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Release Limits for SR-90
- To: Dale.Seiller@fernald.gov, JGEORGE@LANL.gov, KNOELL@LANL.gov, mbayless@LANL.gov, RGMorgan@LANL.gov, RickRas@LANL.gov, Trinoskey1@llnl.gov, david.kent@ohio.doe.gov, PN9@ornl.gov, Jerry.Allen@pnl.gov, Kelly.Neal@pnl.gov, Lindsay_A_Nelsen@rl.gov, robert_j_bob_thomas@rl.gov, RADSAFE@romulus.ehs.uiuc.edu, buddy.crowder@SRS.gov, cbmitchell@tva.gov
- Subject: Release Limits for SR-90
- From: Dave Biela <BielaD@wv.doe.gov>
- Date: Fri, 04 Aug 2000 11:31:04 -0400
- Cc: crotzem@wv.doe.gov
I have a question about DOE sites interpretation of Appendix D of 10CFR835 "Surface Contamination Values"
West Valley was a former fuel reprocessing facility. We currently use the 5,000 dpm/100cm-2 Total (fixed + removable) limit from appendix D. What I am trying to find out from all the DOE facilities is:
1. Which (fixed + removable) limit do you use for beta and why?
2. If you are dealing with mixed fission products and use the 5000 limit, do you use the 1000 limit in any areas such as LABS where Sr-90 extraction is taking place or after ion exchange processes (even if it is a Cs removal process that leaves you with a remaining effluent which technically has a higher Sr-90 ratio after the ion exchange process) etc.
3. If you are dealing with mixed fission products and use the 1000 limit why?
4. What is your general interpretation of note #5 in the same appendix as it applies to Sr-90 in mixed fission products.
" This category of radio nuclides includes mixed fission products, including the Sr-90 which is present in them. It does not apply to Sr-90 which has been separated FROM the other fission products or mixtures where the Sr-90 has been enriched. "
I am definitely interested in all opinions.
Please respond to Dave Biela at:
bielad@wv.doe.gov
716-942-4423
Once again Thank you for all your support.
Dave B
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