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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
ML20059F157	31 October 1993	Nonproprietary Analysis to Determine Relative Tube/Tube Support Plate Displacements Under Steam Line Break Loads for Catawba Unit 1 Sgs
ML20116N053	11 November 1992	Rev 1 to Mark-BW Reload LOCA Analysis for McGuire & Catawba
ML20106A827	30 September 1992	Nonproprietary WCAP-13495, Technical Support for SG Interim Tube Plugging Criteria for Indications at Tube Support Plates,Catawba Unit 1	Stress corrosion cracking
ML20106A293	30 September 1992	Nonproprietary WCAP-13497, Catawba Unit 1 Steam Generator Tube Interim Plugging Criterion Presentation Matls
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
ML20217A662	31 July 1990	DPC Catawba,Unit 1,Reactor Vessel Radiation Surveillance Program
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
ML20006A823	10 January 1990	Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1
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
ML20247H043	13 September 1989	Revised Pages to Reactor Vessel Surveillance Capsule Z Analysis Rept	Hydrostatic
ML19332C153	31 August 1989	Analysis of Capsule X from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program.
ML20042F232	31 August 1989	Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies.
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)
ML20154M242	30 September 1988	Simulate-3 Validation & Verification
ML20154J983	30 April 1988	RCS Flow Anomaly Investigation Rept
ML20237C409	30 November 1987	Nonproprietary Rev 2 to Byron/Braidwood T-Hot Reduction Final Licensing Rept	Boric Acid Loop seal Turbine Missile Fuel cladding Flow Induced Vibration
ML20235T999	30 September 1987	Rev 2 to RTD Bypass Elimination Licensing Rept for Catawba Units 1 & 2	Shutdown Margin Hydrostatic
ML20235V427	31 August 1987	Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co,Catawba 1,Nuclear Station Steam Generators	Boric Acid Safe Shutdown Earthquake Finite Element Analysis Stress corrosion cracking Eddy Current Testing
ML20235Z584	31 May 1987	Nonproprietary Rev 1 to WCAP-11309, Resistance Temp Detector Bypass Elimination Rept for Catawba Units 1 & 2. RCS Nozzle & Thermowell Locations Encl	Hydrostatic
ML18149A512	30 November 1986	Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code.
ML20207H976	30 November 1986	Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Byron 1 & 2 & Braidwood 1 & 2	Hydrostatic Nondestructive Examination
ML20210A605	5 September 1986	Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification
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
ML20155J523	31 May 1986	Rev 1 to Functional Design Requirement for Core Protection Calculator	Anticipated operational occurrence
ML20155J505	31 May 1986	Rev 1 to Functional Design Requirements for Control Element Assembly Calculator	Anticipated operational occurrence
ML20155J491	31 May 1986	Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block	Anticipated operational occurrence
ML20203G548	31 March 1986	Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs	Power change
ML20151Z064	31 January 1986	Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
ML20151Z052	31 January 1986	Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
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
ML20140A682	31 December 1985	Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations

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