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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.

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