ML19327A206

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Provides Review of Loss of Feedwater Accident Scenario Postulated in NRC 800728 Telcon.Line Break Accident Analysis Judged Breaks in Main & Auxiliary Sys W/ & W/O Offsite Power Loss.Fsar Limiting Accident Is Main Break W/O Power Loss
ML19327A206
Person / Time
Site: North Anna 
Issue date: 07/28/1980
From: Sylvia B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Youngblood B
Office of Nuclear Reactor Regulation
References
592A, NUDOCS 8008010271
Download: ML19327A206 (1)


Text

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VinorxrA ELucrnic Ann Pownn Co>uwxr Rrcztxoxn,VznorazA 20261 July 28, 1980 Mr. Harold R..Denton, Director Serial No. 592A Office of N'1 clear Reactor Regulation N0/LEN:smv Attention:

Mr. B. Joe Youngblood, Chief Docket No.59-339 Licensiag Branch 1 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

NORTH ANNA UNIT 2 AUXILIARY FEEDWATER SYSTEM REQUIREMENTS We have reviewed the loss of feedwater accident senerio postulated by Olan Parr of your staff in a telecon on July 28, 1980.

This condition, a loss of offsite power plus a high energy line break in the auxiliary feedwater system and a single failure, was considered by Westinghouse under the feedwater line b

break analysis rather than under the normal loss of feedwater accident analysis.

The feedwater line break accident analysis considered breaks in the main and the auxiliary feedwater systems, both with and without the loss of offsite power. The limiting accident, as identified in our FSAR and shown in Table 2-1 of our July 10, 1980 letter, is the main feedline break without the loss of offsite power which requires 340 gpm to be delivered to one steam generator.

If you have any questions or should require additional infornation, please contact us.

Very truly yours,

./.U k

L. R. Sylvia Manager - Nuclear Operations and Maintenance LEN/smv:S01 cc:

Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II Atlanta, Georgia 30303 8008010 N/

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