LD-87-052, Requests That Steam Generator Tube Vibration Issue Be Closed on C-E Std SAR - FSAR (CESSAR-F) Docket.Any Potential Design Improvements for Future Steam Generators Can Be Reviewed as Part of Review of Improved Design Sys 80+

Requests That Steam Generator Tube Vibration Issue Be Closed on C-E Std SAR - FSAR (CESSAR-F) Docket.Any Potential Design Improvements for Future Steam Generators Can Be Reviewed as Part of Review of Improved Design Sys 80+

ML20235F708
Person / Time
Site:	05000470
Issue date:	09/18/1987
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Miraglia F NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
LD-87-052, LD-87-52, NUDOCS 8709290288
Download: ML20235F708 (2)

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September 18, 1987 LD-87-052 Docket No. STN 50-470F Mr. Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation Attn: Document Control Desk j U.S. Nuclear Regulatory Commission i Washington, D.C. 20555

Subject:

Steam Generator Tube Vibration l

Reference:

C-E letter LD-87-038, A. E. Scherer to Dennis M.

Crutchfield, dated July 13, 1987

Dear Mr. Miraglia:

The purpose of this letter is to request that the Steam Generator Tube Vibration issue be closed on the Combustion Engineering Standard Safety Analysis Report - FSAR (CESSAR-F) docket.

The program for resolution of the generic Steam Generator Tube Vibration issue, as described in the reference letter, has two major components.

The first includes operating plants and results in the plugging and staking l of the potentially affected tubes, coordinated with a monitoring and inspection program. The second component will assess the need for design -

improvements for our System 80+M design.

Based on our efforts to date, Combustion Engineering has not identified l any design change to the operating steam generators which would be necessary to assure their continued safe operation; nor do we have any reason to believe that such changes will be identified by the ongoing components of our program. In other words, we believe that the plugging, staking, monitoring and inspection program assures continued safe operation for all plants which referenced PDA-2. We request, 1 therefore, that the Steam Generator Tube Vibration issue be closed out on '

the System 80 design review.

B709290298 870918 PDR ADOCK 05000470 A PDR, Power Systems 1000 Prospect Hill Road (203) 688-1911 Combustion Engineering, Inc. Post Office Box 600 Windsor, Connemicut 06095 0500 Telex: 99297 pPh l l

Mr. Frank J. Miraglia LD-87-052 September 18,, 1,98,7 Page 2 .

. Any. potential design improvements for future Steafn Generators can be reviewed as part of your. review of our' improved design, System 80+.

If you have any questions or comments, please do not hesitate to call me or Dr. M. D. Green of my staff at (203) 285-5204.

Very truly yours, COMBUSTION ENGINEERING, INC.

Director Nuclear Licensing AES:ss i

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