LER-1979-016, Forwards LER 79-016/01T-0 |
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| 2371979016R00 - NRC Website |
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CommoAalth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60'\\50 Telephone 815/942-2920 BBS Lt;r. /179-311 April 6,.1979 James G. Keppler, Regional Director Directdrate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen-Ellyn, IL 60137
- Reportable Occurrence Report #79-16/0lT-0, Docket # 050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.1.(C),
abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or.primary containment.
BBS/kmh Enclosure en Station Superintendent
_Dresden Nuclear Power Station CC:
Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC REGUU\\10RY DOCl\\ET FIL£ COPY, 7904160 \\/O
ATTACHMENT TO LICENSEE EVENT REPORT 79-016/0lT-0.
COMMONWEALTH EDISON COHPANY (CWE)
DRESDEN UNIT 2 * (ILDRS-2)
DOCKET II 050-237 During the current refueling outage, workers discovered water dripping from an elbow on a drain line from the bottom of LPCI testable check valve 2-1501-25.
All leakage was contained inside the drywell and directed to the Drywell Floor Drain System.
Upon further investigation the leakage was determined to be coming from a crack in.the weld on the elbow.
The weld was cracked 360° around the pipe..
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Calculations showed that a complete severance of a l" line such as this*
would be well within the capabilities of ECCS systems.
The defective weld was ground out, repaired and dy.e. penetrant tested following approved procedures; The weld failure was apparently* due to an improper pipe fitup prior to welding* the. pipe originally i.e., pipe bottomed out in the socket..
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- 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
!During refueling, water was discovered to be dripp.ing from an elbow in the drain line 1 [2JI] ion a LPCI check valve.
This event was of minimal safety significance because all leak-J J j CQ:0 !age was contained in the Drywell Floor Drain System and the potential leakage, con-i []J:IJ 1sidering a complete severance of the l" line is well within the capabilities of the
Previous occurrence reported as R.O. #50-237/1977-10
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Defective weld was ground out, repaired IJ))] 1and dye-penetrant tested in accordance with approved procedures.
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| 05000237/LER-1979-001-03, /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | /03L-0 on 790103:torus Level Increased to -1 Inch, Due to Repetitive Starts of HPCI Turbine.Increase in Torus Level Determined to Be Result of Inadequate Procedure.Hpci Surveillance Procedures to Be Amended | | | 05000237/LER-1979-001, Forwards LER 79-001/03X-1 | Forwards LER 79-001/03X-1 | | | 05000010/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000010/LER-1979-001-03, /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | /03L-0 on 790518:while Digging Ditch for New Pipe, Const Personnel Observed Water Running Into Trench from Proximity of Radwaste return-to-storage Line.Caused by Return Line to 1A Storage Leaking from Aluminum Line | | | 05000010/LER-1979-002-03, /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | /03L-0 on 780825:during Monthly Surveillance DI5 5400-2,offgas Monitor 1 Tripped at Greater than 100%, Which Is Not within Setpoint Limit.Caused by Instrument Drift.Setpoint Recalibr | | | 05000010/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000237/LER-1979-002, Forwards LER 79-002/01X-1 | Forwards LER 79-002/01X-1 | | | 05000237/LER-1979-002-01, /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | /01X-1 on 790103:during Normal Operation,Hpci Turbine Failed to Start During Quarterly Flow Test.Caused by Partial Engagement of Interlock Dump Valve Operating Lever. Lever Adjusted.Hpci Started to Verify Operability | | | 05000237/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000237/LER-1979-003-03, /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | /03L-0 on 790105:PS 2-1430-1466D Tripped at 105 Psi.Caused by Instrument Drift | | | 05000237/LER-1979-004-03, /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | /03L-0 on 790111:LPCI Sys Full Flow Test Valve MO-2-1501-38B Failed While Securing D LPCI Pump.Caused by Broken Pinion Gear on Valve Operator Motor Shaft | | | 05000237/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000237/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000237/LER-1979-005-03, /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | /03L-0 on 790119: During Normal Operation, Mass Spectometer Leak Detector Downscale Condition Annunciated & High Rad Alarm & Half Scram Occurred Twice on Same Day. Log Rad Monitor Replaced | | | 05000237/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000237/LER-1979-008-03, /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | /03L-0 on 790126: LPCI Min Flow Value MO-2-1501-13A Failed to Close Completely During LPCI Pump Operability Surveillance.Cause of Failure Unknown | | | 05000237/LER-1979-009-03, /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | /03L-0 on 790121:plant Chimney Sampling Sys Operating Incorrectly.Caused by Purge Valve V2 Being Stuck Open | | | 05000237/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000237/LER-1979-010-01, /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | /01T-0 on 790202:section of Blowout Panel Blown Out,Breaching Secondary Containment.Cause Under Investigation | | | 05000237/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | | | 05000237/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000237/LER-1979-013-03, /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | /03L-0 on 790223:after Diesel Generator Was Manually Started Prior to Taking Transformer Out of Svc, Water Pump Breaker Thermally Tripped & Redundant Power Supply Also Tripped.Cause Unknown | | | 05000237/LER-1979-014-03, /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | /03L-0 on 790305:U2 Diesel Generator Failed to Start on First & Fifth Attempts.Caused by Bendix Gear Failure to Engage & Failure of Air Start Solenoid to Energize.Solenoid Was Replaced | | | 05000237/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000237/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000237/LER-1979-016, Forwards LER 79-016/01T-0 | Forwards LER 79-016/01T-0 | | | 05000237/LER-1979-017-01, X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Saf | X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety Feature Sys | | | 05000237/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | | 05000237/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000237/LER-1979-020-03, /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | /03L-0 on 790413:measured Leakage for Personnel Air Lock Was 54.63 Std Cubic Ft/H.Leakage Identified Through Outer Lower Handwell.Shaft Packing Was Replaced & Air Lock Retested | | | 05000249/LER-1979-021-03, /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | /03L-0:on 790821,during Normal Operation,Offgas Monitor 3A Took Step Increase W/No Power Change & hi-hi Trip Light Was On.Caused by Faulty V1 Electrometer Tube,Which Was Replaced.Monitors Will Be Tested Monthly | | | 05000237/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000237/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000237/LER-1979-023-03, /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | /03L-0 on 790406:during Radioactive Insp,Lack of Fusion Noted in Weld 4-4 on 4-inch Reactor Head Vent Line 2-0215-4.Weld Cut Out & Rewelded Per ASME Boiler & Pressure Vessel Code.Asme Hydrostatic Test Completed | | | 05000249/LER-1979-023-03, /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | /03L-0:on 790823,source Range Monitor Calibr Supplied Rod Block Trip at 1.03E5,exceeding Tech Specs Limit.Caused by Drift & Temp Dependency in Source Range Monitor.Defective Component Not Yet Identified | | | 05000237/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000237/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000249/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000237/LER-1979-027-03, /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | /03L-0 on 790502:during Startup,Main Turbine Tripped on High Water Level.Caused by Packing Leak on Isolation Valve for PS-263-60B.Packing Adjusted,Tested & Sys Lineup Returned to Normal | | | 05000237/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000249/LER-1979-027-03, /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | /03L-0:on 791003,half of Trip Sys Inoperable Due to Lifting of Flooding Magnetrol Switch Leads to Condenser Pit.Switch Leads Reattached.No Precise Cause Found | | | 05000237/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000237/LER-1979-028-03, /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | /03L-0 on 790508:N2 Line Low Temp Alarm Received & Frost Found on Inerting line.A0-2-1601 & Inerting Line Failed Leak Rate Test.Caused by Failure of Temp Recorder at N2 Vaporizer | | | 05000237/LER-1979-029-03, /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | /03L-0 on 790508:DIS 1400-3,pressure Switch 2-1430-1466D Failed to Trip.Caused by Sticky Plunger in Pressure Switch.Switch Removed,Cleaned & Reset to Trip at 94.5 Psig Increasing | | | 05000237/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000249/LER-1979-030-03, During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | During Scram Testing in Refuel Mode,Substantial Loss of Position Indication Noted for Control Rod Driveline H-9.Caused by Improperly Seated Socket,Suggesting Faulty Electrical pin-socket Alignment | | | 05000249/LER-1979-030, /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9 | | | 05000237/LER-1979-031-03, /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | /03L-0 on 790509:crack Found on 2D1 Feedwater Emergency Spill to Condenser Line & Crack Located on Pipe to Condenser Weld.Caused by Mechanical Failure.Cracked Portion Removed & Rewelded | | | 05000237/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000237/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | |
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