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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
- PLA-3700, Forwards Info Re Organizational Changes in Nuclear Dept as Result of Operational Effectiveness Review.Changes Will Be Reflected in Annual Update to Fsar.Changes Cover Nuclear Maint,Nuclear Security & Nuclear Plant Svcs +
- ML17289A391 +
- ML18036A542 +
- ML071020234 +
- ML18058A406 +
- ML20083R023 +
- ML20100Q457 +
- ML20096A712 +
- ML20094M666 +
- ML20094K178 +
- ML20094K170 +
- ML20094J124 +
- ML20094H592 +
- ML20094H560 +
- ML20090H737 +
- ML20090H058 +
- ML20090H015 +
- ML20090G893 +
- ML20090G511 +
- ML20090G390 +
- ML20090G381 +
- ML20090E908 +
- ML20090E583 +
- ML20090E467 +
- ML20090E224 +
- ML20090D940 +
- ML20128B535 +
- ML20265A766 +
- TAC:M81879 +
- TAC:M81673 +
- ELV-02347, Application for Amends to Licenses NPF-68 & NPF-81,changing TS in Response to Generic Ltr 89-10 to Relocate Procedural Details of Radiological Effluent TS to ODCM & Process Control Program.Draft ODCM & Process Control Program Encl +
- RBG-36584, Forwards Proposed Change to Asiatic Clam Control Program. Approval Requested by 920515 in Order to Allow Implementation of Change Prior to Scheduled Restart of Normal Svc Water Sys as Closed Loop Sys +
- ST-HL-AE-4024, Requests Temporary Waiver of Compliance from TS 3.7.4 & 3.7.14 to Permit Outage Time for One Train of Essential Cooling Water Sys & Essential Chilled Water Sys to Be Extended for Addl 24 H to 96 H +
- U-601941, Submits Revised Repair Schedule for Shutdown Svc Water Sys Temp Regulating Valves,Per Findings Documented in Operational Safety Team Insp Rept 50-461/89-30.Replacement Valves Currently Scheduled for Installation in June 1992 +
- ML20059E547 +
- ML20059E283 +
- ML20059E254 +
- ML20059E212 +
- ML20059E194 +
- ML23156A378 +
- TXX-9206, Forwards Advance FSAR Change to Reclassify Portion of 8 Inch Steam Generator Blowdown Piping & Pipe Supports to Seismic Category II & Permit Relocation of Postulated Breaks to Avoid Unacceptable Interactions +
- ML20261F268 +
- 05000254/LER-1991-039-01, :on 910424,RCIC 1301-49 Pump Discharge Valve Failed to Open.Cause Is Unknown.Valve Disk Manually Cracked Off Seat & Valve Stroked Afterwards +
- 05000254/LER-1992-003-03, :on 920206,Unit 1 HPCI Suction Lube Oil Pressure Relief Line Pipe Hanger Found Outside FSAR Compliance.Cause Unknown.Minor Design Change Initiated to Correct Pipe Hanger Configuration +
- 05000445/LER-1992-003, :on 920203,QA Surveillance Identified Invalid Boron Dilution Event Analyses.Caused by Inadequate Inputs & Methodology by Vendor.Design Basis of Boron Dilution Sys to Be Revised & Deficiencies Addressed +
- 05000298/LER-1992-002, :on 920203 & 4,reactor Vessel Water Setpoint Inaccuracy Resulted from Reference Leg Temp Effects That Had Not Been Correctly Addressed.Setpoint Calculations Were Performed +
- ML20090E048 +
- ML20127D072 +
- 05000280/LER-1992-003-01, :on 920214,incomplete Engineered Safety Features Testing Due to Procedure Deficiency.Testing Procedures Were Changed & Actuation Testing of Low RCS Average Temp Relays Performed Satisfactorily +
- 05000244/LER-1992-002, :on 920203,reactor Trip Occurred W/Reactor at Approx 23% Full Power Just Subsequent to Turbine Trip While at 47% Power.Caused by Lo Lo Level in SG a Due to Design Perturbations.New Setting Calculated +