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

• ML20237A908  + (ML20237A908)
• ML20237A909  + (ML20237A909)
• ML20237A910  + (ML20237A910)
• ML20237A911  + (ML20237A911)
• ML20237A913  + (ML20237A913)
• ML20237A918  + (ML20237A918)
• 05000317/LER-1987-015, :on 871111,reactor Tripped Due to Transformer. Caused by weather-related Problems.Atmospheric Dump Valve Scheduled for Maint Overhaul & Time Delay Will Be Installed on Auxiliary Feedwater Actuation Setpoint  + (ML20237A920)
• ML20237A921  + (ML20237A921)
• ML20237A922  + (ML20237A922)
• ML20237A924  + (ML20237A924)
• ML20237A926  + (ML20237A926)
• ML20237A930  + (ML20237A930)
• ML20237A931  + (ML20237A931)
• ML20237A932  + (ML20237A932)
• ML20237A934  + (ML20237A934)
• IR 07100018/2011021  + (ML20237A935)
• 05000364/LER-1987-005-01, :on 871111,actuation of ESF Equipment Occurred. Caused by Personnel Error.Personnel Counseled  + (ML20237A936)
• NPL-98-0612, Forwards fitness-for-duty Performance Data for six-month Period Ending 980630,per 10CFR26.71(d).No Reportable Events Occurred During Period  + (ML20237A937)
• ML20237A938  + (ML20237A938)
• ML20237A939  + (ML20237A939)
• ML20237A942  + (ML20237A942)
• ML20237A945  + (ML20237A945)
• NUREG/CR-5247, Forwards Corrected Copy of NRC RASCAL Version 2.2 Dose Projection Software,Software Installations & Users Guide (Supplement 1 to NUREG/CR-5247).W/o Encl  + (ML20237A946)
• ML20237A947  + (ML20237A947)
• ML20237A948  + (ML20237A948)

• ML20237A951  + (ML20237A951)

• 05000458/LER-1998-004, Forwards LER 98-004-00 Addressing Failure to Properly Implement Station Surveillance Test Program.Rept Being Submitted for Industry Review of Generic Applicability  + (ML20237A952)
• ML20237A955  + (ML20237A955)
• 3F0898-10, Forwards Information Only Copy of Rev 59 to EPIP EM-202, Duties of Emergency Coordinator, in Order to Assist in NRC Review of Re Radiological Emergency Response Plan  + (ML20237A956)
• ML20237A957  + (ML20237A957)
• ML20237A958  + (ML20237A958)
• ML20237A960  + (ML20237A960)
• ML20237A962  + (ML20237A962)
• ML20237A963  + (ML20237A963)
• IR 05000498/1987063  + (ML20237A964)
• 05000458/LER-1998-004-03, :on 980514,noted That Surveillance Test Had Not Been Completed for Primary Containment Leakage Rate Testing Program.Caused by Lack of Proper Emphasis on Procedure Step Re Summation.Revised Pertinent Surveillance Procedures  + (ML20237A966)
• AECM-87-0240, Responds to LL Kintner 871204 Request for Info Re Exemption from RWCU Class 1 Analyses.Util Commits to Performing ASME Section Iii,Class 1 Stress Analysis for RWCU Piping Through Sys Valve F253.Results Expected by Jan 1988  + (ML20237A967)
• ML20237A968  + (ML20237A968)
• NOC-AE-000255, Requests That NRC Stop Review of Currently Proposed Amends to Operating Licenses NPF-76 & NPF-80,dtd 980208 Re Spent Fuel Pool Heat Loads  + (ML20237A969)
• IR 05000344/1987040  + (ML20237A970)
• 05000456/LER-1996-010-01, :on 960821,noted Failure to Comply W/Design Basis.Caused by Degradation of Boraflex in Spent Fuel Racks. Implemented Controls on SFP Boron Concentration & Silica Concentration  + (ML20237A972)
• ML20237A974  + (ML20237A974)
• ML20237A976  + (ML20237A976)
• 05000302/LER-1998-008, :on 980716,identified Three Components in Nuclear Svcs & Decay Heat Seawater Sys That Did Not Meet Requirements of ASME Code Section Xi.Caused by Personnel Error.Plant Engineering Performed Operability Determination  + (ML20237A978)
• ML20237A979  + (ML20237A979)
• ML20237A981  + (ML20237A981)
• ML20237A983  + (ML20237A983)
• ML20237A985  + (ML20237A985)
• ML20237A988  + (ML20237A988)
• ML20237A990  + (ML20237A990)
• ML20237A993  + (ML20237A993)