Search by property

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

• ML20070F084  + (ML20070F084)
• ML20070F090  + (ML20070F090)
• ML20070F092  + (ML20070F092)
• ML20070F096  + (ML20070F096)
• 05000335/LER-1982-053-03, /03L-0:on 821108,while Performing post-maint Surveillance Test of 1C Steam Driven Auxiliary Feedwater Pump,Steam Supply Valve from 1A Steam Generator Failed to Open.Caused by Failure of Contact in Switch  + (ML20070F097)
• B14892, Forwards Rev 0 to Calculation 0024-00099-MOT-01, Selection of Motion for A-46 Evaluation, Per GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46  + (ML20070F104)
• ML20070F106  + (ML20070F106)
• ML20070F109  + (ML20070F109)
• ML20070F112  + (ML20070F112)
• ML20070F114  + (ML20070F114)
• ML20070F118  + (ML20070F118)
• ML20070F122  + (ML20070F122)
• ML20070F125  + (ML20070F125)
• ML20070F126  + (ML20070F126)
• ML20070F128  + (ML20070F128)
• ML20070F135  + (ML20070F135)
• ML20070F139  + (ML20070F139)
• ML20070F142  + (ML20070F142)
• ML20070F147  + (ML20070F147)
• ML20070F148  + (ML20070F148)
• 3F0291-12, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990  + (ML20070F149)
• AECM-82-597, Forwards Monthly Operating Rept for Nov 1982  + (ML20070F155)
• ML20070F161  + (ML20070F161)
• ML20070F163  + (ML20070F163)
• ML20070F166  + (ML20070F166)

• 05000395/LER-1982-043, Forwards LER 82-043/03L-0.Detailed Event Analysis Encl  + (ML20070F182)

• ML20070F190  + (ML20070F190)
• ML20070F196  + (ML20070F196)
• 05000395/LER-1982-043-03, /03L-0:on 821113,nuclear Instrumentation Power Range Channel (N42) low-range Trip Setpoint Found Set at 50% Instead of 25% of Rated Thermal Power.Caused by Personnel error.Low-range Trip Setpoint Reset  + (ML20070F197)
• ML20070F200  + (ML20070F200)
• ML20070F202  + (ML20070F202)
• NRC-94-0058, Monthly Operating Rept for Jun 1994 for Fermi 2  + (ML20070F203)
• ML20070F206  + (ML20070F206)
• ML20070F208  + (ML20070F208)
• ML20070F210  + (ML20070F210)
• ML20070F215  + (ML20070F215)
• ML20070F222  + (ML20070F222)
• 3F0794-05, Monthly Operating Rept for June 1994 for Crystal River Unit 3  + (ML20070F223)
• 05000267/LER-1982-043, Forwards LER 82-043/03L-0.Detailed Event Analysis Encl  + (ML20070F227)
• ML20070F231  + (ML20070F231)
• ML20070F240  + (ML20070F240)
• JAFP-94-0358, Monthly Operating Rept for June 1994 for Ja FitzPatrick Nuclear Power Plant  + (ML20070F241)
• 05000267/LER-1982-043-03, /03L-0:on 821027 & 28,average Pcrv Cooling Water Sys Inlet & Outlet Temps Fell Below 100 F.Caused by Insufficient Heat to Maintain Loop Averages W/Both Loops in Svc.Auxiliary Heat Obtained & Operators Reinstructed  + (ML20070F244)
• ML20070F246  + (ML20070F246)
• ML20070F247  + (ML20070F247)
• ML20070F249  + (ML20070F249)
• NRC-94-4191, Forwards APWR-0452-NP, AP600 Vortex Mitigator Development Test for RCS Mid-Loop Operation, & APWR-0452-P, AP600 Vortex Mitigator Development Test for RCS Mid-Loop Operation. APWR-0452-P Withheld (Ref 10CFR9.17)(a)(4))  + (ML20070F250)
• ML20070F252  + (ML20070F252)
• ML20070F256  + (ML20070F256)
• ML20070F258  + (ML20070F258)
• PY-CEI-NRR-1328, Suppls Response to Generic Ltr 89-13 Re Evaluation of Potential Service Water Sys Degradation Mechanisms & Plans to Implement Various Water Treatment,Performance Monitoring & Insp Activities,Assuring Safety Functions  + (ML20070F259)