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CORRESPONDENCE-LETTERS  and OUTGOING CORRESPONDENCE

Hydrogen +  and Lead +

10 CFR 50.35#a +  and 10 CFR 50 +

05000461  +, 05000462  +  and 00461  +

Tedesco R +  and Office of Nuclear Reactor Regulation +

ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +, ML20030B862 +  and ML20030B862 +

NUREG-0705 +, NUREG-070 +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0582, Clarifies Reasons to Proceed W/Development of Preliminary Calculational Tool for Steam Bubble Induced Water Hammer. Proposed Use Need Is Essential Adjunct to Efforts in Resolving Water Hammer Task.Graphs Encl +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Illinois +  and Virginia +

Steam Generator +, Feedwater +, Service water +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Containment Spray +

Waller G +  and Illinois Power Company +

Safe Shutdown +, High winds +, Anticipated operational occurrence +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Generic Issues Program +  and Backfit +