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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
- ML20097F807 + (ML20097F807)
- ML20097F816 + (ML20097F816)
- NSD-NRC-96-4640, Provides Response to Sample Problem for Computer Validation Re Containment Vessel Design for AP600.Differences in Modeling Features Mainly Due to Differences in Analytical Uses within Programs + (ML20097F826)
- ML20097F830 + (ML20097F830)
- NSD-NRC-96-4641, Forwards Response to Request for Addl Info for Use of ASME Boiler & Pressure Vessel Code Case N-284,Rev 1 on AP600 Design + (ML20097F831)
- NSD-NRC-96-4645, Forwards Comparison of Use of ASME Code,Section Viii Criteria Versus ASME Code,Section III for Const of Air Storage Tanks for Main Control Room Habitability Sys + (ML20097F835)
- ML20097F838 + (ML20097F838)
- ML20097F843 + (ML20097F843)
- ML20097F844 + (ML20097F844)
- ML20097F858 + (ML20097F858)
- ML20097F861 + (ML20097F861)
- ML20097F875 + (ML20097F875)
- ML20097F887 + (ML20097F887)
- ML20097F889 + (ML20097F889)
- ML20097F897 + (ML20097F897)
- ML20097F899 + (ML20097F899)
- ML20097F909 + (ML20097F909)
- ML20097F914 + (ML20097F914)
- ML20097F915 + (ML20097F915)
- ML20097F919 + (ML20097F919)
- ML20097F936 + (ML20097F936)
- ML20097F940 + (ML20097F940)
- ML20097F949 + (ML20097F949)
- ML20097F956 + (ML20097F956)
- ML20097F960 + (ML20097F960)
- L-95-050, Technical Evaluation Rept on Second 10-Yr Interval ISI Program Plan:Sce,San Onofre Nuclear Generating Station, Units 2 & 3,Docket Numbers 50-361 & 50-362 + (ML20097F968)
- 05000364/LER-1992-006, :on 920515,reactor Trip Occurred When Control Power Fuses in Two of Four Power Range Nuclear Instruments Blew.Caused by Procedural Inadequacy.All Control Power Fuses Were Replaced & Procedure Revised + (ML20097F971)
- ML20097F984 + (ML20097F984)
- ML20097F987 + (ML20097F987)
- ML20097F991 + (ML20097F991)
- ML20097F993 + (ML20097F993)
- BVY-96-009, Monthly Operating Rept for Jan 1996 for Vermont Yankee Nuclear Power Station + (ML20097F995)
- ML20097F998 + (ML20097F998)
- ML20097G001 + (ML20097G001)
- ML20097G006 + (ML20097G006)
- BSEP-96-0051, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves + (ML20097G007)
- 0CAN029605, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves + (ML20097G010)
- LIC-96-0012, Forwards Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves + (ML20097G014)
- ML20097G020 + (ML20097G020)
- NRC-96-0007, Provides Response to Requested 180-day Actions Required by GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves + (ML20097G022)
- ML20097G023 + (ML20097G023)
- LIC-96-0018, Certifies That ANI & Maelu Policies 96134 & Nelia Policy 95087 for on-site Property Damage & Decontamination Insurance Will Be in Force as of 960401 + (ML20097G024)
- ML20097G025 + (ML20097G025)
- RBG-42477, Forwards 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves + (ML20097G026)
- ML20097G029 + (ML20097G029)
- ST-HL-AE-5296, Requests to Update NRC Distribution Lists to Reflect New Title + (ML20097G039)
- ML20097G040 + (ML20097G040)
- 05000298/LER-1995-022, :on 951213,reactor Trip Signal,Esf Occurred. Caused by Personnel Error.Training to Maint Planners Provided to Enhance Ability to Identify & Develop Post Maint Testing Requirements + (ML20097G041)
- ML20097G042 + (ML20097G042)
- U-602547, Discusses Info Re Change to QA Program Re Method Util Plans to Use for Meeting Procedure Adherence Guidelines Contained in ANSI N18.8-1976 + (ML20097G044)
- ML20097G046 + (ML20097G046)