05000313/LER-1983-007, Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure
1CAN059301, Application for Amend to License DPR-51,revising TS to Replace Current Refs to B&W Topical Repts W/Ref to BAW-10179P-A, Safety Criteria & Methodology for Acceptable Cycle Reload Analyses
05000313/LER-1983-028-03, /03L-0:on 831130,during Radwaste Processing,Crack Discovered in Discharge Piping of Clean Waste Transfer Pump P-47B.Probably Caused by Overheating of Pipe During Installation of Valve Along W/Piping Stresses
05000313/LER-1983-029-03, /03L-0:on 831129,bottoms of Carbon Filter for Penetration Room Ventilation Fans Found Wet.Caused by Water from Hydrogen Purge Sys Carried Over Into Plant Vent During Hydrogen Purge Sys Operation.Filters Replaced
05000313/LER-1983-022-03, /03L-0:on 831013,as-found Voltage of 2.06 for Station Battery D07,cell 34,did Not Meet Required 2.13 Volts.Cause Not Determined.Battery Placed on Equalizing Charge
05000313/LER-1983-020-03, /03L-0:on 830828,lead Hydrogen Purge Fan VEF-37A Indicated Low Output Flow.Caused by Debris Collected at Valve HPA-133.Valve Internals Cleaned
05000313/LER-1983-024-03, /03L-0:on 830926,control Rod Assembly 10 Found Misaligned from Group Average by Greater than 9 Inches. Caused by Pole Slippage on Out Command.Control Rod Drive Malfunction Procedure Will Be Revised
05000313/LER-1983-025-03, /03L-0:on 831001,acceptable Sample Flow Criteria Not Met for Reactor Bldg Hydrogen Sampling Standby Purge Sys Test.Caused by Switch on Conductivity Analyzer in Off Position
05000313/LER-1983-018-03, /03L-0:on 830726,emergency Feedwater Bypass Valve CV-2626 to Steam Generator B Failed to Open from Control Room During Surveillance Test.Caused by Failure of Interlock Contact Preventing Reverse Contactor to Open
05000313/LER-1983-009-03, /03L-0:on 830405,during Hot Shutdown After Refueling Outage,Discovered That Nonqualified Diaphragm Was Used to Repair Pressure Switch PS-7503 in Standby Hydrogen Purge Sys.Qualified Pressure Switch Obtained & Installed
05000313/LER-1983-007-03, /03L-0:on 830308,during Performance of Reactor Protection Sys Channel D Calibr,Reactor Bldg Pressure Switch PS-2403 Found Out of Tolerance.Caused by Instrument Drift. Switch Reset Per Reactor Protection Sys Procedure
05000313/LER-1983-015-03, /03L-0:on 830616,while in Hot Shutdown After Reactor Trip,Hpi Control Valve CV-1219 Failed to Open on Demand from Control Room.Cause Not Determined.Operator & Switches Inspected & Switch Settings Checked
05000313/LER-1983-013-03, /03L-0:on 830520,while Raising Steam Generator Level for Wet Layup,Emergency Feedwater Pump P-7B Indicated Flow Appeared Degraded.Caused by Cavitation at High Flows from Suction Fouling Due to Lodged Glove
05000313/LER-1982-001-03, /03L-0:on 820112,RCS Leak Rate Calculation Indicated Leak Rate of 1.433 Gpm from Flange for Vent Line for Reactor Coolant Pump P32C Seal Cavity Pressure Sensing Line.Caused by Loose Flange Bolts
05000313/LER-1981-001-01, /01T-0:on 810117,during Reactor Bldg Cooler Svc Water Lines Engineering Analysis,Discovered Previous Analyses Considering Cooling Unit Piping Nozzles as Rigid Anchors.Nozzle Loads Imposed by Vendor Overlooked
05000313/LER-1983-017-03, /03L-0:on 830707,once-through Steam Generator Exhibited Small Primary to Secondary Leak.During Cooldown, Leak Rate Increased to 0.2 Gpm.Caused by Intergranular Stress Corrosion Cracking on Single Tube 77-18
05000313/LER-1983-016-03, /03L-0:on 830710,pressurizer Cooldown Rate Exceeded Tech Spec Limit.Caused by Personnel Error & Procedural Inadequacies.Dhr Operations Procedure Revised to Add Caution Statements Re Cooldown
1CAN128707, Forwards Info Re Elevated Reactor Bldg Temp & Schedule of Completion of All Committed Actions,Per NRC 871015 Request
05000313/LER-1983-014-03, /03L-0:on 830609,auxiliary Feedwater Pump P-75 Rendered Inoperable.Caused by Supply Piping Seal Break Due to Piping Misalignment.Piping Replaced & Realigned to Reduce Stress
05000313/LER-1983-006-03, /03L-0:on 830321,reactor Coolant Pressure Transmitter PT-1023 Found to Be Out of Tolerance During Reactor Protective Sys Channel B Calibr.Caused by Instrument Drift.All Reactor Coolant Pressure Instrumentation Calibr