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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
- NRC-94-0109, Forwards Price-Anderson Act Guarantee of Payment of Deferred Premiums + (ML20078N454)
- ML20078N462 + (ML20078N462)
- 05000374/LER-1995-001-06, :on 950112,unit 2 in Operational Condition 1 at 100% Power,Eccs & Reactor Core Isolation Cooling Low Level Initiation Occurred Resulting in Rcic.Caused by Incorrect Test Vent Valve Being Opened + (ML20078N464)
- 05000334/LER-1983-024-03, /03L-0:on 830918,during Core Subcooling Monitor Surveillance Test to Check Channel Behavior,Monitor Found to Be Reading Erroneously.Caused by Loose Connector within Unit.Connector Repaired + (ML20078N465)
- ML20078N468 + (ML20078N468)
- B15111, Forwards Rev 0 to Millstone Nuclear Power Station Unit 2 COLR Cycle 13 + (ML20078N470)
- ML20078N475 + (ML20078N475)
- BECO-LTR-95-015, Requests Relief from ASME Code,Section Xi,Articles IWC-2500 & IWF-2500 Insp Requirements for Class 2 Rhr/Fpc Intertie Piping Welds & Supports + (ML20078N480)
- 05000318/LER-1983-053-03, /03L-0:on 830914,control Power Fuse for Starter Cabinet Blew,Causing Containment Cooler 21 to Trip.Caused by Rowan 2084-EPRI-1120 Indicating Light Socket Short Circuit. Socket Replaced + (ML20078N481)
- ML20078N486 + (ML20078N486)
- ML20078N489 + (ML20078N489)
- ML20078N492 + (ML20078N492)
- ML20078N501 + (ML20078N501)
- 05000289/LER-1983-028-01, /01T-0:on 830920,manual Inside Containment Isolation Valve IA-V20 in Instrument Air Sys Found Open. Caused by Threaded Stem Bushing Backed Partially Out of Yoke & Paint Buildup on Stem.Parts Replaced + (ML20078N503)
- ML20078N505 + (ML20078N505)
- 05000361/LER-1995-001, :on 950116,two Firewatch Contractors Were Involved in Physical Altercation.Caused by Firewatch Union Accounting/Financial Matter.No Firewatch Postings Were Missed + (ML20078N507)
- ML20078N509 + (ML20078N509)
- ML20078N510 + (ML20078N510)
- 05000280/LER-1983-043-03, LER83-043/03L-0:on 830914,following Reactor Trip,Flow Control Valve (FCV) Failed to Close Upon Receipt of Feedwater Isolation Signal.Caused by Malfunctioning Solenoid Valve & FCV-1488 Restricted by Antirotation Device + (ML20078N512)
- ML20078N513 + (ML20078N513)
- ML20078N524 + (ML20078N524)
- 05000333/LER-1983-037-03, /03L-0:on 830915,while Conducting Surveillance Testing on Drywell High Pressure Switches for Reactor Protection & Auto Depressurization Sys,Setpoint Found Less Conservative That Tech Specs.Setpoint Adjusted + (ML20078N529)
- ML20078N543 + (ML20078N543)
- ML20078N544 + (ML20078N544)
- ML20078N547 + (ML20078N547)
- ML20078N548 + (ML20078N548)
- 05000271/LER-1983-025-01, /01P-0:on 830928,during Normal Operation,Main Steam Line Radiation Monitor RM-17-251A Trip Setpoint Greater than 3 Times Normal Background at Rated Power.Caused by Inadequate Procedure.Trips Reset + (ML20078N574)
- L-94-021, Evaluation of Util Response to Suppl 1 to NRC Bulletin 90-01:Millstone-2/-3 + (ML20078N592)
- ML20078N600 + (ML20078N600)
- 05000275/LER-1983-006, Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically + (ML20078N613)
- B13888, Submits Response to Review of RI-91-A-0037 Issues 1 & 3 Concerning Plant Activities + (ML20078N640)
- ML20078N648 + (ML20078N648)
- ML20078N661 + (ML20078N661)
- ML20078N664 + (ML20078N664)
- ML20078N667 + (ML20078N667)
- ML20078N685 + (ML20078N685)
- ML20078N694 + (ML20078N694)
- ML20078N698 + (ML20078N698)
- ML20078N708 + (ML20078N708)
- ML20078N720 + (ML20078N720)
- ML20078N723 + (ML20078N723)
- ML20078N727 + (ML20078N727)
- A09453, Submits Response to Review of RI-91-A-0033 Issues Concerning Plant Activities + (ML20078N740)
- LD-95-005, Forwards Proprietary Sys 80+ Parameter List for Safety Analyses. Encl Withheld + (ML20078N744)
- ML20078N752 + (ML20078N752)
- ML20078N765 + (ML20078N765)
- BECO-LTR-95-020, Forwards Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test. Secondary Leak Rate Test Satisfactorily Performed 941121.Test Verified Secondary Containment Integrity as Defined by PNPS TS 4.7.C.1 + (ML20078N773)
- ML20078N802 + (ML20078N802)
- ML20078N805 + (ML20078N805)
- ML20078N810 + (ML20078N810)
- ML20078N821 + (ML20078N821)