ML20023B838
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| ML20023B838 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/29/1983 |
| From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| LER-83-057-01P, LER-83-57-1P, PLA-1642, NUDOCS 8305060442 | |
| Download: ML20023B838 (1) | |
Similar Documents at Susquehanna | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18026A4931998-03-30030 March 1998
[Table view]LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr ML17227A2311991-07-23023 July 1991 LER 91-009-00:on 910624,RWCU Steam Leak Detection Instrumentation Discovered to Be Inadvertently Actuated During Routine Functional Testing.Caused by Adequate Verbal Communication.Technicians briefed.W/910723 Ltr ML18026A5251991-07-0505 July 1991 LER 91-006-00:on 910608,unplanned Actuations of ESF Occurred.Caused by Unexpected Trip of Primary Power Supply EPA Breaker Losing Power.Breakers Reset & Full Power Operation Continued uninterupted.W/910705 Ltr ML20011F7881990-03-0202 March 1990 LER 90-005-00:on 900203,station Alert Declared When Reactor Coolant Temp Exceeded 200 F Due to Temporary Loss of Normal Method Dhr.Caused by Short Circuit to Ground in Bus Distribution Panel.Circuit Breakers replaced.W/900302 Ltr ML20005F3401990-01-0404 January 1990 LER 89-010-01:on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs lapped.W/900104 Ltr ML18040A9121988-09-23023 September 1988 LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr ML19310G9421986-04-21021 April 1986 LER 86-005-00:on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & lubricated.W/860421 Ltr ML20024E8021983-08-19019 August 1983 LER 83-107/01P-0:on 830819,during Maint,Emergency Svc Water Loop Discharge a to Spray Pond Valve Would Travel Only in Closed Direction.Cause Unstated.Mechanical Stops Loosened, Permitting Valve to Be Opened to Proper Position ML20024E6311983-08-0404 August 1983 Updated LER 83-093/01X-1:on 830711,31-day Functional Test of Containment Radiation Monitor a Not Performed for 830612-0711.Caused by Lack of Timely Chemistry Mgt Review of surveillance.W/830804 Ltr ML20024D9141983-07-26026 July 1983 Updated LER 83-035/03X-1:on 830228,during 4 H RCS Unidentified Leakage Test,Pump B of Drywell Sump a Continued to Operate for 4 H W/O Change in Sump Level.Caused by Clogged Pump Impeller.Pump cleaned.W/830726 Ltr ML20024E1601983-07-25025 July 1983 LER 83-098/03L-0:on 830625,position of Valve Indeterminate Due to Dual Status Indication for Suppression pool-to- Drywell Vacuum Breaker.Caused by Insufficient Limit Switch Plunger Position.Limit Switches adjusted.W/830725 Ltr ML20024D9911983-07-22022 July 1983 LER 83-096/03L-0:on 830624,RCIC Leak Detection B Power Failure Alarm Received.Undervoltage Trip Caused by Loss of Startup Transformer.Inverter Manually reset.W/830722 Ltr ML20024C2381983-06-29029 June 1983 LER 83-088/03L-0:on 830530,RCIC Pump Discharge Valve Would Not Open.Caused by Gap Between Breaker Male & Female Stab Clips.Female Clips Reworked to Allow Proper Contact. W/830629 Ltr ML20024C1001983-06-24024 June 1983 LER 83-085/03L-0:on 830525,containment Isolation Valve for Containment Atmosphere Control Sample Line Failed to Close. Cause Not Stated.Maint Personnel Verified Switch Positioning & Reconnected circuitry.W/830624 Ltr ML20024C1141983-06-24024 June 1983 LER 83-087/03L-0:on 830527,A Containment H2/02 Analyzers Found to Have Erratic Readings.Caused by Pressure Control Valve & Sample Pump Degradation to Point Where Proper Flow Not Maintained.Failed Components replaced.W/830624 Ltr ML20024C2451983-06-24024 June 1983 LER 83-086/03L-0:on 830525,reactor Bldg Door Opened While Maint Performed on Turbine Bldg Side of Air Lock to Reactor Bldg.Caused by Personnel Error.Individual W/Radio Communication Will Be posted.W/830624 Ltr ML20024C2461983-06-23023 June 1983 LER 83-084/03L-0:on 830524,during Surveillance Testing, Control Room Emergency Outside Air Supply Sys Fan Tripped. Caused by Out of Tolerance of Time Delay Relay for Heater Differential Temp.Relay reset.W/830623 Ltr ML20024A8401983-06-21021 June 1983 LER 83-082/01T-0:on 830607,main Turbine Trip on High Reactor Pressure Vessel Level Bypassed to Clear Interlock.After Outage,Bypass Discovered Still Installed.Caused by Lack of Clear Requirement for Bypass review.W/830621 Ltr ML20024A5331983-05-27027 May 1983 LER 83-067/01T-0:on 830516,reactor Mode Switch Placed in Startup Position & Half Scram Developed.Caused by Improper Functioning of Reactor Mode Switch Contacts.Switch Replaced. W/830527 Ltr ML20024A3421983-05-27027 May 1983 LER 83-070/01T-0:on 830517,flow Rates Required to Maintain Positive Pressure in Control Structure Appeared to Exceed Tech Spec Limits.Flow Limit Inadvertently Omitted from Procedure.Procedure corrected.W/830527 Ltr ML20024A3301983-05-27027 May 1983 LER 83-075/01T-0:on 830515,found Chlorine Detectors on Control Room Emergency Outside Air Supply May Prevent Operation in Pressurization Mode Following Loss of Power. Emergency Operation Procedures revised.W/830527 Ltr ML20024A3951983-05-26026 May 1983 LER 83-071/03L-0:on 830426,overvoltage Setting on One RPS Alternate Electrical Protection Assembly Found Greater than Tech Spec Limit.Caused by Instrument Drift.Overvoltage Setting Calibr within limits.W/830526 Ltr ML20023D5121983-05-11011 May 1983 LER 83-063/03L-0:on 830411,main Steam Line Drain Valve Leakage Exceeded Tech Spec Limit.Cause Not Stated.Seal Ring Replaced,Outboard Valve Lapped & Valves Reassembled ML20023B8381983-04-29029 April 1983 LER 83-057/01P-0:confirms 830428 Telcon Re Incident Concerning Bypass Leakage Calculations for Feedwater Following DBA LOCA ML20028D6871983-01-10010 January 1983 LER 83-001/01P-0:confirms 830107 Telcon Re Failure to Comply W/Action Statement Requiring Grab Samples of Offgas Sys After Declaring One Train of Hydrogen Monitor Inoperable. Caused by Inadequate Shift Turnover in Chemistry Dept ML20028D3141983-01-0707 January 1983 LER 82-072/03L-0:on 821210,while Performing Surveillance, One Control Rod Would Not Indicate at One Position.Possibly Caused by Intermittent Fault on Circuit Board.Printed Circuit Board Reinstalled ML20028D2871983-01-0606 January 1983 LER 82-069/03L-0:on 821207,during Startup Testing,Hpci Sys Declared Operable Prior to Closing Out Open Equipment Release Form.Caused by Work Program Design Weakness.Present Work Practice Modified ML20028D2601983-01-0505 January 1983 LER 82-061/01T-0:on 821228,during Startup Testing,While Performing Loss of Offsite Power Test,Emergency Svc Water Pumps B & D Failed to Start.Loop B Failure Caused by Loose Relay Terminal Wiring.Loop D Caused by Contact Adjustment ML20028D2671983-01-0505 January 1983 LER 82-062/01T-0:on 821222,during Loss of Offsite Power Startup Test,Standby Gas Treatment Sys Did Not Operate as Designed When False High Radiation Signal Received from Discharge Monitor.Caused by Monitor Failing High ML20028B7201982-11-24024 November 1982 LER 82-045/03L-0:on 821025,essential Svc Water Pump Failed to Start.Cause Could Not Be Determined or Reproduced.Svc Pump Tested 5 Times W/O Recurrence of Failure ML20028B5821982-11-19019 November 1982 Revised LER 82-026/01T-1:on 820717,review Revealed Certain Cables Discussed in Deficiency Rept 80-00-28 Not Flexed or Grounded Prior to Fuel Load.Caused by Failure to Maintain Control Over Fddr KRI-607 During Turnover of Const ML20028B0301982-11-18018 November 1982 LER 82-042/01T-0:on 821117,personnel Failed to Take Grab Samples When RHR Svc Water Sys Radiation Monitor Was Inoperable ML20028B4351982-11-18018 November 1982 LER 82-043/01T-0:on 821117,determined That Failure of Single Component Could Defeat Overload Detection & Protection Devices for Containment Penetration Carrying Power Cables for Reactor Recirculation Pumps.Cause Not Stated ML20028A9541982-11-16016 November 1982 LER 82-040/03L-0:on 821018,deluge Sys in CREOASS Initiated. Caused by Maint Personnel Bumping Fire Sys thermo-switch on Charcoal Beds.Charcoal Changed Out & Preventive Maint Procedures Modified to Valve Out Deluge Sys During Maint ML20028B0461982-11-12012 November 1982 Revised LER 82-003/01T-2:on 820811,during Initial Fuel Loading,Sprinkler Sys Did Not Exist in Area Designated by Tech Specs & Fire Protection Review Rept.Caused by Discrepancies in as-built Conditions.Mods Initiated ML20028A3341982-11-0303 November 1982 LER 82-034/03L-0:on 821011,during Startup Testing,Creoass Train a Declared Inoperable When Outside Air Damper Failed to Close.Caused by Inadequate Lubrication of Actuator Stem. Stem Lubricated & Damper Returned to Svc ML20027D0591982-10-19019 October 1982 LER 82-027/03L-0:on 820920,two Drywell/Suppression Chamber Vacuum Breakers Gave False Position Indications During Stroking.Caused by Loose Couplings Connecting Limit Switch to Vacuum Relief Valve Shaft.Set Screw Replaced ML17139B0311982-09-13013 September 1982 LER 82-013/03L-0:on 820814,radiation Monitor Found Inoperable.Caused by Faulty Gm Tube & Signal Conditioner (Sensor Converter).Tube & Signal Conditioner Replaced & Monitor Returned to Svc ML20027B0571982-09-0808 September 1982 LER 82-007/01T-1:on 820825,updated Secondary Containment Vol Calculation Had Not Replaced Preliminary Analysis Utilized to Obtain Values in Fsar.Vol Based on Preliminary Calculation Which Did Not Account for Floors & Equipment ML20027A9581982-09-0303 September 1982 LER 82-005/01T-1:on 820820,during Preoperational Testing, Control Room Emergency Outside Air Supply Sys Did Not Automatically Start on Isolation Signal.Caused by Unauthorized Personnel Changing Flow Controller Switch ML17139A9071982-08-0202 August 1982 LER 82-001/01T-0:on 820718,unacceptable Linear Indications Found by Radiograph of A-11 Weld.Cause Not Determined.Welds Repaired Per Approved Repair Program 1998-03-30 Category:RO) MONTHYEARML18026A4931998-03-30030 March 1998
[Table view]LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr ML17227A2311991-07-23023 July 1991 LER 91-009-00:on 910624,RWCU Steam Leak Detection Instrumentation Discovered to Be Inadvertently Actuated During Routine Functional Testing.Caused by Adequate Verbal Communication.Technicians briefed.W/910723 Ltr ML18026A5251991-07-0505 July 1991 LER 91-006-00:on 910608,unplanned Actuations of ESF Occurred.Caused by Unexpected Trip of Primary Power Supply EPA Breaker Losing Power.Breakers Reset & Full Power Operation Continued uninterupted.W/910705 Ltr ML20011F7881990-03-0202 March 1990 LER 90-005-00:on 900203,station Alert Declared When Reactor Coolant Temp Exceeded 200 F Due to Temporary Loss of Normal Method Dhr.Caused by Short Circuit to Ground in Bus Distribution Panel.Circuit Breakers replaced.W/900302 Ltr ML20005F3401990-01-0404 January 1990 LER 89-010-01:on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs lapped.W/900104 Ltr ML18040A9121988-09-23023 September 1988 LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr ML19310G9421986-04-21021 April 1986 LER 86-005-00:on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & lubricated.W/860421 Ltr ML20024E8021983-08-19019 August 1983 LER 83-107/01P-0:on 830819,during Maint,Emergency Svc Water Loop Discharge a to Spray Pond Valve Would Travel Only in Closed Direction.Cause Unstated.Mechanical Stops Loosened, Permitting Valve to Be Opened to Proper Position ML20024E6311983-08-0404 August 1983 Updated LER 83-093/01X-1:on 830711,31-day Functional Test of Containment Radiation Monitor a Not Performed for 830612-0711.Caused by Lack of Timely Chemistry Mgt Review of surveillance.W/830804 Ltr ML20024D9141983-07-26026 July 1983 Updated LER 83-035/03X-1:on 830228,during 4 H RCS Unidentified Leakage Test,Pump B of Drywell Sump a Continued to Operate for 4 H W/O Change in Sump Level.Caused by Clogged Pump Impeller.Pump cleaned.W/830726 Ltr ML20024E1601983-07-25025 July 1983 LER 83-098/03L-0:on 830625,position of Valve Indeterminate Due to Dual Status Indication for Suppression pool-to- Drywell Vacuum Breaker.Caused by Insufficient Limit Switch Plunger Position.Limit Switches adjusted.W/830725 Ltr ML20024D9911983-07-22022 July 1983 LER 83-096/03L-0:on 830624,RCIC Leak Detection B Power Failure Alarm Received.Undervoltage Trip Caused by Loss of Startup Transformer.Inverter Manually reset.W/830722 Ltr ML20024C2381983-06-29029 June 1983 LER 83-088/03L-0:on 830530,RCIC Pump Discharge Valve Would Not Open.Caused by Gap Between Breaker Male & Female Stab Clips.Female Clips Reworked to Allow Proper Contact. W/830629 Ltr ML20024C1001983-06-24024 June 1983 LER 83-085/03L-0:on 830525,containment Isolation Valve for Containment Atmosphere Control Sample Line Failed to Close. Cause Not Stated.Maint Personnel Verified Switch Positioning & Reconnected circuitry.W/830624 Ltr ML20024C1141983-06-24024 June 1983 LER 83-087/03L-0:on 830527,A Containment H2/02 Analyzers Found to Have Erratic Readings.Caused by Pressure Control Valve & Sample Pump Degradation to Point Where Proper Flow Not Maintained.Failed Components replaced.W/830624 Ltr ML20024C2451983-06-24024 June 1983 LER 83-086/03L-0:on 830525,reactor Bldg Door Opened While Maint Performed on Turbine Bldg Side of Air Lock to Reactor Bldg.Caused by Personnel Error.Individual W/Radio Communication Will Be posted.W/830624 Ltr ML20024C2461983-06-23023 June 1983 LER 83-084/03L-0:on 830524,during Surveillance Testing, Control Room Emergency Outside Air Supply Sys Fan Tripped. Caused by Out of Tolerance of Time Delay Relay for Heater Differential Temp.Relay reset.W/830623 Ltr ML20024A8401983-06-21021 June 1983 LER 83-082/01T-0:on 830607,main Turbine Trip on High Reactor Pressure Vessel Level Bypassed to Clear Interlock.After Outage,Bypass Discovered Still Installed.Caused by Lack of Clear Requirement for Bypass review.W/830621 Ltr ML20024A5331983-05-27027 May 1983 LER 83-067/01T-0:on 830516,reactor Mode Switch Placed in Startup Position & Half Scram Developed.Caused by Improper Functioning of Reactor Mode Switch Contacts.Switch Replaced. W/830527 Ltr ML20024A3421983-05-27027 May 1983 LER 83-070/01T-0:on 830517,flow Rates Required to Maintain Positive Pressure in Control Structure Appeared to Exceed Tech Spec Limits.Flow Limit Inadvertently Omitted from Procedure.Procedure corrected.W/830527 Ltr ML20024A3301983-05-27027 May 1983 LER 83-075/01T-0:on 830515,found Chlorine Detectors on Control Room Emergency Outside Air Supply May Prevent Operation in Pressurization Mode Following Loss of Power. Emergency Operation Procedures revised.W/830527 Ltr ML20024A3951983-05-26026 May 1983 LER 83-071/03L-0:on 830426,overvoltage Setting on One RPS Alternate Electrical Protection Assembly Found Greater than Tech Spec Limit.Caused by Instrument Drift.Overvoltage Setting Calibr within limits.W/830526 Ltr ML20023D5121983-05-11011 May 1983 LER 83-063/03L-0:on 830411,main Steam Line Drain Valve Leakage Exceeded Tech Spec Limit.Cause Not Stated.Seal Ring Replaced,Outboard Valve Lapped & Valves Reassembled ML20023B8381983-04-29029 April 1983 LER 83-057/01P-0:confirms 830428 Telcon Re Incident Concerning Bypass Leakage Calculations for Feedwater Following DBA LOCA ML20028D6871983-01-10010 January 1983 LER 83-001/01P-0:confirms 830107 Telcon Re Failure to Comply W/Action Statement Requiring Grab Samples of Offgas Sys After Declaring One Train of Hydrogen Monitor Inoperable. Caused by Inadequate Shift Turnover in Chemistry Dept ML20028D3141983-01-0707 January 1983 LER 82-072/03L-0:on 821210,while Performing Surveillance, One Control Rod Would Not Indicate at One Position.Possibly Caused by Intermittent Fault on Circuit Board.Printed Circuit Board Reinstalled ML20028D2871983-01-0606 January 1983 LER 82-069/03L-0:on 821207,during Startup Testing,Hpci Sys Declared Operable Prior to Closing Out Open Equipment Release Form.Caused by Work Program Design Weakness.Present Work Practice Modified ML20028D2601983-01-0505 January 1983 LER 82-061/01T-0:on 821228,during Startup Testing,While Performing Loss of Offsite Power Test,Emergency Svc Water Pumps B & D Failed to Start.Loop B Failure Caused by Loose Relay Terminal Wiring.Loop D Caused by Contact Adjustment ML20028D2671983-01-0505 January 1983 LER 82-062/01T-0:on 821222,during Loss of Offsite Power Startup Test,Standby Gas Treatment Sys Did Not Operate as Designed When False High Radiation Signal Received from Discharge Monitor.Caused by Monitor Failing High ML20028B7201982-11-24024 November 1982 LER 82-045/03L-0:on 821025,essential Svc Water Pump Failed to Start.Cause Could Not Be Determined or Reproduced.Svc Pump Tested 5 Times W/O Recurrence of Failure ML20028B5821982-11-19019 November 1982 Revised LER 82-026/01T-1:on 820717,review Revealed Certain Cables Discussed in Deficiency Rept 80-00-28 Not Flexed or Grounded Prior to Fuel Load.Caused by Failure to Maintain Control Over Fddr KRI-607 During Turnover of Const ML20028B0301982-11-18018 November 1982 LER 82-042/01T-0:on 821117,personnel Failed to Take Grab Samples When RHR Svc Water Sys Radiation Monitor Was Inoperable ML20028B4351982-11-18018 November 1982 LER 82-043/01T-0:on 821117,determined That Failure of Single Component Could Defeat Overload Detection & Protection Devices for Containment Penetration Carrying Power Cables for Reactor Recirculation Pumps.Cause Not Stated ML20028A9541982-11-16016 November 1982 LER 82-040/03L-0:on 821018,deluge Sys in CREOASS Initiated. Caused by Maint Personnel Bumping Fire Sys thermo-switch on Charcoal Beds.Charcoal Changed Out & Preventive Maint Procedures Modified to Valve Out Deluge Sys During Maint ML20028B0461982-11-12012 November 1982 Revised LER 82-003/01T-2:on 820811,during Initial Fuel Loading,Sprinkler Sys Did Not Exist in Area Designated by Tech Specs & Fire Protection Review Rept.Caused by Discrepancies in as-built Conditions.Mods Initiated ML20028A3341982-11-0303 November 1982 LER 82-034/03L-0:on 821011,during Startup Testing,Creoass Train a Declared Inoperable When Outside Air Damper Failed to Close.Caused by Inadequate Lubrication of Actuator Stem. Stem Lubricated & Damper Returned to Svc ML20027D0591982-10-19019 October 1982 LER 82-027/03L-0:on 820920,two Drywell/Suppression Chamber Vacuum Breakers Gave False Position Indications During Stroking.Caused by Loose Couplings Connecting Limit Switch to Vacuum Relief Valve Shaft.Set Screw Replaced ML17139B0311982-09-13013 September 1982 LER 82-013/03L-0:on 820814,radiation Monitor Found Inoperable.Caused by Faulty Gm Tube & Signal Conditioner (Sensor Converter).Tube & Signal Conditioner Replaced & Monitor Returned to Svc ML20027B0571982-09-0808 September 1982 LER 82-007/01T-1:on 820825,updated Secondary Containment Vol Calculation Had Not Replaced Preliminary Analysis Utilized to Obtain Values in Fsar.Vol Based on Preliminary Calculation Which Did Not Account for Floors & Equipment ML20027A9581982-09-0303 September 1982 LER 82-005/01T-1:on 820820,during Preoperational Testing, Control Room Emergency Outside Air Supply Sys Did Not Automatically Start on Isolation Signal.Caused by Unauthorized Personnel Changing Flow Controller Switch ML17139A9071982-08-0202 August 1982 LER 82-001/01T-0:on 820718,unacceptable Linear Indications Found by Radiograph of A-11 Weld.Cause Not Determined.Welds Repaired Per Approved Repair Program 1998-03-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML17164A8451998-10-31031 October 1998 SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept. 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 ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML18026A4931998-03-30030 March 1998 LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A5401998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18017A2921997-10-28028 October 1997 1997 Nrc/Fema Observed Exercise. ML17158C1861997-06-0505 June 1997 Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18026A4781997-03-28028 March 1997 Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads. ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0511995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr ML20092H7641995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Susquehanna Ses ML17158A8771995-08-15015 August 1995 Exercise Manual. ML17158A8061995-07-14014 July 1995 Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage. ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML17164A5871995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Susquehanna Ses ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A4821994-08-23023 August 1994 ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2 ML17158A2391994-04-0505 April 1994 Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept. ML18017A2701993-12-31031 December 1993 PP&L Annual Rept 1993. ML17158A2651993-12-31031 December 1993 Allegheny Electric Cooperative,Inc Annual Rept 1993. ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML17157C2441993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2 ML18017A2031993-02-0101 February 1993 Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept. ML20044C2741993-01-31031 January 1993 Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions ML17157C3691992-12-31031 December 1992 PP&L Annual Rept 1992. ML20056C3941992-12-31031 December 1992 Allegheny Electric Cooperative,Inc Annual Rept 1992 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B9331992-07-24024 July 1992 Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2 ML20097D4681991-12-31031 December 1991 Pennsylvania Power & Light Company,1991 Annual Rept ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr 1999-09-30 |
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PP&L P nnsylvnnia Powcr & Light Company Two North Ninth Street
- Allentown, PA 18101 e 2151 770 5151 April 29, 1983 Mr. J.M. Allan Acting Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 83-057/01P-0 ER 100450 FILE 841-23 PLA- 1642
Dear Mr. Allan:
This transmission confirms the telephone report of April 28, 1983, by L.D. O'Neil to J.J. McCann of your staff, concerning bypass leakage calculations for feedwater following a design basis accident LOCA.
The condition is considered reportable in accordance with Technical Specification 6.9.1.8h.
M H.W. Keiser Superintendent of Plant-Susquehanna APP /pj g cc: Director, Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Director, Office of Management & Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 8305060442 830429 PDR ADOCK 05000387 S PDR P
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