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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20042F3261990-05-0404 May 1990 LER 90-005-00:on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing conducted.W/900504 Ltr ML20024B7221983-07-0101 July 1983 LER 83-015/03L-0:on 830606,during Valve Timing Test for Td Auxiliary Feedwater Pump,Valve Failed to Electrically Open. Caused by Faulty Torque Switch & Maladjusted Tripper Cam. Valve Operator Rebuilt & Cam reset.W/830701 Ltr ML20024B7291983-07-0101 July 1983 LER 83-014/03L-0:on 830603,while Performing Monthly RHR Pump & Valve Surveillance Test,Containment Sump B Isolation Valve SI-350B Would Not Cycle Closed.Caused by Mechanical Interlock Sticking in Open position.W/830701 Ltr ML20023C3681983-05-0606 May 1983 Updated LER 82-030/01X-2:on 821004,sensing Lines on Six safety-related Containment Pressure Transmitters Found Capped Off Inside Containment.Caused by Personnel Error During Maint.Caps Removed ML20028F4361983-01-14014 January 1983 LER 82-035/03L-1:on 821216,during Full Power Operation, Pinhole Leak Discovered in Suction Line from Vol Control Tank to Charging Pumps.Caused by Vibrations & Pulsations in Associated Piping.Leak Plugged ML20028E3821983-01-14014 January 1983 LER 82-035/03L-0:on 821216,pinhole Leak Discovered in Suction Line from Vol Control Tank to Charging Pumps.Caused by Vibrations in Piping.Leak Plugged & Piping to Be Replaced During Next Refueling Outage ML20052G7351982-05-10010 May 1982 LER 82-009/03L-0:on 820410,w/unit at Hot Shutdown Prior to Scheduled Refueling Outage,Both Source Range Nuclear Instruments Were Inoperable.Caused by Accumulation of Water in Instrument Canisters.Spare Detector Installed ML20052G1381982-05-0606 May 1982 LER 82-008/01T-0:on 820422,during Refueling Outage,Leak Repair Procedures on Valve SI-13B Revealed Significant Boric Acid Corrosion Wastage of body-to-bonnet Bolts.Caused by Bolt Degradation.Affected Bolts Replaced ML20052G1401982-05-0606 May 1982 LER 82-007/01T-0:on 820422,during Refueling Outage,Leak Repair Procedures on Valve PS-1A Revealed Significant Boric Acid Corrosion Wastage on body-to-bonnet Bolts.Caused by Bolt Degradation.Affected Bolts Replaced ML20052G7251982-04-0707 April 1982 LER 82-005/03X-1:on 820309,during Quarterly Surveillance Testing of Svc Water pumps,IA2 Svc Water Pump Failed to Start on Demand.Circuit Breaker Failed to Close by Remote Initiation.Caused by Failed Open Closing Coil.Coil Replaced ML20041B3791982-02-15015 February 1982 LER 82-003/03L-0:on 820116,1A Zone SV Fan Started Automatically.Caused by Solenoid Valve Failure Due to Burned Out Coil in Closed Position Which Automatically Opened Damper.Coil Replaced & Sys Tested Satisfactorily ML20041B3601982-02-12012 February 1982 LER 82-002/03L-0:on 820114,deviation in Pressurizer (Pzr) Level Indication Noted.Caused by Instrument Calibr Out of Spec.Transmitter Recalibr ML20040G6081982-02-0505 February 1982 LER 82-001/03L-0:on 820108,during Operability Check of Zone Special Ventilation,Exhaust Fan 1B Failed to Start.Caused by Failure of Solenoid Valve Due to Sticking Solenoid.Valve Replaced & Sys Tested.Design Change Initiated ML20040F3571982-02-0101 February 1982 LER 81-039/03X-1:on 811218,leaking Weld on Discharge Side of 1C Charging Pump Relief valve,CVC-101C,discovered.Caused by Vibrations & Pulsations in Associated Piping.Pipe Section Replaced.Design Change in Progress ML20040A5771982-01-15015 January 1982 LER 81-039/03L-0:on 811218,found Leaking Weld on Discharge Side of 1C Charging Pump Relief Valve CVC-101C.Caused by Weld Fatigue Attributed to Vibrations & Pulsations in Associated Piping.Pipe Replaced.Design Change in Progress ML20039B1831981-12-11011 December 1981 LER 81-038/03L-0:on 811113,during Surveillance Testing on Shield Bldg Vent Sys,Check Damper SBV-10A Failed Shut.Caused by Ruptured Diaphragm Which Separates Motor from Oil Reservoir.Motor Replaced ML20038C2621981-12-0303 December 1981 LER 81-036/03L-0:on 811103,motor-driven Auxiliary Feedwater Pump Lubricator Oil Pump Continued to Run When Pump 1A Was Stopped.Caused by Excessive Wear & Misalignment of Auxiliary Switch Linkage Mechanism Allowing Switch to Remain Closed ML20038B0011981-11-17017 November 1981 LER 81-034/03L-0:on 811018,during Normal operations,1B Zone SV Fan Started Automatically.Caused by Solenoid Failure Due to Burned Out Coil in Safe Position Automatically Starting Fan & Opening Damper.Coil Replaced ML20038B0221981-11-16016 November 1981 LER 81-015/03L-2:on 810510,during Refueling Shutdown,Steam Flow Transmitter Was Out of Calibr Resulting in Less Conservative Hi & hi-hi Steam Flow than Required.Caused by Instrument Drift ML20011A5521981-10-0202 October 1981 LER 81-030/03L-0:on 810903,surveillance Procedure Found to Incorrectly Measure Shield Bldg Vent Sys Exhaust Flow from Annulus.Caused by Surveillance Procedures Written to Demonstrate Original Design Criteria ML20010F5071981-08-28028 August 1981 LER 81-024/03L-0:on 810730,low Boric Acid Heat Tracing Temp Detected on Section of Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Removal of Insulation from Boric Acid Heat Tracing Circuits to Permit Maint ML20010F3421981-08-28028 August 1981 LER 81-025/03L-0:on 810807,safety Injection High Containment Pressure Setpoint Discovered to Be Less Conservative than Required by Tech Spec Due to Foxboro Containment Pressure Transmitter Out of Calibr.Caused by Instrument Drift ML20009E6621981-07-21021 July 1981 LER 81-023/03L-0:on 810621,boric Acid Found Leaking from Instrument Isolation Valve CVC-11188.Caused by Leaking Diaphragm & Corroded Bonnet.Transfer Pump 1A Isolated & Bonnet Assembly Replaced ML20009D5531981-07-17017 July 1981 LER 81-022/03L-0:on 810619,spent Fuel Pool Boron Sampling Not Performed within Allotted Time Frame During Steady State Operation.Caused by Temporary Work Load Increase on Chemistry Staff.Sample Taken & Analyzed ML20009C5651981-07-10010 July 1981 LER 81-021/03L-0:on 810611,found Visual Verification of Valve Motion & Limit Switch Not Performed During Refueling Outage for Valves Inaccessible During Normal Operation Per Iwv 3300 of 1974 ASME Code.Caused by Procedural Oversight ML20009A9381981-07-0606 July 1981 LER 81-020/03L-0:on 810606,condensate Water Storage Tank Level Went Below Tech Spec Limit.Caused by Normal Tank Water Usage During Startup & Turbine Testing Coincident W/ Demineralizer Regeneration ML20009A8631981-07-0303 July 1981 LER 81-019/03L-0:on 810605,during Refueling Outage,Portable Radiation Survey Instrument Checks for May Not Performed Per Tech Specs.Caused by Oversight Due to Reassignment of Personnel.Instruments Will Be Source Checked in June ML20009B5381981-06-15015 June 1981 LER 81-018/03L-0:on 810516,testing Indicated That Low Pressure Safety Injection & Reactor Trip Were Below Tech Spec Limits for Pressure Transmitters.Caused by Instrument Drift.Sensing Lines Flushed.Amplifier Replaced ML20009B5351981-06-12012 June 1981 LER 81-017/03L-0:on 810515,discovered That High Pressure Reactor Trip Setpoints for Pressure Transmitters Were Higher than Tech Spec.Caused by Setpoint Drift.Instruments Recalibr ML20009B5331981-06-12012 June 1981 LER 81-016/03L-0:on 810515,tests Indicated That Two Foxboro RCS Flow Transmitters in Loop a Were Out of Calibr.Caused by Setpoint Drift.Transmitters Recalibr ML20004F0161981-06-0909 June 1981 LER 81-015/03L-0:on 810510,steam Flow Transmitter Found Out of Calibr Resulting in Bi Steam Flow & hi-hi Steam Flow Trip Settings Less Conservative than Tech Spec.Caused by Instrument Drift.Transmitter Recalibr ML1116615181981-05-22022 May 1981 LER 81-013/03L-0:on 810422,during Facility Shutdown for Leak Rate Test,Investigation Revealed Cracked Root Weld on Vent Valve of Containment Sump B to RHR Pump 1B Piping.Caused by Sharp Blow of Unknown Origin.Repair Scheduled ML1116615091981-04-13013 April 1981 LER 81-010/01T-0:on 810330,nonradioactive Liquid Found Discharged from Waste Neutralizing Tank to Svc Water Pretreatment Lagoon.Caused by Error in Calculation of Allowable Discharge Rates.Proposed Tech Spec Submitted ML1116614821981-02-20020 February 1981 LER 81-003/03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected ML1116614601981-01-28028 January 1981 LER 80-044/03L-0:on 801229,noted That RCS Oxygen Sample Test Not Performed W/Frequency Required by Tech Specs.Caused by Personnel Error.Personnel Will Be Instructed in Implementation of Procedure ML19294C0361980-02-29029 February 1980 LER 80-005/03X-1:on 800131,during IE Bulletin 79-14 Insp, Discovered That Thermal Restraint Was Omitted from RHR Sys. Caused by Error in Transferring Piping Design to Const Drawings.Restraint Has Been Installed 1990-05-04
[Table view] Category:RO)
MONTHYEARML20042F3261990-05-0404 May 1990 LER 90-005-00:on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing conducted.W/900504 Ltr ML20024B7221983-07-0101 July 1983 LER 83-015/03L-0:on 830606,during Valve Timing Test for Td Auxiliary Feedwater Pump,Valve Failed to Electrically Open. Caused by Faulty Torque Switch & Maladjusted Tripper Cam. Valve Operator Rebuilt & Cam reset.W/830701 Ltr ML20024B7291983-07-0101 July 1983 LER 83-014/03L-0:on 830603,while Performing Monthly RHR Pump & Valve Surveillance Test,Containment Sump B Isolation Valve SI-350B Would Not Cycle Closed.Caused by Mechanical Interlock Sticking in Open position.W/830701 Ltr ML20023C3681983-05-0606 May 1983 Updated LER 82-030/01X-2:on 821004,sensing Lines on Six safety-related Containment Pressure Transmitters Found Capped Off Inside Containment.Caused by Personnel Error During Maint.Caps Removed ML20028F4361983-01-14014 January 1983 LER 82-035/03L-1:on 821216,during Full Power Operation, Pinhole Leak Discovered in Suction Line from Vol Control Tank to Charging Pumps.Caused by Vibrations & Pulsations in Associated Piping.Leak Plugged ML20028E3821983-01-14014 January 1983 LER 82-035/03L-0:on 821216,pinhole Leak Discovered in Suction Line from Vol Control Tank to Charging Pumps.Caused by Vibrations in Piping.Leak Plugged & Piping to Be Replaced During Next Refueling Outage ML20052G7351982-05-10010 May 1982 LER 82-009/03L-0:on 820410,w/unit at Hot Shutdown Prior to Scheduled Refueling Outage,Both Source Range Nuclear Instruments Were Inoperable.Caused by Accumulation of Water in Instrument Canisters.Spare Detector Installed ML20052G1381982-05-0606 May 1982 LER 82-008/01T-0:on 820422,during Refueling Outage,Leak Repair Procedures on Valve SI-13B Revealed Significant Boric Acid Corrosion Wastage of body-to-bonnet Bolts.Caused by Bolt Degradation.Affected Bolts Replaced ML20052G1401982-05-0606 May 1982 LER 82-007/01T-0:on 820422,during Refueling Outage,Leak Repair Procedures on Valve PS-1A Revealed Significant Boric Acid Corrosion Wastage on body-to-bonnet Bolts.Caused by Bolt Degradation.Affected Bolts Replaced ML20052G7251982-04-0707 April 1982 LER 82-005/03X-1:on 820309,during Quarterly Surveillance Testing of Svc Water pumps,IA2 Svc Water Pump Failed to Start on Demand.Circuit Breaker Failed to Close by Remote Initiation.Caused by Failed Open Closing Coil.Coil Replaced ML20041B3791982-02-15015 February 1982 LER 82-003/03L-0:on 820116,1A Zone SV Fan Started Automatically.Caused by Solenoid Valve Failure Due to Burned Out Coil in Closed Position Which Automatically Opened Damper.Coil Replaced & Sys Tested Satisfactorily ML20041B3601982-02-12012 February 1982 LER 82-002/03L-0:on 820114,deviation in Pressurizer (Pzr) Level Indication Noted.Caused by Instrument Calibr Out of Spec.Transmitter Recalibr ML20040G6081982-02-0505 February 1982 LER 82-001/03L-0:on 820108,during Operability Check of Zone Special Ventilation,Exhaust Fan 1B Failed to Start.Caused by Failure of Solenoid Valve Due to Sticking Solenoid.Valve Replaced & Sys Tested.Design Change Initiated ML20040F3571982-02-0101 February 1982 LER 81-039/03X-1:on 811218,leaking Weld on Discharge Side of 1C Charging Pump Relief valve,CVC-101C,discovered.Caused by Vibrations & Pulsations in Associated Piping.Pipe Section Replaced.Design Change in Progress ML20040A5771982-01-15015 January 1982 LER 81-039/03L-0:on 811218,found Leaking Weld on Discharge Side of 1C Charging Pump Relief Valve CVC-101C.Caused by Weld Fatigue Attributed to Vibrations & Pulsations in Associated Piping.Pipe Replaced.Design Change in Progress ML20039B1831981-12-11011 December 1981 LER 81-038/03L-0:on 811113,during Surveillance Testing on Shield Bldg Vent Sys,Check Damper SBV-10A Failed Shut.Caused by Ruptured Diaphragm Which Separates Motor from Oil Reservoir.Motor Replaced ML20038C2621981-12-0303 December 1981 LER 81-036/03L-0:on 811103,motor-driven Auxiliary Feedwater Pump Lubricator Oil Pump Continued to Run When Pump 1A Was Stopped.Caused by Excessive Wear & Misalignment of Auxiliary Switch Linkage Mechanism Allowing Switch to Remain Closed ML20038B0011981-11-17017 November 1981 LER 81-034/03L-0:on 811018,during Normal operations,1B Zone SV Fan Started Automatically.Caused by Solenoid Failure Due to Burned Out Coil in Safe Position Automatically Starting Fan & Opening Damper.Coil Replaced ML20038B0221981-11-16016 November 1981 LER 81-015/03L-2:on 810510,during Refueling Shutdown,Steam Flow Transmitter Was Out of Calibr Resulting in Less Conservative Hi & hi-hi Steam Flow than Required.Caused by Instrument Drift ML20011A5521981-10-0202 October 1981 LER 81-030/03L-0:on 810903,surveillance Procedure Found to Incorrectly Measure Shield Bldg Vent Sys Exhaust Flow from Annulus.Caused by Surveillance Procedures Written to Demonstrate Original Design Criteria ML20010F5071981-08-28028 August 1981 LER 81-024/03L-0:on 810730,low Boric Acid Heat Tracing Temp Detected on Section of Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Removal of Insulation from Boric Acid Heat Tracing Circuits to Permit Maint ML20010F3421981-08-28028 August 1981 LER 81-025/03L-0:on 810807,safety Injection High Containment Pressure Setpoint Discovered to Be Less Conservative than Required by Tech Spec Due to Foxboro Containment Pressure Transmitter Out of Calibr.Caused by Instrument Drift ML20009E6621981-07-21021 July 1981 LER 81-023/03L-0:on 810621,boric Acid Found Leaking from Instrument Isolation Valve CVC-11188.Caused by Leaking Diaphragm & Corroded Bonnet.Transfer Pump 1A Isolated & Bonnet Assembly Replaced ML20009D5531981-07-17017 July 1981 LER 81-022/03L-0:on 810619,spent Fuel Pool Boron Sampling Not Performed within Allotted Time Frame During Steady State Operation.Caused by Temporary Work Load Increase on Chemistry Staff.Sample Taken & Analyzed ML20009C5651981-07-10010 July 1981 LER 81-021/03L-0:on 810611,found Visual Verification of Valve Motion & Limit Switch Not Performed During Refueling Outage for Valves Inaccessible During Normal Operation Per Iwv 3300 of 1974 ASME Code.Caused by Procedural Oversight ML20009A9381981-07-0606 July 1981 LER 81-020/03L-0:on 810606,condensate Water Storage Tank Level Went Below Tech Spec Limit.Caused by Normal Tank Water Usage During Startup & Turbine Testing Coincident W/ Demineralizer Regeneration ML20009A8631981-07-0303 July 1981 LER 81-019/03L-0:on 810605,during Refueling Outage,Portable Radiation Survey Instrument Checks for May Not Performed Per Tech Specs.Caused by Oversight Due to Reassignment of Personnel.Instruments Will Be Source Checked in June ML20009B5381981-06-15015 June 1981 LER 81-018/03L-0:on 810516,testing Indicated That Low Pressure Safety Injection & Reactor Trip Were Below Tech Spec Limits for Pressure Transmitters.Caused by Instrument Drift.Sensing Lines Flushed.Amplifier Replaced ML20009B5351981-06-12012 June 1981 LER 81-017/03L-0:on 810515,discovered That High Pressure Reactor Trip Setpoints for Pressure Transmitters Were Higher than Tech Spec.Caused by Setpoint Drift.Instruments Recalibr ML20009B5331981-06-12012 June 1981 LER 81-016/03L-0:on 810515,tests Indicated That Two Foxboro RCS Flow Transmitters in Loop a Were Out of Calibr.Caused by Setpoint Drift.Transmitters Recalibr ML20004F0161981-06-0909 June 1981 LER 81-015/03L-0:on 810510,steam Flow Transmitter Found Out of Calibr Resulting in Bi Steam Flow & hi-hi Steam Flow Trip Settings Less Conservative than Tech Spec.Caused by Instrument Drift.Transmitter Recalibr ML1116615181981-05-22022 May 1981 LER 81-013/03L-0:on 810422,during Facility Shutdown for Leak Rate Test,Investigation Revealed Cracked Root Weld on Vent Valve of Containment Sump B to RHR Pump 1B Piping.Caused by Sharp Blow of Unknown Origin.Repair Scheduled ML1116615091981-04-13013 April 1981 LER 81-010/01T-0:on 810330,nonradioactive Liquid Found Discharged from Waste Neutralizing Tank to Svc Water Pretreatment Lagoon.Caused by Error in Calculation of Allowable Discharge Rates.Proposed Tech Spec Submitted ML1116614821981-02-20020 February 1981 LER 81-003/03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected ML1116614601981-01-28028 January 1981 LER 80-044/03L-0:on 801229,noted That RCS Oxygen Sample Test Not Performed W/Frequency Required by Tech Specs.Caused by Personnel Error.Personnel Will Be Instructed in Implementation of Procedure ML19294C0361980-02-29029 February 1980 LER 80-005/03X-1:on 800131,during IE Bulletin 79-14 Insp, Discovered That Thermal Restraint Was Omitted from RHR Sys. Caused by Error in Transferring Piping Design to Const Drawings.Restraint Has Been Installed 1990-05-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140E9181997-06-0707 June 1997 Safety Evaluation Supporting Amend 133 to License DPR-43 ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20113H4871992-07-30030 July 1992 Part 21 Rept Re Surge Line Flooding Which May Occur When Large Pressurizer Vent Used to Support Reduced Rc Inventory Operations.Notification Received from Westinghouse on 920312.Item Not Reportable Per 10CFR21 ML20086U0311991-11-30030 November 1991 SG Tube Plugging Criteria for Outside Diameter Stress Corrosion Cracking (ODSCC) at Tube Support Plates ML20077K0831991-06-30030 June 1991 Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture as Structural Design Basis for Kewaunee Nuclear Plant ML1118102861991-05-31031 May 1991 Handbook on Flaw Evaluation Kewaunee,Unit 1 Steam Generators Upper Shell to Cone Weld. ML20091E3441991-03-31031 March 1991 Nonproprietary Structural Evaluation of Kewaunee Pressurizer Surge Line,Considering Effects of Thermal Stratification ML20066B2101990-12-31031 December 1990 Generator Mid-Cycle Rept,Dec 1990 ML20062A4641990-09-30030 September 1990 Nonproprietary, Reevaluation of U-Bend Tube Fatique for Kewaunee Plant Steam Generators ML20042F3261990-05-0404 May 1990 LER 90-005-00:on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing conducted.W/900504 Ltr ML1117803551990-04-30030 April 1990 Generator Tubesheet Crevice Indications Return to Power Rept. ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19354D8351989-11-0808 November 1989 Presentation to NRC Re Kewaunee (Wps) SECY-83-472 LOCA Analysis Effort. ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20235J1941988-11-30030 November 1988 Analysis of Capsule P from Wisconsin Public Svc Corp Kewaunee Nuclear Plant Reactor Vessel Radiation Surveillance Program ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20206E9801988-06-30030 June 1988 Rev 2 to Handbook on Flaw Evaluation,Kewaunee Unit 1 Steam Generators Upper Shell to Cone Weld ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20154H0391988-04-30030 April 1988 Slide Presentation Matl,Nrc Meeting 880331,Kewaunee Nuclear Power Plant Steam Generator Tube Sleeve Installation ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147B2921987-12-31031 December 1987 Annual Operating Rept for 1987 ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20236W7341987-11-30030 November 1987 Nonproprietary Kewaunee Steam Generator Sleeving Rept (Mechanical Sleeves) ML20236F3101987-10-31031 October 1987 Nonproprietary WCAP-11620, Addl Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Kewaunee ML20236N3451987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235V1161987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238F7541987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20237H6861987-07-31031 July 1987 Monthly Operating Rept for Jul 1987 ML20235J3101987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20215A3211987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20215L8061987-04-30030 April 1987 Nonproprietary Rev 1 to Technical Bases for Eliminating Large Pipe Rupture as Structural Design Basis for Kewaunee ML20213G4341987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206H4301987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20207R6091987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20211A1761987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20212B9451986-12-31031 December 1986 Reload Safety Evaluation,Kewaunee Cycle 13 ML20207M8271986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 ML20212F4301986-12-31031 December 1986 Annual Operating Rept,1986 ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20211M0441986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F2231986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20207F6021986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20210C8931986-08-31031 August 1986 Monthly Operating Rept for Aug 1986 ML20212F5161986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20202G9981986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211E1391986-05-31031 May 1986 Monthly Operating Rept for May 1986 1997-06-07
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LICENSEE EVENT llEPORT lh f0NTROLULOCK: l l l l l l (PLE ASE PRINT OR TYPE ALL REOutnCD INFORMATION!
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b6 CON'T lolil s$ ,"c' l L l@l 0 l 5 l 0 l 0 l 0 l 3 l 0 l5 l@l 0 l 6 l 0 l 3 l 8 l 3 l@l 0l 7 l 0 l 1 l 8 l 3 l@
EVENT DESCnlPTION At O PROSA L C JS NCES 10121 l During f' power operation, while performing the monthly RHR pump and valve j j u l a j l surveillance test, containment sump B isolation valve SI-350B would not cycle closed. l
[ o 1. l lThis required the valve to be taken out of service to perform corrective maintenance. l l n I s ] [ This placed the plant in an LCO per T.S.3.3.a.2.D and is reportable per T.S.6.9.2.b. (2) . l l o l61 l Since the redundant train was available to function during accident conditions, there l l o l 7 l lwas no effect on the health and safety of the public. j 10l811 I i 8 9 60 SY S T E r.9 CAUSE CAUSE COMP.
COOL VALVE CODE SuuCODE COMPONENT CODE SUBCODE SUBCODE l0[9l l Sl Fl@ W@ l Bl@ l C lK l T lB lR lK l@ l X l@ y @
1 8 9 to 11 12 13 13 19 20
_ SEouf flTI AL OCCURRENCE REFORT REVISION L E Hino EVENT YE AH REPOsti NO. CODE TYPE PJo.
O17 ,ag [--J l 0l 1l 4l26 l , -l l 0l 3 l [L l l_l [o l
_ l218 l3 2/ l 23 24 27 28 23 30 31 32 TAKEf A TO O PL AP ! 1 I C HOURS S B IT FO 1 Ull. S P LI MAN FACTUDEH
' 33b@l Z l@ 34 lZl@
35
[_Zjh 36 l0l0l0l0l 3/ lN lQ lY lg lNl@ l W l 1 l 2 l0 l(
40 44 42 43 44 47 CAUSE DESCnlPTION AND COHRECTIVE ACTIONS l i j o l l Valve Sl-350B failed to cycle closed because the mechanical interlock on the breaker ;
i i lwas sticking in the open position. The mechanical arm was exercised, the valve cycled ;
,,,,,jand returned to' operation within T.S. time limits. The surveillance test was then ;
y l completed satisfactorily. No further action is required. l I L i '.1 I I
i 8 9 STAT S % POWER OTHER STATUS ISC RY DISCOVERY DESCRIPTION i s [_E_j@ l ll 010 l@l NA l l B l@l RHR Pump and Valve Surveillance Test l
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. . ernhoM. G. Nrgem PHONE:
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bptA NRC-83-129 )
WISCONSIN PU B LIC S E RVICE CO RPORATION RO. Box 1200, Green Bay, Wisconsin 54305 July 1, 1983 Mr. J. G. Keppler, Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
Docket 50-305 Operating License DPR-43 Reportable Occurrence 83-014/03L-0 In accordance with the requirements of the Technical Specifications, Section 6.9, the attached Licensee Event Report for reportable occurrence 83-014/03L-0 is being submitted.
Very tr ly yours, WW V C. W. Giesler Vice President - Nuclear Power Js Attach.
cc - Dir, Office of Inspection & Enforcement US NRC, Washington, DC 20555 Dir, Office of Mgt Info & Program Control US NRC, Washington, DC 20555 INP0 Records Center Suite 1500, 1100 Circle 75 Parkway Atlanta, GA 30339 Mr. Robert Nelson, NRC Resident Inspector RR #1, Box 999, Kewaunee, WI 54216 Mr. S. A. Varga, Chief US NRC, Washington, DC 20555 56c ?V \ \
JUL 61983