ML18219E118

Response to Letter of 11-26-75, Furnishing Additional Information Concerning Reactor Vessel Support System

ML18219E118
Person / Time
Site:	Cook
Issue date:	12/29/1975
From:	Tillinghast J Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Rusche B Office of Nuclear Reactor Regulation
References
Download: ML18219E118 (6)

Text

NRC Dlc BUT!ON FOR PART 60 DOCKET I i ERIAL (TEMPORAR Y FQ RM)

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FROM: India a & Michigan Pwr Co DATE OF DOC DATE R EC'D LTR TWX RPT OTHE R New York, NY 12-29>>75 12-31-75 TO: ORIG one signed CC OTHER SENT)(RU PORE, Mr Rusche

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CLASS UNCLASS PROPINFO INPUT NQ CYS REC'D DOCKET NO:"

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our 11-26-75 ltr..... furnishing addi 1

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INDIANA II MICHIGAN POWER COMPANY P. O. BOX 18 BO WL I N G G R E EN STAT ION NEW YORK, N. Y. 10004 December 29, 1975 Donald C. Cook Nuclear Plant Docket No. 50-315 and. 50-316 DPR No. $ 8 CPPR No. 61

>0 Mr. Benard Rusche, Director Office of the Nuclear Reactor Regulation >ol:xo<>

u%889 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 6-

~~ gyp/6 0 Dear Mr.

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The letter of November 26, 1975 from Karl Kniel requested. that we review the design bases for the reactor vessel support system for the Donald C. Cook Nuclear Plant to determine whether the transient loads, described in the enclosure to that letter, were taken into account appropriately in the design.

With respect to loading due to blowdown jet forces, the design of the reactor vessel supports took into account jet forces due to a rupture of either the hot leg or cold leg pipe of the reactor coolant system within the pipe penetration sleeve. Both guillotine and longitudinal ruptures were considered. This evaluation was performed employing the analysis methods available at the time of the design.

The methods for the analysis of asymmetric loads were developed only recently and were not available at the time of the Donald C. Cook Nuclear Plant's design. Therefore, the two other loads mentioned in your letter, namely (1) the transient differential pressure in the annular region between the reactor vessel and the shield. wall and (2) the transient

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1 Mr. Benard Rusche December 29, 1975 differential pressure across the core barrel within the reactor vessel, were not considered. in the design of the reactor vessel supports.

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Very truly yours, o n Till nghas Vice President JT:mam cco Go Charnoff Ro Walsh R. J. Vollen R. C. Callen P ~ W. Steketee R. 8..Hunter R. W. t'urgensen - Bridgman

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