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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
- ML20137Y601 + (ML20137Y601)
- 05000287/LER-1986-001-04, :on 860131,reactor Tripped Due to High RCS Pressure.Caused by Instantaneous Failure of Amplifier in Feedwater Flow Transmitter A1.Unit Stabilized.Amplifier Replaced + (ML20137Y603)
- ML20137Y604 + (ML20137Y604)
- PNO-V-85-066, on 851002,loss of Main Feedwater Event Occurred.Plant Being Maintained in Hot Shutdown Condition Pending Determination of Exact Scenario,Causes & Appropriate Corrective Action.Region Evaluating Response + (ML20137Y605)
- ML20137Y609 + (ML20137Y609)
- 05000366/LER-1986-004, :on 860131,62-day Surveillance Requirement for Fire Detector Alarms Not Met.Caused by Personnel Oversight Resulting in Procedural Deficiency.Procedure 425V-SUV-015-25 Revised + (ML20137Y611)
- ML20137Y613 + (ML20137Y613)
- ML20137Y614 + (ML20137Y614)
- ML20137Y617 + (ML20137Y617)
- ML20137Y618 + (ML20137Y618)
- 05000423/LER-1986-013, :on 860207,feedwater Isolation Signal Received & Reactor Tripped When Steam Generator Level Exceeded 82%. Caused by Large Sys Demand from Lifted Relief Valve in Auxiliary Steam Sys.Valve Setpoint Raised + (ML20137Y619)
- 05000255/LER-1985-016, :on 850830,reactor Trip Initiated by Generator Output Protective Trip.Caused by Personnel Physical Arrangement of Relay Cutouts.Incident Reviewed W/Personnel + (ML20137Y620)
- ML20137Y622 + (ML20137Y622)
- 05000366/LER-1985-020, :on 850726,RWCU Pump Inboard & Outboard Suction Isolation Valves Isolated on High Sys Differential Flow. Caused by Leakage Past RWCU Loop a Resin Strainer Drain Valves.Investigation Continuing + (ML20137Y623)
- ML20137Y624 + (ML20137Y624)
- ML20137Y629 + (ML20137Y629)
- ML20137Y630 + (ML20137Y630)
- ML20137Y631 + (ML20137Y631)
- ML20137Y635 + (ML20137Y635)
- NSD-NRC-97-5071, Responds to NRC Request to Release G-1 & G-2 Blowdown Test Data for Use in Trac Code Validation + (ML20137Y637)
- ML20137Y638 + (ML20137Y638)
- BSEP-97-0147, Forwards Updated MSLB CR Dose Calculation,Per 970228 Commitment + (ML20137Y641)
- ML20137Y643 + (ML20137Y643)
- 05000395/LER-1986-004, :on 860129,missed Readings of Control Board Instrument Channel Operability Checks Discovered,Resulting in Exceeding Tech Spec Surveillance Interval.Caused by Operator Error.Personnel Counseled + (ML20137Y644)
- ML20137Y645 + (ML20137Y645)
- ML20137Y648 + (ML20137Y648)
- ML20137Y649 + (ML20137Y649)
- ML20137Y651 + (ML20137Y651)
- ML20137Y652 + (ML20137Y652)
- ML20137Y654 + (ML20137Y654)
- ML20137Y656 + (ML20137Y656)
- ML20137Y658 + (ML20137Y658)
- 05000261/LER-1985-019-01, :on 850829,reactor Power Increased Above Nine Times Allowable Power Level Prior to Completion of ex-core Calibr Test,Contrary to Tech Spec 3.10.2.9.Calibr Test FMP-011 Revised + (ML20137Y662)
- ML20137Y663 + (ML20137Y663)
- ML20137Y664 + (ML20137Y664)
- ML20137Y665 + (ML20137Y665)
- ML20137Y667 + (ML20137Y667)
- ML20137Y669 + (ML20137Y669)
- 05000254/LER-1996-022-01, Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01 + (ML20137Y670)
- ML20137Y671 + (ML20137Y671)
- RBG-22155, Special Rept Providing Details for Measured Structural Settlement Value Outside Limits of Tech Spec Table 3.7.10-1. Change to FSAR Table 2.5-19 & Tech Spec 3.7.10-1 Will Be Submitted to Revise Predicted Settlement + (ML20137Y673)
- NSD-NRC-97-5059, Forwards Responses to Listed Initial Comments on AP600 Revised Ts,Dtd 961224,as Completion of Open Item Tracking Sys Item 4970 + (ML20137Y674)
- ML20137Y675 + (ML20137Y675)
- ML20137Y677 + (ML20137Y677)
- ML20137Y678 + (ML20137Y678)
- BSEP-97-0135, Application for Amends to Licenses DPR-71 & DPR-62,revising Requirements for Instrumentation Response Time Testing Associated W/Rps,Isolation Actuation Sys & ECCS + (ML20137Y679)
- ML20137Y680 + (ML20137Y680)
- ML20137Y681 + (ML20137Y681)
- ML20137Y682 + (ML20137Y682)
- ML20137Y684 + (ML20137Y684)
- ML20137Y685 + (ML20137Y685)