ML20094L928

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Responds to 840525 Request for Addl Info & Generic Ltr 84-04 Re 760114 & 0618 Asymmetric LOCA Loads Analyses.Util Proceeding W/Fracture Mechanics Evaluation to Demonstrate Applicability to Modeling
ML20094L928
Person / Time
Site: Beaver Valley
Issue date: 07/31/1984
From: Carey J
DUQUESNE LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
TASK-A-02, TASK-A-2, TASK-OR GL-84-04, GL-84-4, TAC-8597, NUDOCS 8408150499
Download: ML20094L928 (2)


Text

'Af Telephone (412) 393-6000 Nuclear Division P.O. Bow 4 Shippingport, PA 15077-0004 July 31, 1984 U. S. Nuclear Regulatory Commission pivisionofLicensing

/ Attn: 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 Request for Additional Information on Asymmetric LOCA Loads Gentlemen:

In response to your letter of May 25, 1984 requesting information on our asymmetric LOCA loads analysis submitted on January 14 and June 18, 1976, we have reviewed the request and Generic Letter 84-04 Our review indicated that it would be more advantageous to perform a fracture mechanics evaluation to justify a leak before break position, instead of analyzing double-ended guillotine breaks.

The bases for revising our position is:

Advances in analytical methods indicate that the leak before break scenario is more realistic than a double-ended guillotine break.

The fracture mechanics evaluation should satisfy the concern raised for asymmetric blowdown loads during N-1 loop operation (SER dated July 20, 1984)

The cost-benefit appears favorable in that future modifications can satisfy GDC-4 w;th the fracture mechanics evaluation.

Per a discussion between Mr. P. Tam (NRC) and Mr. K. D. Grada (DLC) on July 19, 1984, it was indicated that the fracture mechanics evaluation will be a satisfactory response to your letter of May 25, 1984. However, at this time, we are unable to establish a schedule for completion of the evaluation as the contractual commitments have not been finalized with Westinghouse.

When additional scheduling information is available, we will contact the NRC Project Manager and establish a mutually agreeable schedule.

Therefore, we are proceeding with a fracture mechanics evaluation to demonstrate the applicability of Beaver Valley 1 to the modeling and conclusions contained in the Westinghouse A-2 Owner's Group reports on Fracture mechanics as our resolution of Unresolved Safety Issue A-2.

8408150499 040731 PDR ADDCK 05000334

C' B:.av;r Valley Power Station Unit No.1 Dockst No. 50-334, Licensa No. DPR-66 Request for Additional Information on Asymetric LOCA Loads Page 2 If you have any questions on this response, please contact my office.

Very ly ours, J. J Carey 4

Vice President, Nuclear 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 P.O. Box 26666 One James River Plaza Richmond, VA 23261 l

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