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CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

Hydrogen +  and Lead +

10 CFR 50 +, 10 CFR 50.44 +  and 10 CFR 50 Appendix H +

05000400  +, 05000401  +, 00400  +  and 00401  +

Tedesco R +  and Office of Nuclear Reactor Regulation +

ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +, ML20041D045 +  and ML20041D045 +

NUREG-0705 +, 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-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-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-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.82 +  and Regulatory Guide 1.79 +

Tennessee +, North Carolina +, Washington +  and Virginia +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Containment Spray +

Jackie Jones +  and Carolina Power & Light Co. +

Safe Shutdown +, High winds +, Ultimate heat sink +, Stress corrosion cracking +, Loss of Offsite Power +, Control of Heavy Loads +, Generic Issues Program +, Backfit +, Failure to Scram +  and Water hammer +