|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046B1481993-07-30030 July 1993 LER 93-012-00:on 930702,reactor Core Isolation Cooling Sys Declared Inoperable Due to Associated Bus Voltage Dropping Below TS Limits.Sent Operator to Cycle Timer Which Caused Affected Contact to reclose.W/930730 Ltr ML20045D9331993-07-0202 July 1993 LER 93-004-00:on 930604,unexpected CRD Low Charging Water Header Scram Received Followed by Charging Water Header A2/B2 Alarm.Caused by Crud or Foreign Matl Passing Through Suction Filter.Filters Cleaned & reused.W/930702 ML20045D7501993-06-23023 June 1993 LER 93-003-00:on 930524,Div 1 ECCS Initiation Signal Received & LPCS Pump,Lpci Pump 2A & EDG Unit 0 Automatically Started.Caused by Personnel Error.Pumps Secured & Event Documented in Personnel file.W/930623 Ltr ML20044E4161993-05-28028 May 1993 LER 92-009-01:on 920923,spurious Auto Start of CR Ventilation Emergency make-up Train Occurred Due to High Radiation Spike.Radiation Monitor Circuit modified.W/930528 Ltr ML20044E4191993-05-21021 May 1993 LER 93-011-00:on 930423,manual Scram Initiated.Caused by Disconnected Linkage on Valve Positioner on Heater Drain Valve Due to Loose Jam Nut.Tailgate Session Will Be Held W/ Instrument Maint Dept Re Jam nuts.W/930521 Ltr ML20044D5161993-05-15015 May 1993 LER 92-007-01:on 920613,high Radiation Spike Received from CR Ventilation Process Radiation Monitor,Initiating Emergency Makeup Train B.Caused by Normal Variations in Radiation Readings.Spike modified.W/930515 Ltr ML20044D5571993-05-14014 May 1993 LER 93-010-00:on 930414,DG Cooling Water Pump Automatically Tripped on Magnetic Overload.Caused by Inexperienced Trainee in Operation of Control Lever.Lesson Plans & Training Programs for Operators to Be reviewed.W/930514 Ltr ML20044C9801993-05-0707 May 1993 LER 91-010-01:on 910719 & 0805,CR a Ventilation Emergency Makeup Fan auto-started on Spurious Trip of CR Air Intake Process Radiation Monitor.Caused by Normal Variations in Background Radiation.Supply Board replaced.W/930507 Ltr ML20044B6161993-02-25025 February 1993 LER 93-002-00:on 930126,Unit 1 Manual Scram Due to a SRV Being Stuck Open Due to Duct Tape Being Over Actuators Air Valve Manifold Exhaust Port.Maint Procedures That Involve Cleanliness reviewed.W/930225 Ltr ML20024G9771991-05-10010 May 1991 LER 91-005-00:on 910410,determined That Tech Spec Required Surveillance of Suppression Chamber Oxygen Sampling Missed. Caused by Inadequate Review of Tech Spec Change.Drywell & Suppression Chamber Checked for oxygen.W/910510 Ltr ML20044A3851990-06-25025 June 1990 LER 90-008-00:on 900525,Tech Spec Hourly Fire Watch Missed Due to Miscommunications Between Security Personnel & Radiation Protection Personnel.Fire Watch re-established & Memo issued.W/900625 Ltr ML20043F1721990-06-0505 June 1990 LER 90-009-00:on 900510,RWCU Outboard Suction Isolation Valve 2G33-F004 Auto Closed Which Tripped RWCU Pump B. Caused by Procedure Deficiency.Procedure LTS-500-209 Will Be revised.W/900605 Ltr ML20043F1281990-06-0101 June 1990 LER 90-009-00:on 900511,apparent Ruptured Diaphragm Found on Pressure Differential Switch in RCIC Steam Line.Caused by Torn Diaphragm Inside Switch.Replacement Switch Installed, Calibr & Functionally Tested satisfactorily.W/900608 Ltr ML20043B5681990-05-23023 May 1990 LER 89-027-01:on 891113,primary Containment Isolation Sys Group 1 Isolation Occurred During Surveillance Testing. Caused by Burnt Out Window Light Bulbs on Alarm Window. Light Bulbs Replaced & Jumpers installed.W/900523 Ltr ML20043A7721990-05-18018 May 1990 LER 90-007-00:on 900421,reactor Protection Sys Bus a Transfer & Reactor Recirculation Hydraulic Power Unit a Inboard Isolation Valves Closed,Causing Partial Group II isolation.Out-of-svc Procedure revised.W/900518 Ltr ML20043D0591990-05-18018 May 1990 LER 90-008-00:on 900502,ESF Actuation of Control Room B Emergency Ctk Ventilation Makeup Fan Occurred.Caused by Procedure deficiency.LTS-800-205 & Similar Procedures Will Be revised.W/900601 Ltr ML20042H0211990-05-10010 May 1990 LER 90-006-00:on 900412,loop a Primary Containment Chilled Water Sys Inboard Isolation Valves & Reactor Bldg Closed Cooling Water Sys Inboard Isolation Valve Went Closed.Caused by Inadequate Procedure.Procedures revised.W/900510 Ltr ML20042F9001990-05-0404 May 1990 LER 90-005-00:on 900411,experienced Loss of Dc Power to Portion of Div I Primary Containment Isolation Sys Logic Which Resulted in Isolation Signal & Actuation.Caused by Failure to Update Drawings & procedures.W/900504 Ltr ML20042F1941990-04-30030 April 1990 LER 89-025-01:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Door Containing Undervoltage Relays Closed.Caused by Misalignment of Door.Door Repaired. W/900430 Ltr ML20012D5341990-03-16016 March 1990 LER 90-003-01:on 900201,RCIC Isolation Signal Occurred During Warmup.Caused by Spurious High Steam Flow Signal.Rcic Sys Piping Integrity Verified & Isolation Logic Reset.W/ 900316 Ltr ML20012D5371990-03-16016 March 1990 LER 90-002-01:on 900129,oil in Diesel Generator Governor 1A Found to Be Low & Could Not Be Seen in Sight Glass.Caused by Slow Leak from Compensation Needle Valve Plug.Proper Amount of Oil Added & Operability Test performed.W/900316 Ltr ML20012C4931990-03-15015 March 1990 LER 90-004-00:on 900213,control Room B HVAC Intake Radiation Monitor Lost Power Causing auto-start of Emergency make-up Train B.Caused by Blown Fuses.Fuses Replaced.Logic Revs for Radiation Monitors Will Be installed.W/900315 Ltr ML20012B6501990-03-0909 March 1990 LER 90-002-00:on 900209,Operating Surveillance LOS-TG-W1 Determined to Have Exceeded Required Testing Interval,Per Tech Spec 3/4.7.10.Caused by Personnel Error.Personnel Counseled & Ref Procedures Will Be revised.W/900309 Ltr ML20012B5521990-03-0808 March 1990 LER 90-001-00:on 900206,full Reactor Scram Occurred During Instrument Surveillance Testing.Caused by Actuation of APRM E Trip Circuitry.Shutdown Margin Revised & Caution Card Placed on Control Room Bench board.W/900308 Ltr ML20011F8251990-03-0202 March 1990 LER 90-003-00:on 900201,RCIC Received Div 2 Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal Generated When Steam/Water Mixture Admitted to RCIC Steam Line.Isolation Logic reset.W/900302 Ltr ML20011F5551990-02-28028 February 1990 LER 90-002-00:on 900129,after Filling Diesel Generator 1A Governor W/Oil,Generator Started & Declared Inoperable. Caused by Slow Leak Coming from Compensation Needle Valve Plug.Oil Added & Plug Washer replaced.W/900228 Ltr ML20006F5951990-02-21021 February 1990 LER 90-001-00:on 900122,RWCU Sys Received Div 1 Leakage Detection Ambient Temp High Isolation Signal,Causing Trips of RWCU Pumps a & C.Caused by Broken Thermocouple Input Lead.Lead Wire Reconnected & Isolation reset.W/900221 Ltr ML20011F4921990-02-16016 February 1990 LER 89-013-01:on 890907,Group I Isolation Received During Performance of Instrument Surveillance LIS-MS-401.Caused by Depressurization of Main Steam Line Low Pressure Switch. Surveillance Revised to Split Into Two parts.W/900216 Ltr ML20006E4501990-02-15015 February 1990 LER 89-010-01:on 890715 & 17,voltage Oscillations Noted on Div II Battery Charger,Resulting in Inoperability of HPCS Sys.Caused by Failure of Charger in High Voltage Shutdown Relay.Charger Energized & Relay replaced.W/900215 Ltr ML20006E4451990-02-14014 February 1990 LER 89-009-01:on 890619,diaphragm Leak Discovered in RCIC Steam Line High Flow Isolation Switch.Caused by 1 & 1/2-inch Tear in Diaphragm.Pressure Differential Switch Replaced & Calibr.Reported Per NRC Bulletin 86-002.W/900214 Ltr ML20006E3981990-02-14014 February 1990 LER 89-008-01:on 890228,reactor Vessel Low Water Level 2 Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.Channel Placed in Tripped Condition & All Static-O-Ring Pressure Switches to Be replaced.W/900214 Ltr ML20006E3951990-02-14014 February 1990 LER 89-010-01:on 890303,automatic Depressurization Sys Permissive Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.All Static-O-Ring Reactor Vessel Level Switches Will Be replaced.W/900214 Ltr ML19354D8361990-01-15015 January 1990 LER 89-018-00:on 891216,plant 250-volt Battery & RCIC Sys Declared Inoperable Due to Low Battery Electrolyte Temps. Caused by Failure of Div I Switchgear Heat Removal Sys Damper Actuators.Air Intake Dampers closed.W/900115 Ltr ML20042D3921990-01-0404 January 1990 LER 89-011-01:on 890826,spurious Reactor Protection Sys Actuation Occurred.Definite Cause of Trip Not Determined. Brief Disturbance in Reactor Protection Sys Allowed Some Contactors to Trip.Procedure revised.W/900104 Ltr ML20005E2741989-12-22022 December 1989 LER 89-028-00:on 891204,RHR Shutdown Cooling Suction Header Outboard Isolation Valve Automatically Isolated.Caused by Miscommunication Between Technician & Station Operator.Task Force Developed to Review event.W/891222 Ltr ML19351A6301989-12-15015 December 1989 LER 89-006-01:on 890214,reactor Vessel Low Water Level 3 Switch Setpoint Found Out of Tolerance.Caused by Setpoint Drift.Level Switch to Be Replaced by Analog Trip Sys During First Quarter 1990.W/891215 Ltr ML20011D1341989-12-14014 December 1989 LER 89-017-00:on 891117,flow Switch FS-2E22-N006 Found W/ Setpoint Out of Tolerance Above Reject Limit.Caused by Setpoint Drift.Work Request Written to Replace Flow Switch. W/891214 Ltr ML19351A6751989-12-12012 December 1989 LER 89-027-00:on 891113,primary Containment Isolation Sys Group I Isolation Occurred While Performing Instrument Surveillance.Caused by Loss of Power to Leak Detection Sys Logic.Isolation reset.W/891213 Ltr ML19332F0081989-12-0808 December 1989 LER 89-016-00:on 891109,RWCU Isolation Occurred While Instrument Surveillance on Ventilation Differential Temp Isolation Functional Test in Progress.Caused by Faulty Thermocouple.Thermocouple repaired.W/891208 Ltr ML20005D6621989-12-0606 December 1989 LER 89-026-00:on 891106,inadvertent Primary Containment Isolation Actuation Occurred While Clearing out-of-svc. Caused by Inadequate Logic Setup During Mod Installation. Trip Status & Output Switches repositioned.W/891206 Ltr ML19332F2431989-12-0101 December 1989 LER 89-025-00:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Equipment Operator Closed Door Containing Relays.Caused by Misalignment of Door.Isolations Reset,Bus Energized & Circuit Logic tested.W/891201 Ltr ML19332E6581989-11-29029 November 1989 LER 89-015-00:on 891030,shift Control Room Engineer Noted That Quarterly Standby Liquid Control Operating Surveillance LOS-SC-Q1 Was Past Critical Date.Caused by Clerical Data Entry Error.Missed Surveillance performed.W/891129 Ltr ML19332D5181989-11-22022 November 1989 LER 89-018-01:on 890515,RCIC Received Div I & Div II Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal When Steam Added to RCIC Steam Line. Special Test Initiated.Isolation Logic reset.W/891122 Ltr ML19327C2601989-11-17017 November 1989 LER 89-014-00:on 891020,primary Containment Isolation Sys Group 4 Isolation Occurred Causing Isolation Dampers to Close.Caused by Opening of Div 2 125-volt Dc Breaker.Power Supply replaced.W/891117 Ltr ML19325F3411989-11-13013 November 1989 LER 89-024-00:on 891013 & 30,unsealed Openings in Main Control Room Floor & Main Control Room West Wall Discovered. Caused by Wide Gap Between Structural Beam & Cable Tray. Openings Sealed & Fire Watch established.W/891113 Ltr ML19324C1751989-11-0808 November 1989 LER 89-012-01:on 890309,diaphragm Leak Found in Pressure Differential Switch 1E31-N013BB.Caused by Tear Found in Diaphragm.Replacement Switch Installed,Calibr & Functionally Tested satisfactorily.W/891108 Ltr ML20024E9121983-08-26026 August 1983 LER 83-093/03L-0:on 830801,discovered full-in Indication on Core Display for Control Rod 34-47 Inoperable.Caused by Failed Switching Transistor on Data Memory Board 19.Data Memory Board replaced.W/830826 Ltr ML20024B8381983-07-0505 July 1983 LER 83-060/03L-0:on 830606,following Turbine Trip & Scram Due to High Vibration on Main Turbine,Reactor Recirculation Breaker 4B Closed.Cause Undetermined.Auxiliary Contacts cleaned.W/830705 Ltr ML20024B0721983-06-16016 June 1983 Updated LER 83-012/03X-1:on 830210,w/reactor in Cold Shutdown,Setpoints for Switches 1E31-N612A/B Found Above Tech Spec Limits.Cause Unknown.Switches calibr.W/830616 Ltr ML20024A6961983-06-14014 June 1983 LER 83-051/03L-0:on 830516,reactor Protection Sys Trip Channel H2 Limit Switch Failed to Operate Properly.Cause Unknown.Limit Switch readjusted.W/830614 Ltr 1993-07-30
[Table view] Category:RO)
MONTHYEARML20046B1481993-07-30030 July 1993 LER 93-012-00:on 930702,reactor Core Isolation Cooling Sys Declared Inoperable Due to Associated Bus Voltage Dropping Below TS Limits.Sent Operator to Cycle Timer Which Caused Affected Contact to reclose.W/930730 Ltr ML20045D9331993-07-0202 July 1993 LER 93-004-00:on 930604,unexpected CRD Low Charging Water Header Scram Received Followed by Charging Water Header A2/B2 Alarm.Caused by Crud or Foreign Matl Passing Through Suction Filter.Filters Cleaned & reused.W/930702 ML20045D7501993-06-23023 June 1993 LER 93-003-00:on 930524,Div 1 ECCS Initiation Signal Received & LPCS Pump,Lpci Pump 2A & EDG Unit 0 Automatically Started.Caused by Personnel Error.Pumps Secured & Event Documented in Personnel file.W/930623 Ltr ML20044E4161993-05-28028 May 1993 LER 92-009-01:on 920923,spurious Auto Start of CR Ventilation Emergency make-up Train Occurred Due to High Radiation Spike.Radiation Monitor Circuit modified.W/930528 Ltr ML20044E4191993-05-21021 May 1993 LER 93-011-00:on 930423,manual Scram Initiated.Caused by Disconnected Linkage on Valve Positioner on Heater Drain Valve Due to Loose Jam Nut.Tailgate Session Will Be Held W/ Instrument Maint Dept Re Jam nuts.W/930521 Ltr ML20044D5161993-05-15015 May 1993 LER 92-007-01:on 920613,high Radiation Spike Received from CR Ventilation Process Radiation Monitor,Initiating Emergency Makeup Train B.Caused by Normal Variations in Radiation Readings.Spike modified.W/930515 Ltr ML20044D5571993-05-14014 May 1993 LER 93-010-00:on 930414,DG Cooling Water Pump Automatically Tripped on Magnetic Overload.Caused by Inexperienced Trainee in Operation of Control Lever.Lesson Plans & Training Programs for Operators to Be reviewed.W/930514 Ltr ML20044C9801993-05-0707 May 1993 LER 91-010-01:on 910719 & 0805,CR a Ventilation Emergency Makeup Fan auto-started on Spurious Trip of CR Air Intake Process Radiation Monitor.Caused by Normal Variations in Background Radiation.Supply Board replaced.W/930507 Ltr ML20044B6161993-02-25025 February 1993 LER 93-002-00:on 930126,Unit 1 Manual Scram Due to a SRV Being Stuck Open Due to Duct Tape Being Over Actuators Air Valve Manifold Exhaust Port.Maint Procedures That Involve Cleanliness reviewed.W/930225 Ltr ML20024G9771991-05-10010 May 1991 LER 91-005-00:on 910410,determined That Tech Spec Required Surveillance of Suppression Chamber Oxygen Sampling Missed. Caused by Inadequate Review of Tech Spec Change.Drywell & Suppression Chamber Checked for oxygen.W/910510 Ltr ML20044A3851990-06-25025 June 1990 LER 90-008-00:on 900525,Tech Spec Hourly Fire Watch Missed Due to Miscommunications Between Security Personnel & Radiation Protection Personnel.Fire Watch re-established & Memo issued.W/900625 Ltr ML20043F1721990-06-0505 June 1990 LER 90-009-00:on 900510,RWCU Outboard Suction Isolation Valve 2G33-F004 Auto Closed Which Tripped RWCU Pump B. Caused by Procedure Deficiency.Procedure LTS-500-209 Will Be revised.W/900605 Ltr ML20043F1281990-06-0101 June 1990 LER 90-009-00:on 900511,apparent Ruptured Diaphragm Found on Pressure Differential Switch in RCIC Steam Line.Caused by Torn Diaphragm Inside Switch.Replacement Switch Installed, Calibr & Functionally Tested satisfactorily.W/900608 Ltr ML20043B5681990-05-23023 May 1990 LER 89-027-01:on 891113,primary Containment Isolation Sys Group 1 Isolation Occurred During Surveillance Testing. Caused by Burnt Out Window Light Bulbs on Alarm Window. Light Bulbs Replaced & Jumpers installed.W/900523 Ltr ML20043A7721990-05-18018 May 1990 LER 90-007-00:on 900421,reactor Protection Sys Bus a Transfer & Reactor Recirculation Hydraulic Power Unit a Inboard Isolation Valves Closed,Causing Partial Group II isolation.Out-of-svc Procedure revised.W/900518 Ltr ML20043D0591990-05-18018 May 1990 LER 90-008-00:on 900502,ESF Actuation of Control Room B Emergency Ctk Ventilation Makeup Fan Occurred.Caused by Procedure deficiency.LTS-800-205 & Similar Procedures Will Be revised.W/900601 Ltr ML20042H0211990-05-10010 May 1990 LER 90-006-00:on 900412,loop a Primary Containment Chilled Water Sys Inboard Isolation Valves & Reactor Bldg Closed Cooling Water Sys Inboard Isolation Valve Went Closed.Caused by Inadequate Procedure.Procedures revised.W/900510 Ltr ML20042F9001990-05-0404 May 1990 LER 90-005-00:on 900411,experienced Loss of Dc Power to Portion of Div I Primary Containment Isolation Sys Logic Which Resulted in Isolation Signal & Actuation.Caused by Failure to Update Drawings & procedures.W/900504 Ltr ML20042F1941990-04-30030 April 1990 LER 89-025-01:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Door Containing Undervoltage Relays Closed.Caused by Misalignment of Door.Door Repaired. W/900430 Ltr ML20012D5341990-03-16016 March 1990 LER 90-003-01:on 900201,RCIC Isolation Signal Occurred During Warmup.Caused by Spurious High Steam Flow Signal.Rcic Sys Piping Integrity Verified & Isolation Logic Reset.W/ 900316 Ltr ML20012D5371990-03-16016 March 1990 LER 90-002-01:on 900129,oil in Diesel Generator Governor 1A Found to Be Low & Could Not Be Seen in Sight Glass.Caused by Slow Leak from Compensation Needle Valve Plug.Proper Amount of Oil Added & Operability Test performed.W/900316 Ltr ML20012C4931990-03-15015 March 1990 LER 90-004-00:on 900213,control Room B HVAC Intake Radiation Monitor Lost Power Causing auto-start of Emergency make-up Train B.Caused by Blown Fuses.Fuses Replaced.Logic Revs for Radiation Monitors Will Be installed.W/900315 Ltr ML20012B6501990-03-0909 March 1990 LER 90-002-00:on 900209,Operating Surveillance LOS-TG-W1 Determined to Have Exceeded Required Testing Interval,Per Tech Spec 3/4.7.10.Caused by Personnel Error.Personnel Counseled & Ref Procedures Will Be revised.W/900309 Ltr ML20012B5521990-03-0808 March 1990 LER 90-001-00:on 900206,full Reactor Scram Occurred During Instrument Surveillance Testing.Caused by Actuation of APRM E Trip Circuitry.Shutdown Margin Revised & Caution Card Placed on Control Room Bench board.W/900308 Ltr ML20011F8251990-03-0202 March 1990 LER 90-003-00:on 900201,RCIC Received Div 2 Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal Generated When Steam/Water Mixture Admitted to RCIC Steam Line.Isolation Logic reset.W/900302 Ltr ML20011F5551990-02-28028 February 1990 LER 90-002-00:on 900129,after Filling Diesel Generator 1A Governor W/Oil,Generator Started & Declared Inoperable. Caused by Slow Leak Coming from Compensation Needle Valve Plug.Oil Added & Plug Washer replaced.W/900228 Ltr ML20006F5951990-02-21021 February 1990 LER 90-001-00:on 900122,RWCU Sys Received Div 1 Leakage Detection Ambient Temp High Isolation Signal,Causing Trips of RWCU Pumps a & C.Caused by Broken Thermocouple Input Lead.Lead Wire Reconnected & Isolation reset.W/900221 Ltr ML20011F4921990-02-16016 February 1990 LER 89-013-01:on 890907,Group I Isolation Received During Performance of Instrument Surveillance LIS-MS-401.Caused by Depressurization of Main Steam Line Low Pressure Switch. Surveillance Revised to Split Into Two parts.W/900216 Ltr ML20006E4501990-02-15015 February 1990 LER 89-010-01:on 890715 & 17,voltage Oscillations Noted on Div II Battery Charger,Resulting in Inoperability of HPCS Sys.Caused by Failure of Charger in High Voltage Shutdown Relay.Charger Energized & Relay replaced.W/900215 Ltr ML20006E4451990-02-14014 February 1990 LER 89-009-01:on 890619,diaphragm Leak Discovered in RCIC Steam Line High Flow Isolation Switch.Caused by 1 & 1/2-inch Tear in Diaphragm.Pressure Differential Switch Replaced & Calibr.Reported Per NRC Bulletin 86-002.W/900214 Ltr ML20006E3981990-02-14014 February 1990 LER 89-008-01:on 890228,reactor Vessel Low Water Level 2 Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.Channel Placed in Tripped Condition & All Static-O-Ring Pressure Switches to Be replaced.W/900214 Ltr ML20006E3951990-02-14014 February 1990 LER 89-010-01:on 890303,automatic Depressurization Sys Permissive Switch Found W/Setpoint in Excess of Reject Limit.Caused by Setpoint Drift.All Static-O-Ring Reactor Vessel Level Switches Will Be replaced.W/900214 Ltr ML19354D8361990-01-15015 January 1990 LER 89-018-00:on 891216,plant 250-volt Battery & RCIC Sys Declared Inoperable Due to Low Battery Electrolyte Temps. Caused by Failure of Div I Switchgear Heat Removal Sys Damper Actuators.Air Intake Dampers closed.W/900115 Ltr ML20042D3921990-01-0404 January 1990 LER 89-011-01:on 890826,spurious Reactor Protection Sys Actuation Occurred.Definite Cause of Trip Not Determined. Brief Disturbance in Reactor Protection Sys Allowed Some Contactors to Trip.Procedure revised.W/900104 Ltr ML20005E2741989-12-22022 December 1989 LER 89-028-00:on 891204,RHR Shutdown Cooling Suction Header Outboard Isolation Valve Automatically Isolated.Caused by Miscommunication Between Technician & Station Operator.Task Force Developed to Review event.W/891222 Ltr ML19351A6301989-12-15015 December 1989 LER 89-006-01:on 890214,reactor Vessel Low Water Level 3 Switch Setpoint Found Out of Tolerance.Caused by Setpoint Drift.Level Switch to Be Replaced by Analog Trip Sys During First Quarter 1990.W/891215 Ltr ML20011D1341989-12-14014 December 1989 LER 89-017-00:on 891117,flow Switch FS-2E22-N006 Found W/ Setpoint Out of Tolerance Above Reject Limit.Caused by Setpoint Drift.Work Request Written to Replace Flow Switch. W/891214 Ltr ML19351A6751989-12-12012 December 1989 LER 89-027-00:on 891113,primary Containment Isolation Sys Group I Isolation Occurred While Performing Instrument Surveillance.Caused by Loss of Power to Leak Detection Sys Logic.Isolation reset.W/891213 Ltr ML19332F0081989-12-0808 December 1989 LER 89-016-00:on 891109,RWCU Isolation Occurred While Instrument Surveillance on Ventilation Differential Temp Isolation Functional Test in Progress.Caused by Faulty Thermocouple.Thermocouple repaired.W/891208 Ltr ML20005D6621989-12-0606 December 1989 LER 89-026-00:on 891106,inadvertent Primary Containment Isolation Actuation Occurred While Clearing out-of-svc. Caused by Inadequate Logic Setup During Mod Installation. Trip Status & Output Switches repositioned.W/891206 Ltr ML19332F2431989-12-0101 December 1989 LER 89-025-00:on 891101,sys Auxiliary Transformer Feed to Bus 142Y Tripped Open When Equipment Operator Closed Door Containing Relays.Caused by Misalignment of Door.Isolations Reset,Bus Energized & Circuit Logic tested.W/891201 Ltr ML19332E6581989-11-29029 November 1989 LER 89-015-00:on 891030,shift Control Room Engineer Noted That Quarterly Standby Liquid Control Operating Surveillance LOS-SC-Q1 Was Past Critical Date.Caused by Clerical Data Entry Error.Missed Surveillance performed.W/891129 Ltr ML19332D5181989-11-22022 November 1989 LER 89-018-01:on 890515,RCIC Received Div I & Div II Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal When Steam Added to RCIC Steam Line. Special Test Initiated.Isolation Logic reset.W/891122 Ltr ML19327C2601989-11-17017 November 1989 LER 89-014-00:on 891020,primary Containment Isolation Sys Group 4 Isolation Occurred Causing Isolation Dampers to Close.Caused by Opening of Div 2 125-volt Dc Breaker.Power Supply replaced.W/891117 Ltr ML19325F3411989-11-13013 November 1989 LER 89-024-00:on 891013 & 30,unsealed Openings in Main Control Room Floor & Main Control Room West Wall Discovered. Caused by Wide Gap Between Structural Beam & Cable Tray. Openings Sealed & Fire Watch established.W/891113 Ltr ML19324C1751989-11-0808 November 1989 LER 89-012-01:on 890309,diaphragm Leak Found in Pressure Differential Switch 1E31-N013BB.Caused by Tear Found in Diaphragm.Replacement Switch Installed,Calibr & Functionally Tested satisfactorily.W/891108 Ltr ML20024E9121983-08-26026 August 1983 LER 83-093/03L-0:on 830801,discovered full-in Indication on Core Display for Control Rod 34-47 Inoperable.Caused by Failed Switching Transistor on Data Memory Board 19.Data Memory Board replaced.W/830826 Ltr ML20024B8381983-07-0505 July 1983 LER 83-060/03L-0:on 830606,following Turbine Trip & Scram Due to High Vibration on Main Turbine,Reactor Recirculation Breaker 4B Closed.Cause Undetermined.Auxiliary Contacts cleaned.W/830705 Ltr ML20024B0721983-06-16016 June 1983 Updated LER 83-012/03X-1:on 830210,w/reactor in Cold Shutdown,Setpoints for Switches 1E31-N612A/B Found Above Tech Spec Limits.Cause Unknown.Switches calibr.W/830616 Ltr ML20024A6961983-06-14014 June 1983 LER 83-051/03L-0:on 830516,reactor Protection Sys Trip Channel H2 Limit Switch Failed to Operate Properly.Cause Unknown.Limit Switch readjusted.W/830614 Ltr 1993-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML20199E4601998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for LaSalle County Station,Units 1 & 2.With ML20207C7371998-12-31031 December 1998 Annual Rept for LaSalle County Station for Jan 1998 Through Dec 1998 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20206N2261998-12-0909 December 1998 LER 98-S03-00:on 981116,protected Area Was Entered Without Current Authorization for Unescorted Access Due to Programmatic Deficiency Error.Changed Badge Control Process ML20197K0981998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for LaSalle County Station,Unts 1 & 2.With ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings of Safety-Related Power-Operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3191998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for LaSalle County Station.With ML20154H6781998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151W0241998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for LaSalle County Station.With ML20237E2921998-08-21021 August 1998 Special Rept:On 980811,channel 5 of Lpms Became Inoperable. Caused by Channel Failed pre-amplifier Located Inside Primary Containment at Inboard Side of Electrical Penetration E-19.Initiated Repairs of Channel ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B4861998-07-31031 July 1998 Monthly Operating Repts for July 1998 for LaSalle County Nuclear Power Station Units 1 & 2 ML20236V7701998-07-31031 July 1998 Revised LaSalle Unit 1 Cycle 8 COLR & Reload Transient Analysis Results ML20236P8231998-07-14014 July 1998 Special Rept:From 980614-17,various Fire Rated Assemblies Were Inoperable for Period Greater than Seven Days.Caused by Test Equipment Being Routed Through Fire Doors.Established Fire Watches & on 980619 Assemblies Were Declared Operable ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20236P3611998-06-30030 June 1998 Monthly Operating Repts for June 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20249C4891998-06-22022 June 1998 Special Rept:On 980522,Fire Detection Zone 1-31 Was Noted out-of-service for More than 14 Days.Detection Sys Was Taken out-of-service on 980508 to Prevent False Alarms During Hot Work Activities.Sys Was Returned to Operable Status 980528 ML20248M3101998-05-31031 May 1998 Monthly Operating Repts for May 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20236V7771998-05-31031 May 1998 Rev 1 to 24A5180, Supplemental Reload Licensing Rept for LaSalle County Station Unit 1 Reload 7 Cycle 8 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20247M4491998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for LaSalle County Station ML20216F4941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for LaSalle County Station,Units 1 & 2 ML20217N6581998-03-30030 March 1998 Special Rept on Fire Detection,Deluge Sys & Fire Rated Assemblies During Period of 980303-25.Established Fire Watches Until Affected Equipment Is Returned to Operable Status ML20216D9511998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for LaSalle County Station,Units 1 & 2 ML20247M4631998-02-28028 February 1998 Rev Monthly Operating Rept for Feb 1998 for LaSalle County Station ML20203D7241998-02-20020 February 1998 Special Rept:On 980118,Fire Detection Zones 1-18 & 2-18 Taken out-of-svc to Prevent False Alarms During Hot Work Activities on Auxiliary Electric Equipment Room Ventilation Sys.Fire Watches Will Remain in Place ML20202G9851998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for LaSalle County Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr 1999-09-30
[Table view] |
Text
l CONTROL BLOCK: l l I l l I lh (PLEASE PRINT 02 TYPE At.L RECUIRED INF[RMATION)'
AlIILiLl Sic l1IgloloI-IofofololoI-IoloI@l411l0lolo!gl 4 9 LICENSEE CCCE 14 15 LICENSE NLM8ER 2% 26 WCENSE TYPE Jo 1
$7 CAT 54
]g b 4 g
"*O ILl@loi5io1oio!3 17 I3 @l1I2i2to18 12 @l0111118 I 8 i3 l@
60 61 QQCKET NwMEER 64 es EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PRCSABLE CONSECUENCES h yl LSCS was inthe startup mode at 33MWT. A reference leg problem resulted in a loss of g
- 3) ;
Division II Reactor Vessel instrumentation. Division I vessel instrumentation was g providing sufficient indication. Division III was operable and available throughout g this event. When the problem was recognized, appropriate and timely corrective action _y y
was taken. Safe operation of the unit was maintained at all times. ,s ,
. :I I I I
.s11 So 9
- cc S*E #$$o*E s CEE CoupoNENT CODE Suecodt s sc"ot c
i91 l Il A l@ y@ l6 l@ l Zl Zl Zl Zl Zl Z l@
10 12 13 18 4 Q@ y @ 20 8 9 11 OCCURRENCE peroRT REVI58088 SEQUENTIAL CoOE TYPE No,
(
EV ENT YE AR R EPORT NO.
h , reg LER/RO y
._ l21 81 2 l b 22 23 I1l7 l2 l 24 26 d
27 l o 13 l 25 29 W b 30 31 W
33 N C oP T M Hour $ 22 SUS Fo M. 7PL MAN F ER ggl24H [g las lg 23 Z
l,eZl@
l o l o l 0 lU l 27 4e
]g 4i gg l Z lg 42 42 lZ l 9 [ 9 l 9 [g
- 4. c CAUSE DESCRIPTION AND CORRECTIVE ACTIONS
,3 l l The cause of the occurrence was found to be a lesky fitting on line INB56A ". l
- ,,[
An instrument maintenance technician tightened the fitting and backfilled the ]
reference leg. A manual h scram on channel El was taken on 12/20/82 at 0100. ,
,,g Division II level indication 'as wdeclared operable at 0200. g l
i4 1l 30 8 9
%PCWER OTHER STATUS 01 RY DISCDVERY DESCR8PTTCM
$A 3 NA OBSERVATION l i 5* 'l {@ l0 l 0l 1l@l l lA[@l** " '
ACTIVITY c5 TENT F'4 ELE 4sE AuoUNT OF ACTIVITY LOCATION oF RELEASE RELEASE i6llZ l lZl@l 11 NA 44 l l 46 NA 80 l
8 9 to PER5CNNEL EXPOSURES NUMSER TYPE DESCRIPTION NA ]
i I 1 ol o l o l@l Z l@l "
,E RsoNN E L iN;u'A Es NUMsER oESCRimoN@ l.
iailololol@]
NA So 5 9 11 12 i
LCSS of OR CAM ACE 70 8ACILITY i NA
,l l i 9 l lZ s 9 TYP l E @]OE50 AIPTION to 8301280159 830118 to DR ADOCK 05000373 NRC USE ONLY ,
i S PDR ggy9ggggggg;l
] ssuto@SE 5 g lN l j to
- a'PT'cNb NA g 68 69
^
- 80. g PHCNE:
351-6761 k N A'fE : PagoaRgR - - .. -. .. . f
.I. LER Numb 2r: 82-172/03L-0 II. LaSalle County Station: Unit 1 -
III. Docket Number: 050-373 IV. Event
Description:
Sequence of Events This information was collected from the Hathaway recorder and chart recorders IC34-R608 (Upset Range Level & Narrow Range Level Div I),
1B21-R884A (Wide Range Pressure and-Wide Range Level Div. I) and 1B21-R884B (Wide Range Pressure and Wide Range Level Div. II)'
Also, the operator's log.
Dec. 19, 1982 1100 Operators started to lower water level for U1 S/U 1215 Water level reached 34" 1230 Mode switch was put in S/U 1350 Water level exceeded 40", causing a high level alarm. Water level-remained high because of NPSH considerations on the RWCU pumps.
1420-1450 Water level reached 47" and was blown down to 44" using the RWCU System. At this time Rx pressure indicated zero. U1 went critical. Div. II narrow range (B) was noted by the operator to be on scale and shift change occurred.
1450-1610 Water level increased to 58". Rx. pressure still at zero. Rx water level was raised due to NPSH problems on the RWCU pumps (previously noted). Rx was in Heatup phase.
1610-1810 Reactor water level remained between 57"-60" and Rx pressure increased from 0-80#'s during this time frame. Throughout this period, Div. I and Div. II wide range level recorders indicated levels greater than 60".
1810-1900 At 1818 hours0.021 days <br />0.505 hours <br />0.00301 weeks <br />6.91749e-4 months <br /> the Div. II channel B (Rx Vessel Hi Wtr Level Trip)
Reset as shown on the Hathaway printout. This time appears to correspond with a decrease in Rx level below 40" on recorder 1C34-R608 (Narrow Range Level Div. I). Rx pressure was at 130#'s. Level was decreased from 57" to 34" with RWCU blow down.
Towards the end of this time period Rx Level began to increase due to Heatup and continuous CRD inputs.
1900-2030 Rx Level rose from about 38" to 47" due to Heatup & CRD inputs. At 2009 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.644245e-4 months <br /> the Div. II channel B (Rx Vessel Hi Water Level Trip) Reset per the Hathaway Recorder. Around this time frame, a decrease in Rx Vessel Level below 40" was experienced. Rx pressure increased from 130-300 psi. Both wide range recorders were still indicating high level.
2030-2200 Rx Level stabilized at about 36" and Rx pressure increased from 300-600 psi. According to the Hathaway printout, at 2112 the Div. II channel B (Rx Vessel Hi Water Level Trip) tripped. The Chart Recorder IC34-R608 reading shows that a Rx Vessel Level of greater than 40" n.m - - - , - n n m a ~,
occurred at approximately this time. "At 2200 wide range level A came on scale and read 42". B wide range recorder (1B21-R884B) still read high.
2200-00:00 Rx level remained at 36" and Rx pressure increased from approxi-mately 600-800 psi. ('A') Div I wide range indicated Rx level stabilized at 38". ('B') Div II wide range recorder remained high. The afternoon shift suspected that there may have been a vessel instrumentation problem and instructed an Instrument Mainte-nance technician to go to the local instrument racks and check out a few instruments to look for leaks etc. (This happened between 2215-2300 hours). The night shift was informed that there may be a vessel level instrumentation problem. Shift change occurred. The s IM was contacted between 2300-0000 and told to pursue the matter further and that the problem may deal with a Rx vessel instrumenta -
~
tion reference leg. At 2307 an alarm summary was printed out on the Hathaway which showed a Div II Channel B1 (Rx vessel High Water Level Trip) tripped. The alarm did not clear after Rx Vessel Level '
went below 40" at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> as indicated on 1C34-R608. At 00:00 it was determined that Div II level instrumentation was inoperative.
0000-0200 Rx level remained normal as shown by Div I level. Rx pressure was at 850 psi throughout this time frame. The NRC was notified about the occurrence. At 0100 a manual 1/2 scram was taken on channel Bl.
At 0105 commenced procedure to go to Hot Shutdown. During this time period, the IM refilled the Div II level instrumentation reference leg satisfactorily once the leaky fitting on an instrument line to LTIS 1B21-N044B was tightened. From the Hathaway printout Div II level instrumentation was restored at 0109 and the B wide range recorder came on scale and read 38". The 'B' High Rx level channel reset at 0140 (from Hathaway). The channel B11/2 scram was reset.
At 0200 startup was resumed and Div II level instrumentation was declared operable.
See attached charf recording and/or operators log for further description.
V. PROBABLE CONSEQUENCES OF THE OCCURRENCE:
At the time of the occurrence, LSCS was in the startup mode at 33MWT. The reference leg problem resulted in a loss of Division II instrumentation for the B and C RHR pumps, lA Diesel Generator, "B" logic of ADS and PCIS Groups 1-7.
Division I vessel instrumentation was providing sufficiant indication of reactor temperature, water level and pressure to maintain the plant at proper operating conditions. Division III was operable and available throughout this event. A scram would have been able to occur during this happening because 3 of 4 RPS channels were operable. When the problem was recognized, appropriate and timely corrective action was taken. Safe operation of the unit was r.aintained at all times.
,. ---m
VI. CAUSE:
The cause of the occurrence was found to be a leaky fitting on line INB56A " at'LTIS 1B21-N044B which is located on panel 1H22-P009. This fitting was used as a tap for a hydro after recent construction work while the plant was shutdown. No provisions were made to verify that th'e ,
fitting held pressure during the ensuing startup. and plant pressurization, and as reactor pressure increased above 300 psi the reference leg then began to leak past the fitting.
Problems brought to light in this event include: 1) The need for some additi.aal guidance for the plant operatore when instrumentation failures involving multiple reactor vessel parameters are involved. Existing procedures do not appear to be adequate. 2) This event indicated the need to verify that the fitting which was broken for the hydro rig was reconnected properly. This couldn't be done until the subsequent plant heat up.
VII. CORRECTIVE ACTION: ,
An Instrument Maintenance technician assisted by various operating personnel began investigating a possible instrument problem shortly after 2200, 12/19/82.
At approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> he was instructed to search for a possible reference leg problem. Subsequently, the leaky fitting on line 1NB56A "
was detected by the Instrument Maintenance technician at 0000, 12/20/82 and a manual 1/2 scram was taken in order to comply with Technical Specification 3.3.1 at 0100, 12/20/82. The fitting was tightened and the reference leg was backfilled. Division II level indication was declared operable at 0200.
An Action Item Request #01-83-19 has been written requesting that an evaluation be conducted to determine if a procedure should be developed to aid the operator in determining if there has been a common mode failure to Reactor Vessel level instrumentation.
An Action Item Request #01-83-20 has been written to require the General Startup Procedure to include a sign off to verify the Wide Range Level ,
detectors begin to come on scale at the appropriate pressure.
A letter has been issued by the Station Superintendent directing the required parties to ensure work requests that break mechanical fittings on instruments are verified by inspection to be properly sealed.
Prepared by: G. V. Ford O
e
IBbINhhh [!!i N ,. Il l, :
f l !
).[.Q
'$ ;O NM00l! ! l, f600$ ! l i; 00 k!,.th,00l. t 1500 6, ' TC 'I N e #I !lI I NSIG1 N '
H i? E ' ^^I - i
} r- '
'LQ i I f,.
s#
.ty2.;
. ),J., e #. . R - . '
.NN:
af . I l e .
EEd - EI'!J'I ~ ~i I i-
-,q' e i !I' om ' - '
43.l r b g yJ. w y.is P
@ p~-150 cy 3120 l -90) 't
. . .' q ;, / ,0., 30 g . ._ z ..
- 7. . -
..v. ... .. , -
p; v..
e .h, 't -
H ijl' C
l! !hCHES, L"HARj 7, .;.
p y.,-
-g i.
q!,1 Ij j -l '-
..% .. 1 J >
e .; N.. .S :4 !, j!
t i !
7 lil' :'i 1:p l.g i'lI I
'ji Nt t 4 .
'h./h#
'g t
m # .:j:
.t.i .
- l 1
- j. t e .:e. 2 -- gE.p (% -
.ip,:liq.900o f
l12.00 g0 l b ,1500'e)k kh,
- 300.l '600 ilI g . .
y'
~
e
lI;1 i l i 5SIGINEAR l I
,' e g:gy .a ..,. ' - .D[k N
.;g,,.. ;,;
Y g, j- ); 3{. ,,
i 8 {A4.d.$ ',' ' SyNM N1
} ,
i -
- e ;;. l , ;. J-- .& v -
m .< ~
9 e -150 ; ;120 1pr .-90
- ' +
j 0-ep . 3 ,; .
f q fi . --
3 -3 0 r '0 ' '
.h6u e f
v 4,.
e v. . . .I '. 50:. .
i 3.0 e g. .
g l 4 i
'E .
{
y e M . du !rj G :,i iiMh!O J l i 1 ep 1 e 7 em,:$jg 3 j j g lj 1 ,, , y. '.. .
a ..:. ,. m f, [;)j h800-'!
, l y .
g 0 g t.. ,503 1-300'i ! : 1200 I,
.1500 4' .J. >?M . .$ '. ;I - - -
2{ e :i .
i i ,l' l !. !; d, :iG.u,NE,AR
+ a ~;p .n.qp - -
.< . ;q fJ ' 7.cg- -
"c
.. , ~ - .
} g l
f,, e ' !I I ^l I
/ !
l
- . ffs- .. h I g. l g i , , i. . a- r* x e .t~ -*c.
O i.
lgi,
\ 3*/h'pd. '
i;.j.j l...i g' .r.M' l
_ ' 1, l l llI S- g01 12
! ;-90' : /50 ! I i-y0:
0 f.P .
3,0. ( '{e if 1 Sg g, }:j%}h @'
!gT . pes uhEA,R l-j
- dli,]
C.MF .
7
- e Lis[!H 5W, t q MF qw RT e "1 p$'
? .'
q q . &
lldI h; 'Wt pI.9
'i y h S:- h
- 397Ad inno .. i. ;; !; 600 ol
- ni 900 , m 112.00 11 5 e .g4 .
m f l . .: .
g'
.:w e . i i l- j i i PSIG UN[d 4 1 j
4 . , f.
liff
, i. t .
O I O 'a j j .
4),h '
4 > 'e .l
.J2
!)!; ,il:i .i t ia -
a ' '
, 2
[ l -
") I ['! g -. J
.'. -li ,0
]O_ [, . .g,ggg g .~
. im n c w -
, w. w gf% .
? i- M dy pds, 2
Ni M il M@im@:.incats.,uma
. k.: gM w r T '
aem l 3
$m ;f '.+nP? C. ' d e '
c ,i . r h .
ppm5 in n rpm . ., n- .. .
q fiks0c1 l 1 ,isoa.-9, , . ..a -
4GD h:3*
i .. 12m : sh ti. .x , ..
f2.- g { 'iSIG'll'KEA%
, ( y-.., .
a ,
a! R. . -f i& T W ,. .
- v.W.Q . &
&a 7
s
, l :0 ;.
+
4<
I.
- 1. p.] p...pf .;
. n
- b+ p.
- . . v
. .: g: a..
2
' p.( " , . I,gl. '
~
I p15f ;. .-j]0 -
' [ -60'. [i-30s. 1 N1; 0-f.s fl0Mr.0 -
$ i ' ' lei'+ Nm:HESJu a %.n, jE,1 {e].q j [ J ql .h , gj' .{
%o.. {iu.
- ,p g. . g &, _. tg , ,- ..;- -
_.., q., e
. i ,e , .!. o. ci .
',O *
.o-. .
,:/ t.y:1 6 1:
- m. .
..h.
. n ... .n .. i ,
- k. r- . ww . m.'*Q-d
.. ea..g&$._~N
. q. .
.msgy ' ng .
. . 1 s60 : a !:12 m . j -
353 ~ .
-,,w = = _ = _ _ -
srvc
--? 9 l1 %,f?- '
w0,.)-4'hh u[
{ ',
. , , g c i e y .; .
. e,
. .l.
= ;i , ,.i
.; s . .
e ; .e .I l - - - -
- y. . (..:
..3.j ,.
J l l l - I :.
' e' x p i .,
-150 i -120 l ! i I l-60[,".
m ! i i-y0. .30,. T '. ' ' '
a -
30:
50 Ik * .. . ..
, e ,y; ' q ;,; L H P INCHIS, UN, EAR!'
.g M '
il', , p; o .!!!-,-,;}i o
.. 1 ; h. .
~
W
,. s S ,. n ; "Il ,i, al l j , i
~$~
4 ,
q no
,' i, e v a
- i. - t.b in , -
9 lll,; il I
.l
,1 '
, ; a
.1' ',U, a j1- ~ >
3' 1
,('. g '300.ll iB00 l- 9:10. [ 'J200 $o 3500 [
J e ] l j l[ 1 l PSfG'LiKEAk,. .,
~
% . W - a % ,
t
~'
e l i x[ [ Y h.. . ,.,
f.. ;#
.Ww.
g .I 1 pup,. .!
l l}.
! ., i n i -
G"1b4120
%*0 _m.
' ,!-90 -y0i 30 ' :0'
- 36 1
. 6d 4/ [E,[V N 'SM
~
n
..... . . ., f
! t;. 'd' <- * [~
llh, l,U.,IN.CHES, UNEAR ' >mMe dyA Hf 4 4 e ;to u.
i; l' I g.l
.i' J ,
j.l' 2 y
1 i ,
l, ;. '
i w S .jj! ti 9 l i, ~
.il lt l : [i;] 1l, fll '
e L
- +J1- J. J:,-
.f ,g , .
I l
y w n
? gf.lMl, l i !300.!i .600. .
, ie00.. $200: L , -1500 ,
Q W Q h, .
e T 4;'
c
. I I PSIG UNEAR-i
;%a -
c'.mpw'
, A L'- V i
~
?
4d Mu v4 A s%-
n a ~
i_- -l - .
-1 -
m,,p-Qrr-R. ,
h.Q .
.v e.
j ,
i-y d ?, . f *l[-)
'8 .*b, .b 1
{'; $
6 i 87 ln N'
_?
f
,~y . .
-A '
Gf -
$b 80f k y:
fa t
[ .- .~_,
S NN6 A
' ~
? I 30 - *$ M EM A
-93; .-60 l["
M.M.. . Y I [ '['
. ~154 , .
co lll1Ellllld W d G f!.'pg 1
1N,CRESTUNEff '
9, Dq. ' l j i ' -
1- .jl d
4, ,
, j.
+
- 3. ,
d
.,i- i t p t 4
, . 4 / 9 .. .t' .
..y -
.y g ! 'f ij l
lj l -
4 ,-
- 1) l j ,
; p I.- '
f' > .;
;nl300.l '
9 g",Ti g
- k. , :600, j.300s : ,. : lJ200:. N I
/
' 9-
*.pSIG'UNEAAi i j_ s '
M-. -
q i er lj , , . '
'N' ' ,
e.e t d; ' ..
fR . n-N N M 4 2
qI ., - _ . ,
% - - , , . v 3 O ' . ,. .
&R $, ,
; p,.? g _ ;.
e.,.A f.,_-t-"% v: ?w "g ?
y ; f^ q %
a 7wty3-}A ,- ' -}i .r.
g l' ,
J .. 7-g r -
s,p;; ;w J2.g$ _
- yM3 %.:.fis '
,: V I ,
L , r &.;. , 1.: + ..
..; jEjWN .b;$..0 [1 g 15L;120,'
.,4 Wvv-
-90 -
60 * $30-g #-
, dbeD.D.7.I p *-
7
'4 g .g hp l J INCH $S, UNEAR,.
7 h ig:d-W .v.c i ,
!!d : l 4 - - -
S !p."+ '. l
.x Q ,
.. . ',1 I !
h .: p ,
d,s k
i y %
W 4 1 '
- I j i .i ,] l M
' ^
- 9] n 1-.300; 1600, n
$b.0 .; .
1500 - --
m
~
vi "
-. g N[dkM ;< .. .
Mt. rn b ., ,
.%., w ,
,,J.",..
flf
.~
A hSl@'U.1..
r . j ,-
- ,7 7f %- N:- .- ~; ;
s.-
.3,.m *
..-; M.%
i
( *'
4, l ' F g 969
.i ~. -
tii! . ..
, 40 ! !-60' l ~ ; '.-30. ; ; ' 0 ,h f30 l . WG o31 % ' -120 l
N y OU i. , jyi,'scsts, und {!!!((;,j. j} Hjf P ;'nlp H l; d;.y%m',j}h o, mt j. m m 4 y ,'{" .
, i m in nr enjun ijnce ;r'p:
- f d, h .! b
' a %x% I. i k'n2x %
; i . 4
* .#"a s aw } M. sw nsw
,I i '* < 3jj6TT i
, [! ,;; :1fsis'uMEAIll!71
'p.
.4 DN'.
- a f
;, g I
II j 4 f. ,} {j' f j .f d,-[%[el 1, i' h k- I
4 8 n.. 0 i 9
, n .m tH!!! n" punq 4 i q
a jewmew%
qn qmpw ypu a ny- g un 3, .gi -
+-
l ' '
g ! . .
y d' i 7l ;i:;3;;;$f;qi@jd.dg<10,so.
! Y 6
y y{ V A W} ( Nl 9
, 7; '
- 1 i .
z, eggig a
.4 d4 r y; 7,, . A; [-j ..-
.. .~ ., ,. . . ,
l
$7 i
~
i.
.~, -
,gi
.: ;' . 'Tff a }. -
\
l N t.s * -
v 9 r. ."
~=rO --' ' , Nm Lsy,..g W-r
- t'- '; e j .. ' %,[ , ,*.
IffQI 72$';_x,['.
4 '
.'3
. . . . .. s. . ~ . . . - .. . - -
l l
1 l L_ _ _ _ _ _ _ _ . _ _ _ _
It*'t .
~
- . . .'I [ llB@,JLAG$41.I ;
.l,.i :%I
)(.
.,,7 i iic+a ,j -
!-60; .;i 1-p "
#- . -150 l .'.120' p .
-?D. ' p.: t
.3,0,1 -.- 6:1 t pp y *..
..y}F 4fl'fNCHES' E4EMif k j ' '
3
m! L 11' iji { qIly hr L v,
.7 g i n n ., nn i i . ,e J lJ t jj-
{e.{ j. y
,m y (J,l 500 I l i8il.l[,
s e Vl -
3 a t.*I:
q b 04;M l jd900,. { l1200 .
(15 =00 e
;4 e ::300 . .: l ' i ,
iSIG unitAj .L .' -
,33
. I 1
; u .
y :;
w.
a g- a I. ,! . v 1 1 ie y j
? J '. 'f'f ; I. ) Qfh '
f*l (c' k' 40,
,-S3r' 60
[9 a 60.e
. .1(0lMO. l -
i
;. e Y 'N' flh 1,n ,ol,- f.
y . l m .ai s t i r h e; j' %M'{ il:!,l.sp qj 9 93 I
[ h M s'0,g; ' 4 300 : {i !900 i. t l } R00' i,1500 e
, ;F '
j1 Mists u!EAk P J
',e i
c .et
. \; .
i=%* .*
? e J'a .
f'E 3 -
@. . +.j. t. m. ~)0 [ .e..
, dkh0fl2Vsof.'..-80c.'1,A-30, s .
.. .g;q,,- - a 3f :.160 e
;i 7 } ' ,
y! }i Y .. .dHEAN i !
l[ L , e 1 .' 1 1 , w 1 idid i! t L i .
j .. o 41 y .
[ 1 e s .o al$j d men ,
n- i
~
ise e 7aGDR t . I
/ pS}G'UNEAk. $- g g .
!3ts .- ' ' -
i c : a, ;e
,y W g t ,f
% s' l - .
m 1-30; " o( 36b ,s]o V
"%ish;,. g0L lt-sor s
I* W W kNS'. UNEAi ll h
- 1
; L Ij 'e
-
- a 'u i '. 1 tij at it 't i :c i e- l.h ; , ,1 -
r !!' t I l l!- !
ill 19' y- , n i Q]!j Ql ji.
s It l: ' y iI i y j'" l .
t ,
1
,9P .N4 USM e g N., J /i300 o 9!El y ,
" ~ ' ' ' '
'p},g.SSbSIG'UNElk iLfvEL e
- , , A b 21 # .
~!;i'l' li .l } lli!li Il l ili' l g 9
s e-150!M12b
-50 ! I '-60 ; ' -30 ';Oili .30 i 66 0 e 9 " i
; ". I. 4 1 4'INCHI,S','dN.EAN : ,
l 1 L i . h ; ni.1 , i l t- i!.4 m u - -
2 e.
.p gj ....
,;q y i
p 4
w .gsLi,w!@jtj l
, a n .11 1 ise.1 l, us.a0; ::.. n001 , um ,
- - >Stustm e
;[m!ti.
. j ,
!g [c
~
.g.2 w . .s e . . l ~
e nu. ...
, tu . t
. .'~
o
"' ' 'l '
_.I'{l821*hWMl.t j ; 60; d
~
f ' *. -
154 l :.rn 4 ,120 1 ! -90l D. 30 Ik . , 1.; ' ' i
- I HDL'{l 160 'g g( d 1' i p;i. !Ih i 1[ g 9.d $1
',,'- j i ' ; 'IN. .CH.is,' ,gu, 'NEA, i. R, ' h ; !,
llh,'
'.' j['t..
! ,i
> . ii; -
,,, c . .
llj l! t l;p: l;U i I I
,. I . . at.: 2.
l
,4 g
"lIli : H ll'I. ln}h , . :ligl [
2 [ '
ih! 1.. j HH %. !hi t' } .
's e y' v.Y'q -(:l. . ;&%&&f }[(; I eld 500.0{&f (3 00 }d
! \ e Ii]
,9 . -l,) e F M.-,,~H 300 . l t i 1 h !
i h1200.l 4500 e ,
p* . gf . Go t 1
4 J PSIG UMEAR '
4 ,.
w
. - 'e.v g
- '-;. @3.p s...
g
[.- -
; L.; .
fs ..f; . ~' l &, .
9 .I
[ s N
. ' 3 1 4
J
- j. s s g. -
J.
Y2 cr.c. . . - -
- 4 "L. ,l
-m ;.
j
. y" ; ' , M .,< .d
, #-e 150 h 120 }
IS** :. mv
-90 ;-604 ^
,-d (.10l. 30f~ is e
[W v.* > - . .., . , ,. .
)g
- l. . . ,. ..
. .h6 .* I* q ll 8
} l- h h.~ nW
- y. %,$x w -"j{Ijf ^ ]j@ p% %Mg [ }h rjgp .p ; s uu A'u 0 n 2 .
"3 --
g a
[ . M 2ri ji h l:h! ljj ;j0 l! ihl 9W l
?
q h500 .
' '. ;..-4 [" "- I g ?. < .
(Fr! j! i , ; esta ustAe. i '
t l . f; :
g c
,{;il- [
j: .4;2 i ;
'j ..
# H 1 +. '- . d;d'f ic.<.? 3 I ~
- f. ' . 'c. f(;(. 9.,N4i'o F' -M: >
44 .
1
.Yt<.c. -' .i r- ..
W l W
e',M..;m 9 i , , .
i ds.
., *y "
. N$ , .A.- a. f.A J.>
8 .
I j
i i
s ~
I , m.l '
1
. L j
p)- * '4 .- 4 J Q,3 @e _15;L g120j -30i u 30 MfiO '9' J 11-90: 1-60 : .4. O' -
. v . :. ws .g 7 . .. 4
.[- . J ~f) ,VTY .7 c .7,,
.,' I.. p.,. I.T O i j ;i ,ll i.
tI ' -
!!l>tNCHES,0NEAR.hl ,
d.j i 1 'g Y f 9 J h n n{ . A . w e g$9h3 % g}}
g g
,.'j. j f [. .quyHbdR 7 4.Wpo4N h ,3300y .g [
n v.- r<f,{I.]G n o- ui, a; a 2v s o x%w . a: ,.. <
i esm.u.N # . m ,l
} e.. w 4 -
*/ 'f f.. C. r - f % 9 ') l l j.] ' !
lli
! f [i.3 I ,l, , j j j -
t
. l. ui i! ; i, i!j,' ; ,i l
, n.W q%$.w..g /.g$n: .:p1W y , .30 .
W;lLl'4 3 o l:, g.,0 3 Q &oz:. .. : a
<:.' !!i! ' ;;'q,Ji jlh.'l y;.g.Sl u Il. 4 e'b*
"..k..,.1s 4 tcg*. ! ,' ml j ' ; 0]:
4:g.M@; y a ,w h -y o
- ' INCHES. 'JNEA%p! ' qf <m
. o I .
(+,f..h .' p W. !U 3% {d. yj ,, .[c 3 p * .... j/.
e_ # A
? ,} d y
.e
;.; _ ;g ; y m x a . , yI y.. I:,. pI: pl
,p . ,, ,. , h.. ; . . . , , ., p
}!)g.
- , , - .s o SK M Il ;,x 4.: :.
sse ,3.
Q M 7^ # , ).3 . 0 M ' '3@ 7,.
6?0 ' L 11200!.
yh. .
l j i M ., - - '
.q 'j.a "'. '.; g l PSIG UNEAR ;
1; L ,
j1j "k i.j l
!{l,j g ,.; g .. ..c c. < . ; ; .. ., ,. . p : 11 : ' ' '7 i ' .
g .
I , , ,
#C e f>,; ~ g. l* .-t96
' ' t .
;!! {- g -[;' ' ' ' . **. - ;
.. e.: .y. ,;. -
gf% F$?$* 4t. J. *je < ,L il, '
; !l ;3,0 l1%l4 e jg 'Wp';n'dm y e
- w. _m
_n
_sa ,
_33 : ,a .
.s. m3% 4A. m,... #, ,p e.
" . . . =fp - :
- ' , , E.
m m-. i,
& n __ .1 6
, '3
) ~-
m
.lm iO
, .m. d-
4 i'
glh Hh t (b%S hd kr.9AB , a'j: I I iljI t
' p: g e , ; , u o i M
- 4 10 m 300: I '
. 600 j' l2900 . ! 1200 ,' 5's 4 g '
PSIG LINEAR ' i ,
-l ; []jl .g
. ,> ,j' , i 4 e iI1il 4 ', !.I, l J' ,
;6 4
g l lI jl !,i j ,
{ ]i !g i.
" l -
g -150 -120 , -90 '
-E0 ' 30 0 30i 60 8 e ) !
h
;l j ; IN0HES,, UNEAR' p' , , ;,;
.i j'j i h:
!;l e
e .p,,l
'l
,i.
'l. ! '
;; :h'
.i Dji 0
, : ,! i, }}!! .y
, g 'i i '
,ip c' ~' f. Mi pf .f, ,,,i, ;;;ll'[ g'(
;j. g .. !l , rg m-
!!,i n !h
!,I I 3' ,; ,
1 Od l 300 hbt' i500 i: 900h !!'2004 1 ,l- 3500 4 l g, E '
j ). {
i PSIG LINEAk j
{: il1! l'
'g -' 'l3 (
e i: ill +
i i
l!j ,,ii
! i !
1-o, m-
, j1 i;' 'ij t ll i t il '
e l
-120 4 -
-70
-80 i , I-30: l i
).i .40, 3 i
i 4
--150 -
! 3,0 ' ,60 C -
. fe9 -
;, 173p6 J i 3
Jem seu _! a 1 g
- e .
i l
+ m 1 i!
c 37; W. ong .l .. 1233 ,: l 7 150'
/ .
! 7; l, A
._ s?h '. l$ '
i:
l f* l y,
y y F s'; A 3 4.+ 4
, <;q 7" *t
):
3 -j
- ~
i ng$
~ ' ' [d '
Q l'
)\a l
l L
.i 1
1 ':
i i s yg --
^
- 3 __
m 4 .yi m.
p .g.-
W I
.t ,
. (g* g t,.. y vT
.k s ' -
w ' ,j 8 ,4 . " ' - * 'a ' .
e
.;, .,g ,
e 9,,y~ ' , .; ,
' p:;y,,
-\...,, _ , . _. , . . ' ': M, T : <
- -g- - - ~ .- g { ,
w 7 -
(top AeeH i ' '
c 2, *. 4pgo.
@ l! +
, , ,d
=
F. I $0 tc 10. 12D 'C i '. 6 C !150 i
023D :
i 1 Tl !
I i v' b208
) '
j l
L l ' . !.' ,
- t. ~3. PM w
.; .. j _ ' : 5 --l.-. j ; ' ; ; f h '
- j M ' .. .l:;:l d ij-)$ h i' "' l ' ,
50 w.
j I~E*
m I
m
. ,q;i.' i '<. JI)4'llf; mz.m ,, .'
t
,' ; f ' ,- b f h:lh%lbit 85g L ,
i 't .k, i~ j 'i -
i t. , J ' I' - iti s '.
;.t
? , . f . p . ;' ' .. .
w :-
;l .I d $, .l ,j
, ', o W ,~- y g; e
[
- i,' ih j.,',F ;[>
ip Q [ L J. '
W,Rg j 7
'X 3- 20' i , ' d O'607,ff.0 'L, 1b Y'100 'pi 1!~ .
12C[i .
L ]:- y;'
G,;q1i'@tlh{j((:!'pg.'" j oufl?-
.j'@!140 j' l,60g18
{-
i
- i s
i m,i;,f;.
p-o ,' x' 'm'
.{ ,
. i ,
;j
{ti ', } , 'j' j+ .
.l2 !.
' } { .j;:1 g
- i q.> iu1 t .
q3 ,m j qm at el 3
i 10 i
') . '- .,
70
.i 4
- ! T' ~33 '
i .!
- 4-40 :', g i !' 50 g j jl g
3 .
4 l
ijn gt Je b .1 .;l. 1 N. , q iq$
a . '
; , o , ja .
p Q. .: n , moyf{e
'r t
Le,e !
.l , ,e .;p '
Sl C_% l ' il, - q!@qf d
- i.ap.
f 5'" -l ;p l '! a p' ' .,j . y]y g 5
20 .. 4 80 100' !
3' - - 4-
. , . 6, .0' i 120'I Y4bT'f}
i ,w . Ik..h,&,p.
4 ,
Y b f h.I4r; i.' : ,4. h.,
g
,;..9 ,3 4-
- Q-g' !j!f f eh 0,P .'p' l
, i , /t .i g;.Ilh,ql.Of:1, 3
P i: ' 'I:- I. , i ., b; , 4 I 1 U.,ijd i d ]!j : ll ' d ht 1[i Mfk M . ,O 3~ ....,7,,',iy.2,0-.,.);...
1, 4' i , y ' xi.u,,,i, y[
ej ,50 k i n
.g v - m ,er
- s. _ ._ _
i f; d h ' ; 's W,' j If c i
.. 'yi' p ' b SFAMht
!,' i ; lk[.
.' t ; ' ! '. 1, iii !j k
, i i,g i ',;!:a h]MjI T
! s 9 .y ,..,in, i: . i .
- , c. :
n.y ig . c-h i f .
q' i
j 1 e <' Ig* c'D,j: t- ' . . 11, . 9 '
l
. 1 l.
'. V
!. l' , J1 ; p t ? A.3, ,'n.;
'itj 1 ,
,, :. t h .I .
a , .3 f 3 i 20 40 . 0 80 l~100 j *120 .;140: I m. 1,6, ,
f 5
7 > ,
,3 e
3"
[1
[ : 5 I
f',
, #efgy",g.. . g.;
i '
n' w aa 4 >
.; gi !f3 .[ t !: [ en.$ 6 f T %g~.p.w' r J: a
. l:-'. va ,(,MT g .; I*Dg'O$ -
. - i,.o +, 1.,..,. c: :
- r f:,,, i I
.}- ' '4
,.. i .,
t .f
'I' i j i
l -
l i ' . .
'k,, 3 ::' O 1
, 20 ! 3,0 ,
40- i. Sc 6g.' l Lg'.
4,,
, , . i i, f . . s ' k)., -
i i
p1er ;- .
x*.:.. m 2 yte.o o f , .
. . t 1
W, i.. J i
'c t - -
S f = w.
.q1 ppKyj#1
~
eJ . y q. i
;Ci.n.,
- . .. c :- 1 , gi( ! ' ( c C p Q 1 N .c
? d Q: gh.7 fff 1 @4%lgAi k f
.i gc, +q..y.
',[ d.'.,,>i *ju.. -
% .. m. y'E.7 ' E N#hh'4 l J we wqm
,td, WJ hp L. ' % T '
n "w t U I ht; l
+ &,,I". Mf 9', M &(+ +j , 2M . W,i : A m 'V t m }ii b* M.
L , t. .
. ,im. I !c r' .y+...
m.. i~< n W~;.y ;
'b fbd i}r. ' ;, %..
+. -v "e . . ..e
-e . 4 . . .
L .I , . . - i
!{
i 3 ., e 1
!beNQ,wi ' ' Nw
.hlh;{t[F NOMg :
Z " NN .N
~
'I z}
i . .O.i
.,w....
j, r: fdl.dc.e H ; m' i;i ' ! } m.. : n!
r t ,
" ' %m . v. .N il 8, . 44-3 ;; J
.. .w
- s. i, 7.
u- M [r?
.h !
i h k :
? wi . w,. u,m v & M as ne m_.. . _ _
..
2. ,c
(?. 43I hY j' _ A f . . .'n .h h?Y -
.s'
.r-
, 4i 4V i e .
'@ u ,,. . +g? .ty; -. 7 .. ;
.A, c
.,3,.
. ,f . : ,.g ."#. ,
, gg,.. p. j
<g,. s Q,c -..,
g s. 94 ,
~
.. . - l_
i 4 u-ghM ~ . L . ~k ; ; .... e , ;
wt e ,-- ,~ ... %y?!. :s. r5 p} - .. . : M ., .-
y; .y. ,.~q.; -
Qq9 3 , ..
..,y, 9; ~ ,,:g9 , _yg ;z ( _ 1 ..
pv- , . -. ' < *N , .
- f g . ?4 5; a 3, 444 '..
yW.. N ,: Q.v I.s J g ..f g J,. #
. ~ , . . g .. y v. s 4 'y. ,.l.,*'. *. f - y
. y-M. .- ~ :
jG %p z t. ,*+'s -..,>4..,
t %-
v N< ' j,ff e '...w gre ,&
e- ,' . ' k.g 4 t' M L*OF'~;
' .F . l,,,T 4.sl.'. %& . ~ i l 3
+
%.. % a w m * ; a. o 5 . 1 -r -
o - -
J..'7A.-g; ..- '
s b.j. . .G.J
~ t,
- a. w~ A*l~ q~. enn ,
, v
*w 2. W.
m p/= ' "f i
- e. s -
a m.
~'%W% ha x [.&*.?.L , :9 , ' - ' "::r
?- :e .: y , ." 94
- L.
w
.: 3
- M= , s.vs p~e?.**%
'3 7
,... &e 4 e.*
s) ' *
.s
, x - 'y"
& 5
- y)W.e~;2:';'g
*i >
-.,s-
.?-
w ..e .., o:*:..;Wy.;
- ; , };, $' .. , . , W.
-h. -'
.f,, }. .. .:, .%'M ,g ,.4 - "*
- c.' ; -Q * *~ . l Q. + ,.
. _ , ' ,; ','7.,' ~ , [ :' . .,
a...A a _ u. e s ,. -
..; ,t , y. . , : g. e -
, . ' , , . - Q.,., g;
% . ' * * , *) e - , /O . . wg ',)i
{ , , . . , . - p;Q' .,
.I j. g. ,
g .;
- T- . ..g j!. .- r
' f/-
.s .a s.
.g . y yu %
.. e,{.. +[ .q < - ;. - ' .F +x..
a
_> - e.,; / , ,* . ,,,'-Q.s .). A .
,_.Q*g3 ,' 4 ,, 'a ;+4," ' *- _ -g +
x 3 i I.
- , ' '\. ,
" .[ y,'.
g'f.l p."y.-4
..s . .. .
,( . .
, N (,2
,, f ,
, *.- ; +' e-
...,..q,. ~ . f'. %[, g. . + ..
'.( ..
d.
.gf - uwy_ y
- Y '. O& ? fi , ,:*.a s,,t p.;. -, j q
. . z.-.
, , _, , . . . ,*: ay. d.
.' , dub -
- k. J # *. [ ',j. _ . , , . .
p3 .[ f ; ' %
"r g >; f,, i, "$ #; .{., ,{ .. y E. [k [. , 'f. ; . .$ .[ . ( .
{ qlffC }; ,
y y .%. - - - ,
?: <;. -
.m~
y.x, .. ~ . -- . , $. , p.;
- r,
_y.
;g . ,
.ug -
- g. . .n* ,'. - v .-
~
6 .. v. . , -
[ .1;: Q
*Q t; f. ?,T:
s[. ... k * :: . .,. 'g.f. .-4. : ..; . - - ., i+ g, ,,= . ;n. f.e~ k '. .;f ' *', Q . f ,.i .*-
Mg[Q< ' glN .h ' ' ...W L%e.
**) F R. . - w
=e , ... ,. a ..y ..
w.
, ~
~D
%.i v.$ik 3. ,Mh?;%.n . .','.4.ir-f C . -:$f.1.C..%UI
.. . . .,m. m.
m
,[y , .,v . o+
C
-3 g.s h '.
._ _.l la h ,.fYfh +wn . y W T'I
- +. w ..: .~ . o g gy ; % f-W.W %lQT1Q.. :.;
- ~ -
, :w. s. : i h._W - 'i 5j.9 %M
@.W F:;. ' '%x gfhpg.1 lSV ^ Y
/
3 ,_
iy.'..;Q.W*V-1
- QJ J:" ,
- : y1 twj % 2y .?
z , , L::
k ?
n ...:.z ' .
.;.:. fM
. 1.n:y'$ 4 . Qg$ M y .
..].['h n
" Y p ". - k( 5p - { ' %Q.. . ,1 ?** 't .
i
- a. p ~. . a.y .
c - .,
,, g... .. - c ~ .
... s ;. 4 . . ,1. -
g v; f,.. ..... :--; ;
.i' : ;; _ ;y --
.? s' w . ;; y ,u c. a w w m ;g: ' %. n: L.,, ah g,.%,
.. s .. .
s $ .p n p my,y,,s _ mm -
a, 9' .
...- , . : . .- .s .-
.2,
. ,{;Q.y >
u.::;; Wg .. . k (2 z
.. . . .,:.. u ..,.u. ...
(-%w.a s.
. '. y ;. /,Y;
&. 3, :; 9' Q vA , L ,_ . ~ . gT -s.~. 'k*. .:t ',,; , ; ; , Vg ' ,* ? i - h %) . _ s l- .. - '}i}}