ML19316A681
| ML19316A681 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/07/1973 |
| From: | Coffman F US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Rubenstein L US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001130231 | |
| Download: ML19316A681 (1) | |
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1973 hjhD L. S. Rubenstein, Core Performance Branch, L FSAR SUPPLDIENT, FUEL ROD & CLADDING STUDT IN OCONEE II The designs of the 48 " study" fuel rods plus the 4 orifice rod assemblics described in Mr. A.C. Thies', Duke Power Cocpany, letter to R.CC DeYoung, July 18,1973, were examined for similarity with the standard Oconce 11 fuel.
The only questionable variation noted was a decrease in cladding yield strength:
_ CLADDING.
PRODUCT SPECIFICATION (0.27. Yield Strength At Tc=0.)
Standard 45,000 psi Type 1 19,000 i
Type 2 23,000 Type 3 38,000 The fueled type 1 cladding was analysed for effects of fuel densification.
The staff code BUCELE was used to calculate the predicted time to creep collapse.
the as-built data.The input values were supplied by B&W to conservatively represent 23,000 psi rather than the specification value of 19,000 psi.The a BUCKLE calculations predict a time-to-collapse :
it:7 which is greater than the S.E.R. approved 7500 EFFH for the standard fuel.
Additional support for approzal is that the " study" rods will contain fuel pellets of higher density and smaller lengths.
The two assemblies to contain these " study" r6ds will occupy peripheral locations within the core.
It is reccenended the PSAR supplement be approved.
F. D. Coffman, Jr.
Core Performance Branch Directorate of Licensing B. Hardin Reactor Systems Branch Directorate of Licensing cet V. Stello O Y fb
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