ML20053D269

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Submits Info Re Reactor Vessel Head & Core Upper Internals Lifting Devices for Updated Sections 2.1.5.C & 2.1.8.C of NUREG-0612
ML20053D269
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/01/1982
From: Clayton F
ALABAMA POWER CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8206040249
Download: ML20053D269 (2)


Text

Malling Address Alabama Pomer Company 4

600 North 18th Street Post Ofhce non 2641 Birm ngham, Alabama 35291 Telephone 205 783-6081 F. L. Clayton, Jr.

R";'y;c;Pgdent AlabamaPower 9

the Southem dttrC Sys!em June 1, 1982 Docket Nos. 50-348 50-364 Mr. D. G. Eisenhut, Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Joseph M. Farley Nuclear Plant - Units 1 & 2 NUREG-0612 - Control of Heavy Loads

Dear Mr. Eisenhut:

As an update to sections 2.1.5.c and 2.1.8.c of Alabama Power Company's March 15, 1982 response to the Franklin Research Center's (FRC) Technical Evaluation Report concerning the above subject, the following information is submitted.

Alabama Power Company performed a review to determine if rigging devices other than the reactor vessel head and core upper internals lifting devices should be classified as "special lifting devices."

As a result of this review, no other special li f ting devices were identified.

In addition, FRC requested the performance of a comparison of the above lifting devices with ANSI N14.6-1978.

Both of these lifting devices were designed by using a safety factor of five for lifting loads under dynamic conditions.

This design provides adequate confidence that heavy loads will not be dropped on the reactor core.

Since considerable experience has been gained by the nuclear indust ry in the use of these and similiar lifting devices without any known problems, it is Alabama Power Company's position that no further action is necessary.

A similar comparison was performed on the polar crane.

This comparison revealed that the polar crane is in compliance with ANSI B30.2-1976.

OY I

I p 8206040249 820601 PDR ADOCK 05000348 P

PDR

4 Mr. D. G. Eisenhut, Director June 1, 1982 Nuclear Reactor Regulation Page 2 U. S. Nuclear Regulatory Commission If there are any questions, please advise.

Yours very truly, O

F. L. Cla o, J r.

FLCJ r/RWS:Is h-D13 cc:

Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford