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Issue date | From | Title | Project stage | |
---|---|---|---|---|
ML20100H458 | 28 February 1985 | WESTINGHOUSE ELECTRIC COMPANY DIV OF CBS CORP. Meyer T Yanichko S Congedo T | Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program | Other |
ML20100H434 | 5 April 1985 | Duke Energy Tucker H | Forwards WCAP-10786, Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Per App H to 10CFR50.Based on Rept,Rev to Tech Specs May Be Necessary.Nrc Will Be Advised If Rev Needed | Other |
ML20138K810 | 16 December 1985 | Duke Energy Tucker H | Application for Amends to Licenses NPF-9 & NPF-17,extending Authorization to Operate Facilities Until 210612 & 230303, Respectively.Fee Paid | Request |
ML20140A557 | 15 January 1986 | Duke Energy Tucker H | Forwards Projected Values of Rt Pressurized Thermal Shock, Per 10CFR50,Section 50.61(b)(1).Ref Temp Determination Also Encl | Other |
ML20141C857 | 31 January 1986 | WESTINGHOUSE ELECTRIC COMPANY DIV OF CBS CORP. Yanichko S Kaiser W Congedo T | Nonproprietary Analysis of Capsule V from Duke Power Co, McGuire Unit 2,Reactor Vessel Radiation Surveillance Program | Other |
ML20141C845 | 2 April 1986 | Duke Energy Tucker H | Forwards Nonproprietary WCAP-11029, Analysis of Capsule V from Duke Power Co,Mcguire Unit 2,Reactor Vessel Radiation Surveillance Program. Revised Capsule Removal Schedule Recommended | Other |
ML20210U330 | 29 May 1986 | Hood D Office of Nuclear Reactor Regulation | Requests Addl Info Re Concerning Ref Temps for Pressurized Thermal Shock Reactor Vessel Beltline Matls Calculated for Svc Life of Plant.Response Requested within 45 Days | Other |
ML20207B717 | 10 July 1986 | Duke Energy Tucker H | Responds to NRC 860529 Request for Addl Info Re Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock.Values for Best Estimate Weight Percent of Copper & Nickel Obtained from WCAP-10786 & WCAP-11029 | Request |
ML20215K962 | 21 October 1986 | Hood D Office of Nuclear Reactor Regulation | Forwards Evaluations Supporting 860115,0402,05 & 0710 Responses to 10CFR50.61 Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,Based on 32 EFPYs | Other |