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Issue date | Title | Topic | |
---|---|---|---|
ML20154E421 | 31 January 1998 | Amend 1 to CE NPSD-911, Analysis of Moderator Temperature Coefficients in Support of Change in TSs End of Cycle Negative Mtc Limit. App a Consists of Responses to 970226 NRC RAI | |
ML20141L979 | 28 February 1997 | Suppl 8 to Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept | Fuel cladding |
ML20112G530 | 10 June 1996 | Annual Report on Abb CE ECCS Performance Evaluation Models | Fuel cladding |
ML20082H401 | 28 February 1995 | Annual Rept on Abb CE ECCS Performance Evaluation Models, Feb 1995 | Fuel cladding |
ML20073D456 | 30 September 1994 | Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys | |
ML20063C757 | 31 December 1993 | Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys | Shutdown Margin |
ML20079C162 | 31 May 1993 | Analysis of Moderator Temp Coefficients in Support of Change in TS of EOC Negative Mtc Limit | Power change |
ML20044G518 | 30 April 1993 | Suppl 4 to Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46, Final Rept | Fuel cladding |
ML20127M273 | 30 November 1992 | Analysis of Capsule W-97 Entergy Operations,Inc Waterford Generating Station,Unit 3,Reactor Vessel Matl Surveillance Program | Anticipated operational occurrence Hydrostatic |
ML20153E056 | 31 May 1988 | Errata to Handbook on Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds, Consisting of Page Inadvertently Omitted from Original Rept | |
ML20154D628 | 31 May 1988 | Handbook of Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds | Probabilistic Risk Assessment |
W3P86-3328, Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 3 | 31 October 1986 | Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 3 | Safe Shutdown Boric Acid Shutdown Margin |
ML20215H696 | 31 October 1986 | Nonproprietary Statistical Combination of Uncertainties for Waterford 3 | |
ML20203M870 | 31 July 1986 | Nonproprietary Waterford Unit 3,Cycle 2 Shoulder Gap Evaluation | |
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 |
ML20151Z052 | 31 January 1986 | Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure | |
ML20151Z064 | 31 January 1986 | Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines | |
ML20134N302 | 31 July 1985 | Rev 00 to Functional Design Requirement for Core Protection Calculator | Anticipated operational occurrence |
ML20134N294 | 31 July 1985 | Rev 00 to Functional Design Requirement for Control Element Assembly Calculator | Anticipated operational occurrence |
ML20080Q455 | 16 January 1984 | Nonproprietary, Response to NRC Question on Waterford-3 Bypass Flowrate | |
ML20077J680 | 15 July 1983 | Nonproprietary Rev 1 to Final Assessment of Waterford-3 Fuel Structural Integrity Under Faulted Conditions. Info Deleted | Safe Shutdown Earthquake |
ML20028F943 | 31 December 1982 | Responses to Questions on Cesec. | Anticipated operational occurrence |
ML20050B172 | 31 March 1982 | Nonproprietary Version of Cpc/Ceac Protection Algorithm Test Plan. | |
ML20050C530 | 31 March 1982 | Nonproprietary Version of Cpc/Ceac Software Mod for Waterford 3. | |
ML20050C531 | 31 March 1982 | Nonproprietary Version of Safety Evaluation of Reactor Power Cutback Sys. | Power change |
ML20039F866 | 31 December 1981 | Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel. |