ML20197G503

Forwards SER Re Generic Ltr 81-21, Natural Circulation Cooldown. Safety Concerns Re Reactor Vessel Upper Head Voiding During Natural Circulation Cooldown Adequately Addressed

ML20197G503
Person / Time
Site:	Three Mile Island
Issue date:	06/05/1984
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Hukill H GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20197G509	List: ML20197G503 ML20197G517
References
GL-81-21, NUDOCS 8406150278
Download: ML20197G503 (1)

Text

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D June 5,1984 oc&

Docket No. 50-289 Distribution:

WHouston Docket File JNGrace I

BSheron Reading File TBarnhart 4 '

NLauben NRC PDR DBrinkman

) RJones L PDR RDiggs Mr. Henry D. Hukill, Vice President 0 ELD WJones and Director - TMI-1 ACRS 10 LHarmon GPU Nuclear Corporation HDenton CMiles i- P. O. Box 480 DEisenhut TPoindexter.

l Middletown, Pennsylvania 17057 RIngram BSnyder d 0 Thompson TMI Site Pouch

Dear Mr. Hukill:

JVanVliet EBlackwood i EJordan H0rnstein

+

We have ccmpleted our review of your letters dated December 7,1981 and April 4,1984 that respond to Generic Letter 81-21, Natural Circulation j Cooldown, dated May 5,1981 (Multiplant Action B-66). Our Safety Evaluation 1

is enclosed. ,

} The Generic Letter requested your assessment of three items. Our conclusions j on these items are as follows:

! 1. Your analysis of reactor vessel upper head cooldown, using the HEATING 6 computer code, shows that reactor vessel voiding should not occur during natural circulation cooldown conducted as described .in your submittals.

We find your analysis acceptable. Also, the guidance for revising the j procedure "TMI-1 Natural Circulation Cooling Procedure, OP 1102-16," and l your implementation date of June 1984 are acceptable.

} 2. We concur in your conclusion that you have adequate supplies of

condensate-grade auxiliary feedwater to support your cooldown method.

3. We find that your training program and the provisions of your procedures

will be adequate, after implementation of your revised' procedure in

! June 1984, to deal with prevention or mitigation of reactor. vessel l voiding during natural circulation'cooldown.

j We conclude that safety concerns regarding reactor vessel upper head voiding

,' during natural circulation cooldown have been adequately addressed.

I Sincerely, '

I I John F. Stolz, Chief Operating Reactors Branch-No. 4 Division of Licensing

Enclosure:

j' Safety Evaluation -

cc w/ enclosure: .

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8406150278 840605 PDR ADOCK 05000289 ' ^

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