ML20138R477

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Notifies of leak-before-break Analysis to Qualify Primary Loop Piping Until End of Life,Per Deficiencies Noted in 850219 Submittal of WCAP-10743, Technical Bases for Eliminating Large Primary Loop Pipe Rupture..
ML20138R477
Person / Time
Site: Beaver Valley
Issue date: 12/19/1985
From: Sieber J
DUQUESNE LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
NUDOCS 8512310305
Download: ML20138R477 (2)


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'Af Telephone (412) 393-6000 Nuclear Group In$ppingport, PA 15077-0004

, Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Extension of Toughness Criteria for Mechanistic Fracture Evaluation Gentlemen:

In our February 19, 1985 submittal of WCAP-10743 " Technical Bases for Eliminating Large Primary Loop Pipe Rupture as a Structural Design Basis for Beaver Valley Unit 1", we informed you that the predicted end-of-life toughness for some of the material heats used in the primary loop piping did not meet the current Westinghouse toughness criteria to justify a leak-before-break analysis until end of life.

In order to resolve this

issue, we have contracted Westinghcuse to perform work to justify an extension of the toughness criteria to include all the material heats in service at Beaver Valley Unit 1.

Presently, Westinghouse has developed alternate fracture toughness criteria and has recently submitted generic WCAP 10931

" Toughness Criteria for Thermally Aged Cast Stainless Steel" to the NRC for review.

After the NRC review of WCAP 10931 is completed, Westinghouse will perform a

leak-before-break analysis for Beaver Valley Unit 1

which qualifies the entire primary loop piping until end of life.

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

Very truly yours, k

. D. Sieber Senior Manager egg 23 gj{$$o$

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B00 Var Vallcy Powsr Stction,-Unit No. 1 Dockst No. 50-334, Licensa No. DPR-66 Extension of Toughness Criteria for Mechanistic Fracture Evaluation Page 2 cc:

Mr. W. M. Troskoski, Resident Inspector U.

S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company 1

1 P.O. Box 26666 One James River Plaza Richmond, VA 23261

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