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 Issue dateTitleTopic
ML20203L02825 April 1986Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed PointsBackfit
05000255/LER-1986-010, Withdrawn LER 86-010-00 Re Missing Pipe Hangers on Integrated Leak Rate Test Instrument Line.Results of Analysis Using ASME Code Case N-411 Revealed That Line,W/O Pipe Support,Statically Qualified17 April 1986Withdrawn LER 86-010-00 Re Missing Pipe Hangers on Integrated Leak Rate Test Instrument Line.Results of Analysis Using ASME Code Case N-411 Revealed That Line,W/O Pipe Support,Statically Qualified
05000255/LER-1982-015, Updated LER 82-015/03X-1:on 820519,snubber 17 (Main Steam Line Upstream of Atmospheric Dump Valve CV-0780) Contained Insufficient Oil.Caused by Deteriorated O-rings.Snubber Replaced & Will Be Rebuilt on 5-yr Cycle14 July 1982Updated LER 82-015/03X-1:on 820519,snubber 17 (Main Steam Line Upstream of Atmospheric Dump Valve CV-0780) Contained Insufficient Oil.Caused by Deteriorated O-rings.Snubber Replaced & Will Be Rebuilt on 5-yr Cycle
05000255/LER-1981-037, Updated LER 81-037/03X-1:on 810908,during Maint on Check Valves CK-3103,CK-3118,CK-3133 & CK-3148,disc Nut,Washer & Pin Found Missing.Caused by High Fluid Velocity & Turbulence Creating Accelerated Wear4 June 1982Updated LER 81-037/03X-1:on 810908,during Maint on Check Valves CK-3103,CK-3118,CK-3133 & CK-3148,disc Nut,Washer & Pin Found Missing.Caused by High Fluid Velocity & Turbulence Creating Accelerated Wear
05000255/LER-1982-012, Updated LER 82-012/01X-1:on 820423,primary to Secondary Leakage in Steam Generator Tubes Increased to Approx 0.32 Gpm.Caused by Two through-wall Defects.Tubes W/Defects Plugged4 June 1982Updated LER 82-012/01X-1:on 820423,primary to Secondary Leakage in Steam Generator Tubes Increased to Approx 0.32 Gpm.Caused by Two through-wall Defects.Tubes W/Defects Plugged
ML20147A83111 September 1978/01T on 780828:During Cooldown of the Reactor,The Containment Bldg Was Ventilated Thru the Purge Supply & Exhaust Valves.Improper Tagging Caused Valves to Be Open & Containment Integrity Not Met. (Encl to 7809190170)
ML20084U2434 April 1977LER ER-77-011:on 770130,secondary Water Chemistry Limits for Sodium Concentration,Ph & Conductivity Exceeded Tech Spec 3.18 Due to Leak in Main Condenser West Half.Cause Suspected to Be Tube Vibration.Tubes Plugged
ML20084U32721 March 1977LER ER-77-002:on 770106,secondary Water Chemistry Spec Exceeded Tech Spec 3.18 Limits Due to Condenser Leak.Leakage Caused Power Reduction & Plugging of Three Tubes in East Water Box.Leakage Cause Not Determined
ML20084U31021 March 1977Updated LER ER-77-002:on 770106,secondary Water Chemistry Spec Exceeded Tech Spec 3.18 Limits.Caused by Condenser Leakage Which Caused Power Reduction & Plugging of Tubes in East Water Box.Leakage Cause Undetermined
ML20084U22923 February 1977LER ER-77-015:on 760623,discharge Water Temp Rose Above 5 F Limit.Caused by Cooling Water Sys Design.Npdes Limits Not Exceeded
ML20084U22823 February 1977LER ER-77-016:on 770210,two Events Caused Discharge Water Temp to Rise Above 5 F Limit.Cause Related to Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded
ML20084U23022 February 1977LER ER-77-014:on 770107,discharge Water Temp Exceeded 5 F Limit Twice.Cause Related to Stopping or Starting of Cooling Pump P-39B During Startup
ML20084U24222 February 1977LER ER-77-012:on 770205,tank Heater H68A for Boric Acid Tank T-53A Found Leaking During Routine Insp of Chemical & Vol Control Sys.Cause Not Stated.Heater ReplacedBoric Acid
ML20084U24414 February 1977LER ER-77-010:on 770131,ice Loading on 345-kV Bus Tie & Station Power Lines Greater than Expected Due to Cooling Tower Plume Passing Lines.Caused by Environ Conditions & Cooling Tower Operation
ML20084U2459 February 1977LER ER-77-009:on 770130,discharge Water Temp Rose Above 5 F Limit During Power Escalation.Caused by Either Starting or Stopping of Cooling Tower Pump P-39A During Power Escalation.Npdes Limits Not Exceeded
ML20084U2912 February 1977LER ER-77-006:on 770117,control Rod 21 Found 9.1 Inches Above Lowest Rod in Bank.Caused by Trainee Pulling Rods While in Manual Individual Rather than Sequential,During Critical Approach for Trip Recovery
ML20084U2532 February 1977LER ER-77-008:on 770117,control Rod 38 Driven 13.6 Inches Below Group When Operator Manually Ran Control Rods in Order to Avert Reactor Trip Following Feedwater Pump Trip.Caused by Operator Failure to Switch Mode Selector
ML20084U28431 January 1977LER ER-77-007:on 770117,discharge Water Temp Rose Above 5 F Limit Following Plant Trip & Subsequent Startup.Caused by Either Effects of Plant Trip or by Placing Cooling Towers in Svc.Npdes Limits Not Exceeded
ML20084U29917 January 1977LER ER-77-004:on 770111 & 12,discharge Water Temp Rose Above 5 F Limit Following Plant Trip & Subsequent Startup.Caused by Either Effects of Plant Trip or by Placing Cooling Towers in Svc.Npdes Limits Not Exceeded
ML20084U33017 January 1977LER ER-77-001:on 770103,control Rod Drive Mechanism 4 Declared Inoperable Due to Seal Leakage Problems.Caused by Beginning Seal Failure.Drive Seal to Be Replaced
ML20085E42311 January 1977LER ER-76-046:on 761225,drain Valve Not Closed Upon Neutralizer Tank Drainage Completion During Shift Change. Caused by Poor Communications Between Operating Shifts & by Operator Error.Procedures Revised
ML20085E4374 January 1977LER ER-76-044:on 761206,steam Generator Low Level Trip Setpoint (Channel D) Found Below Tech Spec Limit.Caused by Setpont Drift & Indistinct Administrative Limit Vs Tech Spec Limit
ML20085E44030 December 1976LER ER-76-043:on 761202,small Leak Observed in Charging Pump Suction Header Near B Charging Pump.Caused by Type of Tee (Field Fabricated Type) & by Pipe Vibration at Tee Location
ML20085E42821 December 1976LER ER-76-045:on 761209,DBA Sequencer 34-1 Failed to Operate During Quarterly Safeguards Test Rerun.Caused by Failure of Sequencer Clutch to Reset Due to Insufficient Clutch Disk Gap to Set Screw Slippage
ML20085E45517 December 1976LER ER-76-038:on 761117,discharge Water Rose Above Temp Limits During Startup.Events Related to Placing Cooling Towers in Svc.Npdes Limit Not Exceeded
ML20085E44317 December 1976LER ER-76-042:on 761201 & 02,two Events Resulted in Discharge Water Above Temp Limit.Cause Related to Effects of Plant Trip or to Placing Cooling Towers in Svc for Plant Startup.Npdes Limits Not Exceeded
ML20085E45317 December 1976LER ER-76-040:on 761130,discharge Water Rose Above Temp Limit During Plant Shutdown.Event Related to Cooling Tower Removal from Svc.Npdes Limit Not Exceeded
ML20085E45417 December 1976LER ER-76-039:on 761125,discharge Water Rose Above Tech Spec Limits During Plant Startup.Event Related to Placing Cooling Towers in Svc
ML20085E45613 December 1976LER ER-76-037:on 761115,trip Setpoint Found Out of Spec While Doing Check Sheet on Neutron Monitor Channel C.Caused by Instrument Setpoint Drift
ML20085E44910 December 1976LER ER-76-041:on 761130,total Chlorine Discharge Into Lake Exceeded Tech Spec Limits During Chlorination of B Cooling Tower.Caused by Excessive Flow from Weir Discharge to Mixing Basin
ML20085E45919 November 1976LER ER-76-036:on 761105,air Leakage Noted During Escape & Personnel Air Lock Door Testing.Caused by Personnel Failure to Follow Procedures.Remedial Action Taken
ML20085E46211 November 1976LER ER-76-034:on 761020,cooling Tower Pumps Tripped Due to Plant Operational Problems.Caused Water Box Vacuum Reestablishment & Pump Starting,Raising Discharge Temp Above Limit.Npdes Limit Not Exceeded
ML20085E4633 November 1976LER ER-76-033:on 761020,dc Bus 2 Voltage Dropped to 60 Volts,Dropping Associated Ac Preferred Bus Voltage to 90 Volts.Caused by Improper Coordination of Battery Charger Current Limiter & Charger Output Breaker
ML20085E51422 September 1976LER ER-76-017:on 760520,one of 24 Reactor Protective Matrix Relays Failed to Operate.Apparently Caused by Mercury Wetted Contacts.Replacement Relays Tested
ML20085E46421 September 1976LER ER-76-031:on 760913,control Rod Drive Mechanism (CRDM) 13 Considered Inoperable Due to Seal Leakage Problems.Caused by Beginning Seal Failure on CRDM 13
ML20085E46521 September 1976LER ER-76-030:on 760826,rod Withdrawal Unsuccessful After Rod Drop Test.Cause of Failure Probably Associated W/Motor/ Brake Assembly Replaced.Brake Insp Procedures Developed
ML20085E46621 September 1976LER ER-76-029:on 760827,necessary Control Rod Motion to Maintain Reactor Criticality Resulted in Misalignment of Rod 37.Cause Associated W/Motor/Brake Assembly.Motor/Brake Assembly Replaced.Insp Procedures Developed
ML20085E4679 September 1976LER ER-76-028:on 760823,Group 3 Rods Moved While Group 4 Rods Inserted by Manual Sequential Mode.Event Classified as Reportable on 760826.Cause Not Determined
ML20085E4859 September 1976LER ER-76-025:on 760813,during Semiannual Operational Check of Hydrogen Recombiners,Unit M69B Loaded to 43 Kw,Resulting in Heater Temp Below Tech Spec Limits.Caused by Grounded Heater Phase
ML20085E4687 September 1976LER ER-76-027:on 760823,as-found Leakage Rate Found Unacceptably High During Quarterly Testing of Penetration 1 (Purge Air Supply CV1808).Caused by Recent Mod to Valve Stem multi-ring Packing Grease Fitting
ML20085E47631 August 1976LER ER-76-026:on 760817,cooling Water Basin Level Increased More Rapidly than Expected During Determination of Effect of Dilution Water Flow on Plant Output.Test Procedure Revised to Accommodate Level Increase
ML20085E48713 August 1976LER ER-76-024:on 760730,power Dependent Insertion Limits Exceeded Three Times During Power Reduction to Remove Leaking Feed Pump from Svc.Caused by Rapid Power Reduction
ML20085E50122 July 1976LER ER-76-021:on 760627,containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test.Valve Tagged Closed to Meet Containment Integrity Requirements.Cause Not Known.Failure Will Be Investigated
ML20085E54325 May 1976LER ER-76-014:on 760510,diesel Generator Made Inoperable for Preventive Maint W/One of Two HPSI Pumps Also Inoperable. Caused by Operations Staff Oversight.Possible Procedure Changes Reviewed
ML20085E53221 May 1976LER ER-76-013:on 760507 & 09,four Events Resulted in Discharging Water Above 5 F Limit During Startup/Shutdown of Cooling Towers.Cause Related to Cooling Tower Removal from Svc to Repair Leaking Condenser Tube
ML20085E57420 May 1976LER ER-76-010:on 760421,charging Pump P55-A Failed to Perform Properly During Loss of Offsite Power/Sis Test. Caused by Plug Oil Filter.Filter Changed
ML20085E54914 May 1976LER ER-76-012:on 760430,equipment Review Revealed Valves CV-2113 & CV-2115 Possibly Did Not Meet Original Design Specs Re Allowable Stresses at Valve body-to-bonnet Flange. Caused by Use of Different Calculations
ML20085E57614 May 1976LER ER-76-009:on 760419,left Channel Relay SP7 Showed Intermittent Operation During Containment Spray Sys Testing. Causing by Dirty Contacts.Relay Contacts Cleaned
ML20085E5616 May 1976LER ER-76-011:on 760328,test on Penetration 46 Indicated Leakage Above Acceptable Limits.Caused by Worn Valve Seats
ML20085E57822 April 1976LER ER-76-008:on 760408,4 Psig Released from T-101A Instead of T-101B Waste Gas Decay Tank.Caused by Operator Error. Total Kr-85 Activity Released Is 0.02% of Allowable Limit. Event & Possible Consequences Reviewed