We had a situation recently where the containment tritium levels spiked after 
we stopped a source of secondary side containment leakage. It was determined 
that the secondary side leakage was enhancing removal of tritium from the 
containment atmosphere (such as through more frequent sump pump downs and 
containment depressurizations). If you can't find a tritium source, perhaps 
something has changed to decrease the removal of tritium from the atmosphere.

Our tritium never reached the action levels to require bioassay so I don't have 
any direct experience to share with you on that aspect. Perhaps you could 
estimate CEDE based on air sampling and then assign dose based on the 
urinalysis. This is how we handle differences between the electronic dosimeter 
dose and the OSL/TLD dose. We communicate that the ED dose is just an estimate, 
and we report the actual dose after the dosimetry is processed.

My feeling is that the urine results will give you a better/more defensible 
estimate of CEDE than the air sampling. Hopefully, the air sample results and 
urine sampling results will agree pretty well. If you can do the urinalysis 
in-house, it shouldn't take too long to get the final CEDE numbers. With air 
samples, there is always the question of how well the air sample represents the 
actual intake activity.

If you know anybody who works at a CANDU reactor, they do extensive tritium 
sampling and should be able to give you good advice. I have a couple of 
contacts which I can share with you if you need them.

-Steve

Stephen J Holmes, CHP, PE
Sr. Plant Health Physicist, CENG-RE Ginna NPP
[email protected]
585-771-3577

From: [email protected] [mailto:[email protected]] On Behalf Of 
Rolph, James Thomas Jr
Sent: Monday, June 03, 2013 4:25 PM
To: [email protected]
Subject: Powernet: Tritium Bioassay Practices

We have encountered an unusual situation for us here at Sequoyah. We are having 
some ice condenser issues inside containment requiring frequent containment 
entries where we typically entered containment once or twice a month while 
online.  We are experiencing increased temperatures and humidity levels inside 
containment, and along with this increased tritium levels.  Our containment 
tritium airborne activity has been 35% to 105% of a DAC, whereas we typically 
are < 5% of a DAC.  As a result, we realize that we may reach the 10 mrem CEDE 
threshold on many of the individuals involved in the work being conducting 
inside containment and that we need to assess the workers internal dose as a 
result.  We are requesting and obtaining urine samples for bioassay analysis, 
typically 24 hours after an entry so we will have the data available.  Acute 
intake situations are what we typically experience from airborne not continuous 
exposures. Besides Regulatory Guide 8.9 (based on NUREG CR-4884) do you have 
any other suggestions, guidance, or recommendations on using DAC-hrs and time 
versus urinalysis data for dose assessment based on your experience?

If you monitor and report CEDE, what CEDE do you use the one based on air 
sample results, or wait until you have the bioassay results, or replace the air 
sample one with the bioassay one after you have the results? We are concerned 
that if we report the one based on air sampling and then adjust that number 
after we complete the dose assessment based on urinalysis that this will look 
funky to individuals who look at trending results.

Any tips or suggestions on addressing this situation would be appreciated.  
Thoughts on possible sources of increased tritium levels without a noticeable 
increase of RCS leakage may also be of interest.

Best regards,

Jim Rolph, CHP
RP Technical Support Superintendent
Tennessee Valley Authority
Sequoyah Nuclear Power Plant
SB2A
PO Box 2000
Soddy Daisy, TN 37384-2000
(423) 843-8115 - Work
(423) 593-0247 - Cell

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