Search by property
Jump to navigation
Jump to search
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
- ML20077G693 + (ML20077G693)
- 05000373/LER-1983-072-03, /03L-0:on 830609,motor Driven Air Compressor for HPCS Diesel 1B Broke.Caused by Loose Head Gasket Blocking Second Stage Discharge Valve.Compressor Repaired & Tested Satisfactorily on 830610 + (ML20077G700)
- ML20077G701 + (ML20077G701)
- 0CAN069101, Forwards Proposed Changes to Tech Specs,Per NRC Request,Re Reactor Vessel Level Monitoring Sys for Units 1 & 2 & Hot Leg Level Measurement Sys for Unit 1.Original Application Submitted on 891026 + (ML20077G712)
- ML20077G716 + (ML20077G716)
- ML20077G720 + (ML20077G720)
- 05000287/LER-1983-008-03, /03L-0:on 830707,during Emergency Safeguards on- Line Test,Valve 3LPSW-565 Failed to Operate.Caused by Mechanical Interlock & Motor Starter Coil Bind.Motor Starter Repaired + (ML20077G730)
- ML20077G731 + (ML20077G731)
- ML20077G732 + (ML20077G732)
- ML20077G735 + (ML20077G735)
- 05000373/LER-1983-068-03, /03L-0:on 830611,during Surveillance LOS-AA-D1, Div I Suppression Pool Temp Recorder Was Not Printing.Caused by Chart Recorder Switch Being in Off Position.Operator Training Conducted + (ML20077G740)
- 05000324/LER-1983-055-03, /03L-0:on 830704,while Performing ECCS Reactor Low Water Level Channel Calibr & Functional Test,Ads Relay 2-B21C-K24 Remained Energized When Test Signal Removed from N031A-3.Caused by Defective Slave Trip Unit + (ML20077G743)
- 05000373/LER-1983-074-03, /03L-0:on 830627,accumulator Trouble Alarm for Control Rod Drive 42-23 Energized.Caused by Collection of Water in Hydraulic Control Unit Level Switch Instrument Block.Block Cleaned & Dried + (ML20077G765)
- 05000346/LER-1981-070-03, Control Rod Drive Trip Breaker B Failed to Trip Consistently During Anticipatory Reactor Trip Sys Trip Test.Caused by Binding in Undervoltage Coil Device Linkage of Trip Breaker + (ML20077G769)
- ML20077G776 + (ML20077G776)
- ML20077G777 + (ML20077G777)
- 05000325/LER-1983-026-03, /03L-0:on 830702,while Securing Diesel Generator 2 from Load Operation,Diesel Tripped Due to Generator Reverse Power Making Automatic Operation Unavailable.Caused by Operator Error.Trip & Lockout Reset + (ML20077G778)
- ML20077G779 + (ML20077G779)
- 05000395/LER-1983-073-03, /03L-0:on 830703,6% Discrepancy Observed Between Main Control Board & Control Room Evacuation Panel Indication for Boric Acid Tank Level.Caused by Instrument Drift on Transmitter LT-163A + (ML20077G780)
- ML20077G789 + (ML20077G789)
- ML20077G794 + (ML20077G794)
- 05000338/LER-1983-039-03, /03L-0:on 830706,w/unit at 100% Power,Containment Inner Personnel Air Lock Had Detectable Seal Leakage.Caused by Improper Setting of Closed Limit Switch on Door.Switch Adjusted.Satisfactory Leak Test Performed + (ML20077G795)
- ML20077G802 + (ML20077G802)
- ML20077G803 + (ML20077G803)
- 05000254/LER-1983-026-03, /03L-0:on 830705,while Performing Main Steam Line High Flow Calibr,Discovered That Pressure Switch DPIS 1-261-2J Tripped at 146% Steam Flow.Probably Caused by Setpoint Drift.Instrument Recalibr + (ML20077G816)
- 05000265/LER-1983-010-03, /03L-0:on 830623,while Performing Standby Gas Treatment Sys Operability Test,Heater Did Not Start Automatically When Train 1/2A Started.Caused by Heater High Temp Switch Trip Due to Incorrect Setpoint + (ML20077G817)
- ML20077G818 + (ML20077G818)
- ML20077G819 + (ML20077G819)
- ML20077G820 + (ML20077G820)
- ML20077G839 + (ML20077G839)
- ML20077G841 + (ML20077G841)
- ML20077G848 + (ML20077G848)
- ML20077G853 + (ML20077G853)
- ML20077G856 + (ML20077G856)
- ML20077G867 + (ML20077G867)
- SNRC-1818, Requests Termination of License NPF-82 & Decommissioning of Facility.Request Made Per Pending Application to Transfer License to Long Island Power Authority + (ML20077G886)
- JPN-91-027, Forwards Response to NRC Request for Addl Info Re 900531 Application for Amend to License DPR-59,changing Tech Specs Covering Spent Fuel Storage Capacity + (ML20077G888)
- ML20077G889 + (ML20077G889)
- ML20077G894 + (ML20077G894)
- ML20077G895 + (ML20077G895)
- RBG-15-558, Interim Deficiency Rept DR-30 Re Interpretation of Radiographs Performed by Bf Shaw Co.Initially Reported on 830624.Condition Upgraded to Reportable.Final Rept Will Be Submitted by 830825 + (ML20077G896)
- 2CAN069104, Application for Amend to License NPF-6,revising Limiting Conditions for Operations for Associated Bases,Per Generic Ltr 87-09 + (ML20077G901)
- ML20077G905 + (ML20077G905)
- W3P83-1784, Forwards Addl Info Requested Per 830104-06 Environ Qualification Audit Re TMI Action Plan NUREG-0737 & Rev 2 to Reg Guide 1.97 + (ML20077G908)
- ML20077G911 + (ML20077G911)
- 1CAN069101, Application for Amend to License DPR-51,changing Tech Specs to Incorporate Recommendations in Generic Ltr 87-09 Re Limiting Condition for Operation Section 3.0.4 & Surveillance Requirement Section 4.0 + (ML20077G912)
- ML20077G916 + (ML20077G916)
- ML20077G917 + (ML20077G917)
- 05000272/LER-1983-008, Supplemental LER 83-008/03X-1:on 830311,pressurizer Code Safety Valves 1PR3,1PR4 & 1PR5 Exceeded Lift Set Pressure Range & Had Heavy Seat Leakage.Partly Caused by Difference in Test Vs Actual Operating Conditions + (ML20077G918)
- 2CAN069108, Forwards Proprietary A-MPS-ER-003, Final Rept on Low Temp Overpressure Protection Pressure-Temp Limits for Arkansas Nuclear One Unit 2 for 21 Effective Full Power Yrs. Rept Withheld (Ref 10CFR2.790(b)(4)) + (ML20077G923)
- HL-1703, Responds to NRC Re Violations Noted in Insp Rept 50-366/91-12.Corrective Actions:Administrative Controls Governing Content,Review & Approval of Safety Evaluations for Design Change Requests Enhanced + (ML20077G924)