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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
- ML17264A590 +
- Press Release-III-96-048, NRC Augmented Inspection Team to Present Findings at Uranium Fuel Plant in Missouri +
- ML18065A882 +
- ML20117G283 +
- ML20117F237 +
- ML20117E910 +
- ML20117D806 +
- ML20117D705 +
- ML20117D471 +
- ML20137V093 +
- ML20137J964 +
- ML20135A120 +
- ML20147H458 +
- ML20134K087 +
- ML20134K080 +
- ML20129G858 +
- ML20129G104 +
- ML20129E612 +
- ML20128N977 +
- ML20149K077 +
- ML20149J080 +
- ML20237C203 +
- ML20266B095 +
- ML20216F776 +
- U-166242, Functional Diagrams Pressurizer Heater Control.Sheet 12 +
- LIC-96-0129, Forwards Fort Calhoun Station Performance Indicators +
- RC-96-0219, Notifies of Implementation of Current Order Timing Changes & New Current Order Surveillance Test Re GL 93-04, Rod Control System Failure & Withdrawal of Rod Control Cluster Assemblies +
- JAFP-96-0336, Forwards Attachment Ii,Rev 1 to JPN-96-003, Instrumentation & Miscellaneous Sys Se. Changes Made by Rev,Submitted +
- 3F0896-19, Forwards Response to NRC Re Violations Noted in Insp Rept 50-302/96-06.Corrective actions:OP-402 Was Revised on 960702 +
- 3F0896-21, Advises That Util Revising Completion Schedule & Program Content for Plant EOP Enhancement Program +
- ST-HL-AE-5442, Submits List of Changes,Temporary Addendums 4 & 5 & Rev 5A to Physical Security Plan.Encl Withheld +
- NSD-NRC-96-4804, Forwards NRC Policy on Magnitude of Site Specific Seismic Analyses Ground Motion in Response to Action from 960717 Westinghouse/Nrc AP600 Meeting +
- NSD-NRC-96-4803, Forwards Responses to NRC RAIs on AP600 Design Certification Program +
- BSEP-96-0312, Responds to NRC Re Violations Noted in Insp Repts 50-324/96-07 & 50-325/96-07.Corrective Actions:Appropriate Personnel Will Participate in Addl Training Re Emergency Classification & Exercise Weakness and Decision Making +
- ST-HL-AE-5455, Forwards Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, in Response to RAI +
- PY-CEI-NRR-2090, Special Rept:On 960814,channel of Post Accident Monitoring Instrumentation Was Inoperable 24 H More than OOS Time Allowed by Ts.Instrumentation Has Been Repaired & Operable +
- ML20266F353 +
- ML20135B870 +
- 05000352/LER-1996-015, :on 960726,failure to Maintain Equipment Needed for Operator Actions to Assure Fire Safe SD Capability. Caused by Unclear Ownership & Accountability of Procedures. Interim Procedure Revs Implemented +
- 05000382/LER-1996-009-01, :on 960725,failure of Containment Vacuum Relief Valves CVR-402A & CVR-402B Occurred.Caused by Excessive Roughness in Valve Body Bore.Valves Replaced & Retested +
- 05000424/LER-1996-006, :on 960525,RX Trip Occurred Due to Blown Fuse in Main Feedwater Isolation Valve.Fuse Was Replaced & Unit Was Restarted & Returned to Power +
- 05000352/LER-1996-016, :on 960725,core Thermal Power Exceeded Licensed Power Limit During Power Transient.Caused by Defective EHC Sys Component & Reactor Scram.Defective Primary Frequency/ Voltage Converter Replaced & Calibration Performed +
- ML20129E548 +
- ML20129G176 +
- ML20198Q180 +
- ML20198Q173 +
- ML20117H621 +
- ML20132A698 +
- 05000281/LER-1996-005-01, :on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other Tubing +
- IR 05000280/1996007 +