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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
- ML20107F318 + (ML20107F318)
- IR 05000219/1975026 + (ML20107F329)
- ML20107F330 + (ML20107F330)
- 05000352/LER-1996-009, :on 960314,five of Six as-found Setpoint Tests on Main Steam Sys SRVs Found Outside Required Pressure Ranges.Caused by Setpoint Drift Due to Corrosion Induced Bonding.Modified Pilot Disc Installed in SRVs + (ML20107F333)
- ML20107F334 + (ML20107F334)
- ML20107F338 + (ML20107F338)
- ML20107F343 + (ML20107F343)
- 3F0496-18, Forwards Summary of Statistical Analysis Re non-leakage Under Steam Line Break Conditions Based on in-situ Pressure Testing Performed on Facility SG Tubes During Current Refuel Outage 10,related to TS Change Request 203 + (ML20107F358)
- ML20107F360 + (ML20107F360)
- ML20107F363 + (ML20107F363)
- 05000321/LER-1985-010, :on 850116,reactor Scrammed on Reactor Vessel Low Water Level Signal.Caused by Vital Ac Power Supply Trip. Personnel Restored Reactor Level to Normal + (ML20107F371)
- ML20107F378 + (ML20107F378)
- ML20107F382 + (ML20107F382)
- ML20107F384 + (ML20107F384)
- ML20107F385 + (ML20107F385)
- ML20107F391 + (ML20107F391)
- ML20107F401 + (ML20107F401)
- ML20107F429 + (ML20107F429)
- ML20107F434 + (ML20107F434)
- 05000336/LER-1996-013-01, :on 960314,assessed Wide Range Logarithmic Neutron Flux Monitors Nuclear Instrumentation Channels A,B,C & D as Inoperable Due to Potential Susceptability to Common Mode Failure.Replaced Failed Power Supply + (ML20107F436)
- 05000321/LER-1996-004, :on 960323,reactor Pressure Increased & Reactor Automatically Shut Down.Caused by Inadequate Sys Operating Procedure 34SO-N30-001-1S, Main Turbine Operation. Procedures 34SO-N30-001-1S & -2S Revised + (ML20107F438)
- ML20107F442 + (ML20107F442)
- ML20107F445 + (ML20107F445)
- ML20107F457 + (ML20107F457)
- ML20107F460 + (ML20107F460)
- ML20107F463 + (ML20107F463)
- ML20107F468 + (ML20107F468)
- 05000352/LER-1985-009, :on 850112,HPCI Steam Supply Isolation Valve Isolated.Caused by Erratic Output from Temp Switch Due to Poor Connection within Switch.Wire Properly Reconnected & HPCI Declared Operable + (ML20107F472)
- 05000334/LER-1996-001-01, :on 960320,main Steam Valve Setpoints Not within Specification.Caused by Relatively Small Amount of Normal Setpoint Drift.C/A:Main Steam Safety Valve Adjustment Performed + (ML20107F476)
- ML20107F477 + (ML20107F477)
- ML20107F480 + (ML20107F480)
- ML20107F482 + (ML20107F482)
- ML20107F484 + (ML20107F484)
- ML20107F486 + (ML20107F486)
- ML20107F487 + (ML20107F487)
- B15648, Forwards Rev 1 to Calculation M3LOCA94/01048-R3, Eab & LPZ Doses from Millstone Unit 3 Loca + (ML20107F489)
- 05000352/LER-1985-008, :on 850112,reactor Water Cleanup Sys Isolated. Caused by Blown Fuse in Nuclear Supply Shutoff Sys Logic. Fuse Replaced + (ML20107F490)
- AECM-85-0035, Forwards High Groundwater Level Study,Grand Gulf Unit 1, Describing Cause for Exceeding Design Groundwater Level in Response to Concerns Expressed in 841115 Telcon.Change to Design Basis Groundwater Level Unnecessary + (ML20107F495)
- ML20107F499 + (ML20107F499)
- ML20107F501 + (ML20107F501)
- ML20107F506 + (ML20107F506)
- ML20107F507 + (ML20107F507)
- ML20107F508 + (ML20107F508)
- IR 05000219/1975010 + (ML20107F514)
- ML20107F522 + (ML20107F522)
- AECM-85-0023, Forwards Quarterly Status Rept for Oct-Dec 1984 for Degraded Core Accident Hydrogen Control Program + (ML20107F526)
- ML20107F528 + (ML20107F528)
- B11456, Forwards Discussion of Critical Flow Models Used for Subcompartment Analysis,Providing Justification for Use of Homogeneous Equilibrium Model,Per NRC Question 480.9 & SER Open Item 10 + (ML20107F536)
- ML20107F541 + (ML20107F541)
- ML20107F550 + (ML20107F550)
- ML20107F557 + (ML20107F557)