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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-264, Forwards Plant Recovery Plan Presented at 830425 Meeting Re Reactor Vessel Internals & Thermal Shield,In Response to Item C of .Plan Will Be Revised Daily W/Updates Provided Upon Availability +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-280, Advises That 10-yr pressure-temp Operating Limits (P-T) for Plant Recovery Program Reactor Vessel Internals & Thermal Shield Valid for Upcoming Cycle 6.P-T Limits Will Be Reviewed & Revised,If Necessary,Prior to Exceeding 7.4 EFPY +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-509, Discusses Reactor Vessel Internals & Thermal Shield & Plant Recovery Program.Outline of Final Rept of Integrity & Stability of Internals W/O Thermal Shield,Presented at 830922 Meeting,Encl.Info Submittal Dates Listed +, L-83-52 +, L-83-53 +, L-83-545, Notifies That Presentation of Thermal Shield Failure Analysis,As Part of Plant Recovery Program,Rescheduled for 831110,per NRC Request +, L-83-582, Forwards Final Rept for Plant Recovery Plan Re Reactor Vessel Internals & Thermal Shield Conclusions & Findings. Schedule Changes Reevaluation of D (5) Integrity & Stability of Internal & D (6) Conclusions & Findings Encl +, L-83-585 +, L-83-49 +, NRC 830426 +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup +, L-83-369, Forwards Assessment of Safety Impacts of Removal of Thermal Shield from Facility,Per 830419 Commitment.Assessment Addresses Cycle 6 Reload Safety Analysis of Plant Recovery Program +  and L-83-584, Discusses 830711 Request for Transfer to NRC of ex-core Detector Neutron Noise & Accelerometer Data from Plant Recovery Program.Frequency Spectra Plots for Time Period of Interest & Magnetic Tapes Being Forwarded to D Fry of ORNL +

05000335  +  and 00335  +

NextEra Energy +  and Williams J +

ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +, ML17214A644 +  and ML17214A644 +

L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations +, L-83-264, Forwards Plant Recovery Plan Presented at 830425 Meeting Re Reactor Vessel Internals & Thermal Shield,In Response to Item C of .Plan Will Be Revised Daily W/Updates Provided Upon Availability +, L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility +, L-83-280, Advises That 10-yr pressure-temp Operating Limits (P-T) for Plant Recovery Program Reactor Vessel Internals & Thermal Shield Valid for Upcoming Cycle 6.P-T Limits Will Be Reviewed & Revised,If Necessary,Prior to Exceeding 7.4 EFPY +, L-83-345, Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting +, L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed +, L-83-509, Discusses Reactor Vessel Internals & Thermal Shield & Plant Recovery Program.Outline of Final Rept of Integrity & Stability of Internals W/O Thermal Shield,Presented at 830922 Meeting,Encl.Info Submittal Dates Listed +, L-83-52 +, L-83-53 +, L-83-545, Notifies That Presentation of Thermal Shield Failure Analysis,As Part of Plant Recovery Program,Rescheduled for 831110,per NRC Request +, L-83-582, Forwards Final Rept for Plant Recovery Plan Re Reactor Vessel Internals & Thermal Shield Conclusions & Findings. Schedule Changes Reevaluation of D (5) Integrity & Stability of Internal & D (6) Conclusions & Findings Encl +, L-83-585 +, L-83-49 +, L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup +, L-83-369, Forwards Assessment of Safety Impacts of Removal of Thermal Shield from Facility,Per 830419 Commitment.Assessment Addresses Cycle 6 Reload Safety Analysis of Plant Recovery Program +  and L-83-584, Discusses 830711 Request for Transfer to NRC of ex-core Detector Neutron Noise & Accelerometer Data from Plant Recovery Program.Frequency Spectra Plots for Time Period of Interest & Magnetic Tapes Being Forwarded to D Fry of ORNL +

Florida +  and Washington +

John Miller +  and Office of Nuclear Reactor Regulation +