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CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

05000245  +  and 00245  +

Opeka J +, NORTHEAST UTILITIES +, Mroczka E +  and Northeast Nuclear Energy +

B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +, B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +  and B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A +

ML20054M695 +  and A02113, Forwards Isolation Condenser Sys Water Hammer Events, in Response to NRC Questions Re 810810 Transient & Millstone Point 1 Isolation Condenser & Shutdown Cooling Sys Piping Cracks +

NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +  and NRC Bulletin 79-14 +

NUREG-0993 +, NUREG/CR-1889, Advises That NRC Requirement for Encl Bldg Mods to Meet Combined LOCA Plus SSE Load Combination Criteria No Longer Reasonable.Cites Late Sept 1980 Meeting Re Relaxation of Requirements Per NUREG/CR-1889 Probability Calculations +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, 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-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Connecticut +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Core Cooling System +, Control Rod +  and Containment Spray +

Office of Nuclear Reactor Regulation +  and Charemagne Grimes +

Reactor Vessel Water Level +, Design basis earthquake +, Earthquake +  and Water hammer +