Letter Sequence Request |
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MONTHYEARML17139B0511982-08-16016 August 1982
Informs Commission of Recent Developments in Connection W/Issuance of OLs w/40-yr Duration.Several Applicants Requested Info.Susquehanna License Restricted to 5% Power for 40-yr Term
Project stage: Approval
ML20100H4581985-02-28028 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
ML20197G9911985-04-30030 April 1985
Discusses Procedure to Be Used That Allows Util to Receive License Extension to 40 Yrs from Date of Ol.Environ Assessment Should Be Prepared Following Guidelines of Encl Licensee Review
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
ML20214D1851986-11-18018 November 1986
Forwards Request for Addl Info Re Util 851216 Application for Amend to License to Extend OL for 40 Yr Term.Response Requested by 861212 in Order to Maintain Present Schedule
Project stage: RAI
ML20214M0961986-11-24024 November 1986
Forwards Response to NRC 861118 Request for Addl Info Re 851216 Application Extending OLs to Full 40-yr Term. Responses to NRC Questions & Data on Exposure of Plant Workers Encl
Project stage: Request
ML20207C3201986-12-16016 December 1986
Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Proposed Amends to Change Expiration Dates for Licenses NPF-9 & NPF-17 to 210612 & 230303, Respectively
Project stage: Approval
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
1986-11-18
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DUKE POWER GOMPANY P.O. nox 33180 CliARLOTTE, N.O. 28242 ILG B. TUCKER m......,
(*) **
July 10, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation i
U.S. Nuclear Regulatory Consaission Washington, D.C.
20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Mr. Denton:
By letter dated May 29, 1986, NRC requested additional information relative to the fracture toughness requirements for protection against pressurized thermal shock.
In response to this request, Duke notes that the values for best estimate weight percent of copper and nickel were obtained from Westinghouse Capsule Reports 1
WCAP-10786 and WCAP-11029. These have been previously submitted to NRC by Duke letters dated April 5, 1985 and April 2, 1986, respectively.
Combustion Engineering had supplied the weld qualification values given in these Westinghouse reports.
The weld wire heat numbers for McGuire Unit I are as follows:
Intermediate longitudinal welds (M1.22) - #20291 and 12008 Lower longitudinal weld (M1.32) - #21935 and 12008 Lower longitudinal weld (M1.33) - #21935 Lower longitudinal weld (M1.34) - #305424 Based on the PTS screening criteria, the most bounding weld is M1.34.
- However, M1.34 is located at an azimuthal angle of 60 degrees, which places it behind a neutron pad.
19 The neutron fluence associated with this location is approximately 2.50 x 10 n/cm (WCAP-10786, Figure 6-3, which relates flux with azimuthal angle). The calculation submitted in Duke letter date Januap 15, 1986 employed a conservative value of fluence of 2.9 x 10 n/cm.
(This maximum occurs at an azimuthal location of approximately 70 to 73 degrees.) Thus, using the realistic value of fluence for this weld, the value of the reference temperature for pressurized thermal shock (RTPTS) is reduced to 257 degrees F.
The weld materials data has been reviewed with Westinghouse. Weld wire #305424, which corresponds to M1.34, has average chemical composition values from Westinghouse material data bank of Cu - 0.28 and Ni - 0.63.
(This data is based
?
g0
,= g i
8607180189 860710 ggg MSUM/d
{g DR ADOCK 0000 9
g,g Apff
Mr. Harald R. De;;. ton July 10, 1986 Page 2 on weld qualification reports.) When these adjusted values, as well as the realistic fluence value, are input into the 10 CFR 60.61 equations, the resulting RT is 238 degrees F.
PTS Very truly yours, r*
Hal B. Tucker RLG/75/jgm Attachments xc:
W.T. Orders NRC Resident Inspector McGuire Nuclear Station Darl Hood, Project Manager Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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