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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr ML18039A6031998-11-0404 November 1998 LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr ML18039A5971998-10-28028 October 1998 LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve ML18039A5171998-09-15015 September 1998 LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls ML18039A3311998-05-0404 May 1998 LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11 ML18039A3141998-04-0909 April 1998 LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions ML18039A3101998-04-0707 April 1998 LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source ML18039A3051998-04-0101 April 1998 LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized ML18039A2041997-12-0303 December 1997 LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges ML18038B9961997-11-25025 November 1997 LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced ML18038B9931997-11-18018 November 1997 LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated ML18038B9861997-11-10010 November 1997 LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped ML18038B9701997-10-0909 October 1997 LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule ML18038B9661997-10-0303 October 1997 LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed ML18038B9321997-08-0707 August 1997 LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated ML18038B9231997-07-25025 July 1997 LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr ML18038B8811997-05-14014 May 1997 LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr ML18038B8801997-05-0808 May 1997 LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr ML18038B8701997-04-29029 April 1997 LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored ML18038B8521997-04-0909 April 1997 LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr ML18038B8511997-04-0909 April 1997 LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified ML18038B8481997-04-0909 April 1997 LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified ML18038B8451997-04-0909 April 1997 LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr ML18038B8551997-04-0404 April 1997 LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays ML18038B8441997-03-26026 March 1997 LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers ML18038B8071997-01-15015 January 1997 LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR ML18038B8041997-01-13013 January 1997 LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited ML18038B7931996-12-0404 December 1996 LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr ML18038B7921996-11-27027 November 1996 LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr ML18038B7911996-11-27027 November 1996 LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised ML18038B7741996-10-15015 October 1996 LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr 1999-09-30
[Table view] Category:RO)
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr ML18039A6031998-11-0404 November 1998 LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr ML18039A5971998-10-28028 October 1998 LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve ML18039A5171998-09-15015 September 1998 LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls ML18039A3311998-05-0404 May 1998 LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11 ML18039A3141998-04-0909 April 1998 LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions ML18039A3101998-04-0707 April 1998 LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source ML18039A3051998-04-0101 April 1998 LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized ML18039A2041997-12-0303 December 1997 LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges ML18038B9961997-11-25025 November 1997 LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced ML18038B9931997-11-18018 November 1997 LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated ML18038B9861997-11-10010 November 1997 LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped ML18038B9701997-10-0909 October 1997 LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule ML18038B9661997-10-0303 October 1997 LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed ML18038B9321997-08-0707 August 1997 LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated ML18038B9231997-07-25025 July 1997 LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr ML18038B8811997-05-14014 May 1997 LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr ML18038B8801997-05-0808 May 1997 LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr ML18038B8701997-04-29029 April 1997 LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored ML18038B8521997-04-0909 April 1997 LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr ML18038B8511997-04-0909 April 1997 LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified ML18038B8481997-04-0909 April 1997 LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified ML18038B8451997-04-0909 April 1997 LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr ML18038B8551997-04-0404 April 1997 LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays ML18038B8441997-03-26026 March 1997 LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers ML18038B8071997-01-15015 January 1997 LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR ML18038B8041997-01-13013 January 1997 LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited ML18038B7931996-12-0404 December 1996 LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr ML18038B7921996-11-27027 November 1996 LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr ML18038B7911996-11-27027 November 1996 LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised ML18038B7741996-10-15015 October 1996 LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30
[Table view] |
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anwe vam mo e U FDAl t. Ktf0Kr - PREVIOUS REPORT DATE 9/14/81
"# " ~"
..g LICENSEE EVENT REPORT
' CONTROL BLOCK: I n
l l l l l lh 6
(PLEASE PRINT OR TYPE ALL REQUf RED INFORMATION) lo !1l l 8 9 l Al LICENSEE El BICODE Rl Fl 1l@l 0l 0l -l 0lLICENSE le 15 0l 0l 0l Ol -l 0l Ol@l 4lLICENSE NUMBER 25 26 1l Il TYPE Il 1l@l JO l
57 CAT 58 l@
CON'T 1011!
7 8 S lL@lOl51Ol010l2l916@lOl81117l8l1l@l1l1l1l3l811l@
60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB A8LE CONSEQUENCES h J o l 2 l lDurine normal coeration. while nerfoTwing SI 4.1. A-14. turbine first-stage l
,To 131 lperinissive switch 3-PS-1-81A was found 3 percent above limit of T.S. table 3.1.A. l
'lo14l lThere was no dancer to the health or safety of the nublic. Previous similar events: 1
'I o I d i 1BFRO-50-259/78016. 79008. 80058. 81029. 81032. 81038: 260/79016. 79017. 79024. 80020. I I
lo 16 ] 180057. 81030: 296/79007. 79012. 79028. 80022. 80045. 80052. 81007. 81032.
l o l 7 l l Redundant systems were available and coerable. I 1
101811 80 7 8 9 CE CODE SUBC E COMPONENT CODE SUSCODE S E lol91 lI l A lh h [,,J,,,jh lIlNlSlTlRlUlh d h d h 7 8 9 10 11 12 IJ 18 19 20 SE QUE NTI AL OCCURRENCE REPORT REVISION EVENTYEAR REPORT NO. CODE TYPE NO.
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_ 21 22 1-1 23 l01319l 24 26 M
27 1013 l 28 29 M
30
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32 T KEN A ON PL NT MET HOURS SB f FO 8. SU LIE MANUFACTURER
[A_J@l1J@ L2.J@ lzl@ l 010 l 010 I Ly_i@
41 l_yJ@ l4311 @ l B I O l 6 lyh 33 34 3b 36 37 40 42 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l1 i o l lThe Barksdale bourdon tube pressure switch model B2T-A12SS setpoint had drif ted. l li li l IReplaced switch with an identical replacement and functionally tested per SI 4.1.A-14 l 1.
I i i , I lon 10/9/81. Design change request 1398 has been initiated to replace this switch I Ii1al Iwith'an analog transmitter with a trip switch. A study of setpoint drift problems is I Iil$ 1 lattached. 80 I
u 4 ')
'((NE power oTHER STATUS hEsIc"ov50v' oiSCovERv oESCRIPTION @
l1 l r, j d h l0l9l8l@l '
NA l lBl@l Surveillance test ]
A TtytTY CO TENT aELeasto os aELE ASE AMOUNT OF ACTivtiv LOC ATION OF RELEASE W d @ (JJ@l 7 8 9 to . 11 NA 44 l l 45 NA 80 l
Pf RSONNEL EXPOSURES NUMBE R TYPE' DESCHIPTION ll l71l0lolQ,,jh d hl NA l Prnsne.NSiNsuZEs Nums a w,cniPiioN@
l i l a#fl 9l 0 l 0 l 0 lhl 11 12 NA 80 l
t Os5 OF OH DAMAGE TO F AGI iT V tvPE D E SCHIF TION
[i l o l [2 jhl NA l t a 9 to 80
~
i;g j f ESCHIPTION I e I ol [g [@l NA l lll!lIIilllIlgI H J 10 68 69 80 4
~ "
8111240857 811113 psoNs: (205) 729-6134 2 PDR S ADOCK 05000296 PDR
Tennessee Valley Authority Form BF-17
.- Browns Ferry Nuclear Plant BF 15.2 6/04/81 LER SUPPLEMENTAL INFORMATION BFRO-50 296 / 81039 RITechnical Specification Involved Table 3.1.A Reported Under Technical Specification 6.7.2.b(2) *Date due NRC: NA _ , , _
Date of Occurrence 8/17/81 Time of Occurrence 1330 3 Unit Identification and Description of Occurrence:
While performing SI 4.1.A-14, turbine first stage permissive switch 3-PS-1-81A was found 3 percent above the limit of T.S. table 3.1.A.
t Conditions Prior to Occurrence:
i Unit 1 in refeuling outage.
r Unit 2 at 36%.
i 5
Unit 3 at 98%.
r Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
None i
Apparent Cause of Occurrence:
Setpoint drift.
r i Analysis of Occurrence:
There was no danger to the health or safety of the public, no release of 2,
activity, no damage to the plant or equipment, and no resulting significant
! chain of eve nts.
~
l l
i Corrective Action: Replcced switch with an identical replacement and functionally
- tested per SI 4.1.A-14 on 10/9/81. Design change request 1398 has been initiated to replace this switch with an analog transmitter with a trip switch. A study of setpoint drift problems is attached.
i' Failure Data: BFRO-50-259/78016, 79008, 80058, 81029, 81032, 81038; 260/79016, 79017, I
I 79024 N 0, 80057, 81030; 296/79007, 79012, 79028, 80022, 80045, 80052, 81007, l '
81032.
{
- Retention : Period - Lifetime;. Responsibility - Document Control Supervisor
- Revision:
~
1 F -
6.
4 - . . _ . - . -- -
. . - . .- ~. . .
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Subj ect: SETPOINT DRIFT - DARKSDALE PRESSURE SWITC11ES Recently there has been a number of LERs on Barksda,le pressure switches; I
six during 1981, 21 since January 1978. Our commitment _ to training on
' these swit,ches has been strong and continuous, theref ore, we do not
' believe this is the problem.
L Our attention was turned to the switch and the application to which it was being used. At tacbraent 1 plots the setpoint drift of 4 of these switches for a period 6f 4 years. It is readily obvious these switches l- are cyclic, being high in the warm months and low in the cold months.
Attachments 2 and 3 provide the specifications for the Barksdale B2T-Al2SS switch. The important. characteristics f or PS-1-81, 91 are:
Element type: Bourdon Tube Proof Pressure: 1800 psig
> Rated Accuracy: 1% or 12 psig Setpoint: 154 psig - recently changed from 160 psig Adjustable Range: 77-1200 psig It would appear based on Attachments 2 and 3, the switch would perform very reliably. llowever, the reason it does not becomes apparent when Attachment 4 is reviewed. The .f ollowing conclusi. is can be drawn from -
Attachment 4:
u l- For our application, a piston switch is better thon a
,' l.
diaphragm or bcurdon tube. Our experience indicates l the piston type Static-0-Ring to be a very reliable and accurate switch.
- 2. Bourdon tube switches are extremely sensitive to process surges. In our application, snubbers have been in-stalled to help alleviate this deficiency.
i
- 3. For greatest accuracy, the setpoint should fall in the upper 65% of the adjustable range. For the most f avorabic life f actor the setpoint should be in the
- 7 lower 65% of the adjustable range. For PS-1-81. 91:
Span - 1123 and Setpoint (% Span) = 13.7%.
!- t This places these switches in the lower portion of Zone
? C, which is FAIR accuracy and EXCELLENT life. p I
l* Our experience proves this correct. Other switches we
!i have drift problems with are PS-68-93, 94 They have i setpoints of 108 psig or se: point (% span) is 9.6%.
i
[ In the final analysis, one ,can only conclude. a misapplication of these
- I switches, both in switch type and % of adjustable range. We recognized this years ago and DCR 1398 (12/7/77) was initiated. EN DES does not have An implementation date f or DCR 1398 as it now is tied to 79-OlB and environmental qualifications. In the interim we are investigating
;, en improved switch and will keep you informed. ,
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- D del.AVAL TURDINE INC + BAR.tSOALE C0t:1ROLS DiviSICN + 5125 Alcoa AvCnue Los Angeles
- Calal 900%
Hr.sted Bostdon f ute Modela OPERATINGCHARACTERISTICS
%fer fight Houset (NEMA 4) and terminal 5tr p PRESSURE SWITCHES - All values given in P.S.I.(Cauge)
Tseper proof [aternal Adjustment p,,ng Adjustable Rsage Appron.
gp l ggy h (Test) lecreasing increasing 'O' Catalog Catalog tied e Pressure M,n. M a n. Min. Man. (o;rre,ential) MateriaP "" * ' ""*D
I ME1 ~" '
1800 50 1180 70 1200 10lo 20 Bronte BIT H12 02T Hl2 1800 50 1173 77 1200 11 to 27 316 81T Al213 82T A1255 4500 160 3170 190 3200 15 to 30 Dronze BlfH32 BIT H32
;A: 4800 160 3161 199 3200 16 to 39 316 Blf H3255 02i H32$$
7200 240 4715 325 4800 toto 85 316 alTA485s B2T A481$
I " 9750 325 6385 440 6500 54 to ll5 316 OIT A65SS 82TA655$
I *
" 18000 600 11450 1150 12000 275 to S50 316 DIT Al20$$ B2f Al2055
" 24000 603 17450 1150 13000 2751o 550 31 6 l
, ., -. BIT Alltoss!o2T A18055 O *"Bronas" reptesents Phosphor Bronze f ute with SA[ 83 Brass socket BIT SINGLE $tTTING B2T DUAL CONTROL "316" represent: 316 Stamiess steel Tube & Socket
"-AMINC0" female opening for %' 00 tube connection. To chaage A6555 and Al20$%
switches to M* not. add P4 sutfin to model number. Price addition requi ed.
Appronimate shipping weistit 2 5 lbs.
OETalt DATA tt[CTRtCAL CHARACTIR15ftC3: Att models incorporats Underwriters' Laboratories. Inc.
listed Eingle pole dnuble throg snap action switching e!ctnefitt. [lettiscal fating (con-tinuous inductive) 10 amps 125 or 250 volts AC. 3 amps 480 votts AC. Automat =alle reset ty snap action of switch. For more details and other switch classes. see paites 33 35.
EttCTRICAL CONNTC110m: To screer terminals on covercd terrrinal strip through %*nos conduit connector.
WIRE C00lMC - PRissVRE PRI55URE CONNECT 10N: %* N P.T. internal thread except as noted**, anodels with Circuit 41: Comrrion - Purple Proof Pressures abo,e 8.000 P 31. have "AMihCO' fewe cHning for %* 0 0. tuto Normal'y Closed - Blue unnection. Normally Open - Red Circuit s2: Common- Brown AD1USTMENT INSTRUCTICNS Normally Cicsed - Orange Tura selvstment screw clock,ise to to er actuation point (saitch setting). Normatly Open- Yellow Bli D2T 8 315 ----
;;p[y ggg k i , /,3
, P;a P 5 (f* Cutt CMCT104
.:3 3
.. - no itB* MAL Si8 P 5 C0=ratf1 10 int).
^
-l_--- i
- ,s i; senws i -.q&
g 4q
- e. r T f . kf
![eWitat stit? -
3 CCatatrl .
Actusfig; scatw1 8612 *EN l !'A (etuC4 C0vit
) 5 315 /
7A0sutitnG scalw 83 l 40s i_
TC solv 5r) y,,-
tetuovt CCvte I i I
(.rfCieatif *!
s I F C(i /- "
10 aust)
~
O Q._. 'n .
g _
l Cat -l 9tl
/
! _ Ib Not e: All citer dimensons for 02T are the same as 81T Pets cet PCet t{q P t Udth arisiCO' fluail CPf uG W( Nett)".-
(
S 0
0 3 ..
l %< A rTMHMENY 4
. - HOW TO SELECT A PRESSURE SWITCH FOR YOUP. APPLICATION
) STEP 1 SERVICE tr E OF THE SWITCH Terminal hMcii pressure sw.iches are houmi and en aritti.
l'On. 're *';uipped with enrinsed term.nat titocks thas Especteo service hf e is the first considesation to be made ehm'nat'r'E t'io t a pen *,*: 'if buying and installirq enteretnl an selectmg d pressure switcli. regaidless c: the pressure junction bones.
or sensitnnty desired. If the serveco ble (the r umtpr of Emplosion prrx,f pressure sw tches are cessitned with ! cavy cycles the switch es espected to operate) es one rind on er housings huvt to conform to .icrepted electncal standards less, use of either a bourdon tube c,r diaphragm snatch is m isotating the umt?. fenm explosive atmosphere. All cu-indicated. il a service hfe of more than one miNeon cycles plosion pecot enodels are courpped with termmal blods is desired, a proton switch should be used/An exception for convenience in wirinC.
to this rule may be made whern pressure change in a sys-tem asirefy shght (20% or less, of the adfustatste rance).
STEP 5 SELECYlON OF ADJUSTABLE RAftGC Uncerl such conditions a bourdon , tube or diaphragm switch can be used up to 2.5 millica cyctes tvefore metaf The term ,, working range" defmes the pressure rance a fatigue, switch may see under nortnat workmg conditions this is A second consideration in choosmg a pressure switch as normally the adjustahte rar ge, the speeo of CYCL *S. regardless of the service hf e. If a for greatest accuracy the set pomt should f allin the upper switch is espected to cycle more than once every three gg g seconda, a pisten type switch should be specified. The factor the set point should te in the lower 65% of the metal of any bourdon tube of Claphragni acts as a spring adjustable range. Therefore, the most favorable combina-which will heat and fatigue in entremely fast cycfmg tion of accuracy and life facter lies in the rmddle 30% of operations, thus shortening the life of the switch,
- the ediustable range (scc diagram) This general rule The media to be centtolled must slaays be considered apphes both to diaphragm and bourdon tube pressure when selecting a pressure switch and.to simplify selection, switche s.
wetted materials for each type of swetch are noted on applicabie Catalog pages, t ice acNaser s Ort stWr rent 4 ,,,,
'8ws8 r rLn Uit seurs fW C v e=
PROOF PRESSURES STEP 2 Choice of the type of pressure smtch to be used - d.3-
/
p*1ragm, bourdon tutie or piston - also must be governed C""
"*-r naassure to which it will be subjected. f Proof [
'"**sure that will over be . :l -
j, n arbered that. l wnstant oper- l although a pressure ggawgs en.9 y .*""* -o
/jg / ll emig pressure, there may t;e surges go.ng througn a sys- w,,,
tern that are dampened out by the onface m the Eaun 5 -
t~
Diaphragm and bourdon tube pressure switches are en-tremely sensitive and would be affected tsy those surges.
l !' ,
3 M Darksdale drapnragm switches are available in an adjust- -
at,te range from vacuum to 150 psi with proof pressures af,' f 'N.( i_
to 300 psi.Herksdale bourdon tube switenes are art i u. table ,
S **
{l 6
to 18,000 psiwith proof pressures of 24.0M psi. Berksifale 'l$ ;*h l ' ,,,,,,.,,
piston switches have an adjust =hte rae.go tr.,12.000 pse ;
ai c . *'
with a proof pressure of 20,000 psi. wi.ci /p_o..! r.u .or coco Feneur ia -
FUNCTION OF THE Swi1CH
' " ' L'.9 '"
- STEP 3 The function of the switch is another determmm,t factor in mahmg is selection. Thece types of Darkssaia presuire switches, based on function, are itescribed below. HOW f 0 7EAD CMALOG NilhtDERS OF (1) Singte setting pressure switches sense a smete rres- DIAPHitACM sure source and open or close a smgte efect9ca r circuit
- by means of one snap ection electrical switch. g g g g, l c. (2) Pressure difference switches sense a change un refa-
! tionship between two variaL4 contained pressures and DIA. SEAL PISTON l
open or close a single electrical circuit by means of one PRESSURE SWITCHES
! snap action electrical switch.
(3) Dual contret pressure switches serise two prcuure m ura meen
. ; hmits frorn a single pressure source and open or cfose two r,,,,,.,,,,,,,,,,,,,.,,y.,,,,n,,,,,,,,,,,g,,p.g,,s.,
- independent electrical chcmts by means of two snap action i,,, ,,, ,, s,. ,, i . s.. , s,ii.., p . t,, ,i c.c. .
electrical switch es. r, .. weg s. sm, , ii . w.m n....s ma j r . a.sm,.sn .e n ,as .a s . .a e.s
, . g ,,, ,,g
, e TYPES OF HOUSING AVAtt.ADLE STEP 4 ete *
! l Stripped pressure switches are basic Barksdale peessure *****88""
switch units without housings. TPey may be used whereves j'"
atectrical enclosures are atteady available and are tevorrei by original eWpment manuf actu rers for uso m t.ommon -- Olt $1055 UL si,.g cabinets featurally, stripped switches may be purchased ,,, ,,,,,,,,,,,,, , , , , , , , , , ,
u ,, ,,,,,,,,,,,n,,,,,,,,,,,,,,,,,,,,;.,,,,,, o.. *as;te:s.
at a lower cost. *
..e fo w b..iiastw s'ws Hous'eY p'ress6re switches are comt)letely enclos.wf to s. %. .~ . ,,. .w . o ti n s 'c s < v
4.o.d possibie narard inom iew w.res in c.veen soc . ...i....,,,........,
l tions, s
I .
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