ML19254D836

Forwards Map of Reactor Vessel,Depicting Vertical Weld Seams at Belt Line Evaluation Relative to Core & Surveillance Capsule,In Response to Question Raised at 790525 Meeting W/Nrc

ML19254D836
Person / Time
Site:	Fort Calhoun
Issue date:	10/25/1979
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Harold Denton, Reid R Office of Nuclear Reactor Regulation
References
REF-GTECI-A-11, REF-GTECI-RV, TASK-A-11, TASK-OR NUDOCS 7910300235
Download: ML19254D836 (2)

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_.h Omaha Public Power Disnict 1623 HARNEY OMAHA, NEBRASKA 68102

• TELEPHONE 536-4000 AREA CODE 402 October 25, 1979 Director of Nuclear Reactor Regulation ATTN:

Mr. Robert W. Reid, Chief Operating Reactors Branch No. h U. S. Uuclear Regulatory Commission Washington, D. C.

20555

Reference:

Docket No. 50-285 Gentlemen:

The Omaha Public Power District met with members of the Com-mission's Staff on May 25, 1979, to discuss results of evaluations performed on the removed Fort Calhoun Station reactor vessel sur-veillance capsule.

In respense to a question posed by the Staff at the meeting, please find attached an end of life fluence map of the reactor vessel which depicts reactor vessel vertical veld seams at the belt line elevation relative to the core and the surveillance capsule.

Sincerely, W. C. Jones Division Manager Production Operations WCJ/KJM/BJH:,Jcm Attach.

cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Aver >1e, N. W.

Washington, D. C.

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