ML19343B130
| ML19343B130 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/25/1962 |
| From: | Gifford F Advisory Committee on Reactor Safeguards |
| To: | Seaborg G Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19343B129 | List: |
| References | |
| NUDOCS 8012090234 | |
| Download: ML19343B130 (2) | |
Text
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i ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATED ATOMIC ENERGY COMMISSION WASHINCION 25, D..C.
August 25, 1962 Honorable Glenn T. Seaborg Chairman U. S. Atomic Energy Commission Washington, D. C.
SUBJECT:
REPORT ON YANKEE ATOMIC ELECTRIC COMPANY
Dear Dr. Seaborg:
At its forty-third meeting on August 23-25, 1962, at Idaho Falls, Idaho, the Advisory Co=mittee on Reactor Safeguards considered the proposal of this licensee to increase the present reactor power level of 485 Mw(t) to 540 Mw(t) and to eliminate the presentDrequirement for temperature coefficient measurements at 2000 operating hour levels. Discussions were presented by representative of the Yankee Atomic Electric Company and'the Westinghouse Electric. Company, concern-l ing' operational and plant changes to be introduced to permit the increase in, I
power. In addition, the Committee had the benefit of information contributed by the AEC staff. Data covering the preposed changes are recorded in the documents listed.
This power plant has operated successfully throughout the life of Core I.
The experience obtained during this period has indicated the possibility of operation l
at a higher power level with Core II.
The major operational and plant changes proposed include: (a) an additional safety injection pump, (b) automatic low pressure activation of the third charging pump, (c) chang'ed scram requirements, (d) elimination of automatic rod withdrawal, and (e) a limitation of amount of rod l
withdrawal at power during any eight-hour period.
Power coef ficients and moderator temperature coefficients have been determined at 2000 equivalent full power hour intervals during Core I life to determine the possible effect of plutonium build-up. These tests were carried on to substant-iate previous theoretical calculations which had indicated that the effect of plutonium build-up would not be significant. Data developed during Core I life l
have shown that there has been no significant effect. The licensee proposes now to make these determinations during initial start-up after fuel changes, and during' scheduled generator load changes and plant shut-down only.
l 8012090 S k I