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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
- ML20090B041 + (ML20090B041)
- ML20090B046 + (ML20090B046)
- ML20090B049 + (ML20090B049)
- ML20090B050 + (ML20090B050)
- ML20090B055 + (ML20090B055)
- ML20090B059 + (ML20090B059)
- SNRC-1058, Proposes Alternative Battery Test Requirements of Sser 5. Proposal Would Reduce SER Battery Svc Test Load Profile from 12 to 7 Start Cycles.Battery Performance Test Will Be Run to Demonstrate 90% of Design Capability + (ML20090B060)
- ML20090B062 + (ML20090B062)
- ML20090B063 + (ML20090B063)
- ML20090B064 + (ML20090B064)
- 05000397/LER-1984-060, :on 840613,reactor Low Water Level Trip Occurred Due to Loss of Feedwater Flow.Caused by Low Suction Pressure Trip of Condensate Booster Pumps.Rcic Sys Manually Initiated to Restore Level + (ML20090B067)
- ML20090B072 + (ML20090B072)
- ML20090B082 + (ML20090B082)
- ML20090B085 + (ML20090B085)
- ML20090B099 + (ML20090B099)
- ML20090B110 + (ML20090B110)
- ML20090B112 + (ML20090B112)
- ML20090B114 + (ML20090B114)
- TXX-9210, Forwards Rev 13 to Comanche Peak Steam Electric Station Emergency Plan. Rev in Ref to Corporate Ofc Emergency Response & Support,Departmental Reorganization & Emergency Response Facility Computer Sys & Digital RMS + (ML20090B115)
- ML20090B116 + (ML20090B116)
- SNRC-1052, Advises of Removal of Fire Door Pressure Actuated Release Mechanisms for Carbon Dioxide Protected Areas.Removal of Release Mechanism in Conjunction W/Electrical Supervision & Tech Spec Surveillance Should Assure Reliability + (ML20090B125)
- ML20090B130 + (ML20090B130)
- 05000261/LER-1984-005-02, :on 840608,complete Circuit for Initiation of Safety Injection Due to High Steam Line Flow Coincident W/ Low Steam Line Pressure or Low RCS Average Temp Not Tested. Cause Not Stated.Testing Will Be Completed + (ML20090B140)
- ML20090B142 + (ML20090B142)
- SNRC-1054, Requests Extension Until 840702 of Due Date for Response to Generic Ltr 84-11, Insp of BWR Stainless Steel Piping. Delay Necessary to Clarify Certain Points of Generic Ltr W/Nrc + (ML20090B144)
- ML20090B151 + (ML20090B151)
- ML20090B156 + (ML20090B156)
- ML20090B180 + (ML20090B180)
- ML20090B184 + (ML20090B184)
- ML20090B188 + (ML20090B188)
- 05000315/LER-1984-009-01, :on 840321,flux Map Indicated That Tech Spec Surveillance Requirement 4.2.2.2.C Exceeded.Caused by self-imposed Conservatisms Resulting in Discrete Drop in Allowable Power Level W/Bank D Inserted + (ML20090B192)
- ML20090B198 + (ML20090B198)
- ML20090B208 + (ML20090B208)
- ML20090B216 + (ML20090B216)
- A04136, Forwards Application Fee for Change to Tech Specs, + (ML20090B222)
- 05000272/LER-1984-015-01, :on 840611,received Notification by Westinghouse of Potential Unreviewed Safety Question Re Consistency Between Safety Analysis & Tech Specs.Procedures for Mode 3 Operation Revised + (ML20090B224)
- ML20090B225 + (ML20090B225)
- ML20090B226 + (ML20090B226)
- ML20090B228 + (ML20090B228)
- ML20090B229 + (ML20090B229)
- 05000272/LER-1984-016, :on 840613,document Control Procedures Submitted Late to Station Operations Review Committee.Caused by Administrative Error.Dept Involved Reminded of Tech Spec Requirement + (ML20090B230)
- ML20090B234 + (ML20090B234)
- ML20090B239 + (ML20090B239)
- 05000369/LER-1992-001-03, :on 920116,orderly Shutdown Commenced as Result of primary-to-secondary Leakage.Caused by Steam Generator Tube 47-46 Leaking 30 Drops Per Minute at Secondary Side.Data Review Conducted + (ML20090B241)
- ML20090B244 + (ML20090B244)
- 05000324/LER-1992-001-03, :on 920129,annunicator for Low Electrohydraulic Fluid Pressure Received.On 920202,switch A1 Tripped & Full Scram Signal Received Causing Reactor Trip.Caused by Excessive Cycling.Reactor Power Reduced + (ML20090B247)
- ML20090B249 + (ML20090B249)
- ML20090B254 + (ML20090B254)
- ML20090B256 + (ML20090B256)
- ML20090B266 + (ML20090B266)
- ML20090B269 + (ML20090B269)