Re: Release Concentrations

[Peter Fundarek <p.fundarek@utoronto.ca>]

On Thu, 6 Jul 1995 12:15:22 -0400 Albert Lee Vest wrote:


> I hope they continue to *clearly* communicate this 
intended use for "generic
> MRC's".  Some of the regulatory guides I've been exposed 
to (which contain
> numbers *suggested* for use) have such statements in the 
fine print, where
> nobody seems to notice them!  The suggested numbers then 
become, de facto,
> regulatory limits.


These are going to become regulatory limits as soon as the 
consultation period for the document is complete and all 
comments have been reviewed.

> The MPC's you presented were only for short-lived, "delay 
and decay"
> nuclides.  Are there also MPC's for EVERY nuclide one 
might use - just as
> there are ALI's for every imaginable nuclide in Appendix B 
of USNRC's 10 CFR
> Part 20?

Yes, there are MRC values for most isotopes used in 
biomedical research as well as some for uranium and other 
such animals.  MRC values have been calculated for each 
isotope in each of three release scenarios - gaseous 
discharge to the atmosphere, liquid effluent to the sanitary 
sewer and solid waste to incinerator and landfill.

The document also describes the technique used to derive the 
values but does not give too much in the way of specific 
values used (e.g. Dose Conversion Factors)

A copy of this document may be had by contact the Atomic 
Energy Control Board, Office of Public Information, Ottawa, 
Ontario 1-800-668-5284.  Ask for  a copy of C-123

*************************************
Regards,
Peter J. Fundarek
University of Toronto
email:  p.fundarek@utoronto.ca
phone:  (416) 978-2374
fax:  (416) 971-1384
*************************************