ML19345A378
| ML19345A378 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/06/1967 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML19345A379 | List: |
| References | |
| NUDOCS 8011210213 | |
| Download: ML19345A378 (1) | |
Text
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Distribution:
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UNITED STATES Supplementalw'- -
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WASHINGTON D.C. 20545 Orig:
PENorian C. Hendersor JAN 6 1967 E. G. Case m nce norr m H. Shapar Docket No. 50-29 L. Kornblith (2)
N. Stoner (5)
P. M111spaugh G. Page D. Skovnit N. D. Mason W. F. Nischan Yankee Atomic Electric Company bec.:
H. J. McAlduff, ORO 441 Stuart Street E. Trecrael, IP Boston, Massachusetts 02116 R. Leith, OC W. B. Cottrell, ORNL Attention:
Mr. Roger J. Coe Change No. 78 Vice President Gentlemen:
This refers to your request dated December 30, 1966, for AEC authorization of Proposed Change No. 78 in the Technical Specifications of Facility License No. DPR-3 for the Yankee reactor pursuant to the provisions of 10 CFR 50.59. This change would parmit the boron concentration in an isolated primary system loop to be reduced to the main coolant concentration if the isolation valve and main coolant pump controls have been secured to preclude inadvertent operation.
We have reviewed the proposed change and have found that it dc,es not present significant hazards considerations not described or implicit in the hazards sununary report, and that there is reasonable assurance that the health and safety of the public will not be endangered. A copy of our related safety evaluation is enclosed.
l In view of the foregoing, the following sentence is hereby added to l
Section D.2.d.9 of the Technical Specifications of Facility License No.
DPR-3:
"Following isolation of a main coolant loop, when the loop isolation valve and main coolant pump cor.trols have been removed from service i
l and mechanically prevented from operation by lock and key, the boron I
concentration in the isolated loop may be reduced to that existing in l
the main coolant system at that time."
Sincerely yours, I
griginal Si-nd by pm A. verits i
Peter A. Morris, Diregtor Division of Reactor Licensing
Enclosure:
AEC Safety Evaluation z
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OGC DRL L
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