ML20087M401

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Rev to 831212 Application for Amend to Licenses NPF-9 & NPF-12,changing Listed Tech Spec Bases,Per Y Hsii & Ms Dunenfeld 840315 & 16 Telcons,Respectively.Westinghouse Proprietary Info Withheld (Ref 10CFR2.790)
ML20087M401
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 03/23/1984
From: Tucker H
DUKE POWER CO.
To: Adensam E, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19268E719 List:
References
NUDOCS 8403290267
Download: ML20087M401 (3)


Text

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.. O l 4 o DUKE Powna GOMI%NY P.O. DOX 33180 C11AnLOTrE. N.C. 26242 HALH. TUCKER TELEPHONE voce ..r.inent (704) 073-4531 mm . .."'"""

March 23, 1984

. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief ,

Licensing Branch No. 4

Subject:

McGuire Nuclear Station ,

Docket Nos. 50-369, and 50-370 McGuire 1/ Cycle 2 0FA Reload g

I

Dear Mr. Denton:

My letter of December 12, 1983 transmitted proposed License Amendments to Facility Operating Licenses NPF-9 and NPF-12 for McGuire Nuclear Station Units 1 and 2, respectively. These amendments, which basically change plant operating limitations given in the Technical Specificatio'ns affected by use of the Optimized Fuel Assembly (OFA) Design for McGuire Unit 1/ cycle 2 to ensure plant operation consistent with the Design and Safety Evaluations, were subsequently revised by my letter dated February 20, 1984. The " Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed no Significant Hazards Consideration Determination and Opportunity for Hearing" related to the submittals was published in the Federal Register on March 2, 1984.

Ms. E. G. Adensam's letter dated March 5, 1984 requested additional information necessary to support NRC Staff Review of the Proposed Amendments. This infor-mation was provided by my letter of March 9, 1984. As a result of continuing NRC Staff Review, the following revisions to the Proposed Amendments were re-quested by Messrs. Y. Hsii and M. S. Dunenfeld in Telecons on March 15 and 16, 1984, respectively.

Attachment 1 is a revision to Proposed Technical Specification Bases Page B 2-1 which clarifies where the minimum DNBR value of 1.30 for Unit 2 comes from.

This clarification was necessitated in view of the differing correlations used for this application on Units 1 and 2.

Attachment 2 is a revision to Proposed Technical Specification Bases Page B 3/4 2-4 insert "X" which provides information on thethermal margin available to offset various penalties for Unit 1. The original submittal provided this information only for Unit 2.

Attachment 3 is a re"ision to Proposed Technical Specification Page 6-23 which reflects the fact that the Radial Peaking Factor Limit Reporting Requirements for Units 1 and 2 differ as a result of the OFA reload on Unit 1 (i.e. Fxy limit for Unit 2 W(z) function for Unit 1). Since the Unit 2/ cycle 2 reload is plan-ned to use the OFA design, the December 12, 1983 submittal deleted the current Fxy Unit reporting requirements for both units in anticipation of the W(z) Eunction 1

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PDR ADOCK 05000369 #I m__--

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2 Report being required for Unit 2/ cycle 2 startup. However, this did not take into account the possibility (although unlikely) of a limit report submittal becoming necessary at some time during Unit 2/ cycle 1 core life (as was the case with the Unit 1 Mid Cycle 1 Core Redesign), in which case an Fxy limit report would be appropriate. The revision provides for the separate reporting require-ments of each unit.

Since the attached revisions are corrections / clarifications to the previous sub-mittal which is corrently under review and are bounded by the analyses of that submittal, no additional justification and safety analysis, significant hazards consideration, or amendment fee is required.

In reference to the above mentioned March 9, 1984 letter which provided additional information requested by the NRC Staff, it was requested that portions of the information which is proprietary to Westinghouse Electric Corporation be withheld from public disclosure. In support of that request, enclosed is one copy of the application for withholding, CAW-84-18 (non-proprietary), and the Westinghouse Affidavit, AW-76-60 (non-proprietary). Also enclosed are two copies (one

" proprietary" version and one "non-proprietary" version) of the responses on the McGuire Nuclear Station instrumentation uncertainties for the Improved Thermal Design Procedure (Attachment No. 1 of the March 9, 1984 letter-rerponse to questions No. 10.(3), 10.(4), and 10.(6)), and the uncertainties used in the McGuire ITDP DNBR Analyses (Tables 1,2, and 3 of the March 9,1984 letter-response to question No. 10.(5)). These items are submitted in support of the ITDP for the McGuire Nuclear Station 0FA reload transition core and is to be treated as proprietary information of Westinghouse Electric Corporation. The information is marked and bracketed accordingly. The information will be separately re-submitted in whole in conformance with the requirements of 10CFR2.790 should it be employed as part of a license application or other action identified in 10CFR2.790(a).

Correspondence with respect to the affidavit or application for withholding should reference AW-84-18 and should be addressed to R. A. Wiesemann, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.

Should thera be any further questions concerning these matters, please advise.

Very truly yours, b, mci %

b Hal B. Tucker PBN:glb Attachments Enclosures cc: (w/ attachments-enclosures)

Mr. J. P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

3 cc: (w/ attachments-enclosures)

Mr. Dayne Brown, Chief Radiatien Protection Branch Division of Facility Services Department of Human Resources P. O. Box 12200 Raleigh, North Carolina 27605 Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station l

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