Browse wiki

CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

Nickel +, Copper +, Nitrogen +, Hydrogen +  and Lead +

10 CFR 50 +  and 10 CFR 50.35 +

NRC 1503 +  and NRC 245 +

05000244  +  and 00244  +

Lainas G +  and Office of Nuclear Reactor Regulation +

ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +, ML17256B053 +  and ML17256B053 +

NRC 1503 +  and NRC 245 +

NUREG/CR-2083, Forwards NUREG/CR-2083, Evaluation of Threat to PWR Vessel Integrity Posed by Pressurized Thermal Shock Events. Joint Ofc of Nuclear Reactor Regulation/Ofc of Research Team Will Review Rept.W/O Encl +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, 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 +  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 +

RT +, TP +  and CP +

B5M-designe +  and 8EM-designe +

Pennsylvania +, Maryland +, Washington +, Idaho +, New York +  and New Hampshire +

Steam Generator +, Reactor Coolant System +, Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +  and Decay Heat Removal +

Maier J +  and Rochester Gas and Electric +

Non-Destructive Examination +, Control of Heavy Loads +  and Generic Issues Program +