ML19248D769
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| ML19248D769 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/09/1979 |
| From: | Mitchell D METROPOLITAN EDISON CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19248D767 | List: |
| References | |
| LER-79-015-01T, LER-79-15-1T, NUDOCS 7908170430 | |
| Download: ML19248D769 (2) | |
Similar Documents at Three Mile Island | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046C1101993-08-0202 August 1993
[Table view]LER 93-006-00:on 930701,lube Oil Accumulation Discovered on EDG EG-Y-1B Due to Inadequate Maint.Edg Removed from Svc & Leak Repaired by Retorquing Filter Housing bolts.W/930802 Ltr ML20045B3161993-06-0909 June 1993 LER 93-005-00:on 930510,discovered That Surveillance Procedure Sp 1301-8.1, Reactor Bldg Annual Insp Not Performed by Required Completion Date of 930402.Caused by Lack of Mgt Oversight.Tracking Mechanism Developed ML20045A0271993-06-0101 June 1993 LER 93-004-00:on 930503,plant Process Computer Malfunction Event Occurred Due to Suspected Hardware Problem.Cause of Malfunction Not Revealed.Computer Sys Software Change Has Been implemented.W/930601 Ltr ML20044A9551990-07-0909 July 1990 LER 90-003-01:on 900227,turbine Bypass Valves Isolated During Plant Heatup Due to Main Steam Valve Closure.Caused by Personnel Error.Personnel Reviewed Event to Emphasize Need to Follow Administrative requirements.W/900709 Ltr ML20012E5981990-03-27027 March 1990 LER 90-003-00:on 900227,isolation of Turbine Bypass Valves Due to Main Steam Valve Closure.Caused by Personnel Error. Personnel Will Review Event in Order to Emphasize Need to Follow Proper administration.W/900327 Ltr ML20011E4261990-02-0606 February 1990 LER 90-001-00:on 900107,inadvertent Trip of Reactor Protection Sys Occurred,Followed by Inadvertent Engineered Safeguards Actuation Sys Actuation.Caused by Inadequate Procedural Detail.Procedure Improvements made.W/900206 Ltr ML20011D4551989-12-21021 December 1989 LER 89-003-00:on 891129,rapid Reduction in Turbine Load Occurred Resulting in High Temp & Pressure in RCS & Reactor Trip.Caused by Loose Shield Wire on Input to Speed Error Circuit.Connections in EHC Cabinet checked.W/891221 Ltr ML19332F9681989-12-12012 December 1989 LER 89-002-00:on 891114,discovered That Radiator Fan Right Angle Gear Drive Bearing Lubrication Inadequate Due to Formation of Sludge in Lubrication Lines.Procedure Revised to Increase Maint on Lubrication sys.W/891212 Ltr ML19332F4551989-11-30030 November 1989 LER 89-001-00:on 891030,operator Error Resulted in Inadvertent Actuation of Es Components B.No Equipment Was Damaged & Vol of Water Injected Into RCS Minimal.Operators counseled.W/891130 Ltr ML20023D5011983-05-0606 May 1983 LER 83-012/03L-0:on 830406,while Performing Functional Testing of Hydraulic Snubbers,Snubber MS-209 Failed to Lock in Tension Direction.Caused by Damaged Piston Seal Ring. Snubber Overhauled & Tested Satisfactorily ML20028G3771983-02-0101 February 1983 LER 83-001/03L-0:on 830101,during Reactor Bldg Purge,Station Radiation Monitor RM-A9,iodine Channel,Failed.Caused by Single Channel Analyzer Circuit Board Failure.Circuit Board Replaced & Quarterly Calibr Performed ML20027B8301982-09-17017 September 1982 LER 82-012/01T-0:on 820902,after Surveillance for Station Liquid Effluent Monitor (RML-7),discovered That Alarm Setpoint Improperly Calculated Since Implementation of Nov 1981 License Amend 72.Caused by Personnel Error ML20052J0661982-05-13013 May 1982 Updated LER 81-011/01T-2:on 811019,determined That Catwalk Structure Used to Support safety-related Components Not Adequately Designed for Seismic Loads.No Seismic Design Calculations Performed by Ae.Repairs Completed by Restart ML20052G4581982-05-10010 May 1982 LER 82-005/03L-0:on 820411,while in Ordered Shutdown,Liquid Effluent Radiation Monitor Discovered Inoperable.Caused by Failure of Pump SR-P4,due to Piping Clogged W/Mud.Piping Cleared & Motor Replaced ML20051Q5741982-04-29029 April 1982 LER 82-004/01T-0:on 820413,during Shutdown & Tests Conducted Per NUREG-0737,Item II.D.1,EPRI Valve Test Results Indicated Potential Problem W/Pressurizer Code Safety Valves (Dresser Model 31739A).Evaluation Continuing ML20050D5411982-03-31031 March 1982 LER 82-003/01T-0:on 820318,while Regenerating B String Cation & Anion Deep Bed Demineralizers,Rinse Cycles Filled Secondary Neutralizing Tank (Snt) Causing Snt to Overflow Caused by Operator Error.Procedures Revised ML20050A4711982-03-17017 March 1982 LER 82-001/01T-0:on 820225,computer Room Air Conditioning Unit Found W/O Shutdown Radiation Signal & W/Potential for Contaminated Air Flow,Contrary to TMI Item III.D.3.4. Long-term Corrective Action to Be Provided by 820630 ML20052G0451982-02-25025 February 1982 LER 82-001:on 820225,discovered That Potential for Allowing Contaminated Air from Fuel Handling Bldg to Area Served by Control Room Ventilation Sys Exists Due to Ductwork Penetrating Wall Between Control & Fuel Handling Bldgs ML20040B3421982-01-0606 January 1982 LER 81-014/01T-0:on 811223,during IE Bulletin 79-02/14 Insps of Pipe Supports,Nine Structural Interfacing Areas Were Identified as-built in Nonconformance to Original Design Areas in Final Stages of Mod.Reanalysis Initiated ML20039B0571981-12-0909 December 1981 LER 81-013/01T-0:on 811125,tests on a once-through Steam Generator Indicated 88 Tube Leaks of Approx 0.2 to 0.3 Gpm at Reactor Coolant Pressurization of Approx 45 Psig. Investigation to Identify Cause Continues ML20038D0011981-11-30030 November 1981 LER 81-012/04L-0:on 811116,ETS 2.2.1.a,limiting Condition for Riverwater Chlorination,Was Exceeded.Caused by Malfunctioning Timing Device.Faulty Timer Repaired.Tech Spec Change Request 100A Allows Condition to Equal NPDES Permit ML20040D6311981-11-10010 November 1981 Updated LER 81-010/03L-1:on 811008,QC Audit Showed One of 21 Reactor Bldg Prestressing Tendons Inspected During 1980 Surveillance Had Low Liftoff Force.Caused by Use of Incorrect Calibr Data.Procedure Being Rewritten ML20040D6351981-11-0404 November 1981 Updated LER 81-011/01T-1:on 811019,determined That Catwalk Structure,Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Did Not Meet Seismic Criteria. Caused by Ae Failure to Perform Calculations ML20009E6771981-07-0808 July 1981 LER 81-007/99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified ML20039E2701981-06-10010 June 1981 LER 81-006/03L-0:on 810507,corrosion on Diesel Fire Pump Battery Terminals Noted.Caused by Failure to Include Surveillance in Computer Tracking Sys.Surveillance Entry Into Computer Data Base Verified ML19347E3071981-04-20020 April 1981 LER 81-001/03L-1:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17 During Limited Plant Heatup.Caused by Flange Socket Fillet Weld Failure Due to fabrication-induced Crack in Root of Weld ML19350C7871981-03-30030 March 1981 LER 81-004/03L-0:on 810324,during Refueling Interval Functional Testing of Hydraulic Snubbers,Snubber RC-21/MUE-43 Discovered W/Shipping Plug Installed in Fluid Reservoir Vent Port.Caused by Procedure Violation ML19347D3981981-03-13013 March 1981 LER 80-013/03L-1:on 800715,pressurizer Code Safety Valve, RC-RV1B,lifted Below Tech Spec Limits.Cause Not Determined. Addl Testing Planned to Verify Site Heated Nitrogen Test Procedure Yields Results Comparable to Steam Pop Test ML19347D4171981-03-12012 March 1981 LER 81-003/03L-0:on 810210,new Penetration in Fire Wall Between Engineered Safeguards Actuation Sys,Fire Area CB-3C & Relay Room,Fire Area CB-3D,found Necessary for New Cable Routing for Mods on Containment Isolation RM-5C ML20003C6161981-03-0202 March 1981 LER 81-002/03L-0:on 810130,three Snubbers Failed to Lock Up as Required by Tech Spec.Caused by Worn Piston Ring Seals & Springs W/Excessive Spring Constants.Snubber Seals,Pistons, Valve Blocks & Weight Springs Replaced ML20003B6441981-02-18018 February 1981 LER 81-001/03L-0:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17.Leak on Flow Instrument Possibly Caused by Localized Pitting Attack.Leak on Socket Weld Caused by Initial Root Weld Defect.Components Removed ML19341A9411981-01-23023 January 1981 LER 80-016 Has Been Cancelled ML19341A7021981-01-22022 January 1981 Updated LER 78-001/01T-2:on 780106 B&W Identified Transients Which May Result in Exceeding DNBR on Kw/Ft Safety Limits. Caused by Positive Difference Between Indicated Reactor Power Subtracted from Actual Reactor Power ML19340D7331980-12-24024 December 1980 LER 80-019/03L-0:on 801126,A & B Battery Room Smoke Detector Monthly Surveillance Test Not Performed.Caused by Inadequate Implementation of Administrative Controls.Surveillance Modified ML19339B6771980-11-0404 November 1980 LER 80-018/01T-0:on 801017,while Replacing Coils for Asco Solenoid Valves Per IE Bulletin 79-01A,coils Were Discovered to Conflict W/Station Voltage Range.Caused by Incorrect Purchase Order for Coils ML19347B6471980-10-0808 October 1980 LER 80-017/01T-0:on 800923,during Review,Per IE Bulletin 79-01b,documentation to Demonstrate That Breaks on Motor Operators on Purge Valves AH-V1B/C & safety-related Valves DH-V5A/B Re Environ Qualified Found Insufficient ML19344F0501980-09-0909 September 1980 LER 80-015/04T-1:on 800721,w/unit in Cold Shutdown,Actual River Water Temp Change Exceeded Limit for Approx 6-h. Caused by Calculation Error in Instrument Loop Used to Measure River Water Outlet Temp ML19344A6881980-08-18018 August 1980 LER 80-013/03L-0:on 800715,during Pressurizer Code Safety Valve Setpoint Verification,Found RC-RV1B at Low Release Setting.Possibly Caused by Leaks within Site Testing Equipment Prior to Installation ML19331C7771980-08-14014 August 1980 LER 80-015/04T-0:on 800721,while Units Were in Cold Shutdown Condition,Actual River Water Temp Exceeded Tech Spec Limits for 6-h.Caused by Inaccurate Compensation for Resistance Temp Detector Lead Resistance During Calibr ML19331C7421980-08-14014 August 1980 LER 80-014/03L-0:on 800715,during Insp,Snubber NSE-151 Had Low Fluid Level & Failed Functional Test.Possibly Caused by Leakage Past Seal Damaged During Installation.Seals Replaced & Snubber Passed Functional Test ML19330C7521980-08-0404 August 1980 LER 80-008/99X-1:on 800430,during Insp of Emergency Diesel Generator A,Bearing Insulation Determined to Have Deteriorated.Caused by Normal Aging or from Heating of Lube Oil.Insulation Repaired & Oil Changed.Diagram Encl ML19320C3001980-07-11011 July 1980 LER 80-011/03L-0:on 800610,reactor Bldg Spray Sys Compressed Air Test Exceeded Late Date.Caused by Incorrect Date Being Entered Into Surveillance Data Tracking Sys.Info Corrected. Review of Infrequent Surveillances Will Be Performed ML19320C2541980-07-11011 July 1980 LER 80-012/01T-0:on 800627,during Review of Environ Qualification of Equipment Required to Operate During Main Steam Line Break Per IE Bulletin 79-01B,found That post- Accident Analysis Exceeded Previous Figures ML19318D2231980-07-0303 July 1980 Revised LER 80-004/01T-1:on 800306,errors Found in Seismic Analysis of Common Decay Heat Suction Piping Associated W/ Valves DH-V1 & DH-V2.Seismic Analysis Corrected & Mods Made to DH-V2.Mods to DH-V1 to Be Completed by 801015 ML19318D0441980-06-30030 June 1980 LER 80-010/01T-0:on 800606,licensee Received Ltr Stating FSAR Does Not Assume That Radioactive Release Paths Exist Via Main Safety Valves or Emergency Feed Pump Turbine Exhaust.Caused by Implementation of Small Break Guidelines ML19318D0831980-06-30030 June 1980 LER 80-008/99X-0:on 800430,during Annual Insp of a Emergency Diesel Generator,Bearing Insulation Determined Deteriorated. Caused by Normal Aging or Heating Bearing Lube Oil. Insulation Replaced & Lower Viscosity Oil Used ML19318C0531980-06-25025 June 1980 LER 80-009/03L-0:on 800607,reactor Bldg Tendon Surveillance Late Date Was Exceeded.Caused by Problems W/Availability of Contractor Equipment.Surveillance Continuing ML19323G6381980-05-30030 May 1980 Revised LER 80-001/01X-1:on 800123,results of Load Study Performed on Es Busses Determined Overload Could Exist on 1P & 1S Busses Upon Loss of Es Channel & One of Four Situations.Caused by Inadequate Design ML19323C4001980-05-0808 May 1980 LER 80-007/01T-0:on 800423,results of Radiographic Exam of Piping Welds for Leak Rate Test Sys Disclosed That 8 Out of 17 Welds Did Not Meet Acceptance Stds of Power Piping Code. Caused by Lack of Preservice Exam ML19305E3341980-04-0808 April 1980 LER 80-006/01T-0:on 800325,during Periodic Reactor Bldg Local Leak Rate Testing,Containment Isolation Valve RB-V7 Had Excessive Leakage.Cause Suspected to Be Seat Damage. Improved Valve Placed on Order 1993-08-02 Category:RO) MONTHYEARML20046C1101993-08-0202 August 1993
[Table view]LER 93-006-00:on 930701,lube Oil Accumulation Discovered on EDG EG-Y-1B Due to Inadequate Maint.Edg Removed from Svc & Leak Repaired by Retorquing Filter Housing bolts.W/930802 Ltr ML20045B3161993-06-0909 June 1993 LER 93-005-00:on 930510,discovered That Surveillance Procedure Sp 1301-8.1, Reactor Bldg Annual Insp Not Performed by Required Completion Date of 930402.Caused by Lack of Mgt Oversight.Tracking Mechanism Developed ML20045A0271993-06-0101 June 1993 LER 93-004-00:on 930503,plant Process Computer Malfunction Event Occurred Due to Suspected Hardware Problem.Cause of Malfunction Not Revealed.Computer Sys Software Change Has Been implemented.W/930601 Ltr ML20044A9551990-07-0909 July 1990 LER 90-003-01:on 900227,turbine Bypass Valves Isolated During Plant Heatup Due to Main Steam Valve Closure.Caused by Personnel Error.Personnel Reviewed Event to Emphasize Need to Follow Administrative requirements.W/900709 Ltr ML20012E5981990-03-27027 March 1990 LER 90-003-00:on 900227,isolation of Turbine Bypass Valves Due to Main Steam Valve Closure.Caused by Personnel Error. Personnel Will Review Event in Order to Emphasize Need to Follow Proper administration.W/900327 Ltr ML20011E4261990-02-0606 February 1990 LER 90-001-00:on 900107,inadvertent Trip of Reactor Protection Sys Occurred,Followed by Inadvertent Engineered Safeguards Actuation Sys Actuation.Caused by Inadequate Procedural Detail.Procedure Improvements made.W/900206 Ltr ML20011D4551989-12-21021 December 1989 LER 89-003-00:on 891129,rapid Reduction in Turbine Load Occurred Resulting in High Temp & Pressure in RCS & Reactor Trip.Caused by Loose Shield Wire on Input to Speed Error Circuit.Connections in EHC Cabinet checked.W/891221 Ltr ML19332F9681989-12-12012 December 1989 LER 89-002-00:on 891114,discovered That Radiator Fan Right Angle Gear Drive Bearing Lubrication Inadequate Due to Formation of Sludge in Lubrication Lines.Procedure Revised to Increase Maint on Lubrication sys.W/891212 Ltr ML19332F4551989-11-30030 November 1989 LER 89-001-00:on 891030,operator Error Resulted in Inadvertent Actuation of Es Components B.No Equipment Was Damaged & Vol of Water Injected Into RCS Minimal.Operators counseled.W/891130 Ltr ML20023D5011983-05-0606 May 1983 LER 83-012/03L-0:on 830406,while Performing Functional Testing of Hydraulic Snubbers,Snubber MS-209 Failed to Lock in Tension Direction.Caused by Damaged Piston Seal Ring. Snubber Overhauled & Tested Satisfactorily ML20028G3771983-02-0101 February 1983 LER 83-001/03L-0:on 830101,during Reactor Bldg Purge,Station Radiation Monitor RM-A9,iodine Channel,Failed.Caused by Single Channel Analyzer Circuit Board Failure.Circuit Board Replaced & Quarterly Calibr Performed ML20027B8301982-09-17017 September 1982 LER 82-012/01T-0:on 820902,after Surveillance for Station Liquid Effluent Monitor (RML-7),discovered That Alarm Setpoint Improperly Calculated Since Implementation of Nov 1981 License Amend 72.Caused by Personnel Error ML20052J0661982-05-13013 May 1982 Updated LER 81-011/01T-2:on 811019,determined That Catwalk Structure Used to Support safety-related Components Not Adequately Designed for Seismic Loads.No Seismic Design Calculations Performed by Ae.Repairs Completed by Restart ML20052G4581982-05-10010 May 1982 LER 82-005/03L-0:on 820411,while in Ordered Shutdown,Liquid Effluent Radiation Monitor Discovered Inoperable.Caused by Failure of Pump SR-P4,due to Piping Clogged W/Mud.Piping Cleared & Motor Replaced ML20051Q5741982-04-29029 April 1982 LER 82-004/01T-0:on 820413,during Shutdown & Tests Conducted Per NUREG-0737,Item II.D.1,EPRI Valve Test Results Indicated Potential Problem W/Pressurizer Code Safety Valves (Dresser Model 31739A).Evaluation Continuing ML20050D5411982-03-31031 March 1982 LER 82-003/01T-0:on 820318,while Regenerating B String Cation & Anion Deep Bed Demineralizers,Rinse Cycles Filled Secondary Neutralizing Tank (Snt) Causing Snt to Overflow Caused by Operator Error.Procedures Revised ML20050A4711982-03-17017 March 1982 LER 82-001/01T-0:on 820225,computer Room Air Conditioning Unit Found W/O Shutdown Radiation Signal & W/Potential for Contaminated Air Flow,Contrary to TMI Item III.D.3.4. Long-term Corrective Action to Be Provided by 820630 ML20052G0451982-02-25025 February 1982 LER 82-001:on 820225,discovered That Potential for Allowing Contaminated Air from Fuel Handling Bldg to Area Served by Control Room Ventilation Sys Exists Due to Ductwork Penetrating Wall Between Control & Fuel Handling Bldgs ML20040B3421982-01-0606 January 1982 LER 81-014/01T-0:on 811223,during IE Bulletin 79-02/14 Insps of Pipe Supports,Nine Structural Interfacing Areas Were Identified as-built in Nonconformance to Original Design Areas in Final Stages of Mod.Reanalysis Initiated ML20039B0571981-12-0909 December 1981 LER 81-013/01T-0:on 811125,tests on a once-through Steam Generator Indicated 88 Tube Leaks of Approx 0.2 to 0.3 Gpm at Reactor Coolant Pressurization of Approx 45 Psig. Investigation to Identify Cause Continues ML20038D0011981-11-30030 November 1981 LER 81-012/04L-0:on 811116,ETS 2.2.1.a,limiting Condition for Riverwater Chlorination,Was Exceeded.Caused by Malfunctioning Timing Device.Faulty Timer Repaired.Tech Spec Change Request 100A Allows Condition to Equal NPDES Permit ML20040D6311981-11-10010 November 1981 Updated LER 81-010/03L-1:on 811008,QC Audit Showed One of 21 Reactor Bldg Prestressing Tendons Inspected During 1980 Surveillance Had Low Liftoff Force.Caused by Use of Incorrect Calibr Data.Procedure Being Rewritten ML20040D6351981-11-0404 November 1981 Updated LER 81-011/01T-1:on 811019,determined That Catwalk Structure,Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Did Not Meet Seismic Criteria. Caused by Ae Failure to Perform Calculations ML20009E6771981-07-0808 July 1981 LER 81-007/99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified ML20039E2701981-06-10010 June 1981 LER 81-006/03L-0:on 810507,corrosion on Diesel Fire Pump Battery Terminals Noted.Caused by Failure to Include Surveillance in Computer Tracking Sys.Surveillance Entry Into Computer Data Base Verified ML19347E3071981-04-20020 April 1981 LER 81-001/03L-1:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17 During Limited Plant Heatup.Caused by Flange Socket Fillet Weld Failure Due to fabrication-induced Crack in Root of Weld ML19350C7871981-03-30030 March 1981 LER 81-004/03L-0:on 810324,during Refueling Interval Functional Testing of Hydraulic Snubbers,Snubber RC-21/MUE-43 Discovered W/Shipping Plug Installed in Fluid Reservoir Vent Port.Caused by Procedure Violation ML19347D3981981-03-13013 March 1981 LER 80-013/03L-1:on 800715,pressurizer Code Safety Valve, RC-RV1B,lifted Below Tech Spec Limits.Cause Not Determined. Addl Testing Planned to Verify Site Heated Nitrogen Test Procedure Yields Results Comparable to Steam Pop Test ML19347D4171981-03-12012 March 1981 LER 81-003/03L-0:on 810210,new Penetration in Fire Wall Between Engineered Safeguards Actuation Sys,Fire Area CB-3C & Relay Room,Fire Area CB-3D,found Necessary for New Cable Routing for Mods on Containment Isolation RM-5C ML20003C6161981-03-0202 March 1981 LER 81-002/03L-0:on 810130,three Snubbers Failed to Lock Up as Required by Tech Spec.Caused by Worn Piston Ring Seals & Springs W/Excessive Spring Constants.Snubber Seals,Pistons, Valve Blocks & Weight Springs Replaced ML20003B6441981-02-18018 February 1981 LER 81-001/03L-0:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17.Leak on Flow Instrument Possibly Caused by Localized Pitting Attack.Leak on Socket Weld Caused by Initial Root Weld Defect.Components Removed ML19341A9411981-01-23023 January 1981 LER 80-016 Has Been Cancelled ML19341A7021981-01-22022 January 1981 Updated LER 78-001/01T-2:on 780106 B&W Identified Transients Which May Result in Exceeding DNBR on Kw/Ft Safety Limits. Caused by Positive Difference Between Indicated Reactor Power Subtracted from Actual Reactor Power ML19340D7331980-12-24024 December 1980 LER 80-019/03L-0:on 801126,A & B Battery Room Smoke Detector Monthly Surveillance Test Not Performed.Caused by Inadequate Implementation of Administrative Controls.Surveillance Modified ML19339B6771980-11-0404 November 1980 LER 80-018/01T-0:on 801017,while Replacing Coils for Asco Solenoid Valves Per IE Bulletin 79-01A,coils Were Discovered to Conflict W/Station Voltage Range.Caused by Incorrect Purchase Order for Coils ML19347B6471980-10-0808 October 1980 LER 80-017/01T-0:on 800923,during Review,Per IE Bulletin 79-01b,documentation to Demonstrate That Breaks on Motor Operators on Purge Valves AH-V1B/C & safety-related Valves DH-V5A/B Re Environ Qualified Found Insufficient ML19344F0501980-09-0909 September 1980 LER 80-015/04T-1:on 800721,w/unit in Cold Shutdown,Actual River Water Temp Change Exceeded Limit for Approx 6-h. Caused by Calculation Error in Instrument Loop Used to Measure River Water Outlet Temp ML19344A6881980-08-18018 August 1980 LER 80-013/03L-0:on 800715,during Pressurizer Code Safety Valve Setpoint Verification,Found RC-RV1B at Low Release Setting.Possibly Caused by Leaks within Site Testing Equipment Prior to Installation ML19331C7771980-08-14014 August 1980 LER 80-015/04T-0:on 800721,while Units Were in Cold Shutdown Condition,Actual River Water Temp Exceeded Tech Spec Limits for 6-h.Caused by Inaccurate Compensation for Resistance Temp Detector Lead Resistance During Calibr ML19331C7421980-08-14014 August 1980 LER 80-014/03L-0:on 800715,during Insp,Snubber NSE-151 Had Low Fluid Level & Failed Functional Test.Possibly Caused by Leakage Past Seal Damaged During Installation.Seals Replaced & Snubber Passed Functional Test ML19330C7521980-08-0404 August 1980 LER 80-008/99X-1:on 800430,during Insp of Emergency Diesel Generator A,Bearing Insulation Determined to Have Deteriorated.Caused by Normal Aging or from Heating of Lube Oil.Insulation Repaired & Oil Changed.Diagram Encl ML19320C3001980-07-11011 July 1980 LER 80-011/03L-0:on 800610,reactor Bldg Spray Sys Compressed Air Test Exceeded Late Date.Caused by Incorrect Date Being Entered Into Surveillance Data Tracking Sys.Info Corrected. Review of Infrequent Surveillances Will Be Performed ML19320C2541980-07-11011 July 1980 LER 80-012/01T-0:on 800627,during Review of Environ Qualification of Equipment Required to Operate During Main Steam Line Break Per IE Bulletin 79-01B,found That post- Accident Analysis Exceeded Previous Figures ML19318D2231980-07-0303 July 1980 Revised LER 80-004/01T-1:on 800306,errors Found in Seismic Analysis of Common Decay Heat Suction Piping Associated W/ Valves DH-V1 & DH-V2.Seismic Analysis Corrected & Mods Made to DH-V2.Mods to DH-V1 to Be Completed by 801015 ML19318D0441980-06-30030 June 1980 LER 80-010/01T-0:on 800606,licensee Received Ltr Stating FSAR Does Not Assume That Radioactive Release Paths Exist Via Main Safety Valves or Emergency Feed Pump Turbine Exhaust.Caused by Implementation of Small Break Guidelines ML19318D0831980-06-30030 June 1980 LER 80-008/99X-0:on 800430,during Annual Insp of a Emergency Diesel Generator,Bearing Insulation Determined Deteriorated. Caused by Normal Aging or Heating Bearing Lube Oil. Insulation Replaced & Lower Viscosity Oil Used ML19318C0531980-06-25025 June 1980 LER 80-009/03L-0:on 800607,reactor Bldg Tendon Surveillance Late Date Was Exceeded.Caused by Problems W/Availability of Contractor Equipment.Surveillance Continuing ML19323G6381980-05-30030 May 1980 Revised LER 80-001/01X-1:on 800123,results of Load Study Performed on Es Busses Determined Overload Could Exist on 1P & 1S Busses Upon Loss of Es Channel & One of Four Situations.Caused by Inadequate Design ML19323C4001980-05-0808 May 1980 LER 80-007/01T-0:on 800423,results of Radiographic Exam of Piping Welds for Leak Rate Test Sys Disclosed That 8 Out of 17 Welds Did Not Meet Acceptance Stds of Power Piping Code. Caused by Lack of Preservice Exam ML19305E3341980-04-0808 April 1980 LER 80-006/01T-0:on 800325,during Periodic Reactor Bldg Local Leak Rate Testing,Containment Isolation Valve RB-V7 Had Excessive Leakage.Cause Suspected to Be Seat Damage. Improved Valve Placed on Order 1993-08-02 Category:TEXT-SAFETY REPORT MONTHYEARML20217K4701999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30 |
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