ML19345A381
| ML19345A381 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/04/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Minnick L YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML19345A382 | List: |
| References | |
| NUDOCS 8011210228 | |
| Download: ML19345A381 (1) | |
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Distribution:
W. Dooly, DR 4
R. Engelken, CO (2)
H. Shapar, OGC N. Dube, DRL (5)
Docket No. 50-29 J. Buchanan, ORNL H. McAlduff, OR00 T. Laughlin, DTlE D. Skovholt Yankee Atomic Electric Company R. Vollmer ATTN:
Mr. L. E. Minnick R. DeYoung Vice President R. Boyd 2.,cket File 441 Stuart Street ACRS (3)
DR Reading Boston, Massachusetts 02116 R. S &emel DRL Reading Change No. 95 License No. rFR-j. Burger ORB '. Reading Gentlemen:
Document Room This refers to your request dated July 15, 1970, and supplements dated July 22, and October 9, 23 and 29, 1970, for AEC authorization of Proposed Change No. 95 to the Technical Specifications of Facility License No. DPR-3 for the Yankee reactor. The proposed change would allow modifications to provide a capability for recirculation of primary coolant, necessary for long-term removal of core fission product decay heat in the event of a loss-of-coolant accident.
We have reviewed your Proposed Change No. 95 and supplements, which include:
your system analysis and evaluation of safety considerations; the arrangement of components in the proposed recirculation system; the codes which you will i
use in the design, fabrication and testing to assure the installation of l
reliable, high quality components; and your proposed pre-operational tests and surveillance requirements.
We have concluded that the proposed installation will provide a significant I
improvement in the capability for long-term core coolin2 in the event of a loes-of-coolant accident, We have also concluded that the proposed change does not present significant l
hazards considerations not described or implicit in the safety analysis report and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor in the manner proposed.
Accordingly, pursuant to Section 50.59,10 CFR 50, Proposed Change No. 95 is hereby suthorized.
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