ML19345E696
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| ML19345E696 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 01/30/1981 |
| From: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19345E695 | List: |
| References | |
| LER-81-001-03L, LER-81-1-3L, NUDOCS 8102050564 | |
| Download: ML19345E696 (2) | |
Similar Documents at Vermont Yankee | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D6131994-04-29029 April 1994
[Table view]LER 94-005-00:on 940330,fire Suppression Water Supply Sys Declared Inoperable.Caused by Inadequate Design of cross- Connection Portion of Svc Water Sys & Inadequate Procedures. Valve SW-8 Tagged Shut to Prevent re-opening.W/940429 Ltr ML20046B4901993-07-30030 July 1993 LER 93-008-00:on 930701,discovered That During Previous Surveillance Testing on 910515,pump Differential Pressure Entered IST Required Action Range Due to Personnel Error. Plant Procedure AP 0164 Will Be revised.W/930730 Ltr ML20046A1141993-07-16016 July 1993 LER 93-007-00:on 930609,determined That Daily Instrument Checks Required by TS Were Not Included in Operator Rounds. Caused by Mgt & Human Factors Weakness.Ts Proposed Change & Amend Issue Process Will Be performed.W/930716 Ltr ML20045G5991993-07-0707 July 1993 LER 93-001-02:on 921217,indeterminate Fire Penetration Seal Configuration Identified When Insulation Removed from Piping.On 930324,addl Indeterminate Seals Identified.Fire Watches Established & New Seals installed.W/930707 Ltr ML20045D9191993-06-24024 June 1993 LER 93-006-00:on 930527,both Core Spray Sys Trains a & B Declared Inoperable When Calibr Procedure Error Resulted in Setpoint Set Nonconservatively.Caused by Failure to Apply Head Correction Factor.Procedure corrected.W/930624 Ltr ML18100B2771992-05-20020 May 1992 LER 92-016-00:on 920422,discovered That TS Quarterly Flow Test Not Performed During safety-related HVAC Sys Surveillance of Chilled Water Pump.Caused by Personnel Error.Procedure Re Ref Valves revised.W/920520 Ltr ML18100B2761992-05-19019 May 1992 LER 92-015-00:on 920424,RCIC Sys Declared Inoperable When Sys Flow Controller Meter Indicated Approx 30 Gpm Flow W/ RCIC Not Operating.Caused by Setpoint Drift.Work Orders Initiated to Correct Meter indication.W/920519 Ltr ML20028H7501991-01-23023 January 1991 LER 91-001-00:on 910104,radiation Protection (RP) Technician Entered Posted High Radiation Area W/O Dose Rate Monitoring Device Due to Personnel Error.Technician Relieved of Further RP duties.W/910123 Ltr ML20043G5691990-06-15015 June 1990 LER 90-007-00:on 900515,determined That Concentration of Old Bottle of Ammonia Span Gas Not within Spec Causing Ammonia Trip Setting to Be Nonconservative.Caused by Incorrect Certification by Vendor.Bottle replaced.W/900615 Ltr ML20042F3611990-05-0202 May 1990 LER 90-006-00:on 900403,Tech Spec Surveillance Requirement Missed Due to Failure to Include Basis on Tracking List. Caused by Personnel Error.Changes to Master Surveillance List & Any Affected Procedures Will Be made.W/900502 Ltr ML20042F2231990-05-0202 May 1990 LER 90-006-01:on 900403,discovered That Flow Transmitters That Supply Advanced off-gas Sys Flow Indication Had Not Been Calibr.Caused by Failure to Include Procedure on Surveillance List.Personnel retrained.W/900503 Ltr ML20042E1691990-04-12012 April 1990 LER 90-003-00:on 900319,inadvertent Primary Containment Isolation Sys Actuation Occurred.Caused by Lack of Coordination Between Monitor Downscale Setpoint & Monitor Reading.Proper Coordination established.W/900412 Ltr ML20012E9301990-03-22022 March 1990 LER 90-002-00:on 900302,identified That Key Sprinkler Isolation Valve Not Adequately Surveilled.Caused by Personnel Error.Valve Verified as Sealed & Surveillances for Fire Protection Valves revised.W/900322 Ltr ML20012B6061990-03-0808 March 1990 LER-90-001-00:on 900209,primary Containment Isolation Sys Group III Isolation & Subsequent Standby Gas Treatment Sys Initiation Occurred.Caused by Personnel Error.Isolation Reset.Personnel Counseled on Proper procedures.W/900308 Ltr ML20012C4291990-03-0707 March 1990 LER 87-015-01:on 871003,reactor Scram Occurred as Result of Turbine Control Valves Rapid Opening & Subsequent Fast Closure.Caused by Flow Imbalance in Turbine Control Oil Sys. Turbine Startup Procedure revised.W/900207 Ltr ML20006B4701990-01-22022 January 1990 LER 89-026-00:on 891223 & 900105,primary Containment Isolation Sys Group III Isolation & Standby Gas Treatment Sys Initiations Occurred.Caused by Failure of Sensor Converter.Isolation Reset & Monitor bypassed.W/900122 Ltr ML20005E1511989-12-26026 December 1989 LER 89-025-00:on 891128,primary Containment Isolation Sys Group III & Standby Gas Treatment Sys Initiation Occurred. Caused by Failure of Reactor Bldg Ventilation Radiation Monitor/Sensor Converter.Converter replaced.W/891226 Ltr ML20011D4901989-12-20020 December 1989 LER 89-024-01:on 890913,while Reviewing RHR Sys Surveillance Procedure,Determined That Leak Testing of RHR Valve V10-18 Not Incorporated & Implemented in Rev 9.Caused by Incomplete Review.Event Reviewed w/personnel.W/891220 Ltr ML19327A8881989-10-13013 October 1989 LER 89-024-00:on 890913,noted That Requirement from Previous Inservice Test Program Rev 9 Re Leak Testing of Valve V10-18 Not Incorporated & Implemented.Caused by Incomplete Review & Omission.Procedure Changes implemented.W/891013 Ltr ML19325C7821989-10-11011 October 1989 LER 89-023-00:on 890911,discovered That Remote Indication to Valve RHR-20 Not Available from 890320-0912,when Supply Breaker Replaced.Caused by Lack of Personnel Recognition. Breaker Replaced & Indication restored.W/891011 Ltr ML20024A8681983-06-22022 June 1983 LER 83-015/01T-0:on 830608,error Discovered in Spacing Table Developed for Support of Copper Piping in Svc Water Sys.Addl Supports Required to Fully Comply W/Ansi B31.1.W/830622 Ltr ML20024A8311983-06-0909 June 1983 LER 83-015/01P-0:on 830608,Yankee Atomic Electric Co Informed Util That Addl Piping Supports Required to Support Piping in Svc Water Sys & Torus Attached Piping.Cause & Corrective Actions to Be Provided in Next rept.W/830609 Ltr ML20024A3441983-06-0707 June 1983 LER 83-014/03L-0:on 830510,discovered Surveillance Frequency for Svc Water Processs Monitor Exceeded Tech Specs.Caused by Schedule Error.Analysis Immediately Performed.Applicable Personnel reinstructed.W/830607 Ltr ML20024A4151983-05-13013 May 1983 LER 83-013/03L-0:on 830413,while Reactor Shutdown,Weekly Environ Air Sample for 830405-12 at Station AT1.3 Not Obtained.Caused by Technician Failure to Test for Sys Vacuum.Technician Reinstructed in procedure.W/830513 Ltr ML20023B4741983-04-25025 April 1983 LER 83-011/03L-0:on 830325,during Visual Insp,Shock Suppressor MS-6 on Main Steam a Piping Found W/No Visible Fluid in Sight Glass & Failed to Lock Up.Caused by Damaged Lenztee.Snubber Cleaned & Rebuilt ML20028F3741983-01-21021 January 1983 LER 83-002/02T-0:on 830108,discovered Leak in 2-inch Stainless Steel Schedule 160 Isolable Section of Reactor Drain Line.Cause Unknown.Leaking Elbow Replaced w/304L Type Stainless Steel Matl Per NUREG-0313 Requirements ML20028F3921983-01-19019 January 1983 LER 82-026/03L-0:on 821220,while Shifting from Reactor Bldg Closed Cooling Water HX B to A,Closed Cooling Water Temp Rapidly Dropped 20 F.Caused by Increased Efficiency of HX Upon Cleaning ML20028D5591983-01-10010 January 1983 LER 83-001/01P-0:on 830107,valves V-16-19-20 & 22B Failed to Close When Operator Attempted to Secure Nitrogen Flow.Caused by Accumulation of Iron Particles on Magnet Used to Provide Valve Position Indication.Valves Cleaned ML20028D5421983-01-10010 January 1983 LER 83-002/01P-0:on 830108,indication of Leak in 2-inch Stainless Steel Schedule 160 Isolable Section of Reactor Drain Line Found.Caused by Pipe Crack.Cause of Pipe Crack Unknown.Elbow Replaced w/304L Type Stainless Steel Matl ML20028A3601982-11-0303 November 1982 LER 82-022/03L-0:on 821005,diesel Generator a Failed to Reach Required Voltage & Frequency within Tech Spec Time Limit.Caused by Fuel Oil Return Line Check Valve Failure. Valve Replaced ML20052C0051982-04-23023 April 1982 LER 82-007/01T-1:on 820309,standby Liquid Control Storage Tank Level & Sodium Pentaborate Concentration Calculations Did Not Correctly Account for Specific Gravity of Sodium Pentaborate.Caused by Procedure Equation Errors ML20052C0451982-04-23023 April 1982 LER 82-003/01T-1:on 820220,boron Concentration Fell Below Tech Spec Requirement.Caused by Apparent Boron Loss Coupled W/Small Sodium Pentaborate Concentration Margin ML20050B3941982-03-25025 March 1982 LER 82-005/03L-0:on 820223,uninterruptible Ac Electric Power Sys Tripped & Lost Power to Motor Control Ctr 89B, Rendering Sys Inoperable.Caused by Shorted Out Transient Suppression Capacitor Due to Aging.Capacitor Replaced ML20050A9291982-03-23023 March 1982 LER 82-007/01T-0:on 820309,calculations of Standby Liquid Control Storage Tank Concentration Versus Tank Level Correlation Did Not Account for Specific Gravity of Sodium Penaborate.Procedures Corrected ML20050A3781982-03-21021 March 1982 LER 82-006/03L-0:on 820219,during Normal Surveillance on Differential Pressure Switches DPIS 2-120 A,B,C & D,Switches A,B & C Found to Be Out of Tech Spec Limits.Caused by Setpoint Drift.Switches Reset to within Required Tolerance ML20042B2361982-03-16016 March 1982 LER 82-004/03L-0:on 820216,discovered That Continuous Environ Air Sample Not Obtainable at Station AT1.4 Per Tech Spec.Caused by Solder Lug of Std 125V-8A Power Toggle Switch Parting at 90 Degree Bend.Faulty Switch Replaced ML20042A4111982-03-0909 March 1982 LER 82-007/01P-0:on 820309,error Revealed in Calculations of Sodium Pentaborate Concentration in SLC Tank.Caused by Specific Gravity of Solution Not Being Factored Into Weight Percent Calculation in Accordance W/Tech Specs ML20042A6031982-03-0606 March 1982 LER 82-003/01T-0:on 820208,sample of Standby Liquid Control Boron Concentration Below Tech Spec Limits.Investigation in Progress.Administrated Limit & Sampling Frequency Increased ML20041F9281982-03-0303 March 1982 LER 82-002/03L-0:on 820206,ac Ground & Blown Fuse Alarms Activated,Rendering Trouble Alarm UPS-B Inoperable.Caused by Blown Fuse M Transient Suppression Circuit Due to Shorted Out Capacitor Off Board 2A 17 ML20041D7771982-02-25025 February 1982 LER 82-001/03L-0:on 820128,IRM Channel B Declared Inoperable.Caused by Failed Voltage Pre AMP (GE 112C-2218G001).Half Scram Manually Initiated.Component Will Be Repaired Prior to Entering IRM Range ML20041D4281982-02-22022 February 1982 LER 82-003/01P-0:on 820220,after Addition of Water to SLC Tank,Solution Sample Found Boron Concentration Below Required Amounts.Cause Unknown.Administrative Limit for Concentration Will Be Increased & Addl Sampling Conducted ML20040E2581982-01-26026 January 1982 LER 81-037/03L-0:on 811227,while Attempting to Start RHRSW Pump P-8-1A,breaker Tripped Contrary to Tech Specs.Caused by Worn Bushings on Operating Mechanism.Circuit Breaker Replaced.Breaker Mfg by Ge,Model Am 4.16 250-8HB ML20040C6971982-01-16016 January 1982 LER 81-036/03L-0:on 811217,containment Isolation Valve CU-15 Failed to Seat Satisfactorily Per Tech Spec 4.7.D.1 During Quarterly Surveillance Testing.Caused by Failure of Closing Torque Switch.Torque Switch Will Be Replaced Next Shutdown ML20040B1941981-12-30030 December 1981 Updated 81-028/03X-1:on 811017,field Breaker Failed to Open, Effectively Disabling Rrmg Set Recirculation Pump Trip Instrumentation.Caused by Binding of Operating Mechanism.New Breaker Installed ML20039F0101981-12-30030 December 1981 LER 81-035/03L-0:on 811204,during Core Spray Valve Test, Breaker for V14-11A Tripped & Reactor Shutdown Commenced. Caused by Breaker Not Latching When Closed,Allowing Breaker to Trip Below Setpoint.Breaker Replaced ML20039C2991981-12-18018 December 1981 LER 81-032/03L-0:on 811120,valves RWCU 68 & 15 Found to Have Seat Leakages Exceeding Tech Spec Range.Cause Not Stated. Disc Replaced & Valves Satisfactorily Retested ML20039C3071981-12-18018 December 1981 LER 81-034/03L-0:on 811121,operating Cycle Test of Standby Gas Treatment HEPA Filters Found Not to Have Been Done Since Sept 1979.Caused by Failure to Include Test on Dept Surveillance List.Test Completed & Schedule Revised ML20039C1121981-12-17017 December 1981 Updated LER 81-011/03X-1:on 810507,leak Discovered in Socket Weld Reducing Fitting.Caused by Intergranular Stress Corrosion Cracking.All Similar Fittings Replaced W/Differently Designed Fitting Less Susceptible to Failure ML20039C3821981-12-17017 December 1981 Updated LER 81-016/03X-1:on 810622,small Leak Found in Socket Weld Reducing Fitting in Vent Line of Regenerative Heat Exchanger E-15-1A.Caused by Intergranular Stress Corrosion Cracking Due to Wetting of Asbestos Insulation ML20039B1281981-12-0909 December 1981 LER 81-033/01T-0:on 811125,reactor Bldg Roof Hatch Opened by Work Crew W/O Notice to Supervisor Until Fire Permit for Welding Requested.Caused by Personnel Error.Personnel Reinstructed Re Procedural Requirement 1994-04-29 Category:RO) MONTHYEARML20029D6131994-04-29029 April 1994
[Table view]LER 94-005-00:on 940330,fire Suppression Water Supply Sys Declared Inoperable.Caused by Inadequate Design of cross- Connection Portion of Svc Water Sys & Inadequate Procedures. Valve SW-8 Tagged Shut to Prevent re-opening.W/940429 Ltr ML20046B4901993-07-30030 July 1993 LER 93-008-00:on 930701,discovered That During Previous Surveillance Testing on 910515,pump Differential Pressure Entered IST Required Action Range Due to Personnel Error. Plant Procedure AP 0164 Will Be revised.W/930730 Ltr ML20046A1141993-07-16016 July 1993 LER 93-007-00:on 930609,determined That Daily Instrument Checks Required by TS Were Not Included in Operator Rounds. Caused by Mgt & Human Factors Weakness.Ts Proposed Change & Amend Issue Process Will Be performed.W/930716 Ltr ML20045G5991993-07-0707 July 1993 LER 93-001-02:on 921217,indeterminate Fire Penetration Seal Configuration Identified When Insulation Removed from Piping.On 930324,addl Indeterminate Seals Identified.Fire Watches Established & New Seals installed.W/930707 Ltr ML20045D9191993-06-24024 June 1993 LER 93-006-00:on 930527,both Core Spray Sys Trains a & B Declared Inoperable When Calibr Procedure Error Resulted in Setpoint Set Nonconservatively.Caused by Failure to Apply Head Correction Factor.Procedure corrected.W/930624 Ltr ML18100B2771992-05-20020 May 1992 LER 92-016-00:on 920422,discovered That TS Quarterly Flow Test Not Performed During safety-related HVAC Sys Surveillance of Chilled Water Pump.Caused by Personnel Error.Procedure Re Ref Valves revised.W/920520 Ltr ML18100B2761992-05-19019 May 1992 LER 92-015-00:on 920424,RCIC Sys Declared Inoperable When Sys Flow Controller Meter Indicated Approx 30 Gpm Flow W/ RCIC Not Operating.Caused by Setpoint Drift.Work Orders Initiated to Correct Meter indication.W/920519 Ltr ML20028H7501991-01-23023 January 1991 LER 91-001-00:on 910104,radiation Protection (RP) Technician Entered Posted High Radiation Area W/O Dose Rate Monitoring Device Due to Personnel Error.Technician Relieved of Further RP duties.W/910123 Ltr ML20043G5691990-06-15015 June 1990 LER 90-007-00:on 900515,determined That Concentration of Old Bottle of Ammonia Span Gas Not within Spec Causing Ammonia Trip Setting to Be Nonconservative.Caused by Incorrect Certification by Vendor.Bottle replaced.W/900615 Ltr ML20042F3611990-05-0202 May 1990 LER 90-006-00:on 900403,Tech Spec Surveillance Requirement Missed Due to Failure to Include Basis on Tracking List. Caused by Personnel Error.Changes to Master Surveillance List & Any Affected Procedures Will Be made.W/900502 Ltr ML20042F2231990-05-0202 May 1990 LER 90-006-01:on 900403,discovered That Flow Transmitters That Supply Advanced off-gas Sys Flow Indication Had Not Been Calibr.Caused by Failure to Include Procedure on Surveillance List.Personnel retrained.W/900503 Ltr ML20042E1691990-04-12012 April 1990 LER 90-003-00:on 900319,inadvertent Primary Containment Isolation Sys Actuation Occurred.Caused by Lack of Coordination Between Monitor Downscale Setpoint & Monitor Reading.Proper Coordination established.W/900412 Ltr ML20012E9301990-03-22022 March 1990 LER 90-002-00:on 900302,identified That Key Sprinkler Isolation Valve Not Adequately Surveilled.Caused by Personnel Error.Valve Verified as Sealed & Surveillances for Fire Protection Valves revised.W/900322 Ltr ML20012B6061990-03-0808 March 1990 LER-90-001-00:on 900209,primary Containment Isolation Sys Group III Isolation & Subsequent Standby Gas Treatment Sys Initiation Occurred.Caused by Personnel Error.Isolation Reset.Personnel Counseled on Proper procedures.W/900308 Ltr ML20012C4291990-03-0707 March 1990 LER 87-015-01:on 871003,reactor Scram Occurred as Result of Turbine Control Valves Rapid Opening & Subsequent Fast Closure.Caused by Flow Imbalance in Turbine Control Oil Sys. Turbine Startup Procedure revised.W/900207 Ltr ML20006B4701990-01-22022 January 1990 LER 89-026-00:on 891223 & 900105,primary Containment Isolation Sys Group III Isolation & Standby Gas Treatment Sys Initiations Occurred.Caused by Failure of Sensor Converter.Isolation Reset & Monitor bypassed.W/900122 Ltr ML20005E1511989-12-26026 December 1989 LER 89-025-00:on 891128,primary Containment Isolation Sys Group III & Standby Gas Treatment Sys Initiation Occurred. Caused by Failure of Reactor Bldg Ventilation Radiation Monitor/Sensor Converter.Converter replaced.W/891226 Ltr ML20011D4901989-12-20020 December 1989 LER 89-024-01:on 890913,while Reviewing RHR Sys Surveillance Procedure,Determined That Leak Testing of RHR Valve V10-18 Not Incorporated & Implemented in Rev 9.Caused by Incomplete Review.Event Reviewed w/personnel.W/891220 Ltr ML19327A8881989-10-13013 October 1989 LER 89-024-00:on 890913,noted That Requirement from Previous Inservice Test Program Rev 9 Re Leak Testing of Valve V10-18 Not Incorporated & Implemented.Caused by Incomplete Review & Omission.Procedure Changes implemented.W/891013 Ltr ML19325C7821989-10-11011 October 1989 LER 89-023-00:on 890911,discovered That Remote Indication to Valve RHR-20 Not Available from 890320-0912,when Supply Breaker Replaced.Caused by Lack of Personnel Recognition. Breaker Replaced & Indication restored.W/891011 Ltr ML20024A8681983-06-22022 June 1983 LER 83-015/01T-0:on 830608,error Discovered in Spacing Table Developed for Support of Copper Piping in Svc Water Sys.Addl Supports Required to Fully Comply W/Ansi B31.1.W/830622 Ltr ML20024A8311983-06-0909 June 1983 LER 83-015/01P-0:on 830608,Yankee Atomic Electric Co Informed Util That Addl Piping Supports Required to Support Piping in Svc Water Sys & Torus Attached Piping.Cause & Corrective Actions to Be Provided in Next rept.W/830609 Ltr ML20024A3441983-06-0707 June 1983 LER 83-014/03L-0:on 830510,discovered Surveillance Frequency for Svc Water Processs Monitor Exceeded Tech Specs.Caused by Schedule Error.Analysis Immediately Performed.Applicable Personnel reinstructed.W/830607 Ltr ML20024A4151983-05-13013 May 1983 LER 83-013/03L-0:on 830413,while Reactor Shutdown,Weekly Environ Air Sample for 830405-12 at Station AT1.3 Not Obtained.Caused by Technician Failure to Test for Sys Vacuum.Technician Reinstructed in procedure.W/830513 Ltr ML20023B4741983-04-25025 April 1983 LER 83-011/03L-0:on 830325,during Visual Insp,Shock Suppressor MS-6 on Main Steam a Piping Found W/No Visible Fluid in Sight Glass & Failed to Lock Up.Caused by Damaged Lenztee.Snubber Cleaned & Rebuilt ML20028F3741983-01-21021 January 1983 LER 83-002/02T-0:on 830108,discovered Leak in 2-inch Stainless Steel Schedule 160 Isolable Section of Reactor Drain Line.Cause Unknown.Leaking Elbow Replaced w/304L Type Stainless Steel Matl Per NUREG-0313 Requirements ML20028F3921983-01-19019 January 1983 LER 82-026/03L-0:on 821220,while Shifting from Reactor Bldg Closed Cooling Water HX B to A,Closed Cooling Water Temp Rapidly Dropped 20 F.Caused by Increased Efficiency of HX Upon Cleaning ML20028D5591983-01-10010 January 1983 LER 83-001/01P-0:on 830107,valves V-16-19-20 & 22B Failed to Close When Operator Attempted to Secure Nitrogen Flow.Caused by Accumulation of Iron Particles on Magnet Used to Provide Valve Position Indication.Valves Cleaned ML20028D5421983-01-10010 January 1983 LER 83-002/01P-0:on 830108,indication of Leak in 2-inch Stainless Steel Schedule 160 Isolable Section of Reactor Drain Line Found.Caused by Pipe Crack.Cause of Pipe Crack Unknown.Elbow Replaced w/304L Type Stainless Steel Matl ML20028A3601982-11-0303 November 1982 LER 82-022/03L-0:on 821005,diesel Generator a Failed to Reach Required Voltage & Frequency within Tech Spec Time Limit.Caused by Fuel Oil Return Line Check Valve Failure. Valve Replaced ML20052C0051982-04-23023 April 1982 LER 82-007/01T-1:on 820309,standby Liquid Control Storage Tank Level & Sodium Pentaborate Concentration Calculations Did Not Correctly Account for Specific Gravity of Sodium Pentaborate.Caused by Procedure Equation Errors ML20052C0451982-04-23023 April 1982 LER 82-003/01T-1:on 820220,boron Concentration Fell Below Tech Spec Requirement.Caused by Apparent Boron Loss Coupled W/Small Sodium Pentaborate Concentration Margin ML20050B3941982-03-25025 March 1982 LER 82-005/03L-0:on 820223,uninterruptible Ac Electric Power Sys Tripped & Lost Power to Motor Control Ctr 89B, Rendering Sys Inoperable.Caused by Shorted Out Transient Suppression Capacitor Due to Aging.Capacitor Replaced ML20050A9291982-03-23023 March 1982 LER 82-007/01T-0:on 820309,calculations of Standby Liquid Control Storage Tank Concentration Versus Tank Level Correlation Did Not Account for Specific Gravity of Sodium Penaborate.Procedures Corrected ML20050A3781982-03-21021 March 1982 LER 82-006/03L-0:on 820219,during Normal Surveillance on Differential Pressure Switches DPIS 2-120 A,B,C & D,Switches A,B & C Found to Be Out of Tech Spec Limits.Caused by Setpoint Drift.Switches Reset to within Required Tolerance ML20042B2361982-03-16016 March 1982 LER 82-004/03L-0:on 820216,discovered That Continuous Environ Air Sample Not Obtainable at Station AT1.4 Per Tech Spec.Caused by Solder Lug of Std 125V-8A Power Toggle Switch Parting at 90 Degree Bend.Faulty Switch Replaced ML20042A4111982-03-0909 March 1982 LER 82-007/01P-0:on 820309,error Revealed in Calculations of Sodium Pentaborate Concentration in SLC Tank.Caused by Specific Gravity of Solution Not Being Factored Into Weight Percent Calculation in Accordance W/Tech Specs ML20042A6031982-03-0606 March 1982 LER 82-003/01T-0:on 820208,sample of Standby Liquid Control Boron Concentration Below Tech Spec Limits.Investigation in Progress.Administrated Limit & Sampling Frequency Increased ML20041F9281982-03-0303 March 1982 LER 82-002/03L-0:on 820206,ac Ground & Blown Fuse Alarms Activated,Rendering Trouble Alarm UPS-B Inoperable.Caused by Blown Fuse M Transient Suppression Circuit Due to Shorted Out Capacitor Off Board 2A 17 ML20041D7771982-02-25025 February 1982 LER 82-001/03L-0:on 820128,IRM Channel B Declared Inoperable.Caused by Failed Voltage Pre AMP (GE 112C-2218G001).Half Scram Manually Initiated.Component Will Be Repaired Prior to Entering IRM Range ML20041D4281982-02-22022 February 1982 LER 82-003/01P-0:on 820220,after Addition of Water to SLC Tank,Solution Sample Found Boron Concentration Below Required Amounts.Cause Unknown.Administrative Limit for Concentration Will Be Increased & Addl Sampling Conducted ML20040E2581982-01-26026 January 1982 LER 81-037/03L-0:on 811227,while Attempting to Start RHRSW Pump P-8-1A,breaker Tripped Contrary to Tech Specs.Caused by Worn Bushings on Operating Mechanism.Circuit Breaker Replaced.Breaker Mfg by Ge,Model Am 4.16 250-8HB ML20040C6971982-01-16016 January 1982 LER 81-036/03L-0:on 811217,containment Isolation Valve CU-15 Failed to Seat Satisfactorily Per Tech Spec 4.7.D.1 During Quarterly Surveillance Testing.Caused by Failure of Closing Torque Switch.Torque Switch Will Be Replaced Next Shutdown ML20040B1941981-12-30030 December 1981 Updated 81-028/03X-1:on 811017,field Breaker Failed to Open, Effectively Disabling Rrmg Set Recirculation Pump Trip Instrumentation.Caused by Binding of Operating Mechanism.New Breaker Installed ML20039F0101981-12-30030 December 1981 LER 81-035/03L-0:on 811204,during Core Spray Valve Test, Breaker for V14-11A Tripped & Reactor Shutdown Commenced. Caused by Breaker Not Latching When Closed,Allowing Breaker to Trip Below Setpoint.Breaker Replaced ML20039C2991981-12-18018 December 1981 LER 81-032/03L-0:on 811120,valves RWCU 68 & 15 Found to Have Seat Leakages Exceeding Tech Spec Range.Cause Not Stated. Disc Replaced & Valves Satisfactorily Retested ML20039C3071981-12-18018 December 1981 LER 81-034/03L-0:on 811121,operating Cycle Test of Standby Gas Treatment HEPA Filters Found Not to Have Been Done Since Sept 1979.Caused by Failure to Include Test on Dept Surveillance List.Test Completed & Schedule Revised ML20039C1121981-12-17017 December 1981 Updated LER 81-011/03X-1:on 810507,leak Discovered in Socket Weld Reducing Fitting.Caused by Intergranular Stress Corrosion Cracking.All Similar Fittings Replaced W/Differently Designed Fitting Less Susceptible to Failure ML20039C3821981-12-17017 December 1981 Updated LER 81-016/03X-1:on 810622,small Leak Found in Socket Weld Reducing Fitting in Vent Line of Regenerative Heat Exchanger E-15-1A.Caused by Intergranular Stress Corrosion Cracking Due to Wetting of Asbestos Insulation ML20039B1281981-12-0909 December 1981 LER 81-033/01T-0:on 811125,reactor Bldg Roof Hatch Opened by Work Crew W/O Notice to Supervisor Until Fire Permit for Welding Requested.Caused by Personnel Error.Personnel Reinstructed Re Procedural Requirement 1994-04-29 Category:TEXT-SAFETY REPORT MONTHYEARML20217L8831999-10-21021 October 1999
[Table view]Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30 |
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