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	Issue date	Title	Topic
ML20248F744	31 May 1998	Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18151A659	31 October 1997	Non-proprietary WCAP-14984, Handbook on Flaw Evaluation Surry Units 1 & 2 SGs Upper Shell to Cone Weld Regions.	Safe Shutdown Earthquake Hydrostatic Finite Element Analysis
ML17353A434	31 October 1995	Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range.
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.
ML17264A118	31 July 1995	Response to Part (1) of GL 92-01,Rev 1,Suppl 1.
ML18152A041	30 November 1992	Suppl 1 to Pdq Two-Zone Model.	Shutdown Margin
ML18153D164	31 December 1991	Demonstration of Compliance of Primary Loop Pump Casings of Surry Units 1 & 2 to ASME Code Case N-481.	Safe Shutdown Earthquake Hydrostatic VT-2
ML18151A894	30 November 1991	Reactor Power Distribution Analysis Using Moveable In-Core Detection Sys & Tip/Cecor Computer Code Package.
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.
ML20235N276	30 June 1988	Analysis of Capsule V from Virginia Power Co Surry Unit 1 Reactor Vessel Radiation Surveillance Program - Surry Unit 1 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation	Hydrostatic
ML20210B480	30 April 1987	Rev 1 to Customer Designated Distribution Surry Units 1 & 2 Reactor Vessel Fluence & Ref Temp PTS Evaluations
ML20214M031	28 February 1987	Analysis of Capsule V from VEPCO Surry Unit 1 Reactor Vessel Radiation Surveillance Program
ML18149A512	30 November 1986	Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code.
ML20203G548	31 March 1986	Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs	Power change
ML20203C710	31 March 1986	Reactor Pressure Vessel & Surveillance Program Matls Licensing Info for Surry Units 1 & 2	Hydrostatic
ML20135H949	31 August 1985	Rev 1 to Reload Nuclear Design Methodology	Boric Acid Shutdown Margin
ML20137W748	31 August 1985	Steam Generator Girth Weld 6 Repair Rept
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
ML18142A350	31 March 1985	Cycle 7 Core Performance Rept.	Fuel cladding
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
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
ML20078K336	30 September 1983	VEPCO Nomad Code & Model
ML18141A054	31 July 1983	Cycle 6 Core Performance Rept. W/Undated Ltr	Fuel cladding
ML18139C264	31 March 1983	Cycle 6 Core Performance Rept.	Fuel cladding
ML18139C061	4 October 1982	Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code.
ML18139B663	31 December 1981	Cycle 5 Core Performance Rept.	Fuel cladding
ML20010B610	31 July 1981	Pdq 07 Discrete Model.	Boric Acid
ML20010B617	31 July 1981	Pdq 07 One Zone Model.	Boric Acid Shutdown Margin
ML20010B624	31 July 1981	VEPCO Flame Model.
ML18139B401	30 April 1981	Reload Nuclear Design Methodology.	Shutdown Margin
ML19352A279	31 March 1981	Reactor Sys Transient Analyses Using Retran Computer Code.
ML20002D277	31 December 1980	Control Rod Reactivity Worth Determination by Rod Swap Technique.	Shutdown Margin
ML18139A294	31 December 1979	Metallurgical Investigation of Cracks in Steam Generator Feedwater Lines of Surry Station 1.	Nondestructive Examination
ML18136A022	31 August 1979	VEPCO Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code.	Fuel cladding
ML18116A364	23 July 1979	GE Vertical Induction Motors Inside Containment Recirculation Spray Pumps.
ML18113A771	31 October 1978	Vepco Flame Model. Util Developed 3 Dimensional(X,Y,Z) Modified Diffusion Therory Calculational Model Designated as Vepco Flame Model.Accuracy of Model Is Demonstrated Through Comparisons Taken at Units 1 & 2

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