LER-1981-010, /03L-0:on 810224,fan for Standby Filter Unit B Found Not Running During Operational Test.Caused by Personnel Error in Opening Breaker for Control Bldg Emergency Air Supply Fan.Personnel Reinstructed |
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text
REGULATORYNFORMATION DISTRIBUTION S TEM (RIDS)
ACCESSION NBR:8103310679 DOC.DATE: 81/03/25 NOTAR ED: NO DOCKET #
FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTH.NAME AUTHOR AFFILIATION PAGERM.S.
Iowa Electric Light & Power Co.
RECIP.NAME.
RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director SUBJECT: LER 81-010/03L*0:on 810224,fan for standby filter unit B found not running during operational test.Caused by personnel error in opening breaker for control bldg emergency air supply fan.Personnel reinstructed.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR -! ENCL j.
SIZE:- I TITLE: Incident Reports NOTES:
RECIPIENT ID CODE/NAME ACTION:
IPPOLITO,T, 04 INTERNAL: A/D COMP&STRU06 A/D MATL & QU08 A/D PLANT SYSIO A/D SFTY ASSE12.
AEOD ASLBP/JHARD CHEM ENG BR 16 CORE PERF BR 18 DIR,HUM FAC 821 EFF TR SYS BR23 GEOSCIENCES 26 I&E 05 LIC GUID BR
- 30.
MECH ENG BR 33 NRC PDR 02 OR ASSESS BR 35 R
BRR39 01 EVA42 SYS INTERAC 845 COPIES LTTR ENCL 3
3 RECIPIENT ID CODE/NAME A/D ENV TECH 07 A/D OP REACT009 A/D RAD PROT 11 ACC EVAL BR 14 AEOD/DMU AUX SYS BR 15 CONT SYS BR 17 DIRENGINEERI20 DIRSYS INTEG22 EQUIP QUAL BR25 I&C SYS BR 29 JORDANE,/IE MATL ENG SR 32 MPA OP EX EVAL BR34 POWER SYS BR 36 REACT SYS BR 40 REL & RISK A 41 STRUCT ENG BR44 COPIES LTTR ENCL 1
1 1
1 3
1 1
1 1,
1 1
1 1
3 3
1 1
1 1
EXTERNAL: ACRS NSIC 46 05 16 1
16 1
LPDR 03 1
1 4v I 19BA TOTAL NUMBER OF COPIES REQUIRED: LTTR 68 ENCL-68
w Mw Iowa Electric Light and Ibwer Company March 25, 1981 DAEC-81-171 Mr.
James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission -
Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Licensee Event Report No.81-010 (30 day)
File:
A-118a
Dear Mr. Keppler:
In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold Energy Center and Regulatory Guide 10.1, please find attached a copy of the subject Licensee Event Report.
(Total of 3 copies transmitted).
Ve truly yours, Daniel L. Mineck Chief Engineer Duane Arnold Energy Center DLM/M$SR/pl Docket 50-331 attachment cc:
Director, Office of Inspection and Enforcement (30)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Director, Management Information and Program Control (3)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D. C.
20555 NRC Resident Inspector -
DAEC Duane Arnold Enemv Center
- Cedar Rpids, Iowa 52406 319/851-5621
NFIC FOR 17-774 M 388 LICENSEE EVENT REPORT CONTROL 8LOCK:
PLEASE ?RINT OR Ty"'i ALL REQUIRED INFORMATION)
Llj 1
I 1
01 1-1 ololololol-hono 03111 TIIL0.
7 8 9 C
LICENSCELICENS NUMER 25 26 LICENSE TYPE 40 57 CAT sa
- - CON'T E
LL 10 5 10 [0 01 31 3 I L LT a
01 31 21 5 8 1 8Z
- - 1 COCK ETNUMSAR 6a 69
- VENT DATE 74 7S REPORT DATE 80 EVENT OESCRIPTION AND PROSA8LE CONSEQUENCES Durn surveillance testing of the.-Standb' Filter Units.(SBFU) the-a or SBFU "B" was found not runningduring an operational test. Investigati.....
on revealed the breaker for the Control BidL Emerq Air Supply Fan, 1V-SF 30B,..hadbeen opened byOperations personnel. Tech.Spec 3 a both trains of the SBFU to be operable during reactor operation. The "A" SBFU had previously been operationally tested sat. No previous occurrence s of this nature have been recorded.
I a89 80 SYSTEM
CAUSE
CAUSE COMP.
VALVe CODE COoE SUBCOOE COMPCNENT CO0E SU8CO0E SUSCOOS SG LA (5 A
' B I L 1 0 WIEI R Z
LjD 7
3 S
10 it 12 13 IS 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION O PRO rEVENT YEAR REPORT NO.
CODE TYPE NO.
of1 11 0 1
0L.
L 0
2uI 1 2
23 24 26 27 28 29 30 31 32 C7ION FUTURe EFFECT SHUTOOWN ATTACHMENT NPRO4 PRIMECOMPOMPONENT TAKEN ACTION ONPLANT METHCO HOURS SUBMITED FORM US.
SUPPLIER MANUFACTURER r[_@
IZJ LzJ 1oool 1! LYNJ@ J 1J@
Z 10 111 33 34 35 36 37 Qo 41 42 43 47 CA;EE DESCRIPTION AND CORRECTIVE ACTIONSs 71 1 Personnel error. Preventative mainte er be opened. Ops personnel inadvert jr instead. This interrupted operatio
( in to be inop. Brkr open for aporox 1 I sat. Ops personnel reinstructed. Pla FACILI STATUS
% POWER OTHER STATUS IJ [E
Of 9 1 5I 1 NA 7
83
!0 12 tT 44 ACTIVt T CONTENT PELEASE0 0% R5EASE AMOUNT OF ACTIVITY L7J LOLB INA 1
3 9 to II 4
- SRONNEL ixPCSURE2 umiaEA 307Y OESCRIPTi N S0 LOOIJO NA 1.
9 11
!3 13
?5SCSONNEL INJURES ol n Lo n
W1 NA 7
8 I 1 12 LOSS OF OR OAMAGE TO XAC:LIT;Y TYPE ZESCRIP71ON ZZ li NA 8 9 10 Ou8tlCITY DOESCRIPTION
&opesy Matthew Si Raqe nance on "A" SBFU required its break ently ooened the "B" SBFU fan breake nal run of "B" SBFU and caused B-tra 0.5 hrs. Operational test completed nt procedures will be reviewed.
METHOO Cf OISCOVER V OISCOVERY OESCRIPTrOM 32 SB j(ei Surveillance Testing
'5 s4 80 NA 45 LOCATION Of RELEA5E 80 SO 80 NRC USE ONLY 68 69 90 319,851-5611 I
U. S. NUCLEAR REGULATORY COMMSSION 1
.DUANE ARNOLD ENERGY CENTER Iowa Electric.Light and Power Company Licensee Event Report -
Supplemental Data Docket No. 050-0331 Reportaole Occurrence No:
8' 00 During surveillance testing of the Standby Filter Units (SBFU),
the "B"
SBFU was discovered to be not running during a
10-hour operational run.
Investigation revealed that the breaker for the Control Building Emergency Air Supply
- Fan, IV-SF-30B, had been opened by Operations personnel.
The breaker was closed and operational test restarted.
The "B"
SBFU was out of service for approximately 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Technical Specification 3.10.A.3 requires both SBFUs to be operable during reactor operation.
The "A"
train of SBFU had previously completed its 10-hour operational.
test satisfactorily.
No previous occurrences of this nature have been recorded.
Cause
Description:
Personnel error.
Operations.
personnel had begun the 10-hour operational run of the "B"
SBFU when its breaker was mistakenly opened.
Maintenance personnel had been instructed to perform lubrication on the "A"
SBFU.
To provide for their safety the breaker for that unit's fan was to be opened prior to maintenance.
Poor communications between ops personnel resulted in the wrong breaker being opened.
Corrective Action:
Ops personnel discovered the "B"
SBFU wasn't running at the scheduled completion of its 10-hour run.
Investigation revealed the wrong breaker had been opened and not reclosed following maintenance.
The breaker was closed and the operational test completed with satisfactory results.
Plant procedures will be reviewed to determine if weaknesses which may have contributed to this event can be identified and eliminated.
Operations personnel have been reinstructed on the need to
- monitor, more
- closely, maintenance on safety-related equipment.
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| 05000331/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000331/LER-1981-002-03, /03L-0:on 810106,temp Switch Tis 4477,zone 2, Tripped Outside Tech Spec.Caused by Instrument Drift.Switch Recalibr | /03L-0:on 810106,temp Switch Tis 4477,zone 2, Tripped Outside Tech Spec.Caused by Instrument Drift.Switch Recalibr | | | 05000331/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000331/LER-1981-003-03, /03L-0:on 810108,drywell Particulate Radiation Element Re 8101B Found Inoperable.Caused by Sensor Failure Due to Condensation on Particulate Detector.New Radiation Element,Mylar Window & Beta Phosphor Installed | /03L-0:on 810108,drywell Particulate Radiation Element Re 8101B Found Inoperable.Caused by Sensor Failure Due to Condensation on Particulate Detector.New Radiation Element,Mylar Window & Beta Phosphor Installed | | | 05000331/LER-1981-004-03, /03L-0:on 810111,drywell Particulate Radiation Monitor B Failed Downscale.Caused by Condensate on NMC Model RAK-221F Radiation Element Re 8101B.Design Review Initiated & Particulate & Iodine Filters Examined Daily | /03L-0:on 810111,drywell Particulate Radiation Monitor B Failed Downscale.Caused by Condensate on NMC Model RAK-221F Radiation Element Re 8101B.Design Review Initiated & Particulate & Iodine Filters Examined Daily | | | 05000331/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000331/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000331/LER-1981-007-03, /03L-0:on 810219,during Normal Operation,Pressure Differential Across RHR Svc Water Strainer 1S-90B Read High, Resulting in Loop B Inoperability.Caused by Sand Plugged in Strainer Mesh.Strainer Cleaned | /03L-0:on 810219,during Normal Operation,Pressure Differential Across RHR Svc Water Strainer 1S-90B Read High, Resulting in Loop B Inoperability.Caused by Sand Plugged in Strainer Mesh.Strainer Cleaned | | | 05000331/LER-1981-008-03, /03L-0:on 810212,during Preventive Maint, Recirculation Pump B Tripped Upon Restart,Recirculation Pump Motor Hi/Lo Oil Level Alarm Activated & Would Not Clear.Caused by Lack of Oil in Recirculation Pump Motor B | /03L-0:on 810212,during Preventive Maint, Recirculation Pump B Tripped Upon Restart,Recirculation Pump Motor Hi/Lo Oil Level Alarm Activated & Would Not Clear.Caused by Lack of Oil in Recirculation Pump Motor B | | | 05000331/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000331/LER-1981-010-03, /03L-0:on 810224,fan for Standby Filter Unit B Found Not Running During Operational Test.Caused by Personnel Error in Opening Breaker for Control Bldg Emergency Air Supply Fan.Personnel Reinstructed | /03L-0:on 810224,fan for Standby Filter Unit B Found Not Running During Operational Test.Caused by Personnel Error in Opening Breaker for Control Bldg Emergency Air Supply Fan.Personnel Reinstructed | | | 05000331/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000331/LER-1981-011-03, /03L-0:on 810310,condensate Storage Tank a Low Level Switch LS 5218 Was Found Inoperable.Caused by Moisture on Probe Leads within Terminal Box.Moisture Removed.Switches Will Be Rewired | /03L-0:on 810310,condensate Storage Tank a Low Level Switch LS 5218 Was Found Inoperable.Caused by Moisture on Probe Leads within Terminal Box.Moisture Removed.Switches Will Be Rewired | | | 05000331/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000331/LER-1981-012-01, /01T-0:on 810321,pump Discharge Valve MOV 4628 Would Not Close W/Control Room Switch.Probably Caused by Burned Contacts at Motor Control Center.Contacts Replaced | /01T-0:on 810321,pump Discharge Valve MOV 4628 Would Not Close W/Control Room Switch.Probably Caused by Burned Contacts at Motor Control Center.Contacts Replaced | | | 05000331/LER-1981-012, Forwards LER 81-012/01T-0 | Forwards LER 81-012/01T-0 | | | 05000331/LER-1981-013-01, /01T-0:on 810324,MSIVs 4412,4413,4416,4418,4419, 4420 & 4421 Found W/Seat Leakage on Inboard & Combined Seat & Steam Leakage on Outboard Valves.Cause Under Investigation.Valves Will Be Repacked & Repaired | /01T-0:on 810324,MSIVs 4412,4413,4416,4418,4419, 4420 & 4421 Found W/Seat Leakage on Inboard & Combined Seat & Steam Leakage on Outboard Valves.Cause Under Investigation.Valves Will Be Repacked & Repaired | | | 05000331/LER-1981-013, Forwards LER 81-013/01T-0 | Forwards LER 81-013/01T-0 | | | 05000331/LER-1981-014-01, Four Relief & Safety Valves Found Out of Spec.Cause Unknown.Relief Valve Pilot Assemblies Cleaned,Reworked & Satisfactorily Retested. Safety Valve Will Be Disassembled & Reworked | Four Relief & Safety Valves Found Out of Spec.Cause Unknown.Relief Valve Pilot Assemblies Cleaned,Reworked & Satisfactorily Retested. Safety Valve Will Be Disassembled & Reworked | | | 05000331/LER-1981-014, Forwards Updated LER 81-014/01X-1 | Forwards Updated LER 81-014/01X-1 | | | 05000331/LER-1981-015, Updated LER 81-015/01T-1:on 810421,lower Crankshaft 14 Bearing Found Wiped on Journal Surface Similar to Problem Identified on Diesel 1G-31.Caused by High Temp.Bearing Replaced & Crankshaft Relapped | Updated LER 81-015/01T-1:on 810421,lower Crankshaft 14 Bearing Found Wiped on Journal Surface Similar to Problem Identified on Diesel 1G-31.Caused by High Temp.Bearing Replaced & Crankshaft Relapped | | | 05000331/LER-1981-016, Updated LER 81-016/01T-1:on 810421,lower Crankshaft Thrust Bearing 13 & Adjacent Bearing 12 Found Wiped on Journal Surface.Caused by High Temp.Crankshaft Thrust Bearings Replaced & Crankshaft Relapped | Updated LER 81-016/01T-1:on 810421,lower Crankshaft Thrust Bearing 13 & Adjacent Bearing 12 Found Wiped on Journal Surface.Caused by High Temp.Crankshaft Thrust Bearings Replaced & Crankshaft Relapped | | | 05000331/LER-1981-019-01, /01T-0:on 810526,found Tech Spec Surveillance Requirements for Determining River Water Supply Sys Pump TDH Not Being Met.Caused by Limits on Nameplate Data Being Too Stringent for Normal Operation | /01T-0:on 810526,found Tech Spec Surveillance Requirements for Determining River Water Supply Sys Pump TDH Not Being Met.Caused by Limits on Nameplate Data Being Too Stringent for Normal Operation | | | 05000331/LER-1981-020, Forwards LER 81-020/01T-0 | Forwards LER 81-020/01T-0 | | | 05000331/LER-1981-020-01, /01T-0:on 810527,primary Containment Integrity Breached When Inner & Outer Airlock Doors Were Open Simultaneously While H/P Technician Exited Drywell.Cause Unknown | /01T-0:on 810527,primary Containment Integrity Breached When Inner & Outer Airlock Doors Were Open Simultaneously While H/P Technician Exited Drywell.Cause Unknown | | | 05000331/LER-1981-021-03, During Reactor Startup, Suppression Chamber to Drywell Vacuum Breaker Valve Cv 4237H Did Not Close After Torus Inerting.Caused by Pneumatic Cylinder Piston Sticking in mid-position | During Reactor Startup, Suppression Chamber to Drywell Vacuum Breaker Valve Cv 4237H Did Not Close After Torus Inerting.Caused by Pneumatic Cylinder Piston Sticking in mid-position | | | 05000331/LER-1981-021, Forwards Updated LER 81-021/03X-1 | Forwards Updated LER 81-021/03X-1 | | | 05000331/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000331/LER-1981-022-03, /03L-0:on 810607,during Testing,Reactor Core Isolation Cooling Turbine Repeatedly Tripped on Overspeed on Fast Starts.Caused by Upward Drift of Flow Controller FIC-2509 High Limit Setpoint.Setpoint Recalibr | /03L-0:on 810607,during Testing,Reactor Core Isolation Cooling Turbine Repeatedly Tripped on Overspeed on Fast Starts.Caused by Upward Drift of Flow Controller FIC-2509 High Limit Setpoint.Setpoint Recalibr | | | 05000331/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000331/LER-1981-023-03, /03L-0:on 810611,during Surveillance Testing, Reactor Core Isolation Cooling Steam Line High Flow Pressure Differential Switch Pdis 2442,tripped at 100 Inches of Water.Caused by Instrument Drift.Switch Recalibr | /03L-0:on 810611,during Surveillance Testing, Reactor Core Isolation Cooling Steam Line High Flow Pressure Differential Switch Pdis 2442,tripped at 100 Inches of Water.Caused by Instrument Drift.Switch Recalibr | | | 05000331/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000331/LER-1981-024-03, /03L-0:on 810616,drywell Equipment Drain Line Valve CV-3729 Did Not Give Fully Closed Indication During Testing.Caused by Seat Leakage in Solenoid Valve SV-3729. Solenoid Valve Replaced | /03L-0:on 810616,drywell Equipment Drain Line Valve CV-3729 Did Not Give Fully Closed Indication During Testing.Caused by Seat Leakage in Solenoid Valve SV-3729. Solenoid Valve Replaced | | | 05000331/LER-1981-025-03, /03L-0:on 810616,RHR B Svc Water Pump Did Not Develop Required Discharge Pressure at Rated Flow.Caused by Normal Wear Creating Excessive Clearances Between Impeller & Casing Rings.Impellers Adjusted | /03L-0:on 810616,RHR B Svc Water Pump Did Not Develop Required Discharge Pressure at Rated Flow.Caused by Normal Wear Creating Excessive Clearances Between Impeller & Casing Rings.Impellers Adjusted | | | 05000331/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000331/LER-1981-026-03, /03L-0:on 810615,containment Atmosphere Monitoring Sys B Was Found Operating W/O Sample Point Selected.Caused by Personnel Error.Particulate Radiation Element Replaced | /03L-0:on 810615,containment Atmosphere Monitoring Sys B Was Found Operating W/O Sample Point Selected.Caused by Personnel Error.Particulate Radiation Element Replaced | | | 05000331/LER-1981-027-03, /03L-0:on 810620,radiation Monitor RM-4101A Failed Upscale.Caused by Component Failure.Equipment Drawer Replaced | /03L-0:on 810620,radiation Monitor RM-4101A Failed Upscale.Caused by Component Failure.Equipment Drawer Replaced | | | 05000331/LER-1981-027, Forwards LER 81-027/03L-0 | Forwards LER 81-027/03L-0 | | | 05000331/LER-1981-028, Forwards LER 81-028/03L-0 | Forwards LER 81-028/03L-0 | | | 05000331/LER-1981-028-03, /03L-0:on 810703,during Control Room Panel Check, HPCI Pump Discharge Flow Indicating Controller FIC-2309 Found Indicating Low.Caused by Erroneous Indication of HPCI Flow Rate Due to Air Lock in HPCI Flow Indication Lines | /03L-0:on 810703,during Control Room Panel Check, HPCI Pump Discharge Flow Indicating Controller FIC-2309 Found Indicating Low.Caused by Erroneous Indication of HPCI Flow Rate Due to Air Lock in HPCI Flow Indication Lines | | | 05000331/LER-1981-029-03, /03L-0:on 810701,during Testing,Containment Atmosphere Monitoring Sys (Cams) a Found to Be Operating W/O Sample Point Having Been Reselected.Cams B Inoperable Due to Testing.Caused by Personnel Error | /03L-0:on 810701,during Testing,Containment Atmosphere Monitoring Sys (Cams) a Found to Be Operating W/O Sample Point Having Been Reselected.Cams B Inoperable Due to Testing.Caused by Personnel Error | | | 05000331/LER-1981-029, Forwards LER 81-029/03L-0 | Forwards LER 81-029/03L-0 | | | 05000331/LER-1981-030, Forwards LER 81-030/03L-0 | Forwards LER 81-030/03L-0 | | | 05000331/LER-1981-030-03, /03L-0:on 810701,torus Atmosphere Sampling Line Isolation Valve SV-8108A Would Not Close During Testing. Caused by Rust in Mechanical Portion of Solenoid,Impeding Proper Operation.Solenoid Dismantled & Cleaned | /03L-0:on 810701,torus Atmosphere Sampling Line Isolation Valve SV-8108A Would Not Close During Testing. Caused by Rust in Mechanical Portion of Solenoid,Impeding Proper Operation.Solenoid Dismantled & Cleaned | | | 05000331/LER-1981-031, Forwards LER 81-031/03L-0 | Forwards LER 81-031/03L-0 | | | 05000331/LER-1981-031-03, /03L-0:on 810820,reactor Core Isolation Cooling Suppression Pool Area Steam Leak Detection Temp Differential Switch TDS-2521C Found Tripping at Value Exceeding Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr & Tes | /03L-0:on 810820,reactor Core Isolation Cooling Suppression Pool Area Steam Leak Detection Temp Differential Switch TDS-2521C Found Tripping at Value Exceeding Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr & Tested | | | 05000331/LER-1981-032-03, /03L-0:on 810812,containment Atmosphere Monitoring Sys a & B Found to Be Operating W/O Reselection of Sample Points,Resulting in Containment Atmosphere Not Being Monitored.Caused by Personnel Error.Design Review Initiated | /03L-0:on 810812,containment Atmosphere Monitoring Sys a & B Found to Be Operating W/O Reselection of Sample Points,Resulting in Containment Atmosphere Not Being Monitored.Caused by Personnel Error.Design Review Initiated | | | 05000331/LER-1981-032, Forwards LER 81-032/03L-0 | Forwards LER 81-032/03L-0 | | | 05000331/LER-1981-033, Forwards LER 81-033/03L-0 | Forwards LER 81-033/03L-0 | | | 05000331/LER-1981-033-03, /03L-0:on 810817,reactor Core Isolation Cooling Sys Declared Inoperable to Replace Motor Operated Full Flow Test Valve MOV-2515.Caused by Pinhole Leak in Valve Body. Valve Hydrostatically Tested | /03L-0:on 810817,reactor Core Isolation Cooling Sys Declared Inoperable to Replace Motor Operated Full Flow Test Valve MOV-2515.Caused by Pinhole Leak in Valve Body. Valve Hydrostatically Tested | |
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