ML19308D053

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Responds to NRC 780120 Request for Assessment of Potential for Damage of NSSS Components Due to Postulated RCS Piping breaks.BAW-1597, Effects of Asymmetric LOCA Loadings - Phase II Status, Is Interim Rept for Facility
ML19308D053
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/15/1980
From: Crouse R
TOLEDO EDISON CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
593, NUDOCS 8002250550
Download: ML19308D053 (1)


Text

TCLEDO EDISON Docket No. 50-346 meswa p Cwet momne aw License No. NPF 3 ew as ur Serial No. 593 February 15, 1980 Director of Nuclear Reactor Regulation Attention:

Mr. Robert N. Reid, Chief Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Reid:

On January 20, 1978, Mr. Victor Stello, of your staff, requested of "all PWR licensees" an assessment of the potential for damage of nuclear steam supply system (NSSS) components due to postulated reactor coolant system piping breaks. Toledo Edison has participated jointly with other Babcock & Wilcox NSSS owners and have issued an interim report in response to your request.

This interim generic report is entitled, BAW 1597, " Effects of Asymmetric LOCA Loadings - Phase II Status" and is applicable to the Davis-Besse Nuclear Power Station, Unit 1 (DB-1).

This has been submitted to your staff by letter from Mr. J. H. Taylor of Babcock & Wilcox on February 14, 1980.

This report provides the status o' the assessment effort to-date; a final report is scheduled to be submitted no later than July 1, 1980.

Very truly yours,

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//O THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO CHIO 43652 8002250 55O

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