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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
- ML20077F154 + (ML20077F154)
- ML20077F155 + (ML20077F155)
- ML20077F158 + (ML20077F158)
- ML20077F162 + (ML20077F162)
- ML20077F165 + (ML20077F165)
- ML20077F166 + (ML20077F166)
- NRC-94-0113, Provides Results of QA Review + (ML20077F168)
- ML20077F170 + (ML20077F170)
- 05000254/LER-1994-014-05, :on 941107,twelve Instrument Maint Dept Fire Surveillance Exceeded Critical Dates.Caused by Lack of Training in Use of Stations General Surveillance Database for Im Dept Schedulers + (ML20077F176)
- ML20077F177 + (ML20077F177)
- ML20077F180 + (ML20077F180)
- ML20077F193 + (ML20077F193)
- ML20077F195 + (ML20077F195)
- ML20077F196 + (ML20077F196)
- ML20077F200 + (ML20077F200)
- ST-HL-AE-4937, Submits 30 Day Rept Re Significant Changes to Accepted ECCS Evaluation Model at Plant.Summary of Changes Made to Current SBLOCA Evaluation Model Since Last Annual 10CFR50.46 Rept Listed + (ML20077F203)
- ML20077F205 + (ML20077F205)
- 05000285/LER-1994-008, :on 941108,potential for Raw Water Pump Room Flooding Heavy Load Drop Occurred.Caused by Lack of Depth in Evaluation/Review Associated W/Original Load Drop Analysis. Danger Tag Placed to Restrict Use of HE-5 + (ML20077F207)
- ML20077F209 + (ML20077F209)
- 05000424/LER-1993-011, :on 930924,failure to Perform Leak Rate Testing Following Maint Occurred.Caused by Inadequate Safety Evaluation for FSAR Change.Fsar Revised + (ML20077F211)
- ML20077F213 + (ML20077F213)
- ML20077F216 + (ML20077F216)
- ML20077F219 + (ML20077F219)
- U-602379, Monthly Operating Rept for Nov 1994 for Clinton Power Station Unit 1 + (ML20077F224)
- HL-4750, Monthly Operating Repts for Nov 1994 for Ei Hatch Nuclear Plant Units 1 & 2 + (ML20077F226)
- B15052, Responds to NRC Re Violations Noted in Insp Rept 50-423/94-24 on 940817-0926.Corrective Actions:Review Team Established to Explore Potential Failure Mechanisms & to Identify Potential Solutions + (ML20077F227)
- ML20077F231 + (ML20077F231)
- 05000416/LER-1983-052-03, Vessel Head/Vessel Flange Thermocouples Found Not Mounted on Respective Surfaces. Incident Should Not Have Been Reported.Caused by Inadequate Procedures.Procedures Revised + (ML20077F234)
- ML20077F237 + (ML20077F237)
- W3P83-2494, Forwards Response to NRC Re Emergency Plan + (ML20077F238)
- 05000311/LER-1983-032-03, /03L-0:on 830623,large Leak Discovered in Svc Water Bay 2.Caused by Failed Gasket in Joint Downstream of Check Valve 22SW5 Due to Poor Access to Joint.Joint Remade & Design Changed + (ML20077F239)
- ML20077F240 + (ML20077F240)
- PLA-1749, Interim Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 830621.Preliminary Vibration Tests Performed. Also Reportable Per Part 21.Final Rept to Be Issued by Oct + (ML20077F244)
- ML20077F246 + (ML20077F246)
- ML20077F256 + (ML20077F256)
- ML20077F260 + (ML20077F260)
- ML20077F261 + (ML20077F261)
- ML20077F267 + (ML20077F267)
- ML20077F268 + (ML20077F268)
- ML20077F271 + (ML20077F271)
- 05000366/LER-1983-041-03, /03L-0:on 830620,while Performing RPS & ECCS Instrument Valve Lineup,Valves 2B21-N031C R114,2B21-N031D IV1 & IV2 Discovered Closed.Cause Unknown.Valves Returned to Open Position + (ML20077F281)
- ML20077F289 + (ML20077F289)
- ML20077F299 + (ML20077F299)
- RBG-15-490, Final Deficiency Rept DR-113 Re Apparent Misapplication of in-line Cable Splices on Electrical Connections for Hydrogen Igniter Assemblies Not in Accordance W/Heat Shrink Tubing Guide.Condition Not Reportable Per 10CFR50.55(e) + (ML20077F309)
- ML20077F315 + (ML20077F315)
- ML20077F323 + (ML20077F323)
- 05000328/LER-1983-089-03, /03L-0:on 830704,steam Generator 1 Pressure Channel 2-PI-1-1c Failed High.Caused by Failed Transistor in GE Model 5500 Module.Transistor Replaced + (ML20077F331)
- ML20077F332 + (ML20077F332)
- BVY-94-121, Monthly Operating Rept for Nov 1994 for VT Yankee Nuclear Power Station + (ML20077F346)
- 05000244/LER-1983-021-03, /03L-0:on 830618,pressurizer Water Level Dropped Below 12%.Caused by RCS Cooldown After Reactor Trips.Level Restored by Increasing Charging Flow + (ML20077F350)
- ML20077F351 + (ML20077F351)