ML19250C058
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| ML19250C058 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/31/1979 |
| From: | Rogers W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19250C055 | List:
|
| References | |
| LER-79-021-03L, LER-79-21-3L, NUDOCS 7911060458 | |
| Download: ML19250C058 (54) | |
Similar Documents at Hatch | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E2071994-05-0909 May 1994
[Table view]LER 94-004-00:on 940416,discovered That Surveillance Frequency for Sp 34SV-SUV-008-1S Not Correct for Seven Primary Containment Vent & Purge Valves Due to Personnel Error.Surveillance Brought Up to date.W/940509 Ltr ML20045B0371993-06-10010 June 1993 LER 93-009-00:on 930514,scram Occurred When Mode Switch Moved to Run Position Due to Blown Fuses in Rps.Procedures 52PM-B21-005-1S,52PM-B21-005-2S & 52GM-MEL-007-0S Revised. W/930610 Ltr ML20045B7111993-06-10010 June 1993 LER 93-005-00:on 930521,unplanned Insertion of Manual Scram Initiated Due to Personnel Error.Personnel Involved Temporarily Removed from License Duties & Being Subjected to Formal discipline.W/930610 Ltr ML20028H8431991-01-27027 January 1991 LER 90-024-00:on 901228,pretreatment Monitoring Station Offgas Samples Not Collected & Analyzed within 4 H of Increased Fission Gas Release.Caused by Misinterpretation of Tech Specs.Personnel instructed.W/910125 Ltr ML19277C5931983-06-28028 June 1983 LER 83-033/03L-0:on 830606,surveillance Coordinator Discovered Procedure HNP-2-3195, Weekly Breaker Alignment Checks, Not Performed by 830605.Caused by Personnel Error. Procedure Performed on 830606.W/830628 Ltr ML20028A4901982-11-0909 November 1982 LER 82-078/03L-0:on 821014,discovered Safety Evaluations for Revisions to Procedures Not Reviewed by Safety Review Board Per Tech Specs.Caused by Misinterpretation of Tech Specs.All safety-related Evaluations Will Be Reviewed ML20027C1741982-09-28028 September 1982 Updated LER 82-008/03X-2:on 820126,during steady-state operation,115 Control Rod Drive Accumulator Low Pressure Alarm Switches Found in Need of Calibr.Caused by Instrument Drift.Setpoints Reset.Fill Valves Being Overhauled ML20027B2661982-09-0202 September 1982 LER 82-086/03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup ML20052A4211982-03-0202 March 1982 LER 82-013/03L-0:on 820213,during Startup,Average Power Range Monitor Not Adjusted within 2-h Time Limit & Corrective Action Ineffective.Caused by Spatial Redistribution of Xenon & Faulty Rod Pattern Adjustment ML20040C7201982-01-19019 January 1982 LER 82-001/03L-0:on 820101,low Pressure Alarm Received on Control Rod Drive Line Hydraulic Control Unit 26-47 Due to Switch Being Out of Tolerance.Caused by Setpoint Drift. Switch Recalibr & Returned to Svc ML20039F3711981-12-22022 December 1981 LER 81-135/03L-0:on 811215,level of Both Fire Protection Water Storage Tanks Dropped Below Tech Spec Requirement. Caused by Ruptured Fire Main in Low Voltage Switchyard. Rupture Isolated & Tanks Restored to Required Level ML20038B7371981-12-0101 December 1981 LER 81-110/03L-0:on 811107,RHR Loop a Removed from Shutdown Cooling Mode to Standby Configuration.While Swapping from Shutdown Cooling to Torus Suction,Torus Suction Valve 2E11- FOO4C Failed.Caused by Valve Limit Switch Failure ML20011A5111981-09-29029 September 1981 LER 81-094/03L-0:on 810904,during Testing of Standby Gas Treatment Sys Filter Train T46-D001A,filter Train Would Not Remove Required Amount of Halogenated Hydrocarbon Gas.Caused by Defective Charcoal.Charcoal Replaced ML20010J5401981-09-25025 September 1981 LER 81-087/03L-0:on 810902,during Removal of Radioactive Matl from Fuel Pool,Containment Atmosphere Dilution Sys Analyzers Failed & Drywell to Torus Delta P Dropped Below Spec.Caused by High Radiation Levels ML18023A0011981-08-0404 August 1981 LER 81-068/03L-0:on 810706,following Reactor Scram,Hpci Sys Auto Initiated,Tripped on High Reactor Water Level,Then Failed to Restart,Due to Failure of Turbine Stop Valve to Open.Caused by Overspeed Trip Sys Malfunction ML20004B6671981-05-21021 May 1981 LER 81-041/03L-0:on 810426,diesel Generator 1B Declared Inoperable.Caused by Spurious Trip from High Crankcase Pressure Switch W/Generator in Manual Start Mode.Generator Proven Operable & Returned to Svc ML19347E6941981-05-0707 May 1981 LER 81-039/01T-0:on 810428,supports B21-f30-H007 & B21-f30-H004 Found to Fail Support Functionality Criteria Per IE Bulletin 79-14.Caused by Design Requirements Being Exceeded ML20008F9541981-05-0505 May 1981 LER 81-030/03L-0:on 810413,during Refueling outage,1C71- K751B & D,Rps M-G Set Overvoltage Relays & 1C71-K752C,RPS M-G Set Undervoltage Relay Did Not Actuate.Caused by Setpoint Drift.Relays Recalibr & Returned to Svc ML19350B8071981-03-17017 March 1981 Updated LER 80-149/03X-1:on 801031,RHR Pump Suction Isolation Valve 2E11-F4B Was Found Leaking.Caused by Scratches on Valve Seat,Probably Due to Valve Closing on Debris.Valve Seat Polished ML20003A4081981-01-27027 January 1981 LER 80-128/03L-0:on 801230,while Performing High Drywell Pressure Function Test,Relay ANP-1-3002 Failed.Caused by Broken Insulation Preventing Contacts from de-energizing. Replay Replaced & Returned to Svc ML20002E1921981-01-15015 January 1981 LER 80-123/03L-0:on 801219 & 801226,turbine Trip & Throttle Valve on Reactor Core Isolation Cooling Sys Failed.Failures Caused by Gall on Valve Poppet & Body & Improper Limit Switch Setting.Gall Removed & Switch Reset ML19345E2831980-12-11011 December 1980 LER 80-156/03L-0:on 801113,determined RHR Return Inboard & Outboard Thermal Expansion Bellows Leaking in Excess of Spec.Caused by Cracks in Test Connection Tubing.Retest to Be Performed ML19345B3141980-11-18018 November 1980 LER 80-116/03L-0:on 801105,reactor Recirculation Pump a Motor Generator Tripped.Cause Unknown.Generator Set Restarted & No Problems Found ML19344E6631980-08-29029 August 1980 LER 80-123/03L-0:on 800812,during Normal Operation,While Performing Reactor Core Isolation Cooling Steam Line Pressure Instrument Functional Test,Outboard Isolation Valve Failed to Fully Close.Caused by Defective Torque Switch ML19344E0881980-08-21021 August 1980 LER 80-120/03L-0:on 800811,during Normal Steady State Power Operation,Recirculation Pump 2B Rx Tripped on Low Oil Pressure to Mg Set When Dc Control Power Was Lost to Mg Set Oil Pumps.Caused by Failure to Restore Normal Dc Power ML19344E0351980-08-15015 August 1980 LER 80-088/03L-0:on 800725,w/reactor in start-up Mode & Reactor Pressure at 150 1b & 0% Power,During HPCI Overspeed Trip Test,Turbine Failed to Trip at or Below 5,000 Revolutions Per Minute.Caused by Setpoint Drift ML19330A5691980-07-22022 July 1980 LER 80-081/03L-0:on 800705,w/mode Switch in Run,Drywell Pressure Recorder 1T48-R608 Found Inoperative.Redundant Recorder 1T48-R609 Was Operable.Caused by Component Failure. Transmitter Repaired,Recalibr & Returned to Svc ML19320A8131980-06-27027 June 1980 LER 80-056/03L-0:on 800205,standby Gas Treatment Sys Ventilation & Valve Operability Procedure,Changed on 800122, Had Not Been PRB Reviewed or Approved within 14 Days as Required by Tech Spec.Caused by Personnel Error ML19318C4801980-06-24024 June 1980 Revised LER 80-068/03X-1:on 800422,while Performing Primary Containment Recombiner Sys Functional Test,Recombiner Sheath Temp Failed to Remain within Tech Spec.Caused by Setpoint Being Set Too High ML19318C4661980-06-24024 June 1980 LER 80-089/03L-0:on 800530,while Performing HNP-2-3315,torus Suction Valves 2E41-F041 & 2E41-F042 Failed When Given Open Signal.Torus Valves Shorted Out Due to Condensation in HPCI Room.Cause of Condensation Was Steam Leakage Around Seal ML19318B0051980-06-19019 June 1980 LER 80-087/03L-0:on 800528,during Surveillance Procedure HNP-2-3154,reactor Pressure Vessel Level Instrument (LPCI) Ft&C on 2B21-NO31B,Switch 4,had Double Actuation.Caused by Slipped Magnets on Pointer Shaft Due to Corrosion ML19318A9741980-06-17017 June 1980 LER 80-084/03L-0:on 800521,unit Scrammed While Operating at Steady State.Reactor Core Isolation Cooling Tripped on High Water Level.Sys Maunally Restarted,But Tripped on Mechanical Overspeed Trip ML19312E6081980-05-23023 May 1980 LER 80-043/03L-0:on 800503,while at Steady State Power, Torus Air & Water Temp Recorder Was Discovered to Be Stamping Erratic & Upscale.Caused by Faulty Balancing Motor in Recorder.Balancing Motor Replaced ML19312E2031980-05-22022 May 1980 LER 80-044/03L-0:on 800506,during Normal Full Power Operation,Primary Containment Oxygen Concentration Exceeded Allowable Limit.Caused by Operator Failure to Initiate Dinitrogen Makeup to Drywell Prior to Reaching Limit ML19318A3981980-05-19019 May 1980 Updated LER 80-053/03X-2:on 800505,during Normal Operation, Notification Received from Comsip,Inc of Design Defect on Primary Containment hydrogen-oxygen Analyzers.Caused by Absence of Design to Prevent Deadheading ML19309H5981980-05-0606 May 1980 LER 80-063/03L-0:on 800421,w/reactor in Startup/Hot Standby Mode,D/W Torus Temp Recorder Found Inoperable.Caused by Loose Wire on Common Terminal Block on Recorder.Connection Tightened ML19309H6211980-05-0505 May 1980 LER 80-050/03L-0:on 800407,during ISI Pump Operability Testing,While Shut Down for Surveillance/Vent Header Installation Outage,Determined That Standby Liquid Control Pump B Did Not Meet Acceptance Criteria ML19309H2241980-05-0101 May 1980 LER 80-037/03L-0:on 800408,during Normal Operations & While Reviewing Surveillance schedule,post-LOCA Monitor Calibr Had Not Been Performed within Interval Required by Tech Specs. Caused by Personnel Oversight.Personnel Change Was Made ML19309H5911980-05-0101 May 1980 LER 80-052/03L-0:on 800408,during Maint of Standby Gas Treatment Sys,Power Cables to Heaters & Fans Found Undersized.Caused by Design Error.Cables Will Be Replaced by 800601 ML19309H1701980-04-30030 April 1980 LER 80-033/03L-0:on 800402,while Inspecting CST Access Stairway,Cold Joint Between Original Base Slab & Added Slab for Retaining Walls Lacked Watertight Seal.Caused by Const Oversight.Maint Request Issued ML19309H2011980-04-30030 April 1980 LER 80-051/03L-0:on 800409,while Shutdown for Surveillance/ Vent Header Deflector Installation Outage,Dirty Radwaste Discharge Isolation Valve 2G11-F004 Found Leaking in Excess of Spec.Caused by Improper Sealing of Valve Gate ML19309H2381980-04-30030 April 1980 LER 80-036/03L-0:on 800409,during Steady Power Operation, Fire Water Storage Tank Levels Dropped Below Tech Spec Limits.Caused by Separation of Fire Main Pipe Fitting Due to Settling of Concrete Drainage Ditch ML19309H2521980-04-29029 April 1980 LER 80-047/03L-0:on 800405,while Performing Remote Shutdown Panel Instrument Checks,Torus Water Level Instrument 2T48-R070 Found Downscale.Caused by Technician Failing to Verify Markings of Transmitter 2T48-N070 W/Proper Tubing ML19309H1931980-04-28028 April 1980 LER 80-046/03L-0:on 800404,during 18-month Surveillance Procedure HNP2-3832,loss of Sys Pressure Was Simulated on Diesel Generator 2C & Bus 2G.Generator Started But Did Not Tie to Bus.Caused by Personnel Error ML19309H1851980-04-28028 April 1980 LER 80-039/01X-1:on 800411,during Normal Operation,Psw & RHR-SW Pump Motor Cooling Water Supply Did Not Meet Single Failure Criterion.Caused by Design Not Specifying Divisional Cooling Water Supply to Pumps ML19309F1901980-04-22022 April 1980 LER 80-034/03L-0:on 800403,during Steady State Power Operation on Unit 1 & Cold Shutdown on Unit 2,fire Water Level on Both Water Tanks Was Discovered Below Tech Specs. Caused by Valve Trip at North End of 1B Cooling Tower ML19309G0921980-04-22022 April 1980 LER 80-042/03L-0:on 800328,while Performing Hydraulic Visual Insp,Snubber 2T46-R65B Found Low on Fluid.During Subsequent Testing,Snubber Failed to Meet Acceptance Criteria on Lockup Velocity.Caused by Seal Failure ML19309E6441980-04-15015 April 1980 LER 80-045/01T-0:on 800404,while in Cold Shutdown,Leak Rate Test Was Performed on Auto Depressurization Sys Valves Air Supply Accumulator Check Valves.Leaks Were Beyond Acceptable Rate.Cause Unknown.Valves Will Be Repaired Prior to Startup ML19305D8271980-04-0808 April 1980 LER 80-032/01T-0:on 800327,during Maint Outage & Surveillance Test,Noted That 2D Psw Pump Sequenced to Bus in 2 to 5-s.Cause Unknown ML19305C9581980-04-0303 April 1980 LER 80-029/01T-0:on 800325,during 18-month Surveillance Test on Emergency Station Battery Chargers 2G & 2J,both Failed to Maintain Respective Loads.Caused by Voltage Control Module & Current Limit Module Requiring Fine Tuning 1994-05-09 Category:RO) MONTHYEARML20029E2071994-05-0909 May 1994
[Table view]LER 94-004-00:on 940416,discovered That Surveillance Frequency for Sp 34SV-SUV-008-1S Not Correct for Seven Primary Containment Vent & Purge Valves Due to Personnel Error.Surveillance Brought Up to date.W/940509 Ltr ML20045B0371993-06-10010 June 1993 LER 93-009-00:on 930514,scram Occurred When Mode Switch Moved to Run Position Due to Blown Fuses in Rps.Procedures 52PM-B21-005-1S,52PM-B21-005-2S & 52GM-MEL-007-0S Revised. W/930610 Ltr ML20045B7111993-06-10010 June 1993 LER 93-005-00:on 930521,unplanned Insertion of Manual Scram Initiated Due to Personnel Error.Personnel Involved Temporarily Removed from License Duties & Being Subjected to Formal discipline.W/930610 Ltr ML20028H8431991-01-27027 January 1991 LER 90-024-00:on 901228,pretreatment Monitoring Station Offgas Samples Not Collected & Analyzed within 4 H of Increased Fission Gas Release.Caused by Misinterpretation of Tech Specs.Personnel instructed.W/910125 Ltr ML19277C5931983-06-28028 June 1983 LER 83-033/03L-0:on 830606,surveillance Coordinator Discovered Procedure HNP-2-3195, Weekly Breaker Alignment Checks, Not Performed by 830605.Caused by Personnel Error. Procedure Performed on 830606.W/830628 Ltr ML20028A4901982-11-0909 November 1982 LER 82-078/03L-0:on 821014,discovered Safety Evaluations for Revisions to Procedures Not Reviewed by Safety Review Board Per Tech Specs.Caused by Misinterpretation of Tech Specs.All safety-related Evaluations Will Be Reviewed ML20027C1741982-09-28028 September 1982 Updated LER 82-008/03X-2:on 820126,during steady-state operation,115 Control Rod Drive Accumulator Low Pressure Alarm Switches Found in Need of Calibr.Caused by Instrument Drift.Setpoints Reset.Fill Valves Being Overhauled ML20027B2661982-09-0202 September 1982 LER 82-086/03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup ML20052A4211982-03-0202 March 1982 LER 82-013/03L-0:on 820213,during Startup,Average Power Range Monitor Not Adjusted within 2-h Time Limit & Corrective Action Ineffective.Caused by Spatial Redistribution of Xenon & Faulty Rod Pattern Adjustment ML20040C7201982-01-19019 January 1982 LER 82-001/03L-0:on 820101,low Pressure Alarm Received on Control Rod Drive Line Hydraulic Control Unit 26-47 Due to Switch Being Out of Tolerance.Caused by Setpoint Drift. Switch Recalibr & Returned to Svc ML20039F3711981-12-22022 December 1981 LER 81-135/03L-0:on 811215,level of Both Fire Protection Water Storage Tanks Dropped Below Tech Spec Requirement. Caused by Ruptured Fire Main in Low Voltage Switchyard. Rupture Isolated & Tanks Restored to Required Level ML20038B7371981-12-0101 December 1981 LER 81-110/03L-0:on 811107,RHR Loop a Removed from Shutdown Cooling Mode to Standby Configuration.While Swapping from Shutdown Cooling to Torus Suction,Torus Suction Valve 2E11- FOO4C Failed.Caused by Valve Limit Switch Failure ML20011A5111981-09-29029 September 1981 LER 81-094/03L-0:on 810904,during Testing of Standby Gas Treatment Sys Filter Train T46-D001A,filter Train Would Not Remove Required Amount of Halogenated Hydrocarbon Gas.Caused by Defective Charcoal.Charcoal Replaced ML20010J5401981-09-25025 September 1981 LER 81-087/03L-0:on 810902,during Removal of Radioactive Matl from Fuel Pool,Containment Atmosphere Dilution Sys Analyzers Failed & Drywell to Torus Delta P Dropped Below Spec.Caused by High Radiation Levels ML18023A0011981-08-0404 August 1981 LER 81-068/03L-0:on 810706,following Reactor Scram,Hpci Sys Auto Initiated,Tripped on High Reactor Water Level,Then Failed to Restart,Due to Failure of Turbine Stop Valve to Open.Caused by Overspeed Trip Sys Malfunction ML20004B6671981-05-21021 May 1981 LER 81-041/03L-0:on 810426,diesel Generator 1B Declared Inoperable.Caused by Spurious Trip from High Crankcase Pressure Switch W/Generator in Manual Start Mode.Generator Proven Operable & Returned to Svc ML19347E6941981-05-0707 May 1981 LER 81-039/01T-0:on 810428,supports B21-f30-H007 & B21-f30-H004 Found to Fail Support Functionality Criteria Per IE Bulletin 79-14.Caused by Design Requirements Being Exceeded ML20008F9541981-05-0505 May 1981 LER 81-030/03L-0:on 810413,during Refueling outage,1C71- K751B & D,Rps M-G Set Overvoltage Relays & 1C71-K752C,RPS M-G Set Undervoltage Relay Did Not Actuate.Caused by Setpoint Drift.Relays Recalibr & Returned to Svc ML19350B8071981-03-17017 March 1981 Updated LER 80-149/03X-1:on 801031,RHR Pump Suction Isolation Valve 2E11-F4B Was Found Leaking.Caused by Scratches on Valve Seat,Probably Due to Valve Closing on Debris.Valve Seat Polished ML20003A4081981-01-27027 January 1981 LER 80-128/03L-0:on 801230,while Performing High Drywell Pressure Function Test,Relay ANP-1-3002 Failed.Caused by Broken Insulation Preventing Contacts from de-energizing. Replay Replaced & Returned to Svc ML20002E1921981-01-15015 January 1981 LER 80-123/03L-0:on 801219 & 801226,turbine Trip & Throttle Valve on Reactor Core Isolation Cooling Sys Failed.Failures Caused by Gall on Valve Poppet & Body & Improper Limit Switch Setting.Gall Removed & Switch Reset ML19345E2831980-12-11011 December 1980 LER 80-156/03L-0:on 801113,determined RHR Return Inboard & Outboard Thermal Expansion Bellows Leaking in Excess of Spec.Caused by Cracks in Test Connection Tubing.Retest to Be Performed ML19345B3141980-11-18018 November 1980 LER 80-116/03L-0:on 801105,reactor Recirculation Pump a Motor Generator Tripped.Cause Unknown.Generator Set Restarted & No Problems Found ML19344E6631980-08-29029 August 1980 LER 80-123/03L-0:on 800812,during Normal Operation,While Performing Reactor Core Isolation Cooling Steam Line Pressure Instrument Functional Test,Outboard Isolation Valve Failed to Fully Close.Caused by Defective Torque Switch ML19344E0881980-08-21021 August 1980 LER 80-120/03L-0:on 800811,during Normal Steady State Power Operation,Recirculation Pump 2B Rx Tripped on Low Oil Pressure to Mg Set When Dc Control Power Was Lost to Mg Set Oil Pumps.Caused by Failure to Restore Normal Dc Power ML19344E0351980-08-15015 August 1980 LER 80-088/03L-0:on 800725,w/reactor in start-up Mode & Reactor Pressure at 150 1b & 0% Power,During HPCI Overspeed Trip Test,Turbine Failed to Trip at or Below 5,000 Revolutions Per Minute.Caused by Setpoint Drift ML19330A5691980-07-22022 July 1980 LER 80-081/03L-0:on 800705,w/mode Switch in Run,Drywell Pressure Recorder 1T48-R608 Found Inoperative.Redundant Recorder 1T48-R609 Was Operable.Caused by Component Failure. Transmitter Repaired,Recalibr & Returned to Svc ML19320A8131980-06-27027 June 1980 LER 80-056/03L-0:on 800205,standby Gas Treatment Sys Ventilation & Valve Operability Procedure,Changed on 800122, Had Not Been PRB Reviewed or Approved within 14 Days as Required by Tech Spec.Caused by Personnel Error ML19318C4801980-06-24024 June 1980 Revised LER 80-068/03X-1:on 800422,while Performing Primary Containment Recombiner Sys Functional Test,Recombiner Sheath Temp Failed to Remain within Tech Spec.Caused by Setpoint Being Set Too High ML19318C4661980-06-24024 June 1980 LER 80-089/03L-0:on 800530,while Performing HNP-2-3315,torus Suction Valves 2E41-F041 & 2E41-F042 Failed When Given Open Signal.Torus Valves Shorted Out Due to Condensation in HPCI Room.Cause of Condensation Was Steam Leakage Around Seal ML19318B0051980-06-19019 June 1980 LER 80-087/03L-0:on 800528,during Surveillance Procedure HNP-2-3154,reactor Pressure Vessel Level Instrument (LPCI) Ft&C on 2B21-NO31B,Switch 4,had Double Actuation.Caused by Slipped Magnets on Pointer Shaft Due to Corrosion ML19318A9741980-06-17017 June 1980 LER 80-084/03L-0:on 800521,unit Scrammed While Operating at Steady State.Reactor Core Isolation Cooling Tripped on High Water Level.Sys Maunally Restarted,But Tripped on Mechanical Overspeed Trip ML19312E6081980-05-23023 May 1980 LER 80-043/03L-0:on 800503,while at Steady State Power, Torus Air & Water Temp Recorder Was Discovered to Be Stamping Erratic & Upscale.Caused by Faulty Balancing Motor in Recorder.Balancing Motor Replaced ML19312E2031980-05-22022 May 1980 LER 80-044/03L-0:on 800506,during Normal Full Power Operation,Primary Containment Oxygen Concentration Exceeded Allowable Limit.Caused by Operator Failure to Initiate Dinitrogen Makeup to Drywell Prior to Reaching Limit ML19318A3981980-05-19019 May 1980 Updated LER 80-053/03X-2:on 800505,during Normal Operation, Notification Received from Comsip,Inc of Design Defect on Primary Containment hydrogen-oxygen Analyzers.Caused by Absence of Design to Prevent Deadheading ML19309H5981980-05-0606 May 1980 LER 80-063/03L-0:on 800421,w/reactor in Startup/Hot Standby Mode,D/W Torus Temp Recorder Found Inoperable.Caused by Loose Wire on Common Terminal Block on Recorder.Connection Tightened ML19309H6211980-05-0505 May 1980 LER 80-050/03L-0:on 800407,during ISI Pump Operability Testing,While Shut Down for Surveillance/Vent Header Installation Outage,Determined That Standby Liquid Control Pump B Did Not Meet Acceptance Criteria ML19309H2241980-05-0101 May 1980 LER 80-037/03L-0:on 800408,during Normal Operations & While Reviewing Surveillance schedule,post-LOCA Monitor Calibr Had Not Been Performed within Interval Required by Tech Specs. Caused by Personnel Oversight.Personnel Change Was Made ML19309H5911980-05-0101 May 1980 LER 80-052/03L-0:on 800408,during Maint of Standby Gas Treatment Sys,Power Cables to Heaters & Fans Found Undersized.Caused by Design Error.Cables Will Be Replaced by 800601 ML19309H1701980-04-30030 April 1980 LER 80-033/03L-0:on 800402,while Inspecting CST Access Stairway,Cold Joint Between Original Base Slab & Added Slab for Retaining Walls Lacked Watertight Seal.Caused by Const Oversight.Maint Request Issued ML19309H2011980-04-30030 April 1980 LER 80-051/03L-0:on 800409,while Shutdown for Surveillance/ Vent Header Deflector Installation Outage,Dirty Radwaste Discharge Isolation Valve 2G11-F004 Found Leaking in Excess of Spec.Caused by Improper Sealing of Valve Gate ML19309H2381980-04-30030 April 1980 LER 80-036/03L-0:on 800409,during Steady Power Operation, Fire Water Storage Tank Levels Dropped Below Tech Spec Limits.Caused by Separation of Fire Main Pipe Fitting Due to Settling of Concrete Drainage Ditch ML19309H2521980-04-29029 April 1980 LER 80-047/03L-0:on 800405,while Performing Remote Shutdown Panel Instrument Checks,Torus Water Level Instrument 2T48-R070 Found Downscale.Caused by Technician Failing to Verify Markings of Transmitter 2T48-N070 W/Proper Tubing ML19309H1931980-04-28028 April 1980 LER 80-046/03L-0:on 800404,during 18-month Surveillance Procedure HNP2-3832,loss of Sys Pressure Was Simulated on Diesel Generator 2C & Bus 2G.Generator Started But Did Not Tie to Bus.Caused by Personnel Error ML19309H1851980-04-28028 April 1980 LER 80-039/01X-1:on 800411,during Normal Operation,Psw & RHR-SW Pump Motor Cooling Water Supply Did Not Meet Single Failure Criterion.Caused by Design Not Specifying Divisional Cooling Water Supply to Pumps ML19309F1901980-04-22022 April 1980 LER 80-034/03L-0:on 800403,during Steady State Power Operation on Unit 1 & Cold Shutdown on Unit 2,fire Water Level on Both Water Tanks Was Discovered Below Tech Specs. Caused by Valve Trip at North End of 1B Cooling Tower ML19309G0921980-04-22022 April 1980 LER 80-042/03L-0:on 800328,while Performing Hydraulic Visual Insp,Snubber 2T46-R65B Found Low on Fluid.During Subsequent Testing,Snubber Failed to Meet Acceptance Criteria on Lockup Velocity.Caused by Seal Failure ML19309E6441980-04-15015 April 1980 LER 80-045/01T-0:on 800404,while in Cold Shutdown,Leak Rate Test Was Performed on Auto Depressurization Sys Valves Air Supply Accumulator Check Valves.Leaks Were Beyond Acceptable Rate.Cause Unknown.Valves Will Be Repaired Prior to Startup ML19305D8271980-04-0808 April 1980 LER 80-032/01T-0:on 800327,during Maint Outage & Surveillance Test,Noted That 2D Psw Pump Sequenced to Bus in 2 to 5-s.Cause Unknown ML19305C9581980-04-0303 April 1980 LER 80-029/01T-0:on 800325,during 18-month Surveillance Test on Emergency Station Battery Chargers 2G & 2J,both Failed to Maintain Respective Loads.Caused by Voltage Control Module & Current Limit Module Requiring Fine Tuning 1994-05-09 Category:TEXT-SAFETY REPORT MONTHYEARML20217D3061999-10-13013 October 1999
[Table view]SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML20212G3101999-09-24024 September 1999 Safety Evaluation Supporting Amends 217 & 158 to Licenses DPR-57 & NPF-5,respectively ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With 05000366/LER-1999-006, :on 990615,loss of Condenser Vacuum Leads to Manual Reactor Scram & ESF Actuation.Caused by Loss of Vacuum in Main Condenser.Operating Order Issued.With1999-07-14014 July 1999
HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization ML20237D6371998-08-20020 August 1998 Safety Evaluation Supporting Amends 213 & 154 to Licenses DPR-57 & NPF-5,respectively ML20237C4531998-08-18018 August 1998 Safety Evaluation Supporting Amends 212 & 153 to Licenses DPR-57 & NPF-5,respectively HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 1999-09-30 |
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