LER-1980-007, /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 |
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8 60 si DOCKET NUM3ER 64 SS EVENT DATE 74 75 MEPORT DATE 80 EVENT CESCRIPTloN AND PROBABLE CONSEQUENCES h I O I 21 i On February 13, 1980, while cerforming a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test on Standbv Gas I
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CAusE DESCRtPTION AND CORRECTIVE ACTIONS 27 Iitol l The cause of this occurrence was sliaoina drive belts nn avhwet %
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SGTS #1 was taken out of service after SGTS 42 was confi-ad %
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10 455-8784 NAME OF PREPARER PHONE.
Jersey Central Power & Ught Company kh
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Mornstown, New Jersey o7960 Madison Avenue at Punen Bowt Road (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-7/3L Report Date March 7, 1980 Occurrence Date February 13, 1980 Identification of Occurrence Standby Gas Treatment System (SGTS) #1 was found to be operating with a flow less than that prescribed in the Technical Specifications.
This event is considered to be a reportable occurrence as defined in the Techni-cal Specifications, paragraph 6.9.2,(b),(2).
Conditions Prior to Occurrence The plant was shutdown for a refueling / maintenance outage.
The reactor mode switch was locked in refuel.
The reactor cavity was flooded and less than 212*F.
Description of Occurrence On Wednesday, February 13, 1980, at approximately 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, while performing a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test on SGTS #1, the system flow was observed to be 1350 CFM, which is less than rated capacity of 2600 CFM.
Apparent Cause of Occurrence The reduced system flow was caused by slipping drive belts on exhaust fan EF1-8.
Analysis of Occurrence Standby Gas Treatment System is used to process the reactor building atmosphere, should conditions develop which require its functioning, and exhaust it through the plant stack.
Despite its degraded condition, SGTS #1 was considered oper-able since only the process rate of the system was affected and not its ability to process.
SGTS #2 was available to perform its function at rated system capa-
{
bility. The safety significance of this event is considered minimal, since the only concern was a loss of SGTS redundancy at rated system flow.
1 1
Jersey Central Power & Ught Company is a Member of the General PucFc Utities System l
s..
Reportable Occurrence No. 50-219/80-7/3L Page 2 March 7, 1980
Corrective Action
SGTS #1 was taken out of service after SGTS #2 was confirmed to be functional at rated system flow, and the subject exhaust fan drive belts were replaced.
Operability tests and filter aP tests were again perfonned to prove the system operable.
Failure Data Not Applicable.
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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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