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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
- 05000352/LER-1985-004, :on 850106,during Startup,Transmitter Trip Unit Alarm Light Indicated Gross Fail/Inop for One HPCI Low Steam Pressure Transmitter PT-55-IN058F.Pressure Transmitter Repaired + (ML20106F630)
- HL-5113, Provides FFD Performance Data for Six Month Reporting Period of Jul-Dec 1995 for Ei Hatch Nuclear Plant,Per 10CFR26.71(d) + (ML20106F631)
- ML20106F635 + (ML20106F635)
- ML20106F636 + (ML20106F636)
- 05000249/LER-1985-001-04, :on 850112,during Turbine Checks Surveillance, Reactor Scrammed from Turbine Trip.Caused by Oil Trip Solenoid Valve Malfunction.Solenoid Valve Replaced.Group I Isolation Caused by Switch Vibration + (ML20106F642)
- ML20106F645 + (ML20106F645)
- ML20106F653 + (ML20106F653)
- ML20106F671 + (ML20106F671)
- ML20106F676 + (ML20106F676)
- ML20106F703 + (ML20106F703)
- ML20106F725 + (ML20106F725)
- ML20106F726 + (ML20106F726)
- 05000265/LER-1984-014-07, :on 840919,HPCI Isolation Occurred.Caused by Small Intermittent Leak from Steam Seal on HPCI Turbine. HPCI Isolation Reset + (ML20106F756)
- B11435, Forwards Draft Inservice Testing Program for Pumps & Valves as Committed in Response to Question 210.43.Matl Subj to Change as Result of Review Process Constraints Identified During Preparation of Surveillance Procedures & Comments + (ML20106F758)
- 05000322/LER-1985-004, :on 850108,continuous Fire Watch Not Posted in Relay Room During Fuel Loading.Fire Watches in Area Where Operable Redundant Equipment Required During Fire Instated on 850108 + (ML20106F765)
- ML20106F776 + (ML20106F776)
- ML20106F780 + (ML20106F780)
- L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2 + (ML20106F797)
- ML20106F803 + (ML20106F803)
- ML20106F808 + (ML20106F808)
- ML20106F810 + (ML20106F810)
- ML20106F811 + (ML20106F811)
- A04377, Forwards Addl Info Requested in NRC Re Emergency Operating Procedures Generation Package & Rev 1 to Emergency Operating Procedures Generation Package, Per Suppl 1 to NUREG-0737 + (ML20106F822)
- ML20106F836 + (ML20106F836)
- ML20106F856 + (ML20106F856)
- ML20106F873 + (ML20106F873)
- ML20106F875 + (ML20106F875)
- 2CAN028503, Forwards Summary Rept on Exam,Testing & Evaluation of Irradiated Pressure Vessel Surveillance Specimens from Arkansas Nuclear One,Unit 2. No Tech Spec Changes Submitted Due to Conservative Pressure Temp Limits + (ML20106F882)
- 05000361/LER-1985-007, :on 850103,containment Purge Isolation Sys Train B Actuated When Containment Area Radiation Monitor 2RT-7857 Cabinet Opened for Surveillance.Sign Will Be Placed on Door Cautioning Personnel + (ML20106F886)
- ML20106F889 + (ML20106F889)
- ML20106F901 + (ML20106F901)
- 05000282/LER-1985-003, :on 850107,cooling Water Outlet Valve CL-40-2 Closed.One Component Cooling HX in Each Unit Inoperable. Caused by Human Error.Valve Opened Upon Discovery + (ML20106F904)
- RBG-20048, Final Deficiency Rept DR-179 Re Test Loop Diagrams Not Updated to Agree W/Latest Approved Design Documents Prior to Testing Control Circuitry Identified on 11 Loop Calibr Repts.Item Not Reportable Per 10CFR50.55(e) + (ML20106F912)
- 05000261/LER-1985-003-01, :on 850108,low Voltage Spike Occurred on Buses 4 & 9.Caused by Grounding Digital Metal Impact Monitoring Sys Through Oscilloscope to Plant Electrical Receptacle. Technician Counseled + (ML20106F916)
- ML20106F924 + (ML20106F924)
- ML20106F935 + (ML20106F935)
- ML20106F939 + (ML20106F939)
- ML20106F940 + (ML20106F940)
- 05000325/LER-1985-003-02, :on 850108,adequate Surveillance Testing Did Not Exist to Verify Operability of Degraded Voltage & Loss of Voltage Regulation Relay Circuitry.On 850110,master-slave Feeder Breakers to Bus Automatically Opened + (ML20106F943)
- ML20106F947 + (ML20106F947)
- 05000316/LER-1985-001-01, :on 850111,automatic ESF Actuation Occurred, Providing Start Signal to Motor Driven Auxiliary Feedwater Pumps.Caused by Personnel Error in Manual Control of Feedwater Regulator Valves + (ML20106F953)
- ML20106F954 + (ML20106F954)
- ML20106F975 + (ML20106F975)
- 05000316/LER-1985-002, :on 850112,automatic ESF Actuation Occurred, Resulting in Reactor Trip.Caused by lo-lo Level in Steam Generator 22 Due to Unexpected Increase in Steam Flow.Event Discussed W/Shift Personnel & Operating Memo Written + (ML20106F987)
- ML20106F988 + (ML20106F988)
- ML20106F999 + (ML20106F999)
- ML20106G001 + (ML20106G001)
- ML20106G009 + (ML20106G009)
- ML20106G038 + (ML20106G038)
- ML20106G045 + (ML20106G045)
- ML20106G046 + (ML20106G046)