ML19273C110

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Responds to NRC Re Small Break LOCA analysis.C-E Rept, Review of Small Break Transients in C-E Nuclear Steam Supply Sys, CEN-114-P,constitutes Response to Request for Addl Info
ML19273C110
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/14/1979
From: Short T
OMAHA PUBLIC POWER DISTRICT
To: Reid R
Office of Nuclear Reactor Regulation
References
NUDOCS 7908270405
Download: ML19273C110 (1)


Text

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Omaha Public Power District 1623 HARNEY e OMANA. NESRASMA 68102 e TELEPHONE S36 40C0 AREA CODE 402 August 14, 1979 Mr. Robert W. Reid Operating Reactors Branch #4 Division of Operating Reactors t

U. S. Nuclear Regulatory Comission 7920 Norfolk Avenue Bethesda, Maryland

References:

1.

Letter from R. W. Reid to All Combustion Engineering Designed Operating Reactors, dated June 5,1979.

2.

Review of Small Break Transients in Contustion Engin-eering Nuclear Steam Supply System, CEN-114-P, dated July, 1979.

Dear Mr. Reid:

Reference (1) transmitted an NRC request for additional information con-cerning the Small Break LOCA Analysis in the light of events which occurred at Three Mile Island Unit 2.

As a result of this request, an Owners Group was formed which has worked closely with Combustion Engineering, Inc. to produce the requested response.

Reference (2) contains the Owners Group and Combustion Engineering res-pcases to this request.

This report supercedes the preliminary documen-tation submitted to you on July 18, 1979.

This response is applicable to Fort Calhoun Station Unit No. I and, therefore, constitutes our response to Reference 1.

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T. E. Short Assistant General Manager TES/KJM/JKG/ rh xc:

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N. W.

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Washington, D. C.

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