ML20116G605

Intervenor Exhibit I-GANE-68,consisting of Re Radiological Analyses of Samples Collected from Clayton Water Treatment Plant in Atlanta,Ga

ML20116G605
Person / Time
Site:	Neely Research Reactor
Issue date:	06/26/1996
From:	Adams W OAK RIDGE ASSOCIATED UNIVERSITIES
To:
References
REN-I-GANE-068, REN-I-GANE-68, NUDOCS 9608080212
Download: ML20116G605 (3)

Text

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u u ,8 P/2:37 Q'1M N ,kWk Mr. Craig Basset y cc(>U g c8 uf U. S. Nuclear Regulatory Commission )j Region II 101 Marietta Street, Suite 2900 drO T QS1Ewir Q

Atlanta, GA 30323 SUBJECTr RADIOLOGICAL ANALYSES OF SAMPLES COLLECTED FROM THE CLAY' ION WATER TREATMENT PLANT, ATLANTA, GEORGIA (RPTA NO. 95-18)

Dear Mr. Basset:

The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed a site visit and collected four sludge samples from the Clayton Water Treatment Plant located in Atlanta, Georgia on March 13, 1995. Per the request of the U. S. Nuclear Regulatory Commission, the two liquid sludge samples (raw sludge and digested sludge) were filtered and the dissolved and suspended solids samples were analyzed C separately. Two solid. samples (feed cake and ash) were also collected. ESSAP performed the requested gamma sptirstry and Sr-90 analyses on all the samples and performed gross alpha and gross beta analyses on the liquid portions of the sludge samples. 'Ihe results of the radiological analyses of the samples are presented in Table 1.

If you have any questions or comments, please contat me at (615) 576-0065 or William L.

(Jack) Beck at (615) 576-5031.

Sincerely, YC =

Wade C. Adams Health Physicist / Project Leader Environmental Survey and Site Assessment Program WCA:daa Attachments cc: R. Uleck, NRC/NMSSSWFN/7F27 D. Tiktinsky, NRC/NMSSNWFN/8A23 PMDA, NRC/NMSS/TWFN/8A33 O W. Beck, ORISE/ESSAP E. Abelquist, ORISE/ESSAP File /288 e o. Box 1n. oat accE TENNESSEE 37931-0117 Ma va ww w o a e+ A mia u.~m*, w s. u s % or e- , b NUCLEAR REGULATORY COMMISSION

-- - Docket No. for /6 o-Od EXHIBIT NO. A 9608080212 960626 in me inaner d /h MU D Staff O Applicant t3fntervenor O other FDR ADOCK 05000160 G PDR t R4dentfied O Received gnje Reporter (AlG c)

Date (t /2.ls /9 6 Witness AstJL $ a

TA. 1 .

RADIONUCIJDE CONCENRNITONS IN SLUDGE SAMPLES PROM CLAYTON WATER TREATMENT PLANT ATLANTA, GEORGIA Radionsclide Concentrations

• * ^*

[ ", Raw Sludge (pCi/L) Digested Sludge (pC1/L) yg yh Dissolved Suspended

• Dissolved Suspended" Solid Solid

\k ' Gross Alpha 5.32 i 1.336 -

12.69 i 2.93 - - -

gT S 13.36 i 1.57 70.31 3.77 - - --

Gross Beta --

l Be.7 <55.3 < 16.2 < %.9 125.0 1 23.9 5.9 i 0.6 10.9 i 1.1 7

\ Ga-67 <44.9 <10.8 < 99.1 < 22.6 2.4 i 0.2 5.9 i 0.6 Q g)k Sr-90 <3.7 < 2.0 <3.4 11.0 2.8 0.5 0.1 1.1 i 0.2 h ( s I I.131 8.6 i 6.0 <l.8 94.2 i 12.8 < 3.7 4.6 0.1 0.1 i 0.1 Cs-137 < 7.1 < 2.3 < 11.6 < 4.2 0.1 0.I < 0.1 Eu-155 <15.7 < 3.8 < 23.5 12.8 i 7.1 0.1 i 0.1 < 0.3 TI-201 53.2 i 8 5 < 2.9 < 25.7 37.8 i 4.1 8.0 i 0.2 18.1 i 0.4 Bi-214 61.5 i 19.2 7.8 i 11.9 < 30.3 141.8 i 15.5 < 0.2 0.6 i 0.2 Th-228 5.4 i 9.6 -2.3 i 5.7 11.0 i 16.0 148.1 i 8.4 0.7 i 0.1 1.2 i 0.2 Th-232 < 32. I' 2.8 i 14.5 < 51.2 143.6 i 20.6 1.1 0.3 2.0 i 0.4 U-235 < 9.6 5.5 i 2.6 <13.2 T .7 i 5.2 < 0.1 < 0.3 U-238 <152 <50 <209 214.5 i 83.6 0.5 1.2 < 3.9

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? *Except where noted by an asterick (*), the activity of the fiber was subtracted from the sample. The activity of G the filter was act subtracted for the U-235 concentration due to the minute quanity.

' Uncertainties represent the 95% confklence level, based only on counting statistics.

'A dash indicates that analysis was not performed.

_ _ _ _ _ __ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ ___________ _ _______ _-_____ -_ _______________ _ _______ _ _ ~

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I ATTACHMENT 2 RADIONUCLIDE CONCENTRATIONS IN SLUDGE SAMPLES FROM THE CLAYTON HATER TREATNENT PLANT ATLANTA, GEORE1A Radionuclide concentrations Feed Cake Ash Radionuclide/ (pC1/q) (pCf/g)

Analyses Raw Sludge (pCl/L) Digested Sludge {pti/L)

Dissolved Suspended

• Dissolved Suspended

• Solid Solid Gross Alpha 5.32 i 1.33* --

12.69 i 2.93 -- -- -

Gross Beta 13.36 i 1.57 -- 70.31 i 3.77 -- -- -

Be-7 <tLD' <LLD <tLD 125.0 t 23.9 5.9 1 0.6 10.9 f 1.1

<tLD <LLD <tLD <LLD 2.4 i 0.2 5.9 i 0.6 Sa-67 Sr-90 <LLD <LLD <LLD 11.0 1 2.8 0.5 i 0.1 1.1 1 0.2 8.6 i 6.e <tLD 94.2 i 12.8 <LLD 4.6 1 0.1 0.1

• 0.1 0 1-131 p' Cs-137 <tLD <LLD <LLD <LLD 0.1 i 0.1 <tLD Eu-155 <tLD <LLD <LLD 12.8 i 7.1 0.1 i 0.1 <LLD-T1-201 33.2 i 8.9 <LLD <LLD 37.8 i 4.1 8.0 i 0.2 18.1 i 0.4 Cp /4 61.5 i 19.2 7.8 i 11.9 <LLD 141.8 i 15.3 <LLD 0.6

• 0.2 81-214 4

Th-228 514 i 9.6 <tLD 11.0 1 16.0 148.1 t 8.4 0.7 1 0.1 1.2 i 0.2 Th-232 <lLD 2.8 i 14.5 <tLD 143.6 i 20.6 1.1 1 0.3 2.0 t 0.4 U-235 <LLD <LLD dLD <LLD <LLD <LLD U-238 <LLD <LLD <LLD 214.5 i 83.6 0.5 i_1.2 <LLD g

• The back9round activity of the filter was subtracted from the sample. '

%ncertainties represent the 95K confidence level, based only on counting statistics.

'A dash Indicates that analysis was not performed. *

• Less than the lower limit of detection (LLD).

m _ _ _ _ - - _ - _ - _ - _ _ _ _ _ - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - . - - _ _ _ - - _ - _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ . -----______-.-_-_-_______________J