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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000311/LER-1990-0301990-07-24024 July 1990 LER 90-030-00:on 900703,ESF Actuation Containment Purge/ Pressure Vacuum Relief Sys Isolation Occurred After Channel Function Not Placed in Block.Caused by Personnel Error. Individuals Involved Held accountable.W/900724 Ltr 05000311/LER-1990-0271990-07-17017 July 1990 LER 90-027-00:on 900628,determined That ESF Signal Actuation 2R41C Channel Failed Low Due to 2R45 Interlock.Caused by Design/Equipment Concerns.Engineering Investigated Concerns & Uninterruptable Power Sys installed.W/900717 Ltr 05000311/LER-1990-0261990-07-0909 July 1990 LER 90-026-00:on 900609,radiation Monitoring Sys Channel 2R12B Failed Low.Caused by Design/Equipment Concerns.Failed Components Replaced & Pins Connecting Backplane Replaced W/Longer pins.W/900709 Ltr 05000311/LER-1984-010, Corrected LER 84-010-00:on 840423,during Startup Operations, Turbine Trip & Reactor Trip Occurred.Caused by hi-hi Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed1984-05-23023 May 1984 Corrected LER 84-010-00:on 840423,during Startup Operations, Turbine Trip & Reactor Trip Occurred.Caused by hi-hi Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed 05000272/LER-1981-059, Supplemental LER 81-059/01X-01:on 810616,during Initial Testing,Auxiliary Feedwater Pump 23 Turbine Steam Supply Check Valves 21MS46 & 23MS46 Found Damaged Internally.Caused by Steam Flow Sys Oscillations1984-02-24024 February 1984 Supplemental LER 81-059/01X-01:on 810616,during Initial Testing,Auxiliary Feedwater Pump 23 Turbine Steam Supply Check Valves 21MS46 & 23MS46 Found Damaged Internally.Caused by Steam Flow Sys Oscillations 05000272/LER-1983-062, Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced1984-02-24024 February 1984 Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced 05000272/LER-1979-068, Supplemental LER 79-068/03X-1:on 791018,safety Injection Pump Motor 12 Tripped on Overcurrent.Caused by Impeller Locknuts Improperly Secured at Mfg Facility.Pumps Reassembled Using Locktite Compound1984-02-24024 February 1984 Supplemental LER 79-068/03X-1:on 791018,safety Injection Pump Motor 12 Tripped on Overcurrent.Caused by Impeller Locknuts Improperly Secured at Mfg Facility.Pumps Reassembled Using Locktite Compound 05000311/LER-1982-141, Updated LER 82-141/03X-1:on 821121 & 1204,P-250 Computer Inoperable Due to Parity Error.Caused by Periodic Increases in Ambient Temp Due to Insufficient Ventilation.Computer Reprogrammed & Action Statement Terminated1983-12-16016 December 1983 Updated LER 82-141/03X-1:on 821121 & 1204,P-250 Computer Inoperable Due to Parity Error.Caused by Periodic Increases in Ambient Temp Due to Insufficient Ventilation.Computer Reprogrammed & Action Statement Terminated 05000272/LER-1983-023, Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented1983-12-13013 December 1983 Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented 05000272/LER-1982-024, Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised1983-11-17017 November 1983 Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised 05000311/LER-1982-017, Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve1983-11-17017 November 1983 Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve 05000272/LER-1982-029, Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve1983-11-17017 November 1983 Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve 05000311/LER-1982-001, Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed1983-11-11011 November 1983 Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed 05000311/LER-1983-017, Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified1983-09-16016 September 1983 Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified 05000272/LER-1983-008, Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions1983-07-13013 July 1983 Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions 05000311/LER-1982-077, Supplemental LER 82-077/01X-1:on 820818,leakage Discovered from Containment Fan Coil 21.Caused by Erosion of Copper Nickel Piping.Cooling Coils Replaced w/erosion-resistant Matl1983-06-29029 June 1983 Supplemental LER 82-077/01X-1:on 820818,leakage Discovered from Containment Fan Coil 21.Caused by Erosion of Copper Nickel Piping.Cooling Coils Replaced w/erosion-resistant Matl 05000311/LER-1982-024, Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added1983-06-29029 June 1983 Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added 05000311/LER-1982-070, Supplemental LER 82-070/01X-1:on 830809,0.5 Gpm Svc Water Leak Observed on Containment Fan Coil 24.Caused by Failed Cooling Coil Resulting from Silt Erosion by Particles in Svc Water1983-06-29029 June 1983 Supplemental LER 82-070/01X-1:on 830809,0.5 Gpm Svc Water Leak Observed on Containment Fan Coil 24.Caused by Failed Cooling Coil Resulting from Silt Erosion by Particles in Svc Water 05000311/LER-1982-092, Supplemental LER 82-092/01X-1:on 820908,svc Water Leak Discovered on Containment Fan Coil Unit 21,rendering Unit Inoperable.Caused by Motor Cooler Erosion Due to Silt in Svc Water.Cooler Replaced1983-06-29029 June 1983 Supplemental LER 82-092/01X-1:on 820908,svc Water Leak Discovered on Containment Fan Coil Unit 21,rendering Unit Inoperable.Caused by Motor Cooler Erosion Due to Silt in Svc Water.Cooler Replaced 05000272/LER-1982-090, Supplemental LER 82-090/01X-1:on 821121,video Insp of Removed Fuel Assemblies Revealed Cladding Ruptures on Element 13 in Fuel Assembly D-20.Caused by Isolated Instance of Secondary Hydriding1983-06-29029 June 1983 Supplemental LER 82-090/01X-1:on 821121,video Insp of Removed Fuel Assemblies Revealed Cladding Ruptures on Element 13 in Fuel Assembly D-20.Caused by Isolated Instance of Secondary Hydriding 05000311/LER-1983-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired1983-06-0808 June 1983 Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired 05000272/LER-1982-091, Supplemental LER 82-091/01X-1:on 821130,operator Discovered Leakage from Weld of Svc Water Piping to Component Cooling HX 12.Caused by Extensive Biofouling & Corrosion of Circumferential Welds1983-06-0808 June 1983 Supplemental LER 82-091/01X-1:on 821130,operator Discovered Leakage from Weld of Svc Water Piping to Component Cooling HX 12.Caused by Extensive Biofouling & Corrosion of Circumferential Welds 05000272/LER-1982-083, Supplemental LER 82-083/03X-1:on 821102,control Room Operator Observed Temp Recorder for Air temp-delta T Channels Not Printing.Caused by Failure of Pinion Gear on Chart Drive Motor.Motor Replaced1983-06-0101 June 1983 Supplemental LER 82-083/03X-1:on 821102,control Room Operator Observed Temp Recorder for Air temp-delta T Channels Not Printing.Caused by Failure of Pinion Gear on Chart Drive Motor.Motor Replaced 05000272/LER-1982-035, Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced1983-06-0101 June 1983 Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced 05000311/LER-1982-083, Supplemental LER 82-083/03X-1:on 820812,during Routine Surveillance,Control Room Operator Received Low Svc Water Flow Indication on Containment Fan Coil Unit (Cfcu) 25. Caused by Oysters or Silt Restricting Cfcu Flow1983-04-20020 April 1983 Supplemental LER 82-083/03X-1:on 820812,during Routine Surveillance,Control Room Operator Received Low Svc Water Flow Indication on Containment Fan Coil Unit (Cfcu) 25. Caused by Oysters or Silt Restricting Cfcu Flow 05000272/LER-1981-121, Supplemental LER 81-121/03X-1:on 811228,svc Water Leak in Spool Piece Discovered Between Valves 12SW57 & 58.Design Change Package 1EC-0504 Implemented to Replace Piece W/Stainless Steel for Improved Corrosion Resistance1983-03-30030 March 1983 Supplemental LER 81-121/03X-1:on 811228,svc Water Leak in Spool Piece Discovered Between Valves 12SW57 & 58.Design Change Package 1EC-0504 Implemented to Replace Piece W/Stainless Steel for Improved Corrosion Resistance 05000272/LER-1982-081, Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt1983-03-0303 March 1983 Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt 05000272/LER-1983-012, Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway1983-02-28028 February 1983 Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway 05000311/LER-1983-007, Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days1983-02-18018 February 1983 Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days 05000272/LER-1982-002, Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing1982-12-29029 December 1982 Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing 05000272/LER-1982-008, Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added1982-12-29029 December 1982 Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added 05000311/LER-1982-015, Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip1982-12-0808 December 1982 Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip 05000311/LER-1981-089, Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened1982-11-0303 November 1982 Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened 05000311/LER-1982-027, Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State1982-10-20020 October 1982 Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State 05000272/LER-1982-042, Supplemental LER 82-042/03X-1:on 820628,valves 12AF10 & 12AF86 Discovered Open.Caused by Personnel Negligence in Failure to Notice That Chains on Valves Improperly Installed.Valve Operation & Tagging Lesson Plans Revised1982-10-20020 October 1982 Supplemental LER 82-042/03X-1:on 820628,valves 12AF10 & 12AF86 Discovered Open.Caused by Personnel Negligence in Failure to Notice That Chains on Valves Improperly Installed.Valve Operation & Tagging Lesson Plans Revised 05000272/LER-1982-009, Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage1982-10-20020 October 1982 Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage 05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo1982-10-20020 October 1982 Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage 05000311/LER-1982-072, Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled1982-10-20020 October 1982 Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled 05000272/LER-1982-004, Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration1982-10-20020 October 1982 Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration 05000311/LER-1982-111, Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-241982-10-0404 October 1982 Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-24 05000311/LER-1982-084, Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress1982-08-30030 August 1982 Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress 05000311/LER-1982-074, Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges1982-08-18018 August 1982 Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges 05000272/LER-1982-0031982-05-26026 May 1982 LER 82-03L/031-0:on 820502,while Testing Valve 11SW122, Safeguards Equipment Control Cabinet Actuation Occurred. Caused by Locked Out Supply Breaker to Safety Injection Pump 11,due to Spurious Nature of Actuation 05000272/LER-1982-028, Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated1982-05-21021 May 1982 Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated 05000311/LER-1982-0191982-03-31031 March 1982 LER 82-019/03L-0:on 820307,undervoltage Condition in Safeguards Equipment Control Cabinet Caused Mod 1 2A Sec Actuation.Caused by Failure of Card File Assembly.Card File Assembly Replaced & Loads Secured.Sys Returned to Svc 05000272/LER-1982-0141982-03-31031 March 1982 LER 82-014/03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable 05000311/LER-1982-0181982-03-31031 March 1982 LER 82-018/03L-0:on 820304,steam Generator 24 Feedwater Channel 2 Flow Indicator Failed.Caused by Failure of Force Motor in Flow Transmitter.Transmitter Properly Repaired, Calibr & Returned to Svc 05000272/LER-1981-0921981-11-0202 November 1981 LER 81-092/01T-0:on 811020,during Routine Containment Insp, Operator Discovered Svc Water Leaking from Third from Top Secondary Coil on Containment Fan Coil Unit 15.Caused by Secondary Coil Failure.Leaking Coil Blank Flanged Off 05000311/LER-1981-0361981-07-0606 July 1981 LER 81-036/03L-0:on 810606,pressurizer Pressure Channel 1 Indicated Greater than Max Allowable Tolerance.Caused by Pressure Transmitter 2PT455 Out of Spec.Unit Calibr & Returned to Svc 05000272/LER-1976-030, Updated LER 76-030/03L:on 761228,during Sample Analysis of Boric Acid Storage Tanks 11 & 12,boron Concentration Noted Low.Cause Unknown.Chemical Analysis After Batching Confirmed Findings1978-04-0404 April 1978 Updated LER 76-030/03L:on 761228,during Sample Analysis of Boric Acid Storage Tanks 11 & 12,boron Concentration Noted Low.Cause Unknown.Chemical Analysis After Batching Confirmed Findings 1990-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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LER-2083-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired |
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~ r, 1 a.m LICENSEE EVENT REPORT coNTrot stoCx: l l l l l l@ :PLE AsE PRINT cm iveE ALL tE:uinEo iNEenuari:Ni foTil'Is la IS la IS 12 Igl of ol -1 ofLtCENSE of of of ol -l ol ol@l 4 l 11 li 11 lI@L i ig.
- 1 8 9 LICENSEE CODE .4 it Nved8ER 25 26 LICENSE TYPE Jo 67 Cai se CON'T b EU l Ol SI OI 010131il1@l0 l5 l2 l 7l 8l 3 @l 0l 6l 0l 8l 8 l 3 lg 74 75 J B 40 Si DOCKET NUMSER 88 69 EVENT D ATE REPORT DATE $0 EVENT DESCRIPTION AND PROB 8LE CONSEQUENCES O'o g l From January 17 to April 18, 1983, routine surveillance of Containment Type B and C
o l components revealed 7 containment isolation valves with leakage raten greater than the o , g maximum range of the test equipment. It was therefore not possible to demonstrate thatj gg the total Type B and C leakage was less than 0.60 La as required by the Technical o 6 l Specifications. All valves were repaired and satisfactorily tested; combined leakage a 7 gwas satisfactory prior to plant startup. The event involved potential operation in a gg degraded mode in accordance with Technical Specification 6.9.1.9b. g 7 se so
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31 L11@ LA_l@ l"I112i0ih 40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l Steam Generator Blowdown Valve 23GB4 was steam cut; due to normal pressure in the steaq y l generator being greater than containment design pressure, a license change to eliminatq
, 7 l testing of the valve is being considered. Valve 2VC6 liner was found damaged. Investy
, 3 lgation of routine liner replacement is underway. Finally the failure of 4 air particuq i 4 l late detector backup sample line valves was attributed to insufficient seating pressurg 7-apes Qyiyring initial stroke adjustment, A e ygQ g g,were restroked. 80 status sPoWER oTHER $fATUS k,,,) DISCOVERY DISCOVERY DESCRIPTION h 1 5 d h l0l0l0l@l AETiviry coSTENT " "
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, O PSEG Public Service Electric and Gas Company P.O. Box E Pancocks Bridge, New Jersey 08038 Salem' Generating Station July 11, 1983 Dr. Thomas E. Murley .
Regional' Administrator USNRC Region 1 631 Park-Avenue King'of Prussia, Pennsylvania 19406
Dear Dr..Murley:
LICENSE NO.-DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 83-023/03L This letter is to correct errors in previously submitted
. Licensee Event Report 83-023/03L (the report was erroneously dated August 6, 1983). The corrected report is attached.
Sincerely yours, f
7 6,
J. M. Zupko, Jr.
General Manager -
Salem Operations
' RF:kls
- CC:' -Distribution The Energy People .
poV l i' 95-2169 (20M) 118i
, Report Number: 83-023/03L
~
Report Date:- 06-08 Occurrence Date: 05-27-83 -
= Facility:/ -Salem-Generating Station Unit 2 Public Service Electric & Gas. Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
' Containment Systems - Containment Type B and C Leak Rate -
.Out-of-Specification.
This report:was initiated by Incident Report 82-118.
CONDITIONS PRIOR TO OCCURRENCE: l Mode 5 - Rx Power 0 5 - Unit Load 0 MWe. ;
DESCRIPTION OF OCCURRENCE: .
~
.From January 17 to April 18, 1983, during a scheduled refueling, routine surveillance of Containment Type B and C components. revealed 7 containment isolation valves with leakage rates greater than the
. maximum range of the leak rate test equipment (20,000 acem). The i components involved were Containment Isolation Valves 23GB4, 2VC5, 2VC6, 2VC9, 2VC10, 2VC13, and 2VC14. Since actual. leakage due to each l valve could.not be ascertained, it was not possible to demonstrate !
that the total Type B and'C leakage uas less than 0.60 La as required 4
by Technical Specifications Limiting Condition for Oper ation 3.6.1.2b
.(applicable only in Modes 1 through 4).
The integrity of the steam generator. tubes was maintained during
- previous operation providing a redundant barrier to Steam Generator Blowdown Valve 23GB4. Valves 2VC5 and 2VC6 are tested together since
.no isolation capability exists to allow separate testing.-
Investigation revealed that the leakage was, in fact, past. Valve 2VC5,
-with Valve-2VC6 providing a-redundant boundary. The remaining valves were in the backup' sampling lines'for the Containment air particulate
-detector-(APD). The_-Technical Specifications had previously exempted these valves;from leak-rate' testing since they are normally closed-and
. operated only on an intermittant basis.
All valves) involved.in the occurrence were' repaired and satisfactorily.
. tested; combined Type-B and C leakage was determined to be within
' specification prior to returning to Mode 4 operation.
APPARENT CAUSE OF OCCURRENCE:
4 Disassembly ~of Steam Generator Blowdown Va'lve 23GB4 reveale9 that the valve seating. surfaces ~were damaged by steam cutting. As-noted, investigation-revealed-leakage past Valve 2VC5; an inspection of the 1 valve showed degradation'of.the rubber valve liner. 1No degradation t
was found in the case of Valve 2VC6. Reduced life of-the linera has been.noted:and.the. manufacturer has' suggested-replacing them on a
' routine basis.
. - + , . a-. - _ . ~ - - = - -- -. - . - - . .. ....- - a . = - - , , -- .
-LER 83-023/03L , APPARENT CAUSE OF OCCURRENCE: (cont'd)
The APD sample line isolation valves tested satisfactorily following stroking of the valves.. As noted, the Technical Specifications
.oxempted the valves from leak rate testing. The valves had recently been added to the procedure,-and were tested this refueling for the first: time since plant startup. It was assumed that the original otroke adjustment of the valves did not provide adequate force to maintain-seating'of the valves with normal wear of the seat and reduction in actuator spring tension.
ANALYSIS OF OCCURRENCE:
The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the cccident analyses at the peak accident pressure of 47 psig.
Action Statement 3.6.1.2 requires:
With either the measured overall integrated containment leakage rate exceeding 0.75 La, or with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System (RCS) temperature above 200 F.
Leakage rate limits during performance of periodic tests incorporate conservatism to account for possible degradation of the leakage barriers between testing. The combined leakage rate had previously been demonstrated within specification during leak rate testing in 1980-81. As noted, the valves were repaired and total leakage was demonstrated to be within specification during the recent testing.
Due to the loss of redundancy in containment barriers, the event constituted operation in a degraded mode permitted by a limiting condition for operation. The occurence is reportable in accordance with Technical Specification 6.9.1.9b.
CORRECTIVE ACTION:
Valve 23GB4 was reworked and satisfactorily tested. Problems with steam cutting in the Type GB4 valves have previously been noted in Salem Unit 1 (see Unit 1 LER 83-010/03L). Investigation of the problem is underway. In view of the fact that the steam generator would be at a higher pressure than the 47 psig design pressure of the Containment System, consideration is being given to submitting a license change to delete the requirement for testing the valves.
The rubber liners on Valves 2VC5 and 2VC6 were replaced. Based on the recommendations of the manufacturer, investigation of routine replacement of the liners is in progress. As noted, Valves 2VC9, 2VC10, 2VC13 and 2VC14 were restroked and satisfactorily tested.
Following repair of all valves with excessive leakage, final results of Type B and C leak rate testing demonst.ated combined-leakage was within specification.
L
, LER'83-023/03L , FAILURE DAIA:
Masoneilan International, Inc.
'3/4 inch Control Valve Model 38-20571
- Masoneilan International, Inc.
10 inch Control-Valve Type 69-32200
. Prepared By R.'Frahm ' N V
(/ Genen'1 4 Man'ager -
Salem Operations SORC Meeting No.89-077 e
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05000311/LER-1983-001, Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | Forwards LER 83-001/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-002, Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | Forwards LER 83-002/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-003, Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | Forwards LER 83-003/04L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-004, Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | Forwards LER 83-004/04L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-004, Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | Forwards LER 83-004/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-005, Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | Forwards LER 83-005/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | Forwards LER 83-006/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-007, Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | Forwards LER 83-007/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-007, Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days | | 05000311/LER-1983-008, Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | Forwards LER 83-008/99X-0.Detailed Event Anaysis Encl | | 05000272/LER-1983-008, Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions | | 05000311/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-009, Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | Forwards LER 83-009/99X-0.Detailed Event Analysis Encl | | 05000311/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-011, Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | Forwards LER 83-011/01T-0.Detailed Event Analysis Encl | | 05000311/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | Forwards LER 83-011/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-012, Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway | Telecopy Message of LER 83-012/01P-0:on 830222,both Reactor Trip Breakers Failed to Open.Cause Not Yet Determined. Investigation Underway | | 05000311/LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | Forwards LER 83-013/99T-0.Detailed Event Analysis Encl | | 05000272/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-017, Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified | Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified | | 05000272/LER-1983-017, Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1983-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired | Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired | | 05000272/LER-1983-023, Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented | Supplemental LER 83-023/01X-1:on 830602,notification Received from Westinghouse of Potential Unreviewed Safety Question Re Operation at Full Power Following Extended Reduced Power Operation.Procedures Implemented | | 05000272/LER-1983-062, Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced | Supplemental LER 83-062/99X-1:on 831122,during Testing on Seismic Instrumentation,Triaxial Time History Accelograph Did Not Respond as Required.Caused by Detector Failure. Accelerometer Replaced | | 05000311/LER-1983-083, Forwards Supplemental LER 83-083/03X-1.Detailed Event Analysis Encl | Forwards Supplemental LER 83-083/03X-1.Detailed Event Analysis Encl | |
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