ML19345A270
| ML19345A270 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/15/1972 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Minnick L YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011180422 | |
| Download: ML19345A270 (2) | |
Text
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k NOV 151972
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s Docket No. 50-29 a
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t Yankee Atomic Electric Coc:pany ATIih Pr. L. E. Minnick Vice President i
20 Turnpike Road Westboro, Massachusetts 01581 Change No. 104 License No. DPR-3 Gentlemen:
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E By letter dated November 7,1972 (superseding your letter of October 17, T
1972), you requested authorization of a change in the Technical Specifi-K cations appended to License No. DPR-3 for the Yankee reactor. S e pro-posed change would reinstate the initial Core X control rod withdrawal y
program that was included in the Technical Specifications before the e 7 occurrence of control md difficulties.
] pfa To meet the specified shutdown margin with one control zod inoperable, d
you have operated the reactor with the nore restrictive control rod in-g sertion limits that are specified presently. At this time, the reactor is shut down for replacing 22 control rods. Be other two control mds
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$si have already been replaced during outage in the spring of 1972 for re-fueling with Core X.
.R; ggt he installation of new control rods and deronstration of their opera-bility during preoperational testing will restore the ability to meet 8E the specified shutdown nargin without the present added restrictions SE on the control rod insertion limits. Be control rod withdrawal pro-Et gram that you request to be reinstated has previously been evaluated and found acceptable in cornection with our authorizing reactor oper-k:;,
ation with Core X in Change No. 97. Eerefore, pmviously detemined Db margins and consequences of accidents remain unchanged by the change 3$
in the control rod insertion limits that you propose for operating the gg Yankee reactor.
WW We have also reviewed your pmposed control rod surveillnnce program J(p including preoperational testing. Wis pmgram is designed to establish confidence in the long-tem ability of the new control rads to perfom f
the intended function when needed. We have concluded that the proposed surveillance program is acceptable.
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We have concluded that the proposed change cbes not involve _ significant hazards considerations not described or implicit in the Final Hazards i
Surmary Report and that the health and safety of the public will not
-1 be endangend by operation of the reactor in the ma:iner proposed.
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Accordingly, pursuant to Secticn 50.59 of 10 CFR Part 50, the control l
rod withdrawal protywh is changed as indicated in the attached Pigum j~~
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Ibnald J. Skovholt i
Assistant Dimetor for Operating Peactors
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Directorate of Licensing 5
. Enclosum:
Figum 103-5 i.
Distribution Docket File AEC PDR Local PDR RP Reading File Branch Reading File J. R. Buchanan, OKIL T. W. Lau@lin, DI'IE, ORDO W3 TM)
R. DeYoung, L:FER D. J. Skovholt, L:OR i
i R. L. Tedesco, L:CS ACPS (16 cys)
B0 (3 cys) s Kaufkan, OGC d
R. J. Sheenel, L:0R-1 T. J. Carter, L:0R jl-N. Dube, L:0PS
.I M. Jinks, DPA (4 cys)
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