ML20117F343

Notifies of Submission of Completed 10CFR50.59 Safety Evaluation & Load Path Drawing by 961101 Instead of License Amend Re NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in the Reactor Core or Over Safety

ML20117F343
Person / Time
Site:	San Onofre
Issue date:	08/29/1996
From:	Rainsberry J SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-002, IEB-96-2, NUDOCS 9609040020
Download: ML20117F343 (2)

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1. g" Southem Califomia Edison Company P,O. DOM 128 SAN CLEEMENTE, CALIFORNIA 92674-0128 J. L. RAINSBERRY August 29, 1996 TELEPHONE SAN ONOF EN LE E T O S T ATION U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety Related Equipment" San Onofre Nuclear Generating Station Units 2 and 3

Reference:

Letter from Walter C. Marsh (Edison) to the Document Control Desk (NRC) dated May 14, 1996;

Subject:

Draket Nos. 50-361 and 50-362 Response to NRC Bulletin 96-02, " Movement of Heavy Loads Gver Spent Fuel, Over Fuel in the Reactor Core, or Over Safety Related Equipment," San Onofre Nuclear Generating Station Units 2 and 3 In a May 14, 1996, letter (Referenced) Southern California Edison (Edison) informed the NRC that Edison would be submitting a license amendment application requesting approval to lift a 480 V auxiliary transformer during Modes 1 through 4. The referenced letter stated that Edison planned on submitting this request by August 30, 1996, and would request approval by March 3, 1997.

Edison has re-evaluated our plans to install a second, independent lifting hoist against the guidelines contained in NUREG 0612, Appendix C, and 10 CFR 50.59 for the portion of the lift that will be over safety related equipment. By using manually operated, redundant hoists, Edison believes that the single failure proof crane guidelines of NUREG 0612 are met and a successful 10 CFR 50.59 safety evaluation can be performed.

Therefore, instead of submitting a license amendment application, which is not required, as discussed with our NRC Project Manager, Edison will submit a completed 10 CFR 50.59 safety evaluation and load path drawing for your information by November 1, 1996.

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Document Control Desk If you have any questions in this matter, please call me.  ;

Very truly yours, h

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cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3