ML19347E700

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Submits Revised Response to FSAR Question 211.103.Responses Supersede Those Provided in FSAR Amend 17 & Will Be Contained in Next Amend Planned for Submittal in mid-May 1981
ML19347E700
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/11/1981
From: Maurin L
LOUISIANA POWER & LIGHT CO.
To: Tedesco R
Office of Nuclear Reactor Regulation
References
3-A29, W3P81-1252, NUDOCS 8105130244
Download: ML19347E700 (1)


Text

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I LOUISIANA 242 ceu acNas Srneer P O W E R & LI G H T[ P O BOX 6008

  • NEW ORLEANS.

70,74LOUISIANA

. (504) 368-2345 Eu?$2rsE W3P81-1252 3-A29 May 11, 1981 ,,

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Mr. R. L. Tedesco D-Assistant Director for Licensing # N' Division of Licensing -- Io, U.S. Nuclear Regulatory Commission

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Washington, D. C. 20555

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SUBJECT:

Waterford 3 SES Q/ **" ~ @s ' @'

Docket No. Lu-?>82 '#

Revised Response to FSAR Question 211.103 / ' #2 -

Dear Mr. Tedesco:

We have revised our responses to Reactor Systems Branch Questions 211.103, as submitted in Amendment 17, to read as follows:

The Chapter 15 accident analyses shall be reviewed to ensure that those transients which resulted in fuel DNBR less than 1.19 shal'1 be analyzed for radiological con-sequences assuming fuel clad failure for all such tran-sients.

An initial review indicated that in addition to the seized RC Pump Shaft addressed in Question 211.106, only the Increased Main Steam Flow with Concurrent Single Active Failure (Subsection 15.1.2. 3) and the Inadvertent Opening of a Steam Generator Atmospheric Dump Valve with Single Active Failure (Subsection 15.1.2.4) yield fuel with DNBR less than 1.19 which has not been assumed to have a similar amount of fuel clad failure.

These transients will be revised in the mid-May 1981 FSAR Amendment.

These responses supercede those submitted in FSAR Amendment 17 on April 30, 1981 and will be contained in the next amendment planned for submittal in mid May 1981.

Ve ' truly yours,

, BOO l L . i au Assistant Vice President Nuclear Opeations cc: Mr. E. L. Blake l Mr. W. M. Stevenson 1

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