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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] |
Text
'
- u. s. NUCLEAR CEGuLATORY C00secespeces tRcFgRt4 sea. UPDATE REP 0JtT - PREVIOUS REPORT DATE 6/25/81 j (7 771* LICENSEE EVEMT REPORT CONTHOL BLOCK: I I l l l l 1h 6
(PLEASE PRINT OR )YPE ALL RE!uf EE3 INPZesATIONI l @
[o l t l l Al Ll Bl Rl Pl 2l@IS0l 0l -l 0l 0l 0l Ol 0l-l 0l760 @ 264 l 1 l 1 l 1 57 CAT Sil LICENSE TYPE JO 44 LICENSE NuMSEA 7 8 9 LICENSEE CoOE
- i CON'T 101 1 y',"c' LIJ@l 01 510101012161 ooCKET NuweER 88 ol@l 88 016111118111@l EVENT oATE 74 79 017oATE RSPoRT l 21418 80 l 1 l@ .
i
'/ 8 eo el EVENT DESCntPTION AND PROGA8LE CONSEQUENCE 5 h SI 4.2.B.8, l Q l Durine a maintenance outane. while oerformina routine surveillance test. ,
@Ti'l I reactor high-pressure switches _ PS 68-93 switch 12 and PS 68-94 switch #2 controlling j 9
1 TOTT] I shutdown coolina valves of the RHR system were found above limits of T.S. Table 3.2.A.)
There was no danger to the health I e ITITI l_ The areatest out of tolerance was 6.5 percent. i i
BFRO-50-259/7816. 7908, 8058, j
@ l or ==fety of the oublic. Previous s4=11mr events: )
l'oTTlI 8129. 8132r 260/7802. 7917. 7924. 8022. 8057. 8123: 296/7907. 7912. 7928, 8022, I {
loIail 8030. 8045. 8052. 8107.
NE yon su N E couroNENT COct OE 5 C E l,o,1,2J.
- l. C l F l@ L,,rJ@ LrJ@ I 2r i N I S I r i a i n i@ r io i
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htEPo84T NO 3 Tv O ug(R/Ho a
L EVENTYEAM I8111
,_2 8 22 L--J 23 10 218 24 21 ,
a 27 10111 25 29 px y1 y3lj EN" 'EYS oVIEr *Ee E Bo' e5IsSus. ET uAYNAcEden A
- fe'TYw Nouns l 0 l 01 O f g g g l15l0l6[9lg CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I i l o I l Setpoint drif t. Setpoints on the model B2T-M12SS pressure switches were reset to thej Addi- 1 t, roper value, and the survei.llance instruction was completed satisfactorily.
L' ).1.) I j
i7 I tionally, a design change request (DCR 1398) has been' initiated to replace these
)
Lij,1) I switches with an analog transmitter with a trip switch.
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' oiscovenyoEseniPrioN @
'sTEIs* snowEn oTwEnsTArus @SiEoSEEv' l I5l (.g.j @ l 01 Ol 0l @ l NA l Q @l Surveillance test l
' Activity ColrENT '* "
LOCATION op MELEASE @
aELEAsto OF aELEASE j l AMoVNToP NA ACTIVITv l
@l NA LiJ.aJ
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Nuu.Ea ex,or. L1J@sEs Tv,E oEsca., Tion @
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' eusti$7v PDR ADOCK 05000260 otsCniefioNh S PDR g l ; ; ; ; g g g {g 3 l.d.13 ! esvehl_ 68 69 30 g a
- al 9 10 Gene Holder (205) 729-6134 6, PHONE:
NAME OF PREPARER m
Form BF 17
-
- Tennessee Valley Authority DF 15.2 Brrmns Ferry Nuclear Pl. int 6/04/81 1
LER SUPPLEMENTAL ISFORMATION e Table 3.2.A :
n t. ItO -r,0- 260 / 81028 R1 T+ chaical Specification involved .
Itcported Under Technical Spec;fication . 6.7.2.AO)
. 0920 1115 Unit 2 $,
l)are of Occurrence _6/.1._1_/_8_1__ Time of Occurrence 7
Idt ntification and !)c.s cription of Occurrence:
Durinig ~St 4'.'2.Y.T,"reac'toiT1gh pressure switches were found above T.S. limits. ;
At 0920 PS 68-93 switch #2 was found at 124 psi; at 1115, PS 68-94 switch #2 was found at 131 pai. Test limit is 123 ysi, which is the limit of 115 psi a l.
plus 8 psi water leg. 4 e
Conditions Prior to O_ccurrence:
Chit I ref~ueling outags~ ,
Unit 2 maintenance outage. I f
Unit 3 at 100%. !
I i
i Action specified in the Technical Specification Surveillance Requirements met j-
.due tc inoperable equipment. Describe.
=
None 't I
p.pp.trent Cause of O< currence: . j Setpoint drif t. -
1-An3hsis of Occurrence:
There was no danger to the health or safety of the public, nh release of actirity, no damage to :.he plant or equipment, and no resulting significant chain of events.
fjorr,!.ctive Act_io,n : Setpoints wer'e reset to the proper value, and the surveillance instruction completec' satisfactorily. Additionally, a desigir change request (DCR 1398) has been initiated to replace these switches with an analog transmitter with a trip switch. A study of the setpoin~. drift problem is attached.
t l
BPd) 50-259/7816, 7908, 8058, 8129, 813"; 260/7802, 7917, 7924, Failure 80zz, cuai, Data:8123; 296/7907, 7912, 7928, 8022, 8030, 8045, 8052, 8107.
j Period - 1.ifetime; Responsibility - Document Control Supervisor 3etention:
/ s
1 . . .
e E
yi
Subject:
SETPOINT DRIFT - BARKSDALE PRESSURE SWITCllES *
-l
- e. f i
Recently there has been a number of LERs on Barksdale pressure switches; {
six during 1981, 21 since January 1978. Our commitment to training on ,
these switches has been strong and continuous; therefore, we do not /,
believe this is the problem. )
Our attention was turned to the switch and the application to which it Il i
was being used. Attachment 1 plots the setpoint drift of 4 of these j switches for a period of 4 years. It is readily obvious these switches m are cyclic, being high in the warm months and low in the cold months. }l Attachments 2 and 3 provide the specifications for the Barksdale pj B2T-A12SS switch. The important characteristics f or PS-1-81, 91 are: $
Element type: Bourdon Tube
Proof Pressure: 1800 psig , ;
Rated Accuracy: tl% or 12 psig '
. I 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 perfonn e very reliably. However, the reason it does not becomes apparent when Attachment 4 is reviewed. The following conclusions can be drawn from Attachment 4:
- 1. For our application, a piston switch is better than a I diaphrage or bourdon tube. Our experience indicates.
{
the piston type Static-0-Ring to be a very reliable ^ _
r and accurate switch. -
t
- 2. Bourdon tube switches are extremely sensitive to prosess 5 surges. In our application, snubbers have been in-stalled to help alleviate this deficiency.
- 3. For greatest accurt_y, the setpoint should fall b the upper 65% oC the adjustable range. For the most f avorable life iactor the setpoint should be in the lower 65% of the adjustable range. For PS-1-81, 91:
Span = 1123 and setpoint (% Span) = 13.7%.
This places these swi:ches in the lower portion of Zone C, which is FAIR accuracy and EXCELLENT life.
Our experience proves this correct. Other switches we have drif t problems with are PS-68-93, 94. They have setpoints of 108 psig or setpoint (% span) is 9.6%. ,
In the final analysis, one can only conclude a misapplication of these 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 for DCR 1398 as it now is tied to 79-01B and environmental qualifications. In the interim we are investigating an improved switch and will keep you informed.
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!!;5TF.U::E ii DATA SHEET 'i 224A9300 -
1 DRESEURE S'.4ITCII SRC::!:S FERRY 1~2,3 -
e., e $.m 95 i ,. 95 rnsi m.t t r::a L -l- St !- ',,
- ITE!' (TAG) ?!O 5-11A r.o 0 . l5-1? t r. 9 i Eia a b-91o l ~
4 4 l l .1 l fi $
- 00*flTITY /PLA:li e l lD"'.i en !T oore l ne: 1,
- sTr. g., l . ).
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- SERV!CE I cot:0 VAC'eti ,
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. ELEMEllT: DIAPHRAG!1 BOURDO:t TUBE ,- t.
TYPE DIAPHF.AGli ~
MAii.d! AL 55 Bil!!A ti l' lSS
[,
. BODY MATEP.IAL ,
C0;it;ECTOR SIZE , i ga npT :1 n. nor I n nor
< i SCALE RA;;GE/UillTS l ,
1-S!!AP ACTIO t ,
5::AP ACT10:1 . 2-5:!AP ACTIC:: --
CD:lTACT: i TYPE /FOR!i SPDT 0 POT SPOT RAT!!iG -
Ina a los i!sc lina n pen ife.c l f 10A a 120 VAC 'g
)
- RE00 rat;GE ( ADJ) ! l0-5osio l I
- C0:! TACT #1 CPER AT l?3.3!!! HG '!AC DEd I1 M: m b '9- I' l.8"d 7 % I' C 9 f
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- CO ITACT d2 CFER AT lspaor l lco:gg l5cq- ' $
PURCHASE R :; E (*.0J11 2_?o ? p pr: l l .y_s m in
F.ESET 5 A:t O!F~ l . .:_ , p i n pr; l ,1 e . 2 ; .
,,,4,, l l1177.,,, -
- - 1 PP..us Frecs -. .S go .e 5 i . . n ., , 4 , l l i c nn .,4,.
- PP.CCE55 FLUID l l I l fg-
- DE5!G:1 TE::P l. .
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- CESIGi PRESS 1 4
- t;CE:'AL TE '? f I * !:00.:'*L PRESS 27-?9 i'! Uq l .65 .ee- aC4 . .' ! !
$20oEia lI a.0
- PCCD /CCURACY ! ! 0. 3 t Un Vr.C ,ei- .
I:ATED ACCU?*CY I 1% l I.1/2",
l
! 15 F5 Pl.IEC'd 5E SPEC 12532013:001 fic'2r.513:6M' I :n sr. a ee:--a t
'/Ei;00R BARY.5 DALE l kiTATIC-0-P ::", ' _!!nA.gKjoALE l !a27-AljlS.s I FAT ';0 lOIT-H1355 h?!!3A.1 LC ATIO'i LOCAL !?5-57.6 l l LOCAL ,I l l I P',10 l 729E135 l729E13C I. l720E155 l -
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- YM DELAVAL TURBINE INC. e BARKSDALE CONTROLS Olvt5:CN
- 5125 Alcoa Aisnue L0s Angeles e Cant 90G5P. i, He.ued Saurdien Tube Models OPERATINGCHARACTERISTICS
- ORDERINGDATA nVater f gnt Howng (NEMA 4)
$c Ip'r"o'et r,$rnal Adiustment UNE EE ~ U
Miust:ble Range Appron. '
Proof 81T 82T Actue Catalog Cate nce N,_ (Test) Decreasing 'acteasing yg g, ,,
Number Number Ain. Mas. (Differentid) Matenal* ,
j.y .gg.g]q Pressure ( Min.l Man.
D2T Hl2 {
#C ,Ygf, ,h 1800 to 1180 70 1200 toto 20 Broere 316 BIT.H12 BIT Al253 82T.Al253 1800 50 1173 77 1200 11 to 27
[,*p f. _ ,, J ;,3' ,.. -
jf..% 4800 160 3170 190 3200 15 to 30 Dronze 81T H32 82T H32
+'1.l'M@lL 4 -N b Ir4
- d. 4000 7200 100 240 3161 199 3200 4715 325 4500 16 to 39 40 te 85 316 316 81T M12SS 81T.A4Rss 02T H3250 h 82T A47.S$ '
" 1750 325 6385 440 6500 54 to !!5 31 6 BIT A6553 R2T.A6535 I' die 31 6 81T.Al20$$ 02T Al20SS
.+
E " 18000 C00 11450 1150 12000 275 to 550
" 24000 603 17450 275 to S$0 316 DIT A18055l02T.AlaC55 4d.. 1150 l18000 _
**Stonte* represents Phosphor 8 tonne Tube with SAE 88 Brass Socket E2T OttAL CONTROL "216" represents 316 Stainless Steel fute & Socket 31T $1NCLC $EITING
"*APAINCO ' male opening for %* 00 tube connection. To change .A6553 and Al2355 switenes to %* not, add .P4 suths to model number. Perce adoitson required.
Approsimate shipping weight 2.5 Itrs.
DET.t!L DATA ELECTR: CAL CHAllACitRISTICS: A16 models incorporate Underwriters' Laboratories. Inc.
listed smie cole double throw snap actes switchms elements. Electncal rating (con.
Imurms inductive) 10 amps 125 or 250 volts AC. 3 amos 480 volts AC. Automatically reset by sao action of seitch. For more details and other switch classes. ies pages 33 35.
[LLCTRICAL CONNECTION: To scron termino 6s on covered terminal strip through %*nps conduit connector.
g Circuit JI: Common- Purple P1tE!31JRE CONNECTION: %* N.P.T. internal threed. escept as noted". models with Normally Closed- Blue Proot Pressures above 8.000 P.S.I. have "AMINCO* le:nale opening for %* 0.D. tube Normally Open- lied connection. Circuit #2:Commen- Bro =9 Normally Closed-Oronte A0JUSTMENT INSTRUCTICMS Norma 61y Open - Yellow Turn adjustment screw c!ocanise to lower a:tuation point (switch setting).
D2T BIT .
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As#USTinC 1CetWS
#612 ';Crtas (Muo.1 Covtt A0
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- B2T are the same as 817 (left).
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MOW TO SELECT A PRESSU.T SWITCH FOR YOUR APPLICA -
}
t Termmal block pressure switches are houeed and. en cel s
), SEftVICE LIFE OF THE SwtTCH tron. .*re equipped with enciosad terminal blocks, taic STEP 1 Espected sa rvice hfe is the first cons.deratecri to be made e'imir.ating His encense of buyine. and installing e.ste:tr.it [
in sciecting a pressure sw tttt regardless o: the pres.sure junction bones.
or sensitivity des 6 red. If the servsce lite tihe number of Emplosion proof pressure switches are cesigned with Iear.*
Cycles the switch is espected to o;:erate) is one shillio or housmgs buet to Conform to acceptad electncal standstis fess, use of either a bourdon tube or diaphrry,m smtch is in escialmg the smits from emplosive atmosphere. Att e s- '
andicated. If a service hfe of more than Gris enillion cycles plosion proof models are equipped with terminal hirwas j is desired. a piston switch should t,e used. Ari caception for convemence in wiring.
to this rule may tse made when pressure chrent:e ett a sys-tem es very sin;nt (20%. or less, of the adtustable range). SELECTION OF AOJUSTA81.E RANCC Under such conditic.9 a bourdon tube or deaphragm STEP S smtett can be used up to 2.5 emilion cycles before metal The term " working range" dsfines the pressure rance a -
smtch may see under nnernal wortung conditions. Iris :s I f a t Ct8". normaily the adlustable raege.
A second consideration in chooseng a pressure swittft is I the speed of cycimg regardless of the servece hfe. II 4 For greatest accurney the set point should faU its the upper I swstch as espected to cycle more than once every three 65% of the adjustabte range. For the most favorable life
- t+conos. a piston type switch should be specified. The factor the set point should be in the lower 65% of tne t metal of any bourdors tube ot diaphragm acts as a spring adiustable rante. Therefora, the most favomble combera- ;
which will heat and fatigue in entremety fast Cycling tion of 30 curacy and life faClor lies in the medole 30% o' operations. thus shortening the life of the switch. the adjustable range (see disgrem). This general rui.
applies both to diaphragm and bourdon tube pressure f The media to be controiled must always be considered r when selectsng a pressure switch and. to simplify selection
- smtches. i wettert materials for each type of swich are noted on ;
- t. see acct **c? & 8W1 uttet it'4 a . , , ,
apphcable catalog pages. 2 8cm tett Wttet IM c aw.as 20 l.
STEP 2 PetOOF PRESSURES Choice of the type of pressure switch to be used - dia- -
,,,,,,,,v ,
=s = e J
[#
pnragm, bourdon tube or pitton - also enust be goserned ,
l by the proof pressure to whict) it well be subsected. (Proof g* y ga '
- l pressure is ttie highest surge pressure that we6l ever be p esperienced in a system.) It must be rememtiered that, l.
although & pressure gauge may register a constant Oper*
e/ abng pressure, there may be surges going througri re sys- .M / g.,, ;l (
tem that see dampened out by the orifice en the Cauete. $ '
U , l Diappragm end bourdon tube pressure switches are en- " g treme6y sensitive and wouid be affected by those surges. 5 M j Darlisd.ile diaphragm .witclies are available in an adlust- ;x 4 .
~
able tante from vacuum to 150 psi mth proof pressures / C.
['
' y ,'*p(, l ' ,,l.
to 300 pse. flark sdale bourdon tube switeries are adiustable .
' ' a * -
to 18.000 pse with proof pressurns of 24 C03 osi. Barksdale piston switches have an adsustaible range tr,12.000 psi mth a proof pressure of 20.000 psi.
acc. -
unact Pood_r ei, veer cooo i escrucur '
ST!'P 3 FUNCTION OF THE SWITCH .
y The tunttion ot the switch is another sictermemng (Jft9r t' ,
m mahmg .e selection. Thiee types of Uasksaaie pressurs .
smtches. taaseet on function, ase itcscritmd below: HOW 10 READ CATALOG NilMBERS OF (1) Sinr:le setting pressure switches sense a sinr,te pres- DIAPHRACM surer source and open or cluse a sa.igle electrical cercu,1 by rneans of one snap action electrical switch. .
BOURDON TUDE AND (2) Pressure difference switches sense a change in rela.
tionship between two vanable contained pressures and OfA SEAT. P!STON open ct Ctose a single electncal circuit by m rans of one PRESSURE SWITCHES
! snap at. tion elei.trical switch.
(3) Dual control pressure switches sense two pressere l lamals fount a ringle pressure source arid (Ten ur close two gyp, tat cuatec wasets t.a. t u p a r . '
r,,, e , : e ., p. ey., .,.. s . s,,,e i
snetependent electrical ci.cuits by means of two soap action m e m se semw. .s.as seen..< J.De s cenere electrical smtches. t,w et owwe t.N,see. w.w.mmum.e neo 6
' r.m.enerwm % e4 en >=ae e+6
. . t .,,, w ,,a STEP 4 TYPES OF HOUSING AVAlt.ARLE ,
085818.I**'"" W' Strippret pressure smtches are basic BJrksdale pressure switch unik. mthout housant1. fl ey snay be u,cd wherevce
* **{*('Q
*%f r:r.si e nciosures ara stready .wailable and are f avorerl ,g ter creapn.nl equipment enamatacturt es for rasat m sommtm _ g,q gg c.ilemet s roetusally, strapped smtches may be puschased , ,
g, ,,,,,,,,,,,,,,,,,,,,
at a inws r cost,
- a.em r. n 8. essee a 4. s T *W e=wewas a e Xt o vs.,
Haused pressure switches Jre completely encfosad to wW' 'T * ' * .*e e.s.e e Ott ne c. .wt avoed possable hazard from Icuse wires in eaposed loca- ,
newsesse See e,ee ea d ease *v ti an s .
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