ML19345A293

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Responds to & 0313 Teletype Requesting Authorization to Make Limited Rearrangement of Fuel Assemblies in Core 10.Proposed Change 107 to Tech Specs Granted Based on Review
ML19345A293
Person / Time
Site: Yankee Rowe
Issue date: 03/14/1973
From: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
To: Minnick L
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML19345A294 List:
References
NUDOCS 8011180612
Download: ML19345A293 (2)


Text

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MAR i4 B73 Docket lio. 50-29 Yankee Atomic Electric Company AlTi:

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3.Mirnick Vice Pmaident 20 Tumpike Poad Westboro, Massachusetts 01581 Change No. 107 Gentle:nen:

License No. DPR-3 By letter dated Parch 1,1973, and supplemntal inforention contained in your teletype dated Parca 13, 1973, you mquested autnorization for enking a limited rearrangeant of fuel asse211es in Com X.

You have re;orted that en October 30, 1972, while mroving the upcer core barrel, the Pael assedly in com location D-9 was dansad.

Althou;;1 s@ sequent inspecticn detemined that the danage was =inor, you prtpcae to aplace the danaged fuel asse21y with the Pal assently frcm con locaticn K-5 You also propese to install a new fuel assedly in the vacated cors location K-5 All fuel asse211es involved in this li":ited rearrmaemnt of Com X are sM1u in all respects, have zircaloy clad fuel rods, except that the fuel rods in the new asse217 am unirmdiated and paprescri::ed whemas the fuel rods in the other two asse:Dll's that have already experienced sore bumup in Core X am inprepressuidzed.

We have reviewed.the infomatico you have provided on your evaluation of the safety emsiderations associated with the defimd core rearrange-

nent. Your nuclear reanalysis has confirmed that the proposed chanw, e

would have a negligible effect on the nuclear characteristics deteded previously by Yankee in the Core X analysis; hence, the margins of safety and the consequences of accidents deterr:ined paviously for operatirg the reactor in the Com X c<2ifiguraticn re nin inchanged.

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2-Yankee Atomic Elcctric Company

'We have concluded that the p:cposed cnang does not involve sintificant hmW.s considerations not described or inplicit in tne Final Safety

. Analysis ?.eport, and that the health and safety of the public will not be endangered. Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, Cnanige No.107 is hemby authorized.

Since mly,

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Donald J. Skovholt Assistant Director for Operatine; Reacters Dimetorate of Licensing DISTRIBUI'ICN Docket File AEC PDR RP Pend Mg File Branch Peading File J. R. Buchanan, CE~u T. W. I.augilin, DTIE, CPOO R. DeYcur.g, L:PW?.

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