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Issue date | Title | Topic | |
---|---|---|---|
ML17059B513 | 30 April 1997 | Non-proprietary Version of Rev 1 to Shroud Repair Anomalies NMP Unit 1,RF014. | Safe Shutdown Stress corrosion cracking Flow Induced Vibration |
ML17059B512 | 30 April 1997 | Non-proprietary Version of Rev 1 to Design Rept for Improved Shroud Repair Lower Support Latches. | Finite Element Analysis Earthquake Flow Induced Vibration |
ML18040A155 | 24 February 1995 | Suppl 1 to GE-NE-B13-01739-04, Nine Mile Unit 1 Shroud. | Finite Element Analysis |
ML17059A522 | 4 November 1994 | Structural Evaluation & Justification of Nine Mile Point 1 Core Shroud for Continued Operation. | Intergranular Stress Corrosion Cracking Stress corrosion cracking |
ML20077M518 | 13 September 1994 | Fatigue Evaluation Power Uprate Operating Conditions, Rev 1 | Power Uprate |
ML18038A401 | 29 January 1988 | Mark I Torus Shell & Vent Sys Thickness Requirements for Nine Mile Point Unit 1 Nuclear Station. Viewgraphs & Agenda Encl | |
ML18038A758 | 30 September 1987 | Nonproprietary Suppl 1 to Nine Mile Point Unit 1 Safer/ CORECOOL/GESTR-LOCA,LOCA Accident Analysis. | |
ML20237D829 | 30 June 1987 | Nonproprietary Nine Mile Point Unit 1 SAFER/CORECOOL/GESTR- LOCA LOCA Accident Analysis | Stroke time |
ML17053A758 | 28 June 1979 | Extended Load Line Limit Analysis,License Amend Submittal (Cycle 6). | |
ML20062D396 | 24 June 1977 | RWR-1tm Radwaste Vol Reduction Sys. Describes RWR-1tm Vol Reduction Sys for Appl to Radioactive Waste Produced at Nuc Elec Generating Station Utilizing Fluidized Bed to Calcine Liquids & Incinerate Solids | |
ML17053A858 | 29 April 1969 | Addendum I to Test Rept of Limitorque Valve Actuator in Nuclear Reactor Containment Environ,Prepared by Philadelpha Gear Corp.Forwarding Ltr Encl | Environment Report |
ML17053A857 | 30 November 1968 | Rept Re Limitorque Valve Operator Test Under Simulated Reactor Containment post-accident Steam & Chemical.Prepared for Philadelphia Gear Corp | Boric Acid |