ML20059E057

Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4))

ML20059E057
Person / Time
Site:	Beaver Valley
Issue date:	08/10/1990
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19302E171	List: ML20059E057 ML20059E060 ML20059E064
References
TAC-71086, NUDOCS 9009100013
Download: ML20059E057 (2)

Text

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August 10, 1990 l

U.-S.. Nuclear Regulatory Commission Attn: -Document Control Desk Washington, DC 20555 i

Reference:

Beaver Valley Power Station, Unit No. 2  !

Docket No. 50-412, License No. NPF-73 Primary Component Support Snubber Elimination.

Gentlemen:' ,

Enclosed are:

1. Five (5) copies of WCAP-12093, Supplement 3 entitled,

" Evaluation of Pressurizer. Surge Line Transients Exceeding 320*F for Beaver Valley Unit 2 (Proprietary)."

1

2. Five (5) copies of WCAP-12094, Supplement 3 entitled,

" Evaluation of- Pressurizer Surge Line Transients Exceeding 320*F for Beaver Valley Unit 2-(Non-Proprietary)."

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3. A Westinghouse Application for Withholding, CAW-90-058, i

Accompanying Affidavit, Proprietary Information Notice,  !

and copyright Notice.

t As Item 1 contains information . proprietary to Westinghouse Electric Corporation, it .is supported by an affidavit signed by Westinghouse, the owner of the information. This affidavit sets forth the basis on which the information may be withheld from l public disclosure by the Commission and addresses with. specificity the considerations listed in paragraph (b)(4) of Section 2.790 of '

the Commission's regulations, 1

Do Accordingly, it is respectfully requested that the information 3o@ which .is proprietary tx) Westinghouse be withheld from public 20 disclosure in accordance with 10 CFR Section 2.790 of the 88 "O

Commission's regulations. Correspondence with. respect to the copyright or proprietary aspects of the' items. listed above or the

$$ supporting Westinghouse affidavit should reference. CAW-90-058 and  !

oo should be addressed to R. A. Wiesemann, Manager ~ Regulatory and 8@ Legislative Affairs, Westinghouse Electric Corporation, y P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355. ,

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Beavor Valloy Powar Station, Unit No. 2

-Docket No. 50-412, License No. NPF-73 Primary Component-Support Snubber Elimination .

Page 2 l

The enclosed WCAPs are being provided in response to a telecon ,

between Messrs. Sam Lee, Arnold Ime, shou Hou-and Peter S. Tam of l the NRC staff and Mr. Brian F. Sepelak of my staff in March, 1990  !

which discussed exceeding a 320*r system delta temperature during.

the heatup from the Beaver-Valley Unit 2 (BV-2) first refueling i outage. WCAP-12093, Supplement 3- concludes' that the maximum stress intensity, fatigue usago factor and growth of postulated cracks are not significantly affected and that the forty year design life is. not impacted. In addition, we have revised our operating procedures to add precautions and limitations to prevent exceeding a 320'F-system delta temperature in the future.

We believe that the anclosed information along with our May 15, 1990 submittal which reviewed load combination case'B/G 1 provides the necessary information for the NRC staff to complete I its review on the subject request (TAC No. 71086). In its y March 3, 1989 letter, the NRC provided interim approval of our request for the BV-2 second fuel cycle. 1[f the NRC staff cannot' complete its review by -the start of the BV-2 second refueling outage (scheduled- for S(stember 1, 1990), then we request an extension of the interim' approval until-the NRC staff's review is complete.

If you have any questions concerning this matter, please contact my office.

Very-truly yours,

( . Sieber ice President Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. A. W. DeAgazio, Project Manager i

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