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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
{{#Wiki_filter:.. OmnATF RFPORT PREVIOUS REPORT DATE 3/4/83 NRC F3CM 366 U S. NUCLTAfD Ul@ULATORY COMMIIil11N APFROVED SY OUR s
j'o'e,Q so LICENSEE EVENT REPORT 3'50-801' CONTROL 8 LOCK. l l l l l
@ (PLEASE PeilNT on TYPE ALL REQUIRED INFoRMATaoN) l ol1 .l .l A lL 7 LIC ElNSEBElC R ODE l F l l!@l0 l0 l- l 0 le 89 l 0 l 0 l 0l 0l 0l 0l 0IS l@l 4LICENSE blC ENSE NUMSEN 1.
l 1 l TYPE ll 1l1 l@l 3. .7 cat l
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3 .. .3 DOCK ET NUMB ER .. 4. EVENT D ATE Fe ,5 R E PO R T D A T E s.
EVENT DESCRIPTION AND PRO 3ABLE CONSCOUENCES h l 0 l2 l l Following reactor scram MSRV l-1-22 apparently failed to close and drvwell l 1013ll unidentified leakane exceeded 5 com (T.S. 3.6.C.1). Unit 1 was placed in l l o l4 l l ccid shutdown; the vacuum relief valve for MSRV l-1-22 was replaced. Durini; l lolsll reactor heatup on 2/8/83, drywell unidentified leakage exceeded 5 gpm. Unit l
lolsll 1 was placed in cold shutdown. The vacuum relief valve for MSRV l-1-22 was l lol7ll found damaged. There was no effect on public health or safety. The remaining l lolsll vacuum relief valves were operable.
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l C l@lF lh l C!h l A lh l 0 l 112 12s.l lY 39 34 35 34 3r .s l@ lY lh lN lh lC l 2 l 0 l 2l 4, *43 44 4, CAUSF DESCRIPTION AND CORRECTsVE ACTIONS h I'l0Il The 10 inch vatau n elief valve (GPE Controls Model #LF240-435) failed to l l 1 l tl l reseat. With 1-1-22 open, this resulted in leakage to the drywell. The l I1I:ll vacuum relief valve was replaced. The vacuum relief valves have been l l1l3ll modified on unit 2 and are to be modified durine the present unit 1 and the l l111ll next unit 3 refueling outages. (See additional details on supplemental sheet). [
STAT s % Po w s e OTNEW ST ATUS DISCOV E R V DISCOVER Y DESCRIPTION l il s .l l. G l @ l 0 l 0 l 0 nl@l NA l l l@l Surveillance Instruction l i.
is
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N u' w"D E [" '"oUs C IPTION l il a.l .l'0 l 0l0 l@l 1 i, in NA l TTPE D E S C # tPTIO N l1l9l, . hl NA 8307120501 830630 I qi l
, ,. PDR S
ADOCK 05000259 , ..
...u R I,"" le'. ,,Tio,. @ PDR l N9e utE oNLv l 2 l 0 l l Y l@l Press release to media.
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l lllllllllllll NAME OF PREPARFR E. T. Holder psoNE; (205)-729'-0885
r - -
_ Tennessee Valley Authority
' Form RF 17 l Browns Ferry NucIcar Plant BF 15.2 2/12/82
['l. LER SUPPLEMENTAL INFORMATION
{', BFRO 259 / 83007 Technical Specification Involved 3 6.c.1 Reported Under Technical Specification 6.7 2.b.(2)* Date Due NRC 7/01/83 f Event Narrative:
[ Cu 2/5/83, unit 2 was in a refueling outage, unit 3 was operating at 100 percent
[ power, and unit 1 was being shutdown after a scram and subsequent failure to reseat of MSRV 1-1-22, when drywell unidentified leakage exceeded 5 gpm
-- (Technical Specification 3.6.c.1). Reactor was placed in cold shutdown. Repairs j were effected on MSRV 1-1-22 (see BFR0 50-259/83006). The vacuum relief valve for MSRV 1-1-22 was found opened and was replaced. Four other vacuum relief valves were found damaged and replaced.
On 2/8/83, during reactor heatup, drywell unidentified leakage again exceeded 5 gpm. Unit 1 was placed in cold shutdown. The vacuum relief valve for MSRV 1-1-22 was found damaged and was replaced. MSRV 1-1-22 was found stuck open (see -
BFR0 50-259/83006). In addition, the degree indicating arm on the vacuum relief valve was found to be bent and has caused the vacuum relief valve to be stuck open. The degree indicating arms were removed from the vacuum relief valves in unit 1 until these valves are modified during the next outage.
The vacuum relief valves on unit 2 were modified during the unit 2 cj cle 4 refueling outage, unit 1 valves are to be modified this refueling outage, and I the unit 3 vacuum relief valves are to be modified during the next refueling outage on the unit. This modification includes the installation of a new modified hinge arm, a new modified hinge shaft, a new modified hinge bearing and associated components, a spacer, and also the removal of the valve position indicators. The modification is required to prevent the damage that occurs to the vacuum relief valvi when abnormal cycling of MSRVs occurs.
a The failure analysis revealed that the suspected cause for damage to the vacuum relief valves are opening conditions that were not anticipated in the design r process. Thus, the valves were procurred to operate under conditions less severe
{ than are actually experienced (see attached NRC'and failure evaluation).
, The attached safety evaluation by Engineering Design provides justification for
, continued operation of unit 3 unti'l the cycle 5 refueling outage. Modifications t -
of these valves will be completed on all three units by the end of the unite 3 cycle 5 refueling outage.
Previous Similar Events :
None Retention: ?criod - Lifetime; Responsibility - Document Control Supervisor
g 5 '
DIVISIOM OF ENGINEERING DESIGN SVONCOEBFORMANCE REPORT 8.
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MEos accewon No r3 s830310
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B M E88303 l @ maront No.
e pas,amanioncasiratioN/ oaf t T. W. Parkalev/EN DES-NES/ March 3, 1983 N //[!4 Jd /e r l - @ ossemittion os coNoiticN p CPE vacuum breaker valves installed cn the main steam safety / relief valve ta11 pipes have been unexpectedly damaged in service. The suspected cause is that tha valves
{
are being subjected to opening conditions that were not anticipated in the design 3
process. Thus, the valves were procured to operate under conditions less severe
' than are actually experienced.
r . oaTE cr ocevaarNet Esv t i acT i [s,hvis t sicNiFicaNicoNoitioN ensE70ountiiv p'es g % r 5
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Ccncurrence: H-5 n t/ 2 -
3/ 8%
[ Croup Head b f/l}DU S //7,[# ~3 .
5 NCR NF 8 6 830'3 (copy attached) i .
l The deficiency identified by the NCR renders the affected syste (s):
Still qualified for all design 1cadi:s cc binaticas and design
' conditions.
= .
Not qualified for some design leading co=binatics or design condition. However, a functional i= pair =est of the syste (s) is not likely.
Not qualified for seme design loading combination or design
[ -
conditien. A system (s) failure or functional i=; air =ent is
[*- .j likely. If this item is checked, cc=plete the folleving two
.' items cf additional infor=ation.
.t _
Idestify the critical leading ec=binatics or ec:ditics:
3 ---- , Rec.etel sRv a.c.e e l.(,. 0 ., amad<fe s.
trA em 54v ew/.S . 7
}-
----G Identify the type and locatien of the failu e or functional (L Z i= pair =ent: Vu ma. bre aA e / <</r e dis c /ai/s ce s ea e er s n r ~Ot.ec s 4raus. A;A e c . W/s is>
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e 6+ .ee'll w SKil e aseers.!
n,a disc e., AsJ.* e*^ A /*ps.a
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Justificatica for the above f,ud., ent:
l N Uilt / ve.e.we. bre d e.r ** /v e. e n. $RV ed/pice s sAnwstL dana.ee.
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y en G al* 13 value,s . Valee. slonci<q o rs+ clasaa.a . ren,e f
r, y v m* treaJ feilere. .ak. dise u.A.se.re w;u fr.n r:me arn . TIL f y ass oc.o'o.t'tE MV kad. hee e. a.< t%e.t*A.
gre. c.y s.Ja. 4 opsra.eiAg partet.
Cc=ents and/cr recc=enda.icns (c; tic al):
. vs m br.aker v <A e. were. r e.o k e.= d e r t u it /. Unir & ,
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valv4 w r e. weddie.L osis e t. e,& of resfwahn o.dma e..
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. v-wie> l s 3 oe. e&e/v oo .ra2ia> witL
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R O i
E Baaw4's FERRY FOCLEAR PLANT SAFETY EVAltaTION REPORT
~
TITLE: NCN 8U 8E89303 Dell & r'/p in e. V'cnu 8eeake_r Dwa e_
SYSTEM: L!ct/A - 5 te-A. A APPLICABLE LNITS: / a.ncL 3 SYSTEM PUEER: I MECS ACCES$loN No.
m ,
T ra' M 221
.au. ro cviemo l m ov' ; 1EB '830318
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m 3 4 R 4
5
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NES '83 0 318 221 H o e t" (
w ee .< of P<e ble, ;
To dete.ruirte ek e < < fe 9 iy a e a f fors o f easa p ur.
bewary ;, s. n. . 11 <, s a/ .6, /r e /ie { a a /a e U.ey) taiIpipe & a e- te s<<wtura/ G it'ar e. o f a. vo.w a b e c.a k e- r edu c-Refarenee s:
- 1) Area.< h~d '%yemt- A/ w e ~ fren N.d. a<a.1/ey se
- 0. w witsea. .t a t e. d. 2/ir/s .1 a) c.w.< a se:aas aiek c/vis Hoffu.s (s w rs- M a A. Fr.) , .
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- w. K. Suc.h (xrB-M), J.M. 40k e//. (cl~0), ui
- S.R. Law.s e n (8 vP)
') N' K BfM'fE8e 3c3 [NE8 830.h'c 8 S.~)
E .Accior .
. kL & stean n fexy/re fie./~ valv (sse v) hn s s.
tar l pipe. siet ecwt'5 c-k e- Mll aisky c- ta b eneatk tk e- tcr% s niet e.r . 7'A e- tai / pip e s c.* + te d n. e- % k
aej. n /C
- va.c.u. w b y e-a k e r 7'A e. 2f
- ymu.x breake r is a- Powe-ll e.le d vg.lv e- a.e d is swir; to " v .e u- a. n pa.er a f tie. anyim/ desay. TA e bt e sker is a GPE vaeu w .bre.a.ker verlet ~ i+A. n 7
- clice. ,A is o. p.< tio n. e f ek s /any cera +o r es s ttnen,a l m oelifimtion s . Th. c. Fue-tion a f e k <.s c-t wo v a.c. u u A br'erNers bs tc aA +it dry w' Y < it imb t'er n kg.s th e- tri/pif e s i Ste./ SKU d r *r c.ka.t bee.n. e o nele n e a . ri,, p ,.v - ~ q areiJ n a.u. ~
feen 4e< tag in +ke ca.i/pe;pe. scL mkinir.e s tA<
. = = . . un NEB '83 0 318 221 mer a te9m,y wak e.r lay eA.at de-v=Jops san & a. A p a.r ri e l -
v a.e a.m i> fo rmed. . rhe. Gpf va e m breaker.
va lv e was edde.d to p< ovid - iner -a n d r e l, e /*
wpeeity >c e: te m ininit e- e k e. w e-t e r /ep rker e s ~ d a ve /cp . Jn fer wat e ly , r A e- p ee ss uee d rop ia ete-ca.1/ pipe ane +coffsren d e n ra.rior o f r h e. steam v e e tA.e srely 5gV e lose s is A so rapid. tItac- tk e GPE ga e.u.m Jrea.te r e a /ve . f/< > s op-^- ud ionyin;. e-S p or. e 4 e.
iu e., yip e- -a Il . 71e r e eu /ta.rt impac2 / sad .s eke G PE va /v e- Ed eime. W SA'y da,m1 e-acxaate e <a r e e loses ,
its a. s souated G 7E vae u.m bre.ake r wi// op e.r a.ul s w Wer ,ispacs
- load s . Da e. s.py e a < s to a.c.e a Ject e- wieL y re-p eci e d impa.e&s O e.el G PE va.e. u, g,x
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- 5i breek u r a /ve :1 kave. be.er & & ist uns /
ud 3 . Pe.t tLe axkAecL %.ap ne Not "
da+e k a/is-/e 3 ud e..ver .s ect ic st vi+ k this
=_ //o// ins 6& pa , Mea. or.) , r-Le. most da.mapc el
= G PE va/ve. sie utt- / was near sed Ai/ete (dise- was u :c rewist fren. Aisye a.nn ) u.cl its assa taeet .sa u a sea we natel alcu1 G + im e s .
m fa.ilure s ocLe.s iduSNed. are twa :
C Va lva- retains ie7<ie7 ,be At(s te s e.ad a.nd.
perni+s steu. leaky e. ico evywe l1 -%ew
& SR V elise W y e s ) e h e) Valve- lo s e.s irt ,.isy wi+k. disc sefurokr^j
221. gg e 3 NEB '83 0318 frow A,57e arr
% Le e- Lim Ner ni op e-r e re n or re aAsiests F*o < e-1el$r idene,fied faik, e n ad e_ , vax.w w n reli I w;// 6e previded . sitter hi/a.re tode.
eow/d r e sa /t in r e d a e.ed. va e-w u ee lief c.ap,Jp if +Ae dise- /edge d at sae.k a. m e r a.s to eeda< e tke efreediee. F/cw a r e et o f +4.e. vafu e .
Er. tAis cas e. +Ae waker /ey e.owtd. rir e to s.
kryer level a.n cL e.x a.s t
/enper &en a.s raed in.
a.nalys e s If eA, sgu assae.;atet w;rk 4. R danerge.d. vec.w an breaAer va/ve rea.c -tuate d. w A.ex 4Ac. water /cy wa.s at rt.s hiy dest peix2, th e-.
sab.seyw e n+ load s impsed on. tA e- +ui/ pipe eaa&
be. hoyke r %. prev,ca.s fy an a /y s a el . Lodpi f fke va/ve ciisc- su.c k. a.s to pro eide siyn/fie.ut r e d uenica ef -rde. vacuw re./tef ye ity i.r exasidueel
- m. n r< e cap,,2 kiqll u w.n//ke.Jue.
~ n.
/a arewdias de s- s 4u snak ana_
ir a.,ea ps% a "For eitker ident.+ified hi/a e med e,pp ste
.e m lea.kag e inte t-Ae dqwe.ll wl.e~ t-A s x y a ,i v i e.s wi// se ix.c.-r e a..s ed . Th e- evur dar N to rite discover of -tAe de ect GPE vac.aa. bre aN valve s involved su e.iest leakye to cAe d qwet /
n se asesea ns_ce carie.ee ixvw, pica .
thr Ass m p the GPE valve- failed in. see L a. way tie. dise- elicL & in.p e.d e_ f/cw ir cik dIrveio<<.
thic /t. -tk e- va.lv e. , tken. +4 =- clisc.Aufr.-.from tale-
. a.ss ee.iated MV wadcL en+er eA.e- s.ry we //
n
a i
221 same y NEB '83 0318 rk;, wegd rat he.c tAar b- co nda ,es ed. in +Ae ceras _
e c. e. v. c da - eo r A e. p2k. ees42 a.n c e. Leirty /a.srs (ae f/*a eo tA c. d.rywe-ll t ks. Ase f4a c A to u y. 4.
rh a. T ysene Ae e s . vsL e sa. A e.,tdi+io ,e s av ry +ike-eke a.ssec.iccte 0 $RV a.c-twaxe.cl , sij nifim-t pas.ctik,s o( <. e ~ w;il .-rs r & e d.,y a e. //. ro e vuy bei./
askua:tian s bypte.a./ of prayer acinatior . f a.s. s R V eLwe- to tesfotary eve.rf re s s u r e. c.cnelitiers Nforr/y
- a. tie.ipax A trans ier+s sae A a s tstbine trip), tke-s tean r lenses s istro et citywe// wig - orel<x.se wklo e de(e.c e.r io a. s. safety sor s epwe.oue e > . Foe weie,es s a.e.A. a. s may easu h fra, yec leyel a.e
&-lafera+e- blowdeu or a. s e u.e k op e-r SR v, exe.
s teae. re/ w eA irte tAa. dry well wiU pt=ssurize the- drywe.// a..u L r ais e- ek - euywe // ataosp, Aerie teyeratste.. -lh e.<,editiests e-terteA will tkose ca.u.ses by a_ 0. /5 f*t
a.pp t exisai e.
tai, sia e. stem beer.k to ele.
brea.k . be.torys internehrte. be4 a.wiede.r-e cra A) wyo ey .
An EBA results i,e kyk dry w ell tey er a.+ure c.eadHieoc s whiel e ey u.u e a.du.aktu a f cese+Um Sfeey kt etiti adr* cit A r E8 A a.ls o /*esuks iA.
the. AyJ.e,r a.xoly tae<J dpuvete. /oaA.1 an. t<e.
to e a s stine u., z w eo etty we.Il ye e. s s y e.
te lie f via. +1e. dowru euter s <* yra.LanlG f* lows (,dia L ,e. e. e.okd r e. to a.Agip).
ine.reasiy TBh h.ve. beest exwively m (yzed auL cru f
221 fre e 5-NEB '830318 s er w a./ aadineariors sa.de sp-edie.1/7 for ae.
^
IB4 a.raly tieal load s . Evau ,,iek rf e. ca a s s tea.ete r rl xadificatibn s in. a- p ar+ia./ly a.l/
isf fe m ted. seade (a.s fee.serr/Y u is+s a r.
w
*dt ec RA it S ) y c u u. k AC di[[c.At/ ors dsumm- d e.t/t.
<.e kie.v e-cl te wi+ b tc.<.cl re4 < val p eiea./ fondr.
A-rica rep ares ec n;rja.ee u IB A % ben w -(/
definet . 1%s 8FN is desijned fo r a.r d. e l e.
ap e ea+.t s a.e e e raie ed r, <>+ ,y <f IBAs. fr <.
v a.l yz e d.
- o. e e- two ke.y differene es be+ ween.
m [BA s a ,.& s +en. r e.ter s e. ra e-Ae drywe// dne g +o a. fail.d v a. e.w w a. br e a ke r valu e f d EBA s a. r - ass a el to 4e ye<na.,-+ kife-
^E a 3R v c-a L e. ~h <e c ta a ed (tes a. s calaffe.
5 L e - a h) , ud. ,
-$ 2) E8A s t e u. is released direce./y e vi,.
--a drya e // a+ no syk er <- wLeie e %tu aiseAarye s tern e.xpa.r.d s ise+= rie. ta.i/ pip e. axd tM ine tLe. etry we // vie +ke fQiled va.ea.a. dreak er
^
va/ve 1% s/,jb/y rekee , tie. ro d .a.erp y y ted s ele i arpal < sop.2fte.s differe nee s + end +a na.ks +Le Affe d 4 vu wo. beeake e case /e.s.s s e v e., e tAar u TBA.
Ho wev e r, if a a.otte r vaew u b res.her v<.lve.s or a tv= s frJ/ed tLe e ue.r-t , tAe n Ja.t in$
s es u e u
= c-oa./d- b ms.d <,s ec it.s e-y we.e.e.e s
+ke'^'[BA. In ny ea.s e +L e. faifel vae w un.
beesket wi+L pro /cyad SKV set Ain. is danoded.
. ww 221.
NEB '830318 by am/y se.s anL is witAir 4 capa.M!y _
exis+iy/
rLe ef p aa to xitijat e .
[f is wl$a possible fer the SRV to sinre y a.c a- p;ven pre s s u.t e . A sonstasct or nev _
eonsin.rt valax cf s+eu. wi// Ja ee/ea,eJ ir a.n n x+.s m ae A. less +Lu. fro n a. faJ/y ope.n.
SR t] . U ekis scea n or a partii,t of iv >> r e. /=u<J.
to sk- elepell aia. a.
leakip or fu.i/e/ va.c.u. a beerhee valve., tke e.orseyu. era.e., a., e. e. < e. A. le n fa fly opex SA U.
^^
t-ka,e. For *fA* e.
se v e e <. a.
-- wi// 6 e. e.e nel e.rse cl wi+Le a aeJere.r/o g.s sa.fe.sy j j eonseyaer es.
//ewev e , e.ortinge.d p/a..cc epvection as a.y b e kinde r ed- clu.e- ,e-e p r ada. ally tre-reas/p Arywefl ptessuee a.,tajo f 1*a.e 4. Sp ee-. / hiss a n.
*f'A i s +yp e j r lea.ky e. x sid - prixary ecxinixre.itt.
e.veret clicl. oe-e.ae o se uit / ie. oely & /ruay
/763 For the fail wee acde wkere c k <. eLis c. separete,s hos ek<- /t iry c. a. < n , je is con ecivad/e 1Aat
-tke dis e. eon /L + < +4 e- w/pi;oe. H ete foes e.
eli s c. sett /d ir s ae.A. a. w e.r a.s ce e ne taase y.r bc f F0f1*llck by a-
$kbr5c.yaext disc-fae e, it ce 4.l0-rLe. sm ud b eccs e. a. mis,;/ witAir e d s. t a.ite n .
E sa an i,ttern/ mis.si/e en id prodwe ispaes hads clue to inyipn ea az yip eJ/>ows , espaeis/?y if a<
e-lice is a.t the e<d af a fe.ry t/.y Ant hor / toe.]
r s t. . A loose. eli., e ceald eos.xcualf <.ortu tL e_ .
.. . -.-.: ..L._. . . . : a ._ _
221 54e
- 7 NEB '830318 L.ee it wealcL eken c a.s a n<. . Sjoe./c e_ o.f _
-f*ysenk.=.r ite les l0 0 se. disc. w e !ck sof pre s eA+ a.
f= yatu.4e. t b y a.
pre blem. as the vsse rAjority of the stw wo (d. fe ank an 1 de Jrpell. The iycu.* loaAs Jae to ),.piy& calcl da e_ _
a<.tulpe y aut raf ipe f ,apporo ;f ele is.)s vere very Ivy.
na a.rs e o. as e wy -Ja s ra,cac<. J a- wi p,pa. .s ide.
t'h' forsi sirsf1C t . $~ueE a. rnft arc ~ coslcl c.r este- a s e r e/ *.
Ioadin eeditis n 1A*. eor u otraetar - if eks Sg v w
- e,lo s e a.n J. toe a s c.estalwxt spia.y as aut acmee 4. to r/m. turns qirs e.u , je.as s<.or er s c.cn/t Ase- the steaA estati
<W ritis esse ~oa.tk be. e ce tha. tev/ppe. sap,rart.s dat weall Ind te brily y<- shrotrekn .vithea e /rss o f iatteyri+y. Wrile tA= t% /p y e. vaali no /9 c.t &a p liRed a ut e., ea a llo s a l /~.-s , presu w o . of prassar La udary
+o r a s s erarv e wo~ll suc-irrep ri+y ~,JL answee che be. d eck eve ~ ;/ f.e che,- SXVa<x eko oe.c.gerd.
Ispn - etoad 1 w e.t a. J.;, va> > ut . i<L j. x . sea e.//e c'e' rd .
A cc.or +o hin rha eUs c.
,eiyk, apprexiwe /r tr. c. p. 4.1 u el u s-t be. u e < le ea+ e es s., e a. ve/oe;+y af eto.ce-
? f0 fej sl ec. yeioe to jya c 6- in. oeder ev y /aolac 9 losL> e ha.+ wa</d yi /d a- ett/ppe syp.er, rA<
laxpers Lorizoical + ail y rye. ru is k f S'o fes t. Th e.
rey %e c a <= A.ie r <
eLis e- ~ < rt la seeal raiec i by StsC
< SC fe/,ee. eis h So k1. cu 1iderJ/e. Bre.
maIcl 6e reyek.d- +c a.eet y l4 L t/ is. Yk' o^ly c.r dible . ne eka is n a.va tkile- is +Ae Gre. <- a f +A.e SRII clisekye. s n .aat . O nly > e< u . flo~iy rAro yL
l 221 "*d i tiEB '830318 en ni pe p c. +re 1:y ~~4a. , ait/ a.1f.ee a. /c , a due . __
v R As st tes errfie.r ths majority of +Ae SKYJisckarye sm l- will s++nt r-A*- dry wedl. 'I'his r esu.e s t-Ae st ee r flos/
tha.t- .*Ill - I fe c + *.!cose dis e. . Sirt< c H e d is c Ars
- a. Lias te:+e e oS 1.c f ' ,,L ehe +r;/p,pe i aer wm, ;,
9,SG H ', a. . Orc eda 3idetsb/L ysf **/// sfise betwe cst. td e-esye a eA e u it y,y e ,,Jr e..n is a- ai,c. ,:,,e,4e+p yasy eulie u.lar <c +he <aiype. o<1 (ie. Mis pai+ ton i+ wd l
espos e- ti e yr ertrot pstfac.e. atea.
ael yap yerrJts > +ea n n e.,e p atoad +A.e eus e-b <ed.u.e.s vAe. fo <e <. e-><e eeeA en rle dis c . Af+ r c onsideri +k e's L fors, tie- Cran.e cow //'ipe
/
ieA. n.,r. g<eek erd, rioa wa , a.aA aissussup cre suai.a.
ria.c as d.is . stl/ not e ns <,aiaa pia-criy jye is a ro fr/s -c..
g = _. ^< e- e touy k fore.e. exa.t+ed an is to a.a ie.v e.
Tkas ie is e-ene /udeeL eAa+ a. /oe.se. disc s ;// e e t rc*< /c- i<
l
+<il y p e eaftae or dayed w/p,pe = yport.s.
n Ia e s m s a a1-,, i, +iI,.ye. e < sp.s.s a. e
{
reac+i.~ fo re.e.s ~ se.& t>y st ea. ~ exi+iy inte +A dryv=JI H ria. ne-a. bewet adue. J<ae.
_ hatey n s n a rela <y e..
,ee r.n , r<.~ se h..p ,n , c&- ,. .J< ., eaty r.< <<
5
- c. < J e .toee(e. (sya< 4e. orifiee ar ene 4 Ja. Ae<eypa).
St - Cla u 4. <o A. the. aputy ane ip <.s. Snv dise.laye-
[
nc s c s-~ aa e,~
n,, a,s. i,,up) nee load s . fer d is e,s si.s.s ait4. .I.it. l(ce.le/4 (cEB , fN w i
res al ttuJ- /*s & , w/// no+ da.*utyc-rke.ts*lf'fc,eti/,ao,* pet Aest. Thas tAs- e > it!' 16"G '*C supports , of inf injed. _
. . - - . - . - - . . . . -o n---
l
" " ' 9 1 NEB '830318 221 i
[ will e er pr. seat a orfety yto Llen . _
fn sn m ery a.// fei/u r .- eersep. .re< s dwri wrst <4 j ,
tree.sicc pt w -ediHou o.e e 6 cud cA by ua/y a e.d.
i l e e ees s . Ho w u -r, cAc eens perees a f ~ seta k opes.
i $A i/ a.r e. inc.re a,s e.d- // exe. v e u u a bre4 Aer va de A//s
[ oper. Also, eke- probo bi//7 ek s d.ry wel i// v p < tie.n c e.
Aiyh. ee.y<.rakse. cedition.s a n d.
7844/sadips i.s iu.c = s = = 1 a. s e A e- //Ae/ibo4 / a. .re. k ope 4. 54 v wick ILiled. v e.uxx 6reakw va./ve is kiyke.r tAtA. a-( pip 4eealt et c.ritic.a) c..t 1.e.k .
iL failur e CL<im k.iden- Cudpicas
/
% previe~> d is c u n io.us pertaisi<j te v aca w re/ief f;
f phi /i+y , sepua.eter of tAa du e taadiy to ~lcese dize- /~
L H e- tri/p.pe. , n d s t-- ~ je+ fordig/ s a.r e. a.ppfia.affe in less 6/ oo/ut
- j-- to Lilute dain L
-), L a a.ceicia.s t- c-en d i+ica .s .
H-we.ver, rAe. e.fr-<r & s+ en.~ /ealcap. e ico de.
i dryws/l is diffe / c ^t~.
L e f* ton the- vie wpoi.r t .f rense ~<1e r /ev e / a.n.el vesse l pres s are. /*e.spon s e s , SR V <.e ha-tion el v i y ^
an S8,9 f.mJ/ beea/c a.eeided) oe Z8 A 6dernedin+e be al< acc.idert-) is tke s a ae- ty aeller.s a f ~A n d e e e-Ag.
l-t - sr-aka x <- nains ye,t . New.eu, os a. ,
cersideri e h e- tot u.s ste exar,{ /ca dinp s it do e.s ,
y- + nt<c airra n cA chu se n en~ s s
( tuns via. a. elowne one r or a. 7;p.e ne Av. A//
I g stru.kwest loa.d.iy c.ed tha.c hue 6 e.en. s Aa /p eel
NEB '83 0318 221 suainj s. pape4rea) ;a side. the cuy we// tAat- is o f e- -
j' ired size. Skerrm. e f stea.^ ;<+o rke d ry.,s // m a h,'fe$ varnss- ben /st vrl* e- wie n. tke. nssee iat-ed .$ oft / is oper y eed ae es art e ffar a-s tAoupk eA e. pipe 4r caA .
site- Aetyes- Si e7 0 plc, a. n '9A coa Jeun.< c^ 1~!A a u l A a.<. retmen es as sSA wkar an . fell opu.s ud.
e,lo .re s . tac e fhes s f t-fir A a., ce W ine luled. in
(
, yea v feu.s analyse s. ,a,y,,
% ritua+im e ar se t <d.e .<ste e.op beat <L ifA r<ema-preaker vale s fa il d ae i y rh e sa.id est (she- e. tk e.
; faeees operirj t-A e vneaan- Jeep.A'u ea./oc.s inc r ease s Jn,y $0A/18A esa&M eke- vafues bees-e. <<e- t,Ae/y O fail auL anay fetll -wk fe-es S&V accatica s). For egayle, as S6A occurs . Vyer cert <imc.<t ise /< tion Serv a /ife at their ytessure serpelives arcL raset . A va m brerAer valv e. fails darity this. Sulsepc** SRV ac.taatiosa esca.t'd 18A typs auli+'hs ke toYfaile<L ousa- he</<er rafa e- e. < d-4itss ~.
U fur ther vaenan breake , value s A / 4 b4wdawn. e e.e ges (eitker sau.a./ or 40.:5) a. sd. .rteas r a tis deps// fres sevem/ A ,i/e l g e. m Jr ea ker ,, /ge_3 c, e e4 Nr 1.d e sf B B 4 (rein swn-lik eype e.orelirier.s ins /cle priwy con-kinect .
Needles s to .eay such a- denNn Ass neau } =e+ inves+je+cd not ans(pad . A .ardi to J. x. He eAe/le. (cr8) rA.e.
I at< associa.+e el w .'tA n key. BA [Aese-tera s cruet twal lead;r/,
t-ru ~.,reslcn,a n an uA i, r-08Aa ~r e. se v erc. it r, *. A c fa<ti nu e reates Z6A ttye e o A d i n a s . 7A c.
torns r e spox.s e. te nn DFA te artd > + Ais s /M. tion. . .
l
' i
s l
' \
' 221 I4..e a 4
NEB '830318 11e erns r espro as e to aot 764 is ao+ m da- swore. seve r e. if _
[ es se.M Nng SofI' rads aor e steas to ac ettp, e. //. fA t-r wer e e o< se- aa/pis stiff bouds dis cre d . No otAe r el ped uerra a r a. nad e ass e s e vere. t M M e norst
[ ease us/pir d u e +o racu s~ 6teaker va fee hi/n ee. Th-t cLey aeff pressaier+ier , redet%,n ja m f/*v n Me
_ fpercku of de failed vae u m b e ender v /,- m;/y,pe ,
I n d. . itered dereal lod were- all considered. stree. r .,-tm j= t-k a s,Mtiers enside < e et , , e. u y a fyg e_d , d ,_ , ! !~
/
ssmyuau
? J ^- loadiso siner,' eses " "
' A a.a/y geol Aceds
/ s eria.rty /,eLefon@ . ' //* we v e r', c.ez s e t era +/o'e-enowrf b e. - ^ j ,' _ : 2 :,^ c
^
l
. .2 p eyinee rin jud;sted is fAat- t/e w w a/yse d e u eretx l-un beardeci by de ~c t. - + we. aralyds .
3 I~ sway ll fsen vonsepes dwo tap mdw r Nc-e.o+ <L'+kse s ar. / J ed 1 te 6e bouuled b7 wer,eereA e-as e an/y14 T
Wa s>c-ver, ras m sep e, tees af as .:S/Vi st-ould /> e de
= worse. du e +a vac a n bre-ake r value. /qi/ure .
E Co^e/.s/orz d n' +<4fiecl ceX asosa brerker ee/ves will aperieu.e.-
Ja a wie.never SR V*s n eaa te<l,.
d Ca-<je scewla h s Jek sddMesa.] Si v a cka.W e
}a a.e aM p
*ieh a ra,a.af..a,sev.ers.
esulerk k .a. clen x*/e/b
-a ii.bo* utwi G r. actuatier.a.s er . . - . -
- 3) Sepantica of Me. vala s. do;c e. from e4e kh'y a. arr ait a.
[ S ev ere Iy ciasa.7 ed. ya /v - eowid oce.ca. Qsei)ad&7 Q
wwt be pr e e/udedj
( ')t The- eseseywe,eee.s o f G PE exe ww krea.ker ya.lu E
1 , .
. . . . . .-.- .. ~ . ..........-. - =
NEB '83 0318 221 kla ro a ar - lad y ed to bu 6auded by untyzect <vuts A wo rse eas e an alyzes ; a4
$) $t- f f0 bQ h/fitf y b- c.4st J t u t sce 5 olfctrt/E4lAt a vu ts /mevrien s are jaer ess ed- Ja e +a use of we ga.nedified CPE vs.ea<x. 6teaker veh es. % ws.w . es sferg ~6+,oIte.caey n e, oe ; ~ctp e g n he Nukek hy % ytM{ e v e oL Y f> O.c . the- k adf 3 ea.n s a.vs> G dly wit /.stauL d u+,yae. As vde A d i c. cors7u.e me s) ,
4 D t .d. -
d 9
L '
>l 4 -
f" f.
e e
- pr . ..
TENNESSEE VALLEggpfHkRI 5 CH ATTANOOGA, TEtiNSME*E Shkot 1750 Chestnut Streec Tower g S '. O O
June 30, 1983 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30303
Dear Mr. O'Reilly:
TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UHIT 1 - DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-259/83007 - REVISION 1 The enclosed report is a supplement to my letter dated March 4, 1983, concerning unidentified leakage exceeding 5 gpm following a reactor scram.
This report is submitted in accordance with Browns Ferry unit 1 Technical Specification 6.7.2.b(2).
Very truly yours, TENNESSEE VALLEY AUTHORITY e f $8//93
- H. J. Green U Director of Nuclear Power Enclosure oc (Enclosure):
Document Control Desk U.S.' Nuclear Regulatory Commission Washington, D.C. 20555 Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 NRC Inspector, Browns Ferry gvCh00d
- p-g
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