ML16340B230

Provides Comments on Facility Responses to NRC 800310 Info Request Re Basis for Auxiliary Feedwater Sys Flow Requirements.Sys Must Be Supplied to at Least Two Steam Generators in Order to Provide Adequate Heat Transfer Area

ML16340B230
Person / Time
Site:	05000000, Diablo Canyon
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: ML13319A698 ML14190A386 ML14190A407 ML14190A410 ML15260A018 ML16245A451 ML16245A464 ML16245A519 ML16340B230 ML17208A670 ML17208A671 ML17319A601 ML17340A460 ML18044A564 ML18044A670 ML18044A671 ML18082A762 ML18082A870 ML18082B237 ML18085A271 ML18139A593 ML18139A594 ML19207B142 ML19208A323 ML19254G983 ML19254H090 ML19254H091 ML19262E717 ML19264A126 ML19264B199 ML19271A912 ML19273C792 ML19273D125 ML19275E724 ML19275E727 ML19276J691 ML19281C520 ML19290G036 ML19290G038 ML19294C656 ML19294C857 ML19295B828 ML19295B969 ML19295D087 ML19295D182 ML19295E448 ML19295E739 ML19296E856 ML19296F114 ML19297A101 ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8011190165
Download: ML16340B230 (4)

Text

pqpllfli )I tIj/II( gl OI.'T 3'I gIg Docket Nos.:

50-275.

and 60-323 MEMORANDUM FOR:

Olan Parr, Chief, Auxiliary Systems

Branch, DSI FROM:

Themis P. Speis, Chief, Reactor Systems

Branch, DSI

SUBJECT:

AFW FLOW REQUIREMENTS FOR DIABLO CANYON, UNITS 1 5 2 Reactor Systems Branch has reviewed responses by Diablo Canyon, Units 1 and 2

to the NRC information request, of h1arch.10., 1980, "Basis for Auxiliary Feed-water System, Flow Requirements,"..

Our coments are as;follohis:

1.

440 GPM AFM flow to the SGs,has, been demonstrated to be sufficient to meet acceptance criteria for..transients hand accidents.

Therefore,

.the ARl system must have the capacity to supply at least 440 gpm total to the SGs.*

2.

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

3.

The auxiliary feedwater system must be guarang6eP 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 l,iye break) assume operator action at 10 minutes to properly distribute,auxiliary'feedwater flow.

Auxiliary Systems Branch should determiye the,acceptaSility of this assumed time for operator actions,to assure'adequate auxiliary feed-water system performance fol,lowing,a.feedwater, l,ine-break event.

6.

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.

ContailIment Systems may be consulted to verify maximum permissibl!e auxi.l.iary, feedwater flow rate.

Original Signed By Themis p. Sye>8 Themis P. Speis, Chief Reactor, Systems Branch Division of Systems Integration cc; See next page

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