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

• ML20066G769  + (ML20066G769)
• 05000334/LER-1982-047, Forwards LER 82-047/03L-0  + (ML20066G771)
• ML20066G775  + (ML20066G775)
• ML20066G776  + (ML20066G776)
• ML20066G778  + (ML20066G778)
• TXX-3590, Discusses Intention to Perform Reactor Vessel Insp Per Westinghouse Contract W/O Implementation of Reg Guide 1.150 During Latter Part of First Quarter 1983  + (ML20066G779)
• 05000334/LER-1982-047-03, /03L-0:on 821013,pressurizer Level Channel I Indicator LI-RC-459 Recorded to Be Out of 4% Tolerance Band. Caused by Leaking Instrument Valve Resulting in Loss of Level in Ref Leg of LT-RC-459.Valve Internals Replaced  + (ML20066G782)
• ML20066G790  + (ML20066G790)
• ML20066G795  + (ML20066G795)
• L-82-507, Interim Deficiency Rept 82-021 Re Incorrect RPS Low Flow Input Signals.Initially Reported on 821013.Problem Still Being Reviewed.Final Rept Will Be Provided by 821212  + (ML20066G797)
• ML20066G800  + (ML20066G800)
• ML20066G805  + (ML20066G805)
• ML20066G807  + (ML20066G807)
• ML20066G808  + (ML20066G808)
• ML20066G809  + (ML20066G809)
• ML20066G811  + (ML20066G811)
• ML20066G814  + (ML20066G814)
• ML20066G816  + (ML20066G816)
• ML20066G818  + (ML20066G818)
• ML20066G820  + (ML20066G820)
• ML20066G821  + (ML20066G821)
• ML20066G822  + (ML20066G822)
• ML20066G824  + (ML20066G824)
• ML20066G826  + (ML20066G826)
• ML20066G828  + (ML20066G828)

• 05000219/LER-1982-047, Forwards LER 82-047/03L-0.Detailed Event Analysis Encl  + (ML20066G836)

• 05000374/LER-1990-014-06, :on 901222,smoke Discovered Coming from Front Area of turbine-driven Reactor Feedwater Pump.Caused by Oil Leak on Insulation.Pump Taken off-line for Repair & Vibration Probe Flange Machined  + (ML20066G839)
• ML20066G842  + (ML20066G842)
• JAFP-82-0981, Responds to NRC Re Violations Noted in IE Insp Rept 50-333/82-13.Corrective Actions:Work Halted,Whole Body Counts Taken,Mpc Hours Calculated & Recorded,Personnel Briefed & Followup Pair Samples Taken  + (ML20066G846)
• ML20066G848  + (ML20066G848)
• ML20066G853  + (ML20066G853)
• 05000219/LER-1982-047-03, /03L-0:on 821004,loss of Power to Reactor Protection Sys Motor Generator Set 1 Caused Half Scram. Caused by Burned & Scarred Relay Contacts.Relay Replaced & Sys Returned to Svc.Spare Relays on Order  + (ML20066G854)
• ML20066G857  + (ML20066G857)
• 05000328/LER-1982-122, Forwards LER 82-122/03L-0  + (ML20066G861)
• ML20066G867  + (ML20066G867)
• 05000328/LER-1982-122-03, /03L-0:on 821021,during Mode 1 Operation, Pressurizer Pressure Channel 2-PS-68-323B Declared Defective Due to Loss of Ac Power to Channel.Caused by Defective Fuse Holder Cap.Cap Replaced & Channel Returned to Svc  + (ML20066G869)
• ML20066G879  + (ML20066G879)
• 1CAN029111, Monthly Operating Rept for Jan 1991 for Arkansas Nuclear One Unit 1  + (ML20066G880)
• 05000366/LER-1982-117, Forwards LER 82-117/03L-0  + (ML20066G881)
• ML20066G884  + (ML20066G884)
• ML20066G890  + (ML20066G890)
• 05000277/LER-1982-037-03, /03L-0:on 821012,control Rod Drive Area Smoke Detector Circuit Set Off False Alarm.Caused by Stripped Terminal Screw in Auto Code Box & Loose Connection from Circuitry.Screw Replaced & Connection Tightened  + (ML20066G891)
• ML20066G893  + (ML20066G893)
• ML20066G896  + (ML20066G896)
• 05000366/LER-1982-117-03, /03L-0:on 821017,instrument a of Channel a Did Not Trip at Greater than or Equal to 100 Psig During Ft&C Procedure.Caused by Setpoint Drift in Core Spray Pump Discharge Pressure Instrument.Instrument Calibr  + (ML20066G897)
• ML20066G900  + (ML20066G900)
• ST-HL-AE-3692, Monthly Operating Repts for Jan 1991 for South Texas Project Electric Generating Station Units 1 & 2  + (ML20066G901)
• ML20066G904  + (ML20066G904)
• ND-20-0204, Enclosure 1 - Vogtle Electric Generating Plant (VEGP) Unit 4, Exemption Request 10 CFR Part 50, Appendix E Exercise Requirements  + (ML20066G906)
• ELV-02388, Application for Amends to Licenses NPF-68 & NPF-81,revising Tech Spec 6.4.1.2.Amend Revises Composition of Plant Review Board by Adding Technical Support Dept in Place of Quality Control & Nuclear Safety & Compliance Depts  + (ML20066G907)
• NG-82-2348, Responds to NRC Re Violations Noted in IE Insp Rept 50-331/82-11.Corrective Actions:Operability Test Procedures for HPCI & RCIC Revised & Instruments Used to Measure Inservice Test Quantities Reviewed  + (ML20066G908)