LER-1981-011, /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 |
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REGULARY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8104140507 DOC.DATE: 81/04/06 NOARIZED: NO FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow AUTH.NAME!
AUTHOR AFFILIATION RAGER#M.S.
Iowa Electric Light&
Power Co.
RECIP.NAMEi RECIPIENT AFFILIATION..
Region 3, Chicago, Office of the Director
SUBJECT:
DOCKET #
05000331 LER 81-011/03LP0:on 810310,condensate storage tank A low level switch LS 5218 was found inoperableCaused by moisture on probelleads within terminal boxMoisture removed.Switches will berewired.
DISTRIBUTION CODE: A0028 TITLE!: Incident Reports COPIES RECEIVED:LTR L ENCL L.
SIZE:
NOTES:
RECIPIENT ID CODE/NAMEi ACTION:
IPPOLITOIT 04' INTERNAL: A/D COMP&STRU06 A/D MATL:&
QU08 A/D PLANT SYSI.
A/D SFTY ASSEI2.
AEOD ASLBP/J*HARD CHEM ENG BR 16 CORE'PERF BR 18 DIRHUM FAC 321 EFF TR SYS BR23 GEOSCIENCES 26 I&E 05 LIC GUID BR 30, MECH ENG BR 33, NRC PDR 02 OR ASSESS BR 35 RAD ASSESS 8R39 c
- 01.
S EVA42 SYS INTERAC S45 EXTERNAL: ACRS NSIC 46 05 COPIES' LTTR ENCL 3
3 RECIPIENT' ID CODE/NAME COPIES LTTRENCL A/D ENV TECH 07 A/D OPREACTO09 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 JORDAN,E,/IE MATL ENG BR 32 MPA OP.EX EVAL BR34 POWER SYS BR 36 REACT SYS BR 40 REL & RISK A 41 STRUCT ENG BR44 16 1
16 1
LPDR 03 1
1 68 TOTAL NUMBER OF COPIES REQUIRED: LTTR I
? -
1981 68 ENCLI
Iowa Electric Light and Pbwer Company April 6, 1981 DAEC-81-205 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.81-011 (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).
Very truly yours, Daniel L. Mineck Chief Engineer Duane Arnold Energy Center DLM/MSR/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 Enermv Center
- Cedar apids, loy 5406 319/851 -6APR 8
1981
NRC POS (7-")_
,go.
LICENSEE EVENT REPORT CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
I IA ID IA IC 11 k120 [-L-0 0 1 1 Q10 1-101 4 1 1 1 I.IJL4 I
9 LICENSES CODE 14 15 LICENSE NUM8ER 25 26 LICENSE TYPE JO 57 CT s SOE (0 15 10 10 1013131 1 8-013111018 1 10,141016181110 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 79 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES S,.-
CGNE 7
8 S8 7
8]
7
]8 SYSTEM
CAUSE
CAUSE COMP.'
VALVE CODE coos SUSC006 COMPONENT CO0S SUGCO06 SUSCODE IW I Fl(q) L-l] (
LJ (3) 1 11 NI sl TI RI ul31 LJ )
IJ 6
9 10 1t 12 13 18 19 32 SEQUENTIAL OCCURRENCE REPORT 0
LE/RO EVENTYEAR REPORTNO.
co0 TYPE REPORT; LJLJ L=
0 1 11 11 L;dL:L:-LU b:J NUMBER 18 11a.
Lj'.~i 3.i LL LUL Li r21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTOOWN ATTACHMENT NPRO-A PRIME COMP.
TAKEN ACTION ON PLANT METHOO HOURS 22 SUSMITTED FORM sUS.
SUPPLISR UU LI@
L2@1O 10 lo 10 10 1
LN.J@
LU.JD UAJ @
I 33 34 35 38 37 4
41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS REVISION NO.
L0 32 COMPONENT MANUFACTUREA BI 0 01 sl@
L4 47 IMoisture on the probe's leads within 11 1 qnal to be grounded, Moisture was re izIT evel switch was retested with sat re 13 jswitches will be rewired to run susp 1477I o a watertight pull box on top of CS 78 3 FACILITY STATUS POWER OTHER STATUS LE]
10 1921@
NA 7
8 9
1012 1
ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY 16 L.J @ LO I NA 7
19 10 44 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
I 0 1 o0 01z 161 NA 7
8 9
It 12 13 PERSONNEL INJURIES NUMBER OESCRIPTION 41 1
OOj 0 0
NA 7
8 9
1t 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
19 O@I NA 7
8 9 10 PUBLICITY ISSUED OESCRIPTION L S@I NA 7
8 9
10 NAME OF PREPARER Matthew S. Rager the terminal box caused the trip si moved from leds aind terminail box. L sults. During 1981 refuel, bothilevelI ension wires from electrode holder t T. Conduits to be sealed with RTV.
METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 jB lI(TISurveillance Testing 45 46 80 I
NA 4s LOCATION OF RELEASE so 80 80 so NRC USE ONLY 68 69 8o.;
0 PHONE:
.319-851-5611 M 366 U. S. NUCLEAR REGULATORY COMMISSION l uuring surveillance testing or tne-Condensate Storage IanlkCSI) 11-5 I
IA low level switch,.LS 5218 was found inoperable. This switch provides a.
Hlow level alarm forthe CSTs and shifts HPCI pump suction to torus on CS IT low level. Tech Spec 3.2-B requires this switch to be operable during ireactor power operation. LS 5219 was tested and found operating sat. LS I
15218 is a B&W Controller Corp level switch model E1F/50201. Repetitive p Iroblem. See LER 81-005,80-045. and 76-038, 9
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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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