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Issue date | Title | Topic | |
---|---|---|---|
ML20211B128 | 31 August 1999 | Dynamic Rod Worth Measurement Using Casmo/Simulate | |
ML20211F344 | 17 August 1999 | Updated non-proprietary Page 2-4 of TR DPC-NE-2009 | |
ML20196L188 | 31 May 1999 | Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology | GOTHIC |
ML20236U160 | 31 July 1998 | Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept | Anticipated operational occurrence Fuel cladding |
ML20202D192 | 31 December 1997 | Rev 2 to UFSAR Chapter 15 Transient Analysis Methodology | Boric Acid Shutdown Margin Loop seal Fuel cladding Coast down Manual Operator Action |
ML20197J301 | 30 November 1997 | Non-proprietary TR DPC-NE-3004-A, Mass & Energy Release & Containment Response Methodology | Shutdown Margin GOTHIC Power Uprate |
ML20248L263 | 20 February 1997 | Non-proprietary Version of DPC-NE-2004-A, Duke Power Co McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 | Power change Affidavit |
ML20108D209 | 30 April 1996 | Nonproprietary App C, Mcguire/Catawba Plant Specific Data Mark-BW Fuel BWU-Z CHF Correlation to DPC Thermal- Hydraulic Statistical Core Design Methodology | |
ML20107M893 | 31 October 1995 | Nonproprietary DPC Fuel Reconstitution Analysis Methodology | Anticipated operational occurrence Safe Shutdown Earthquake Earthquake Fuel cladding Affidavit Depleted uranium |
ML20073J915 | 19 September 1994 | Replacement Steam Generator Topical Rept | Safe Shutdown Boric Acid Non-Destructive Examination Anticipated operational occurrence Commercial Grade Dedication Safe Shutdown Earthquake Weld Overlay Hydrostatic Nondestructive Examination Finite Element Analysis Condition Adverse to Quality Design basis earthquake Stress corrosion cracking Eddy Current Testing Code Reconciliation Earthquake Fuel cladding Liquid penetrant Flow Induced Vibration Thermal fatigue |
ML20070K071 | 30 June 1994 | Rev 1 to FSAR Chapter 15 Sys Transient Analysis Methodology | Fuel cladding Manual Operator Action |
ML20065D806 | 28 February 1994 | Analysis of Capsule V Specimens & Dosimeters & Analysis of Capsule Z Dosimeters from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program | Hydrostatic |
ML20064M452 | 28 February 1994 | WCAP-13948, Evaluation of Pressurized Thermal Shock for McGuire Unit 1 | |
ML20116N053 | 11 November 1992 | Rev 1 to Mark-BW Reload LOCA Analysis for McGuire & Catawba | |
ML20114A977 | 31 December 1991 | Nonproprietary McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 | Power change Affidavit |
ML20114A991 | 30 November 1991 | Nonproprietary Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology | |
ML20114A971 | 30 November 1991 | FSAR Chapter 15 Sys Transient Analysis Methodology | Boric Acid Shutdown Margin Fuel cladding Coast down Affidavit |
ML20065M738 | 30 November 1990 | Mark-BW Reload LOCA Analysis for Catawba & McGuire Units | Boric Acid |
ML20073H628 | 31 January 1990 | Nonproprietary Topical Rept DPC-NE-2001-A, Fuel Mechanical Reload Analysis Methodology for Mark-BW Fuel, Rev 1 | Fuel cladding Power change Flow Induced Vibration |
ML20011E254 | 31 December 1989 | ARROTTA-HERMITE Code Comparison, Final Rept | |
ML19351A419 | 30 September 1989 | Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. | Boric Acid |
ML20042F232 | 31 August 1989 | Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. | |
ML19332C153 | 31 August 1989 | Analysis of Capsule X from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program. | |
ML20235M911 | 20 February 1989 | Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue | Flow Induced Vibration |
ML20207L778 | 6 October 1988 | Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue | Finite Element Analysis Flow Induced Vibration |
ML20207L926 | 30 September 1988 | Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) | |
ML20212B884 | 31 July 1986 | Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators | Boric Acid Safe Shutdown Earthquake Finite Element Analysis Stress corrosion cracking Eddy Current Testing |
ML20137L059 | 31 December 1985 | Nonproprietary Supplementary Info to WCAP-10585, Technical Bases for Eliminating Large Primary Loop Pipe Rupture on Structural Region Bases for McGuire Units 1 & 2 | |
ML20127K138 | 30 June 1985 | Nuclear Physics Methodology for Reload Design | |
ML20100H458 | 28 February 1985 | Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program | Hydrostatic |
ML20093N081 | 19 October 1984 | App a to Topical Rept DPC-NF-2010, Code Summary | FLEX |
ML20135E269 | 30 June 1984 | Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases for McGuire Units 1 & 2 | Safe Shutdown Earthquake Stress corrosion cracking Pressure boundary leak |
ML20092N576 | 30 June 1984 | Nonproprietary Technical Basis for Eliminating RHR Line Rupture as Structural Design Basis for Catawba Units 1 & 2 & McGuire Units 1 & 2 | Safe Shutdown Safe Shutdown Earthquake |
ML20078C241 | 31 July 1983 | Nonproprietary Preliminary Version of McGuire Post-Mod Steam Generator Tube Vibration Monitoring Program | |
ML19331C692 | 31 July 1980 | Reliability Analysis of Auxiliary Feedwater Sys for McGuire Nuclear Station Unit 1. | Safe Shutdown Safe Shutdown Earthquake Earthquake |