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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
- 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)
- B13870, Suppls 900926 Request for Relief from ASME Code,Section XI for Temporary Noncode Repair to Pipe 3SWP*EJ10A.Extension Until 910815 Requested to Allow Continued Use of Temporary Rubber Expansion Joint in Pipe + (ML20077G926)
- ML20077G930 + (ML20077G930)
- ML20077G931 + (ML20077G931)
- RBG-35251, Application for Amend to License NPF-47,revising Test Frequency Requirements for Diesel Generators Identified in Tech Spec 3/4.8.1.1 + (ML20077G933)
- ML20077G935 + (ML20077G935)
- ML20077G938 + (ML20077G938)
- ML20077G949 + (ML20077G949)
- L-83-387, Responds to NRC Re Violations Noted in IE Insp Repts 50-250/83-09 & 50-251/83-09.Corrective Actions: Training Dept Will Review Requirements Re Resetting Horn Disable Light W/Licensed Operators + (ML20077G958)
- ML20077G960 + (ML20077G960)
- ML20077G962 + (ML20077G962)
- ML20077G963 + (ML20077G963)
- L-83-411, Informs That Util Completed Balance of Actions Requested in Action Item 4 of IE Bulletin 82-02 Re Maint Procedures for Threaded Fasteners + (ML20077G964)
- RBG-15-547, Interim Deficiency Rept DR-118 Re Insufficient Penetration of Welds for Platform Channels on Primary Shield Wall.Addl QA Info Needed to Complete Evaluation.Interim or Final Rept Will Be Provided by 830914 + (ML20077G965)
- BVY-91-062, Forwards Suppl to Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters,1990,Including Annual Radiological Impact on Man for 1990 + (ML20077G972)
- ML20077G974 + (ML20077G974)
- ML20077G976 + (ML20077G976)
- 2CAN069116, Forwards Arkansas Nuclear One,Unit II Reactor Containment Integrated Leakage Rate Test. Test Performed During Eighth Refueling Outage + (ML20077G978)
- ML20077G980 + (ML20077G980)
- ML20077G986 + (ML20077G986)
- ML20077G989 + (ML20077G989)
- ML20077G990 + (ML20077G990)
- ML20077G994 + (ML20077G994)
- ML20077G995 + (ML20077G995)
- ML20077G997 + (ML20077G997)