ML18143A980

Letter in Response to Reviewing the Design Bases for the Reactor Vessel Support System

ML18143A980
Person / Time
Site:	Ginna
Issue date:	11/20/1975
From:	White L Rochester Gas & Electric Corp
To:	Purple R Office of Nuclear Reactor Regulation
References
Download: ML18143A980 (4)

Text

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VICE PRESIDENT TtttP<<IONE ARCA CODE TIS 546.2700 November 20, 1975 Director of Nuclear Reactor Regulation ATTN: Mr. Robert A. Purple, Chief Operating Reactors Branch Il U.S. Nuclear Regulatory Commission Washington, D.C.

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Dear Mr. Purple:

This reply is in response to your letter dated October 15, 1975 and received October 22, 1975.

We have reviewed the design bases for the reactor vessel support system at R.E. Ginna Nuclear Power Plant.

The three dimensional forces developed by our nuclear steam system supplier and given to our architect engineer for the design of the supports included the vessel deadweight and piping reactions which would result from unbroken attached loop piping.

Transient effects due to asymmetric differential pressures in the annular region between the vessel and the shield and across the core barrel within the reactor vessel were not considered.

At the time Ginna Station reactor vessel supports were designed, the forces due to the asymmetric pressure in the cavity surrounding the reactor vessel were not understood and thus were not considered.

The reactor pressure vessel internals forces also were not calculable at the time of the design of Ginna Station.

The methods for the analysis of these asymmetric loads were developed only recently.

This issue is complex.

Even quantification of the potential problem requires specific plant analyses involving significant engineering effort.

As a result, RGGE will continue discussions with our nuclear steam system supplier to determine an ap ropriate course of action.

c'incerely

yours, L. D. Whi e, Jr.

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