ML19199A430

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Forwards Decay Heat Removal During Very Small Break LOCA for B&W 205 Fuel Assembly PWR, Prepared for TVA
ML19199A430
Person / Time
Site: Crane 
Issue date: 04/20/1979
From: Mckinley J
Advisory Committee on Reactor Safeguards
To:
Advisory Committee on Reactor Safeguards
Shared Package
ML19199A431 List:
References
TASK-TF, TASK-TMR NUDOCS 7905020155
Download: ML19199A430 (1)


Text

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fg UNITED STATES q

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g NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS j

WASHINGTON D. C. 20555 April 20,1979 b

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FILE (THREE MILE ISLAND UNIT 2) g SUB?ECT:

TECHNICAL REPORT BY C. MICHELSON l~

Attached is a technical report entitled " Decay Heat Removal r

During a Very Small Break LOCA for a B&W 205-Fuel-Assembly

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PWR" by C. Michelson.

Mr. Michelson prepared this report in

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early 1978 for his employer, TVA, who forwarded it to B&W r

for review and comment.

Copies of the report were not

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supplied to the ACRS office at that time.

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Mr. Michelson has assisted the ACRS on a number of occasions Il and was called upon to provide assistance in the evaluation I

of the Three Mile Island Unit 2 (TMI-2) accident.

In conjunction with this review, Mr. Michelson provided copies

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of his report to the ACRS on or about April 4,1979.

I Mr. Micholson hc said that the report is considered a document which may be given to anyone requesting it.

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f f'Y C. McKi nl ey,

ef Operations S'ipp t Branch cc:

R. Fraley

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M. Libarkin M. Gaske 41!ib hq 7905020155' f,,

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