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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
- 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)
- U-602643, Forwards Revised Special Assessment:Confirmatory Action Ltr Dtd 960911, Involving 960905-06 Reactor Recirculation Pump Seal Failure & Associated Shutdown at Plant + (ML20129F118)
- ML20129F121 + (ML20129F121)
- 05000388/LER-1985-016-01, :on 850427,water Hammer Caused Reactor Water Level Transient.Caused by Rapid Filling of Partially Drained RHR Piping from Reactor Vessel.Operating Procedure for RHR Being Revised + (ML20129F123)
- 05000352/LER-1985-022, :on 841129,during Fire Damper Insp,Two Reactor Enclosure Fire Penetrations Discovered Unsealed.Caused by Failure to Reinstall Seal After Const Activities.Fire Watch Established.Conduit Penetration Seals Replaced + (ML20129F127)
- ML20129F129 + (ML20129F129)
- ML20129F130 + (ML20129F130)
- ML20129F132 + (ML20129F132)
- ML20129F134 + (ML20129F134)
- ML20129F137 + (ML20129F137)
- ML20129F138 + (ML20129F138)
- ML20129F139 + (ML20129F139)
- ML20129F141 + (ML20129F141)
- ML20129F142 + (ML20129F142)
- ML20129F146 + (ML20129F146)