Re: Research reactor surveys

[loesch@cedr.lbl.gov (Robert M. Loesch)]

I sounds to me that the Regional NRC inspector was either not that
knowledgeable or the University over (mis) interpreted the comment 
or both.  As an ex-Region I research reactor inspector, surveying of
items that have been exposed to a neutron flux is appropriate if one
is removing them from a restricted area to an unrestricted area for 
unconditional release.  However, since you were not specific as to the 
inspector's actual comment, it is difficult to evaluate the
appropriateness of actions being taken.

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>I would like to get some opinions on a subject that recently came up 
>at a reactor operator training session.
>
>Idaho State has an AGN-201 reactor in its engineering school that is 
>rated at a whole 5W (5*10^8 n/cm^2-s).  Because of a comment made by 
>the NRC after a recent inspection we are know surveying everything 
>that has been exposed to a nuetron flux from the reactor.
>
>While I don't have a problem doing this, I feel it's an over reaction 
>in many cases.  For example some common materials that are put into 
>the experimental beam ports are: 1) polyethalene, which never 
>activates to levels that can even be measured  2) Wood spacers, same 
>as above.  3) Lead shielding, has such a low cross-section to thermal 
>neutrons that a much higher flux is required to have appreciable 
>activity.
>
>
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* Robert M. Loesch                                   *
* DOELAP Administrator     U.S. Department of Energy *
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