ML19350A556: Difference between revisions

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Latest revision as of 03:21, 18 February 2020

Interim Deficiency Rept Re Cut Reinforcing Bar,Originally Reported on 791227.Sargent & Lundy Engineering Completed Analysis of Five Most Critical Slabs.One Slab Appears Overstressed.Final Rept Will Be Forwarded by 810710
ML19350A556
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 03/10/1981
From: Wells D
DETROIT EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, EF2-49-946, NUDOCS 8103160482
Download: ML19350A556 (1)


Text

.

Detroit '

CS2,^ 5eNY?)NT$2:s

biwv !atar 22M:n I March 10, 19 d \Y %*l'S EF2-49,946 N/

\

Mr. James G. Keppler, Director Region III @j J , 7 h' A) )

U.S. Nuclear Regulatory Cccmission "Mk,j 3 g* I A -Q- -

- 14 4 799 Roosevelt Road Glen Ellyn, Illinois 60137 E

%l,gra,,77 c%

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Subject:

Interim Report M 10CFR50.55(e) Item en Cut Reinforcing Ba ,

Dear Mr. Keppler:

The final report cn the Cut Reinforcing Bar problem cannot be submitted to you by March 13, 1981, as scheduled. This additional interin report is to provide you with the current status of the evaluation of this problem.

This item was originally reported to Mr. F.J. Jabicnski of NRC-Region III by Mssrs. R.W. Barr and W.M. Street of Detroit Edisen cr. Decerber 27, 1979.

At that time, it had been determined that cut rebar ray have resulted in a reduced floor lead capacity in the Reactor Auxiliary Building at the Fermi 2 site.

Sargent and Lundy Engineering has cccpleted an analysis of the five (5) most critical slabs utilizing detailed field as-built layout diagrars.

Their evaluation indicates that rebar cuts have not significantly rs iuced the capacity of th slabs. The floor load design rating will be ret and need not be reduced. Based on this report, Sargent and Lundy's analysis of the affected ccupenents is c,ccplete (SL5 No.1840, datec February 13, 1981).

Only a 4" thick slab at elevaticn 697' 6" appears to be overstressed and hence would be subjected to more detailed investigation.

A final report cn this item should be submitted to you by July 10, 1981. If l

you have any questions concerning this matter, please contact Mr. H.A. Walker, Supervisor-Ccnstruction Quality Assurance.

l Very truly yours, t

Donald a. Nells,.".r 'ger j Ouality Assurance DW/HAN/cp

/

cc: Mr. Victor Stello, Jr., Director l Office of Inspection and Enforcement Division of Reactor Inspection Programs U.S. Nuclear Regulatory Cccrcission Washington, DC 20555

[ Ql O 8108160482 0