Search by property

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

• ML20101L092  + (ML20101L092)
• ML20101L096  + (ML20101L096)
• ML20101L098  + (ML20101L098)
• ML20101L104  + (ML20101L104)
• ML20101L107  + (ML20101L107)
• 05000285/LER-1992-020, :on 920601,determined That Operators Failed to Obtain Appropriate Grab Samples During Radiation Monitor Inoperability.Caused by Procedural Inadequacies.Procedure Upgraded & Personnel Trained Re Monitors  + (ML20101L120)
• ML20101L126  + (ML20101L126)
• ST-HL-AE-1153, Revised Final Deficiency Rept Re Rejectable Indications in Welds in Essential Cws.Initially Reported on 800312. Evaluation of Reexam Data Concluded Replacement Unnecessary for 12 Inaccessible Welds  + (ML20101L127)
• ML20101L131  + (ML20101L131)
• ML20101L135  + (ML20101L135)
• 05000331/LER-1984-042, :on 841123,reactor Scram Occurred as Result of Loss of Nonvital Buses.Caused by Transformer Trip from Spurious Fire Protection Deluge Sys Activation.Deluge Sys Modified  + (ML20101L141)
• ML20101L151  + (ML20101L151)
• ML20101L157  + (ML20101L157)
• ML20101L161  + (ML20101L161)
• ML20101L163  + (ML20101L163)
• ML20101L167  + (ML20101L167)
• ML20101L175  + (ML20101L175)
• ML20101L178  + (ML20101L178)
• BECO-92-070, Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,Consisting of NRC-approved Insp Program Governed by Procedures & Encl TS  + (ML20101L181)
• ML20101L185  + (ML20101L185)
• ML20101L186  + (ML20101L186)
• 05000369/LER-1992-007, :on 920506,ESF Actuation Occurred While Control Room Personnel Performing Wet Layup Evolution on SG 1D. Caused by Defective Procedure & Inappropriate Personnel Action.Procedure Revised  + (ML20101L189)
• HL-2280, Suppls Containing Commitments to Comply W/Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance,Per Findings in Insp Repts 50-321/92-04 & 50-366/92-04.Exceptions for in Situ Testing Discussed  + (ML20101L192)
• ML20101L193  + (ML20101L193)
• ML20101L199  + (ML20101L199)

• ML20101L205  + (ML20101L205)

• ML20101L211  + (ML20101L211)
• ELV-03871, Provides Info Describing Deviations from Approved Fire Protection Program Resulting from Plant Review in Response to NRC Bulletin 92-001,per 920626 Conversation W/Nrc. Transient Combustibles Limited Inside Containment  + (ML20101L213)
• ML20101L229  + (ML20101L229)
• PY-CEI-NRR-1500, Forwards Response to Rev 1 to Generic Ltr 92-01, Reactor Vessel Structural Integrity. Util Utilized Assistance of GE to Performed Technical Analysis to Predict Effects of Neutron Irradiation on Reactor Vessel Matls  + (ML20101L250)
• ML20101L251  + (ML20101L251)
• ML20101L255  + (ML20101L255)
• BVY-92-072, Responds to NRC Re Violations Noted in Insp Rept 50-271/92-08 on 920413-17.Corrective Actions:Supervisor Counseled on Importance of Compliance W/All Applicable Procedures,Policies & Correct Method to Initiate Changes  + (ML20101L262)
• ML20101L275  + (ML20101L275)
• ML20101L277  + (ML20101L277)
• 05000445/LER-1992-012, :on 920603,reactor Shutdown Initiated Per Procedure.Caused by Less than Adequate Procedure Control of Oil Return Valve.Repositioned Valve,Procedure Change Stating Required Position of Valve & Controls Applied  + (ML20101L283)
• ML20101L292  + (ML20101L292)
• ML20101L299  + (ML20101L299)
• ML20101L312  + (ML20101L312)
• ML20101L313  + (ML20101L313)
• 05000457/LER-1992-004-08, :on 920531,during Reactor start-up,both MG Set Tripped.Caused by Voltmeter Readings.Unit 1 MG Set Operator Will Be Tested Dynamically & Bench Testing Will Be Performed on Bov to Determine Self Heating  + (ML20101L322)
• ML20101L330  + (ML20101L330)
• ML20101L334  + (ML20101L334)
• 05000265/LER-1992-002, :on 920103,determined That TS 3.7.A.2.a.2 Limit of 293.75 Scfh Exceeded.Cause Not Determined.Feedwater Checkvalve 2-220-62A Repaired  + (ML20101L344)
• ML20101L345  + (ML20101L345)
• ML20101L348  + (ML20101L348)
• ML20101L349  + (ML20101L349)
• ML20101L357  + (ML20101L357)
• ML20101L359  + (ML20101L359)
• 05000397/LER-1984-124, :on 841203,reactor Scram Occurred Due to Reactor Level Decreasing to Level Strip Setpoint.Caused by Personnel Failure to Follow Procedures for Transfer of Level Control  + (ML20101L362)
• 05000265/LER-1992-003, :on 900205,determined That Measured Leakage Rate of 528.6 Standard Cubic Feet Per Hr Exceeded TS for All Valves.Caused by Excessive Leakage of HPCI Steam Exhaust Check Valve.Valve Replaced  + (ML20101L363)