ML20009F240

From kanterella
Jump to navigation Jump to search
Interim Deficiency Rept,Originally Reported on 791227,re Cut Reinforcing Bar Possibly Causing Reduced Floor Load Capacity in Reactor Auxiliary Bldg.Investigation Continuing.Next Rept by 811106
ML20009F240
Person / Time
Site: Fermi 
Issue date: 07/10/1981
From: Wells D
DETROIT EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, EF2-53569, NUDOCS 8107300188
Download: ML20009F240 (2)


Text

.

h Donald A. Wells to Manager QuaMy As%rance 4

(O (313) 237 % 57 Edison er ue J 6j *!$o Lb l

2000 Second Aven a M o g198W,8 C

July 10, 1981 o [ g" f- /

EF2-53569 0

W' ',/h

,A Mr. Janns G. Keppler, Director \\'h/ #dli N *~

Region III U.S. Nuclear Regulatory Ccumission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Interim Report of 10CFR50.55(e) Item on Cut Reinforcing Bar (#25)

Dear Mr. Keppler:

The final report on the Cut Reinforcing Bar probl I: cannot be subnitted to you by July 10, 1981, as scheduled. This additit.a1 interim report is to provide you with the current status of the evaluation of this problem.

The item was originally reported to Mr. F. J. Jablonski of NRC-Region III by Mssrs. R.W. Barr and W.M. Street of Detroit Edison on December 27, 1979.

/U that time, it had been determined that cut rebar may have resulted in a s duced floor load capacity in the Reactor Auxiliary Building at the Fermi 2 site.

Sargent and Lundy Engineering had previously empleted an analysis of the five (5) nest critical slabs utilizing detailed field as-built layout dia-grams. Their evaluation indicated that rebar cuts have not significantly reduced the capacity of the slabs. The floor load design rating will be met and need not be reduced. Based on this report, Sargent and Lundy's analysis of the affected components is cmplete (SLS No.1840, dated Feb-ruary 13,1981). Only a 4" thick slab at elevation 697' 6" appeared to be overstressed, and hence, Sargent and Lundy is presently working on the re-analysis of the 4" auxiliary roof slab.

Another report on this item, either interim or final, is scheduled to be sent to you on or before November 6, 1981. If you have any questions ccn-cerning this matter, please contact Mr. H.A. Walker, Supervisor-Construction Quality Assurance.

Very truly yours,

)1 Mll I

DAW / HAW /cp

'dllte 2 4198f1 f 8107300188 8107 go

+

DR ADOCK 05000341' f

"DR g,

w Mr. James G. Keppler July 10, 1981 Page Two EF2-53569 cc: Mr. Victor Stello, Jr., Director Office of Inspection and Enforcement D; vision of Reactor Inspection Programs U.S. Nuclear Regulatory Coninission Washington, D.C. 20555 Mr. Bruce Little, Resident Inspector U.S. Nuclear Regulatory Ccmnission Resident Inspectors Office 6450 North Dixie Highway Newport, Michigan 48166