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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
- 0CAN018905, Responds to Violations Noted in Insp Repts 50-313/88-26 & 50-368/88-26.Corrective Actions:Procedure Rev Effort Initiated in Mar 1988 to Consolidate Procedures Associated W/Design Control Process & Will Address Reorganization + (ML20235U741)
- IR 05000289/1987009 + (ML20235U742)
- ML20235U743 + (ML20235U743)
- ML20235U744 + (ML20235U744)
- ML20235U745 + (ML20235U745)
- ML20235U746 + (ML20235U746)
- 3F1087-10, Monthly Operating Rept for Sept 1987 + (ML20235U747)
- ML20235U748 + (ML20235U748)
- RBG-26763, Forwards Proposed Draft Outline for Hydrogen Control Rept, in Response to NRC 870909 Request.Util Revising Schedule for Submittal of plant-specific Hydrogen Control Analysis to 6 Months Following Issuance of SER on Topical Rept HGN-112 + (ML20235U750)
- 05000313/LER-1988-009, :on 880922,three Inoperable Snubbers Discovered on safety-related Piping Sys.One Snubber Failed Due to Spec of Undersized Snubber & Other Two Found W/Inadequate Travel Remaining for Thermal Growth + (ML20235U751)
- ML20235U752 + (ML20235U752)
- ML20235U753 + (ML20235U753)
- ML20235U754 + (ML20235U754)
- ML20235U756 + (ML20235U756)
- ML20235U757 + (ML20235U757)
- 05000369/LER-1987-011-02, :on 870610,leak Rate Testing of Containment Electrical Penetrations Not Performed.Caused by Inadequate Administrative Controls Surveillance Testing.Leak Rate Test Procedures Corrected + (ML20235U759)
- ML20235U760 + (ML20235U760)
- ML20235U763 + (ML20235U763)
- ML20235U764 + (ML20235U764)
- ML20235U765 + (ML20235U765)
- 05000456/LER-1987-045, :on 870908,process Computer Rebooted,Causing Axial Flux Difference Monitor Alarm to Be Inoperable.Caused by Failure of Engineer to Realize That Rebooting Renders Computer Inoperable.Surveillance Initiated + (ML20235U766)
- ML20235U771 + (ML20235U771)
- AECM-87-0189, Application for Amend to License NPF-29,changing Tech Specs to Support Cycle 3 Reload.Description,Justification,Nshc Determination,Reload Summary Rept,Proposed Startup Physics Test & Advanced Nuclear Fuels Corp Repts Encl.Fee Paid + (ML20235U772)
- IR 05000424/1989005 + (ML20235U778)
- NLS8700473, Responds to NRC 870908 Request for Addl Info Re Util 870817 Response to Violations Noted in Insp Rept 50-298/87-12.SRAB Training Records for 1986 for Five Individuals Encl.Filing & Documentation of Srab Training Improved + (ML20235U780)
- ML20235U782 + (ML20235U782)
- ML20235U783 + (ML20235U783)
- ML20235U784 + (ML20235U784)
- TXX-6805, Interim Deficiency Rept CP-87-85 Re Degradation of Class 1E Circuits.Initially Reported on 870903.Addl Analysis Needed to Assure That non-Class 1E Safety Sys Inoperable Indication Panel Will Not Degrade Class 1E Circuit.Next Rept on 871211 + (ML20235U786)
- ML20235U787 + (ML20235U787)
- ML20235U789 + (ML20235U789)
- B13158, Requests Extension of Required Analyses in Response to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Required Insp at Facility Expected to Be Performed During Scheduled 890909 Refueling Outage + (ML20235U792)
- 05000395/LER-1987-022, :on 870911,motor-driven Emergency Feedwater Pumps Autostarted Due to Tripping of All Three Pumps.Caused by Personnel Error.Personnel Reindoctrinated to Anticipate Responses to Changing Plant Conditions + (ML20235U794)
- ML20235U796 + (ML20235U796)
- ML20235U798 + (ML20235U798)
- ML20235U801 + (ML20235U801)
- ML20235U803 + (ML20235U803)
- ML20235U804 + (ML20235U804)
- ML20235U806 + (ML20235U806)
- TXX-6813, Interim Deficiency Rept CP-87-33 Re Rotational of Auxiliary Feedwater Pump Motor Cooling Fans.Initially Reported on 870708.Evaluation Continuing.Submittal of Next Rept Anticipated by 871202 + (ML20235U807)
- ML20235U809 + (ML20235U809)
- ML20235U810 + (ML20235U810)
- ML20235U812 + (ML20235U812)
- IR 05000454/1989001 + (ML20235U813)
- ML20235U816 + (ML20235U816)
- ML20235U818 + (ML20235U818)
- ML20235U819 + (ML20235U819)
- ML20235U820 + (ML20235U820)
- 05000482/LER-1989-004, :on 890202,reactor Trip Occurred from 100% Power as Result of Steam Generator Reaching lo-lo Level Trip Setpoint.Caused by Loose Screw on Terminal Strip in Solid State Protection Sys.Other Cabinets Checked + (ML20235U822)
- ML20235U823 + (ML20235U823)
- ML20235U824 + (ML20235U824)