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	Issue date	Title	Topic
ML17229A710	30 April 1998	Analysis of Capsule 263 from FPL St Lucie Unit 2 Reactor Vessel Radiation Surveillance Program.
ML17229A571	31 October 1997	Criticality Safety Analysis for Spent Fuel Storage Rack Using Soluble Boron Credit.
ML17229A042	30 September 1996	Rev 1 to CEN-405-NP, Application of Reactor Vessel Surveillance Data for Embrittlement Mgt.
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.
ML17228B226	30 June 1995	Generic Upper Shelf Values for Linde 1092,124 & 0091 Reactor Vessel Welds, Final Rept
ML17228B190	31 May 1995	Joint Applications Rept for Safety Injection Tank Aot/Sti Extension.	Boric Acid Maintenance Rule Program
ML17228B183	31 May 1995	Joint Applications Rept for LPSI Sys AOT Extension.	Safe Shutdown Mission time Probabilistic Risk Assessment Maintenance Rule Program
ML17228B180	31 May 1995	Joint Applications Rept for EDGs AOT Extension.	Safe Shutdown Mission time Enforcement Discretion Maintenance Rule Program
ML18064A698	31 March 1995	Nonproprietary Rev 1 to Palisades Loss of Load Analysis.
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
ML18064A590	19 October 1994	Non-Proprietary Palisades Loss of Load Analysis.
ML17228B499	31 July 1993	Nonproprietary Version of Application of Reactor Vessel Surveillance Data for Embrittlement Mgt.
ML18058B874	31 May 1993	Reactor Vessel Neutron Fluence Measurement Program for Cpc,Results to End of Cycle 9.
ML17228A459	30 September 1991	Suppl 1 to Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Nuclear Power Plant Unit 1.	Boric Acid Shutdown Margin
ML17228A458	30 September 1991	Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Power Plant Unit 1.	Safe Shutdown Boric Acid Shutdown Margin
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 Rod Drop Event Coast down
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
ML20011F498	30 November 1989	Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2.
ML20154J434	7 September 1988	Rev 1 to Palisades Cycle 8:Disposition & Analysis of SRP Chapter 15 Events	Shutdown Margin Anticipated operational occurrence Rod Drop Event Coast down
ML20153G092	1 September 1988	Boric Acid Concentration Reduction	Safe Shutdown Boric Acid Shutdown Margin
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
ML20195H030	13 June 1988	Nonproprietary Low Flow Trip Setpoint & Thermal Margin Analysis for Three Primary Coolant Pump Operation of Palisades Reactor	Coast down
ML20195H327	13 June 1988	Nonproprietary Vol 2 of Palisades Modified Reactor Protection Sys Rept:Analysis of Chapter 15 Events	Shutdown Margin Anticipated operational occurrence
ML17221A597	22 January 1988	Concentration Reduction Effort,Technical Bases & Operational Analysis.	Safe Shutdown Boric Acid Shutdown Margin Non-Destructive Examination Hydrostatic Nondestructive Examination Liquid penetrant
ML20206J826	7 April 1987	Rev 1 to Thermal Analysis of West Engineered Safeguards Room of Palisades Nuclear Power Plant
ML17221A588	31 March 1987	Rev 0 to Criticality Safety Analysis St Lucie New Fuel Storage Vault W/4.5% Enriched 14x14 Fuel Assemblies.
ML17219A262	31 October 1986	I Steam Generator Allowable Tube Wall Degradation.	Safe Shutdown Safe Shutdown Earthquake
ML20238F259	31 August 1986	Tube Burst & Leakage Testing of Intergranular Attack & IGSCC Defects Representative of Those Found in St Lucie Unit One Steam Generators
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
ML20155B128	20 March 1986	Loca/Eccs Analysis W/11% Steam Generator Tube Plugging
ML17216A616	28 February 1986	Rev 1 to St Lucie Unit 1:New & Spent Fuel Storage Criticality Safety Evaluation for Natural U Axial Blanket Fuel.
ML20140E196	31 December 1985	Suppl 1 to St Lucie Unit 1 Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging Break Spectrum & Exposure Results
ML17216A346	5 November 1985	Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging.
ML17346B171	31 July 1985	Retran Code Transient Analysis Model Qualification.	Anticipated operational occurrence Fuel cladding Coast down
ML20099D451	30 September 1984	Analysis of Capsules T-330 & W-290 from CPC Palisades Reactor Vessel Radiation Surveillance Program
ML17215A369	30 April 1984	Nonproprietary Conservatism of Axial Shape Index DNB Limiting Condition for Operation Below 30% Power.
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
ML20078E295	26 August 1983	Rod Withdrawal Transient Reanalysis for Palisades Reactor	Hydrostatic
ML20085H551	16 August 1983	Core Support Barrel Insp,Repair & Analysis & Thermal Shield Removal
ML20083N248	7 January 1983	Rev 1 to St Lucie Unit 1 Cycle 6 Sar
ML20083N266	7 January 1983	Plant Transient Analysis for St Lucie Unit 1	Shutdown Margin Anticipated operational occurrence
ML20083N209	20 December 1982	LOCA Analysis Using Exem/Pwr ECCS Model
ML20039F866	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel.
ML20039F858	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Fort Calhoun Reactor Vessel.

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