ML19210A577

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Notifies of Favorable Review of Containment Design Mod Request Submitted 680701 in PSAR Amend 11 & in . Requests Addl Info Re Listed Items.Final Approval Subj to NRC Evaluation of Sys Adequacy at OL Review Stage
ML19210A577
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/24/1968
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Neidig R
METROPOLITAN EDISON CO.
References
NUDOCS 7910300615
Download: ML19210A577 (3)


Text

  • y' Docket No. 50-289 Metropolitan Edison Company P. O. Box 543 Reading, Pennsylvania 19603 Attn:

Mr. R. E. Neidig Vice President Gentlemen:

We have reviewed your request to modify the containment design of the Three Mile Island Nuclear Station such that 170-wire, rather than 90-wire, DBaV tendons will be uti-lized.

Our review was based on your Amendment 11, dated July 1,1968, to the PSAR and in supplementary information provided in a letter to us dated October 9, 1968 and in our meetings.

We conclude that you have submitted that information essential to our review that is now available.

1Ye also understand that you will provide the following information as it becomes available:

(1)

A stress analysis of the anchorage hardware com-ponents to determine approximate stress / strain values at critical sections, and, in addition, an evaluation Jf oXisting and/or additional test data on the effects of assembly eccentricities.

(2)

Results of tests of full size tendon anchorage system (s) at a temperature at least 30 F lower than the lowest service metal temperature for the Three Mile Island facility.

1491 330 (3)

The results of an evaluation on the effect on the bearing plate of welding the trumpet to the plate.

(4)

The results of an evaluation at the anchorage zone 32 thc gffects of local svorstress and uivavuisvLau, OFFICE >

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I On the basis of our evaluation to date and our under-standing of the additional information you will provide, we are agreeable to a 170-wire BBRV system in the design of the containment for the Throo Mile Island facility.

This is, however, subject to our evaluation of the ade-quacy of the system at the operating license review stage when the design has been completed and all omitted technical information has been supplied.

11aceroly, Orignal Signed by Peter A. Morris Peter A. Morris, Director Distribution

Division of Reactor Licensing PDR Formal file Suppl.g s DR reading fil]e DRL reading file RPB-3 reading file M. M. Mann C. K. Beck

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Karas L. L. Kintner D. F. Ross J. R. Buchanan, OnNL (see attached for other concurrences)

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'ietropolitan Edison Company On the basis of our evaluation to date and our under-standing of the information you will provide, we conclude that the proposed change to a 170-wire DBRV system is acceptable.

Sincerely, Peter A. 'forris, Director Division of Reactor Licensing Distribution:

Public Document Room Formal File Suppl.

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