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	Issue date	Title	Topic
ML20199H407	30 June 1997	Non-proprietary,Rev 1 to WCAP-14733, Probabilistic Analysis of Reduction in Turbine Valve Test Frequency for Nuclear Plants W/W BB-269 Turbines W/Steam Chests	Turbine Missile
ML20116M536	22 November 1995	Rv Closure Head Penetration Tube Id Weld Overlay Repair, Westinghouse Owners Group Program Rept	Weld Overlay
ML18151A644	31 October 1995	Response to GL 92-01,Rev 1,Suppl 1 for Virginia Power North Anna Units 1 & 2 Beltline Matls & Surry Units 1 & 2 Rotterdam Beltline Weld Metals.
ML20072T831	31 July 1994	Response to Closure Ltr for NRC GL 92-01,Rev 1
ML20065K148	30 November 1993	Nonproprietary Rev 1 of Heatup & Cooldown Limit Curves for Normal Operation for North Anna Unit 1	Hydrostatic
ML20046B475	31 July 1993	Rev 2 to Non-Proprietary Westinghouse Series 44 & 51 SG Generic Sleeving Rept.
ML20046B450	31 July 1993	Rev 1 to Non-Proprietary Specific Application of Laser Welded Sleeves for North Anna Unit 2 Sg.	Nondestructive Examination
ML18152A041	30 November 1992	Suppl 1 to Pdq Two-Zone Model.	Shutdown Margin
ML20115G670	30 September 1992	Rev 1 to Response to GL 92-01 VEPCO North Anna Unit 1 & North Anna Unit 2	Anticipated operational occurrence Hydrostatic Backfit
ML20095L134	30 April 1992	Nonproprietary North Anna Unit 1 1992 SG Operating Cycle Evaluation	Coast down
ML20096F270	30 April 1992	Nonproprietary North Anna Unit 1 SG Startup Approval Meeting Presentation Matls
ML18151A894	30 November 1991	Reactor Power Distribution Analysis Using Moveable In-Core Detection Sys & Tip/Cecor Computer Code Package.
ML20082N988	31 August 1991	Steam Generator Operating Cycle Evaluation
ML20081L495	28 February 1991	Steam Generator C-3 Startup Approval Meeting Presentation Matls
ML20059L076	31 July 1990	Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code
ML20028H085	31 July 1990	VEP-NAF-1, Pdq Two Zone Model.
ML20012C012	31 January 1990	Analysis of Capsule U from VEPCO North Anna Unit 2 Reactor Vessel Radiation Surveillance Program.
ML20246D764	31 July 1989	Steam Generator Update Tube Bundle Structural Integrity Presentation
ML20012D766	31 May 1989	Nonproprietary North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue.	Flow Induced Vibration
ML20155D168	31 August 1988	Safety Evaluation:Zirconium Base Advanced Cladding Matls Usage in North Anna Unit 1 Demonstration Fuel Assemblies
ML20196C128	31 May 1988	Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation	Hydrostatic
ML20150C515	31 January 1988	Rev 3 to North Anna Units 1 & 2 Reactor Vessel Fluence & Ref Temp PTS Evaluations
ML20235K427	30 September 1987	Nonproprietary North Anna Unit 1 Steam Tube Rupture & Remedial Actions Technical Evaluation	Flow Induced Vibration
ML20236H775	30 September 1987	Cycle 5 Core Performance Rept
ML20235M415	31 May 1987	Cycle 6 Core Performance Rept	Fuel cladding
ML18149A512	30 November 1986	Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code.
ML20213E055	31 August 1986	Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for North Anna Units 1 & 2	Safe Shutdown Safe Shutdown Earthquake Pressure boundary leak
ML20203G548	31 March 1986	Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs	Power change
ML20135H949	31 August 1985	Rev 1 to Reload Nuclear Design Methodology	Boric Acid Shutdown Margin
ML20133H359	31 July 1985	Statistical DNBR Evaluation Methodology
ML20128Q275	31 May 1985	Revised Nomad Code & Model
ML20129E988	30 May 1985	VEPCO Reactor Sys Transient Analysis Using Retran Computer Code	Boric Acid
ML20116N836	30 April 1985	Reactor Vessel Pressure - Temp Limit Curves for VEPCO North Anna Units 1 & 2	Anticipated operational occurrence Hydrostatic
ML18142A153	31 December 1984	Nonproprietary Version of Revised VEPCO Evaluation of Control Rod Ejection Transient.	Shutdown Margin
ML20140D889	31 October 1984	VEPCO Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs	Power change
ML20097D066	31 August 1984	Cycle 3 Core Performance Rept	Fuel cladding
ML20092H474	31 May 1984	Cycle 4 Core Performance Rept	Fuel cladding
ML20095A127	31 October 1983	Analysis of Capsule V,Vepco,North Anna Unit 2,Reactor Vessel Matls Surveillance Program	Hydrostatic
ML18141A258	31 October 1983	Revised Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code.	Fuel cladding
ML20082M885	31 October 1983	Nonproprietary Version of VEPCO Evaluation of Control Rod Ejection Transient	Shutdown Margin
ML20100G262	31 October 1983	Study of Effects of Reduced Number of Thimbles on Results of In-Core Flux Map Analysis
ML20078K336	30 September 1983	VEPCO Nomad Code & Model
ML20065Q458	31 October 1982	Steam Generator Impacted Tube Ends Recovery Evaluation	Hydrostatic
ML18139C061	4 October 1982	Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code.
ML20077J962	31 July 1982	Cycle 3 Core Performance Rept
ML20010B624	31 July 1981	VEPCO Flame Model.
ML20010B617	31 July 1981	Pdq 07 One Zone Model.	Boric Acid Shutdown Margin
ML20010B610	31 July 1981	Pdq 07 Discrete Model.	Boric Acid
ML20095A148	31 May 1981	Analysis of Capsule V,Vepco,North Anna Unit 1,Reactor Vessel Matls Surveillance Program
ML18139B401	30 April 1981	Reload Nuclear Design Methodology.	Shutdown Margin

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