ML20002C966
| ML20002C966 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/10/1969 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P, Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101150489 | |
| Download: ML20002C966 (4) | |
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January 10, 1969 Dr. P. A. Morris, Director Re: Ibeket 50-155 Division of Reactor Licensing DPR-6 7EK United States Atomic Energy Commission Washington, D. C.
20545
Dear Dr. Morris:
Attention: Mr. D. J. Skovholt As a follow-up to conversations with your staff, we are sending you infor=ation on the mechanical design and manufacturing changes of a single Reload "E" fuel bundle (designated W-1) which will be inserted into the Big Rock Point reactor during our next fefueling outage in early 1969 The fuel bundle is being fabri-cated by a vendor other than our previous fuel supplier. However, it has been designed and manufactured to the same criteria as the Reload "E" fuel and as such does not, in the opinion of Consumers Power Company, involve an unreviewed safety question or a change to the Technical Specifications of License DPR-6, Docket No 50-155, issued to Consumers Power Company on May 1, 1964, for the Big Rock Point Nuclear Plant.
Discussion The mechanical design (see drawing attached) and fabri-cation of this Reload "E" Fuel Bundle W-1 was provided by Canadian Westinghouse and, hence, is slightly different from the other Feload "E" bundles in the following respect:
A combination of brazed wear pads and positioning grids F
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( M, h M Canadian Westinghouse Company, Ltd. Although it is somewhat different from the United States spring spacer concept, it has roven successful in the Canadian nu-4' e
clear power program. We expect that it vill prove gy
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The physics design of Reload Bundle W-1 is exactly equiva-lent to the other Reload "E" bundles. However, the fuel enrichment hk.lYhY
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Dr.'P A. Morris' 2
January 10, 1969 has been decreased slightly to compensate for a slightly increased fuel rod stack density. The bundle power distribution and all other physics characteristics of Bundle W-1 are exactly the same as the Reload "E"
. fuel; and the-flow analysis shows a slight increase in coolant flow arising from improved geometry characteristics of the W-1 bundle.
Hazards Considerations -
All present limits on control rod worth, heat flux, center
. melting, fuel temperature and critical heat flux ratio will be ob-served, and operation of the reactor will be within these limits.
In the R&D Program at Big Rock Point, it has been shown that major differences in mechanical design between fuel bundles have little or no effect with respect,to hazards considerations. The above-4 j
detailed design and manufacturing changes have not altered the re-sults of the hatards analyses. Based upon this, we have concluded that the use of Reload Bundle W-1 in the. Big Rock Point Nuclear Plant does not present a change in the hazards considerations described or implicit in the Final Hazards Summary Report.
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Yours very truly,
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