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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 |