ML19322B631
| ML19322B631 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/22/1973 |
| From: | Thies A DUKE POWER CO. |
| To: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19322B629 | List: |
| References | |
| NUDOCS 7912040653 | |
| Download: ML19322B631 (1) | |
Text
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Powna Burt.orno 4aa SouTu Cauncu SrazzT, CuAnzartz, N. C. asaos A. C. THtES P. O. Box 217e saNeOR vice PWationNr PROOuCr80N AND TRANSe8aSSION February 22, 1973 Mr. John G. Davis Directorate of Regulatory Operations U. S. Atomic Energy Commission Region II, Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re:
RO:II:JGD 50-269
Dear Mr. Davis:
With my letter of January 12, 1973, ten copies of the report summarizing our program of valve wall thickness measurements for Oconee 1 were for-warded to your office.
Enclosed are ten copies of Revision #1 to this report. Please update the report by inserting these revised pages.
The Crane wall thickness calculations for the four core flood check valves as submitted in the original report as part of Attachment 4 employed the most severe desip condi* ions of 2500 psig at 6500F.
However, this is true only for the two valves adjacent to the reactor (valves 1/53/2 and 4).
The design' conditions for valves 1/53/1.and 3 are 2500 psig at 300 F.
Using these conditions, the. required wall thickness for valves 1/53/1 and 1/53/3 is calculated to be 1.60 in.
This new calculation should become part of those calculations performed by Crane.
The design conditions incorporated in the new calculation are not detrimental to the other analyses presented in Attachment 4 of
~l the subject report.
~
Very truly yours,
$. $. /
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A. C. Thies ACT:vr Enclosures cc: Mr. W. S. Lee Mr. R. L. Dick Mr. W. H. Owen Mr. E. D. Powell 7912040 6'873
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