ML20006F028

Details Responses in 900124 Telcon W/B Carter Re Aspects of Procedure, Experiments for Reactor Power Level Determination Sent to NRC w/891212 Ltr

ML20006F028
Person / Time
Site:	05000199
Issue date:	02/13/1990
From:	Berlin R MANKATO STATE UNIV., MANKATO, MN
To:	Michaels T Office of Nuclear Reactor Regulation
References
NUDOCS 9002270095
Download: ML20006F028 (1)

Text

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i n asaan 1  : MANHATTAN COLLEGE PARKWAY MECHANICAL ENGINEERING DEPARTMENT RIVERDALE. NEW YORK 10471 (212) 920-0146 g

gb/U y J t February _lk1990.

Theodore Michaels

- Project Manager

Standardization and Non Power Reactor Project Directorate

' Division of Reactor Projects Ill; IV, V and Special Projects - ,

4 LOfflee of Nuclear. Reactor Regulations

,U.S. Nuclear _ Regulatory Commission Washington, .DC; 20555 J '

SUBJECT:

Response to Questions Raised by Bob Carter

=

Dear Ted:

m- -f This letter will confirm my responses,in a telephone conversation with Bob Carter on January 24,1990, to verbal questions that had been raised relative to certain aspects of; Manhattan College procedure " Experiments for Reactor Power Level Determination" sent to you in our letter of. December 12,1989 _ The responses were:

• Method 11 described in the " Experiment" will be the primary approach used to determine

- the reactor' power level. We will revise the physics in method I and use it'as a-backup-procedure.

f

• The core parameters will be experimentally redetermined when the new core is loaded into the reactor,

~

• inumcthod ll.) the ratios -

0.695 and k- 1.20f were extracted from 'the data

]c'ollected during the initial," Critical ~and Subcritical Reactor Experiments" run af tcr ~

installation'of the reactor in~ the 1960's. Thes_c values will be' properly redetermined -

.during the experiments to be run-upon installation of the new core. -

-.* The value 3.54 x 10'" used in equation 2 had been empirically arrived at. ,This value will now be independently determined from the parameters of the fission process for use in the calculation of reactor power.

, i Sincerely, a y 33 J ' Robert E. Berlin-

[' - Reactor Administrator l 0V 0

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