Semantic search
Jump to navigation
Jump to search
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 |