ML19276D594

Forwards Branch Input to Facility SER Suppl Re B&W Mark-C Fuel Assembly Fretting & Wear.Believes Topical Rept Would Be Unnecessary

ML19276D594
Person / Time
Site:	Green County
Issue date:	12/27/1978
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-80-515, FOIA-80-555 NUDOCS 7901050391
Download: ML19276D594 (2)

Text

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DEC 2 71978

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Docket No.: 50-549

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ENORANDWf FOR:. D. B. Vassa1To, Assistant Director. for Light Water Reacers. DPM 7 ~~._'' '

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R. L. Tedesco', Assistant Director for Reactor Safety, DSS - ~'

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SUBJECT:

. GREENE COUNTY SER SUPPLEMENT ON MARK-C FUEL ASSEM LY FRETTING'AND WEAR

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Plant Name:

Greene County Docket Number:

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Milesh Mr-27-24~ ~

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Licensing Stage:

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PSAR ~ ~':

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Responsible Branch

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and Project Manager:

T ~~S.'Burwell

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Systems Safety Branch Involved: ~ Core Perfo~mance Branch

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Description of Review:

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Requested Completion Date:

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Review Status-

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The Reactor Fuel's Section of the Core Perfomance Branch has pritpared~~

the attached input'.to the Greene' County"SER Supplem^ent.

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Original Signed by Robert L. Tedesco

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Robert L. Tedesco. Assistant Direc+or for Reactor Safety

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_ Divisica of" Systems Safety cc:

S. Hanauer R. Mattson/F. Schroeder ' -~~' ~-~ '

R. Boyd

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R. Baer

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Files 79010503%

NRR Reading t' D D D n 1 A 4 r. r,

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B&W Mark-C Fuel Assembly Fretting and Wear In the Greene County SER we discussed tests to be performed by Babcock & Wilcox (B&W) to confirm the absence of fretting and wear in the Mark-C fuel assembly. We stated that results and interpretation of test data would be presented to NRC in a topical report at least one year prior to submittal of an FSAR on a reactor incorporating Mark-C fuel assemblies.

The topical report would also address the applicability and adequacy of the data.

We have subsequently been informed that B&W intends to address fretting and wear onia plant-specific basis. We believe that

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this is an acceptable procedure for the subject of fretting and wear, and that a topical report will not be necessary because, after operation of the first or second load of Mark-C fuel, we r

would not expect B&W to refer to preoperation predictions but rather to post-operation results (i.e., results from post-irradiation surveillance in the lead plants).

Thus, while a fretting and wear topical report would be convenient, it would not have archival value.

Bellefonte and Wash. Nucl.1 & 4 are expected to be the lead Mark-C plants, and results from post-irradiation examination of fuel from these plants will, therefore, precede the irradiation of Mark-C fuel in Greene County.

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