ML20049A314

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Submits Comments on Licensee Response to 800122 Info Request Re Basis for Auxiliary Feedwater Sys Flow Requirements
ML20049A314
Person / Time
Site: Beaver Valley
Issue date: 10/27/1980
From: Speis T
Office of Nuclear Reactor Regulation
To: Parr O
Office of Nuclear Reactor Regulation
Shared Package
ML093450149 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8011070179
Download: ML20049A314 (2)


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OCT 2 71980 Docket Nos.: 50-334 MEMORANDUM FOR: Olan Parr, Chief, Auxiliary Systems Branch, DSI FROM:

Themis P. Speis, Chief, Reactor Systems Branch, DSI

SUBJECT:

AFW FLOW REQUIREMENTS FOR BEAVER VALLEY UNIT 1 Reactor Systems Branch has reviewed responses by Beaver Valley, Unit 1 to the NRC information request of January 22,1980, " Basis for Auxiliary Feed-water System Flow Requirements." Our comments are as follows:

1.

350 GpM AFW flow to the SGs has been demonstrated to be sufficient to meet acceptance criteria for transients and accidents. Therefore, the AFW system must have the capacity to supply at least 350 gpm total to the SGs.*

2.

The above auxiliary feedwater capacity must be supplied to at least two steam generators (in order to provide adequate heat transfer area).

3.

The auxiliary feedwater system must be guaranteed to satisfy require-ments numbers 1 and 2 for an initiating event plus Auxiliary Systems Branch failure criteria for auxiliary feedwater systems.

4.

The licensing analyses (feedwater line break) assume operator action at 10 minutes to properly distribute auxiliary feedwater flow. Auxiliary Systems Branch should determine the acceptability of this assumed time for operator actions to assure adequate auxiliary feedwater system per-formance following a feedwater line break event.

5.

Reactor Systems Branch considerations impose no upper bound for maximum auxiliary feedwater flow rates permissible for these plants; however, a bound may be set based on another branch's branch criteria, for example, Containment Systems Branch. Containment Systems may be consulted to verify maximum permissible auxiliary feedwater flow rate.

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Themis P. Spets, Chief l

Reactor Systems Branch Division of Systems Integration i

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  • An exception to this required flow rate is that no AFW flow has been shown to be required for the first 10 minutes of a feedwater line break (350 gpm thereafter. See item 4) l

Contact:

F. Orr

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