ML20137G437

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Forwards,For Comment, Description of Nuclear Flux Controller 4,Nuclear Reactor Flux Regulator & Multirange Picoammeter Channel. Equipment Being Purchased to Modernize Control Circuitry
ML20137G437
Person / Time
Site: Dow Chemical Company, 05000000
Issue date: 04/30/1971
From: Hoyle H
DOW CHEMICAL CO.
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20136D183 List: ... further results
References
FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 2155, NUDOCS 8508270299
Download: ML20137G437 (2)


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g THE DOW CMEMICAL COMPANY MIDLAN D. MICHIG AN 48840 April 30,1971 1

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Division of Reactor Licensing D_

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ffte M _P'N Gentlemen:

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With reference to our communicatiois of February 9,1971, Docket 50-264-R108, I would like to send you the enclosed copy of a descrip-tion of the Nuclear Reactor Flux Regulator and Multirange Pico-i

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ammeter Channel which we are purchasing from the manufacturer of our Dow TRIGA Reactor to modernize the control circuitry.

I We are assured by Gulf General Atomics that the design and circuits k

have been incorporated as standard equipment in the more modern consoles installed since 1967 and have proven themselves very reliable and requiring but littic maintenance. The new c1cetronics is to replace older tube-type components presently performing the same functions, so that no change in the specifications are intended.

The control rod to be employed for the flux controller has a nominal reactivity valye of $3. in our reactor. The enclosed specifications for the flux controller NFC-3 list a maximum control rod velocity of 0.43 in/sec. for a $4. rod. The latter resulting in a maximum reactivity insertion rate of $.16/sec, which is equivalent to.11*/o sik/k/sec., a value falling within our Technical Specifications.

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We are planning to install the new equipment sometime after May 25, at which time we shall carry out detailed testing of the new circuitry before using it on a routine basis.

We would appreciate hearing froin you any comments you wish to make so that we can proceed with this modernization as soon as the equipment is delivered.

Very truly yours, Lt4S C

Dr. Harold Hoyle Chairman Radiation Safety Committee 1

1701 Building YY rir enc 1.

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