Browse wiki

Pages with broken file links, CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

ACI-301 +  and ACI-310 +

ASME Section XI +, ASME Section III +, ASME Section II +, ASME Section VIII +  and ASME Section XXIX +

Hydrogen +  and Lead +

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

L 137 +  and L 136 +

P.4(s) +, S.1(l) +, P.4(t) +, P.5(e) +  and P.9(d) +

05000322  +  and 00322  +

Long Island Lighting Company +  and Novarro J +

ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +, ML20004B614 +  and ML20004B614 +

L 137 +  and L 136 +

NUREG-0467 +, NUREG/CR-0261, Approves 860416 Request to Utilize Subarticle NC-3600 of Winter 1981 Addenda to 1980 Edition of ASME Section III Code for Class 2 Piping Stress Analysis (NUREG/CR-0261),to Resolve IE Bulletin 79-14 Items +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, 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-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-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +

ES +, SP +, CP +  and Emergency Plan +

NEDE-24302 +  and NEDE-21985 +

U31a-t +  and 3PS-1 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Circulating Water System +, Reactor Building Closed Loop Cooling +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Main Turbine Bypass System +

Office of Nuclear Reactor Regulation +  and Harold Denton +

Nondestructive Examination +, High Energy Line Break +, Feedwater Controller Failure +, Loss of Offsite Power +, Control of Heavy Loads +, Fatigue Rule +  and Control Room Habitability +