ML19344E037

Special Rept 80-2,Revision 1:on 800706,moderator Temp Coefficient Found Not to Meet Tech Specs Criteria.Control Rod Withdrawal Limits Determined.Conservatism Included in Limits to Ensure Proper Reactor Operation

ML19344E037
Person / Time
Site:	Sequoyah
Issue date:	08/18/1980
From:	Calhoun J TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8008260543
Download: ML19344E037 (3)

Text

TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 1750 Omstant Street Tooer II

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POOR ORIGINAL Mr. James P. O'Reilly, Direster U.S. Mosleer Regalatory h =ia=

Offias of Inspestiam and anfareamsat l

Rassen u 1a1 morsetta street, seite 3100 Atlanta, Geersia 30303 Deer Mr. O'Enf11 3 7

'N m neumann VALLET AUT30EITT - SEQUUTAE IEICLEAR FLANT UNIT 1 - PO E rr

30. 305-327 - FACILI!T OPEEAZING LICIEEE Drn SPECIAL REPORT 86 REFISION 1 The enslemed report, whish ourr1-*= our latter dated July 15, 1960, provides 4=faw==*ia= eseem a positive moderater temperature assifiasset whiah was meneered during the law poser phyelas testing at the all oestrel reds out a== fig===*1==.

This raport is submitted la asserdenes with Segueysk unit 1 T==h= h t ' - m==*4

-- 6.9.2 and 3.1.1.3.

Very truly yours, TEMNEREME TALLEY AgTunany J. 1. Calhous Diressor of Reeleer Feuer assimeure (3) es (Easleeure):

Diressor (3)

Offias of Ma==gn===* Inf====tiam and Program Central U.S. Eseleer Regolasery w==i==

Weah1astem, BC 20555 Diressor (40)

Offias of Inspestime and ' "+-:-

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U.S. Ih=s t aar = ; " _

" "- = __ DC 20555

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oW mr. nau x.s ne.

Meeleer Safety amalvets Center Pale Alte. California 94303 b

Mr. W. T. Cottle, NEC Inspester, Sequeysk u 2:uu c c:cc:-a, t,:-

8008210 l S '1 S 3

.s SPECIAL REPORT 80 REVISION 1 l

MODERATOR TEMPERATURE COEFFICIENT

'd The all control rods out, beginning of life, moderator temperature

-5 coefficient (MIC) was determined on July 6,1980, to be 0.85 x 10 delta k/k/0F. This does not meet the criteria of less positive than 0 delta k/k/0F established in the Sequoyah Nuclear Plant Unit 1 Technical Specifications. Control rod withdrawal limits (see attached)

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have been determined. A conservatism of 1 x 10 delta k/k/ F has been included in the limits to ensure that the reactor is not operated with a positive MIC. The predicted burnup at which the MIC will be restored to within its limit is 1000 MWD /MIU.

This report is submitted in accordance with Technical Specification 6.9.2 and 3.1.1.3 Action a.

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