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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- 05000366/LER-1982-130-03, /03L-0:on 821203,w/unit Shutdown for Refueling, Discovered Secondary Containment Integrity Above Refueling Floor Not Maintained.Caused by Defective Procedures. Procedures Revised + (ML20064H825)
- ML20064H828 + (ML20064H828)
- ML20064H829 + (ML20064H829)
- ML20064H831 + (ML20064H831)
- JAFP-83-0043, Forwards Monthly Operating Rept for Dec 1982 + (ML20064H832)
- ML20064H835 + (ML20064H835)
- 05000348/LER-1982-060-03, /03L-0:on 821217,leakage Rate for RCS Exceeded Required Rate.Caused by Failure to seal-wire Seal Injection Throttle Valves.Valves Adjusted & seal-wired + (ML20064H843)
- 2CAN128201, Forwards to Provide Record of Compliance W/Ie Bulletin 82-01, Rev 1,Suppl 1, Alteration of Radiographs of Welds in Piping Subassemblies + (ML20064H844)
- ML20064H846 + (ML20064H846)
- ML20064H847 + (ML20064H847)
- ML20064H850 + (ML20064H850)
- 05000338/LER-1978-127, Forwards LER 78-127/03L-0 + (ML20064H857)
- 05000338/LER-1978-127-03, /03L-0 on 781204:during Pwr Reduction,Axial Flux Difference Deviated Greater than 5%;during Return to Full Pwr Afd Deviated Greater than -5%.Caused by Load Reduction Caused by Unit Being on Load Following + (ML20064H861)
- 05000361/LER-1982-149, Forwards LER 82-149/03L-0.Detailed Event Analysis Submitted + (ML20064H867)
- ML20064H868 + (ML20064H868)
- 05000259/LER-1978-034, Forwards LER 78-034/01T-0 + (ML20064H869)
- HL-4528, Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Plant,Per 10CFR50.54(w)(3) + (ML20064H873)
- ML20064H874 + (ML20064H874)
- 05000259/LER-1978-034-01, /01T-0 on 781205:during Refueling Outage 6 MSIVs Exceeded Leakage Limits.Caused by Degradation of Valve Seating Surfaces Thru Normal Oper + (ML20064H877)
- ML20064H880 + (ML20064H880)
- 05000348/LER-1978-088, Forwards LER 78-088/03L-0 + (ML20064H882)
- 05000296/LER-1982-062, Forwards LER 82-062/03L-0 + (ML20064H885)
- ML20064H886 + (ML20064H886)
- 05000348/LER-1978-088-03, /03L-0 on 781125:Train a River Water Pumps Were Found in Tripped Condition & Could Not Be Started from Control Room.Cause of Occurrence Is Undetermined + (ML20064H887)
- ML20064H890 + (ML20064H890)
- 05000325/LER-1978-091, Forwards LER 78-091/03L-0 + (ML20064H892)
- ML20064H895 + (ML20064H895)
- 05000325/LER-1978-091-03, /03L-0 on 781120:Senior Control Operator Did Not Have Completed Hatch Leak Rate Test Before Beginning Reactor Startup Due to Misunderstanding.Test completed.GP-1 Revised to Require Leak Test Verification by Control Operators + (ML20064H896)
- ML20064H897 + (ML20064H897)
- 05000324/LER-1982-137, Forwards LER 82-137/03L-0 + (ML20064H900)
- ML20064H901 + (ML20064H901)
- 05000368/LER-1978-018, Forwards LER 78-018/03L-0 & 78-019/03l-0 + (ML20064H902)
- 05000361/LER-1982-149-03, /03L-0:on 821123,during Mode 1,while Attempting to Shift Steam Generator Feedwater from Auxiliary Feed to Main Feed,Containment Isolation Valve 2HV4730 Would Not Close. Caused by Failure of Limit Switch.Switch Adjusted + (ML20064H906)
- 05000368/LER-1978-018-03, /03L-0 on 781128:both Doors of the Personnel Hatch Doors Were Simultaneously Opened,Caused by a Sheared Mechanical Door Interrlock Gear Key.Mechanical Interlock Repairs Made & Containment Air Lock Declared Operable + (ML20064H907)
- 05000348/LER-1978-086, Forwards LER 78-086/03L-0 & 78-087/03L-0 + (ML20064H908)
- 05000361/LER-1982-151, Forwards LER 82-151/03L-0.Detailed Event Analysis Submitted + (ML20064H909)
- ML20064H910 + (ML20064H910)
- 05000348/LER-1978-085, Forwards LER 78-085/03L-0 + (ML20064H914)
- ML20064H918 + (ML20064H918)
- 05000348/LER-1978-086-03, /03L-0 on 781221:both Trains of Component Cooling Water Were Discovered to Be cross-connected at Charging Pump 1B.FNP-1-STP-23.7 Was Rev to Show Alignment of Charging Pump 1B to Either Train + (ML20064H919)
- 05000296/LER-1982-062-03, /03L-0:on 821211,during Rod Pattern Adjustment, Calculated R Factor Less than R Factor Used to Set Average Power Range Monitor Scram Rod Blocks.Caused by Control Rod Pattern Adjustment in Nonequilibrium Xenon Conditions + (ML20064H920)
- RC-94-0074, Responds to Violation Noted in Insp 50-395/94-03 Re Service Water Booster Pump Area Air Handling Units Must Be Isolated for SW Inlet Temps Less than 48F.Both Trains of Chill Water to Svc Water Booster Air Pump Handling Units Isolated + (ML20064H921)
- RC-94-0076, Application for Amend to License NPF-12,consisting of TS Change TSP 940001,revising AOT for RHR Suction Relief Valves as Specified in LCO for TS 3.4.9.3, Overpressure Protection Sys. Change Parallels Guidance of GL 90-06,GI-94 + (ML20064H922)
- 05000368/LER-1978-019-03, /03L-0 on 781129:Chilled Water Return Containment Isolation valve,2CV3850-2,was Taken Out of Svc to Repair Control Room Communication Breaker Contacts.Breaker Was Changed to Type AB Contacts + (ML20064H924)
- ML20064H925 + (ML20064H925)
- 05000348/LER-1981-010, Updated LER 81-010/03X-1:on 810429 & 30,containment Atmosphere Radioactivity Monitoring Sys R-11 Declared Inoperable When Filter Paper Did Not Advance.Caused by Paper Spool Slipping on Shaft.Drive Shaft Adjusted + (ML20064H926)
- 05000348/LER-1978-085-03, /03L-0 on 781120:train a River Water(Rw)Pump 9 Secured Due to Vibration.Tech Specs Req at Least 2 Independent RW Loops to Be Operable.Caused by Bearing Damage Due to Fouling of Lube/Cooling Piping + (ML20064H928)
- 05000348/LER-1978-087-03, /03L-0 on 781221:vibration Readings Taken on River Water Pump 4 Exceeded Acceptable Limits.Work on Pump Bedplate,Adjustment of Impeller Lift & Pump/Motor Realignment Restored Vibration to W/In Acceptable Range + (ML20064H933)
- B14776, Requests Relief from ASME Boiler & Pressure Vessel Code Section XI Requirements Per 10CFR50.55a(g)(6)(i),in Response to GL 90-05.Description of Actions Taken by Util to Make Interim Repairs to Leak in Subj Piping Encl + (ML20064H935)
- 05000361/LER-1982-151-03, /03L-0:on 821128,while Performing Monthly Channel Check Surveillance,Temp Indication TI-0111BX for Reactor Coolant Hot Leg Read More than 48 F Lower than TI-0911X1. Caused by Setpoint Drift.Indicator Recalibr + (ML20064H936)
- ML20064H943 + (ML20064H943)