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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
- ML20129F034 + (ML20129F034)
- ML20129F035 + (ML20129F035)
- 0CAN099605, Informs That Effective 960912,CR Hutchinson Appointed Vice president-operations.Modification of Correspondence Distribution List,Requested + (ML20129F036)
- ML20129F037 + (ML20129F037)
- ML20129F039 + (ML20129F039)
- ML20129F040 + (ML20129F040)
- ML20129F042 + (ML20129F042)
- ML20129F044 + (ML20129F044)
- ML20129F045 + (ML20129F045)
- ML20129F047 + (ML20129F047)
- ML20129F049 + (ML20129F049)
- ML20129F052 + (ML20129F052)
- ML20129F054 + (ML20129F054)
- ML20129F055 + (ML20129F055)
- BVY-96-107, Responds to NRC Re Violations Noted in Insp Rept 50-271/96-07.Corrective Actions:Completed Addl Training of Design Engineering Staff,Completed Review of Current Design Change & Performed Engineering Evaluation + (ML20129F058)
- ML20129F059 + (ML20129F059)
- ML20129F061 + (ML20129F061)
- ML20129F062 + (ML20129F062)
- ML20129F063 + (ML20129F063)
- 05000334/LER-1985-010, :on 850506,reactor Tripped Due to lo-lo Level in Steam Generator B.Caused by Combination of Inadequate Communication Between Reactor & Turbine Operators.Event Discussed W/Appropriate Personnel + (ML20129F064)
- ML20129F065 + (ML20129F065)
- ML20129F066 + (ML20129F066)
- ML20129F068 + (ML20129F068)
- NRC-96-0085, Proposed Tech Specs 3/4.8.4 Re Electrical Equipment Protective Devices + (ML20129F069)
- ST-HL-AE-1257, First Interim Deficiency Rept Re Pipe Support eye-rod Interferences.Initially Reported on 850425.Installation Spec Changed & eye-rod Repair Initiated.Next Rept Will Be Submitted by 850816 + (ML20129F072)
- ML20129F074 + (ML20129F074)
- ML20129F076 + (ML20129F076)
- ML20129F077 + (ML20129F077)
- ML20129F078 + (ML20129F078)
- ML20129F086 + (ML20129F086)
- ML20129F089 + (ML20129F089)
- ML20129F090 + (ML20129F090)
- RBG-21454, Forwards Revised Drywell Break Base Case Analysis. Peak Containment Pressure Calculated for Revised CLASIX-3 Drywell Break Analysis During Hydrogen Release Was 12.7 Psig & Occurred in Wetwell Vol + (ML20129F091)
- ML20129F093 + (ML20129F093)
- ML20129F095 + (ML20129F095)
- ML20129F096 + (ML20129F096)
- ML20129F097 + (ML20129F097)
- ML20129F098 + (ML20129F098)
- ML20129F099 + (ML20129F099)
- ML20129F103 + (ML20129F103)
- DCL-85-222, Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 7 to EP G-2 Re Onsite Emergency Organization & EP G-251 Re Notification of Onsite Emergency organization.W/850708 Release Memo + (ML20129F105)
- ML20129F106 + (ML20129F106)
- ML20129F107 + (ML20129F107)
- ML20129F108 + (ML20129F108)
- ML20129F109 + (ML20129F109)
- PNO-IV-96-053, on 961003,personnel at Refinery Attempted to Disconnect Source Guide Tube Following Exposure. Investigation Was Conducted & State of Ok Was Informed + (ML20129F110)
- ML20129F112 + (ML20129F112)
- ML20129F113 + (ML20129F113)
- 05000249/LER-1985-011, :on 850416,high Radiation Signal from Refueling Floor Radiation Monitors Caused Reactor Bldg Ventilation Sys Trip & Isolation W/Standby Gas Treatment Sys B Automatically Starting + (ML20129F114)
- BVY-96-111, Documents Info Provided During Re License Change Requested That We Revise P. 278 Reference to Include Word Legible in Section 6.13.A.3 + (ML20129F115)
- ML20129F116 + (ML20129F116)