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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Sodium +, Hydrogen +, Zirconium +, Lead +, Aluminum +  and Calcium +

05000255  +  and 00255  +

Consumers Energy +  and Vandewalle D +

GDC 20 +  and GDC 41 +

NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +

ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +, ML18047A431 +...

ML18047A401 +, ML18047A345 +, ML18046B335 +, ML18046A945 +, ML18046A941 +, ML18046A637 +, ML18046A457 +, ML18046A428 +, ML18045A799 +, ML18044A933 +, ML18043B089 +, ML18347A188 +, 05000255/LER-1981-021, Forwards LER 81-021/03L-0 +, 05000255/LER-2077-031-03, Primary Coolant System Leakage +, ML18044A696 +, ML18047A316 +  and ML17336A024 +

NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +  and NRC Bulletin 79-27 +

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-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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0820, Safety Evaluation Supporting Amend 125 to License DPR-20 +, NUREG-0569, Forwards NUREG-0569, Evaluation of Integrity of SEP Reactor Vessels, Completing Review of SEP Topic V-6.W/o Encl +  and 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 +

Regulatory Guide 1.7 +  and Regulatory Guide 1.139 +

Washington +, Michigan +  and Arkansas +

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

Crutchfield D +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Ultimate heat sink +, Safe Shutdown Earthquake +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Backfit +  and Water hammer +