LER-1981-004, /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 |
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REGULATO*)NFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8102120120.
DOCDATE: 81/02/05 NOTARIZED: NO DOCKET #
FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTH.NAME AUTHUR AFFILIATION
- RAGERMS, Iowa Electric Light & Power Coo RECIP.NAMET RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director
SUBJECT:
LER 81"004/03L-0:on 810111,drywell particulate radiation monitor 8 failed downscale.Caused by condensate on NMC Model RAK-221F radiation element RE 8101B,Design review initiated
& particulate.& iodine filters examined daily*
DISTRIBUTION CODE: A0028 TITLE: Incident Reports COPIES RECEIVED:LTR -ZENCL,
SIZE:.,
W NOTES:
RECIPIENT ID CODE/NAME, ACTION:
IPPOLITOT. 04 INTERNAL: A/D COMP&STRU06 A/ MATL & QU08 A/D PLANT SYSO.
A/D SFTY ASSE12 AEOD AUX SYS BR 15 CONT SYS BR 17 DIRDIV OF LIC DIRHUM FAC $21 EFF TR SYS BR23c GEOSCIENCES 26 I&E 05 LIC GUID BR
- 30.
MECH.ENG BR 33 NRC PDR 02 OR ASSESS BR 35.
SBR39 FILE 01
' 8FTYZ E VA 42 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 ASLBP/J.HARD CHEM ENG BR 16 CORE PERF BR 18 DIRENGINEERI20 DIRSYS INTEG22 EQUIP QUAL BR25 I&C SYS BR 29 JORDANE,/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 COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
.1 1
3 35 1
1 1
1 EXTERNAL; ACRS NSIC 46 05i 16 1
16 1
LPDR 03 1
TERA:DOUG MAY 1
A.% At TOTAL NUMBER OF COPIES REQUIRED: LTTR
/
1 1
Lb 68 ENCL 68
Iowa Electric Light and Power Company
_U February 5, 1981 DAEC-81-82 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.81-004 (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 Docket 50-331 attachment DLM/MSP/pJ 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 Huane Arnoid Energy Center
NRCFOR (771~R 7
a CON'T 7
8 7
8 7
8 REVISION NO.
LOJ COMPONENT MANUFACTURER Ni - n 15@
4 17 i7' IThe cause was determined to be condensate on RE 8101B.
The moisture was TI removed from the detector prior to beinq reinstalled. The detector was 1 ource checked-sat. RE 81018 is an NMC model RAK-221F radiation element.
1]
Design review has been initiated As an interim measure HP personnel are 1 exaining the particulate and iodine filters once per day.
FACILITY 30 METHOO OF STATUS
% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION G
([
LJ I Q19 19 Ji NA I AJOiOperator Observation 7
8 9
10 12 11 44 45 46 30 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE EID LzJ @ LzJ l
NA I
NA 1
7 a
9 10 iI 4
s5 80 PERSONNEL ExPOSURES NUMBER TYPE
DESCRIPTION
m7 1 In Wo01 7 I@)
NA 7
8 9 I1 12 13 80 PERSONNEL INJURIES NUMBER DESCRPTION S 1 o oL01 NA I
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
'T 1 I1I NA I
7 8
9 10 80 PUBLICITY NAC USE ONLY ISSUED
DESCRIPTION
7 8
9 10 68 69 80*.
319-851-5611 LICENSEE EVENT REPORT CONTROL SLOCK:
(PLEASE PRINT OR TYod ALL REQUIRED INFORMATION) lA ID A IC 11 10I 001 0 -1 0 10 1 Q0Q1 0 1 01 --0 0 (DI4111L.111 n
9 LICENSEE CODE 14 is LICENSE NUMBER 25 26 LICFNSE TYPE 30 57 AT 58 RR LL 10 15 10 0 1 01 313 1
- 0) 1 1 1 [ b 1t1 01 21 01 51 81 110 60 61 COCKEY NUMBER 6a 69 EVENT DATE 7
75 REPOAT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During normal power operation the "B" Drywell Particulate Radiation Moni tor failed downscale. Redundant radiation monitor element RE 8101A had p Ireviously been declared inop. This placed the plant in a 7-day LCO in ac cordance with Tech Spec 3.6.C.2 which requires both the sump and air sam I pling systems be operable durinq reactor power neeration Mnisture on th 1
je detector is a repetitive problem. See LER 81-003,81-001, 80-038. 78-0 19, 77-04, and 77-03.
V80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUSCODE COMPONENT CODE SUBCODE SUBCOCE:
cl IL@
E LE@ [
hi NI SI TI RI UI L J L7 9
to It 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT LERRO VENT YEAR REPORT NO.
cos Type (DNUMEl [a ll_
_-J 0I 0 41
-- 1 1 01 3 ILU1 1-N 2ME1R 2
23 24 25 27 29 20
- 1.
ACTION FUTr'pE EFFECT SuTOCwN A-TACHMENT' NI-C.4 PRIMEComm.
TAKEN ACTION ON PLANT METHOO HOURS 2
SUIMITTED FORM tU8.
SUPPLIER L..L1FJ I.
LLzO lo lato [
LLn I 0.@
Lt.JO LL.J@ 1 33 34 35 6
37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS U. S. NUCLEAR REGULATORYV COMMISSION M 316 NAME OF PREPAAEA Matthew S-. Rager
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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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