ML20206F066

Forwards Info to Suppl 880801 Amend Request for Change to License R-92 Tech Specs

ML20206F066
Person / Time
Site:	05000192
Issue date:	09/13/1988
From:	Bauer T, Fonken G, Klein D TEXAS, UNIV. OF, AUSTIN, TX
To:	Alexander Adams NRC
References
NUDOCS 8811180321
Download: ML20206F066 (2)

Text

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COLLEGE OF ENGINEERING o[6

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TITE UNIVERSITY OF TEXAS AT AUSTIN

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DepartmentopfechanicalEngineering Nucle.tr F.ngineeringProgwn Austin, Texas 78712 (312)4713136

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September 13, 1988 U. S. Nuclent Regulatory Cornission M. S . OkTN 11-H-3 k'ashington , D.C. 20555 Attn Al Adams Re Docket 50-192 (R-92)

Subject:

Letter of August 1, 1988 Dec.r Sir:

The enclosed infornation is provided to supplecent the acendrent request (August 1, 1988) fo. a change to the R-92 license technical crecifications.

Sincerely, j c ea s ) (A#

Thomas L. Eauer <

Assistant Director Nuclear EnF ir.ec. ring Teaching Laboratery AFl' ROVED :

Dale Klein, Director Nuclean Engineering Teaching Lab.

APPROVFD:

[b]) bOs-Cerhyd J. Fonken Exectitive Vice President & Provent 1LL/1s Enclosure ce: H. Marcus Signsd before ce this / I/m day of Septerber, .1968.

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(2Dt c .c4 e 7 ,g Notary for the State et Icxas.V /

NWA r singg "I'"f f 3 'D 1) 83111803:1 GOO 913 FDR ADOCK 0"XOO192 P FDC

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I f AMENDMENT TO TECHNICAL SPECIFICATIONS add:

1 4.2.1 f. The reactor shall not b6 operable untti the surveillancec a-e of this section are complete. Surveillance intervals for sections a-c of this section may be extended if the reactor is not operable.

add:

l 4.2.2 f. The reactor shall not be r erable until the surveillances a-e of this section are conplete. Surveillance intervals for sections a-e of this ccetien eay be extended if the

reactor is not crerable.

l ANA1.YSIS l

The specifications of section 4.2.1 erd 4.2.2 determine the surveillance requirements for liniting conditions of operation applicable to au cperable reactor core. The rourveillance requirements of section 4.2.1 and 4.2.2 sections e-e do not effect the safety of the shutdown recctor core if the conditions of shutdevn rerF i n and excess reactivity are as specified in section 3.2.1 and 3.2.2. If fuel is removed frem an operabic reactor core the general expectatico is that the conditions of section 3.2.1 and 3.2.2 vill continue to be applicable. Certainly this is f

the case in a partially loaded core. If the core array has an effe;cive culttplication factor of less than 0.8 with removal of the contrsi rods as crecified for a fuel storage array, the curveillance requiremerts of section 4.2.1 and 4.2.2 would not epply to the storage configuration safety and the conditions of section 3.2.1 c.nd 3.2.2 would attil ba app 11:able.

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