TAC:62779
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Other: ML20100H434, ML20100H458, ML20140A557, ML20141C845, ML20141C857, ML20210U330, ML20215K962, ML20235W092, ML20236B613 | |
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MONTHYEARML20100H4581985-02-28028 February 1985
[table view]Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program ML20100H4341985-04-0505 April 1985 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 ML20138K8101985-12-16016 December 1985 Application for Amends to Licenses NPF-9 & NPF-17,extending Authorization to Operate Facilities Until 210612 & 230303, Respectively.Fee Paid ML20140A5571986-01-15015 January 1986 Forwards Projected Values of RT Pressurized Thermal Shock, Per 10CFR50,Section 50.61(b)(1).Ref Temp Determination Also Encl ML20141C8571986-01-31031 January 1986 Nonproprietary Analysis of Capsule V from Duke Power Co, McGuire Unit 2,Reactor Vessel Radiation Surveillance Program ML20141C8451986-04-0202 April 1986 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 ML20210U3301986-05-29029 May 1986 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 ML20207B7171986-07-10010 July 1986 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 ML20210C0331986-09-0808 September 1986 Proposed Changes to Tech Specs,Incorporating Improvements Re RCS Pressure Temp Operating Limits ML20210C0091986-09-0808 September 1986 Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Incorporate Improvements Re Pressure Temp Operating Limits as Result of Exam of Capsules Withdrawn During First Refueling Outage.Fee Paid ML20215K9621986-10-21021 October 1986 Forwards Evaluations Supporting 860115,0402,05 & 0710 Responses to 10CFR50.61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 ML20235W0921987-10-13013 October 1987 Requests That Portions of Util 860908 Application for Amends to Licenses NPF-9 & NPF-17 to Change Tech Specs Re RCS Pressure/Temp Limits Be Revised Due to Change Not Having Endorsement of Westinghouse Owners Group ML20236B6131987-10-20020 October 1987 Responds to Requesting Rev to 860908 Proposal to Update Existing RCS pressure-temp Limits.Present Operating Limits Valid Until 1989.Proposed Tech Spec Rev Withdrawn. Appropriate Proposal Will Be Submitted at Later Date 1986-10-21 | |
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