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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
- 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)
- ML20237A994 + (ML20237A994)
- ML20237A995 + (ML20237A995)
- ML20237A996 + (ML20237A996)
- ML20237A997 + (ML20237A997)
- ML20237A998 + (ML20237A998)
- ML20237A999 + (ML20237A999)
- ML20237B000 + (ML20237B000)
- ML20237B003 + (ML20237B003)
- ML20237B004 + (ML20237B004)
- ML20237B007 + (ML20237B007)
- ML20237B008 + (ML20237B008)
- TXX-7071, Interim Deficiency Rept CP-87-101 Re Class 1E Electrical Circuits W/Multiple Conductor Per Phase Feeders W/Potential to Overheat.Initially Reported on 870910.Evaluation Continuing.Next Rept Will Be Submitted by 880322 + (ML20237B009)
- ML20237B011 + (ML20237B011)
- PY-CEI-NRR-2311, Responds to NRC Re Violations Noted in Insp Rept 50-440/98-11.Corrective Actions:Operability Determination Was Performed Which Concluded That Breakers Covered by Calculation PDRC-007 Would Perform as Required + (ML20237B012)
- ML20237B013 + (ML20237B013)
- ML20237B015 + (ML20237B015)
- ML20237B016 + (ML20237B016)
- ML20237B018 + (ML20237B018)