Pages that link to "05000289/LER-1997-006-02, Re Unqualified Cable Terminations.Ler 97-006-00 Retracted"
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The following pages link to 05000289/LER-1997-006-02, Re Unqualified Cable Terminations.Ler 97-006-00 Retracted:
Displayed 15 items.
- 05000289/LER-1997-006, Forwards LER 97-006-00,resulting from Violation of TS 3.3 & Declaring Reactor Bldg fans,AH-E-1B & C,Inoperable on 970424 (← links)
- ML20195K282 (← links)
- 05000289/LER-1997-009, Forwards LER 97-009-00,re Condition Which Was Evaluated & Determined to Be Reportable on 970725.Condition Was Identified as Result of Review of Crystal River 3 LER for Applicability at TMI-1 (← links)
- 05000289/LER-1997-003-01, Forwards LER 97-003-01 Re Potential Overpressurization of Makeup Pump Suction Piping,Due to Inadequate Test & Operating Procedures (← links)
- 05000289/LER-1997-009-01, :on 970725,engineering Analysis of Loss of a Train DC Power W/Loss of Offsite Power & LOCA Was Determined.Caused by Plant Designers Error.Trained Operators on Methodology to Regain Control of Es Equipment (← links)
- 05000289/LER-1997-005, Has Been Cancelled (← links)
- ML20202E082 (redirect page) (← links)
- 05000289/LER-1997-006-02 (redirect page) (← links)
- 05000289/LER-1997-010-01, :on 971012,PORV Inoperability Was Determined. Caused by mis-wiring & Failure to Perform post-maintenance Test Following Replacement During 11R Refueling Outage.Porv Replaced During 12R Refueling Outage Was Wired Correctly (← links)
- 05000289/LER-1997-008, :on 970621,power to Control Rod Drive Mechanisms Was Lost & Reactor Tripped.Caused by Long Trip Insertion Times at Tmi.Rods Were Trip Tested Per Surveillance Procedure 1303.11.1 (← links)
- 05000289/LER-1997-006-01, :on 970424,reactor Bldg Fan Motors Unqualified Cable Termination Occurred Due to Incorrect Engineering Guidance.Caused by Personnel Error.Qualifiable Repair of AH-E-1A Fan Motor Termination Was Installed on 970323 (← links)
- 05000289/LER-1997-005-01, :on 970410,declared motor-operated Reactor Bldg Purge Valves Inoperable Due to Inadequate Closing Torque. Caused by Deficient Design Analysis.Will Perform Evaluation of Valve Specific Seating Torque Test Data (← links)
- 05000289/LER-1997-002, :on 970129,potential Inability of Startup Feedwater Block Valves to Fully Close Following Main Steam Line Break Occurred Due to MOV Program Weakness.Increased Torque Switch Settings on Valve Operators (← links)
- 05000289/LER-1997-001-01, :on 970117,potential Overpressurization of Piping Between Closed Reactor Building Isolation Valves Occurred Due to Inadequate Design Code Guidance.Results of This Review Will Be Documented (← links)
- 05000289/LER-1997-001-02, :on 970117,potential Overpressurization of Piping Between Closed Reactor Building Containment Isolation Valves Occurred Due to Inadequate Design Code Guidance. Results of Review Will Be Documented.Pages 2 & 3 Corrected (← links)