ML19312C944
| ML19312C944 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/18/1973 |
| From: | Thies A DUKE POWER CO. |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19312C945 | List: |
| References | |
| NUDOCS 8001140600 | |
| Download: ML19312C944 (2) | |
Text
. _ _
AEC Die 7ITUTIO3 FCR PART 50 torYET MATeoIAL CONTROL NO:
5 /M (TDIPORARY FORM) 1 e
FILE:
DATE OF DOC DATE REC'D LTR MEMO RPT OILER FRCH:
Duke Power Company Charlotte. N. C.
28201 7-18-73 7-23-73 X
A. C..Thies.
TOs SENT LOCAL PDR X
1 stened Mr. neYouno CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
1 50-270 XX ENCLOSURES:
DESCRIPTION:
Report on Fuel Rod Cladding Study in Ltr trans the following:
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Dune PowEn COMPANY Pt>WER DUIt DINO 422 SOtJTit CH UNCH STREET, CHW1DTTE, N C. reso P. O. Ilon 217s St pesON VICE pee,sLE NT P#00UC ? SON AND TeaNtesessecos p,,p p July 18, 1973 W L
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Mr. R. C. DeYoung, Assistant Director 4 ',,
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for Pressurized Water Reactors Q
Directorate of Licensing N
U. S. Atomic Energy Commission 9-Washington, D. C.
20545 C
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Re: Oconee Nuclear Station Unit 2 Docket No. 50-270
Dear Mr. DeYoung:
The Babcock & Wilcox Company and Duke Power Company are currently con-sidering a fuel rod irradiation program in Oconee Unit 2 Core 1.
This program has been discussed with members of your staff, and based on their concurrence, we are proceeding with modification of two Oconee 2 Batch 2 fuel assemblics. The attachment provides a description of this program and will be added to the Final Safety Analysis Report as a supplement as soon as practical.
In addition, the supplement will be referenced in the Final Safety Analysis Report as follows:
(1) On FSAR Page 3-63, add a note at the bottom of the page stating:
"A maximum of 48 test fuel rods may be included in two Batch 2 fuel assemblies of Oconce 2; see Supplement 16."
(2) On FSAR Page 3-79 just above Table 3-24, add a note stating:
"A maximum of four test orifice rod assemb31es may be included in Oconee 2; see Supplement 16."
We believe that this program will enable Duke and B&W to gain a better understanding of fuel densification phenomena, pellet cladding, inter-action, and Zr-4 cladding creep.
Very 'ruly yours,
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,g3 31973 P '5 ACT:vr 117
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