ML19308C002

Discusses Davis-Besse Staff Treatment of Safety Issue Re Pressurizer Voiding,Discovered During IE Insp Rept 50-346/78-06.Condition Not Analyzed in Sar.Licensee Actions Should Be Examined

ML19308C002
Person / Time
Site:	Crane, Davis Besse
Issue date:	12/19/1978
From:	Creswell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
TASK-TF, TASK-TMR NUDOCS 8001170743
Download: ML19308C002 (2)

See also: IR 05000346/1978006

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December 19, 1978

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Docket No. 50-346

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G. Fiore111, Chief, Reactor Operations and Nuclear ,

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MDIORANDUK FOR:

Support Branch

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J. F. Strecter, Qiicf Nuclear Suj> port Section 1

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J. S. Cresuell, Reactor Inspector-

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CONCERN REGARDING VOIDIliG OF FRESSU

SUBJECT:

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ding th$ treatment of a safety issu

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_This is to inform you'of.a concern regar

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by the Davis-Besse staff.'

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MrI streateP informed me'of'the resud Mr.' Knop, ha

On December- 18,-1978]

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. sation that he, Mr. Tambling, anApparently,iunder_certain conditions,

ith, auxiliary

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to void the pressuriser by overfeeding the ateam generators _w

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To my ktiowledge, this. condition is not analyzed ~inthnl sa

Further, . voiding in the hot les. associated with the

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feedwater.

The foregoing

[ pressurizer can result in blocked flow in that loop. c

_ analysis report.

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stion.

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ce during

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I first encounpared the problem with pressurizer level na

1977..

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an inspection 1

During the course of that inspection, I reviewed a si= nary

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November - 29, 1977

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This report stated:

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coolant shrunk, we lost level to

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"As the prinary system reac or

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the pressurizer."

In addition the following statements were noted:

"We have asked B&W to investigate why we had this rapid decreas

Specifically, we

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in temperature of the reactor coolant system.

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have asked the following:

50-346/78-06.

If IE Inspection Report

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800117o 7

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Are we maintaining too high a level of relatively cold water in theWe int

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secondary side of the steam generators?

90 inches of 70 F water to each steam generator through the automatic

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starting of the auxiliary feedpumps.

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1 questioned the licensee about the results of the EW inquiry, and aske

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to see documentation regarding the matter.

No docu-

was available since the matter was discussed over the telephone.The licensee did

mentation of the telephone conversations were available. s

in level.

~ here was Yproblem with the. voiding of pressuris

tresponse has been, no,. there wasn' t."

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II feel'tiut NRC should conduct,a thorough investigatio

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identified it (BW or TECo') and if the issue was properly reported per

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In addition,' the licensee's performance

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the requirements of Part 21.regarding any corrective actions associa

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examined in light of reguintory requirements. --

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J. S. Creswell

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Reacter Inspector

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R. E. Knop

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T. N. Tambling

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