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MONTHYEARML20100H4581985-02-28028 February 1985
Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program
Project stage: Other
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
Project stage: Other
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
Project stage: Request
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
Project stage: Other
ML20141C8571986-01-31031 January 1986
Nonproprietary Analysis of Capsule V from Duke Power Co, McGuire Unit 2,Reactor Vessel Radiation Surveillance Program
Project stage: Other
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
Project stage: Other
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
Project stage: Other
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
Project stage: Request
ML20210C0331986-09-0808 September 1986
Proposed Changes to Tech Specs,Incorporating Improvements Re RCS Pressure Temp Operating Limits
Project stage: Request
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NPF-17,changing Tech Specs to Incorporate Improvements Re Pressure Temp Operating Limits as Result of Exam of Capsules Withdrawn During First Refueling Outage.Fee Paid
Project stage: Request
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
Project stage: Other
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
Project stage: Other
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
Project stage: Other
1986-10-21
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DUKE Powna GOMPANY P.O. HOK 33180 CHAHLOTTE, N.C. 28242 HALB. TUCKER Traspuosa po4) ara-4nas m mm m mm.mou-April 2, 1986 l
[Nr$ Harold'RTDealtos, Director
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~~0ffice'of' Nucle'ar Reactor Regulation
~
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
B.J. Youngblood, Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station, Unit 2 Docket No. 50-370
Dear Mr. Denton:
. Pursuant to 10 CFR50, Appendix H, please find attached a report entitled
" Analysis of Capsule from the Duke Power Company McGuire Unit 2 Reactor Vessel Radiation Surveillance Program", WCAP-11029.
Please note that in Section 7 of the report, a revise capsule removal schedule is recommended.
It is noted that Capsule V was removed in lieu of Capsule U as required by Technical Specification Table 4.4.5.
The revised schedule accounts for this. A proposed Technical Specification revision is in the process of being developed which will reflect the new pressure-temperature limits as well as the revised schedule.
Please note that my letter dated April 5, 1985 provided the capsule report for Unit 1 and indicated that revised pressure-temperature limit curves would be submitted.
It is Duke's intention to submit proposed technical specifications for both units in summer 1986.
Please feel free to contact us if you require any additional information.
Very truly yours,
.Y lfh Hal B. Tucker RLG/jgm h4070324860402 p
ADOCK 05000370 I {(
Attachments PDR
3 Mr. Harold R. Denton April 2, 1986 Page 2 xc: w/o attachment Dr. J. Nelson Grace, Reg. Admin.
U.S. Nuclear Regulatory Commission l
Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood, Project Manager Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station L_