREG/CR*4740, Nuclear Plant-Aging Research on Reactor Protection Systems Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Failure to protect cable insulation and Occasional Not discussed in No specific Further research is needed to 20,21, &
15 conductors.
report program determine if improved maintenance 48 and new predictive techniques are needed. [4]
Radiation causes embrittlement and Rare Not discussed in No specific Further research is needed to 20&23 16 insulation degradation, corrosion causes report program determine if improved maintenance material degradation and material build and new predictive techniques are up, leaking seal allow loss of fill gas and needed. [2]
then moisture intrusion resulting in failure to accurately transmit voltage and current.
See components Rare Not discussed in lEE 338-1987, Further research is needed to IV,69,&
17 report RG 1.118, ISA determine if improved maintenance A-16 67.06, Tech.
and new predictive techniques are Spec needed. [2]
Document: NUREG/CR-4747 V1, An Aging Failure Survey of LWR Safety Systems and Components Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item The aging information in Volume 1 is the Not stated Not discussed in N/A Not stated 1
same as that covered in the Volume 2 report reveiw.
Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Fails to close Rare Not discussed in lEE 741-1986 Not stated F-20 1
report Section 7 Failure to operate - the circuit breaker Occasional Not discussed in lEE 741-1986 Not stated F-20 2
does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to operate - the circuit breaker Rare Not discussed in lEE 741-1986 Not stated F-20 3
does not function properly, either fails to report Section 7 open or fails to close on demand.
Erroneous or erraric signals - erroneous Rare Not discussed in IEEE 338-Not stated F-21 4
or erraric signals are produced by the report 1987, Tech.
instrument because of foreign material Spec.
intrusion.
requirements Erroneous or erratic signals - erroneous Rare Not discussed in IEEE 338-Not stated F-21 5
or erratic signals are produced by the report 1987, Tech.
instrument due to faulty module or loss of Spec.
calibration.
requirements Failure to operate Rare Not discussed in IEEE 338-Not stated F-21 6
report 1987, Tech.
Spec.
requirements Erroneous/erratic signals - erroneous Rare Not discussed in IEEE 338-Not stated F-22 7
erratic signals are produced by the report 1987, Tech.
instrument.
Spec.
requirements Erroneous/erratic signals - erroneous Rare Not discussed in IEEE 338-Not stated F-22 8
erratic signals are produced by the report 1987, Tech.
instrument being out of calibration.
Spec.
reqUirements Eroneous or erratic signals are produced Rare Not discussed in IEEE 338-Not stated F-23 9
by the instrument report 1987, RG 1.118,ISA 67.06, Tech Spec Lossofperlormance Occasional Not discussed in IEEE 338-Not stated F-23 10 report 1987, RG 1.118,ISA 67.06, Tech Spec
Table A.2 Gall Report for NPAR Reports Page 16A Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Item S tr etC S b M
- ystem S uctur omp u component aterials Manufacturer ARD mechanism ARDeffects 11 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated WEAR Attrition System 12 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Erroneous/erratic System Indicators signals 13 Auxiliary Feedwater Level Control Not stated Not stated Not stated FAT Cumulative fatigue System Indicators damage 14 Auxiliary Feedwater Level Control Not stated Not stated Not stated WEAR Attrition System Indicators 15 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Loss of performance System Indicators or end of life 16 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Erroneous/erratic System signals 17 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated FAT Cumulative fatigue System damage 18 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Loss of performance System 19 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CONTAM Buildup of deposits System 20 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated Not stated Loss of performance System 21 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated WEAR Attrition System 22 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CORR Loss of material System 23 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CURSTR Arcing, material System attrition, and carbon deposits 24 Auxiliary Feedwater Pressure Not stated Not stated Not stated Not stated Loss of performance System Transmitter
Table A,2 Gall Report for NPAR Reports Page 168 Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electricai)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Failure to operate Rare Not discussed in IEEE 338-Not stated F-23 11 report 1987, RG 1.118,ISA 67.06, Tech Spec Out of caiibration or faulty module related Rare Not discussed in IEEE 338-Not stated F-27 12 to aging.
report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F-27 13 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F-27 14 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate because of end of life or Rare Not discussed in IEEE 338-Not stated F-27 15 faulty module related to aging.
report 1987, RG
.1.118,ISA 67.06, Tech Spec Loss of performance due to out of Rare Not discussed in IEEE 338-Not stated F-28 16 caiibration or faulty module report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F-28 17 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate due to faulty module Rare Not discussed in IEEE 338-Not stated F-28 18 related to aging.
report 1987, RG 1.118,ISA 67.06, Tech Spec Erroneous or erratic signals are produced Rare Not discussed in IEEE 338-Not stated F-38 19 by the instrument.
report 1987, RG 1.118,ISA 67.06, Tech Spec Erroneous signals are produced by the Occasional Not discussed in IEEE 338-Not stated F-38 20 instrument because of out of caiibration report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F-38 21 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338*
Not stated F-38 22 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F*38 23 report 1987, RG 1.118,ISA 67.06, Tech Spec Erroneous signals are produced by the Rare Not discussed in IEEE 338-Not stated F-39 24 instrument due to out of caiibration or report 1987, RG faulty module.
1.118,ISA 67.06, Tech Soec
Table A.2 Gall Report for NPAR Reports Page 17A Document: NUREG/CR-4747 V2, An Aging Failure Survey of UghtWater Reactor Safety Systems and Components (Electricai)
Reviewed by:
L. C. Meyer, INEL Item S tu e/e S b M
. I M
ARD h
system Struc r omp u componen aterlas anu acturer mec an Ism ARD ff ts eec 25 Auxiliary Feedwater Pressure Not stated Not stated Not stated WEAR Attrition System Transmitter 26 Auxiliary Feedwater Pressure Not stated Not stated Not stated Not stated Open circuit System Transmitter 27 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition System 28 Auxiliary Feedwater Relays Not stated Not stated Not stated Not stated Loss of function System 29 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition System 30 Chemicai and AC Circuit Breakers Not stated Not stated Not stated FAT Cumulative fatigue Volume Control damage System 31 Chemicai and Heat Tracing Not stated Not stated Not stated CaRR Loss of material Volume Control Heaters System 32 Chemicai and Heat Tracing Not stated Not stated Not stated Not stated Abnormal resistance Volume Control Heaters or aging related set System point drift.
33 Chemical and Level Controllers Not stated Not stated Not stated FAT Cumulative fatigue Volume Control damage System 34 Chemicai and Level Controllers Not stated Not stated Not stated Not stated Loss of performance Volume Control System 35 Chemicai and Level Transmitters Not stated Not stated Not stated Not stated Loss of performance Volume Control System 36 Class 1 E DC Power Batteries Not stated Not stated Not stated Not stated Cause accelerated Supply System aging, not hold charge, or end of life 37 Class 1 E DC Power Battery Not stated Not stated Not stated WEAR Attrition Supply System 38 Class 1 E DC Power Battery Not stated Not stated Not stated CONTAM Buildup of deposits Supply System 39 Class 1 E DC Power Battery Not stated Not stated Not stated Not stated Loss of performance Supply System 40 Class 1 E DC Power AC Circuit Breaker Not stated Not stated Not stated WEAR Attrition Supply System 41 Emergency On-Site Diesel Generator Not stated Not stated Not stated Not stated Loss of performance Power Supply System
Table A.2 Gall Report for NPAR Reports Page 178 Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Effect of ~ing on COI1!Ponent Function Contrib to Failure Reported proQs Rel.proQs Report Recommendations Page No. Item Failure to open - failure to operate Rare Not discussed in IEEE 338-Not stated F-39 25 report 1987, RG 1.118,ISA 67.06, Tech Spec Failure to operate Rare Not discussed in IEEE 338-Not stated F-39 26 report 1987, RG 1.118,ISA 67.06, Tech Spec Fails to open - failure of a normally closed Rare Not discussed in Vendor Not stated F-40 27 relay to open upon demand because of report specific, NEMA binding, or wear PE 5, IEC 146-2 Failure to operate because of drift or Rare Not discussed in Vendor Not stated F-40 28 insulation breakdown related to aging.
report specific, NEMA PE 5, lEe 146-2 Failure to operate Rare Not discussed in Vendor Not stated F-41 29 report specific, NEMA PE 5, lEe 146-2 Failure to operate - the circuit breaker Rare Not discussed in ANSI/IEEE Not stated F-47 30 does not function properly, either fails to report 741-1986 open or fails to close on demand.
Section 7 Loss of function Rare Not discussed in No specific Not stated F-48 31 report program Loss of function Rare Not discussed in No specific Not stated F-48 32 report program Erroneous or erratic signals are produced Rare Not discussed in IEEE 338-Not stated F-49 33 by the instrument.
report 1987, RG 1.118,ISA 67.06 Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338-Not stated F-49 34 by the instrument because of being out of report 1987, RG calibration.
1.118,ISA 67.06 Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338-Not stated F-50 35 by the instrument because of being out of report 1987, RG calibration or faulty module.
1.118,ISA 67.06 Loss of function - lack of specified output Occasional Not discussed in IEEE 450-Not stated F-56 36 from batteries report 1987, RG 1.129, Tech Spec Surveil.
Loss of function - inability of the charging Rare Not discussed in Vendor Not stated F-57 37 unit to perform its function to report specific, NEMA specifications.
PE 5, IEC 146-2 Loss of function - inability of the charging Rare Not discussed in Vendor Not stated F-57 38 unit to perform its function to report specific, NEMA specifications.
PE 5, IEC 146-2 Loss of function - inability of the charging Frequent Not discussed in Vendor Not stated F-57 39 unit to perform its function to report specific, NEMA specifications because of set point drift or PE 5, lEe 146-faulty module.
2 Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-58 40 does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to perform as expected because of Rare Not discussed in Vendor Not stated F-61 41 aging related component drift or out of report specific, RG calibration.
1.108, Tech.
Specs.
Table A.2 Gall Report for NPAR Reports Page 18A Document: NUREG/CR-4747 V2, An Aging Failure SUivey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Item System StructureiComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 42 Emergency On-Site Diesel Generator Not stated Not stated Not stated Not stated Loss of function Power Supply System 43 CLASS 1E AC Circuit Breaker Not stated Not stated Not stated WEAR Attrition Instrumentation, Uninterruptable Power Supply System 44 CLASS 1E Inverter Not stated Not stated Not stated WEAR Attrition Instrumentation, Uninterruptable Power Supply System 45 CLASS 1E Inverter Not stated Not stated Not stated Not stated Loss of function Instrumentation, Uninterruptable Power Supply System 46 CLASS 1E Inverter Not stated Not stated Not stated Not stated Loss of performance Instrumentation, Uninterruptable Power Supply System 47 High Pressure AC Circuit Breakers Not stated Not stated Not stated FAT Cumulative fatigue Injection System damage 48 High Pressure AC Circuit Breakers Not stated Not stated Not stated WEAR Attrition Injection System 49 High Pressure AC Circuit Breakers Not stated Not stated Not stated Not stated Los of performance Injection System 50 High Pressure Row Transmitter Not stated Not stated Not stated Not stated Cause accelerated Injection System aging 51 High Pressure Row Transmitter Not stated Not stated Not stated Not stated Loss of performance Injection System 52 High Pressure Row Transmitter Not stated Not stated Not stated FAT Cumulative fatigue Injection System damage 53 High Pressure Flow Transmitter Not stated Not stated Not stated WEAR Attrition Injection System 54 High Pressure Heat Tracing Not stated Not stated Not stated CORR Loss of material Injection System Heaters 55 High Pressure Heat Tracing Not stated Not stated Not stated Not stated Winding failure, Injection System Heaters open, short, or high resistance 56 High Pressure Load Sequence Not stated Not stated Not stated Not stated End of life Injection System Controllers 57 High Pressure Load Sequence Not stated Not stated Not stated CONTAM Builup of deposits Injection System Controllers 58 High Pressure Load Sequence Not stated Not stated Not stated Not stated Loss of performance Injection System Controllers 59 High Pressure Level Transmitters Not stated Not stated Not stated Not stated Loss of performance Injection System 60 High Pressure Pressure Not stated Not stated Not stated Not stated Loss of performance Injection System Transmitter 61 Service Water AC Breakers Not stated Not stated Not stated FAT Fatigue system accumulative damaaes
Table A.2 Gall Reportfor NPAR Reports Page 188 Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Eff fA' d.
ecto,glng on Component Function Contrib to Failure Reported progs Rel.progs Report Recommen ations P age N lte
- o.
m Failure due to open circuit.
Rare Not discussed in Vendor Not stated F-61 42 report specific, RG 1.108, Tech.
Specs.
Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-63 43 does not function properly, either fails to report Section 7 open or fails to close on demand.
Loss of function - the inverter fails to Occasional Not discussed in Vendor specific Not stated F-64 44 perform its intended function to specified report programs.
requirements.
Tech. Specs.
The inverter fails to perform its intended Occasional Not discussed in Vendor specific Not stated F-64 45 function to specified requirements due to report programs.
electrical failure, insulation breakdown, Tech. Specs.
open or short circuit related to aging.
The inverter has degraded operation Occasional Not discussed in Vendor specific Not stated F-64 46 because of aging related drift or faulty report programs.
modules.
Tech. Specs.
Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-66 47 does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-66 48 does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-66 49 does not function properly, either fails to report Section 7 open or fails to close on demand because of a faulty module.
Erroneous or erratic signals are produced Rare Not discussed in IEEE 338-Not stated F-67 50 by the instrument report 1987, RG 1.118 Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338-Not stated F-67 51 by the instrument because out of report 1987, RG calibration.
1.118 Failure to operate Rare Not discussed in IEEE 338-Not stated F-67 52 report 1987, RG 1.118 Failure to operate Rare Not discussed in IEEE 338-Not stated F-67 53 report 1987, RG 1.118 Loss of function Rare Not discussed in No specific Not stated F-71 54 report program Loss of function Occasional Not discussed in No specific Not stated F-71 55 report program Erroneous or erratic signals Rare Not discussed in IEEE 338-Not stated F-72 56 report 1987, RG 1.118 Failure to operate Occasional Not discussed in IEEE 338-Not stated F-72 57 report 1987, RG 1.118 Failure to operate because of faulty Occasional Not discussed in IEEE 338-Not stated F-72 58 module report 1987, RG 1.118 Erroneous or erratic signals because unit Occasional Not discussed in IEEE 338-Not stated F-73 59 out of calibration.
report 1987, RG 1.118 Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338-Not stated F-82 60 by the instrument because of set point report 1987, RG drift due to agill9.
1.118 Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-88 61 does not function properly, either fails to report Section 7 open or fails to close on demand.
Table A.2 Gall Report for NPAR Reports Page 19A Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Item System S
etC b
tructur omp Su component Materials Manufacturer ARD mechanism ARDeffects 62 Service Water AC Breakers Not stated Not stated Not stated WEAR Attrition System 63 Service Water AC Breakers Not stated Not stated Not stated Not stated Binding or out of System adjustment 64 Service Water AC Breakers Not stated Not stated Not stated CONTAM Buildup of deposits System 65 Service Water AC Breakers Not stated Not stated Not stated Not stated Coil failure System 66 Service Water Row Indicators Not stated Not stated Not stated Not stated Loss of performance System 67 Service Water Row Swicthes Not stated Not stated Not stated CONTAM Buildup of deposits System 68 Service Water Row Swicthes Not stated Not stated Not stated Not stated Loss of performance System 69 Service Water Pressure Indicators Not stated Not stated Not stated CLOG Buildup System 70 Service Water Pressure Indicators Not stated Not stated Not stated Not stated Loss of performance System Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Item System StructuretComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
SOY ASCO 3-Way Coil Class H insulation ASCO
- ELETEMP, Loss of dieletric Direct Acting CURSTR,&
strength and VOLSTR conductor short/open 2
SOY Core Stainless steel ASCO CONTAM Friction between core and guide 3
SOY Disk Holder Assy EPDRM OR Vitron ASCO ELETEMP Degradation of Seat elastomers 4
SOY Disc Holder Spring Steel AS CO CORR Spring relaxation or failure 5
SOY Core Spring Stainless steel ASCO CORR Spring failure 6
SOy Disc Holder EPDM OR Viton ASCO CONTAM&
Seat degradation Assembly Seat ELETEMP 7
SOy 3-Way Pilot Coil Not stated ASCO
- ELETEMP, Insulation failure and Operated CURSTR, &
conductor VOLSTR open/short 8
SOY Core Not stated ASCO CONTAM Binding between core and guide 9
SOY Disc Holder Assy Elastomers ASCO CORR ELETEMP Valve disc adheres Seat to oriface
Table A.2 Gall Report for NPAR Reports Page 19B Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommen d ations P age N lte
- o.
m Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-88 62 does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-88 63 does not function properly, either fails to report Section 7 open or fails to close on demand.
Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-88 64 does not function properly, either fails to report Section 7 open or fails to close on demand.
Premature open - the opening of the Rare Not discussed in IEEE 741-1986 Not stated F-88 65 circuit breaker prior to demand.
report Section 7 Failure to operate due to bGing out of Occasional Not discussed in IEEE 338-Not stated F-89 66 calibration (aging related).
report 1987, RG 1.118 Erroneous or erratic signals Rare Not discussed in IEEE 338-Not stated F-89 67 report 1987, RG 1.118 Erroneous or erratic signals due to set Frequent Not discussed in IEEE 338-Not stated F-90 68 point drift, insulation breakdown or out of report 1987, RG calibration.
1.118 Erroneous or erratic signals Rare Not discussed in IEEE 338-Not stated F-104 69 report 1987, RG 1.118 Erroneous or erratic signals because of Rare Not discussed in IEEE 338-Not stated F-104 70 being out of calibraton.
report 1987, RG 1.118 Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Valve does not operate Occasional Not discussed in Vendor specific R&D to develope test methods.
25-26.34-1 report programs Testing of proposed monitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Partiallfull failure of valve to change Occasional Not discussed in Vendor specific R&D to develope test methods.
25-26.34-2 position report programs Testing of proposed mOnitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34-3 report programs Testing of proposed monitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34-4 report programs Testing of proposed monitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Seat leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34-5 report programs Testing of proposed monitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Seat leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34-6 report programs Testing of proposed monitoring 35.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
7 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
8 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [41 Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
9 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Table A.2 Gall Report for NPAR Reports Page 20A Document: NUREG/CR-4819 Y1, Aging and Service Wear of Solenoid-Operated Yalves Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Item S e/
Sb iystem Structur Comp u component Materials Manufacturer ARD mechanism ARDeffects 10 SOY Disc Holder Spring Steel ASCO CORR Spring relaxation or failure 11 SOY Pressure Diaphragm ASCO CONTAM Blocked bleeder hole Bleed Hole 12 SOY Exhaust Diaphragm ASCO CONTAM Blocked bleeder hole Bleed Hold 13 SOY Core Spring Stainless steel ASCO CORR Spring failure 14 SOY Disc Holder Assy EPDM ASCO CONTAM Seat degradation Seat ELETEMP 15 SOY Pressure Diaphragm EPDM OR Nomex ASCO CONTAM Continuous exhaust fabric ELETEMP 16 SOY Exhaust Diaphragm EPDM OR Nomex ASCO CONTAM Leakage through fabric ELETEMP exhaust port 17 SOY 2-Way Direct Coil Class H insulation Yalcore ELETEMP Insulation failure Operating CURSTR YOLSTR short/open conductors 18 SOY 2-Way Direct Coil Not stated Yalcore ELETEMP Insulation failure Operating CURSTR YOLSTR short/open conductors 19 SOY 2-Way Direct Plunger Spring Stainless steel Yalcore CONTAM CORR Binding in guide.
Operating spring breakage 20 SOY 2-Way Direct Plunger Spring Stainless steel Yalcore CONTAM CORR Binding in guide.
Operating spring breakage 21 SOY 2-Way Direct Pilot Spring Not stated Yalcore CORR Spring failure Operating 22 SOY 2-Way Direct Plunger Stainless steel Yalcore CONTAM Binding in guide tube Operating 23 SOY 2-Way Direct Plunger.
Stainless steel Yalcore CONTAM Binding in guide tube Operating 24 SOY 2-Way Direct Pilot Spring Stainless steel Yalcore CORR Spring failure Operating 25 SOY 2-Way Direct Position Reed Not stated Yalcore Not stated Contact failure Operating 26 SOY 2-Way Direct Poppet Seat Elastomers Yalcore ELETEMP Eroded seat Operating CONTAM
- Table A.2 Gall Report for NPAR Reports Page 208 Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
10 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve slow to respond Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
11 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4J Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
12 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4J Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
13 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4J Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
14 report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4J Valve leakage - valve failure to operate as Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
15 required report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve leakage - valve failure to operate as Not stated Not discussed in Vendor specific R&D to develope test methods.
25-26.34.
16 required report programs Testing of proposed monitoring 36.41-43.
techniques. Develope baseline data. 54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
16.25-28.
17 report programs Testing of proposed monitoring 34.37.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
18 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4J Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
16.25-28.
19 report programs Testing of proposed monitoring 34.37.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
20 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
21 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve sluggish or not operational Not stated Not discussed in Vendor specific R&D to develope test methods.
16.25-28.
22 report programs Testing of proposed monitoring 34.37.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve sluggish or no operation Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
23 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Slow valve closure Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
24 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
No or constant position indication Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
25 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
16.25-28.
26 report programs Testing of proposed monitoring 34.37.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Table A.2 Gall Report for NPAR Reports Page 21A Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Item S S
e/
b
- >},stem tructur Comp Su comp_onent Materials Manufacturer ARC mechanism ARC effects 27 SOY 2-Way Direct Poppet Seat EPDM Val core ELETEMP Eroded seat Operating CONTAM 28 SOY 2-Way Direct Pilot Seat Seal EPDM Valcore ELETEMP Eroded seat Operating CONTAM 29 SOY 2-Way Direct Coil Class H insulation TRC ELETEMP Insulation failure and Operating CURSTR VOLSTR short/open conductor 30 SOY Coil Diode Not stated TRC Not stated Open diode 31 SOY Core Not stated TRC CONTAM Binding in core tube 32 SOY Pilot Disc Seat Stainless steel TRC ELETEMP Degradation of CONTAM elastomers 33 SOY Main Disc Stainless steel TRC CONTAM Jammed disc 34 SOY Position Switch Not stated TRC WEAR Contact failure 35 SOY Position Relay Not stated TRC Not stated Coil conductor short/open 36 SOY Return Spring Stainless steel TRC CORR Spring breakage 37 SOY Main Disc Seat Stainless steel TRC WEAR Seat degradation Document: NUREG/CR-4819 V2, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants, Vol. 2 Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARC mechanism ARC effects 1
Solenoid-Operated Core Seat & Seals Not stated ASCO AND Skinner THERM &AGR*
Prolonged Valves (Elastomeric CHEM temperatures Components) degrades seals, chem attack by oils 2
Solenoid-Operated Solenoid Coil Not stated Not stated THERM Degraded insulation Valves Insulation 3
Solenoid-Operated Core Spring Not stated Not stated WEAR & CORR Changes in Valves mechanical propeties. binding, 0 corrsion contam 4
Solenoid-Operated Sliding Surfaces Not stated Not stated WEAR & CORR Loss of material and Valves crud buidup
Table A.2 Gall Report for NPAR Reports Page 218 Document: NUREG/CR-4819 Vl, Aging and Service Wear of Solenoid-Operated Valyes Used in Safety Systems of Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
27 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods.
19.25-28.
28 report programs Testing of proposed monitoring 34.38.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
29 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails closed Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
30 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
31 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
32 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
33 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Loss of position indication Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
34 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Position indication does not change Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
35 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve remains open Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
36 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Valve does not have a tight shutoff Not stated Not discussed in Vendor specific R&D to develope test methods.
21.25-28.
37 report programs Testing of proposed monitoring 34.39.
techniques. Develope baseline data. 41-43.54 Evaluation of failures [4]
Document: NUREG/CR-4819 V2, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants, Vol. 2 Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Chemical attack of elastomers by oil and Rare Not discussed in Vendor specific Determine the sensitivity with which 5,7,8, 1
degradation of elastomers resulting from report programs degraded elestomeric valve seats 11, &44 prolonged operation at excessively high can be determined from electrical temperatures resulting in failure to measurements [2]
o!>9rate.
Electrical failure of solenoid coil, caused Occasional Not discussed in Vendor specific Visual inspections and electrical 5,7,8, 2
by high-voltage turn-off transients in report programs resistance tests [2]
11, &44 combination with insulation weakened by prolonged operation at high temperatures, electrical failure due to short circuit, conductor burnout.
Changes in mechanical properties of Rare Not discussed in Vendor specific Visual inspections and electrical 5,7,8, 3
materials, binding in operation, hum or report programs characterization of inrush currents 11, &44 chatter, worn spring, & wear, change in
[2]
valve operating time or in rush current.
Mechanical binding and sluggish shifting Occasional Not discussed in Vendor specific Visual inspections and electrical 5,7,8, 4
caused by wom or improper parts or the report programs characterization of inrush currents 11, &44 presence of foreign materials inside the and valve actuation times. [2]
valve, increase in frictional force
Table A.2 Gall Report for NPAR Reports Page 22A Document: NUREG/CR*4928, Degradation of Nuclear Plant Temperature Sensors Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeHects 1
Temperature RTD Sensing Wire Platinum Not stated OXIDAT, VIB, Platininum oxide Sensors or Film CONTAM, & ELE*
build up, fat, ion TEMP migration, & strain 2
Temperature RTD Insulation Powder or cement Not stated MOIST*EL Moisture decreases Sensors (material not resistance identified in report) 3 Temperature RTD Sheath Stainless steel Not stated VIB Cold working in Sensors metals Document: NUREG/CR-4939 V1, Improving Motor Reliability in Nuclear Power Plants - Performance Evaluation and Maintenance Practices Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Electric Motors Dielectric, Not stated Not stated Not stated Insulation is most Rotational, affected by aging Mechanical mechanisms Document: NUREG/CR-4939 V2, Improving Motor Reliability in Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Motor Insulation Glass, mylar, dacron Westinghouse ELETEMP Slot wedge w/poly binder, epoxy, developed hole(s),
poly fibers & poly arcing to ground varnish 2
Motor Bearing Not stated Westinghouse ELETEMP WEAR Bearing failure Document: NUREG/CR-4939 V3, Failure Analysis and Diagnostic Tests on A Naturally Aged Large Electric Motor Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
400HP, 2400 V Not stated Not stated VOLSTR Insulation Motor breakdown Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems Reviewed by:
L. C. Meyer, INEL Item S Strtue/C Sb t
MOl M
.ystem uc r omp u componen aterla s anu acturer ARD h
0 mec amsm ARD H e ects 15 PWR high pressure Air Operated Valves Not stated Not stated CONTAM Parts degrade from injection system oil in air supply 16 PWR high pressure HPI Nozzles and Stainless steel Not stated THERM FAT Crack initiation and injection system Thermal Sleeve propagation 17 PWR high pressure I & C ElectroniCS Small Electronic Not stated Not stated CORR Opens, shorts, and injection system Components loose connections 18 PWR high pressure PIPING Stainless steel Not stated THERM FAT, Cracking & abrasive injection system WEAR, VIB,&
wear MECHSTR 19 PWR high pressure Valve Stainless steel Not stated WEAR & CONTAM Leakage, blockage, injection system
& mechanical linkage faults 20 PWR high pressure Pump Stainless steel Not stated THERM-CY, Wear on parts and injection system WEAR, VIB, & FAT seal leaks 21 PWR high pressure Pipe Supports Not stated Not stated VIBAND FAT Loosening of injection system connections or breaking loose 22 PWR high pressure Motor Operated Stainless steel Not stated WEAR AND Loose connections, injection system Valve VOLSTR wear on moving parts, motor failure
Table A.2 Gall Report for NPAR Reports Page 228 Document: NUREG/CR-4928, Degradation of Nuclear Plant Temperature Sensors Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Changes in resistance causes calibration Not stated Not discussed in RG 1.118, Burn-in program for new sensors, A-9, and 1
changes report IEEE 338-1987 develop a data base for degradation A-31 to A-mechanisms, and simple tests to 36 check sensor prob. [2]
Shunting of sensing element occurs when Not stated Not discussed in No specific Burn-in program for new sensors, A-9, and 2
insulating powder gets wet. moisture report program develop a data base for degradation A-31 to A-intrusion occurs when the seals dry out, mechanisms, and simple tests to 36 shrink, crack, or leak resulting in check sensor prob. [2]
calibration shift or failure to function.
Mechanical shock and vibration can Not stated Not discussed in No specific Burn-in program for new sensors, A-9, and 3
cause cold working in metal that leads to report program develop a data base for degradation A-31 to A-failure of the sheath and moisture mechanisms, and simple tests to 36 intrusion.
check sensor prob. [2]
Document: NUREG/CR-4939 V1, Improving Motor Reliability in Nuclear Power Plants - Performance Evaluation and Maintenance Practices Reviewed by:
Jerry Edson, INEL f
R I R
rtR d ti P
Effect 0 Aging on Component Function Contrib to Failure Reported progs e.progs epo ecommen a ons age N It
- o.
em This report references a phase I study Not stated EPRI; IEEE EPRI; IEEE 4, Motors important to safety should 1-6; 2-7; 1
that investigated aging effects. This 4,43,85,95,112,117, 43,85, 95, 112, undergo cost-effective PM programs 4-1; 5-report only addresses motor evaluation 286,429,432,522 117,286, 429,
[2]
9,10,11,&
and maintenance practices 12; 7-1 Document: NUREG/CR-4939 V2, Improving Motor Reliability in Nuclear Power Plants Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure* Reported progs Rel.progs Report Recommendations Page No. Item Motor failure Not stated Not discussed in IEEE 334-1974 The 'plug reversal life test' is 2-1,6-1 1
report Section 14.2.3 recommended for motor qualification. [2]
Motor failure Not stated Not discussed in IEEE 334-1974 Not stated 4-1,5-1, 2
report Section 14.2.3 6-1 Document: NUREG/CR-4939 V3, Failure Analysis and Diagnostic Tests on A Naturally Aged Large Electric Motor Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Motor failure Frequent DC insulation &lor IEEE 334-1974 Install effective grnd or grnd 3-4 1
polarization tests Section 14.2.3 detectors on 3 Ph 'capacitance' grnded (delta) PWR syst [2]
Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems Reviewed by:
L. C. Meyer, INEL E
f ffect 0 Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Fail to operate Rare Not discussed in Vendor specific Not stated 36 15 report program. Tech Spec surveil!.
Nozzle leaks and loose parts resulting in Rare Not discussed in Dye penetrant, Not stated 36&53 16 degraded HPI system report ultrasonic, radiography Failure to operate Occasional Not discussed in IEEE 338-1987 Not stated 36 17 report Through the pipe wall leakage resulting in Rare Not discussed in Dye penentant, Not stated 36&53 18 HPIS degraded operation or failure to report ultrasonic, function.
radiography Failure to operate resulting in HPIS Rare Not discussed in Vendor specific Not stated 36&53 19 failure. Valve failure allowes cold water to report programs flow back into primary system resulting piping cracks.
Fail to start or run Rare Not discussed in Vendor specific Not stated 36 20 report programs Lose of pipe supports stresses piping Rare Not discussed in Plant specific Not stated 36 21 leading to potential pipe failure and HPIS report program failure.
Valve failure to operate results in HPIS Rare Not discussed in Vendor specific Not stated 36 22 failure.
report programs
Table A.2 Gall Report for NPAR Reports Page 23A Document: NUREG/CR-4992 V1, Aging and Servcie Wear of Multistage Switches Used in Safety Systems of Nuclear Power Plants Reviewed by:
Jerry Edson, INEL Item S t
Str tu eJC S b t
M
. I M
ARD h'
- iysem uc r omp u componen aterlas anufacturer mee anlsm ARD ff e eets 1
Multistage Switches General GE, Westinghouse, Electro., Micro 2
Multistage Switches Cam Shaft Steel, AI, brass GE, Westinghouse, EXFORCE, WEAR Bent or twisted shaft Electro., Micro 3
Multistage Switches Cam Shaft Steel, AI, brass GE, Westinghouse, MECHSTR, WEAR Broken camshaft Electro., Micro 4
Multistage Switches Contacts Silver or silver alloy GE, Westinghouse, CORR, FAT, Broken or distorted Electro., Micro FATITHERM, VIBR, contac~ sticking,
- CONTAM, loose contact ELETEMP, WEAR 5
Multistage Switches Contacts Silver or silver alloy GE, Westinghouse,
- ELETEMP, Pitted, worn, or Electro., Micro CURSTR, VOLSTR, welded contact 6
Multistage Switches Contact Block Phenolic GE, Westinghouse, VIBR Loose contact bank Electro., Micro 7
Multistage Switches Moving Contact Steel, AI, brass GE, Westinghouse, FAT Spring breaks Spring Electro., Micro 8
Multistage Switches Moving contact Not stated GE, Westinghouse, FAT Gear breaks Assembly Electro., Micro 9
Multistage Switches Moving Contact Pin Not stated GE, Westinghouse, ELETEMP, FAT, Pin breaks Electro., Micro THERM-CY 10 Multistage Switches Cams Polyphenylene oxide, GE, Westinghouse, ELETEMP, RAD, Closing or opening acetal, phenolic Electro., Micro THERM-CY, WEAR cam failure 11 Multistage Switches Cam Follower Polycarbonate GE, Westinghouse, ELETEMP, RAD, Broken or warped Electro., Micro VIBR follower 12 Multistage Switches Cam Follower Polycarbonate GE, Westinghouse, WEAR Slipping of cam Electro., Micro follower 13 Multistage Switches Switch Handle Polycarbonate GE, Westinghouse, VIBR Broken or loose set Electro., Micro screws 14 Multistage Switches Shaft Bearings Not stated GE, Westinghouse, LOSLUB, WEAR, Bearing freezes up Electro., Micro CONTAM 15 Multistage Switches Gear Not stated GE, Westinghouse, FAT, WEAR Gear failure Electro., Micro 16 Multistage Switches Detent Mechanism Steel, AI, brass, GE, Westinghouse, FAT, WEAR Wom detent vulcanized fiber Electro., Micro mechanism, loose detent roller pin 17 Multistage Switches Detent Stop Arm Steel, AI, brass GE, Westinghouse, EXFORCE Bent stop arm Electro., Micro
Table A.2 Gall Report for NPAR Reports Page 238 Document: NUREG/CR-4992 V1, Aging and Servcie Wear of Multistage Switches Used in Safety Systems of Nuclear Power Plants Reviewed by:
Jerry Edson, INEL Effect of Aging on Com~nent Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Not stated Not discussed in No Operators provide feedback on 2,10,52 1
report specific/vendor problems, failures should be specific analyzed,no further consideraten by programs NPAR [2]
Bent or twisted shaft causes incorrect Not stated General - none No Not stated 2,10,,31-2 contact alignment and failure to operate specifically for specific/vendor 37,41-44, as required switches specific 52 programs Switch will not change state resulting in Not stated General - none No Not stated 2, 10,31-3 failure to operate specifically for specific/vendor 37,41-44, switches specific 52 programs Contacts do not close or change state, Frequent General - none No Not stated 2, 10,31-4 open or short circuit, high electrical specifically for specific/vendor 37,41-44, resistnace resulting in failure to operate switches specific 52 programs High contact resistance resulting in failure Frequent General - none No Not stated 2, 10,31-5 to operate as required specifically for specific/vendor 37,41-44, switches specific 52 programs Contacts do not mate properly resulting in Not stated General - none No Not stated 2, 10,31-6 failure to operate specifically for specific/vendor 37,41-44, switches specific 52 programs No positive return of cam followers, Not stated General - none No Not stated 2, 10, 31-7 contacts may open or close randomly specifically for specific/vendor 37,41-44, resulting in failure to operate switches specific 52 programs Contacts to not change state resulting in Not stated General - none No Not stated 2, 10, 31-8 failure to operate specifically for specific/vendor 37,41-44, switches specific 52 programs Contacts will tend to remain closed during Not stated General - none No Not stated 2, 10,31-9 opening cam action resulting in failure to specifically for specific/vendor 37,41-44, operate switches specific 52 programs Contacts to not change state resulting in Not stated General - none No Not stated 2, 10,31-10 failure to operate specifically for specificlvendor 37,41-44, switches specific 52 programs Contacts do not change state resulting in Not stated General - none No Not stated 2, 10,31-11 failure to operate specifically for specificlvendor 37,41-44, switches specific 52 programs Incomplete contact closure resulting in Not stated General - none No Not stated 2, 10,31-12 failure to operate as required specifically for specificlvendor 37,41-44, switches specific 52 programs Switch will not change state resulting in Not stated General - none No Not stated 2, 10,31-13 failure to operate specifically for specificlvendor 37,41-44, switches specific 52 programs Switch will not change state resulting in Not stated General - none No Not stated 2, 10,31-14 failure to operate specifically for specific/vendor 37,41-44, switches specific 52 programs Switch will not maintain position resulting Not stated General - none No Not stated 2, 10,31-15 in failure to operate specifically for specificlvendor 37,41-44, switches specific 52 programs False indication of position change, Frequent General - none No Not stated 2, 10,31-16 contacts do no properly line up resulting in specifically for specific/vendor 37,41-44, failure to operate as required switches specific 52 programs Overtravel of cams at end stop resulting in Not stated General - none No Not stated 2, 10,31-17 failure to operate as required specifically for specificlvendor 37,41-44, switches specific 52 programs
Table A.2 Gall Report for NPAR Reports Page 24A Document: NUREG/CR-5008, Development of A Testing and Analysis Methodology to Determine the Functional Condition of Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL ISS tu e/C S b ARD A
ff tem
'}'Stem truc r omp u comp_onent Materials Manufacturer mechanism ROe ects 1
Solenoid Valves General Not stated 2
Solenoid Valves Spring Not stated Not stated Not stated Weakened spring 3
Solenoid Valves Valve Seat Not stated Not stated CONTAM Not stated 4
Solenoid Valves Plunger Not stated Not stated Not stated Sticking plunger Document: NUREG/CR-5051, Detecting and Mitigating Battery Charger and Inverter Aging Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Inverter Automatic Transfer Not stated Not stated ELETEMP&
Degraded Switch (Two Pairs of CURSTR component or burn SCR's) out 2
Battery Electrolytic Not stated Not stated ELETEMP Reduced capacitor Capacitors life 3
Battery Semi-Conductors Not stated VIB, THERM, &
Vibration loosens CURSTR connections & heat degrades operation 4
Battery Magnetics -
High permeability Not stated ELETEMPAND Aging degradation Transformers alloys, copper CURSTR resulting from over windings, &
heating & elec.
insulation stress 5
Battery Complete Assembly Enclosures and Seven listed ELETEMP&
Overheating &
electrical
- CURSTR, electrical transients components from stresses Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers Reviewed by:
Jerry Edson, INEL Item S t
Str tu e/C S b M t - I M
f tu
.ys em uc r omp u componen a erla s anu ac rer ARD h
mec amsm ARD ff ts eec 1
Motor Control Center General 2
Motor Control Center Molded Case Circuit Lubr., adhes.,
Not stated FAT, WEAR, Mech. stress, Breakers neoprene, silicone, CONT AM, CORR, sticking, surface polyester, phenolic, CORR/PIT, deterioration, low rubber, silver alloy, torque copper, stainless steel 3
Motor Control Center Molded Case Circuit Lubr., adhes.,
Not stated
- WEAR, Out of adjustment, Breakers neoprene, silicone, defective latch, polyester, phenolic, short/ground, rubber, silver alloy, stresses copper, stainless steel 4
Motor Control Cente Relay Phenolic, vulcanized Not stated ELETEMP, CORR, Breakdown of rubber, silver alloy, CORR/PIT insulation, contact copper, steel surface degradation 5
Motor Control Cente Relay Phenolic, vulcanized Not stated CONTAM, CORR, Foreign mat'I rubber, silver alloy, CORR/PIT, VIBR, accumulation, copper, steel FAT surface degradation, misalign.
6 Motor Control Cente Relay Phenolic, vulcanized Not stated WEAR Out of calibration rubber, silver alloy, copper, steel 7
Motor Control Center Transformer Phenolic, fiberglass, Not stated
- ELETEMP, Overheating, copper wire, teflon CURSTR,VOLSTR deterioration and breakdown of insulation
Table A.2 Gall Report for NPAR Reports Page 24B Document: NUREG/CR-5008, Development of A Testing and Analysis Methodology to Determine the Functional Condition of Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs R eport R d ti ecommen a ons P age N lte
- o.
m This report is not an aging assessment of Not stated Not discussed in Vendor specific Explore altemative analytical 23 1
sovs. The report investigates testing and report programs techniques. Further develop and analysis methodologies.
validate coherency model [2]
Not stated Not stated Not discussed in Vendor specific Not stated 13 2
report programs Not stated Not stated Not discussed in Vendor specific Not stated 13 3
report programs Not stated Not stated Not discussed in Vendor specific Not stated 13 4
report programs Document: NUREG/CR-5051, Detecting and Mitigating Battery Charger and Inverter Aging Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Inverter fails and vital bus loads are Not stated Not discussed in Vendor specific Not stated 3-15 TO 1
automatically transferred to altemate report programs 3-22 source if failure occurs.
Aging due to high temperature leads to Frequent Not discussed in Vendor specific Improve thermal efficiency by using 3-4 TO 3-2 capacitor failure resulting in improper report programs forced air cooling. Manufacture 6
output.
. improvements such as adding a fuse module. [2]
Aging due to local heat buildup results in Occasional Not discussed in Vendor specific Improved maintenance and testing 3-7,4-13, 3
short circuit of the SCR and an inverter report programs done more often. [2]
&5-7 failure.
Transformer aging caused by over Not stated Not discussed in Vendor specific Improved maintenance and testing XIII,1-6, 4
heating, electrical transients, and report programs done more often. [2]
3-9, &5-6 personnel error results in chargerlinvertor failure.
Electrolytic capacitors, fuses, magnetics Not stated Plant maintenance Vendor specific Establish a comprehensive XIII,4-15, 5
(inductors and transformers) and programs maintenance program that
&7-4 semiconductors failure results in addresses inspection, testing, chargerlinvertor failure.
predictive and corrective maintenance [2]
Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers Reviewed by:
Jerry Edson, INEL Eft C
F
- b F*I R
ed R
ect of Aging on omponent unction Contrl to al ure eport progs Rel.progs eport R d.
ecommen ations P
N o.
age tem Not stated IEEE 308,279,317; IEEE 308, 279, Detailed survey of PM, surveillance 5-1 thru 5-1 RG 1.106,1.63; 317; RG 1.106, techniques, and oper. expo review 13,6-5 NEMA; UL 1.63; NEMA; maintenance data. PRA to thru 6-7 UL determine importance [2]
Failure to open or failure to close Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 2
RG 1.106,1.63; 317; RG 1.106, 4-20,4-NEMA; UL 1.63; NEMA; 21,5-1 UL thru 5-13 Inadvertent trip, failure to trip Occasional to IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 3
Frequent RG 1.106,1.63; 317; RG 1.106, 4-20,4-NEMA; UL 1.63; NEMA; 21, 5-1 UL thru 5-13 Open circuits Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6,
- 4 RG 1.106,1.63; 317; RG 1.106, 4-20,4-NEMA; UL 1.63; NEMA; 21,5-1 UL thru 5-13 Failure to open or failure to close Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 5
RG 1.106,1.63; 317; RG 1.106, 4-20,4-NEMA; UL 1.63; NEMA; 21,5-1 UL thru 5-13 Response on incorrect signal Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 6
RG 1.106,1.63; 317; RG 1.106, 4-20, 4~
NEMA; UL 1.63; NEMA; 21,5-1 UL thru 5-13 Open or short circuits Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 7
RG 1.106,1.63; 317; RG 1.106, 4-22,5-1 NEMA; UL 1.63; NEMA; thru 5-13 UL
Table A.2 Gall Report for NPAR Reports Page 25A Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers Reviewed by:
Jerry Edson, INEL Item S Str tu e/C S b M
. I system uc r omp u componen atefla s Manu acturer A RD h
mec anlsm ARD ff ts eec 8
Motor Control Cente r TERMINAL BLOCK Phenolic Not stated VIBR, WEAR Mechanical stresses 9
Motor Control Center Terminal Block Phenolic Not stated ELETEMP Conduction paths are formed 10 Motor Control Center Thermal Overloads Phenolic, silver Not stated ELETEMP, FAT Overheating plating, copper, vulcanized rubber 11 Motor Control Center Thermal Overloads Phenolic, silver Not stated CORR, CORR/PIT Surface degradation plating, copper, vulcanized rubber 12 Motor Control Center Thermal Overloads Phenolic, silver Not stated WEAR, CONTAM Out of calibration, plating, copper, sticking vulcanized rubber 13 Motor Control Center Starter/Contactor Lubricant, adhesive, Not stated FAT, CORR, Mech. stresses, neoprene, silicone, CORR/PIT, surface degradation, polyester, phenolic, CONTAM foreign substance rubber, silver alloy, coppper, stainless steel 14 Motor Control Cente Fuse Not stated Not stated Not stated Material degradation causes open circuits 15 Motor Control Center Coils Phenolic, fiberglass, Not stated CURSTR Overcurrent causes copper wire, teflon overheating and insulation breakdowr 16 Motor Control Center Trip and Control Not stated Not stated Not stated Drifting of setpoint, out of calibration 17 Motor Control Center Trip and Control Not stated Not stated CONTAM Degradation of contact surfaces, buildup of grease and dirt 18 Motor Control Cente Cabinets Steel Not stated Not stated Not stated Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
SOV-ASCO Coils Elastomers ASCO MOIST-EL, Decreased insulatior ELETEMP and coil resistance 2
SOV-ASCO Core Disc Buna-N, EPDM ASCO ELETEMP, RAD Hardening, decreased elongation 3
SOV-ASCO Seat Buna-N and nylon ASCO ELETEMP, RAD Hardening, metal and EP decreased elongation 4
SOV-ASCO Body O-Rings Buna-N, EPDM ASCO ELETEMP, RAD Hardening, decreased elongation
Table A.2 Gall Report fot NPAR Reports Page 258 Document: NUREG/CR-S053, Operating Experience and Aging Assessment of Motor Control Centers Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs R eport R d "
ecommen ations age o.
em P
N It Poor connection/open circuit Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 8
RG 1.106,1.63; 317; RG 1.106, 4-22,5-1 NEMA; UL 1.63; NEMA; thru 5-13 UL Ground/short Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 9
RG 1.106,1.63; 317; RG 1.106, 4-22,5-1 NEMA; UL 1.63; NEMA; thru 5-13 UL Open circuit Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 10 RG 1.106,1.63; 317; RG 1.106, 4-23,4-NEMA; UL 1.63; NEMA; 24,5-1 UL thru 5-13 Would not operate Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 11 RG 1.106,1.63; 317; RG 1.106, 4-23,4-NEMA; UL 1.63; NEMA; 24,5-1 UL thru 5-13 Tripped and response on incorrect signal Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 12 RG 1.106,1.63; 317; RG 1.106, 4-23,4-NEMA; UL 1.63; NEMA; 24,5-1 UL thru 5-13 Failure to open or close Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 13 RG 1.106,1.63; 317; RG 1.106, 4-23,4-NEMA; UL 1.63; NEMA; 24,5-1 UL thru 5-13 Premature operation Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 4-6,4-23, 14 RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5-NEMA; UL 1.63; NEMA; 13 UL Open circuit, short/ground Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,4-6, 15 RG 1.106,1.63; 317; RG 1.106, 4-24,5-1 NEMA; UL 1.63; NEMA; thru 5*13 UL Response on incorrect signal Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 4-6,4-24, 16 RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5-NEMA; UL 1.63; NEMA; 13 UL Sticking and material degradation result in Rare IEEE 308,279,317; IEEE 308, 279, Not stated 4-6,4-24, 17 faiure to operate RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5 NEMA; UL 1.63; NEMA; 13 UL Not stated Not stated IEEE 308,279,317; IEEE 308, 279, Not stated 3-4,5-1 18 RG 1.106,1.63; 317; RG 1.106, thru 5-13 NEMA; UL 1.63; NEMA; UL Document: NUREG/CR-S141, Aging and Qualification Research on Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL Eff t fA" C
F "b
F"I R
ed R I eco Iglng on omponent unction Contrl to 81 ure eport :progs el"lnogs R eport R d "
ecommen ations P
N It age o.
em Water enters during MSLBILOCA Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,9,28-1 conditions. Failure to operate report if EQ'd, plant 31,41-48, specific 75-78 programs Leakage Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,9,28-2 report if EQ'd, plant 31,73, specific 75-78 programs Leakage. Laquer like organic depOSits Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,9,28-3 surrounding the metal to metal seats report if EQ'd, plant 31,75-78 caused failure to transfer.
specific programs Failure to transfer Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,9,28-4 report if EQ'd, plant 31,74, specific 75-78 programs
Table A.2 Gall Report for NPAR Reports Page 26A Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL Item System Structure/Comp b
Su component Materials Manufacturer AR h
Cmec anlsm ARC ff e ects 5
SOV-ASCO Housings, Washers, Not stated ASCO Not stated Not stated Core Spring, Gaskets 6
SOV* VALCOR Coils Elastomers Valcor MOIST-EL, Decreased coil and ELETEMP insulation resistance 7
SOV-VALCOR Seats EPR Valcor ELETEMP, RAD Hardening and decreased elongation 8
SOV-VALCOR Shaft Seal O-Ring EPR Valcor ELETEMP, RAD Hardening and decreased elongation 9
SOV-VALCOR Upper Assembly EPR Valcor ELETEMP, RAD Hardening and Seal O-Ring decreased elongation 10 SOV-VALCOR Shaft,Cage, Ports Not stated Valcor Not stated Not stated Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARC mechanism ARC effects 1 1E Power General 2 1E Power Transformer General 3 1E Power Transformer Insulating Oil Mineral oil, systhetic Not stated MOIST-EL, Degraded insulation chlorinated aromatic ELETEMP value hydrocarbon 4 1E Power Transformer Core (Magnetic Copper, aluminum, Not stated FAT, ELETEMP Magnetic core Circuit and silicon steel, deformation Windings) cellulose, phenolics, fiberglass, varnish, epoxy 5 1E Power Transformer Core (Magnetic Copper, aluminum, Not stated ELETEMP, VISR, Arcing, hot spots, Circuit and silicon steel, MOIST-EL, winding insulation Windings) cellulose, phenolics, VOLSTR, CURSTR, degradation fiberglass, varnish, CORR/OX epoxy 6 1E Power Transformer Case (Tank)
Structural steel, Not stated FAT Failure of tank paints welds, moisture seal cracking 7 1E Power Transformer Insulating Gas Nitrogen, air, Not stated MOIST-EL Insulation flourocarbon breakdown 8 1E Power Transformer Core (Magnetic Copper, aluminum, Not stated FAT, ELETEMP Magnetic core Circuit and silicon steel, deformation Windings) cellulose, phenolics, figerglass, varnish, epoxy 9 1E Power Transformer Core (Magnetic Copper, aluminum, Not stated MOIST-EL, Arcing, hot spots, Circuit and silicon steel,
- ELETEMP, winding insulation Windings) cellulose, phenolics, CORR/OX, degradation figerglass, varnish, CURSTR, VISR, epoxy VOLSTR 10 1E Power Transformer Case (Tank)
Structural steel, Not stated FAT Failure of tank paint welds, moisture seal cracking
Table A.2 Gall Report for NPAR Reports Page 268 Document: NUREG/CR*5141, Aging and Qualification Research on Solenoid Operated Valves Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem Not stated Not stated Not discussed in 10 CFR 50.49 Not stated 9
5 report if EQ'd, plant specific programs Water enters during MSLBILOCA Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,11, 6
conditions. Failure to operate report if EQ'd, plant 20-28,41-specific 48,75-78 programs Not stated Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,11, 7
report if EQ'd, plant 20-28,41-specific 48,75-78 programs O-rings adhered to the guide tube -
Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,11, 8
caused sticking and failure to transfer report if EQ'd, plant 20-28,41-specific 48,73-78 programs O-rings adhered to seat - caused sticking Frequent Not discussed in 10 CFR 50.49 Not stated 6-7,11, 9
and failure to transfer report if EQ'd, plant 20-28,41-specific 48,73-78 programs Not stated Not stated Not discussed in 10 CFR 50.49 Not stated 11 10 report if EQ'd, plant specific programs Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated RG 1.118, IEEE-RG 1.108, Eval. surveillance & monitoring 49,51, 1
338, IEEE,943 1.118,1.129; practices. Determine which 54, 71 IEEE 338, 387, components contribute most to 450 system unavailability [4]
Not stated Representative plant Vendor specific Industry continue developing 66, 70 2
programs monitoring techniques. Transf. and surge suppressor aging studies should be performed [4J Reduction in dielectric strength resulting Not stated Not discussed in Vendor specific Not stated 20,21,22 3
in internal shorts and winding failures report programs Vibration and excessive temperature Not stated Not discussed in Vendor specific Not stated 20,21,22 4
cause the magnetic core circuit to report programs become deformed and loosen and can result in failure of the windings Winding-to-winding short circuit, winding-Not stated Not discussed in Vendor specific Not stated 20,21,22 5
to-case short circuit report programs Leakage, moisture instrusion resulting in Not stated Not discussed in Vendor specific Not stated 21,22 6
degradation of the insulating oil report programs Reduction in dielectric strength resulting Not stated Not discussed in Vendor specific Not stated 21,22 7
in internal shorts and winding failures report programs Deformation and loosening of the Not stated Not discussed in Vendor specific Not stated 21,22 8
magnetic core resulting in winding failures report programs Winding-to-winding short circuit, winding-Not stated Not discussed in Vendor specific Not stated 21,22 9
to-case short circuits report programs Moisuture intrusion and leakage of the Not stated Not discussed in Vendor specific Not stated 21,22 10 gas coolantlinsulation resulting in failure report programs of the winding insulation
Table A.2 Gall Report for NPAR Reports Page 27A Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 11 1E Power Cable Insulation XLPE, EPR, silicon Not stated ELETEMP, RAD, Embrittlement of or butyl rubber, MOIST-EL, insulation, treeing Kapton, PE, PVC, AGRCHEM teflon, CSP 12 1E Power Cable Jacket CSP Not stated ELETEMP, RAD, Embrittlement of MOIST-EL, insulation AGRCHEM 13 1E Power Connections and Not stated Not stated Not stated FAT Cracking Terminations 14 1E Power Electrical Cable Cable Clamp Stainless steel Not stated Not stated Not stated 15 1E Power Electrical Cable Terminal Strip Glass filled phenolic Not stated Not stated Not stated Assembly 16 1E Power Electrical Cable Shrink Tubing Polyolefin Not stated Not stated Not stated 17 1E Power Electrical Cable Plug Sleeve and Bronze Not stated Not stated Not stated Coupling Ring 18 1E Power Electrical Cable O-Ring Seal Elastomer Not stated Not stated Not stated 19 1E Power Electrical Cable Contact Socket Copper Not stated Not stated Not stated 20 1E Power Electrical Cable Interfacial Seal Dow Corning Not stated Not stated Cracking Sylgard 21 1E Power Electrical Cable Insulator, Plug Skirt Polysulfone Not stated Not stated CraCking 22 1E Power Electrical Cable Washer Stainless steel Not stated Not stated Not stated 23 1E Power Electrical Cable Module Assembly Brass Not stated Not stated Not stated 24 1E Power Circuit Breaker Insulation Polyester, glassfiber Not stated ELETEMP Reduced insulation filled epoxy resins, value phenolic 25 1E Power Circuit Breaker Contacts Silver alloy in copper Not stated CURSTR,VOLSTR Poor electrical base contact 26 1E Power Circuit Breaker Arc Chutes Not stated Not stated ELETEMP Structural damage to the arc chutes 27 1E Power Circuit Breaker Overload Not stated Not stated ELETEMP Reduced overload Mechanism rating 28 1E Power Circuit Breaker Connections Not stated Not stated VIBR Loose connections 29 1E Power Circuit Breaker Lubricant Not stated Not stated
- ELETEMP, Hardening of the
- AGRCHEM, lubricant CONTAM 30 1E Power Circuit Breaker Frame Painted or Not stated Not stated Not stated electroplated steel
Table A.2 Gall Report for NPAR Reports Page 278 Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Re.J!I'ogs R eport R ecommen d.
ations P age N lte
- o.
m Embrittlement results in cracking which Occasional Not discussed in No specific Not stated 22,23, 11 permits moisture to enter and result in report program 25,41 conductor-to-conductor and conductor-to-ground shorts. Treeing results in conductor-to-conductor and conductor-to-ground shorts Embrittlement results in cracking and Occasional Not discussed in No specific Not stated 22,23, 12 moisture instrusion report program 25,41 Not stated Not stated Not discussed in Plant specific Not stated.
23,24 13 report Iprogarms Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 22,25, 14 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 15 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 16 Vendor specific 49,56 I programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 17 Vendor specific 49,56 programs Pressure leak Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 18 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 19 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 20 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 21 Vendor specific 49,56 programs Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 22 Vendor specific 49,56 programs Notstated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 23 Vendor specific 49,56 programs Excessive temperature caused by poor Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 24 contact, large currents, or elevated report 741-1986 environment degrades the insulation Section 7, resulting in shorts and arcing vendor specific Degraded/poor contacts result in Not stated Not discussed in ANSIIIEEE Not stated 25,26,27 25 degraded or open circuits report 741-1986 Section 7, vendor specific Flashover/arcing, failure to extinguish the Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 26 arc report 741-1986 Section 7, vendor specific Premature trip at low current Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 27 report 741-1986 Section 7, vendor specific Improper operation and open circuits Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 28 report 741-1986 Section 7, vendor specific Improper operation, failure to open or Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 29 close report 741-1986 Section 7, vendor specific Not stated Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 30 report 741-1986 Section 7, vendor sDeclfic
Table A.2 Ga" Report for NPAR Reports Page 28A Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARC mechanism ARC effects 31 1E Power Circuit Breaker Housing, Doors Painted sheet steel Not stated Not stated Not stated 32 1E Power Circuit Breaker Mechanisms Cast bronze and Not stated CORR, AGRCHEM, Reduced force, steel, stamped steel WEAR, VISR, FAT, increased friction, CONTAM embrittled mat.
33 1E Power Relays Coil Insulation Not stated Not stated
- VOLSTR, Reduced insulation ELETEMP value 34 1E Power Relays Moving Parts Not stated Not stated WEAR, FAT Increased friction, binding 35 1E Power Relays Contacts Not stated Not stated WEAR, CORR, Poor electrical VIBR, CONTAM contact 36 1E Power Relays Connections Not stated Not stated VIBR, ELETEMP Loose or poor electrical connections 37 1E Power Relays Coil Bobbin Not stated Not stated ELETEMP Accelerate aging 38 1E Power Chargers and Circuit Breaker Not stated Not stated
- CONTAM, Increased friction, Inverters LOSLUB, WEAR, binding, loss of CORR/PIT continuity 39 1E Power Chargers and Fuse Not stated Not stated THERM-CY, FAT Metal fatigue, Inverters melling of link 40 1E Power Chargers and Relay Not stated Not stated CORR/PIT, Loss of continuity Inverters CORR/OX 41 1E Power Chargers and Electrolytic Not stated Not stated ELETEMP, VIBR Loss of electrolyte, Inverters Capacitors failure of leads 42 1E Power Chargers and Oil Filled Capacitors Not stated Not stated ELETEMP, VIBR Dielectric Inverters breakdown, failure 0 leads 43 1E Power Chargers and Magnetics Not stated Not stated ELETEMP, LOW Degraded insulation, Inverters (Transformer, TEMP, VOLSTR, cracked moisture Inductor)
VIBR seals, broken wires 44 1E Power Chargers and Silicon Controlled Not stated Not stated ELETEMP Over voltage or over Inverters Rectifiers current caused by transients 45 1E Power Chargers and Resistor Not stated Not stated VIBR, ELETEMP Decrease in Inverters resistance, lead fails 46 1E Power Chargers and Printed Circuit Not stated Not stated TEMP, THERM-CY, Cracking of circuit Inverters Boards CORR, VIBR lines, open circuits, loose connections
Table A.2 Gall Report for NPAR Reports Page 288 Document: NUREG/GR-5181. Nuclear Plant Aging Research: The 1 E Power System Reviewed by:
Jerry Edson.INEL Eft fA' R I ecto 19m9 on Component Function Contrib to Failure Reported progs e.progs R epor tR ecommen d.
ations P age N It
- o.
em Not stated Not stated Not discussed in ANSI/IEEE Not stated 25.26,27 31 report 741-1986 Section 7.
vendor specific Improper operation. failure to oper or Not stated Not discussed in ANSI/IEEE Not stated 25.26.27 32 close report 741-1986 Section 7.
vendor specific Excessive temperture from ohmic heating Not stated Not discussed in RG 1.118.
Not stated 25,26, 33 or the environment causes insulation report IEEE 338-1987 27.28 failure and results in failure of the relay to operate Misopertion. failure to operte. slow or Not stated Not discussed in RG 1.118.
Not stated 25,26.
34 sluggish operation, inadvertant contact report IEEE 338-1987 27.28 closure Open circuit. failure to close. arcing.
Not stated Not discussed in RG 1.118.
Not stated 25,26, 35 increased temperature due to ohmic report IEEE 338-1987 27.28 heating Open circuit heating at the socket/pin Not stated Not discussed in RG 1.118.
Not stated 25.26.
36 interlace report IEEE 338-1987 27.28 Coil failure Not stated Not discussed in RG 1.118.
Not stated 25.26.
37 report IEEE 338-1987 27.28 Failure to operate, failure to open Occasional IEEE-446. NEMA IEEE 446.
Not stated 29-36.55.
38 PE5. lEG 146-2.
NEMAPE5.
60-64 ANSI/IEEE-944 lEG 146-2.
Fails open (opens prematurely)
Occasional IEEE-446. NEMA IEEE 446.
Not stated 29-36.55, 39 PE5. lEG 146-2, NEMAPE5.
60-64 ANSI/IEEE-944 lEG 146-2.
Open circuit or coil, contacts open Occasional IEEE-446, NEMA IEEE 446.
Not stated 29-36,55.
40 PE5. lEG 146-2.
NEMA PE5.
60-64 ANSI/IEEE-944 lEG 146-2.
Loss of capacitance or open circuit Frequent IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 41 causes the chargerlinverter to have PE5. lEG 146-2, NEMAPE5.
60-64 improper output ANSI/IEEE-944 lEG 146-2.
Loss of capacitance or open circuit Frequent IEEE-446. NEMA IEEE 446.
Not stated 29-36.55.
42 causes the chargerlinverter to have PE5. lEG 146-2.
NEMAPE5.
60-64 improper output ANSI/IEEE-944 lEG 146-2.
ANSI/IEEE
Not stated 29-36.55, 43 to-tum or turn-to-ground) or change in PE5. lEG 146-2.
NEMA PE5, 60-64 inductance ANSI/IEEE-944 lEG 146-2.
ANSI/IEEE
- 944, Failure of device due to open or short Occasional IEEE-446. NEMA IEEE 446, Not stated 29-36.55.
44 circuits PE5, lEe 146-2.
NEMA PE5.
60-64 ANSI/IEEE-944 lEG 146-2.
Failure of device due to open circuit or Rare IEEE-446. NEMA IEEE 446.
Not stated 29-36,55.
45 change in value of resistor PE5. lEG 146-2.
NEMAPE5.
60-64 ANSI/IEEE-944 lEG 146-2.
Output changes from desired value Frequent IEEE-446. NEMA IEEE 446.
Not stated 29-36.55, 46 PE5. lEG 146-2.
NEMA PE5.
60-64 ANSIIIEEE-944 lEG 146-2.
Table A.2 Gall Report for NPAR Reports Page 29A Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1 E Power System Reviewed by:
Jerry Edson, INEL I
S e/C S b tern System tructur omp u comj)onent Materials Manu acturer A RD mechanism ARD ff e ects 47 1E Power Chargers and Surge Suppressor Not stated Not stated VOLSTR,CURSTR Semiconductor Inverters breakdown 48 1E Power Chargers and Connections Not stated Not stated MECHSTR Fatigue failure of Inverters wire at terminals 49 1E Power Chargers and Meters Not stated Not stated CONTAM Increase in bearing Inverters friction 50 1E Power Chargers and Switch Not stated Not stated CORR, CORR/PIT Loss of continuity Inverters across contacts 51 1E Power Chargers and Potentiometer Not stated Not stated ELETEMP Loss of continuity Inverters 52 1E Power Batteries Grids/Plates Lead-calcium alloy Not stated
- OVERCHG, Accelerates
- ELETEMP, corrosion and CONTAM oxidation 53 1E Power Batteries Active Material Lead dioxide and Not stated GAS Dislodges active lead sulfate material 54 1E Power Batteries Separator Rubber/glass matt Not stated ELETEMP Accelerates deterioration of electrical insulation 55 1E Power Batteries Electrolyte Sulfuric acid and Not stated CONTAM Hydrolysis of the water water and loss of electrolyte 56 1E Power Batteries Vent Fused alumina Not stated MECHSTR Vent breaks allowing contamination to enter 57 1E Power Batteries Top Connectors Lead-calcium alloy Not stated ELETEMP, CORR, Low electrolyte level EMBR causes corrosion and embrittlement 58 1E Power Batteries Terminals Lead-calcium alloy Not stated CORR/OX, CORR Poor electrical contact with external busses 59 1E Power Batteries Container and Top Polycarbonate, Not stated
- MECHSTR, Oxidation of lead Cover styrene acryolonitrile, CORR/OX causes plate growth acrylo-butadiene styrene Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Inverter Resistors Carbon conposition Not stated ELETEMP & MOIST Ohms decrease -
temperature, & ohm~
increase - moisture 2
Inverter Wire Not stated Not stated Not stated Turns contact
Table A.2 Gall Report for NPAR Reports Page 298 Document: NUREG/CR*5181, Nuclear Plant Aging Research: The 1 E Power System Reviewed by:
Jerry Edson, INEL Eff t fA*
F F *1 ed R I eco 'grng on Component unction Contrib to al ure Report progs e.progs R
rtR epo ecommen d ti a ons P
N lte age o.
m Semiconductor breakdown due to Rare IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 47 overheating causes short circuits and PE5, IEC 146-2,
- NEMAPE5, 60-64 improper output ANSI/IEEE-944 IEC 146-2, ANSI/IEEE
- 944, Improper output due to open or short Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 48 circuits PE5, IEC 146-2, NEMA PE5, 60-64 ANSI/IEEE-944 IEC 146-2, ANSI/IEEE
- 944, Improper indication Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 49 PE5, IEC 146-2,
- NEMAPE5, 60-64 ANSIIIEEE-944 IEC 146-2, ANSI/IEEE 944 Improper output due to switch failing open Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 50 or closed PE5, IEC 146-2, NEMA PE5, 60-64 ANSI/IEEE-944 IEC 146-2, ANSI/IEEE 944 Improper output due to open or short Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36,55, 51 circuit PE5, IEC 146-2, NEMA PE5, 60-64 ANSI/IEEE-944 IEC 146-2, ANSIIIEEE 944 Corrosion/oxidation causes plate growth Frequent RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 52 resulting in reduced capacity and stresses IEEE 450-36,37, the container 1987, Tech 38,50, Spec Surveil.
54,62-65 Dislodging active material from the plates Not stated RG 1.129,IEEE-450 RG1.129, Not stated 30,31, 53 causes loss of capacity IEEE 450-36,37, 1987, Tech 38,50, Spec Surveil.
54,62-65 Loss of electriCal insulation between Not stated RG 1.129,IEEE-450 RG 1.129, Not stated 30,31, 54 plates causes short circuits and loss of IEEE 450-36,37, capacity 1987, Tech 38,50, Spec Surveil.
54,62-65 Loss of electrolyte results in loss of Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 55 capacity IEEE 450-36,37, 1987, Tech 38,50, Spec Surveil.
54,62-65 Contaminates in the electrolyte result in Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 56 reduced capacity IEEE 450-36,37, 1987, Tech 38,50, Spec Surveil.
54,62-65 Embrittled top conductors are susceptible Frequent RG 1.129,IEEE-450 RG 1.129, Not stated 30,31, 57 to breaking and causes loss of capacity IEEE 450-36,37, 1987, Tech 38,50, Spec Surveil.
54,62-65 Poor electrical contact results in loss of Not stated RG 1.129, IEEE-450 RG1.129, Not stated 30,31, 58 capacity and may result in total battery IEEE 450-36,37, failure 1987, Tech 38,50, Spec Surveil.
54,62-65 Plate growth and handling stresses Frequent RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 59 results in cracked containers which allow IEEE 450-36,37, electrolyte to escape resulting in reduced 1987, Tech 38,50, capacity or total failure Spec Surveil.
54,62-65 Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei.progs Report Recommendations Page No. Item Resistance change causes improper Not stated Not discussed in Vendor Individual fusing of filter capaCitors 3-23 1
output.
report specific, Tech. to preclude a capacitor failure in the Spec., IEEE short circuit mode [2]
446, NEMA When turns of wire in resisor make Not stated Not discussed in Vendor Not stated 3-23 2
contact it decreases total resistance of report specific, Tech.
resistor resulting in improper output.
Table A.2 Gall Report for NPAR Reports Page 30A Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger Reviewed by:
L. C. Meyer, INEL It S
t Str tu e/C S b M
. I M
f tu em sys em uc r omp u componen aterla s anu ac rer ARD h
mec amsm ARD ff ts eec 3
Inverter Electrolytic Not stated Not stated Not stated Capacitance Capacitors decreases with age 4
Inverter Ceramic Capacitor Not stated Not stated Not stated Unstable capacitance value 5
Inverter Silicon Controlled Silicon Not stated ELETEMP Deterioration of the Rectifiers thermal joint compound 6
Inverter Various Electrical Not stated Not stated Not stated No aging effects Components noted for 12 year old equipment 7
Battery Various Electrical Not stated Not stated Not stated No aging effects Components noted for 12 year old equipment Document: NUREG/CR-5280 V1, Age-Related Degradation of Westinghouse 48o-Volt Circuit Breakers Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
DS-206/0S-416 Power Operated Spring steel Westinghouse WEAR, LOSLUB, Wear out, loss of Circuit Breakers Mechanisms CORR/UA material, friction, &
corr product buildup 2
DS-206/0S-416 Contacts Contacts mounted Westinghouse WEAR, CURSTR, & Wear from Circuit Breakers on high strenght CORR/UA operation, pitting, &
insulating base and erosion from arcs steel arm 3
OS-206/0S-416 Arc Chutes Steel and arc Westinghouse WEAR, & CURSTR Erosion & burned Circuit Breakers resisting plastic splitter plates plates 4
OS-206/0S-416 Amptector Trip Unit Not stated Westinghouse VIB, CURSTR, &
Loose parts, Circuit Breakers (Electronic VOLSTR component burn out Components) or degraded operation 5
OS-206/OS-416 Current Magnitude Current transformers Westinghouse CURSTR, &
Dielectric properties Circuit Breakers and Direction VOLSTR degraded from Sensors electrical stresses 6
OS-206/0S-416 Optional Electro-mechanical Westinghouse VIB, CURSTR, &
Not stated Circuit Breakers Accessories devices, switch, and VOLSTR solid state device 7
OS-206/0S-416 Electrical and Not stated Westinghouse VIB, CURSTR, Coil burnings, Circuit Breakers Mechanical VOLSTR, LOSLUB, binding of linkage, Components in
& WEAR wear, overheating, &
General dust Document: NUREG/CR-5280 V2, Age-Related Oegradation of Westinghouse 48o-Volt Circuit Breakers (Mechanical Cycling)
Reviewed by:
L. C. Meyer, INEL I
S Str tu e/C S b t
M
- I tern system uc r omp u componen aterlas Manufacturer ARD mechanism ARD effects 1
OS-416 Breaker/480 Structural Steel Westinghouse VIB& CORR Vibration will loosen V
Components
. parts, corrosion degrades metals 2
OS-416 Breaker/480 Contact Assembly Insulating material Westinghouse WEAR & CURSTR Wear & loss of V
and stainless steel material from arcing.
Table A.2 Gall Report for NPAR Reports Page 30B Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Distortion of signals to SCRs may result Not stated Not discussed in Vendor Not stated 3-23 3
in improper putput.
report specific, Tech.
Spec., IEEE 446, NEMA Not stated Not stated Not discussed in Vendor Not stated 3-23 4
report specific, Tech.
Spec., IEEE 446, NEMA Over heating of SCRs may result in SCR Not stated Not discussed in Vendor Not stated 4-1 5
failure and loss of output.
report specific, Tech.
Spec., IEEE 446, NEMA None Not stated Not discussed in Vendor Not stated 4-3 6
report specific, Tech.
Not stated Not discussed in Vendor specific Not stated 3-1,4-1, 7
report progarm, Tech.
&4-3 Spec. Surveil.
Document: NUREG/CR-5280 Vl, Age-Related Degradation of Westinghouse 48Q-Volt Circuit Breakers Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Excessive force or rubbing causes Occasional Not discussed in Vendor specific Twelve recommendations given 2-7,6-2, 1
distortion & wear out, rust on pivotal parts report
, IEEE 741-relating to three separate issues
&7-4
& trip gears can cause hang up, hardened 1986 Section 7 covering reliability, pole shaft welds, or improper lubricants or lubricant and maintenance. [2]
application can cause sluggish operation.
Contacts wear from repeated operations, Occasional Maintenance per Vendor specific Filing or dressing with abrasive cloth 2-9,6-2, 2
arcing causes pitting, contacts become owner's group MPM,IEEE 741-is not recommended [2]
&7-6 mottled, dirty, and eroded due to arc WORGTSDS416 1986 Section 7 buming. Contacts over heat from resistance due to weak springs.
Slots in arc chute gradually erode with arc Frequent Maintenance per Vendor specific Ufe of the DS-16 breaker should be 2-9,6-3, 3
interruptions, fault currents cause heavy owner's group MPM, IEEE 741-5000 cycles or 20 years. [2]
& 7-6 erosion, and throat of the arc chute WORGTSDS416 1986 Section 7 enclosure becomes bumed and coated with soot from arc interruptions.
Vibration may loosen parts, voltage and Occasional Maintenance per Vendor specific Ufe of the DS-16 breaker should be 2-9,6-3, 4
current stress may cause part bum out or owner's group MPM,IEEE741-5000 cycles or 20 years. [2]
&7-6 insulation damage. Electrical stress WORGTSDS416 1986 Section 7 reduces dielectric properties Not stated Not stated Maintenance per Vendor specific Not stated 2-12 5
owner's.group MPM, IEEE 741-WORGTSDS416 1986 Section 7 Not stated Not stated Maintenance per Vendor specific Not stated 2-12 & 2-6 owner's group MPM, IEEE 741-13 WORGTSDS416 1986 Section 7 Most breaker problems result from control Occasional Owner's group Vendor specific Twelve recommendations given 2-1,7-1, 7
problems involving contacts, coil recommended
, IEEE 741-related to reliability, weld failures,
&7-4.
bumings, and trip device bindings, maintenance 1986 Section 7 and maintenance [2]
followed by operating mechanism problems. Loss of lubrication, erosion of contacts, burning of arc chutes, & loss of adjustment are from aging Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 48Q-Volt Circuit Breakers (Mechanical Cycling)
Reviewed by:
L. C. Meyer, INEL Eff t fA' C
'b F*I R
ed R I R
eco 'gmg on omponent Function Contrl to al ure eport progs el.progs Report ecommendations Page N o. Item Failure to operate Rare Not discussed in Vendor specific Not stated 3-2&6-2 1
report
, IEEE 741-1986 Section 7 Unreliable contact Not stated Not discussed in Vendor specific Not stated 3-2 & 6-2 2
report
, IEEE 741-1986 Section 7
Table A.2 Gall Report for NPAR Reports Page 31A Document: NUREG/CR*5280 V2, Age-Related Degradation of Westinghouse 48o-Volt Circuit Breakers (Mechanical Cycling)
Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent M aterials Manu acturer h
ARD mec an ism ARD ff ts eec 3
DS-416 Breaker/480 Power Operated Steel Westinghouse WEAR, FAT, & EX Wear, fracture, and V
Mechanism FORCE distortion.
4 DS-416 Breaker/480 Pole Shaft Steel Westinghouse FAT, & EX FORCE
- Cracking, V
misalignment &
binding due to poor welds 5
DS-416 Breaker/480 Charging System Steel, carbon brush Westinghouse WEAR, FAT, &
Wear on moving V
(Rachet, Motor, in motor, insulation CURSTR parts & electric Brushes, Oscillator., varnish on motor motor burn out Spring) windings 6
DS-416 Breaker/480 Electrical Coils Not stated Westinghouse CURSTR Extended duration of V
(UVTA. STA, AND current flow caused Closing Coil) burn out 7
DS-416 Breaker/480 Sensors, Amptector Not stated Westinghouse Not stated Extended V
Trip Unit, & Arc energization of coils.
Chutes DocLlment: NUREG/CR-5334, Severe Accident Testing of Electrical Penetration Assemblies Reviewed by:
L. C. Meyer, INEL Item S S
e/C Sb Mt*1 M
ftu system tructur omp u componen a erlas anu ac rer ARD h
mec amsm ARD ff ts eec 1
D. G. O'Brien SEALS Silicon O-ring D. G. O'Brien ELETEMP, MOIST-Seal cracks and Electrical EL, AND RAD moisture intrusion.
D. G. O'Brien Electrical Not stated Not stated ELETEMP, MOIST-Moisture or Electrical Components (Wire, EL, AND RAD contaminants Penetration Insulation, and caused electrical Connectors) shorts to ground 3
Westinghouse Seals Silcion O-ring Westinghouse ELETEMP, MOIST-Seal cracks and Electrical EL, AND RAD moisture intrusion Penetration 4
Westinghouse Electrical Not stated Westinghouse ELETEMP, MOIST-Insulation Electrical Components (Wire, EL, AND RAD degradation Penetration Insulation, and Connectors) 5 CONAX Electrical Seals Viton O-rings Conax ELETEMP, MOIST-Seal cracks and Penetration EL, AND RAD moisture intrusion 6
CONAX Electrical Electrical Not stated Conax THERM, MOIST-Embrittlement and Penetration Components (Wire, EL,AND RAD cracking Insulation, and Connectors)
Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials*
Manufacturer ARD mechanism ARD effects 1
Pressure Diaphragm Not stated Not stated VIBR FAT PRESS Deformation, Transmitter cracking, and hysteresis of diaphragm 2
Pressure Mechanical Unkages Not stated Not stated PRESS CORR Changes in system Transmitter CORR/OX restoration ability 3
Pressure Seals Not stated Not stated EMBR Moisture on Transmitter electronics Electronics
Table A.2 Gall Report for NPAR Reports Page 318 Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 48o-Volt Circuit Breakers (Mechanical Cycling)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations P
N lte age o.
m Aging degradation in parts between the Occasional Not discussed in Vendor specific Monthly inspection and every 50 to 6-2 & 6-5 3
motor and the poles redistributes the force report
,IEEE741-100 cycles inspect parts vulnerable transmitted from the charging motor 1986 Section 7 to aging, maintenance & lubrication causing large unbalanced stresses in at 250 cycles [2]
subcomponents & wear Once cracks grow to a quarter the size of Not stated Not discussed in Vendor specific Monthly inspection and every 50 to 6-2& 6-5 4
an effective weld the fIVe levers report
,IEEE 741-100 cycles inspect parts vulnerable connecting the pole contacts become 1986 Section 7 to aging, maintenance & lubrication misaligned and caused excesssive at 250 cycles [2]
movement leading to fracture, binding and other problems.
Wear of ratchet wheel, holding pauls, Not stated Not discussed in Vendor specific Assure design adequacy by 6-2,6-4 5
motor crank, and handle dominated the report
, IEEE 741-inspection,enhancedinspections aging of the charging system. Carbon 1986 Section 7 and maintenance & install cycle brushes needed frequent maintenance.
counter. [2]
Sluggish operation, binding, failure to Freqwhen Not discussed in Vendor specific Assure design adequacy by 4-18 6
operate.
mechanism binding report
,IEEE 741-inspection,enhancedinspections 1986 Section 7 and maintenance & install cycle counter. [2]
Not stated Not stated Not discussed in Vendor specific Not stated 3-2 7
report
, IEEE 741-1986 Section 7 Document: NUREG/CR-5334, Severe Accident Testing of Electrical Penetration Assemblies Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Cracks in the seals from high temperature Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 4-1,4-16, 1
and radiation allows moisture to leak into IEEE 323-1974 vendor specific leak potential is highly dependent on and 7-1 penetration resulting in electrical faults.
DESIGNSTD the temperatures to which the EPA is subject [2]
Short to ground and electrical faults due Not stated IEEE 317-1976 AND 10 CFR 50.49, Not stated C-1,4-16, 2
to moisture intrusion.
IEEE 323-1974 vendor specific and 7-1 DESIGN STD Seal cracks allow moisture intrusion into Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 1-3,5-1, 3
penetration resulting in electrical faults.
IEEE 323-1974 vendor specific leak potential is highly dependent on 5-15, and DESIGN STD the temperatures to which the EPA 7-1 is subject. [2]
Decreased insulation resistance results in Rare IEEE 317-1976 AND 10 CFR 50.49, Not stated 4-1, 4-16, 4
excessive leakage currents.
IEEE 323-1974 vendor specific and 7-1 DESIGN STD Seal cracks allow moisture intrusion Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 6-1,6-13, 5
resulting in electrical faults.
IEEE 323-1974 vendor specific leak potential is highly dependent on and 7-1 DESIGN STD the temperatures to which the EPA is subject. [2]
Electrical faults due to moisture intrusion Occasional IEEE 317-1976 AND 10 CFR 50.49, Look at types of cables and 6-1,6-13, 6
through connectors.
IEEE 323-1974 vendor specific connectors rather than penetration and 7-1 DESIGN STD design to improve future electrical penetrations. [2]
Document: NUREG/CR-S383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Response time degradation for pressure Not stated RG 1.118, IEEE RG 1.118, Revise RG and standards to take 23,115 1
transmitter 338, & ISA Standard IEEE 338, into account recent advances in 67.06 Tech Spec testing technology and other surveillance available information. [2]
Response time degradation for pressure Not stated RG 1.118, IEEE RG 1.118, Revise RG and standards to take 23,115 2
transmitter 338, & ISA Standard IEEE 338, into account recent advances in 67.06 Tech Spec testing technology and other surveillance available information. [2]
Response time degradation for pressure Not stated RG 1.118, IEEE RG 1.118, Revise RG and standards to take 23, 115 3
transmitter 338, & ISA Standard IEEE 338,10 into account recent advances in 67.06 CFR 50.49, testing technology and other Tech Specs available information. [2]
Table A.2 Gall Report for NPAR Reports Page 32A Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors Reviewed by:
E. W. Roberts, INEL Item System Structure/Com p Subcoml!onent Materials Manufacturer ARD mechanism ff ARDe ects 4
Pressure Electronic Not stated Not stated ELETEMP RAD Changes in value of Transmitter Components MOIST-EL electronic Electronics components Document: NUREG/CR-5448, AGING EVALUATION OF CLASS 1E BATIERIES: SEISMIC TESTING Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Batteries Not stated Not stated SEISMIC Plate movement or breakup Document: NUREG/CR-5461, Aging of cables, Connections, and Electrical Penetration Assemblies Used in Nuclear Power Plants Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp b
Su comp_onent Materials Manufacturer ARD mechanism ff ARDe ects 1
cable Insulation EPR, CSPE, EPDM, Ten manufactures MOIST-EL, Insulation XLPE, silicon listed ELETEMP, AND degradation, short rubber, butyl rubber, RAD and open circuits polyethylene, and 13 others used less often 2
cable Jacket Neoprene, hypalon, Ten manufactures MOIST-EL, Jacket degradation, XLPO, CSPE, &
listed ELETEMP, AND cracks, and
- CPE, RAD discoloration 3
Connections Terminal Blocks Phenolic with glass Seven listed ELETEMP, RAD, &
Loose connections, or cellulose filler with VIB cracks and short metal terminals circuits 4
Connections Splices Crimp type ring lugs, Raychem ELETEMP, VIB, Loose connections copper conductor, AND RAD and loss of dielectric nylon or kynar isolation insulation, and Raychem heat shrink tubing 5
Connections Coax Connectors Metal with organic Not stated ELETEMPAND Insulation insulation such as RAD degradation teflon 6
Electrical Seal Material Steel tubes, seal Conax, O'Brien, and ELTEMP& RAD Seal leaks and Penetrations materials are Westinghouse cracking polysulfone, metaJ-glass, and epoxy 7
Electrical Electrical Wire or Insulations (XLPE, Ten manufacturers ELETEMPAND Change in dieletric Penetrations cable EPR, EPDM &
listed RAD properties, Polymide) and embrittlement, and jacket(CSPE, SPE, cracking Hypalon, FR, and fiberglass)
Document: NUREG/CR-5546, An Investigation of The Effects of Thermal Aging on the Fire Damageability of Electric Cables Reviewed by:
L. C. Meyer, INEL Item St S
tue/C Sb M'I
- iysem truc r omp u componen aterlas Manufacturer ARD mechanism ARD effects 1
Electrical Cables Insulation XPE, and interstitial Rockbestos ELETEMP Not stated material (Nylon &
paper) 2 Electrical Cables Jacket Neoprene Rockbestos ELETEMP Embrittlement and cracking 3
Electrical Cables Insulation EPR, and interstitial Boston Insulated ELETEMP Not stated material (Nylon &
Wire paper) 4 Electrical cables Jacket Hypalon Boston Insulated ELETEMP Embrittlement, Wire dielectric loss and forms cracks
Table A.2 Gall Report for NPAR Reports Page 328 Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Response time degradation for pressure Not stated RG 1.118,IEEE RG 1.118, Revise RG and standards to take 23,115 4
transmitter 338, & ISA Standard IEEE 338, into account recent advances in 67.06 Tech Spec testing technology and other surveillance available information. [2]
Document: NUREG/CR-5448, AGING EVALUATION OF CLASS 1E BATTERIES: SEISMIC TESTING Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item No effect on bat capability if maintained to Not stated IEEE STD 450, RG RG 1.129, Batteries not maintained per IEEE 35 1
IEEE Std 450, RG 1.1.29 and MFG 1.129, & Mfg IEEE 450-450, RG1.129, & MFG rec. need recommendations recommendations 1987, Tech adv.monitoring tech. to determine Spec Surveil.
seismic capability. [2]
Document: NUREG/CR-5461, Aging of Cables, Connections, and Electricai Penetration Assemblies Used in Nuclear Power Plants Reviewed by:
L. C. Meyer, INEL
- 1 Effect of Aging on Coml'onent Function Contrib to Fal ure Reported progs Rel.progs R eport Recommen d.
ations P age o.
em N
It Thermal and radiation effects cause Not stated EQDB, IEEE 323-No specific Not stated 8,24,&
1 insulation degradation leading to cracking 1974 & IEEE 383-program 40 which allows moisture to intrude and then 1974 testing shorts or current leakage results.
Jacketlinsulation interaction effect was also noted.
Thermal and radiation effects cause Not stated EQDB, IEEE 323-No specific Not stated 8,24,&
2 jacket material degradation leading to 1974 & IEEE 383-program 40 cracking which allows moisture to intrude 1974 testing into the insulation, jacketlinsulation interaction effect was also noted in the sandia report.
Loss of dielectric isolation or loose Not stated Not discussed in Plant specific Not stated 11,27, &
3 connections to disrupt a circuit, leakage report programs 41 paths through moisture films, and insulation resistance decrease in presents of steam.
Insulaton vulnerable to aging, loss of Not stated Not discussed in 10 CFR 50.49 Not stated 11,27,&
4 dielectric isolation sufficient to disrupt a report 42 circuit or loose connections Decreased insulation resistance results in Not stated Not discussed in Plant specific Not stated 27 5
excesive leakage current.
report programs Seal cracks and leaks result in moisture Not stated Not discussed in 10 CFR 50.49, Not stated 14,28,&
6 intrusion and electrical faults.
report vendor specific 42 program Insulation degradation and jacket cracking Not stated Not discussed in 10 CFR 50.49, Not stated 14,28,&
7 leading to short or open circuits and report vendor specific 42 degraded signals.
program Document: NUREG/CR-5546, An Investigation of The Effects of Thermal Aging on the Fire Damageability of Electric Cables Reviewed by:
L. C. Meyer, INEL Eff t fA*
C t F ti C
- b F*I R
ed ec 0
~glng on omponen unc on ontrl to al ure eport progs Rel~rogs Report Recommendations Page No. Item None Not stated Not discussed in No specific Not stated 10,13, 1
report program and 32 Failure to protect conductors and Not stated Not discussed in No specific Not stated 21,24, 2
insulation.
report program and 32 Reduced the thermal damage threshold.
Not stated Not discussed in No specific Not stated 21,24, 3
report program and 32 Reduced thermal damage threshold.
Not stated Not discussed in No specific Not stated 21,24, 4
report program and 32
Table A.2 Gall Report for NPAR Reports Page 33A Document: NUREG/CR-5560, Aging of Nuclear Plant Resistance Temperature Detectors Reviewed by:
L. C. Meyer, INEL Item S system Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Resistance Seal Not stated Five Companies ELETEMP, MOIST-Dry out, shrink, &
Temperature Usted EL, VIB, & THERM-crack Detector (RTD)
CY 2
Resistance Insulation MgO Five Companies MOIST-EL Moisture degrades Temperature Usted insulation Detector (RTD) 3 Resistance Sensing Element Platinum Five Companies ELETEMP, MOIST-Noisy, cal shift, &
Temperature Usted EL, VIB, & THERM-degraded element Detector (RTD)
CY 4
Resistance Sheath Stainless steel Five Companies ELETEMP, VIB, &
Not stated Temperature Usted THERM-CY Detector (RTD)
Document: NUREG/CR-5619, The Impact of Thermal Aging on the Flammability of Electric Cables Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp SubcomJl_onent Materials Manufacturer ARD mechanism ARDeffects 1
Electric Cables Neoprene jacket, Rockbestos ELETEMP Not stated cross-linked polyethylene (XP E) insulated 2
Electric Cables Hypalon jacket, Boston Insulated ELETEMP Not stated ethylene-propylene Wire rubber (EPR) insulated Document: NUREG/CR-5643, Insights Gained From Aging Research Reviewed by:
Jerry Edson, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Electrical Components Document: NUREG/CR-5655, Submergence and High Temperature Steam Testing of Class 1E Electrical Cables Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent M aterlals Manufacturer ARD mechanism ARDeffects 1
Electrical Cable EPR, XLPO, 12Mfg ELETEMP RAD Insulation failure silicone, kapton, MOIST-EL kerite, coaxial 2
Electrical Cable EPR,XLPO, 12 Mfg ELETEMP RAD Some insulation silicone, kapton, MOIST-EL failure kerite, coaxial 3
Electrical Cable EPR, XLPO, 12 Mfg ELETEMP RAD Some insulation silicone, kapton, MOIST-EL failure kerite, coaxial Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components
. Reviewed by:
E. W. Roberts, INEL Item S},stem Structure/Comp Subcom~onent Materials Manufacturer ARD mechanism ARD effects 1
Instrumentation Indicator Not stated Not stated ELETEMP VIBR Indicator failure System
Table A.2 Gall Report for NPAR Reports Page 338 Document: NUREG/CR-5560, Aging of Nuclear Plant Resistance Temperature Detectors Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations age o.
em P
N It Seal may dry out, shrink, or crack allowing Occasional Not discussed in IEEE 338-Not stated 25, &27 1
moisure intrusion and degraded report 1987, RG performance of RTD.
1.118,ISA 67.06, Tech Spec Moisure intrusion from a leaking seal will Occasional Not discussed in IEEE 338-Not stated 28 2
degrade the insulation.
report 1987, RG 1.118,ISA 67.06, Tech Spec Long term high temp exposure affects Occasional Not discussed in IEEE 338-Calibrate RTDs and perform 28,167, 3
material properties, vibration may cause report 1987, RG response time tests prior to 180,and response time degradation, and therm-cy 1.118,ISA installation in a plant. [2]
A8 can cause calibration shift.
67.06, Tech Spec Sheath not normally effected by aging Rare Not discussed in IEEE 338-Not stated 15,25 &
4 during qualified life of RTD.
report 1987, RG 27 1.118,ISA 67.06, Tech Spec Document: NUREG/CR-5619, The Impact of Thermal Aging on the Flammability of Electric Cables Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations P
N
~ge o. tem Reduction in flammability Not stated Not discussed in No specific No further investigation needed 21 1
report program Reduction in flammability Not stated Not discussed in No specific No further investigation needed 21 2
report.
program Document: NUREG/CR-5643, Insights Gained From Aging Research Reviewed by:
Jerry Edson, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item For electrical components, this report.
Not stated Not discussed in Component Not stated 1
contains information identical to that in report specific other NPAR reports. See the following programs NUREG/CR reports: 4457, 5448, 4564, 5051,5192,5461,5655,4156,4939, 4234 v1 &v2, 5141, 4819 v1 & v2, 5181, 4747v1, 4967, 4740 Document: NUREG/CR-5655, Submergence and High Temperature Steam Testing of Class 1 E Electrical Cables Reviewed by:
E. W. Roberts, INEL Eff f A 0
C F
F II R
ed R
R R
ecto Iglng on omponent unction Contrlb to a ure eport progs el.progs eport ecommen d.
ations age 00 em P
N It Not stated Not stated IEEE 383 No specific Not stated 2,35 1
program Not stated Not stated IEEE 383 No specific Not stated 2,35 2
program Not stated Not stated IEEE 383 No specific Not stated 2,35 3
program Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components Reviewed by:
E. W. Roberts, INEL Eff t fA*
C t F C
tr°b t F 01 R
ed R I R
rt R eco Iglng on omponen unction on I 0
al ure eport progs e.progs epo d
0 ecommen ations P
N lte age o.
m Not stated Frequent Not discussed in RG 1.118, Develop methods to prevent infant 11,24,38 1
report IEEE 338-mortality. Testing for synergistic
,65 1987,ISA effects of aging. Develop industry 67.06, Tech wide data base [2]
Spec
Table A.2 Gall Report for NPAR Reports Page 34A Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components Reviewed by:
E. W. Roberts, INEL I
S e/
S b t
M t. I M
f t
ARD tern System tructur Comp u componen a erlas anu ac urer h
mec amsm ARD ff ts eec 2
Instrumentation Sensor Not stated Not stated ELETEMP VIBR Sensor failure, System PRESS-CY MOIST-response time EL degradation, drift 3
Instrumentation Controller Not stated Not stated ELETEMP VIBR Failure, response System MOIST-EL time degradation, drift 4
Instrumentation Controller Not stated Not stated ELETEMP VIBR Calibration shift System MOIST-EL slow responce time 5
Instrumentation Annunciators Not stated Not stated ELETEMP VIBR Visual unit failure System MOIST-EL sound alarm failure 6
Instrumentation Recorders Not stated Not stated ELETEMP VIBR Failure to record System MOIST-EL Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Protective Relay -
Not stated General Electric Not stated Oxidation on 10, 13, & 24 Years contacts, increased Old(GE) operating temperatures 2
Control Relay Not stated Klockner Moeller Not stated None 3
Control Relay - 2 &
Not stated Struthers Dunn Not stated Slight discoloration 12 Years Old of armature and contact conn. fingers 4
Control Relay Not stated Westinghouse Not stated None 5
Electronic Relay Not stated Blaser Electric Not stated Not stated 6
Auxilliary Relay Not stated General Electric Not stated Worn contacts and dust inside case 7
Auxilliary Relay Not stated Westinghouse Not stated Contact worn, discolored and pitted with age 8
Timing Relay Not stated Agastat Not stated Increased pickup voltage and op.
temp. with age 9
Molded Case Circuit Not stated Square D Not stated None - 6 year old Breakers 10 Molded Case Circuit Not stated Westinghouse Not stated None - 18 & 30 year Breakers old 11 Molded Case Circuit Not stated Klockner Moeller Not stated Overheating Breakers (discoloration) of case & spliting of tubing 12 Molded Case Circuit Not stated ITE Not stated Overheatingldistorati Breakers on/damage to thermal element &
trip mec
Table A.2 Gall Report for NPAR Reports Page 348 Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 2
report IEEE 338-mortality. Testing for synergistic
,41,65 1987,ISA effects of aging. Develop industry 67.06, Tech wide data base [2]
Spec Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 3
report IEEE 338*
mortality. Testing for synergistic
,43,65 1987,ISA effects of aging. Develop industry 67.06 wide data base j2]
Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 4
report IEEE 338-mortality. Testing for synergistic
,47,65 1987,ISA effects of aging. Develop industry 67.06, Tech wide data base [2]
Spec Not stated Frequent Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 5
report IEEE 338-mortality. Testing for synergistic
,48,65 1987,ISA effects of aging. Develop industry 67.06 wide data base [2]
Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 6
report IEEE 338-mortality. Testing for synergistic
,48,65 1987,ISA effects of aging. Develop industry 67.06, Tech wide data base [2]
Spec Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item Higher contact resistance, differences in Frequent Yes - not specifically IEEE 741-1986 Modify current practices to include 3-1 & 7-3 1
induction pickup, significant variation in identified Section 7 the addition of infrared temperature time/current charateristic.
measurement With cover off and relay energized. [2]
None NONE Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7-2 identified Section 7 the addition of infrared temperature 3
and vibration measurements. [2]
Contact resistance increased with age Rare Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7-3 identified Section 7 the addition of infrared temperature 3
and vibration measurements. [2]
None Not stated Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7-4 identified Section 7 the addition of infrared temperature 3
and vibration measurements. [2]
Not stated Not stated Yes - not specifically IEEE 741-1986 Not stated 3-32 & 7-5 identified Section 7 3
Pickup voltage exceeded acceptance Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-36 & 7-6 criteria identified Section 7 measurement and vibration testing to 3
. current plant practices. [2]
Increased contact resistance Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-36& 7-7 identified Section 7 measurement and vibration testing tc 3 current plant practices. [2]
Timing accuracy not within typical Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-52& 7-8 required accuracy identified Section 7 measurement, inrush current and 3
vibration testing to current plant practices. [2]
None Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65& 7-9 identified Section 7 measurement and vibration testing tc 3 current plant practices. modify instantaneous trip test. [2]
Exceeded typical accept. criteria for Rare Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7-10 instantaneous trip (125%) time.
identified Section 7 measurement and vibration testing tc 3 current plant practices. modify instantaneous trip test. [2]
300% overcurrent trip delay exceeded Occasional Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7-11 acceptance criteria.
identified Section 7 measurement and vibration testing tc 3 Damagedlmisa/igigned trip pin caused current plant practices. modify overheating and failure to perform instantaneous trip test. [2]
instantaneous trip when required.
Instantaeous trip inoperable/out of Frequent Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7-12 tolerance on 2 phases. 300% overcurrent identified Section 7 measurement and vibration testing tc 3 trip does not meet acceptance ctiteria.
current plant practices. modify Instantaneous triP test. [2]
Table A.2 Gall Report for NPAR Reports Page 35A Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays Reviewed by:
E. W. Roberts, INEL Item System Structure/Com p Subcomponent Materials Manufacturer ARD mechanism ARDeffects 13 Metal Clad Circuit Not stated Westinghouse Not stated Main/arcing contacts Breakers pitted, insulation.
split, damaged parts 14 Metal Clad Circuit General Electric Not stated Back connections Breakers oxidized. binding of dash pot Document: NUREG/CR-5772 V1, Aging, Condition Monitoring, and Loss-ot-Coolant Accident (LOCA) Tests of Class 1E Electrical Cables Reviewed by:
L. C. Meyer, INEL Item S S
e/
S b M
. I M
ARD A D ff system tructur Comp u componen aterlas an ufacturer mechanism R e ects 1
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica Conductor Cables polyethylene and Usted ANDOXIDAT property - insulation cross linked resistance (IR) polyolefin 2
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica Conductor Cables polyethylene and Usted AND OXIDAT property -
cross linked capacitance & diss.
polyolefin factor 3
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica Conductor Cables polyethylene and Usted AND OXIDAT property -
cross linked polarization index polyolefin 4
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in Conductor Cables polyethylene and Usted ANDOXIDAT mechanical property cross linked
- elongation & tens.
polyolefin strength 5
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in Conductor Cables polyethylene and Usted ANDOXIDAT mechanical property cross linked
- hardness polyolefin 6
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in Conductor Cables polyethylene and Usted ANDOXIDAT mechanical property cross linked
- indenter modulus polyolefin 7
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in Conductor Cables polyethylene and Usted AND OXIDAT mechanical property cross linked
- bulk density polyolefin S
600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in Conductor Cables polyethylene and Usted ANDOXIDAT mechanical property cross linked
- mandrel bend test polyolefin 9
600 V, Single Insulation Cross linked Four Suppliers MOIST-EL Moisture absorbed Conductor Cables polyethylene and Usted into a cable acts as c cross linked plasticizer polyolefin 10 600 V, Single Jacket
- Neoprene, Four Suppliers ELETEMP, RAD, & Jacket - elongation Conductor Cables chlorosulfonated Usted OXIDAT
& tensil strength polyethylene (CSPEj, & CPE 11 600 V, Single Jacket
- Neoprene, Four Suppliers ELETEMP, RAD, & Jacket - hardness Conductor Cables chlorosulfonated Usted OXIDAT and indenter polyethylene modulus (CSPE), & CPE Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1E Electrical Cables Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
600 V I&C Cables Single and Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in electrica Multiconductor ANDOXIDAT property - insulation Cable Insulation resistance (IR)
- 2 600 V I&C Cables Single and Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in electrica Multiconductor ANDOXIDAT property - polarizaton Cable Insulation index
Table A.2 Gall Report for NPAR Reports Page 358 Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Long time delay varied between 110% and Rare Yes - not specifically IEEE 741-1986 Add infrared temperature 3-89 & 7-13 150% of setting identified Section 7 measurement and vibration testing tc 3 current plant practices. modify instantaneous trip test. [2]
One phase failed to trip on long time delay Frequent Yes - not specifically IEEE 741-1986 Add infrared temperature 3-89 & 7-14 overcurrent. Short timedelay overcurrent identified Section 7 measurement and vibration testing to 3 trip not within acceptance criteria.
current plant practices. modify instantaneous trip test. [2]
Document: NUREG/CR-5772 V1, Aging, Condition Monitoring, and Loss-ot-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Rep~rted progs Rel.progs Report Recommendations Page No. Item Not determined since report only Not stated Not discussed in No specific Not stated 6,27,40, 1
addressed detection methods report program andApp C
Not determined since report only Not stated Not discussed in No specific Not stated 6,28,&
2 addressed detection methods report program AppO.
Not determined since report only Not stated Not discussed in No specific Not stated 6,28, and 3
addressed detection methods report program AppC Not determined since report only Not stated Not discussed in No specific Not stated 6,30-33, 4
addressed detection methods report program 39,and App E.
Not determined since report only Not stated Not discussed in No specific Not stated 6,34,56, 5
addressed detection methods report program andApp F.
Not determined since report only Not stated Not discussed in No specific Not stated 33,38,&
6 addressed detection methods report program 39 Not determined since report only Not stated Not discussed in No specific Not stated 35&56 7
addressed detection methods report program Not determined since report only Not stated Testing per IEEE No specific Not stated 47 TO 54, 8
addressed detection methods 383-1974 program
&57.
Not determined since report only Not stated Testing per IEEE No specific Not stated 54&57 9
addressed detection methods 383-1974 program Not determined since report only Not stated Testing per IEEE No specific Not stated 33,39,&
10 addressed detection methods 383-1974 program 56 Not determined since report only Not stated Not discussed in No specific Not stated 39&56 11 addressed detection methods report program Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-ot-Coolant Accident (LOCA) Tests ot Class 1E Electrical Cables Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Not determined since report only Not stated Not discussed in No specific Not stated 31,32,52 1
addressed detection methods.
report program TO 58, 73,74,&
Appendix I
Not determined since report only Not stated Not discussed in No specific The electrical measurements were 13,32, 2
addressed detection methods.
report program not effective tor monitoring aging 46, & 73
Table A.2 Gall Report for NPAR Reports Page 36A Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-ot-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD ff e ects 3
600 V I&C Cables Single and Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Aging effects on Multiconductor AND OXIDAT capacitance and Cable Insulation dissipation factor 4
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in ANDOXIDAT mechanical property
- elongation & tens.
strength 5
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in ANDOXIDAT mechanical property
- hardness 6
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in ANDOXIDAT mechanical property
- indenter modulus 7
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in ANDOXIDAT mechanical property
- bulk densitY 8
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted ELETEMP, RAD, Changes in ANDOXIDAT mechanical property
- cracking 9
600 V I&C Cables Insulation Ethylene propylene Five Suppliers Usted MOIST-EL Moisture absorbed into a cable acts as c plasticizer 10 600 V I&C Cables Jacket CSPE and CPE Five Suppliers Usted ELETEMP, RAD, & Jacket - elongation OXIDAT
& tensil strength 11 600 V I&C Cables Jacket CSPE, & CPE Five Suppliers Usted ELETEMP, RAD, & Jacket -hardness OXIDAT and indenter modulus Document: NUREG/CR-5772 V3, Aging, Condition Monitoring, and Loss-ot-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electrica Types silicon rubber, &
Usted ANDOXIDAT property - insulation polymide (Kapton) resistance (IR) 2 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electrica Types silicon rubber, &
Usted ANDOXIDAT property -
polymide (Kapton) capacitance & diss.
factor 3
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electrica Types silicon rubber, &
Usted ANDOXIDAT property -
polymide (Kapton) polarization index 4
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in Types silicon rubber, &
Usted ANDOXIDAT mechanical property polymide (Kapton)
- elongation & tens.
- strengu, 5
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in Types silicon rubber, &
Usted AND OXIDAT mechanical property polymide (Kapton)
- hardness 6
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in Types silicon rubber, &
Usted AND OXIDAT mechanical property polymide (Kapton)
- indenter modulus 7
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in Types silicon rubber, &
Usted ANDOXIDAT mechanical property polymide (Kapton)
- bulk density 8
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in Types silicon rubber, &
Usted ANDOXIDAT mechanical property
~ymide (Kapton)
- brittleness 9
Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers MOIST-EL Moisture absorbed Types silicon rubber, &
Usted decreases insulation polymide (Kapton) resistance 10 Miscellaneous Cable Jacket FR & fiberglass Three Suppliers ELETEMP, RAD, &
Jacket - elongation Types braided Usted OXIDAT
& tensil strenlih 11 Miscellaneous Cable Jacket FR & fiberglass Three Suppliers ELETEMP, RAD, & Jacket - hardness Types braided Usted OXIDAT and indenter modulus
Table A.2 Gall Report for NPAR Reports Page 368 Document: NUAEG/CA-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported proas Rel.proCls Report Recommendations Page No. Item Not determined since report only Not stated Not discussed in No specific Not stated 33,36,&
3 addressed detection methods.
report program 46 Not determined since report only Not stated Not discussed in No specific Not stated 36 TO 41, 4
addressed detection methods.
report program
&46 Not determined since report only Not stated Not discussed in No specific Not stated 43,46, 5
addressed detection methods.
report program and Appendix F
Not determined since report only Not stated Not discussed in No specific The Franklin indenter is 17,42,&
6 addressed detection methods.
report program recommended because it is a good 46 indicator of aging for jacket and EPA materials. [4]
Not determined since report only Not stated Not discussed in No specific Not stated 43,46,&
7 addressed detection methods.
report program Appendix F
Not determined since report only Not stated Testing per IEEE No specific Follow IEEE 383-1974 66,74, &
8 addressed detection methods.
383-1974 program requirements. [4]
75 Not determined since report only Not stated Not discussed in No specific Not stated 58&74 9
addressed detection methods.
report program Not determined since report only Not stated Not discussed in No specific Not stated 73&75 10 addressed detection methods.
report program Not determined since report only Not stated Not discussed in No specific Not stated 46&73 11 addressed detection methods.
report program Document: NUAEG/CA-5772 V3, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Not determined since report only Not stated Not discussed in No specific Not stated 30,38, 1
addressed detector methods.
report program 40, & 51 Not determined since report only Not stated Not discussed in No specific Not stated 32,38,&
2 addressed detector methods.
report program Appendix D
Not determined since report only Not stated Not discussed in No specific Not stated 31,38,&
3 addressed detector methods.
report program Appendix C.
Not determined since report only Not stated Not discussed in No specific Not stated 34,35,&
4 addressed detector methods.
report program Appendix E
Not determined since report only Not stated Not discussed in No specific Not stated 36&
5 addressed detector methods.
report program Appendix G
Not determined since report only Not stated Not discussed in No specific The indenter is a good indicator of 36,&
6 addressed detector methods.
report program aging for silicon rubber and Kerite Appendix jacket materials, but not for coax F
jackets [4]
Not determined since report only Not stated Not discussed in No specific Not stated 36&
7 addressed detector methods.
report program Appendix G
Not determined since report only Not stated Testing per IEEE No specific IEEE 383-1974 requirements. [4]
45 TO 48, 8
addressed detector methods.
383-1974 program
&52.
Not determined since report only Not stated Not discussed in No specific Not stated 52 9
addressed detector methods.
report program Not determined since report only Not stated Not discussed in No specific Not stated 6,13, &
10 addressed detector methods.
report Iprooram 35 Not determined since report only Not stated Not discussed in No specific Not stated 16&36 11 addressed detector methods.
report program
Table A.2 Gall Report for NPAR Reports Page 37A Document: NUREG/CR-6095, Aging, Loss-ot-Coolant Accident (LOCA), and High Potential Testing of Damaged Cables Reviewed by:
L. C. Meyer, INEL Item S S
tu elC S b M
. I M
ARD
,ystem truc r omp u component aterlas anu acturer h
mec anlsm ARD ff ts eec 1
- 12 AWG, 1C, Insulation Ethylene propylene Okonite RAD, ELTEMP, &
Cracks, degraded Cables MOIST-EL, &
insulation resistance VOLTSTR tor damaged cable 2
- 12 AWG, 1C, Jacket Chlorosulfonated Okonite RAD, ELTEMP, &
Cracks cables polyethylene (CSPE)
MOIST-EL, &
VOLTSTR 3
- 12 AWG, 1C, Insulation Silicon rubber Rockbestos RAD, ELTEMP, &
Fragile & cracks Cables MOIST-EL, &
VOLTSTR 4
- 12 AWG, 1C, Jacket Figerglass braid Rockbestos RAD, ELTEMP, &
Not stated Cables MOIST-EL, &
VOLTSTR 5
- 12 AWG, 1C, Insulation Cross linked Brand Rex RAD, ELTEMP, &
Voltage breakdown Cables polyethylene with no MOIST-EL, &
and moisture and jacket VOLTSTR high temp degradation Document: SAND--88-0754, TIme-Temperature-Dose Rate Superpositions: A Methodology for Predicting Cable Degradation Under Ambient Nuclear Power Plant, RevieWed by:
L. C. Meyer, INEL Item System StructureiComp Subcom~onent Materials Manufacturer ARD mechanism ff ARDe ects 1
Electrical Cable Jacket Neoprene Not stated THERM& RAD Drop in elongation 2
Electrical Cable Jacket Hypalon Not stated THERM& RAD Drop in elongation 3
Electrical Cable Jacket PVC Not stated THERM& RAD Elongation reduced from initial value 4
Electrical Cable Insulation Low density Not stated THERM& RAD Embrittlement &
polyethylene discoloration 5
Electrical Cable Insulation Chemically Cross Not stated THERM& RAD Elongation decrease linked polyethylene Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear RevieWed by:
K D. McCarthy, INEL Item System StructureiComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Electrical SWitchgeal Metal Housing Not stated GE, Westinghouse, FAT, MECHSTR Cracked welds, System ITEIBB detormation of circui breaker rails 2
Electrical Switchgeal Metal Housing Not stated GE, Westinghouse, CONTAM,CORR Rust, pitting, and System ITE/BB corr of structural members and fasteners 3
Electrical Switchgeal Primary Insulating Not stated GE, Westinghouse, EMBR Insulation failure System ITEIBB 4
Electrical Switchgeal Primary Insulating Not stated GE, Westinghouse, CONTAM, EMBR Decrease in surface System ITE/BB resistance 5
Electrical SWitchgeal Primary Insulating Not stated GE, Westinghouse,
- ELETEMP, Decrease in System ITE/BB CONTAM, EMBR volumetric and surface resistance 6
Electrical Switchgeal Horizontal Racking Not stated GE, Westinghouse, WEAR Binding of drawout Mechanism ITEIBB unit 7
Electrical Switchgeal Vertical Racking Not stated GE, Westinghouse, WEAR Ufting motor failure Mechanism ITE/BB
Table A.2 Gall Report for NPAR Reports Page 378 Document: NUREG/CR-6095, Aging, Loss*of-Coolant Accident (LOCAl. and High Potential Testing of Damaged Cables Reviewed by:
L. C. Meyer, INEL Eff fA' R I R
Rd' ecto,grng on Component Function Contrib to Failure Reported progs e.progs eport ecommen ations P age N It
- o.
em Longitudinal cracks were through to Occasional Not discussed in No specific Not stated 4,5,10,&
1 conductor and adjacent to damaged area, report program 18 insulaton resistance degrades until failure occurs.
Jacket cracking can propagate to the OCASSIONAL Not discussed in No specific Not stated 4,5,10,&
2 insulation report program 18 Some cables showed degradation during Rare Not discussed in No specific Not stated 4& 16 3
accident tests, on one cable a crack was report program found adjacent to the damaged area.
Not stated Rare Not discussed in No specific Not stated 4 & 16 4
report program No high potential effects found when Rare Not discussed in No specific Not stated 4
5 insulation remaining was 7 mills, no report program cracks developed from aging. Failure of cables during LOCA testing were at damaged locations Document: SAND--88*0754, Time-Temperature-Dose Rate Superpositions: A Methodology for Predicting Cable Degradation Under Ambient Nuclear Power Plant t Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Jacket failed to provide protection from Rare Not discussed in No current Not stated 28 to 34 1
moisture.
report programs Jacket failed to provide protection from Rare Not discussed in No current Not stated 34 to 38 2
moisture.
report programs Jacket failed to provide protection from Occasional Not discussed in No current Not stated 43 3
moisture.
report programs EmbritUement causes cracking and allows Frequent (for 1960 Not discussed in No current Not stated 44 4
moisture intrusion resulting in failure to cable) report programs accurately transmit voltage or current.
EmbritUement causes cracking and allows Rare Not discussed in No current Not stated 12&54 5
moisture intrusion resulting in failure to report programs accurately transmit voltage or current.
Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Structural degradation caused by material Not stated Various No specific Not stated 4-7 1
fatigue can lead to the loss of structural recommendations program for integrity.
made for this maintenance subcomponent Contaminants and moisture can cause Not stated Various No specific Not stated 4-7 2
corrosion/rust of the metal housing recommendations program for system, resulting in a loss of structural made for this integrity.
maintenance subcomponent Insulation deterioration results from Not stated Various No specific Not stated 4-7 3
ambient temperatures with ohmic heating recommendations program for and can result in a loss of insulating made for this properties and flashover of insulation.
maintenance subcomponent Normal voltage in combination with Not stated Various No specific Not stated 4-7 4
humidity, dirt, and contaminants can lead recommendations program for to surface current tracking which can made for this result in insulation failure and flashover maintenance subcomponent Normal voltage in combination with Not stated Various No specific Not stated 4-7 5
thermal deterioration, humidity, dirt, and recommendations program for contaminants can lead to a decrease in made for this volumetric and surface resistance which maintenance subcomponent can result in bus insulation failure and flashover.
Wear from many racking cycles can lead Not stated Various Vendor specific Not stated 4-7 6
to a binding of the drawout unit which can recommendations programs result in the inability to connect the made for breaker for operation.
maintenance Wear from many racking cycles can lead Not stated Various Vendor specific Not stated 4-8 7
to a lifting motor failure which can result in recommendations programs the breaker not being able to be made for connected for 0 r
PEl ation.
maintenance
Table A.2 Gall Report for NPAR Reports Page 38A Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K D. McCarthy, INEL Item System Structur e/C S
omp ubcomponent Materials Manufacturer h
I ARDmee ansm ARD ff ts eee 8
Electrical Switchgear Arcing Contacts Not stated GE, Westinghouse, CURSTR Arcing contact bum ITEIBB up and vaporization 9
Electrical Switchgear Main Contacts Not stated GE, Westinghouse, CURSTR Contact burning or ITE/BB welding 10 Electrical Switchgear Main Contacts Not stated GE, Westinghouse, VIBR, WEAR Contact burning or ITEIBB welding 11 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, CONTAM, ENVIR Deterioration of Spring and Solenoid ITE/BB greases Operated Mech 12 Electrical Switchgea Stored Energy Not stated GE, Westinghouse, ENVIR, MECHSTR, High friction betweer Spring and Solenoid ITEIBB WEAR moving parts Operated Mech 13 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, VIBR, WEAR Movement of Spring and Solenoid ITEIBB components and Operated Mech loss of tolerances 14 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, FAT, CONTAM Broken welds Spring and Solenoid ITE/BB Operated Mech 15 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, WEAR Wear of spring Spring and Solenoid ITE/BB charging mechanisrr Operated Mech components 16 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, ELETEMP Trip or close coil Spring and Solenoid ITEIBB burn out Operated Mech 17 Electrical Switchgear Solenoid Operated Not stated GE, Westinghouse, ELETEMP Solenoid coil burnou Mechanism ITEIBB 18 Electrical Switchgear Solenoid Operated Not stated GE, Westinghouse,
- CURSTR, Insulation Mechanism ITE/BB ELETEMP deterioration 19 Electrical Switchgear Arc-Chute Not stated GE, Westinghouse, ELETEMP, EMBR Material degradation ITE/BB 20 Electrical Switchgear Primary Disconnect Not stated GE, Westinghouse, WEAR Disconnect wear, ITE/BB spring relaxation 21 Electrical Switchgear Secondary Not stated GE, Westinghouse, WEAR Spring relaxation Disconnect ITEIBB
Table A.2 Gall Report for NPAR Reports Page 388 Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Pciwer Plants - Electrical Switchgear Reviewed by:
K D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations age o.
em P
N It Fault current operation can cause contact Not stated Various IEEE 308-1980 Not stated 4-8 8
deterioration and lead to contact bum up recommendations Section 7.4 &
and vaporization which degrades the made for 7.5 breaker's function.
maintenance Fault current operation can lead to contact Not stated Various IEEE 308-1980 Not stated 4-8 9
deterioration which can result in the recommendations Section 7.4&
breaker's function being degraded.
made for 7.5 maintenance Movement of components and loss of Not stated Various IEEE 308-1980 Not stated 4-8 10 tolerances from mechanical cycling can recommendations Section 7.4&
lead to high resistance at the contact made for 7.5 interface which in tum can lead to contact maintenance buming or welding. This can result in degraded breaker function.
Ambient temperatures can cause greases Not stated Various Vendor specific Not stated 4-8 11 to deteriorate leading to binding of latches recommendations programs and high friction in mechanism. These made for can result in slow or no open or close maintenance operation.
Mechanical cycling of the stored energy Not stated Various Vendor specific Not stated 4-8 12 spring can cause mechanical wear of recommendations programs mechanism parts which leads to high made for friction between moving parts. This can maintenance result in binding of mechanism and latches, slow or no open or close operation.
Mechanical cycling can cause a loss of Not stated Various Vendor specific Not stated 4-8 13 tolerances and movement of components.
recommendations programs This can result in binding and/or failure to made for operate.
maintenance Mechanical cycling can lead to pole shaft Not stated Various Vendor specific Not stated 4-9 14 weld fatigue which can lead to broken recommendations programs welds. This can result in jamming, made for slowing, or failure to operate.
maintenance Mechanical cycling can lead to wear of Not stated Various Vendor specific Not stated 4-9 15 spring charging mechanism components recommendations programs which can result in failure to charge made for closing springs and failure to close.
maintenance Prolonged energization of the control coils Not stated Various No specific Not stated 4-9 16 can lead to elevated temperatures which recommendations program for can lead to trip or close coil bum out.
made for this sub This can result in failure to open, failure to maintenance component close, or failure to operate.
Prolonged energization of solenoid coil Not stated Various No specific Not stated 4-9 17 can cause elevated temperatures in the recommendations program for coil which can lead to solenoid coil made for this sub bumout. This can result in the breaker maintenance component failing to close.
Electrical cycling can cause insulation Not stated Various No specific Not stated 4-9 18 deterioration which can lead to solenoid recommendations program for coil bum out This can result in a failure made for this sub to close.
maintenance component Fault current operation can cause Not stated Various Vendor specific Not stated 4-9 19 elevated temperatures in the arc-chute recommendations programs which can lead to material degradation of made for the arc-chute. This can result in maintenance degraded function of the arc-chute.
Many racking cycles can cause Not stated Various No specific Not stated 4-9 20 disconnect wear and spring relaxation recommendations program for which can lead to high resistivity made for this mechanism connections. This can result in degraded maintenance disconnect function.
Many racking cycles can cause spring Not stated Various No specific Not stated 4-10 21 relaxation which can lead to high recommendations program for resistivity connections. This can result in made for this mechanism degraded disconnect function.
maintenance
Table A.2 Gall Report for NPAR Reports Page 39A Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K. D. McCarthy, INEL I tem System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 22 Electrical Switchgear Mechanical Interlock Not stated GE, Westinghouse, WEAR Wearldamage of ITEIBB mechanical interlock 23 Electrical Switchgear Auxiliary Switch Not stated GE, Westinghouse, WEAR, MECHSTR Burnt contacts ITEIBB 24 Electrical SWitchgea Current and Not stated GE, Westinghouse, EMBR, ELETEMP Insulation Potential ITE/BB deterioration Transformers 25 Electrical Switchgea Undervoltage Trip Not stated GE, Westinghouse, ELETEMP, EMBR Insulation Attachment ITE/BB deterioration 26 Electrical Switchgear Undervoltage Trip Not stated GE, Westinghouse, WEAR Wear of latch Attachment ITE/BB 27 Electrical Switchgear Undervoltage Trip Not stated GE, Westinghouse, WEAR High friction betweer Attachment ITE/BB moving parts 28 Electrical Switchgear Control Wiring Not stated GE, Westinghouse,
- ELETEMP, Loss of electrical ITE/BB MECHSTR, VIBR and mechanical properties 29 Electrical Switchgear Shunt Trip Not stated GE, Westinghouse, ELETEMP Coil deterioration Attachment ITE/BB 30 Electrical Switchgear Shunt Trip Not stated GE, Westinghouse, VIBR, WEAR Loss of tolerances Attachment ITElB8 31 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse, WEAR, FAT Spring relaxation Device (Electro-ITE/88 Mechanical) 32 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse, WEAR, ENVIR Armature Device (Electro-ITE/8B mechanical wear Mechanical) 33 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse,
- CONTAM, Seal degredation Device (Electro-ITE/BB MECHSTR Mechanical)
Table A.2 Gall Report for NPAR Reports Page 39B Document: SAND93*7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Component Function Contrib to FailUre Reported progs Rel.progs Report Recommendations Page No. Item Many racking cycles can cause Not stated Various Vendor specific Not stated 4-10 22 wear/damage from friction. This can recommendations
- Mechanism make it possible to remove or insert the cb made for not safety reI.
into compartment with main contacts maintenance closed. This could jeopardize personnel safety.
Mechanical cycling of the auxiliary switch Not stated Various Vendor specific Not stated 4-10 23 can cause contact deterioration which can recommendations
-Mechanism lead to bumt contacts. This can result in made for not safety reI.
contact failure.
maintenance Temperature and electrical cycling can Not stated Various No specific Not stated 4-10 24 cause insulation deterioration which can recommendations program for lead to shorted windings. This can result made for this in degraded function of the transformer maintenance subcomponent which can cause failure of undervoltage and control functions.
Constant coil energization can caUse Not stated Various Vendor specific Not stated 4-10 25 elevated temperatures which can lead to recommendations programs insulation deterioration. This can result in made for the breaker tripping open due to coil maintenance failure.
Mechanical cycling can cause wear of Not stated Various Vendor specific Not stated 4-10 26 latch which can lead to latch failure. This recommendations programs can result in a failure to trip on made for undervoltage condition.
maintenance Mechanical cycling can cause high Not stated Various Vendor specific Not stated 4-10 27 friction between moving parts which can recommendations programs lead to a lack of adequate force to trip the made for breader in an undervoltage condition.
maintenance High resistance connections, damage due Not stated Various No specific Not stated 4-10 28 to maint, and vibr can cause a loss of recommendations program for elect and mech properties, leading to made for this elevated temp and mech damage. This maintenance subcomponent can result in insulation deterioration and short to ground resulting in failure to operate.
Prolonged energization can cause Not stated Various Vendor specific Not stated 4-11 29 elevated temperatures in the coil whjch recommendations programs can lead to coil deterioration. This can made for cause coil failure and result in a failure of maintenance the shunt trip to operate.
CyCling and vibration can cause a loss of Not stated Various Vendor specific Not stated 4-11 30 tolerances on its mounting leading to recommendations programs loosening or misalignment This could made for result in the device not actuating the trip maintenance mechanism.
Prolonged spring compression can cause Not stated Various Vendor specific Not stated 4-11 31 spring relaxation leading to metal fatigue recommendations programs in the spring. This could result in made for setpointltime delay drift which could maintenance cause the overcurrent trip device to have improper operation or failure to operate.
Mechanical cyding and elevated Not stated Various Vendor specific Not stated 4-11 32 temperatures can cause friction or recommendations programs degraded lubricant which can lead to made for mechanical wear in the armature. This maintenance can result in setpointltime delay drift with the potential loss of overcurrent protection.
Mechanical cycling in conjunction with dirt Not stated Various IEEE 308-1980 Not stated 4-11 33 or contaminants can lead to seal recommendations Sections 7.4 &
degradation which can result in dashpot made for 7.5 leakage and setpointltime delay drift. This maintenance can result in the potential loss of overcurrent protection.
Table A.2 Gall Report for NPAR Reports Page 40A Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K. D. McCarthy, INEL Item S S
elC S b M
. I M
ARD
- iystem tructur omp u componen ater.a s anu acturer mechanism ARD ff e ects 34 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse,
- ELETEMP, Electrical componen Device (Solid State)
ITE/BB
- CURSTR, aging MECHSTR Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism A RD effects 1
Battery Chargers, Circuit Breakers Not stated Not stated CORR Contact pitting Inverters, & UPS's 2
Battery Chargers, Circuit Breakers Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 3
Battery Chargers, Circuit Breakers Not stated Not stated WEAR Attrition Inverters, & UPS's 4
Battery Chargers, Relay Not stated Not stated ENVIR Chemical or physical Inverters, & UPS's degradation 5
Battery Chargers, Circuit Breakers Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical or physical degradatio 6
Battery Chargers, Circuit Breakers Not stated Not stated CURRSTR Equip temp rise, Inverters, & UPS's equipment degradation, 7
Battery Chargers, Relay Not stated Not stated ELETEMP Chemical or physical Inverters, & UPS's degradation 8
Battery Chargers, Transformer Not stated Not stated CORR Loss of material; Inverters, & UPS's corrosion product buildup 9
Battery Chargers, Circuit Boards Not stated Not stated CORR Loss of material; Inverters, & UPS's corrosion product buildup 10 Battery Chargers, Switches Not stated Not stated CORR Contact pitting Inverters, & UPS's 11 Battery Chargers, Relay Not stated Not stated CORR Contact pitting Inverters, & UPS's 12 Battery Chargers, Potentiometer Not stated Not stated CORR Contact pitting Inverters, & UPS's 13 Battery Chargers, Switches Not stated Not stated FAT Cumulative fatique Inverters, & UPS's damage
Table A.2 Gall Report for NPAR Reports Page 40B Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear Reviewed by:
K. D. McCarthy, INEL Eft fA ecto,ging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. Item Elevated temperature, electrical transients Not stated Various IEEE 308-1980 Not stated 4-11 34 and mechanical shock result in material recommendations Sections 7.4 &
degradation from component aging. This made for 7.5 can result in erroneous solid-state deVice maintenance outpuVoperation and potential loss of overcurrent protection.
Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Eft fA' N
ecto
~lng on Component Function Contrib to Failure Reported progs ReJ.progs Report Recommendations Page o. Item Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19,5'15 1
impeadance, heat build-up, and signal inspection, IR program for transmission failure.
scanning this mechanism Fatigue due to high cyclic operation and Not stated Tactile inspection, No specific Not stated 4-20,5-16 2
vibration, resulting in contact degradation, vibration observation, program for loose connections, reduced force output IR scanning this mechanism and component failure.
Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21,5-16 3
operation caused by routine operation and program for periodiC testing and adjustrnen~ results in this mechanism rubbing surfaces, binding of linkages, erosion of contacts and metal surfaces, burning of arc chutes, and loss of adjustment.
Drifting of the electronic setpoint can Not stated Calibration, No specific Not stated 4-21,5'14 4
cause misoperation or component failure.
operational program for surveillance this mechanism Continuous load coupled with poor Not stated Cleaning, visual Vendor specific Not stated 4-22,5-15 5
contact mating, and fault currents can inspection programs cause deterioration of contact support insulation, and possible phase-to-ground faults Damage to contacts and arc chutes Not stated Cleaning, visual Vendor specific Not stated 4-22,5'15 6
occurs regularly due to normal fault inspection programs interruption.
Coil heating due to continuous, long-term Not stated Cleaning, visual Vendor specific Not stated 4-22,5'15 7
energizing of the coil, causing material inspection programs degradation due to accelerated chemical reactionslreduced dielectric strength.
Temperature and moisture create Not stated Visual inspection Vendor specific Not stated 4-19,5-14 8
environmental stresses on transformers programs which could result in corrosion of the windings. A reduction of the dielelctric strength or inSUlation resilience may occur, causing the transformer to ultimately fail.
Temp and moisture create environmental Not stated visual inspection, on-Vendor specific Not stated 4-19,5-15 9
stresses, and deposited contaminants line monitoring programs may affect electronics such as printed circuit boards, resistors, and capacitiors, resulting in corrosion of these components, which may lead to open/short cirCUits at the term in Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19,5'16 10 impeadance, heat build-up, and signal inspection program transmission failure.
Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19,5*14 11 impeadance, heat build-Up, and Signal inspection program transmission failure.
Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19,5-16 12 impeadance, heat build-up, and signal inspection program transmission failure.
Fatigue due to high cyclic operation and Not stated Tactile inspection, Vendor specific Not stated 4-20,5-16 13 vibration, resulting in contact degradation, vibration observation, surveillance loose connections, reduced force output IR scan and component failure.
Table A.2 Gall Report for NPAR Reports Page 41A Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Item System S
e/
SM' I
M f
tu ARD h'
ARD ff ts tructur Comp ubcomp_onen aterla s anu ac rer mec anlsm eec 14 Battery Chargers, Relay Not stated Not stated FAT Cumulative fatique Inverters, & UPS's damage 15 Battery Chargers, Potentiometer Not stated Not stated FAT Cumulative fatique Inverters, & UPS's damage 16 Battery Chargers, Switches Not stated Not stated WEAR Attrition Inverters, & UPS's 17 Battery Chargers, Relay Not stated Not stated WEAR Attrition Inverters, & UPS's 18 Battery Chargers, Potentiometer Not stated Not stated WEAR Attrition Inverters, & UPS's 19 Battery Chargers, Potentiometer Not stated Not stated ENVIRO Chemical or physical Inverters, & UPS's degradation 20 Battery Chargers, Surge Suppressors Not stated Not stated ENVIRO Chemical or physical Inverters, & UPS's degradation 21 Battery Chargers, Circuit Boards Not stated Not stated ENVIRO Chemical or physical Inverters, & UPS's degradation 22 Battery Chargers, Electronics Not stated Not stated ENVIRO Chemical or physical Inverters, & UPS's degradation 23 Battery Chargers, Electronics Not stated Not stated CORR Loss of material; Inverters, & UPS's corrosion product buildup 24 Battery Chargers, Wire Not stated Not stated CORR Loss of material; Inverters, & UPS's corrosion product buildup 25 Battery Chargers, Cooling Fans and Not stated Not stated CORR/OX Loss of material; Inverters, & UPS's Cooling Fan Motors corrosion product buildup;internal damage 26 Battery Chargers, Cabinet Not stated Not stated CORR/OX Loss of material; Inverters, & UPS's corrosion product buildup;internal damage
Table A.2 Gall Report for NPAR Reports Page 418 Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Eft fA' C
C
'b F'I R
ed R I R
rt R d ti P
N lte ecto
~glng on omponent Function ontrl to al ure eport progs el.progs epo ecomrilen a ons age o.
m Fatigue due to high cyclic operation and Not stated Tactile inspection, Vendor specific Not stated 4-20,5-14 14 vibration, resulting in contact degradation, vibration observation, surveillance loose connections, reduced force output IR scan and component failure.
Fatigue due to high cyclic operation and Not stated Tactile inspection, Vendor specific Not stated 4-20,5-16 15 vibration, resulting in contact degradation, vibration observation, surveillance loose connections, reduced force output IR scan and component failure.
Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21,5-16 16 operation caused by routine operation and program periodic testing and adjustmen~ results in rubbing surfaces, binding of linkages, erosion of contacts and metal surfaces, burning of arc chutes, and loss of adjustment.
Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21,5-14 17 operation caused by routine operation and program periodic testing and adjustment, results in rubbing surfaces, binding of linkages, erosion of contacts and metal surfaces, burning of arc chutes, and loss of adjustment.
Physical deterioration due to the cycliC Not stated Not discussed in No specific Not stated 4-21,5-16 18 operation caused by routine operation and report program periodic testing and adjustmen~ results in rubbing surfaces, binding of linkages, erosion of contacts and metal surfaces, burning of arc chutes, and loss of adjustment.
Drifting of the setpoint can cause Not stated Calibration, Tech IEEE 308-1980 Not stated 4-21,5-16 19 misoperation or componenet failure.
Spec, 1/0 logging, Section 7, Tech output Spec surveil.
Drifting of the electronic setpoint can Not stated Calibration No specific Not stated 4-21,5-15 20 cause misoperation or componenet program failure.
Drifting of the electronic setpoint can Not stated Calibration, Tech Tech Spec.
Not stated 4-21,5-15 21 cause misoperation or componenet Spec, 1/0 logging, required failure.
output surveillance Drifting of the electronic setpoint can Not stated Calibration, Tech Tech Spec.
Not stated 4-21,5-15 22 cause misoperation or componenet Spec, 1/0 logging, required failure.
output surveillance Temp and moisture create environmental Not stated Visual inspection, Vendor specific Not stated 4-19,5-15 23 stresses, and deposited contaminants output programs may affect electronics such as printed circuit boards, resistors and capacitors resulting in corrosion of the components, which may lead to open/short circuits at the terminals.
Temp and moisture create environmental Not stated Visual inspection, No specific Not stated 4-19,5-16 24 stresses, and deposited contaminants output program may corrode shields or conductor strands, terminations, etc. eventually causing failure of the circuit due to overheating or dielectric insulation breakdown.
Temp and moisture create environmental Not stated Visual inspection IEEE 334-1974 Not stated 4-19,5-16 25 stresses, and deposited contaminants Section 14.2.3 may increase contact resistance.
Vibration can promote loosening connectons resulting in localized heating and more oxidation.
Temp and moisture create environmental Not stated Visualjnspection No specific Not stated 4-20,5-17 26 stresses, and deposited contaminants program may over time can degrade and give way to oxidation corrosion.
Table A.2 Gall Report for NPAR Reports Page 42A Document: SAND93-7046, Aging Management Guideline for CommericaJ Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Item ~stem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 27 Battery Chargers, Transformer Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 28 Battery Chargers, Inductors Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 29 Battery Chargers, Capacitor Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 30 Battery Chargers, SCR's Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 31 Battery Chargers, Diodes Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 32 Battery Chargers, Surge Suppressors Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 33 Battery Chargers, Circuit Boards Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 34 Battery Chargers, Electronics Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 35 Battery Chargers, Wire Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's damage 36 Battery Chargers, Cooling Fans and Not stated Not stated FAT Cumulative fatigue Inverters, & UPS's Cooling Fan Motors damage
Table A.2 Gall Report for NPAR Reports Page 428 Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Eft t fA*
C F *1 d.
N eco Iglng on omponent Function Contrlb to at ure Reported progs Rel.p~ogs Report Recommen ations Page o. tem High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20,5-14 27 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, IR scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20,5-14 28 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, IR scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20,5-14 29 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, I R scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20,5-15 30 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, IR scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20,5-15 31 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, I R scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20,5-15 32 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, I R scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20,5-15 33 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, IR scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20,5-15 34 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, IR scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20,5-16 35 ferromagnetic resonance can cause inspection, vibration program fatigue resulting in loose parts, open observation, I R scan circuits causing loss of signal or sporatic operation. Regular maint also moveslbends wires/connectors causing conductor or insulation failure.
Vibration induced fatigue in motor mounts Not stated Tactile/audible IEEE 334-1974 Not stated 4-20,5-17 36 can occur due to improper sheave inspection, vibration Section 14.2.3 alignment and dynamic imbalances.
observation, IR scan
Table A.2 Gall Report for NPAR Reports Page 43A Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 37 Battery Chargers, Cooling Fans and Not stated Not stated WEAR Attrition Inverters, & UPS's Cooling Fan Motors 38 Battery Chargers, Transformer Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR or physical changes 39 Battery Chargers, Inductors Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 40 Battery Chargers, Capacitor Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 41 Battery Chargers, Diodes Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 42 Battery Chargers, Surge Suppressors Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 43 Battery Chargers, Circuit Boards Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR, CURSTR or physical changes 44 Battery Chargers, Electronics Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 45 Battery Chargers, SCR's Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 46 Battery Chargers, Switches Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR,CURSTR or physical changes 47 Battery Chargers, Wire Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR, CURSTR, or physical changes EMBR 48 Battery Chargers, Cooling Fan Motors Not stated Not stated THERM-CY, Deterioration of Inverters, & UPS's
- ELETEMP, insulation, chemical VOLSTR, CURSTR, or physical changes EMBR 49 Battery Chargers, Transformer Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 50 Battery Chargers, Inductors Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 51 Battery Chargers, SCR's Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties
Table A.2 Gall Report for NPAR Reports Page 438 Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Shafts and bearings are susceptible to Not stated Noise observation IEEE 334-1974 Not stated 4-21,5-17 37 normal wear, and wear due to Section 14.2.3 misalignment, imbalances, and inherent eccentricity of the rotor. On dc motors, brushes and commutators are also subject to wear.
Overvoltage or turn-to-turn shorts can Not stated
- Cleaning, Vendor specific Not stated 4-22,5-14 38 cause high internal tempreratures, visualltactile/audible program causing insulation to fail, causing local inpection heating and deterioration of material resulting in dielectric failure.
Overvoltage or turn-to-turn shorts can Not stated
- Cleaning, Vendor specific Not stated 4-22,5-14 39 cause high internal tempreratures, visual/tactile/audible program causing insulation to fail, causing local inpection heating and deterioration of material resulting in dielectric failure.
Overvoltage can cause voltage stress Not stated Cleaning, visual Vendor specific Not stated 4-22,5-14 40 causing loss of capacitance, breakdown inspection, program of dielectric.
measuement, part replacement Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22,5-15 41 internal stresses can cause dielectric inspection, program breakdown resulting in change in output temperature &
signal.
input/output Heat due to overcurrent conditions and Not stated Cleaning, visual No specific Not stated 4-22,5-15 42 internal stresses can cause dielectric inspection, program breakdown and misoperation or failure of temperature &
the device.
input/output Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22,5-15 43 intemal stresses can cause dielectric inspection, program breakdown and misoperation or failure of temperature &
components, open/shorts of circuits.
input/output Heat due to over current conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22,5-15 44 internal stresses can cause dielectric inspection, program breakdown and misoperation or failure of temperature &
components, open/shorts of circuits.
input/output Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22,5-15 45 intemal stresses can cause dielectric inspection, program breakdown and misoperation or failure of temperature &
components, open/shorts of circuits.
input/output Heat due to overcurrent conditions and Not stated Cleaning, visual No specific Not stated 4-23,5-16 46 normal operations, and due to contact inspection, program resistance, can cause dielectric temperature logging breakdown of supports and insulation, and misoperation or failure of components.
Thermal effects on wire and cable leading Not stated Cleaning, visual No specific Not stated 4-23 47 to embrittlement, and insulation failure.
inspection, program Ohmic heating and heat from surrounding temperature &
environment degrades insulation, resulting input/output in short circuits.
Heat due to overcurrent conditions and Not stated Cleaning, visual IEEE 334-1974 Not stated 4-23,5-16 48 normal operations, can cause dielectric inspection, Section 14.2.3 breakdown and failure.
temperature &
input/output Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,5-14 49 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,5-14 50 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,5-15 51 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Table A.2 Gall Report for NPAR Reports Page 44A Document: SAND93* 7046, Aging Management Guideline for Commerical Nuclear Power Plants* Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Item System Structure/Comp Subcomponent Materials Manu acturer ARDmec amsm e ects h*
ARD ff 52 Battery Chargers, Diodes Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 53 Battery Chargers, Capacitor Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 54 Battery Chargers, Surge Suppressors Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 55 Battery Chargers, Circuit Boards Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 56 Battery Chargers, Electronics Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 57 Battery Chargers, Wire Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 58 Battery Chargers, Relay Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 59 Battery Chargers, Circuit Breakers Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 60 Battery Chargers, Switches Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 61 Battery Chargers, Potentiometers Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 62 Battery Chargers, Cooling Fan Motoers Not stated Not stated CONTAM Buildup of deposits; Inverters, & UPS's loss of desired surface properties 63 Battery Chargers, Relay Not stated Not stated LOSLUB Viscosity change, Inverters, & UPS's loss of lubricicty 64 Battery Chargers, Circuit Breakers Not stated Not stated LOSLUB Viscosity change, Inverters, & UPS's loss of lubricicty Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants* Power and Distribution Transformers RevieWed by:
Michael W. Vaughn, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Transformer Metal Enclosure Low-alloy steel Not stated ENVIR Chemical/physical (Tank) and Cover degradation 2
Transformer Metal Enclosure Low*a1loy steel Not stated.
CORR Loss of material; (Tank) and Cover corrosion product buildup
Table A.2 Gall Report for NPAR Reports Page 448 Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies Reviewed by:
Michael W. Vaughn, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,5-15 52 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,5-14 53 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,5-15 54 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,5-15 55 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,5-15 56 dirt, and dust, can reduce heat inspection programs dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,5-16 57 dirt, and dust, can reduce heat inspection programs diSSipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,4-58 dirt, and dust, can reduce heat inspection programs 24,5-14 dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23,4-59 dirt, and dust, can reduce heat inspection programs 24,5-15 dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,4-60 dirt, and dust, can reduce heat inspection programs 24,5-16 dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23,4-61 dirt, and dust, can reduce heat inspection programs 24,5-16 dissipation, cause overheating, and eventual failure of components.
Fouling due to accumulation of insects, Not stated Cleaning, visual IEEE 334-1974 Not stated 4-24,5-1' 62 dirt, and dust, can reduce heat inspection SECTION dissipation, cause overheating, and 14.2.3 eventual failure of components.
Material set occurs when the organic Not stated Tactile inspection, Vendor specific Not stated 4-24,5-14 63 materials used as lubricants in those operational programs subconponents harden, gel, or adhere to adjacent materials, which can cause binding of the devices, resulting in faulty operation.
Material set occurs when the organic Not stated Tactile inspection, Vendor specific Not stated 4-24,5-14 64 materials used as lubricants in those operational programs subconponents harden, gel, or adhere to adjacent materials, which can cause binding of the devices, resulting in faulty operation.
Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers Reviewed by:
Michael W. Vaughn, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Chipping, cracking, or peeling of the Not stated Visual inspection, Vendor specific Not stated 4-7,5-3, 1
enclosure's protective coating cleaning, pressure surveillance, 5-15 testing IEEE 308-1980 Exposed metal develops rust and Not stated Visual inspection, Vendor* specific Not stated 4-7,5-3, 2
corrosion cleaning, pressure surveillance, 5-15 testing IEEE 308-1980
Table A.2 Gall Report for NPAR Reports Page 45A Document: SAND93*7068, Aging Management Guideline for Commercial Nuclear Power Plants* Power and Distribution Transformers Reviewed by:
Michael W. Vaughn, INEL Item S S
~C Sb system tructur omp u co,,!ponent Materials Manufacturer ARD mechanism ARDeffects 3
Transformer Metal Enclosure Low*alloy steel Not stated ENVIR, EMBR Deterioration of (Tank) and Cover organic components 4
Transformer Metal Enclosure Low*alloy steel Not stated FAT Cumulative damage (Tank) and Cover from cyclic vibration or thermal stress 5
Transformer Primary and Not stated Not stated ELETEMP Chemical or physical Secondary degradation: thermal Windings, Uquid*
distortion Immersed 6
Transformer Primary and Not stated Not stated VIBR, VOLSTR, Loosening, reduced Secondary EXFORCE tolerances, distortion Windings, Uquid-or bending Immersed 7
Transformer Primary and Not stated Not stated ELETEMP Chemical or physical Secondary degradation; thermal Windings, Dry-Type distortion 8
Transformer Primary and Not stated Not stated VIBR, VOLSTR, Loosening, reduced Secondary EXFORCE tolerances, distortion Windings, Dry-Type or bending 9
Transformer Magnetic Core Not stated Not stated VIBR, MECHSTR, Loosening, EXFORCE distortion, deterioration of meet function 10 Transformer Magnetic Core Not stated Not stated EMBRfTE Loss of fracture toughness 11 Transformer Insulation Not stated Not stated
- ELETEMP, Chemical or physical VOLSTR degradation, degradation of insulation 12 Transformer Insulation Not stated Not stated MOIST-EL, Loss of dielectric CONTAM properties, buildup 0
/
deposits 13 Transformer Insulation Not stated Not stated Not stated High acidity resulting in more water retention 14 Transformer Insulation Not stated Not stated CORR/OX Loss of material; corrosion product buildup;intemal damage
Table A.2 Gall Report for NPAR Reports Page 458 Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers Reviewed by:
Michael W. Vaughn, INEL Eft t fA*
C F*
- b F*I R
ed R I R
Rd*
ec 0 Iglng on omponent unction Contr. to a. ure eport progs el.progs eport ecommen ations P age N It
- o.
em Gaskets and other organic seals used in Not stated Visual inspection, Vendor specific Not stated 4-7,5-15 3
construction of the enclosure degrade due cleaning surveillance, to exposure to heat, ultraviolet radiation, IEEE 308-1980 moisture, or chemicals, while under mechanical stress or compression.
polymeric seal materials embrittle and harden Can affect areas of high local stress such Not stated visual inspection, Vendor specific Not stated 4-7,4-8, 4
a welds, tank edges, etc., resulting in tank cleaning, pressure surveillance, 5-3,5-15 leaks (oil or gas-filled units) and testing IEEE 308-1980 potentially a loss of structural intergrity.
May induce accelerated degradiation of Not stated Electrical testing, Vendor specific Not stated 4-8,5-4, 5
surrounding organic materials.
visual inspection, surveillance, 5-15 cleaning IEEE 308-1980 Movement and vibration allow windings to Not stated Electrical testing, Vendor specific Not stated 4-9,5-4, 6
change clearances/tolerances required for visual inspection, surveillance, 5-15 maintaining satisfactory dielectric cleaning IEEE 308-1980 strength, which can result in dielectric breakdown and localized discharge. Can cause mechanical stress on electrical connections May induce accelerated degradation of Not stated Electrical testing, Vendor specific Not stated 4-9,5-4, 7
surrounding organic materials.
visual inspection, surveillance, 5-15 Degradation of winding conductor cleaning IEEE 308-1980 connections due to high resistance connections causing localized heating.
Movement and vibration allow winding to Not stated Electrical testing, Vendor specific Not stated 4-9,5-4, 8
change clearances/tolerances required for visual inspection, surveillance, 5-15 maintaining satisfactory dielectric cleaning IEEE 308-1980 strength, which can result in deilectric breakdown and localized discharge. Can cause mechanical stress on electrical connections.
Loosining of the core due to vibration, Not stated Electrical testing, Vendor specific Not stated 4-10,5-4, 9
shock, or severe electrical transients, can visual inspection surveillance, 5-15 cause wear or deterioration of the IEEE 308-1980 insulation once dislocation occurs may lead to sufficient insulation damage to allow electrical failure A result of relatively high thermal Not stated Electrical testing, Vendor specific Not stated 4-10,4-10 exposure resulting from core and winding visual inspection surveillance, 11,5-4,5-losses, causing weakening or failure of IEEE 308-1980 15 the laminations, causing increased eddy currents and core losses.
Partial or localized breakdown of the Not stated Sampling and Vendor specific Recommended laboratory and/or in-4-11,5-5, 11 dielectric capacity of the material, which analysis, cleaning, surveillance, situ analysis to detect impending 5-15,5-22 may in tum produce other eleterious replacement IEEE 308-1980 breakdown of dielectric [2]
effects such as the formation of additional gaseous byproducts, decomposition of the surrounding insulating fluid.
Particulates contaminants and moisture Not stated Sampling and Vendor specific Recommended laboratory and/or in-4-12,5-5, 12 may result in blockage of passages analysis, cleaning, surveillance, situ analysis to detect impending 5-16,5-22 leading to hot spots. Chemical replacement IEEE 308-1980 breakdown of dielectric [2]
contaminants may have adverse effects on the material properties, water reduces dielectric strength causing partial discharge or dielectric breakdown High acidity results in more water being Not stated Sampling and Vendor specific Recommended laboratory and/or in-4-12,5-5, 13 held in solution and therefore reduced analysis, cleaning, surveillance, situ analysis to detect impending 5-16,5-22 dielectric strength. Also affects the replacement IEEE 308-1980 breakdown of dielectric [2]
deterioration and decomposition of solid insulating materials reducing the dielectric strenth Formation of sludge which can impead Not stated Sampling and Vendor specific Recommended laboratory and/or in-4-12,5-5, 14 circulation creating hot spots. Dielectric analysis, cleaning, surveillance, situ analysis to detect impending 5-16,5-22 properties associated with the sludge may replacement IEEE 308-1980 breakdown of dielectric [2]
also differ. oxygen will also increase the acidity of the insulating fluid
Table A.2 Gall Report for NPAR Reports Page 46A Document: SAND93*7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers Reviewed by:
Michael W. Vaughn, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 15 Transformer Insulation Not stated Not stated ELETEMP Chemical or physical degradation; thermal distortion 16 Transformer Bushings Not stated Not stated THERM-CY Degradation due to exposure to elements and temp cycles 17 Transformer Bushings Not stated Not stated CONTAM Buildup of deposits:loss of desired surface I properties 18 Transformer Bushings Not stated Not stated ENVIRO Chemical or physical degradation 19 Transformer Bushings Not stated Not stated VOLSTR Dielectric stress causing degradation of insulation 20 Transformer Cooling System, Not stated Not stated FAT, WEAR Attrition and Liquid-Immersed cumulative fatigue and Dry-Type damage over time 21 Transformer Cooling System, Not stated Not stated CONTAM Buildup of deposits; Liquid-Immersed loss of desired and Dry-Type surface properties 22 Transformer Oil Preservation and Not stated Not stated ENVIRO, ELETEMP Chemical or physical Sampling System degredation 23 Transformer Oil Preservation and Not stated Not stated WEAR Attrition Sampling System 24 Transformer Tap Changers Not stated Not stated WEAR Attrition 25 Transformer Tap Changers Not stated Not stated VIBR, MECHSTR Loosening, deterioration of mechanical function 26 Transformer Tap Changers Not stated Not stated ELTEMP, THERM-Chemical or physical CY degradation, insulation deterioration 27 Transformer Protection and Not stated Not stated ENVIRO, EMBR Chemical or physical Monitoring Systems degradation, loss or fracture toughness 28 Transformer Protection and Not stated Not stated THERM-CY Deterioration of Monitoring Systems insulation
Table A.2 Gall Report for NPAR Reports Page 468 Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers Reviewed by:
Michael W. Vaughn, INEL Eft f
ect 0 Aging on Component Function Contrib to Failure Reported progs Rel.proas ReDort Recommendations Page No. Item The elevated temperatures cause thermal Not stated Visual inspection, Vendor specific Not stated 4-13,5-7, 15 deterioration and dielectric breakdown insulation resistance surveillance, 5-16 testing, clean IEEE 308-1980 Breakdown of gaskets and seals, and all Not stated Visual inspection, Vendor specific Manage bushing flashover by 4-14,5-7, 16 organiC materials due to heat caused by power factor testing, surveillance, controling airborne dust and/or salt 5-16,5-22 current in the conductor! solar radiation, cleaning IEEE 308-1980 spray accumulation in combination etc.
with rainlhumidity [2)
The combination of dirt, dust, salt, and Not stated Visual inspection, Vendor specific Not stated 4-14,5-7, 17 other contaminants, alone or with water or power factor testing, surveillance, 5-17 other liquid can form a conductive path cleaning IEEE 308-1980 leading to flashover of the bushing.
Factors such as ultraviolet radiation, Not stated Visual inspection, Vendor specific Not stated 4*14,5-7, 18 humidity, etc. can cause degradation over power factor testing, surveillance, 5-17 time cleaning IEEE 308-1980 Improper storage or loss of insulating oil, Not stated Visual inspection, Vendor specific Not stated 4-14,5-7, 19 or voltage transients, can degrade the power factor testing, surveillance, 5-17 dielectric properties. Dielectric stress cleaning IEEE 308-1980 from potential gradient between the central conductor and other surfaces.
Bearings and other parts wear over time Not stated Visual inspection, Vendor specific Not stated 4-15,5-8, 20 due to friction and other stresses placed monitor, adjust, surveillance, 5-17 on them. This is accelerated by such lubricate, clean IEEE 308-1980 stresses as frequent motor starting and stopping, undue vibration or transverse/longitudinalload placed on the driven unit.
Fouling of heat transfer surfaces such as Not stated Visual inspection, Vendor specific Not stated 4-16,5-8, 21 radiators due to dirt, debris, or other monitor, clean surveillance, 5-17 materials IEEE 308-1980 Elevated temperatures and exposure to Not stated Visual inspection, Vendor specific Not stated 4-16,5-9, 22 the elements can cause thermal and wear
- adjust, surveillance, 5-17 degradation to components.
repair/replace, clean IEEE 308-1980 Wear to components such as sampling Not stated Visual inspection, Vendor specific Not stated 4-17,5-9, 23 and isolation valves, fittings, and pressure
- adjust, surveillance, 5-18 regulating valves, can result in leakage of repair/replace, clean IEEE 308-1980 fluids, binding and/or malfunctioning of devices.
Wear to components due to friction.
Not stated Visual inspection, Vendor specific Not stated 4-18,5-9, 24
- adjust, surveillance, 5-18 repairlreplace, IEEE 308-1980 lubricate, clean Vibration and mencanical stresses can Not stated Visual inspection, Vendor specific Not stated 4-18,5-25 result in a loss of adjustment in parts
- adjust, surveillance, 10,5-18 repairlreplace, IEEE 308-1980 lubricate, clean Degradation of organic insulating Not stated Visual inspection, Vendor specific Not stated 4-18,5-26 materials in motor windings, insulators on
- adjust, surveillance, 10,5-18 main contacts, and materials used in repair/replace, clean IEEE 308-1980 related electrical components which can reduce their dielectric as well as mechanical properties.
Degradation of organic materials used to Not stated Visual inspection, Vendor specific Not stated 4-19,5-27 seal the relay, can embrittle and harden functional testing surveillance, 11,5-18 the gaskets allowing leakage, possibly IEEE 308-1980 leading to the component failure.
Repeated heating and cooling of the Not stated Visual inspection, No specific Not stated 4-20,5-28 temperature indicator elements due to functional testing program 10,5-19 load variation induces thermal stresses which may eventually result in open-circuit failure of the element.
Table A.2 Gall Report for NPAR Reports Page 47A Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers Reviewed by:
K. D. McCarthy, INEL Item System Structure/Com p Subcomponent Materials Manufacturer ARD mechanism ARD ff e ects 1
Motor Control Center Motor Not stated GE, Westinghouse, THEM-CY, EMBR Loss of electrical C-H, KM and mechanical properties of insulator 2
Motor Control Cente Motor Not stated GE, Westinghouse, MOIST-EL, Loss of surface C-H, KM CONTAM, ENVIR insulating properties 3
Motor Control Cente Motor Not stated GE, Westinghouse, MOIST-EL, Loss of volumetric C-H, KM CONTAM, ENVIR insulating properties 4
Motor Control Center Motor Not stated GE, Westinghouse, WEAR, CORR/OX, High resistance C-H, KM CONTAM electrical connections 5
Motor Control Cente Motor Not stated GE, Westinghouse, MECHSTR, VIBR Loosening/loss of C-H, KM fasteners 6
Motor Control Centel Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR Contact surface Breakers glass polyester, C-H, KM deterioration contact-silver or tungsten 7
Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, FAT, MECHSTR Fatigue of various Breakers glass polyester, C-H, KM circuit breaker contact-silver or components tungsten 8
Motor Control Cente Molded-Case Circuit Case-phenolic or GE, Westinghouse, WEAR, CONTAM Wear of internal Breakers glass polyester, C-H, KM components contact-silver or tungsten 9
Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse,
- ELETEMP, Loose or high Breakers glass polyester, C-H, KM CORR/OX, VIBR resistance elect contact-silver or connections or tungsten terminations 10 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR Thermal trip setpoint Breakers glass polyester, C-H, KM variations contact-silver or tungsten 11 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CONTAM, ENVIR Deterioration of Breakers glass polyester, C-H, KM lubricants contact-silver or tungsten 12 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, ENVIR Current limiting fuse Breakers glass polyester, C-H, KM failure contact-silver or tungsten
Table A.2 Gall Report for NPAR Reports Page 478 Document: SAND93*7069, Aging Management Guideline for Commercial Nuclear Power Plants* Power and Distribution Transformers Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations P
N age o. tem Exposure to ambient temps and ohmic Not stated Various Vendor specific Not stated 4-4,4-5, 1
heating can lead to loss of insulating recommendations programs 5-15 properties and thermally induced made for cracking. This has the potential of maintenance causing a flashover of the component insulation and loss of structural integrity.
Voltage and humidity can affect energized Not stated Various Vendor specific Not stated 4-6,4-7, 2
insulation that is dirty or deteriorated and recommendations programs 5-15 cause surface tracking paths on the made for insulator. This can lead to flashover.
maintenance Simultaneous exposure of thermally Not stated Various No specific Not stated 4-6,4-7; 3
deteriorated insulation to temp, voltage, recommendations program for 5-15 humidity, dirt and contaminants can result made for this in loss of volumetric insulating properties, maintenance subcomponent leading to increased surface and volumetric leakage currents and possible flashover Poor mating surface contact or sharp Not stated Various Vendor specific Not stated 4-5,4-8, 4
bends/current flow restrictions near recommendations program 5-15 crimps or terminations can cause high made for resistance elec connections which can maintenance result in excessive heating and potentially fire.
Over-torquing of fasteners, and fasteners Not stated Various Vendor specific Not stated 4-8,5-15 5
loosened by various extemal stresses recommendations program (non-seismic) could cause loss of made for structural integrity or affect electrical maintenance connections.
High temps that accompany fault currents Not stated Various No specific Not stated 4-9,5-15 6
may cause contact material to vaporize, recommendations program for inducing a loss of contact surface material made for this and pitting. This could cause the maintenance subcomponent contacts to bum or weld together and result in breaker failure.
Cyclic stress can cause fatigue failure of Not stated Various No specific Not stated 4-9,5-15 7
various circuit breaker components such recommendations program for as contact assemblies, operating made for this mechanisms, breaker housing. Fatigue maintenance subcomponent may be evidenced by progressive cracking and ultimate failure of the component.
Inadequate or degraded lubrication, Not stated Various No specific Not stated 4-9,5-15 8
normal component wear, or wear caused recommendations program for by contaminants (from other degraded made for this material or from external sources) can maintenance subcomponent cause the breaker to malfunction.
Operation of the breaker and non-seismic Not stated Various No specific Not stated 4-9,5-15 9
vibration cause loose connections.
recommendations program for oxidation or contamination of contact made for this surfaces and sharp bends in wiring near maintenance subcomponent terminations can cause high resistance connections. These can cause excessive heating or fire.
Exposure to fault currents can cause Not stated Various No specific Not stated 4-10,5-15 10 variations in the thermal trip setpoint of a recommendations program for circuit breaker. This can cause the CB to made for this trip at progressively lower current levels, maintenance subcomponent potentially causing nuisance tripping.
Contamination, aging, evaporation, and Not stated Various No specific Not stated 4-10,5-15 11 ambient temperatures can cause recommendations program for lubricants to deteriorate. this can slow or made for this completely prevent operation of a breaker.
maintenance subcomponent Fuses degrade slowly over time until Not stated Various Replace when Not stated 4-10,5-15 12 eventually the current-carrying capability recommendations inoperative of the fuse is reached during made for normalltransient load operation, resulting maintenance in nuisance current interruptions.
Table A.2 Gall Report for NPAR Reports Page 48A Document: SAN D93-7069, Aging Management Guideline tor Commercial Nuclear Power Plants - Notor Control Centers Reviewed by:
K. D. McCarthy, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 13 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse,
- CURSTR, Surface current Breakers glass polyester, CoH, KM CONTAM trackinglloss of contact-silver or insulating properties tungsten 14 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse,
- CURSTR, Thermally induced Breakers glass polyester, CoH, KM ELETEMP degradation contact-silver or tungsten 15 Motor Control Cente Magnetic Not stated GE, Westinghouse, ELETEMP Insulation Contactors/Starters CoH, KM deterioration 16 Motor Control Cente Magnetic Not stated GE, Westinghouse, ELETEMP Organic component Contactors/Starters CoH, KM breakdown 17 Motor Control Center Magnetic Not stated GE, Westinghouse, VIB, WEAR Cyclic fatigue Contactors/Starters CoH, KM 18 Motor Control Center Magnetic Not stated GE, Westinghouse, WEAR, VIB, Wear of contactor Contactors/Starters CoH, KM CONTAM and starter subcomponents 19 Motor Control Center Magnetic Not stated GE, Westinghouse, CONTAM Contact surface Contactors/Starters CoH, KM degradation 20 Motor Control Cente Thermal Overload Not stated GE, Westinghouse, WEAR, CURSTR Degradation of Relays CoH, KM heater or bimetallic elements 21 Motor Control Cente Thermal Overload Not stated GE, Westinghouse, CONT, WEAR Binding of Relays CoH, KM mechanical components 22 Motor Control Center Thermal Overload Not stated GE, Westinghouse, CONT Contact surface Relays CoH, KM degradation 23 Motor Control Center Thermal Overload Not stated GE, Westinghouse, ELETEMP, EMBR Thermal degradation Relays CoH, KM of organic materials
Table A.2 Gall Report for NPAR Reports Page 488 Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers Reviewed by:
K. D. McCarthy, INEL Eft t fA' C
F' C
'b F'I R
ed R I R
rt R eco Iging on omponent unction ontrl to al ure eport progs el.progs epo ecommen d.
ations P age N It
- o.
em Voltage and humidity can affect energized Not stated Various No specific Not stated 4-10,5-15 13 insulation that is dirty or deteriorated and recommendations program for cause surface tracking paths on the made for this insulator. Breaker arc-chute insulation is maintenance subcomponent especially susceptible to surface current tracking. This can lead to flashover.
Fault currents can produce high Not stated Various No specific Not stated 4-11,5-15 14 temperatures and currents that can recommendations program for rapidly damage contacts, arc-chute made for this surfaces and other organic materials.
maintenance subcomponent Continuous load currents can produce ohmic heating in poor connections.
These can cause cb failure.
During operation, the heat generated in Not stated Various Vendor specific Not stated 4-12,5-16 15 the coil during energization could cause recommendations program insulation deterioration of the coil itself.
made for This can lead to coil failure.
maintenance Prolonged coninuous energization of the Not stated Various No specific Not stated 4-12,5-16 16 contactor coil could result in excessive recommendations program for temperatures that cause the organic made for this compounds that encapsulate the maintenance subcomponent contactor to degrade. This could shorten life and lead to coil bumout.
Cyclic fatigue can occur in magnetic Not stated Various Vendor specific Not stated 4-13,5-16 17 contactors if subjected to extremely high recommendations program cycle operation. This can lead to heat made for generation because of higher resistivity, maintenance misalignment of contact, binding of armature, preventing full contact mating and arcing.
Binding of the contactor assembly, Not stated Various Vendor specific Not stated 4-13,5-16 18 binding of contactor armature, binding of recommendations
- program, the contactor mechanism are all caused made for replace when by wear, vibration and contamination.
maintenance failed These can result in poor contactorlstarter operation and failure.
Dust, dirt, and foreign material can lead to Not stated Various Vendor specific Not stated 4-13,5-16 19 coil burnout, pitting of contact surfaces, recommendations program and breakdown of adhesives and made for lubricants. They can also prevent the maintenance contact from closing. All the above can cause the contactor or starter to fail.
In bimetallic devices, variations in the Not stated Various Vendor specific Not stated 4-14,5-16 20 current flowing through the heater will recommendations
- program, result in variations in device setpoint.
made for replace when These variations may be caused by maintenance failed changes in the characteristics of the heater element.
Mechanical interference, dirt and friction Not stated Various Replace when Not stated 4-14,5-17 21 may cause mechanical interference recommendations failed resulting in binding of mechanical made for components.
maintenance Dust, dirt, and foreign material can lead to Not stated Various Vendor specific Not stated 4-14,5-17 22 coil burnout, pitting of contact surfaces, recommendations
- program, and breakdown of adhesives and made for replace when lubricants. They can also prevent the maintenance failed contact from closing. All the above can cause the relay to fail.
Elevated temperatures caused by the Not stated Various Vendor specific Not stated 4-14,5-17 23 heaters cause aging of the heater element recommendations
- program, support material. Failure of the support made for replace when block results in possible failure of the maintenance failed overload relay to perform its required function.
Table A.2 Gall Report for NPAR Reports Page 49A Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers Reviewed by:
K D. McCarthy, INEL Item System S
e/
S b M
. 1 f t ARD tructur Comp u componen aterlas Manu ac urer h
mec anJsm ARD ff ts eec 24 Motor Control Center Thermal Overload Not stated GE, Westinghouse,
- ELETEMP, Loose or high Relays C-H, KM CORR/OX, VIBR resistance elec connections or terminations 25 Motor Control Center Miscellaneous Not stated GE, Westinghouse, ELETEMP Thermal breakdown Relays C-H, KM of organic materials 26 Motor Control Center Miscellaneous Not stated GE, Westinghouse, CONT Contact surface Relays C-H, KM degradation 27 Motor Control Center Miscellaneous Not stated GE, Westinghouse, WEAR, VIBR Wear of mechanical Relays C-H, KM parts 28 Motor Control Cente Miscellaneous Not stated GE, Westinghouse,
- ELETEMP, Loose or high Relays C-H, KM CORR/OX, VIBR resistance elect connections or terminations 29 Motor Control Centel Miscellaneous Not stated GE, Westinghouse, VOLTSTR Coil dielectric Relays C-H, KM breakdown 30 Motor Control Cente Control Not stated GE, Westinghouse, ELETEMP Winding insulation Transformers C-H, KM degradation 31 Motor Control Cente Control Not stated GE, Westinghouse, CURSTR Winding conductor Transformers C-H, KM failure 32 Motor Control Center Control Not stated GE, Westinghouse,
- ELETEMP, Loose or high Transformers C-H, KM CORR/OX, VIBR resistance elect connections or terminations 33 Motor Control Center Terminal Blocks Not stated GE, Westinghouse,
- ELETEMP, Loose or high C-H, KM CORR/OX, VIBR resistance elect connections or terminations 34 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, ELETEMP, EMBR, Degradation or C-H, KM ENVIR organic materials
Table A.2 Gall Report for NPAR Reports Page 49B Document: SAND93*7069, Aging Management Guideline for Commercial Nuclear Power Plants* Notor Control Centers Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Rej)ort R ecommendations P age N lte
- o.
m Operation of the relay and non-seismic Not stated Various Vendor specific Not stated 4-15,5*17 24 vibration cause loose connections.
recommendations program Oxidation or contamination of contact made for surfaces and sharp bends in wiring near maintenance terminations can cause high resistance connections. These can cause excessive heating or fire.
Prolonged continuous energization of the Not stated Various No specific Not stated 4*12,5-17 25 relay could result in excessive recommendations program for temperatures that cause the organic made for this compounds that encapsulate the maintenance subcomponent contactor to degrade. This could shorten life and lead to coil burnout.
Dust, dirt, and foreign material can lead to Not stated Various No specific Not stated 4*15,5-17 26 coil burnout, pitting of contact surfaces, recommendations program for and breakdown of adhesives and made for this lubricants. They can also prevent the maintenance subcomponent contact from closing. All the above can cause the relay to fail.
Wear can lead to setpoint drift, Not stated Various No specific Not stated 4*17,5-17 27 mechanical fatigue, surface burning recommendations program for caused by arcing, and insulation made for this deterioration. These can result in reduced maintenance subcomponent mechanical tolerances, jamming and binding of moving parts.
Operation of the relay and non-seismic Not stated Various No specific Not stated 4-17,5-17 28 vibration cause loose connections.
recommendations program for Oxidation or contamination of contact made for this surfaces and sharp bends in wiring near maintenance subcomponent terminations can cause high resistance connections. These can cause excessive heating or fire.
Inductive voltage surges resulting from Not stated Various No specific Not stated 4-18,5-17 29 current interruptions can stress the relay recommendations program for coil. The inductive surge may cause coil made for this dielectric breakdown at the weak points in maintenance subcomponent the insulation, which can rapidly lead to insulation failure.
Ohmic heating and breaker internal Not stated Various No specific Not stated 4-18,5-17 30 ambient conditions cause elevated recommendations program for temperatures which lead to winding made for this insulation degradation. This can produce maintenance subcomponent shorted transformer winding, resulting in faulty voltage/current transformation or open circuit conditions.
Primary or secondary winding failure can Not stated Various No specific Not stated 4-18,5-17 31 result from continuous use for extended recommendations program for periods or from excessive current drawn made for this through the winding from attached control maintenance subcomponent power loads.
Non-seismic vibration can cause loose Not stated Various No specific Not stated 4-18,5-17 32 connections. oxidation or contamination of recommendations program for contact surfaces and sharp bends in made for this wiring near terminations can cause high maintenance subcomponent resistance connections. These can cause excessive heating or fire.
Operation of motor control center Not stated Various No specific Not stated 4-19,5-17 33 components and non-seismic vibration recommendations program for cause loose connections. Oxidation or made for this contamination of surfaces and sharp maintenance subcomponent bends in wiring near terminations cause high resistance connections. These can lead to heating or fire.
Terminal blocks and the organic glue or Not* stated Various No specific Not stated 4-19,5-17 34 agent used to mount them may degrade recommendations program for because of ohmic heating, ambient made for this temperature, humidity and vibration. This maintenance subcomponent can result in embrittlement of the terminal blocks and loosening from their mounting surfaces.
Table A.2 Gall Report for NPAR Reports Page 50A Document: SAND93*7069, Aging Management Guideline for Commercial Nuclear Power Plants* Notor Control Centers Reviewed by:
K. D. McCarthy, INEL It S
Str tu eJC S b t
Mil M
ARD em ;ystem uc r omp u componen ater a s anu acturer h
mec anlsm ARD ff ts eec 35 Motor Control Cente r Terminal Blocks Not stated GE, Westinghouse,
- EXFORCE, Degradation of C-H, KM MECHSTR terminal block hardware 36 Motor Control Cente Terminal Blocks Not stated GE, Westinghouse, MOIST-EL, Loss of surface C-H, KM CONTAM, ENVIR insulating properties 37 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, MOIST-EL, Loss of volumetric C-H, KM CONTAM, ENVIR insulating properties 38 Motor Control Center Control Wiring Copper wire GE, Westinghouse, ELETEMP, EMBR Insulation insulated by ethylene C-H, KM degradation propylene rubber or X-linked poly 39 Motor Control Center Control Wiring Copper wire GE, Westinghouse, ELETEMP Conductor insulated by ethylene C-H, KM degredation propylene rubber or X-linked poly 40 Motor Control Center Control Wiring Copper wire GE, Westinghouse, VIBR, CORR/OX, Loose or high insulated by ethylene C-H, KM ELETEMP, CONT, resistance elect propylene rubber or EXFORCE connections or X-linked poly terminations 41 Motor Control Center Fuse Not stated GE, Westinghouse, FAT CyClic failure C-H, KM 42 Motor Control Cente Fuse Not stated GE, Westinghouse, CORR/OX, CO NT High resistance C-H, KM contact surfaces 43 Motor Control Center Fuse Not stated GE, Westinghouse,
- ELETEMP, Loose or high C-H, KM CORR/OX, VIBR, resistance elect CONT connections or terminations Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Battery Container Polycarbonate, C&D, GNB, Exide CORR/SCC, Cracks in container styrene acrylonitrile, ELOTEMP, FAT butadiene, styrene 2
Battery Electrolyte Sulfuric acid and C&D, GNB, Exide CONTAM Electrolyte water consumed, water loss
Table A.2 Gall Report for NPAR Reports Page SOB Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers Reviewed by:
K. D. McCarthy, INEL Eff fA -
C R
ecto
~glng on omponent Function Contrib to Failure Reported progs Rel.progs eport Recommen d -
ations P age N lte
- o.
m Terminal block hardware degrades Not stated Various No specific Not stated 4-19,5-17 35 primarily as a result of stresses produced recommendations program for during normal use. Improper made for this maintenance techniques exacerbates this maintenance subcomponent degredation.
Voltage and humidity can affect energized Not stated Various No specific Not stated 4-20,5-17 36 insulation that is dirty or deteriorated and recommendations program for cause surface tracking paths on the made for this insulator. This can lead to flashover.
maintenance subcomponent Simultaneous exposure to thermally Not stated Various No specific Not stated 4-20,5-17 37 deteriorated insulation to temp, voltage, recommendations program for humidity, dirt and contaminants can result made for this in loss of volumetric insulating properties, maintenance sUbcomponent leading to increased surface and volumetric leakage currents and possible flashover.
Insulation degradation can occur with Not stated Various No specific Not stated 4-20,5-17 38 exposure to elevated ambient recommendations program for temperature, ohmic heating of the made for this conductor, and excessive ohmic heating maintenance SUbcomponent that accompanies high resistivity connections.
Conductor degradation may result from Not stated Various No specific Not stated 4-20,5-17 39 bending, pulling, or crimping of the recommendations program for conductor or from localized heating (either made for this from an external heat source or ohmic maintenance subcomponent heating within the wire).
Loose or high resistance connections or Not stated Various No specific Not stated 4-21,5-17 40 terminations may occur from bending or recommendations program for pulling on wire, vibration of components, made for this inadequate torquing of fasteners, or maintenance SUbcomponent oxidation/corrosion/contamination of contact surfaces.
Cyclic fatigue 01 the fuse holder is Not stated Various No specific Not stated 4-21,5-18 41 primarily associated with the installation or recommendations program for removal of fuse elements; usually some made for this sort of frictional arrangement is employed maintenance subcomponent to keep the fuse secure and properly connected.
High resistance contact surfaces may Not stated Various Vendor specific Not stated 4-21,5-18 42 result from corrosion, oxidation, or recommendations programs contamination of the surfaces in contact made for with the fuse element itself. This condition maintenance may result in a loss 01 continuity or increased localized heating.
Loose or high resistance connections or Not stated Various No specific Not stated 4-21,5-18 43 terminations may occur from vibration 01 recommendations program 10r components, inadequate torquing of made for this fasteners, or maintenance subcomponent oxidatiOn/corrosion/contamination of contact surfaces.
Document: SAND93*7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Cracks in container caused by Not stated IEEE Std-450,535, Tech Spec.
Not stated 4-17,21, 1
mishandling during 10CFR surveillance, 25,26 maintenance!installation, seismic events, 50.49,NMAC TA-AG1.129, plate growth and improper use of grease 100248 IEEE 450 or cleaning solvents lead to electrolyte leakage resulting in reduced capacity.
Sulfation caused by undercharging &
Not stated IEEE Std-450,535, Tech Spec.
Not stated 4-23 2
impurities consume electrolyte and results 10CFA surveillance, in reduced capacity.
50.49,NMAC TA-AG1.129, 100248 IEEE 450
Table A.2 Gall Report for NPAR Reports Page 51A Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Item System StructurelComp S b u componen M aterials Manufacturer ARD h
mec anlsm ARD ff ts eec 3
Battery Electrolyte Sulfuric acid and C&D, GNB, Exide GAS, ELETEMP Gassing causes water water loss from electrolyte 4
Battery Plates Lead antimony, lead C&D, GNB, Exide FAT, ELETEMP, Increased calcium, lead MECHSTR mechanical stress on plates 5
Battery Plates Lead antimony, lead C&D, GNB, Exide GAS Active material calcium, lead shedding from plate~
6 Battery Plates Lead antimony, lead C&D, GNB, Exide CORR/OX Increase in battery calcium, lead internal resistance 7
Battery Plates Lead antimony, lead C&D, GNB, Exide CONTAM Local action at plate~
Battery Cell Top Straps Not stated C&D, GNB, Exide CORR/OX Increased battery internal resistance 9
Battery Cell Top Straps Not stated C&D, GNB, Exide FAT Increased mechanical stress on cell top straps 10 Battery Separators Rubber/glass mat, C&D, GNB, Exide Not stated Hydration caused by polyethylene electrolyte low specific gravity 11 Battery Separators Rubber/glass mat, C&D, GNB, Exide ELETEMP Thermal aging polyethylene caused by excessive electrolyte temperature 12 Battery Terminal Posts Lead alloy, copper C&D, GNB, Exide CORR High connection inserts resistance and embrittlement of material 13 Battery Terminal Posts Lead alloy, copper C&D, GNB, Exide FAT Cracked or broken inserts terminal posts
Table A.2 Gall Report for NPAR Reports Page 518 Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Comp_onent Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Gassing and electrolyte evaporation occur Not stated IEEE Std-Tech Spec.
Not stated 4-23 3
from overcharging and excessive 450,535,10 CFR surveillance, temperatures. Gassing and evaporation 50.49, NMAC TR-RG1.129, main cause of water loss in electrolyte.
100248 IEEE 450 Results in reduced capacity.
Repeated the~mal and mechanical Not stated IEEE Std-Tech Spec.
Not stated 4-22 4
stresses from battery charge/discharge 450,535,10 CFR Surveillance, cycles and seismic events can cause loss 50.49, NMAC TR-IEEE 450-1987 of active material or loss of electricai 100248 continuity, resulting in reduced battery capacity or total loss of battery output.
Active material shedding from plates Not stated IEEE Std-Tech Spec.
Not stated 4-23 5
results in sediment buildup at the bottom 450,535,10 CFR Surveillance, of cell. this can cause short circuits 50.49, NMAC TR-IEEE 450-1987 between the positive and negative plates, 100248 resulting in reduced capacity and eventually the inability to hold a charge.
Corrosion caused by oxidizing Not stated IEEE Std-Tech Spec.
Not stated 4-22 6
environment that exists at the positive 450,535,10 CFR Surveillance, plates. Plates become brittle and break 50.49, NMAC TR-IEEE 450-1987 down, decreasing their cross sectional 100248 area and increasing resistance. This leads to seismic vulnerability and decreased battery capacity.
Electrochemicai reactions due to Not stated IEEE Std-Tech Spec.
Not stated 4-21 7
impurities in the electrolyte cause local 450,535,10 CFR Surveillance, action at the plates resulting in decreased 50.49, NMAC TR-IEEE 450-1987 battery capacity and potential 100248 overcharging of the positive plates.
Corrosion caused by oxidizing Not stated IEEE Std-Tech Spec.
Not stated 4-22 8
environment that exists at the positive 450,535,10 CFR Surveillance, plates. Straps become britUe and break 50.49, NMAC TR-IEEE 450-1987 down, decreasing their cross sectional 100248 area and increasing resistance. This leads to seismic vulnerability and decreased battery capacity.
Repeated thermal and mechanicai Not stated IEEE Std-Tech Spec.
Not stated 4-22 9
stresses from battery charge/discharge 450,535,10 CFR Surveillance, cycles and seismic events can cause 50.49, NMAC TR-IEEE 450-1987 fatigue failure. This can cause loss of 100248 electrical continuity, resulting in reduced battery capacity or total loss of output.
Hydration causes material chemical Not stated IEEE Std-No program Not stated 4-21 10 changes in separators. Formation of 450,535,10 CFR specific to this metallic lead on surface of separators 50.49, NMAC TR-material builds numerous short circuit paths 100248 between pos & neg plates, resulting in inability to hold charge.
Excessive electrolyte temp caused by Not stated IEEE Std-No program Not stated 4-23 11 overcharging or excessive ac ripple on the 450,535,10 CFR specific to this charger output reduces dielectric strength 50.49, NMAC TR-material of separator mat'l and causes structural 100248 deterioration, resulting in reduced battery capacity or inability to hold charge.
High connection resistance and Not stated IEEE Std-Tech. Spec.
Not stated 4-22 12 embritUement of material in terminal posts 450,535,10 CFR surveillance, results in decreased battery output and 50.49, NMAC TR-IEEE 450-1987 overheating of the posts.
100248 Repeated or improper torquing of Not stated IEEE Std-Tech. Spec.
Not stated 4-22 13 connections during instal/maint can result 450,535,10 CFR surveillance, in cracked or broken terminal posts. This 50.49, NMAC TR-IEEE 450-1987 results in increased connection resistance 100248 or loss of electrical continuity, resulting in reduced capacity or loss of battery output.
Table A.2 Gall Report for NPAR Reports Page 52A Document: SAN 093*7071, Aging Management Guideline for Commercial Nuclear Power Plants* Stationary Batteries Reviewed by:
K D. McCarthy, INEL Item S
~c Sb
- ystem Structur omp u com~onent Materials Manufacturer h
i ARDmec ansm ARD effects 14 Battery Terminal Posts Lead alloy, copper C&D, GNB, Exide CORR Fouling of terminal inserts posts 15 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide CORR High connection bars resistance, embrittlement 16 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide FAT Cracked or broken bars intercell connectors 17 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide CORR Fouling of intercell bars connectors 18 Battery Terminal Post Seals Not stated C&D, GNB, Exide FAT Cracking of the terminal post seals 19 Battery Battery Racks Steel Not stated CORR, FAT Rack structure weakened 20 Battery Container Polypropylene C&D, GNB, Exide CORR/SCC, FAT Cracks in container 21 Battery Container Polypropylene C&D, GNB, Exide FAT Fatigue cracking of cover 22 Battery Electrolyte Potassium C&D, GNB, Exide Not stated Decreased Hydroxide conductivity of electrolyte 23 Battery Electrolyte Potassium C&D, GNB, Exide GAS Gassing causes Hydroxide water loss from electrolyte 24 Battery Plates Nickel hydroxide, C&D, GNB, Exide Not stated Aging of active cadmium hydorxide material
Table A.2 Gall Report for NPAR Reports Page 528 Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem Fouling of terminal posts can occur due to Not stated IEEE Std-Tech. Spec.
Not stated 4-24 14 accumulation of dirt, dust, and leaked 450,535,10 CFR surveillance, electrolyte. This can cause corrosion at 50.49, NMAC TR-IEEE 450-1987 the electrical connections, short circuits, 100248 and battery grounding, resulting in degraded battery output, discharge or overheating.
Excessive ambient humidity, external dust Not stated IEEE Std-Tech. Spec.
Not stated 4-22 15 and dirt, electrolyte leaks and spills can 450,535,10 CFR surveillance, cause corrosion of connectors. This 50.49, NMAC TR-IEEE 450-1987 results in high connection resistance and 100248 embrittlement resulting in decreased battery output and overheating of connectors.
Repeated or improper torquing of Not stated IEEE Std-Tech. Spec.
Not stated 4-22 16 connections during instailimaint can result 450,535,10 CFR surveillance, in cracked or broken intercell connectors.
50.49, NMAC TR-IEEE 450-1987 This results in increased connection 100248 resistance or loss of elec continUity, resulting in reduced capacity or loss of battery output.
Fouling of intercell connectors can occur Not stated IEEE Std-Tech. Spec.
Not stated 4-24 17 due to accumulation of dirt, dust, and 450,535,10 CFR surveillance, leaked electrolyte. This can cause 50.49, NMAC TR-IEEE 450-1987 corrosion at the electrical connections, 100248 short circuits, and battery grounding, resulting in degraded outpu~ discharge or overheating.
Fatigue failures can occur in post seals Not stated IEEE Std-Tech. Spec.
Not stated 4-23 18 due to improper handling, plate growth, 450,535,10 CFR surveillance, excessive corrosion which stresses the 50.49, NMAC TR-IEEE 450-1987 seals and covers. This can cause a loss 100248 of electrolyte and venting of gases, resulting in reduced capacity or loss of output..
Electrolyte leaks or spills, humidity and Not stated IEEE Std-Tech. Spec.
Not stated 4-22 19 high temp can cause corrosion of battery 450,535,10 CFR surveillance, rack which can weaken the structure.
50.49, NMAC TR-IEEE 450-1987 This can cause structural failure and loss 100248 of supported battery.
Damage to container is caused by Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-25 20 improper use of greases and cleaning CFR 50.49,EPRI surveillance, solvents which react with container NMAC TR-10248 IEEE 1106-material or weaken the structure. This 1987 can lead to reduced capacity.
Thermal expansion and improper handling Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-25 21 introduce stresses to container cover CFR 50.49,EPRI surveillance, which can cause cracking. This can result NMAC TR-1 0248 IEEE 1106-in gas release, possible air intrussion, and 1987 loss of electrolyte which may result in conductive paths to ground and loss of capacity.
Material chemical changes occur due to Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-24 22 carbonation of potassium hydroxide CFR 50.49,EPRI surveillance, electrolyte when exposed to carbon NMAC TR-10248 none for this dioxide in air, which decreases compo conductivity of electrolyte. This increases battery internal resistance and decreases capacity.
Gassing & electrolyte evaporation is due Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-26 23 to overcharging and elevated temp.
CFR 50.49,EPRI surveillance, These ca'use electrolyte water loss, which NMAC TR-1 0248 IEEE 1106-will reduce battery capacity. Evaporation 1987 also contributes to water loss.
Recrystallization of the nickel hydroxide in Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-24 24 the positive plates causes gradual aging CFR 50.49,EPRI surveillance, of the active material. This results in NMAC TR-1 0248 none for this reduced capacity.
compo
Table A.2 Gall Report for NPAR Reports Page 53A Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARC mechanism ARC effects 25 Battery Separators Plastic C&D, GNB, Exide ELETEMP Reduced delectric strength of separator material 26 Battery Terminal Posts Not stated C&D, GNB, Exide CORR Failure of terminal posts 27 Battery Terminal Posts Not stated C&D, GNB, Exide FAT Cracked or broken terminal posts 28 Battery Terminal Posts Not stated C&D, GNB, Exide CORR Corrosion, short ckts and grounding caused by fouling 29 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide CORR Failure of intercell bars with stainless connectors steel hardware 30 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide FAT Cracked or broken bars with stainless intercell connectors steel hardware 31 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide CORR Corrosion, short bars with stainless ckts, grounding steel hardware caused by fouling 32 Battery Terminal Post Seals Not stated C&D, GNB, Exide FAT Fatigue cracking of postseais 33 Battery Battery Racks Steel Not stated CORR, FAT Rack structure weakened 34 Battery Pressure Relier Not stated Not stated Not stated Malfunction of valve Valve 35 Battery Electrolyte Not stated Not stated Not stated Dryout of electrolyte 36 Battery Electrolyte Not stated Not stated ELETEMP Thermal runaway
Table A.2 Gall Report for NPAR Reports Page 538 Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem Overcharging or excessive ac ripple on Not stated IEEE Std-1106,10 No program Not stated 4-26 25 charger output cause excessive CFR 50.49,EPRI specific to this electrolyte temp which reduces the NMAC TR-10248 subcomponent dielectric strength of separator mat'I &
deteriorates mech strength. This results in reduced capacity & eventual inability to hold charge.
Humidity, dust, and elevated temperatures Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4*25 26 can lead to corrosion of the terminal CFR 50.49,EPRI required posts. This can lead to failure of terminal NMAC TR-10248 surveillance.
posts.
IEEE 1106 Repeated or improper torquing of Not stated IEEE Std-1106,10 Tech. Spec.
Not stated 2-25 27 connections can result in cracked or CFR 50.49,EPRI required broken terminal posts. This results in NMAC TR-10248 surveillance.
increased connection resistance or loss of IEEE 1106 continuity. This results in reduced capacity or total loss of output.
Fouling of terminal posts caused by Not stated IEEE Std-1106, 10 Tech. Spec; Not stated 4-24 28 accumulation of dirt, dust, and leaked CFR 50.49,EPRI required electrolyte can cause corrosion, short NMAC TR-1 0248 surveillance.
circuits between pos and neg posts, and IEEE 1106 battery grounding. This results in degraded output, batt discharge, or overheating of connections.
Humidity, dust, and temperature can lead Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-25 29 to corrosion of intercell connectors. This CFR 50.49,EPRI required can lead to failure of the intercell NMAC TR-1 0248 surveillance.
connectors.
IEEE 1106 Repeated or improper torquing of Not stated IEEE Std-1106,10 Tech. Spec.
Not stated 4-25 30 connections can result in cracked or CFR 50.49,EPRI required broken intercell connectors. This results NMAC TR-1 0248 surveillance.
in increased connection resistance or loss IEEE 1106 of continuity which reduces battery capacity or results in total loss of battery output.
Dirt, dust, and leaked electrolyte cause Not stated IEEE Std-1106, 10 Tech. Spec.
Not stated 4-26 31 fouling of intercell connectors. fouling CFR 50.49,EPRI required coupled with moisture condensation leads NMAC TR-10248 surveillance.
to corrosion, which causes current paths IEEE 1106 to ground. This results in degraded batt output, discharge or overheating of connections.
Excessive stresses caused by thermal Not stated IEEE Std-1106,10 Tech. Spec.
Not stated 4-25 32 expansion, corrosion of terminal posts, CFR 50.49,EPRI required and improper handling can lead to fatigue NMAC TR-10248 surveillance.
cracking of terminal post seals, leading to IEEE 1106 gas release, air intrusion, loss of electrolyte. Results in conductive paths to ground.
Humidity, dust accumulation, and Not stated IEEE Std-1106,10 IEEE 1106-Not stated 4-25 33 temperature can lead to corrosion in the CFR 50.49,EPRI 1987 battery racks. This can cause structural NMAC TR-10248 failure and loss of supported battery.
Wear occurs due to relative movement Not stated IEEE Std-1106, 10 No program Not stated 4-27 34 between contacting intemal parts and can CFR 50.49,EPRI specific to this cause malfunction of valve. This can NMAC TR-1 0248 subcomponent allow gases and vapors to escape, resulting in lowered gas re.combination efficiency. This can lead to dryout.
Overcharging, elevated temperatures, Not stated IEEE PAR 1188, 10 Tech. Spec.
Not stated 4-27 35 failed pressure relief valve or cracked CFR 50.49, NMAC surveillance, container or seal can lead to dryout of TR-100248 IEEE 450&
electrolyte. This can result in battery 1106 failure.
Elevated temperature, improper (high)
Not stated IEEE PAR 1188, 10 Tech. Spec.
Not stated 4-28 36 float voltage, or excessive ac ripple from CFR 50.49, NMAC surveillance, battery charger can cause thermal TR-100248 IEEE 450-1987 runaway. This can result in battery failure.
Table A.2 Gall Report for NPAR Reports Page 54A Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries Reviewed by:
K. D. McCarthy, INEL.
Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism AR Deffects 37 Battery Electrolyte Not stated Not stated Not stated Memory effect Document: TIRGALEX, Plan for Integration of Aging and Ufe-Extension Activities Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Cable Not stated Not stated Not stated ELETEMP, RAD, Not stated MOIST-EL, & VIB.
2 Conectors Not stated Not stated Not stated ELETEMP, RAD, Not stated MOIST-EL, & VIB.
3 Switchgear Not stated Not stated Not stated WEAR & LOSLUB Not stated 4
Relays Not stated Not stated Not stated CORR, WEAR, &
Not stated ELETEMP Document: WYLE 60103-1, Test Plan of Molded Case Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plar Reviewed by:
L. C. Meyer, INEL Item System Structure/Com p Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Molded Case Circuit 5 Relay Types and 3 Not stated Three mfg. listed Not stated Not stated Breakers Types of Circuit Breakers Document: WYLE 60103-2, Test Plan of Metal Clad Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for ---- NPAR Pre Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1
Metal Clad Circuit Not stated Not stated GE & Westinghouse Not stated Not stated Breakers Document: WYLE 60103-3, Test Plan of Auxiliary Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- (NPAR) Program PhasE Reviewed by:
L. C. Meyer, INEL 1St Str tu e/C b
t M
tem iYS em uc r omp Su componen atenals Manufacturer ARD mechanism ARDeffects 1
Auxiliary Relays Not stated Not stated Westinghouse Not stated Not stated Document: WYLE 60103-4, Test Plan of Control Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for ---- (NPAR) Program, Pha~
Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Materials Manufacturer ARD mechanism ARDeffects 1
Control Relays Not stated Three mfg.s listed Not stated Not stated Document: WYLE 60103-5, Test Plan of Protective Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Rese Reviewed by:
L. C. Meyer, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism ARD effects Not stated GE & Westinghouse Not stated Not stated
Table A.2 Gall Report for NPAR Reports Page S4B Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants* Stationary Batteries Reviewed by:
K D. McCarthy, INEL Eff ect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Successive small discharge cycles can Not stated IEEE PAR 1188, 10 Tech. Spec.
Not stated 4-28 37 lead to a memory effect in a sintered plate CFR 50.49, NMAC surveillance, nickel-cadmium battery. This can result TR-100248 IEEE 450-1987 in reduced capacity.
Document: TIRGALEX, Plan for Integration of Aging and Ufe-Extension Activities Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated Not stated IBE79-01, NUREG-No specific Five recommendations are given for A31-A36 1
0588, 10CFR 50.49, program resoMng aging and life extension
& RG 1.89 issues [4]
Not stated Not stated IBE79-01, NUREG-No specific Five recommendations are given for A31-A36 2
0588, 10CFR 50.49, program resoMng aging and life extension
& RG 1.89 issues [1]
Not stated Not stated Generic Letter 83-28 IEEE 741-1986 Three issues requiring followup are AS1 &
3 concerns and Tech Section 7 listed. [1]
AS3 Specs Not stated Not stated Generic Letter 83-28 Dependent Followup on calibration frequency for AS2&
4 concerns and Tech upon type and protective relays, seismic fragility, AS3 Specs function of the and effect of common mode failure relay on safety [1]
Document: WYLE 60103-1, Test Plan of Molded Case Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Planl Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated Not stated Not discussed in No specific Not stated 1-1 1
report
- program, application dependent Document: WYLE 60103-2, Test Plan of Metal Clad Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- NPAR Pro!
Reviewed by:
L. C. Meyer, INEL Eff t fA*
C t F ti C
tr'b t F *1 R
rted R I R
rt R d ti P
N lte eco 'g'"g on omponen unc on on I 0
al ure epo progs e.progs epo ecommen a ons age o.
m Not stated Not stated Not discussed in RG 1.118, Not stated 4-1 1
report IEEE 338-1987, TECH.
SPEC. MAl NT.
Document: WYLE 60103-3, Test Plan of Auxiliary Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- (NPAR) Program Phase Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not stated Not stated Not discussed in Dependent Not stated 1-1, 1-2, 1
report upon
&4-1 application, Tech. Spec.
maint Document: WYLE 60103-4, Test Plan of Control Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for.:..--- (NPAR) Program, Phas Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Not stated Not stated Reported progs Not discussed in report Rel.progs Report Recommendations No specific Not stated program
Table A.2 Gall Report for NPAR Reports Page 55A Document: WYLE 60103-6, Test Plan of Timing Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Reseal Reviewed by:
L. C. Meyer, INEL I
S Str tu e/C S b M
0 tem >ystem uc r omp u componen ateria s Manufacturer ARD mechanism AR effects 1
Timing Relays Not stated Not stated Agastat OXIDAT Degradation caused by oxidation surface Document: WYLE 60103*7, Test Plan of Electronic Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Res Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 1
Electronic Relays Not stated Not stated Basler Not stated Not stated
Table A.2 Gall Report for NPAR Reports Page 558 Document: WYLE 60103-6, Test Plan of Timing Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Researc Reviewed by:
L. C. Meyer, INEL Eff ect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. tem Relay failure due to contact oxidation Occasional Not discussed in Application Not stated 4-1 1
caused by low current application of silVer report dependent, alloy contacts.
Tech Spec Surveil!.
Document: WYLE 60103-7, Test Plan of Electronic Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Rese Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Not stated Not stated Not discussed in Application Not stated 4-1 1
report dependent, likely no program
Table A.2 Gall Report for NRC Generic Letters Page 1A Document: GL 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors Reviewed by:
E. W. Roberts, INEL Item S S
e/C Sb M"I M
AR iystem tructur omp u componen aterlas anufacturer h
Dmee an Ism A RD "
e eets 1 Not stated Not stated Solenoid Operated Not stated Not stated Not stated Not stated Valves
Table A.2 Gall Report for NRC Generic Letters Page 18 Document: GL 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors Reviewed by:
E. W. Roberts, INEL Eft t fA*
C F
C*b Flied R I R
rt R eco 'glng on om~onent unction ontrl to a ure Report progs e.progs epo d ti ecommen a ons P age N lte
- o.
m Reference to case report study NUREG-Not stated Not discussed in Vendor specific Review info and consider actions as 1
1275, volume 6, 'Operating Experience report program appropriate [4]
Feedback Report-Solenoid-Operated Valve Problems,' February 1991
Table A.2 Gall Report for Information Notices Page 1A Document: IN NO. 89-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil, and Lube Oil Systems Which Render Emergency Diesel Generators Inoperat Reviewed by:
E. W. Roberts, INEL I
S Str e/C S b M
. I ARD h*
RD ff tern
>ystem uctur om~
u component atefla s Manufacturer mec amsm A
e ects 1 Emergency diesel Small Diameter Stainless Steel Not stated generators Tubing Document: I N NO. 89-17, Contamination and Degradation of Safety-Related Battery Cells ReViewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer 2
Battery Cells Copper Connections Document: IN NO. 89-20, Weld Failures in A Pump of Byron-Jackson Design Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials 3
Pump Welds Not stated Document: IN NO. 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp 4
Subcomponent Pressure Transmitters Materials Not stated Not stated Manufacturer Byron Jackson Manufacturer Rosemount VIBR Cracks, breaks, &
holes in tubing ARD mechanism ARD effects CONTAM Electrolytic transfer of copper to battery lead term/plates ARD mechanism ARDeffects VIBR Weld cracks ARD mechanism ARD effects Not stated Loss of oil from sensing module Docu!1lent: IN NO. 89-43, Permanent Deformation of Torque Switch Helical Springs in Umitorque SMA-Type Motor Operators Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials 5
Torque Switch Helical Springs Not stated Document: IN NO. 89-64, Electrical Bus Bas Failures Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials 6
Electrical Bus Noryllnsulation Not stated Document: IN NO. 89-66, Qualification Ute of Solenoid Valves Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials 7
Duel-Coil Solenoid Elastomer Seat Ethylene Propylene Valve Dimer (EPDM)
Document: IN NO. 89-79, Degraded Coatings and Corrosion of Steel Containment Vessels Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent 8
Containment Coatings Vessels Materials Not stated Manufacturer ARD mechanism Umitorque MECHSTR Manufacturer ARD mechanism Not stated CONTAM EMBR Manufacturer ARD mechanism Automatic Switch CONTAM Co.
ELETEMP Manufacturer ARD mechanism Not stated MOIST-EL Document: IN NO. 89-84, Failure of Ingersoll Rand Air Start Motors as A Result of Pinion Gear Assembly Fitting Problems RevieWed by:
E. W. Roberts, INEL ARDeffects Permnent deformation of helical spring ARDeffects Electrical ground fault, short to ground ARDeffects Sticky and deformed seats ARDeffects Coating failure Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 9 Diesel Generator Air Starter Pinion Tang and Retainer Not stated Ingersol\\ Rand WEARVIBR Cracking ot retainer Gear Bolts ring and loosening 0 bolts
Table A.2 Gall Report for Information Notices Page 18 Document: IN NO. 89-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil, and Lube Oil Systems Which Render Emergency Diesel Generators Inoperam, Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Rep_orted progs Rel.progs Report Recommendations In operability of EDG Not stated Not discussed in.
Vendor Review info and take actions as report specific, RG appropriate. [4]
1.108,IEEE 387, IEEE 749 Document: IN NO. 89-17, Contamination and Degradation of Safety-Related Battery Cells Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Loss of battery capacity Not stated Tech. spec requires exam, clean, & test connections Document: IN NO. 89-20, Weld Failures in A Pump of Byron-Jackson Design Reviewed by:
E. W. Roberts, INEL Eff fA ecto 'ging on Component Function Contrib to Failure Reported progs Broken ring and impeller - fasteners in Not stated Not discussed in recirculation loop report Document: IN NO. 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters Reviewed by:
E. W. Roberts, INEL.
Effect of Aging on Component Function Contrib to Failure Transmitter failure Not stated Reported progs Not discussed in report Tech. Spec.,
Review info and take actions as RG1.129, appropriate [4]
IEEE 450-1987 Rel.progs R eport R d.
ecommen ations Vendor Review info and take actions as specific, may appropriate [4]
have Tech.
Spec. surveil Rel.progs Report Recommendations Bul9o.1 Suppl. Review info and take actions as 1
appropriate [4]
Document: IN NO. 89-43, Permanent Deformation of Torque Switch Helical Springs in Limitorque SMA-Type Motor Operators Reviewed by:
E. W. Roberts, INEL Effect of Aging on Com~onent Function contrib to Failure Reported progs Rel.progs Report Recommendations Operability problem with valve motor Not stated Not discussed in Vendor Not stated operator report
- specific, NUREG-1352 Document: IN NO. 89-64, Electrical Bus Bas Failures Reviewed by:
E. W. Roberts, INEL
. f Effect 0 Aging on Component Function Contrib to Failure Reported progs Rel.progs Report R ecommendations Inoperable electrical bus Not stated Not discussed in IEEE 338-Review info and take actions as report 1987, RG appropriate [4]
1.118,IEEE 741-1986 Document: IN NO. 89-66, Qualification Life of Solenoid Valves Reviewed by:
E. W. Roberts, INEL Eff t fA*
C F
C F II R
eco,glng on omponent unction ontrib to a ure ed eport progs RI el.progs R eport R d ti ecommen a ons Valves fail to operate as required Frequent Not discussed in Application Review info and take actions as report dependent, appropriate [4]
may have Tech Spec req Document: IN NO. 89-79, Degraded Coatings and Corrosion of Steel Containment Vessels Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Oxidation and pitting of steel tanks Not stated Reported progs Not discussed in report Rel.progs Re ort Recommendations Vendor specific Review info for applicability and take actions as appropriate [4]
Document: IN NO. 89-84, Failure of Ingersoll Rand Air Start Motors as A Result of Pinion Gear Assembly Rtting Problems Reviewed by:
E. W. Roberts, INEL Eff t fA*
eco glng on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Diesel generators would not start Frequent Not discussed in RG 1.108,IEEE Review info and consider actions as report 387,IEEE appropriate [4]
749,Tech.
Spec. maint.
Page No. Item 1
PageNo Item 2
P age N It
- o.
em 3
Page No. Item 5
P age N It 0;
em 6
P age N lte
- o.
m 7
Page No. Item 9
Table A.2 Gall Report for Information Notices Page 2A Document: IN NO. 90-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and AK Circuit Breakers Reviewed by:
E. W. Roberts, INEL 1St Str tu e/C S b M t. I M
RD tem >ys em uc r omp u componen a erla s anu acturer A
h.
mec anlsm ARD effects 10 Circuit Breakers Prop Reset Spring Not stated General Electric FAT Broken spring Document: IN NO. 90-51, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 11 Emergency Diesel Governor Control Voltage Dropping Not stated Pacific Resistor ENVIR ELTEMP Loss of resistance Generator Power Supply Resistor value Document: IN NO. 90-51-01, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcom~onent Materials Manufacturer ARD mechanism ARDeffects 12 Emergency Diesel Governor Control Voltage Dropping Not stated Not stated CURSTR&
Loss of resistance Generator Power Supply Resistor ELETEMP value Document: IN NO. 90-80, Sand Intrusion Resulting in Two Diesel Generators Becoming Inoperable Reviewed by:
E. W. Roberts, INEL Item S S
tu e/C S b M t 'I M
>ystem truc r omp u componen a erla s anu acturer AR D h
mec amsm ARD effects 13 Diesel Generatrors Cylinders Liners and Piston Not stated Not stated CONTAM ADH Scoring of liners and Rings piston rings Document: IN NO. 91-20, Electric Wire Insulation Degradation Caused Failure in A Safety-Related Motor Control Center Reviewed by:
E. W. Roberts, INEL ISS e/C S b M t 'I M
ARD tem >ystem tructur omp u componen a erlas anu acturer h '
mec amsm ARD effects 14 Motor Control Center Wire PCV - Vegatable oil Not stated ELTEMP Cond cover emits plasticierR liquid which hardens on electrical contact Document: IN NO. 91-45, Possible Malfunction of Westinghouse ARD, BFD, and NBFD Relays, and A200 DC and DPC 250 Magnetic Contactors Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 15 Relays Coils Epoxy Westinghouse ELTEMP Document: IN NO. 91-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems Reviewed by:
E. W. Roberts, INEL Item S t S
e/C b
Mt'l M
>ys em tructur omp su componen aerlas anu aCturer AR D mechanism 16 Diesel Generators Filters and Injectors Not stated Not stated CON~AM Document: IN NO. 91-62, Diesel Enging Damage Caused by Hydraulic Lockup Resulting From Fluid Leakage Into Cylinders Reviewed by:
E. W. Roberts, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism Diesel Engine Not stated Not stated Not stated Document: IN NO. 91-78, Status Indication of Control Power for Circuit Breakers Used in Safety, Related Applications Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism 18 Indicator Lights Fuse Holders Not stated Not stated FAT Epoxy becomes fluid when coil is energized for ext.
period A RD effects Excessive particulate, fouled filters and injectors ARDeffects Water leaks into cylinder ARDeffects Fuse holder fingers deformed resulting ir poor elect contact
Table A.2 Gall Report for Information Notices Page 28 Document: I N NO. 90-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and AK Circuit Breakers Reviewed by:
E. W. Roberts, INEL Eft fA*
ecto Igmg on Component Function Contrib to Failure Reported progs Rel.progs d.
Report Recommen ations Page N o. tem Breaker would attempt to close but would Frequent Not discussed in RG 1.108,IEEE Review info and consider actions as 10 trip free report 387,IEEE appropriate [4]
749,Tech.
Spec. maint Document: IN NO. 90-51, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems Reviewed by:
E. W. Roberts, INEL Eftect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item Edg loses speed control Frequent Scheduled RG 1.108, Review info and consider actions if 11 Replacement IEEE 387, applicable [4]
IEEE 749 Document: IN NO. 90-51-01, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems Reviewed by:
L. C. Meyer, INEL Eft fA*
R R
ecto Igmg on Component Function Contrib to Failure Reported progs Rel.progs eport d.
ecommen ations P age N lte
- o.
m Failure of resistor leads to governor power Frequent - old; Rare Scheduled RG 1.108, Review info and consider actions if 1&2 12 supply. Failure in original design. resistor
-new Replacement IEEE 387, applicable [41 failure in new replacement assembly IEEE 749 results in a backup mechanical governor taking control of speed.
Document: IN NO. 90-80, Sand Intrusion Resulting in Two Diesel Generators Becoming Inoperable Reviewed by:
E. W. Roberts, INEL Eft fA*
ecto Igmg on Component Function Contrib to Failure Reported ])!ogs Rel.progs R
d.
eport Recommen ations P age N It
- o.
em Inoperable diesel generators -
Not stated Not discussed in No specific Review info and consider actions if 13 maintenance activity introduced sand into report program applicable [4]
diesel cylinders Document: IN NO. 91-20, Electric Wire Insulation Degradation caused Failure in A Safety-Related Motor Control Center Reviewed by:
E. W. Roberts, INEL Eft t fA*
C F
ti C
- b F*I R
rted R I R
rt R eco,gmg on omponent unc on ontrl to al ure epo progs e.progs epo d ti ecommen a ons P age N It
- o.
em Insulates electrical contacts Not stated Not discussed in No specific Review info and consider actions as 14 report program appropriate [4]
Document: IN NO. 91-45, Possible Malfunction of Westinghouse ARD, BFD, and NBFD Relays, and A200 DC and DPC 250 Magnetic Contactors Reviewed by:
E. W. Roberts, INEL Eftect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Degrades or delays relay function Not stated Not discussed in No specific report program Document: IN NO. 91-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems Reviewed by:
E. W. Roberts, INEL Eft fA*
ecto 'glng on Component Function Contrib to Failure Reported progs Rel.progs Inoperable diesel generator Not stated Not discussed in No specific report program Review info and consider actions if applicable [4]
Report Recommendations Review info and consider actions as appropriate [41 Review info and consider actions as appropriate [4]
Document: IN NO. 91-78, Status Indication of Control Power for Circuit Breakers Used in Safety-Related Applications Reviewed by:
E. W. Roberts, INEL Eftect of Aging on Component Function Contrib to Failure Re~orted progs Rel.progs Report Recommendations Improper indication of motor operation Not stated Not discussed in Vendor specific Review info and consider actions as report program appropriate [4]
15 Page No. Item 16 Page No. Item 18
Table A.2 Gall Report for Information Notices Document: IN NO. 91-81, Switchyard Problems That Contribute to Loss of Offsite Power Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials 19 Swithcyard Control Zener Diodes Not stated System Document: IN NO. 91-83, Solenoid-Operated Valve Failures Resulted in Turbing Overspeed Reviewed by:
E. W. Roberts, INEL Item S stem Structure/Com Materials Not stated Manufacturer ARD mechanism Not stated VOLSTR Manufacturer ARD mechanism Parker Hannifin Not stated Page 3A ARDeffects Zenor diode failure ARDeffects Pilot valve assy mechanically bound Document: IN NO. 91-85, Potential Failures of Thermostatic Control Valves for Diesel Generator Jacket Cooling Water Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 21 Diesel Generator Cooling Water Thermostatic Control Not stated Not stated Not stated Valve failure System Valve Document: IN NO. 91-87, Hydrogen Embrittlement of Raychem Cryofit Couplings Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 22 Gas Space Cryofit Coupling Tinel (50% Titanium Raychem EMBRIHY &
Circumferential SamplingUne and 50% Nickel)
ELETEMP fracture at the midpoint of coupling Document: IN NO. 92-04, Potter & Brumfield Model MDR Rotary Relay Failures Reviewed by:
E. W. Roberts, INEL Item System S
tu e/C S b M t - I truc r omp u componen a erla s M
f tu anu ac rer ARD h
mec amsm ARD ff ts eec 23 Rotary Relay Rotor Coil Varnish Potter & Brumfield CORR Deposits on rotor Document: IN NO. 92-27, Thermally Induced Accelerated Aging and Failure of ITE/GOULD A.C. Relaty Used in Safety-Related Applications Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 24 Relay Plastic Armature Not stated ITE/Gould ELETEMP Brittleness and Carrier and Coil cracking Insulation Document: IN NO. 92-44, Problems With Westinghouse OS-206 Type Circuit Breakers Reviewed by:
E. W. Roberts, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism ARO effects 25 Circuit Breaker Not stated Westinghouse FAT Weakened spring Document: IN NO. 92-48, Failure of Exide Batteries Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponen M aterials Manu acturer ARD h
mec anlsm ARD ff ts eec 26 DC Power Battery cells Not stated Exide CORR Cracking of battery face Document: IN NO. 92-78, Piston to Cylinder Uner Tin Smearing On Cooper=Bessemer KSV Diesel Engines Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 27 Diesel Generator Cylinders Walls Not stated Cooper Bessemer CORR Transfer of tin from KSV cyJ. walls and breakdown of lubrication
Table A.2 Gall Report for Information Notices Document: IN NO. 91*81, Switchyard Problems That Contribute to loss of Offsite Power Reviewed by:
E. W. Roberts, INEl E
fA.
ffect 0
~glng on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations loss of switchyard control Not stated Not discussed in RG 1.118, Review info and consider actions as report IEEE 741-1986 appropriate [4J Section 7 Document: IN NO. 91*83, Solenoid-Operated Valve Failures Resulted in Turbing Overspeed Reviewed by:
E. W. Roberts, INEl Effect of A in on Com onent Function Contrib to Failure Not stated Re ort Recommendations Review info and consider actions as appropriate [4J Document: IN NO. 91-85, Potential Failures of Thermostatic Control Valves for Diesel Generator Jacket Cooling Water Reviewed by:
E. W. Roberts, INEl Effect of Aging on Component Function Contrib to Failure Overheating of diesElI generator Not stated Reported progs Not discussed in report Document: IN NO. 91*87, Hydrogen Embrittlement of Raychem Cryofit Couplings Reviewed by:
- l. C. Meyer, INEl Effect of Aging on Component Function Contrib to Failure Reported progs The fractured coupling allowed a reactor Rare Not discussed in coolant system leak that exceded the 1.0 report gpm technical specification limit.
Document: IN NO. 92-04, Potter & Brumfield Model MDR Rotary Relay Failures Reviewed by:
E. W. Roberts, INEl Effect of Aging on Component Function Contrib to Failure Reported progs Mechanical binding of rotor and failure of Not stated Not discussed in relay to operate properly within 2 to 5 report years after installation Rel.progs Report Recommendations Vendor specific Review info and consider actions as program appropriate [4J Rei progs Report Recommendations No specific Not stated program Rel.progs Report Recommendations Vendor specific Review info and consider actions as program applicable [4J Document: IN NO. 92-27, Thermally Induced Accelerated Aging and Failure of ITEIGOUlD A.C. Relaty Used in Safety-Related Applications Reviewed by:
E. W. Roberts, INEl Page 38 Page N o. tem 19 Page No. Item 1&2 22 P
N age o. tem 23 Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Coil shorts and relay fails to operate Not stated Not discussed in Vendor specific report program Document: IN NO. 92*44, Problems With Westinghouse DS*206 Type Circuit Breakers Reviewed by:
E. W. Roberts, INEl Effect of A in on Com onent Function Contrib to Failure Not stated Document: IN NO. 92-48, Failure of Exide Batteries Reviewed by:
E. W. Roberts, INEl Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Leakage of electrolytic and battery cell Not stated Not discussed in RG 1.129, failure report IEEE 450-1987, Tech.
Spec. Surveil.
Review info and consider actions as appropriate [4J Re ort Recommendations Review info and consider action as appropriate [4J Report Recommendations Review info and consider action as applicable [4]
Document: IN NO. 92-78, Piston to Cylinder Uner Tin Smearing On Cooper=Bessemer KSV Diesel Engines Reviewed by:
E. W. Roberts, INEl Eff fA' ect 0 glng on Component Function Contrib to Failure Reported progs Rel.progs d
Report Recommen ations Crankcase explosions and diesel failure Not stated Not discussed in No specific Review info and consider actions as report program appropriate [4]
24 Page No. Item 26 P age N o. tem 27
Table A.2 Gall Report for Information Notices Page 4A Document: IN NO. 93-05, Storm-Related Loss of Offsite Power Events Due to Salt Buildup on Switchyard Insulators Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 28 Switch Yard Insulators Not stated Not stated CONTAM Arcing across salt-lading insulators Document: IN NO. 93-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers due to Support Lever Failure Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 29 Mold-Case Circuit Support Lever Polycarbonate &
K10ckner Moeller Breakers (Spring Arm)
Glass fiber composite Document: IN NO. 93-23, Weschler Instruments Model 252 Switchboard Meters Reviewed by:
E. W.Roberts, INEL Item S stem Structure/Com Materials Manufacturer 30 Indicating Meters Not stated Weschler Document: IN NO. 93-26, Grease Solidification Causes Molded-Case Circuit Breaker Failure to Close Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer 31 Mold-Case Circuit Grease Soap-basad or clay-General Electric Breakers based grease Document: IN NO. 93-33, Potential Deficiency of Certain Class 1 E Instrumentation and Control Cables RevieWed by:
E. W. Roberts, INEL Item System Structure/Comp Materials Manufacturer 32 Not stated Not stated Document: IN NO. 93-64, Periodic Testing and Preventive Maintenance of Modlad Case Circuit Breakers Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer 33 Circuit Breakers Not stated Westinghouse Type EB and EHB Document: IN NO. 94-04, Digital Integrated Circuit Sockets With Intermittent Contact RevieWed by:
E. W. Roberts, INEL Item S stem Structure/Com Materials Manufacturer 34 Digital Board Tin-lead Augat Document: IN NO. 94-33, Capacitor Failures in Westonghouse Easge 21 Plant Protection Systems Reviewed by:
E. W. Roberts, INEL Item System Structure/Comp Subcomponent Materials Manufacturer 35 Westinghouse Eagle ASTEC America DC Electrolytic Epoxy module AVX 21 plant protection Power Supply CapaCitors system CORR FAT Fractured support lever ARD mechanism ARD effects ADH Sticking movement ARD mechanism ENVIR ARD mechanism REFERENCE NUREG/CR-5n2 ARD mechanism Not stated ARDeffects Drying out of grease, friction, gouging of meta/-te-metal ARDeffects Reference nureg/cr-5n2 ARDeffects Thermal and instantaneous trip not within specifications ARD mechanism ARD effects CORR/OX Contact failure ARD mechanism ARD effects ELTEMP CapaCitor failure
Table A.2 Gall Report for Information Notices Document: IN NO. 93-05, Storm-Related Loss of Offsite Power Events Due to Salt Buildup on Switchyard Insulators Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Loss of offsite ac power Not stated Not discussed in IEEE 765-Review info and consider actions as report 1983, Plant appropriate [4]
specific program Document: IN NO. 93-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers due to Support Lever Failure Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Breakers tripped without cause Not stated Not discussed in No specific report program Document: IN NO. 93-23, We schier Instruments Model 252 Switchboard Meters Reviewed by:
E. W. Roberts, INEL Effect of A in on Com onent Function Contrib to Failure Not stated Document: IN NO. 93-26, Grease Solidification Causes Molded-Case Circuit Breaker Failure to Close Reviewed by:
E. W. Roberts, INEL Effect of Aging on Com~onent Function Contrib to Failure Reported progs Rel.progs Breaker fails to close Not stated Not discussed in No specific report program Document: IN NO. 93-33, Potential Deficiency of Certain Class 1E Instrumentation and Control Cables Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs References the result of the NUREG Not stated Not discussed in report to evaluate plant cables report Rel.progs No specific program Review info and consider actions as appropriate [4]
Review info and consider actions as appropriate [4]
Report Recommendations Review info and consider actions as appropriate [4]
Report Recommendations Review info and consider actions as appropriate [4]
Document: IN NO. 93-64, Periodic Testing and Preventive Maintenance of Modlad Case Circuit Breakers Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Age, failure to excercise, and lack of Not stated Not discussed in Vendor specific maintenance caused breakers trips to go report program, Tech.
out of specifications Spec.
Document: IN NO. 94-04, Digital Integrated Circuit Sockets With Intermittent Contact Reviewed by:
E. W. Roberts, INEL Effect of A in on Com onent Function Contrib to Failure Not stated Document: IN NO. 94-33, Capacitor Failures in Westonghouse Easge 21 Plant Protection Systems Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Power supply failure Not stated Not discussed in Vendor specific report program Review info and consider actions as appropriate [4]
Re ort Recommendations Review info and consider action as appropriate [4]
Report Recommendations Review info and consider actions as appropriate [4]
Page 48 Page No. Item 28 Page No. Item 29 Page No. Item 31 PageNo Item 33 Page No. Item 35
Table A.2 Gall Report for Licensee Event Reports Page 1A Document: LER 88-011-282, Auto-5tart of Train A of Auxiliary Building Special Ventilation System as a result of a Radiation Monitor Spike Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 1 Ventilation System Radiation Monitor Not stated Not stated Not stated Not stated Rad monitor spike -
attributed to age of rad mon equipment Document: LER 88-033-02-327, Unplanned Reactor Trip Signal Due to a Reactor Protection System (RPS) Channel 1 Instrument Failure During RPS Channel 2 C Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 2 Reactor Protection Not stated Not stated Not stated Foxboro Not stated Two transistors System shorted and bridge assembly open circuited Document: LER 89-001-280, Unplanned Auto Start of #3 EDG Due to Failed Diode Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 3 Diesel Generator Control Circuit Diode Not stated GM Electro-Motive Not stated Failed diode caused Division start relay to actuate Document: LER 89-002-331, Age-Related Failure of a Governor Printed Circuit Board Results in High Pressure Coolant Injection System Inoperability Reviewed by:
L. C. Meyer,INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 4 High Pressure Turbine Governor Printed Circuit Boarc Not stated Woodward Govemor ELETEMP Intermitant electronic Injection System Component Company componet ou1put Document: LER 89-003-263, Isolation of Reactor Water Cleanup System Due to Capacitor Failure in FilterlDemineralizer Inlet Temperature Indication Switch Reviewed by:
L. C. Meyer, INEL Item System S
eJC S
t M t
- I M
f tu ARD h*
ARD ff ts tructur om~
ubcomponen aenas anu ac rer mec antsm eec 5 RWCU Electronic Circuit Capacitor Not stated Seimans Not stated Capacitor failed Filter Document: LER 89-006-261, Reactor Trip Due to Loss of Turbine E-H Control Power Supplies Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 6 Turbine Control Power Supply Transistor Not stated Solid State Controls CURSTR &
Transistors Inc.
VOLSTR developed leakage current Document: LER 89-010-362, Fuel Handling Isolation System Train 'A' Actuation Due to Power Supply Failure Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent M aterials Manufacturer A RD mechanism ARD ff e ects 7 Fuel Handling Power Supply Regulator Not stated Nuclear Meaurement ELETEMP Nylon screw broken Isolation System Corp.
due to thermal aging
Table A.2 Gall Report for Licensee Event Reports Page 18 Document: LER 88-011-282, Auto-Start of Train A of Auxiliary BUilding Special Ventilation System as a result of a Radiation Monitor Spike Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommen d.
ations P age N o. tem Auto-start of aux building ventilation Not stated 10 CFR 50.73 Vendor specific Not stated 1-3 1
system when not called for. The program electronics was 16 years old. Root cause of spike unknown. rad monitor upgrade pursued.
Document: LER 88-033-02-327, Unplanned Reactor Trip Signal Due to a Reactor Protection System (RPS) Channel 1 Instrument Failure During RPS Channel 2 C Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommen d ations P age N o. tem Failure of a rcs channel 1 delta TfTavg Not stated 10 CFR 50.73 Tech. Spec.
Not stated 1-4 2
loop instrument caused an unplanned surveillance, reactor trip signal. Component aging was RG 1.118, referenced as a possible failure IEEE 338 mechanism.
Document: LER 89-001-280, Unplanned Auto Start of #3 EDG Due to Failed Diode Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item The failure of the diode was attributed to Not stated 10 CFR 50.73 No specific Not stated 1-3 3
normal aging. the start relay iniated the air surveillance for start motors and started the diesel when this component no emergency existed.
Document: LER 89-002-331, Age-Related Failure of a Govemor Printed Circuit Board Results in High Pressure Coolant Injection System Inoperability Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.Jlrogs R eport R d ti ecommen a ons P age o.
em N
It Failure to operate, reason was Rare 10 CFR 50.73 Tech. Spec.
Change out the governor printed 1-4 4
unanticipated age-related response of the Surveillance circuit boards every eight years [4]
printed circuit board's components due to req'd for HPI long term constant energization and possibly environmental factors. Vendor indicated that long term constant current flow could reduce life Document: LER 89-003-263, Isolation of Reactor Water Cleanup System Due to Capacitor Failure in FilterlDemineralizer Inlet Temperature Indication Switch Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Unexpected capacitor failure caused Rare 10 CFR 50.73 No specific Not stated 1-3 5
circuit to actuate a portion of the ESF surveillance for system. Aging was given as the cause of this component the capacitor failure Document: LER 89-006-261, Reactor Trip Due to Loss of Turbine E-H Control Power Supplies Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Transistor leakage current caused Rare 10 CFR 50.73 No specific Not stated 1-4 6
increased gain resulting in higher voltage surveillance for on the output stage of the power supply.
this component the over voltage protective circuitry was triggered causing the fuse to blow.
degraded transistors attributed to aging.
Document: LER 89-010-362, Fuel Handling Isolation System Train "A" Actuation Due to Power Supply Failure Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Lost power from the power supply when Rare 10 CFR 50.73 No specific Not stated 1-5 7
the regulator shifted due to the broken surveillance for screw and allowed a burr on the metal this component heat sink to penetrate the mica insulation.
a short circuit resulted blowing a fuse.
Table A.2 Gall Report for Licensee Event Reports Page 2A Document: LER 89-014-271, Reactor Core Isolation Cooling System Inoperable Due to Motor Bum Out Reviewed by:
L. C. Meyer, INEL 1St S
tu e/C S b tem
>ys em truc r omp u component Materials Manufacturer ARD mechanism ARDeffects 8 Reactor Core Motor Operated Motor Not stated Not stated CURSTR Failed armature Isolation Cooling Valve winding System Document: LER 89-015-327, Control Room Isolation Resulting From a Worn Set of Contacts in the 480V Motor Starter for a Main Control Room Ventilation Intake I Reviewed by:
L. C. Meyer, INEL Item S S
e/C S b
>ystem tructur omp u component Materials Manufacturer ARD mechanism ARDeffects 9 Control Room Motor Starter Contacts Not stated Not stated WEAR Increased contact Isolation resistance causing arcing Document: LER 89-019-01-325, Failure of Service Water System to Meet Design Requirements Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 10 Service Water Pump Winding Insulation Not stated System Document: LER 89-020-01-528, Apparent Ground Causes Control Element Assembly Slip Reviewed by:
L. C. Meyer, INEL Item S stem Structure/Com Materials 11 Coil Not stated General Electric Manufacturer Combustion Engineering ELETEMP ARD mechanism Not stated Degraded insulation on motor winding ARDeffects Not aging related Document: LER 89-031-01-302, Failure of 'A' 480V Engineered Safeguards Transformer Causes Temporary Interruption of Decay Heat Cooling and a Plant Opera Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 12 ESFAS Transformer Transformer Not stated Not stated Not stated Insulation Insulation degradation Document: LER 90-007-01-388, ESF Actuations Due to RPS EPA Breaker Spurious Trip Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 13 Reacotr Protection Electrical Protection Logic Card Not stated General Electric Not stated System Assembly Document: LER 90-018-244, Dropped Control Rod During Rod Control Exercise Causes Automatic Actuation of RPS Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism 14 Control Rod Drive Power Bridge Capacitor Not stated Westinghouse ELETEMP System Document: LER 90-022-01-344, Degraded Fire Penetration Seals as a Result of Inadewuate Construction Technique Reviewed by:
L. C. Meyer, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism Silicon foam Not stated WEAR Logic card failed ARDeffects Degraded capacitor ARDeffects Degradation of foam splits and gaps.
Table A.2 Gall Report for Licensee Event Reports Page 28 Document: LER 89-014-271, Reactor Core Isolation Cooling System Inoperable Due to Motor Bum Out Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Valve failed to close because of failed Rare 10 CFR 50.73 Vendor specific Not stated 1-4 8
motor. An incorrect upper bearing gasket testing thickness resulted in a motor current 20%
above full rated load which is believed to have contributed to premature aging.
Document: LER 89-015-327, Control Room Isolation Resulting From a Wom Set of Contacts in the 480V Motor Starter for a Main Control Room Ventilation Intake F Reviewed by:
L. C. Meyer, INEL Eff fA' C
F C"b F'I R
ed R I R
rt R d ti P
N lte ecto,glng on omponent unction ontrl to al ure eport progs e.progs epo ecommen a ons age o.
m Contacts not conducting properly and Rare 10 CFR 50.73 No specific Not stated 1-3 9
current was arcing over introducing EMI surveillance for into the circuitry resulting in a spurious this component high radiation signal that initiated the control room isolation.
Document: LER 89-019-01-325, Failure of Service Water System to Meet Design Requirements Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item Inadequate air flow through the motor Rare 10 CFR 50.73 IEEE 334-1974 Not stated 1-4 10 winding over a period of time resulted in Section 14.2 thermally aged insulation that resulted in a turn to turn failure.
Document: LER 89-031-01-302, Failure of 'A' 480V Engineered Safeguards Transformer Causes Temporary Interruption of Decay Heat Cooling and a Plant Opera Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item Transformer failed causing a cooling Rare 10 CFR 50.73 RG 1.118, Not stated 1&3 12 pump to de-energize and loss of decay IEEE 338-heat cooling. Power was also interrupted 1987,IEEE to various plant ventilation systems. Event 741-1986 compounded by personnel error.
Document: LER 90:-007-01-388, ESF Actuations Due to RPS EPA Breaker Spurious Trip Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item The logic card failure caused the trip Occasional; (12 10 CFR 50.73 RG 1.118, Not stated 1-5 13 breaker to operate and initiated other esf times/6 Y)
IEEE 338-1987 actuations. The card failure was attributed to aging and the aging process was found to be applicable when the epa logic card was both in service and in storage.
Document: LER 90-018-244, Dropped Control Rod During Rod Control Exercise Causes Automatic Actuation of RPS Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Noisy incoming power to the control rod J-Rare 10 CFR 50.73 Vendor specific Not stated 1-8 14 10 (caused the rod to drop) was attributed program to the degraded capacitor. Elevated temperature at the power supply location was the cause of the decreased service life of the capacitor.
Document: LER 90-022-01-344, Degraded Fire Penetration Seals as a Result of Inadewuate Construction Technique Reviewed by:
L. C. Meyer, INEL Effect of A in on Com onent Function Contrib to Failure Occasional
Table A.2 Gall Report for Licensee Event Reports Page 3A Document: LER 90-023-325, Partial Group 6 Isolation Resulting From Failure of Relay I-CAC-3A Reviewed by:
L. C. Meyer, INEL Item System S
tu eJC S b M t
. I M
f tu truc r omp u componen a erla s anu ac rer ARD h
mec amsm ARD ff ts eec 16 Containment Isolation Logic Coil Not stated General Electric Not stated Coil bumed up Isolation Control Document: LER 90-023-424, Transformer Failure Results in Loss of Steam Generator Level and Manual Reactor Trip Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manu acturer A
mechanism e ects RD ARD ff 17 Non 1-E Power Transformer Not stated Not stated General Electric Not stated Internal fault in the System
'b' phase high side windings Document: LER 90-029-01-325, CBEAF SYSTEM Actuation Resulting From the Failure of the 1-D22A-K2 Relay Coil.
Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 18 Control Building Arm Logic Relay Not stated General Electric Not stated Cracks on epoxy Emergency Air coating, relay bumec Filtration System up (probably shorted)
Document: LER 91-001-293, Automatic Closing of the Primary Containment System Group 5 Isolation Valves During Sruveillance Testing Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponen M aterials Manu acturer AR o mechanism A RD ff e ects 19 Primary Isolation Electric G~emor Transistor Not stated Not stated Not stated Transistor failed Control System 20 Primary Isolation Electric Govemor Cable Insulation Notstated Woodward Governor ELETEMP, MOIST, Embrittlement due to Control System Company
&EMBR past exposure to heat and humidity
,Document: LER 91-002-01-327, EGTS Inoperable Because of a Train EGTS Being Out of Service for Filter Testing and B Train Diesel Generator Being Declared I Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 21 Emergency Gas Diesel Generator Fuse Not stated N()tstated THERM-CY Fuse failed Treatment System (EGTS)
Document: LER 91-006-530, ESF Actuation Due to Loss of Power to 4.16 KV Bus Reviewed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 22 1E Power Circuit Breaker Trip Circuit Not stated Not stated MOIST Moisture induced short circuit in trip circuit Document: LER 91-007-456, Rod Control System Failure Causes Shutdown Bank Control Rods to be in a Condition Prohibited by Technical Specifications RevieWed by:
L. C. Meyer, INEL Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 23 Rod Control System Circuit Card Transistor Not stated Not stated Not stated Transistor failed
Table A.2 Gall Report for Licensee Event Reports Page 38 Document: LER 90-023-325, Partial Group 6 Isolation Resulting From Failure of Relay I-CAG-3A Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs
. Rel.progs Report Recommendations Page No. Item Relay failure resulted in partial loss of cac Occasional; (3 in 18 10 CFR 50.73 RG 1.118, Not stated 1-3 16 logic and subsequent partial group 6 Mo)
IEEE 338-isolation. This normally energized coil 1987, Tech burned up as a result of normal end of life Spec. surv.
failure due to aging.
Document: LER 90-023-424, Transformer Failure Results in Loss of Steam Generator Level and Manual Reactor Trip Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Transformer failed resulted in loss of Rare 10 CFR 50.73 No specific Not stated 1-4 17 power to speed control circuitry of the 1 B surveillance for main feedwater pump. Possible this component premature aging of transformer.
Document: LER 90-029-01-325, CBEAF SYSTEM Actuation Resulting From the Failure of the 1-D22A-K2 Relay Coil.
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item CBEAF system actuation resulted from Occasional 10 CFR 50.73 No specific Not stated 1-3 18 the failed relay. This normally energized surveillance for relay failed due to cracks in the epoxy this component coating on the coil. This was called a normal end of life failure due to aging.
Document: LER 91-001-293, Automatic Closing of the Primary Containment System Group 5 Isolation Valves During Sruveillance Testing Reviewed by:
L. C. Meyer, INEL Eff fA' C
'b F'I ecto
~glng on omponent Function Contrl to al ure Reported progs Rel.progs Report Recommendations Page No. Item Circuit failed to control governor leading to Rare 10 CFR 50.73 No specific Not stated 1-4 19 automatic closure of isolation valves.
surveillance for this component Cable embrittiement due to thermal aging Rare 10 CFR 50.73 No specific Not stated 1-4 20 was listed as the cause. handling of cable surveillance for during maintenance and surveillance this component activities may have contributed to the cable failure.
Document: LER 91-002-01-327, EGTS Inoperable Because of a Train EGTS Being Out of Service for Filter Testing and B Train Diesel Generator Being Declared Ii Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Failed fuse resulted in train B EGTS Rare 10 CFR 50.73 Tech Spec.
Not stated 1-5 21 being declared inoperable. Frequent required cycling on and off of the air start system surveillance due to an air leak is believed to be have degraded the fuse resulting in fuse failure.
Document: LER 91-006-530, ESF Actuation Due to Loss of Power to 4.16 KV Bus Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Breaker opened when it was supposed to Rare 10 CFR 50.73 RG 1.118, Not stated 1-5 22 be closed. A degraded seal around an air IEEE 338-conditioning duct penetration allowed 1987,IEEE moisture from a rain storm to enter the 741-1987 plant multiplexer cabinets causing the SECTIO short circuit.
Document: LER 91-007-456, Rod Control System Failure causes Shutdown Bank Control Rods to be in a Condition Prohibited by Technical Specifications Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Transistor failure caused the circuit to fail Rare 10 CFR 50.73 No specific Not stated 1-4 23 resulting in no motion control for the group surveillance for 1 control rods. Aging degradation was this component given as the cause of the transistor failure.
Table A,2 Gall Report for Licensee Event Reports Page 4A Document: LER 91-008-260, Unplanned Engineered Safety Features Actuation Due to a Failed PCIS Relay Reviewed by:
L. C. Meyer, INEL I
S tem System Structure/Comp ubcomponent Materials Manufacturer ARD mechanism ARDeffects 24 Primary Containmen Logic Relay Coil Not stated General Electric Not stated Burned coil Isolation System Document: LER 91-010-01-155, Reactor Protection System Pressure Switches Experiencing Setpoint Drift, Revision 1 Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 25 Reactor Protection Switches Not stated Foxboro CORR Corrosion caused System switch setpoint drift Document: LER 91-014-01-498, Erratic Containment Extended Range Pressure Channel Output Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 26 Containment Pressure Thermisitor Not stated Barton Not stated Erratic behavior of Extended Range Transmitter instrument Pressure Channel Document: LER 91-016-260, Unplanned Engineered Safety Features Actuation Due to a Blown Fuse Caused by a Failed Relay Reviewed by:
L. C. Meyer, INEL I
S tue/C S b M
'I M
D h
tem System truc r omp u component aterla s an ufacturer AR mec amsm ARD ff e ects 27 ESFAS Relay Coil Not stated General Electric ELETEMP Relay coil failed Document: LER 91-016-424, Failure to Complete Technical Specification Required Action for Battery Cell Low Voltage Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 28 Various Battery NA Not stated C & D Batteries Not stated Low cell voltage while single cell charging Document: LER 91-020-237, Reactor Building Ventilation Isolation and Automatic Standby Gas Treatment Initiation Due to Radiation Monitor Power Supply Failure Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 29 Reactor Building Power Supply Wire Not stated General Electric WEAR Insulation wom and Ventilation System spark caused power supply failure Document: LER91-021-254, RCIC Declared Inoperable Due to High Pump Flow in lSI Required Action Range Reviewed by:
L. C. Meyer, INEL Item S t
S e/C Sb t
Mt'l M
- ys em tructur omp u componen a erlas anufacturer h
ARDmec amsm ARD ff ts eec 30 RCICSystem Tachometer NA Not stated Not stated Not stated Instrument drift Document: LER 91-028-254, Loss of Power to 1A RPS Bus Caused by EPA 1A-1 Tripping on Undervoltage Due to Low M-G Set Output ReViewed by:
L. C. Meyer, INEL Item System S
e/C S b M
. I ARD ff tructur omp u componen aterlas Manufacturer ARD mechanism e ects 31 M-G Set Voltage Regulator Voltage Rheostat Insulation General Electric Not stated Low voltage from m-g set
Table A.2 Gall Report for Licensee Event Reports Page 48 Document: LER 91-008-260, Unplanned Engineered Safety Features Actuation Due to a Failed PC IS Relay Reviewed by:
L. C. Meyer, INEL Eff t fA' C
F
'b F'I eco Iglng on omponent unction Contrl to al ure Reported progs Rel.progs Report Recommen d ations Page No. Item The bumed coil cause the normally Occasional 10 CFR 50.73 Tech Spec.
Not stated 1-3 24 energized relay to fail resulting in loss of required logic power and an unplanned actuation of surveillance the esfas. This was called a thermally aged relay coil failure.
Document: LER 91-010-01-155, Reactor Protection System Pressure Switches Experiencing Setpoint Drift, Revision 1 Reviewed by:
L. C. Meyer, INEL Eff t fA' C
F C'b F*I R
R I R
R ec 0 Iglng on omponent unction ontrl to al ure eported progs e.pr~gs eport ecommen d.
ations P age N o. tem The drift would adversly effect the RPS Rare 10 CFR 50.73 Tech Spec.
Not stated 1-2 25 operation. Found during refueling outage required calibration.
surveillance Document: LER 91-014-01-498, Erratic Containment Extended Range Pressure Channel Output Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item A cracked thermistor was found on the Rare 10 CFR 50.73 Tech Spec.
Not stated 1-4 26 control card, however the erratic behavior surveillance, of the pressure transmitter cannot be RG 1.118, positively attributed to this thermistor.
IEEE 338 Document: LER 91-016-260, Unplanned Engineered Safety Features Actuation Due to a Blown Fuse Caused by a Failed Relay Reviewed by:
L. C. Meyer, INEL Eff t fA' C
F C*b F'I d
R I R
R d ti ecO glng on omponent unction ontrl to al ure.Reporte progs e.progs eport ecommen a ons P age N It
- o.
em Unplanned ESFAS actuation due to failed Rare 10 CFR 50.73 Tech Spec.
Not stated 1-3 27 relay. The failed relay coil was 15 years surveillance, old and the service life for a normally-not specific energized coil relay of this type is 15 to 20 years. This was an end of life failure.
Document: LER 91-016-424, Failure to Complete Technical Specification Required Action for Battery Cell Low Voltage Reviewed by:
L. C. Meyer, INEL Eff t fA*
C t F C
tr'b t F'I R
ed R I R
R eco Iglng on omponen unction on 1 0
al ure eport
~rogs e.progs eport ecommen d ti a ons P age N lte
- o.
m Battery failed to meet technical Rare 10 CFR 50.73 Tech Spec.
Not stated 1-4 28 specification while charging. This was surveillance, considered to be related to battery aging RG 1.118, phenomena IEEE 450 Document: LER 91-020-237, Reactor Building Ventilation Isolation and Automatic Standby Gas Treatment Initiation Due to Radiation Monitor Power Supply Failure Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item The ventilation system and gas treatment Occasional 10 CFR 50.73 No specific Not stated 1-4 29 system actuation resulted from the power surveillance for supply failure.
this component Document: LER 91-021-254, RCIC Declared Inoperable Due to High Pump Flow in 151 Required Action Range Reviewed by:
L. C. Meyer, INEL Eff fA*
C F
F *1 ecto Igln9 on om()onent unction Contrib to al ure Reported progs Rel.progs Report Recommendations Page No. Item Failure due to instrument drift caused by Rare 10 CFR 50.73 No specific Not stated 1-4 30 aging surVeillance for this component Document: LER 91-028-254, Loss of Power to 1A RPS Bus Caused by EPA 1A-1 Tripping on Undervoltage Due to Low M-G Set Output Reviewed by:
L. C. Meyer, INEL Eff t fA' C
F C'b F*I R
ed R d '
eco 'glng on omponent unction ontrl to al ure eport progs el.J)f~gs Report Recommen ations Page No. Item Cause of dip is unknown, but normal wear Occasional 10 CFR 50.73 Vendor specific Not stated 1-6 31 of the voltage adjustment rheostat was program supected. It was believed to have developed a flat spot or corrosion at the point of the previous adjustment due to normal wear at that point over a long period of time.
Table A.2 Gall Report for Licensee Event Reports Page SA Document: LER 91-028-325, Component Failure of a Reactor Water Cleanup System Isolation Logic Relay Resulted in an Unplanned Engineered Safety Feature Reviewed by:
L. C. Meyer, INEL Item System S
e/C b
M RD tructur omp Su component aterials Manufacturer ARD mechanism A
effects 32 RWCU Relay Coil Insulation General Electric Not stated Relay coil failed after insulation breakdowr Document: LER 91-030-423, Motor Control Center Auxiliary Control Relay Failure Due to Thermal Aging Reviewed by:
L. C. Meyer, INEL Item System S
e/C S b t
M M
f tu tructur omp u componen aterlals anu ac rer ARD h
mec anism ARD ff e ects 33 Motor Control Cente Relay Coil Insulation ITE Gould ELETEMP & EMBR Relay coil insulaton embrittiement and failure Document: LER 92-001-155, Brittle Motor Lead Wires Discovered in VOP-70S0 (Main Steam Isolation Valve-MSIV)
Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 34 Main Steam Isolation Valve Motor Lead Wire Insulation Butyl rubber Umitorque ELETEMP & EMBR Brittle and cracked insulation Document: LER 92-001-263, Shutdown Required by Technical Specification Due to Inoperable Bellows Leak Detection System for Safety Relief Valves Reviewed by:
L. C. Meyer, INEL Item S Str tu e/C S b M t. I M
f t
ARD h*
ARD ff ts
,ystem uc r omp u componen a erla s anu ac urer mec anlsm eec 3S Bellows Leak Valve Seating Material Cast urethane Automatic Switch ELETEMP Urethane seat Detection System Company material degraded due to high temperature Document: LER 92-001-296, Engineered Safety Feature Actuation Caused by a Failed Relay Coil Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 36 Engineered Safety Relay Coil Not stated General Electric ELETEMP Degraded insulation Feature Actuating causing coil failure System (ESFAS)
Document: LER 92-001-339, Reactor Trip Caused by MFRV Closure Upon Failure of Driver Card Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 37 Feeclwater system Main Feed Power Supply Not stated Not stated Not stated Power supply failed Regulating Valve on driver card Document: LER 92-002-247, Reactor Trip Due to Main Feedwater Regulating Valve Going Closed RevieWed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent M aterials Manufacturer ARD mechanism ARD ff e ects 38 Feeclwater system Feedwater Solenoid Valve Not stated Not stated Not stated Solenoid valve failed Regulating Valve Document: LER 92-004-389, Manual Reactor Trip Due to Low Steam Generator Water Level Caused by a Failed Circuit in the 2A Feedwater Regulating Control Sy Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 39 Feedwater Power Supply Capacitor Not stated Not stated Not stated CapaCitor failed Regulatiog Valve Control System
Table A.2 Gall Report for Licensee Event Reports Page 58 Document: LER 91-028-325, Component Failure of a Reactor Water Cleanup System Isolation Logic Relay Resulted in an Unplanned Engineered Safety Feature A Reviewed by:
L. C. Meyer, INEL Eff t fA' C
F
'1 R
R I R
Rd' P
N eco Iglng on omponent unction Contrib to Fal ure eported progs e:.progs eport ecommen ations age o. tern ESFAS actuation resulted from the relay Occasional 10 CFR 50.73 Tech Spec. not Not stated 1-4 32 failure. Component failure determined to specific for this be a normal end of life failure due to component aging. This was a normally energized relay.
Document: LER 91-030-423, Motor Control Center Auxiliary Control Relay Failure Due to Thermal Aging Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Elevated temperature from continuous Occasional 10 CFR 50.73 Vendor specific Not stated 1-5 33 operation of relays caused embrittiement program and failure. Heat also discolored other plastic parts near the coil.
Document: LER 92-001-155, Brittle Motor Lead Wires Discovered in VOP-7050 (Main Steam Isolation Valve-MSIV)
Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Loss of isolation capability, the degraded Rare 10 CFR 50.73 Vendor specific Not stated 1-4 34 wire insulation was found in the limit progarm, GL switch housing as a result of planned 89-10, maintenance during a scheduled refueling NUREG-1352 outage.
Document: LER 92-001-263, Shutdown Required by Technical SpeCification Due to Inoperable Bellows Leak Detection System for Safety Relief Valves Reviewed by:
L. C. Meyer, INEL Eff fA' C
F C'b F'I R
ed R I R
rt R d ti P
N It ecto,glng on omponent unction ontrl to al ure eport ;progs e.progs epo ecommen a ons age o.
em Valve failed to seat due to degradation of Rare 10 CFR 50.73 Vendor specific Not stated 1-6 35 the seating material from exposure to program temperatures near manufacturers rated temperature.
Document: LER 92-001-296, Engineered Safety Feature Actuation Caused by a Failed Relay Coil Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item The coil failure iniated partial actuation of OCCAIONAL 10 CFR 50.73 Vendor specific Not stated 1-5 36 the ESFAS system.
program, Tech.
Spec. Surveil.
Document: LER 92-001-339, Reactor Trip Caused by MFRV Closure Upon Failure of Driver Card Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations PageNo Item Power supply failure caused the MFRV Occasional 10 CFR 50.73 No specific Not stated 1-3 37 valve to fail closed isolating normal program feedwater and causing a reactor trip.
Document: LER 92-002-247, Reactor Trip Due to Main Feedwater Regulating Valve Going Closed Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure ed Report progs RI e.progs R ~ort R ecommen d.
ations P age N lte
- o.
m Solenoid valve failued relieVing air Rare 10 CFR 50.73 No specific Not stated 1-3 38 pressure to the diaphragm of the program regulating valve which caused it to go to the closed position.
Document: LER 92-004-389, Manual Reactor Trip Due to Low Steam Generator Water Level Caused by a Failed Circuit in the 2A Feedwater Regulating Control Sy Reviewed by:
L. C. Meyer, INEL Eff f
F b
F'I R
ed R I R
R d Ii P
N lte ect 0 Aging on Component unction Contri to al ure eport progs e.progs eport ecommen a ons age o.
m Because of the capacitor failure the lead Rare 10 CFR 50.73 Vendor specific Not stated 1-3 39 lag circuit output current was low and the program steam regulating valve closed. The reactor was manually tripped.
Table A.2 Gall Report for Licensee Event Reports Page 6A Document: LER 92-006-331, Emergency Safety Feature Actuation During Modification Acceptance Testing Due to Damaged Switchyard Cable Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 40 1E Power Cable Insulation Ethylene propylene Not stated WEATH, CORR, &
Insulation degraded, rubber MOIST galvanic corrosion rusted wire cores Document: LER 92*006-354, Reactor Shutdown to Comply With Technical Specification 3.6.1.1, Due to Failure of Suppression Chamber to Drywell Vacuum Breal Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp S b u component M aterials Manufacturer ARD mechanism ARDeffects 41 Various Drywell Vacuum Seal Not stated Not stated Not stated Seal degraded due Breakers to aging Document: LER 92-007-01-33, Failure of Analog Transmitter Trip System (ATTS) Trip Relays Due to Thermal Aging Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp S ubcomJ)onent Materials Manufacturer ARD mechanism ARD effects 42 Analog Transmitter Relay Coil Not stated Amerace ELETEMP Relay coil wire Trip System insulation embrittlement Document: LER 92-009-01-499, Missed Technical Specification Required Surveillance Due to a Faulty Toxic Gas Monitoring System Modem Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 43 Emergency Modem NA Not stated Black Box Not stated Modem failed Response --
Corporation Display System (ERFDADS)
Document: LER 92-011-325, Primary Containment Monitoring System Inoperability Due to Relay Failure Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 44 Containment Containment Control Relay Not stated General Electric Not stated Relay failed (end of Atmospheric Control - Logic life)
(CAC) System Document: LER 92-021-237, Automatic Isolation of Reactor Building Ventilation Due to Radiation Monitor Trip Relay Failure Reviewed by:
L. C. Meyer, INEL Item S stem Structure/Com Materials Manufacturer ARD mechanism ARD effects RBV Radiation Not stated General Electric Not stated Burned out coil Monitor Document: LER 92-034-01-333, Engineered Safety Feature Actuations Due to Transformer Failure Reviewed by:
L. C. Meyer, INEL Item System Structure/Com p Subcomponent Materials Manufacturer ARD mechanism ARDeffects 46 ESFAS Transformer NA Not stated General Electric ELETEMP Insulation degradation in transfomer
Table A.2 Gall Report for Licensee Event Reports Page 68 Document: LER 92-006-331, Emergency Safety Feature Actuation During Modification Acceptance Testing Due to Damaged Switchyard Cable Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure R~orted progs Rel.progs Report Recommendations Page No. Item A tear or crack in the insulation exposed Rare 10 CFR 50.73 No specific Not stated 1-8 40 wires to ambient conditions and moisture program intrusion with continuous dc potential on wires may have contributed to galvanic corrosion leading to an open circuit The failed circuit caused sf actuation during test.
Document: LER 92-006-354, Reactor Shutdown to Comply With Technical Specification 3.6.1.1, Due to Failure of Suppression Chamber to Drywell Vacuum Break, Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report R ecommendations P~eNo. Item Leak in vacuum breakers was too large Rare 10 CFR 50.73 No specific Not stated 1-5 41 and violated the technical specifications program resulting in reactor shut down. Two of the three leaking breakers also had seal and pallet alignment problems.
Document: LER 92-007-01-33, Failure of Analog Transmitter Trip System (ATIS) Trip Relays Due to Thermal Aging Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs R eport R ecommen d.
ations P age N It em
- o.
Debris from the embrittled coil spool was Occasional 10 CFR 50.73 Tech Spec.
Not stated 1-5 42 inhibiting movement of the relay plunger required resulting in sticking relay and excessive surveillance delay time. The relay had been in service 4 years which exceeded the recommended service life of 3 years Document: LER 92-009-01-499, Missed Technical Specification Required Surveillance Due to a Faulty Toxic Gas Monitoring System Modem Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Garbled data sent to erfdads computer.
Rare 10 CFR 50.73 No specific Not stated 1-5 43 Failure of modem attributed to aging.
program Operators were unable to meet technical specifications requiring the each chemical detection system be demonstrated operable every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Document: LER 92-011-325, Primary Containment Monitoring System Inoperability Due to Relay Failure Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No Item Failure of this relay resulted in loss of Occasional 10 CFR 50.73 Tech Spec.
Not stated 1-3 44 power to various containment isolation required valves and inoperability of the cac system.
surveillance Document: LER 92-021-237, Automatic Isolation of Reactor Building Ventilation Due to Radiation Monitor Trip Relay Failure Reviewed by:
L. C. Meyer, INEL Effect of A in on Com onent Function Contrib to Failure Failure of relay coil caused the RBV Rare system to actuate.
Document: LER 92-034-01-333, Engineered Safety Feature Actuations Due to Transformer Failure Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Pag~No. Item Fault in middle phase b winding due to Rare 10 CFR 50.73 RG 1.118, Not stated 1-16 46 dielectric breakdown of insulation caused IEEE 338-1987 transformer failure resulting in ESFAS actuations. The dielectric breakdown due to aging resulted in multiple faults.
Table A.2 Gall Report for Licensee Event Reports Page 7A Document: LER 92*038*255, Reactor Trip Caused by a Loss of the Preferred AC BUS Y*20 Coincident With a Blown Fuse in a Second Channel of the Reactor Pr, Reviewed by:
L. C. Meyer, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 47 Reactor Protection Inverter Transformer Not stated Sola ELETEMP Transformer coils System failed Document: LER 93*002*249, Control Valve Fast Closure Half*Scram Pressure Switches Out*of Calibration Due to Setpoint Drift Reviewed by:
L. C. Meyer, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARDeffects 48 Reactor Protection Pressure Switch NA Not stated Barksdale VIB Wear of face of the System plunger Document: LER 93*003-530, Emergency Diesel Generator Unable to Start and Run in Manual Test Mode Reviewed by:
L. C. Meyer, INEL Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects 49 Emergency Diesel Starting System Relay Not stated Agastat Not stated Relay failed by fault Generator of a suppression varistor across coil Document: LER 93-005-01-275, Medium Voltage cable Failures Due to Chemical Degradation and Undkown Causes Reviewed by:
L. C. Meyer, INEL Item System StructurelComp Subcomponent Materials ManUfacturer ARD mechanism ARD effects 50 Various Cable 12KV Underground Ethylene-Okonite CHEM, CONTAM, & Chemical cable propylene=rubber CORR degradation of jacket (EPR) and neoprene and corrosion of jacket shield 51 Various Cable 12KV Underground Ethylene-Okonite Not stated Anomalies occurred cable propylene=rubber overtime (EPR) and neoprene jacket Document: LER 93-005-01-305, Annual Transmitter Calibration Finds a Shift in the Pressurizer High Pressure Reactor Trip Signal Initiation Due to Instrument Drift Reviewed by:
L. C. Meyer, INEL 1St S
tu elC S b M t. I M
RD h'
RD ff tem.ys em truc r omp u componen a erlas an ufacturer A
mec anlsm A
e ects 52 Reactor Protection Pressure NA Not stated Foxboro Not stated Transmitter drift System Transmitter Document: LER 93-007-249, Yarway Reactor Water Level Switch Failure Reviewed by:
L. C. Meyer, INEL Item S S
tuelC Sb t
Mt'l
.ystem truc r omp u componen a erla s M an ufacturer ARD h.
mec anlsm ARD ff e ects 53 High PRessure Level Switch NA Not stated Yarway MECHSTR Spring force Coolant Injection degradation System (HPCI)
Document: LER 93-008-237, Yarway Reactor Water Level Switch Failure Reviewed by:
L. C. Meyer, INEL 1St StrtuelC Sb t
Mt'l tem.ys em uc r omp u componen a erlas M anu acturer ARD h
mec amsm ARD ff ts eec 54 High PRessure Level Switch NA Not stated Yarway MECHSTR Spring force Coolant Injection degradation System (HPCI)
Table A.2 Gall Report for Licensee Event Reports Page 78 Document: LER 92-038-255, Reactor Trip Caused by a Loss of the Preferred AC BUS Y-20 Coincident With a Blown Fuse in a Second Channel of the Reactor Pro Reviewed by:
L. C. Meyer, INEL Eff A.
R R
d P
N It ect of 'gmg on Component Function Contrib to Failure Reported progs Rel.progs eport ecommen ations age o.
em The transformer failure resulted from Rare 10 CFR 50.73 Tech. Spec.
Not stated 1-8 47 accelerated aging due to improper inemal required wiring in the inverter. Only one primary surveillance, winding was connected resulting in RG 1.118 operation at a higher temperature. the Y-20 bus power failure tripped the reactor.
Document: LER 93-002-249, Control Valve Fast Closure Half-Scram Pressure Switches Out-of Calibration Due to Setpoint Drift Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page N o. tem Vibration contributed to the drift of the set Rare 10 CFR 50.73 Tech Spec.
Not stated 1-6 48 point because of wear on the plunger required face.
surveillance Document: LER 93-003-530, Emergency Diesel Generator Unable to Start and Run in Manual Test Mode Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rei progs Report Recommendations Page No. Item The starting system check circuitry relay Rare 10 CFR 50.73 RG 1.108, Not stated 1-9 49 shorted and the resulting Current surge IEEE 387-1984 damaged other electrical components on Section 7.5, the fiber optics card in the EDG starting IEEE 749 circuit. The EDG would not start in the manual test mode. Component aging was the cause Document: LER 93-005-01-275, Medium Voltage Cable Failures Due to Chemical Degradation and Undkown Causes Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item A ground fault developed at the cable Rare 10 CFR 50.73 No specific Not stated 1-16 50 jacket degradation location (insulation program breakdown). Excess chlorides and a fatty acid, ethyl ester compound, were identified as the chemical that attacked the cable jacket. Water carried chemical into conduit.
Ground fault occurred on cable. water Rare 10 CFR 50.73 No specific Not stated 1-16 51 was in conduit (cable was designed for program wet conditions) cable removed from conduit and no root cause identified from inspections or tests conducted by utility and manufacturer.
Document: LER 93-005-01-305, Annual Transmitter Calibration Finds a Shift in the Pressurizer High Pressure Reactor Trip Signal Initiation Due to Instrument Drift Reviewed by:
L. C. Meyer, INEL E
fA.
C ffecto Igmg on omponent Function Contrib to Failure Reported progs The transmitter would not initiate a trip Occasional 10 CFR 50.73 signal at the required point. The method of calibration was most probable cause and aging was the next most likely cause.
Document: LER 93-007-249, Yarway Reactor Water Level Switch Failure Reviewed by:
L C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Switch tripped outside of technical Frequently 10 CFR 50.73 specification limits. Excessive set point drifts were also found.
Document: LER 93-008-237, Yarway Reactor Water Level Switch Failure Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Out of tolerance Frequently 10 CFR 50.73 Rel.progs Report Recommendations Page No. Item RG 1.118, Not stated 1-5 52 IEEE 338-1987 Rel.progs Report Recommendations Page No. Item RG 1.118, Not stated 1-5 53 IEEE 338-1987 Rei progs Report Recommendations PageNo Item RG 1.118, Not stated 1-6 54 IEEE 338-1987
Table A.2 Gall Report for Licensee Event Reports Page SA Document: LER 93-009-498, Technical SpeCification 3.0.3 Entry Due to Potentially Undersized Fuses in the Solid State Protection System Reviewed by:
L. C. Meyer, INEL Item System Structure/Comp Subcomponen t M aterials Manu acturer A RD mechanism ARD ff ts eec 55 Solid State Fuse NA Not stated Not stated Not stated Fuse failed Protection System
Table A.2 Gall Report for Licensee Event Reports Page 88 Document: LER 93-009-498, Technical Specification 3.0.3 Entry Due to Potentially Undersized Fuses in the Solid State Protection System Reviewed by:
L. C. Meyer, INEL Effect of Aging on Component Function Contrib to Failure Re~orted ~!~RS Rel.J!I'~gs R~ort Recommendations Page No. Item An independent laboratory determined Rare 10 CFR 50.73 No specific Not stated 1-5 55 that the fuse did not open as the result of program a high current fault. It was not possible to determine whether the fuse had a defect.
LER states that the event was caused by the random age related failure of a ssps fuse.
Table A.2 Gall Report for NRC Bulletins Page 1A Document: BL 90-01, Loss of Fill-Oil in Transmitters Manufactured by Rosemount Reviewed by:
E. W. Roberts, INEL 1St Str tu e/C S b tem
- iy~ em uc r omp u component Materials Manu acturer ARD mechanism ARD ff ts eec 1
Pressure O-Ring Metal Rosemount Not stated Loss of transmitter Transmitters Model oil 1153&1154
Table A.2 Gall Report for NRC Bulletins Page 1B Document: BL 90-01, Loss of FiII*Oil in Transmitters Manufactured by Rosemount Reviewed by:
E. W. Roberts, INEL Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Transmitter drift, slow response, inability Frequent Not discussed in Bul9Q-01 Identify transmitters and take 1
to respond over full range, sustained report Suppl1, RG appropriate corrective action [4]
zero/span drift, or total failure 1.118,IEEE 338*1987
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Distribution for NUREGlCR-6490 Internal:
D. R Diercks (25)
H. Drucker K. E. Kasza (10)
C. A. Malefyt L. A. Neimark R. B. Poeppel External:
Libraries ANL-E ANL-W Manager. Chicago Field Office. DOE W. J. Shack C. E. Till R A. Valentin M. W. Wambsganss R W. Weeks TIS File Energy Technology Division Review Committee:
H. K. Birnbaum. University of Illinois. Urbana R C. Buchanan. University of Cincinnati. Cincinnati. OH S.-N. Liu. Fremont. CA H. S. Rosenbaum. Fremont. CA R K. Shah. University of Kentucky. Lexington S. Smialowska. Ohio State University. Columbus R E. Smith. Altran Corp.. Huntersville. NC INEL Technical Library J. L. Edson (10). INEL NUREG/CR-6490
P-----------------------------------------~------------~.~
NRC FORM US (2-811)
- NRCM1102, 3201,3202 u.s. NUCLEAR REGULATORY COMMISSION
- 1. REPORT NUMBER BIBLIOGRAPHIC DATA SHEET
- 2. TITLE N<<l SUBTITLE Nuclear Power Plant Generic Aging Lessons Learned (GALL)
Main Report and Appendix A
- 5. AUTHOR(S)
- 3.
(AasigneCllly NRC, AcId Vol., Supp.* Rev..
and Addendum Numben;. If any.)
NUREG/CR-6490 ANL-96/13 Vol. 1 DATE REPORT PUBLISHED I
YEAR December 1996
- 6. TYPE OF REPORT KE Kasza: D.R. Diercks: J.W. Holland: S.U. Choi: J.L. Binder: W.J. Shack: O.K. Chopra:
Technical D.C. Ma: A Erdemir,* J.L. Edson,- L.C.Meyer,- and E.W. Roberts.-
- 7. PERIOD COVERED (lnclwive Dates)
- 8. PERFORMNG ORGANZA TION
- NAME AND ADDRESS (If NRC, ptOIIide Division, CIIice cr Region. U.S. Nut::Ieer R8gulelDty Commi&sion. and fNilinQ addmss; if contractor.
ptOIIide_and meiIing ~.)
- Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439
-Idaho National Engineering Laboratory Lockheed Idaho Technologies Company Post office Box 1625 Idaho Falls, 10 83415
- 9. SPONSORING ORGANIZATION* NAME AND ADDRESS (If NRC. type "Same 8$ above"; if contractor. pmtIide NRC Division. Office or ReglOf1. U.S. Nuclear RegularOf}' CommiSSion.
and mailing addmss.}
License Renewal Project Directorate Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
- 10. SUPPLEMENTARY NOTES
- 11. ABSTRACT (2IJO ooanfa cr '-sa)
Argonne National Laboratory and Idaho National Engineering Laboratory in support of the License Renewal Project Directorate of the U.S. Nuclear Regulatory Commission (NRC) performed a comprehensive review of literature pertaining to nuclear power plant aging effects. This generic aging lessons learned (GALL) effort was a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, thermal-hydraulic, and electrical components and systems reviewed consisted of 163 Nuclear Plant Aging Research Reports, 31 NRC Generic Letters, 265 Information Notices, 82 Licensee Event reports, 5 Bulletins, and 10 Nuclear Management and Resources Council Industry Reports. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging related degradation mechanisms and effects. A computerized data base has also been developed for all review tables and can be used to search for information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all significant component and structure aging issues are currently being addressed by the regulatory process. However, aging of what are termed passive components and structures has been highlighted for continued scrutiny.
- 12. KEY WORDSIDESCRIPTORS (Liat wocnfs cr tw- /hat will ~i&t nu.-clNn in locating the report.)
Aging of Nuclear Power Plant Components and Systems License Renewal Ag.Related Degradation Mechanisms Component Aging Data Base Structur~ Aging Generic Aging Lessons Learned NRC FORM 335 (2.a8)
- 13. AVAILABILITY STATEMENT unlimited
- 14. SECURITY CLASSIFICATION (Thi& PaQe) unclassified (Thi& R.."at) unclassified
- 15. NUMBER OF PAGES
- 16. PRICE This form was electronically procluced by Elite Federal Forms. Inc.
':'j
. Printed on recycled paper Federal Recycling Program
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300
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