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	Issue date	Title	Topic
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.
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.
ML18058B874	31 May 1993	Reactor Vessel Neutron Fluence Measurement Program for Cpc,Results to End of Cycle 9.
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
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
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
ML20195H327	13 June 1988	Nonproprietary Vol 2 of Palisades Modified Reactor Protection Sys Rept:Analysis of Chapter 15 Events	Shutdown Margin Anticipated operational occurrence
ML20206J826	7 April 1987	Rev 1 to Thermal Analysis of West Engineered Safeguards Room of Palisades Nuclear Power Plant
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
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
ML20087J816	9 March 1984	Cycle 6 Setpoint Verification W/50% Steam Generator Tube Plugging	Anticipated operational occurrence Power change
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
ML20078E295	26 August 1983	Rod Withdrawal Transient Reanalysis for Palisades Reactor	Hydrostatic
ML17297B168	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palo Verde 1,2 & 3 Reactor Vessels.
ML20039F858	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Fort Calhoun Reactor Vessel.
ML20039F861	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Calvert Cliffs 1 & 2 Reactor Vessels.
ML20039F862	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palisades Reactor Vessel.
ML20039F863	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA W/Loss of Feedwater for Millstone 2 Reactor Vessel.
ML20039F866	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel.
ML20039F867	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for St Lucie 1 & 2 Reactor Vessels.
ML20039F868	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for AR Nuclear One- Unit 2 Reactor Vessel.
ML14092A301	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E Nsss.	Finite Element Analysis Coast down
ML20039F860	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels.	B.5.b
ML19347F452	12 June 1981	Spent Fuel Storage Pool Criticality Safety Reanalysis.
ML20009E728	3 October 1980	Distribution Control Procedures.
ML19323C637	15 April 1980	ECCS & Thermal-Hydraulic Analysis for Reload H Design, Nonproprietary Version.Affidavit Encl
ML19257A009	31 December 1979	Draft Input for Response to NRC Lessons Learned Requirements for C-E Nsss.
ML18044A381	21 December 1979	Post-TMI Evaluation Task 2,Conceptual Design for Reactor Vessel Level Monitoring Sys. Sixteen Oversize Drawings Encl
ML18044A379	30 November 1979	Results from Charge Preamplifier Temp Test.
ML20126J938	31 October 1979	Technical Evaluation of Susceptibility of Safety-Related Sys to Flooding Caused by Failure of Non-Category I Sys	Safe Shutdown
ML20117M441	10 December 1976	Nonproprietary Palisades Steam Generator Tube Repair Sleeving
ML20117M427	31 January 1974	Nonproprietary Palisades Steam Generator Tube Exam & Repair

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