ML17199V399

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Documents 880317 Telcon Re Embedment Plate Assessment Program Re Analysis Method & Acceptance Criteria for Computation of Allowable Loads for Strip Embedment Plates W/ 24-inch Anchor Spacing
ML17199V399
Person / Time
Site: Dresden, Quad Cities, 05000000
Issue date: 03/31/1988
From: Johnson I
COMMONWEALTH EDISON CO.
To: Murley T
Office of Nuclear Reactor Regulation
References
4427K, NUDOCS 8804060524
Download: ML17199V399 (1)


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Commonlllth Edison One First Nat Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 - 0767 March 31, 1988 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 subject:

Dresden station Units 2 and 3 Quad Cities Station Units 1 and 2 "Response to Questions Regarding the Embedment Plate Assessment Program" NRC Docket Nos. 50-237/249 and 50-254/265

Dear Mr. Murley:

The purpose of this letter is to *document information provided in a March 17, 1988 conference call between members of your staff (T. Ross and R.

Lapinski) and our staff.

During that call, a question was raised whether the analysis method and acceptance criteria for computation of allowable loads for strip embedment plates *with 24 inch anchor spacing are the same as those for 18 inch anchor spacing.

At that time, it was indicated that the acceptance criteria is the same.

It was noted that the magnitude of the allowable loads is different due to the difference in. spacing.

This letter is being transmitted as a record of our March 17, 1988 conference call. Please direct any questions you may have regarding this matter to this office.

Very truly yours, I. M. Joh so Nuclear Licensing Administrator.',

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T. Ross - NRR

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i M. Grotenhuis - NRR

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B~ Davis---NRCRegion III

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