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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-1980-024-03, During Performance of ASME Operability Test on RHR Svc Water Pumps,D Pump Flow Dropped.Caused by Debris Drawn Into Suction of Pump.Intake Structure Cleaned & Dredged + (ML20064K995)
- ML20064K997 + (ML20064K997)
- ML20064L004 + (ML20064L004)
- ML20064L005 + (ML20064L005)
- ML20064L006 + (ML20064L006)
- ML20064L009 + (ML20064L009)
- 05000416/LER-1983-006, Forwards LER 83-006/03L-0 + (ML20064L011)
- ML20064L025 + (ML20064L025)
- 05000366/LER-1980-126, Forwards Updated LER 80-126/03X-1 + (ML20064L036)
- BSEP-94-0103, Special Rept 1-SR-94-002:on 940226,fire Barrier Penetration Between EDG Bldg & Diesel Fuel Oil Day Storage Tank Room Opened.Fire Watch Stationed Prior to Opening Penetration & Remained in Place Until Penetration Fire Seal Operable + (ML20064L038)
- ML20064L041 + (ML20064L041)
- 05000416/LER-1983-006-03, /03L-0:on 830112,fire Doors OC714 & OCT10 Temporarily Blocked Open to Facilitate Planned Maint.Fire Watch Posted & Doors Closed at Completion of Work + (ML20064L044)
- ML20064L049 + (ML20064L049)
- ML20064L052 + (ML20064L052)
- 05000416/LER-1983-010, Forwards LER 83-010/99X-0 + (ML20064L055)
- ML20064L056 + (ML20064L056)
- ML20064L057 + (ML20064L057)
- ML20064L061 + (ML20064L061)
- 2CAN039402, Provides Overview of Program Re Steam Generator Tubes Research Plan.Complete Description of Planned Program Included in Attachment + (ML20064L062)
- 05000366/LER-1981-046, Forwards Updated LER 81-046/03X-1 + (ML20064L069)
- ML20064L071 + (ML20064L071)
- 05000366/LER-1980-126-03, Primary Containment Hydrogen & Oxygen Analyzer a Discovered Inoperable.Caused by Insufficient Reagent Gas Flow Through Flowmeter.Gas Flow Increased + (ML20064L074)
- 05000366/LER-1981-046-03, Max Attainable Flow in Water Pump 2C Found to Be 5,600 Gpm While Performing ASME Inservice Operability Test.Caused by Normal Operational Wear.Pump Rebuilt & Returned to Svc + (ML20064L078)
- PY-CEI-NRR-1774, Responds to NRC Re Violations Noted in Insp Rept 50-440/93-23 on 931219-940129.Corrective Actions:Restored Continuous Reactor Water Conductivity Measurement on 940116 & Human Performance Enhancement Sys Evaluation Initiated + (ML20064L085)
- LG-83-049, Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established + (ML20064L089)
- ML20064L092 + (ML20064L092)
- 05000416/LER-1982-187, Forwards LER 82-187/99X-0 + (ML20064L094)
- 05000254/LER-1983-001, Forwards LER 83-001/03L-0 + (ML20064L107)
- 05000416/LER-1982-187-99, /99X-0:on 821229,smoke Detection Zone Covering Auxiliary Bldg Corridors at 166-ft Elevation Alarmed & Would Not Reset.Caused by Accumulation of Dust in Detector. Detector Cleaned,Functionally Tested & Returned to Svc + (ML20064L110)
- 1CAN028306, Submits Updated Info Re Status of Ongoing Steam Generator Tube Inservice insps.Once-through Steam Generator Tube Sheet Maps,Defective Tube Summary & Summary of Operational History of Previous Cycle Encl + (ML20064L113)
- ML20064L117 + (ML20064L117)
- 05000324/LER-1983-004, Forwards LER 83-004/03L-0 + (ML20064L118)
- ML20064L123 + (ML20064L123)
- 05000366/LER-1980-150, Forwards Updated LER 80-150/03X-1 + (ML20064L124)
- ML20064L125 + (ML20064L125)
- 05000254/LER-1983-001-03, /03L-0:on 830104,diesel Generator 1/2 Tripped on High Crankcase Pressure Signal.Caused by Lubricating Oil Splashing on Pressure Sensor Upon Startup.Sensor Replaced + (ML20064L127)
- ML20064L128 + (ML20064L128)
- ML20064L131 + (ML20064L131)
- 05000440/LER-1994-007, :on 940217,passive Seismic Instrument Failure Occurred Due to Intrusion of Water.Affected Instrument, Peak Acceleration Recorder Replaced + (ML20064L132)
- ML20064L134 + (ML20064L134)
- ML20064L137 + (ML20064L137)
- 05000324/LER-1983-004-03, /03L-0:on 830105,during Jumper Installation, Reactor Protection Sys Relay C72-K6C Found Melted Around Coil.Caused by Overheating of Relay.Relays to Be Inspected Monthly Until Replaced W/Improved Components + (ML20064L142)
- L-94-009, Forwards Revised ASME Section XI Pressure Test Program Relief Request PTP-3-03.Relief Request Revised to Include 100% Volmetric Exam of Welded Joints Associated W/Repair as Part of Proposed Alternate Requirement + (ML20064L145)
- NRC-94-4079, Advises That Review of Proprietary Matl NRC RAI on AP600 Received in ,Indicates That RAI Contains No Info Westinghouse Considers Proprietary + (ML20064L147)
- ML20064L148 + (ML20064L148)
- ML20064L151 + (ML20064L151)
- 05000366/LER-1980-147, Forwards Updated LER 80-147/03X-1 + (ML20064L154)
- 05000336/LER-1994-003-02, :on 940218,degration of Sychronizing Capability Between Inverters Potential to Invalidate Assumption for Main Stream Line Break.Adjustments Made to Underfrequency Frequency Limiter Circuit + (ML20064L160)
- 05000366/LER-1980-150-03, HPCI Steamline Pressure a Logic Did Not Auto Isolate Until 89 Psig.Possibly Caused by Switches Not Environmentally Qualified.Switches to Be Replaced by Analog Transmitter Sys + (ML20064L164)
- ML20064L166 + (ML20064L166)
- ML20064L167 + (ML20064L167)