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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 |
ML18065A616 | 31 March 1996 | Nonproprietary Consumers Power Co Reactor Vessel Neutron Fluence Measurement Program for Palisades Nuclear Plant - Cycles 1 Through 11. | |
ML18065A610 | 29 February 1996 | Non-proprietary Consumers Power Co Palisades Surveillance Specimen Annealing Recovery Program. | |
ML18064A698 | 31 March 1995 | Nonproprietary Rev 1 to Palisades Loss of Load Analysis. | |
ML20082H401 | 28 February 1995 | Annual Rept on Abb CE ECCS Performance Evaluation Models, Feb 1995 | Fuel cladding |
ML18065A310 | 31 October 1994 | Non-proprietary Status Rept on CEOG Activities Concerning Primary Water Stress Corrosion Cracking of Inconel-600 Penetrations. | Boric Acid Non-Destructive Examination Intergranular Stress Corrosion Cracking Stress corrosion cracking Eddy Current Testing |
ML18064A590 | 19 October 1994 | Non-Proprietary Palisades Loss of Load Analysis. | |
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 Depleted uranium |
ML18058B874 | 31 May 1993 | Reactor Vessel Neutron Fluence Measurement Program for Cpc,Results to End of Cycle 9. | Depleted uranium |
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 |
ML18057A966 | 9 November 1990 | Review & Analysis of SRP Chapter 15 Events for Palisades W/ 15% Variable High Power Trip Reset. | Shutdown Margin Anticipated operational occurrence Feedwater Heater Rod Drop Event Coast down Loss of condenser vacuum |
ML18057A498 | 30 September 1990 | Preliminary ANF-90-078, Palisades Cycle 9 - Analysis of SRP Chapter 15 Events. | |
ML18057A497 | 31 August 1990 | Rev 2 to Disposition of SRP Chapter 15 Events for Palisades Cycle 9. | |
ML20197H623 | 28 February 1990 | Rev 1 to Palisades Large Break Loca/Eccs Analysis W/ Increased Radial Peaking | Earthquake Fuel cladding |
ML20154J434 | 7 September 1988 | Rev 1 to Palisades Cycle 8:Disposition & Analysis of SRP Chapter 15 Events | Shutdown Margin Anticipated operational occurrence Feedwater Heater Rod Drop Event Coast down Loss of condenser vacuum |
ML20195H030 | 13 June 1988 | Nonproprietary Low Flow Trip Setpoint & Thermal Margin Analysis for Three Primary Coolant Pump Operation of Palisades Reactor | Coast down |
ML20195H074 | 13 June 1988 | Nonproprietary Vol 1 of Palisades Modified Reactor Protection Sys Rept-Disposition of SRP Chapter 15 Events | Shutdown Margin Anticipated operational occurrence Feedwater Heater Overspeed trip Loss of condenser vacuum |
ML20195H327 | 13 June 1988 | Nonproprietary Vol 2 of Palisades Modified Reactor Protection Sys Rept:Analysis of Chapter 15 Events | Shutdown Margin Anticipated operational occurrence Loss of condenser vacuum |
ML20154D628 | 31 May 1988 | Handbook of Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds | Probabilistic Risk Assessment Stress corrosion cracking |
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 | |
ML20206J826 | 7 April 1987 | Rev 1 to Thermal Analysis of West Engineered Safeguards Room of Palisades Nuclear Power Plant | |
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 | |
ML18059A456 | 31 May 1986 | Status & Suggested Course of Action for Nondenting-Related Primary-Side IGSCC of Westinghouse-Type Sg. | Boric Acid Nondestructive Examination Finite Element Analysis Intergranular Stress Corrosion Cracking Stress corrosion cracking |
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 |
ML20155J505 | 31 May 1986 | Rev 1 to Functional Design Requirements for Control Element Assembly Calculator | Anticipated operational occurrence |
ML20155J523 | 31 May 1986 | Rev 1 to Functional Design Requirement for Core Protection Calculator | 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 | |
ML20134N294 | 31 July 1985 | Rev 00 to Functional Design Requirement for Control Element Assembly Calculator | Anticipated operational occurrence |
ML20134N302 | 31 July 1985 | Rev 00 to Functional Design Requirement for Core Protection Calculator | Anticipated operational occurrence |
ML20099D451 | 30 September 1984 | Analysis of Capsules T-330 & W-290 from CPC Palisades Reactor Vessel Radiation Surveillance Program | |
ML20084F027 | 20 April 1984 | Suppl 1 to Analysis of Axial Power Distribution Limits for Palisades Nuclear Reactor at 2530 Mwt:Sensitivity Studies | |
ML20087J819 | 9 March 1984 | Plant Transient Analysis for Palisades Nuclear Power Plant W/50% Steam Generator Plugging | Anticipated operational occurrence Coast down |
ML20087J831 | 9 March 1984 | LOCA-ECCS Analysis for 2125 Mwt Operation & 50% Steam Generator Tube Plugging | |
ML20087J816 | 9 March 1984 | Cycle 6 Setpoint Verification W/50% Steam Generator Tube Plugging | Anticipated operational occurrence Power change |
ML20080Q455 | 16 January 1984 | Nonproprietary, Response to NRC Question on Waterford-3 Bypass Flowrate | |
ML20078E295 | 26 August 1983 | Rod Withdrawal Transient Reanalysis for Palisades Reactor | Hydrostatic |
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. | |
ML20050C531 | 31 March 1982 | Nonproprietary Version of Safety Evaluation of Reactor Power Cutback Sys. | Power change |
ML20050C530 | 31 March 1982 | Nonproprietary Version of Cpc/Ceac Software Mod for Waterford 3. | |
ML20039F862 | 31 December 1981 | Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palisades Reactor Vessel. |