LER-1980-034, /03L-0:on 800729,during Surveillance Test of Standby Gas Treatment Sys 1 (SGTS 1),overload Trip Was Experienced on SGTS Exhaust Fan 1-8.Probable Cause:Unusually High Ambient Temp Around Fan Motor Control Cubicle |
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3 U. S. NUCLEA3 CEGULATO2Y COMMIS$10N NAC FORM 366 '
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60 on DOCKET NUV8ER 58 69 EVENT QATE 74 75 REPORT D ATE 80 EVENT OESCRIPTTCN ANO PRC8ABLE CONSEQUENCES h i o ! 21_ l On July 29, 1980 during a routine surveillance test of the standbv gas 1
treatment system #1 (SGTS #1), an overload trip was experienced on SGTS I
Io isl l l344; l exhaus e fan 1-8.
Automatic circuitry started SGTS 12 which perfor: led I
ioistl satisf acto rily.
he safety significance of the event is considered I
i;is ; l minimal since SGTS 42-vas available and oper'able if the need for its i
jo;7i l operation had occurred.
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.a CAUSE CESCRIPT?CN AND CCRRECrtVE ACrIONS h It 13i } The accarent cause of the overlead trio was unusuntiv high
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I lt it I I erature around the motor control cubiele for fan 1-8.
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--n-1 I,t2i i cective device was reolaced and SGTS 41 was tested satisfactortiv. An I
1 !s t i engineering investiration is in oretress to dete =ine what sters can he l
f l 141 l taken to avoid recuirence of tries due to hizh a ibient conditions.
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OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 '
1 Licensee Event Report Reportable Occurrence No. 50-219/80-34/ 3L Repor: Date September 2, 1980 Occurrence Date July 29, 1980 Identifi_ation of Occurrence Operation of the Standby Gas Treatment System in a degraded mode as allowed by Technical Specification, paragraph 3.5.B.3 when standby gas treatment system #1 was found :o be inoperable during a scheduled surveillance test.
31s event is considered to be a reportable occurrence in :he Technical Specifi-cations, paragraph 6.9.2.b.2.
Conditions Prior to Occurrence The plant was operating at steady state power.
Power:
Reactor,1660 We Electrical, 542 W e Flow:
Recirculation 13 x 10 3pm Feedwater, 6.00 x 10* lb/hr Pressure:
1020 psig Stack Gas Activity: 4.085 x 103 aci/sec Description of Occurrence On Tuesday, July 29,1980 at 2346 hourt, during a routine surveillance :est of
- he s:andby gas :reatment system I (3GTS !), an overload trip was experienced 1
on SGTS exhaus: fan 1-8.
Automatic circuitry started SGS 92 which perforned satis f acto rily.
Apparent Cause of Occurrence A subsequen investigation revealed that an overload trip on the "3" phase of E? l-3 had occurred. S e apparen: cause for the overload trip was an unusually high x2 bien: :*mperature around the noter control cubicle (106*y).
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Analvsis of Occurrence
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Standby gas treatment system is 'used to process the reactor building atmosphere should conditions be' present which require its operation ~ Although SGTS ~ fl s-
,became~1noperable. SGTS 12 did' initiate and performed as designed.
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The. safety ' significance of this event is considered minimmi since SGTS #2 was available and operable if the need for'its operation had occurred.
Corrective Action
'SGTS 11 (Fan 1-8) was. removed from service and the overload protective device-a replaced. An operability test was performed to prove the' system operable.
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' As part of the investigation of the overload trip, the =otor control center breakers for SGTS 11~ (I71-8) and SGTS, d2 (IF 1-9) and their related fusos.
. breakers and overloads were checked and found to be satisfactory.
- - In addition,;the amperage of the motor was found to be in compliance with its design. The full load name place current rating is 12.8 amps. The full lead current was measured at 13.2 amps which is well within the 1.15 rated service s
fac to r.
An Engineering investigation is in progress to determine what steps can be taken m
to" avoid recurrence of trips due to high ambient conditions as experienced.
- - Failure Data General ~Ilectric -
.Model CR124-C028
- - Mocor Overload Relay.
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| 05000219/LER-1980-001-01, /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | /01T-o:on 800105,while Performing Electromatic Relief Valve Operability Test,Emergency Releie Valve D Failed to Open.Caused by Component Failure Due to Retainer Ring Being Backed Off Approx Six Threads | | | 05000219/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000219/LER-1980-002-03, /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised | | | 05000219/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000219/LER-1980-003-01, /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | /01T-0:on 800116,during Inservice Insp on Core Spray Sparger Piping for Sys Ii,Two Indications of Cracks Discovered.Ultrasonic Test Revealed through-wall Cracks. Possibly Caused by Sparger Installation Method | | | 05000219/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000219/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000219/LER-1980-004-03, /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | /03L-0:on 800125,on 800125,29 & 0213,radioactive Water Discovered Leaking from Severely Pitted Aluminum Piping of Condensate Transfer Sys.Caused by Galvanic Corrosion.Leaks Temporarily Repaired & Piping to Be Replaced | | | 05000219/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000219/LER-1980-005-03, /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | /03L-0:on 800205,during Weekly Surveillance of Standby Gas Treatment Sys,Setpoints for Radiation Monitors RNO4A-1 & RNO4A-2 Found to Read Less Conservatively than Tech Spec.Caused by Personnel Error & Instrument Drift | | | 05000219/LER-1980-006-03, /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | /03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift | | | 05000219/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000219/LER-1980-007-03, /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | /03L-0:on 800213,while Performing 10-h Test on Standby Gas Treatment Sys 1,flow Was Less than Tech Spec Limit.Caused by Slipping Drive Belts on Exhaust Fan EF1-8. Drive Belts Replaced | | | 05000219/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000219/LER-1980-008-01, /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | /01T-0:on 800215,during Insp for IE Bulletin 79-14,discovered Nine Pipe Clamps Installed W/O Restraining Welded Lugs.Caused by Oversight During Const.Welded Lugs to Be Installed | | | 05000219/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000219/LER-1980-009-03, During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | During Annual Insp of Containment Spray Heat Exchanges,Leaks Discovered in Four Heat Exchangers.Caused by Component Failure & Design.Heat Exchangers to Be Retubed W/Titanium | | | 05000219/LER-1980-009, Forwards Revised LER 80-009/03L-1 | Forwards Revised LER 80-009/03L-1 | | | 05000219/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000219/LER-1980-010-01, /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | /01T-0:on 800220,during IE Bulletin 79-14 Insp, Pipe hangers,NP-2-R8A & NP-2-R8B Found Improperly Installed. Cleanup Sys Restraint Mod & Nonrigid Restraint Added | | | 05000219/LER-1980-010-03, /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | /03L-1:on 790417,excavation Was Started to Repair Leak Near Inside Penetration within Pipe Tunnel.Activity Was Detected in Soil Near Dedt Line.Dedt Line Rerouted on 800316.Line Will Be Repaired | | | 05000219/LER-1980-011-03, /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | /03L-0:on 800219,during Surveillance Test,Trip Occurred on Standby Gas Treatment Sys 1.Caused by Cracked Flow Sensing Line Which Was Probably Stepped On.Line Replaced | | | 05000219/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000219/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000219/LER-1980-012-03, /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | /03L-0:on 800228,discovered That Weekly Surveillance Tests for Main Station & Diesel Generator Batteries Not Performed During Seventh Wk.Caused by Error in Personnel.Evaluation Will Be Made to Determine Improvements | | | 05000219/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000219/LER-1980-013-01, /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | /01T-0:on 800309,fire Suppression Water Sys Removed from Svc to Replace Cracked Valve,Contrary to Tech Specs.Fire Truck Pumper Used as Water Supply Backup. Cause of Valve Body Crack Under Investigation | | | 05000219/LER-1980-014-01, /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | /01T-0:on 800302,emergency Diesel Generator 1 Failed to Synchronize & Tripped When Generator 2 Was Tagged for Mod.Caused by Component Failure.Fuse F7,found Loose in Holder.Fuseholder Repaired | | | 05000219/LER-1980-014, Forwards LER 80-014/01T-0 | Forwards LER 80-014/01T-0 | | | 05000219/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000219/LER-1980-015-03, /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | /03L-0:on 800403,piston Rod on Closure Mechanism for Reactor Bldg Ventilation Automatic Isolation Valve Was Found Broken,Making Valve Inoperable.Caused by Component Failure.New Piston Rod Eye Stud Was Fabricated & Installed | | | 05000219/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000219/LER-1980-016-01, /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | /01T-0:on 800512,util Recognized That 800420 Discovery of Defective Pressure Switch,Psl D,Constituted Immediate Rept.Caused by Cocked Teflon Actuator.Switch Removed & Will Be Replaced | | | 05000219/LER-1980-017-01, /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | /01T-0:on 800516,while Performing Control Rod Interference checks,green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Caused by Operator & Procedure in Bypass & Component Failure | | | 05000219/LER-1980-017, /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | /03L-0:on 800520,during Investigation of LER 80-17/1T, One Rod Free Travel Interlock Surveillance Requirements Not Performed as Required.Causec by Failure to Perform Procedure & Schedule Surveillance | | | 05000219/LER-1980-018-03, /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | /03L-0:on 800507,during Monthly Surveillance Testing of Reactor High Pressure Scram sensors,RE03D Found to Be Less Conservative than Specified.Caused by Sensor Repeatability.Sensor Reset | | | 05000219/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000219/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000219/LER-1980-020-01, /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watche | /01T-0:on 800605,following Insp of Fire Barriers Protecting safety-related Areas,Several Penetrations Found in Degraded Condition.Caused by Deficiencies in Installation Specs & Personnel Error Re Delay in Establishing Watches | | | 05000219/LER-1980-021, Has Been Cancelled | Has Been Cancelled | | | 05000219/LER-1980-022-03, /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | /03L-0:on 800603,reactor High Pressure Isolation Condenser Initiation Switch Trip Points Found Less Conservative than Specified.Caused by Unusual Svc Condition. Pressure Switches Reset & Exercised to Ensure Operation | | | 05000219/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000219/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000219/LER-1980-023-03, /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | /03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint | | | 05000219/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000219/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000219/LER-1980-025-01, /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | /01T-0:on 800618,during Surveillance Test, Nonfunctioning Operator Discovered in Valves V-9-12 & V-9-8 Found Leaking.Caused by Component Failure.Defective Valves Replaced & Will Be Inspected.Revised Rept Will Follow | | | 05000219/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000219/LER-1980-026-03, /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | /03L-0:on 800709,during Routine Testing Insp of Hydraulic Snubbers Installed in safety-related Sys,Snubber 75/5 Failed to Lock Up in Compression Direction.Caused by Foreign Matl in Snubber Fluid.Snubber Flushed & Refilled | | | 05000219/LER-1980-027, Forwards LER 80-027/01T-0 | Forwards LER 80-027/01T-0 | |
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