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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

Hydrogen +  and Lead +

10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.49 +

05000244  +  and 00244  +

Rochester Gas and Electric +  and Maier J +

ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +, ML17256A352 +  and ML17256A352 +

ML17309A110 +, ML20090B472 +, 05000244/LER-1980-001, Forwards LER 80-001/03L-0 +  and ML17250A680 +

NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG/CR-1717 +, 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/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0569, Forwards NUREG-0569, Evaluation of Integrity of SEP Reactor Vessels, Completing Review of SEP Topic V-6.W/o 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-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, 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/CR-1821, Forwards List of Open Issues from Draft NUREG/CR-1821, Seismic Review of Robert E. Ginna Power Plant as Part of Sep. Addl Info Re Seismic Design Consideration & Component Integrity Should Be Submitted within 30 Days +

ES +  and RT +

Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.61 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Control Rod +  and Containment Spray +

Crutchfield D +  and Office of Nuclear Reactor Regulation +

Hot Short +, Safe Shutdown +, Loop seal +, Ultimate heat sink +, Safe Shutdown Earthquake +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Backfit +, Overexposure +, Failure to Scram +, Eddy Current Test +  and Water hammer +