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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
- Information Notice 1992-55, Current Fire Endurance Test Results for Thermo-Lag Barrier Material +
- IR 05000410/1992019 +
- ML18038A523 +
- ML17157C139 +
- ML17157C138 +
- ML18022A901 +
- ML17306A853 +
- ML17306A854 +
- ML18096A860 +
- ML20099H092 +
- ML20099E044 +
- ML20099C098 +
- ML20099B977 +
- ML20099B969 +
- ML20099B974 +
- ML20099B951 +
- ML20099B930 +
- ML20099B877 +
- ML20099B803 +
- ML20099B488 +
- ML20099B432 +
- ML20105D123 +
- ML20113H943 +
- ML20113H937 +
- ML20113H631 +
- ML20113H627 +
- ML20113H480 +
- ML20141M325 +
- ML20141M309 +
- ML20141M308 +
- ML20126M772 +
- ML20126M697 +
- ML20125E327 +
- IA-92-355, Final Response to FOIA Request for Documents.No Agency Records Subj to Request Have Been Located +
- ML20216B034 +
- B13747, Proposed Tech Specs Section 3.3.3.6 Re Accident Monitoring instrumentation--reactor Vessel Monitoring +
- BECO-92-093, Requests Changes to NPDES Permit MA0003557,changing Listed Part I,Paragraphs A.1.m & A.1.n as indicated.Marked-up Page 5 of NPDES Permit Encl +
- PY-CEI-NRR-1530, Comment Supporting Proposed Rule 10CFR50 Re Minor Mods to Nuclear Power Reactor Event Reporting Requirements +
- 05000321/LER-1992-020, :on 920710,main CR Environ Control Sys Automatically Transferred to Pressurization Mode When CR Air Intake Radiation Monitor Tripped.Caused by Instrument Setpoint Drift.Trip Setpoint Adjusted +
- 05000271/LER-1992-018, :on 920627,during Repairs,Ups Trouble Alarm Received.Caused by Design Weakness in UPS Control Circuitry.Circuitry Was Reviewed & Mod Will Be Implemented Into Both UPS Units +
- 05000445/LER-1992-017, :on 920626,main Steam Supply Valves to AFW Turbine Not Quarterly Close stroke-time Tested.Caused by Procedure Error.Review of Inservice Test Valve Data Will Be Conducted +
- 05000482/LER-1992-011, :on 920626,discovered That Testing Frequency for EDG B Had Not Been Increased to at Least Once Per Seven Days,Per Tss.Caused by Personnel Error.Procedure Adm 01-0244 EDG Reliability... Will Be Revised +
- 05000302/LER-1992-012, :on 920627,valve in RCS Drop Line Closed, Isolating Suction of Operating DHR Pump from RCS & Interrupting Cooling Water Flow to Reactor Core.Caused by Personnel Error.Training Enhanced +
- ML20034E338 +
- ML20127C661 +
- ML20127C448 +
- ML20137M391 +
- ML20044B550 +
- ML20034F568 +
- IR 05000280/1992014 +