LER-1981-020, /01T-0:on 810527,primary Containment Integrity Breached When Inner & Outer Airlock Doors Were Open Simultaneously While H/P Technician Exited Drywell.Cause Unknown |
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DUANE AidCLD ENERGY CENTER Iowa Electric Light and Power Company Licensee Event Report - Supplemental Data Docket No. 050-0331 Licensee Event Report Date: June 10, 1981 81-20 Reportable Occurrence No:
Event Description
During reactor startup on May 27, 1981 following a refueling outage, ~ primary containment integrity was breached when both the inner and outer airlock doors were momentarily open simultaneously. A Health Physics Technician had entered the drywell to start an air sampler. Upon exiting the drywell the technician closed the inner door completely with the handwheel and " bumped" the handwheel to verify closure. The handwheel pointer also indicated closed.
He then opened the outer door and stepped out of the airlock. The interlock mechanism for the outer door, which was subsequently found to operate properly, would have prevented the opening of' the outer door if the inner door had not been closed. As he was closing the outer door, the inner door opened for unknown reasons. The inner door's interlock mechanism should have prevented any movement of the inner door's locking mechanism once the outer door had been opened. The interlock mechanism for the inner door was found
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inoperable during subsequent investigations. Air had begun to rush into the airlock as the inner door opened. This air movement was caused by the slightly negative pressure maintained in the drywell. The H.P. Technician immediately closed the
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outer door and then cycled the inner door's handwheel back to the closed position.
The drywell was subsequently entered by a maintenance supervisor to inspect the inner door's locking mechanism. The, inner door latching mechanism, which was in the closed position, was holding the door open approximately 3 inches.
No problems were found with the inner door's locking mechanism aside from the interlock mechanism problem. The inner door was shut and airlock exited without further problems.
Subsequently an H.P. Technician again entered the drywell to retrieve the air sampler and he experienced no problems with the airlock. Operations _ personnel chained and locked the handwheels on the outside of the airlock to ensure primary containment integrity was maintained.
Technical Specification 3.7.A.2 requires primary containment integrity be maintained whenever the reactor is critical or when coolant temperature exceeds 212 degrees F.
No releases to the environment occurred as a result of this event. No previous similar occurrences have been reported.
Cause Description An examination of the inner door's locking mechanism by maintenance personnel could detennine no definitive cause for the failure of the inner door to stay closed.
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DUANE ARNOLD ENERGY CENTE't Iowa Electric Light and Power Ccmpany Licensee Event Report - Supplemental Data Docket No. 050-0331 Licensee Event Report Date:
June 10, 1981 Reportable Occurrence No:
81-20 (Continued)
However, the inner door's interlock mechanism which should have prevented the inner door from opening once the outer door was open, was found inoperable.
Further investi-gation revealed that the rod which should have prevented the inner door handwheel from cperating while the outer door was open, was bent.
Corrective Action
The bent rod in the inner door's interlock mechanism was straightened and returned to service. The chain which holds the door in the closed position while the latching mechanism is rotated into place, was tightened. This will provide assurance in the future that the door is being secured in the fully closed position.
All DAEC personnel have been instructed that all primary containment entries shall require the independent verification by one individual from the DAEC Operations Department and one other person that at least one door in the primary containment airlock remains closed at all times whenever the ' primary containment is required.
In addition, following each personnel entry and subsequent exit, both primary contain-
. ment airlock doors shall be chained closed and padlocked.
This ins.truction will remain effective until a design review of the airlock system can be completed to evaluate ~if any equipment modifications are appropriate to preclude the occurrence of similar events.
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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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