ML103230097

Oak Ridge Institute for Science and Education (Orise) Letter Report for Four Soil Samples from the University of Michigan Ford Reactor (IR 05000002/2009003)

ML103230097
Person / Time
Site:	University of Michigan
Issue date:	11/17/2010
From:	Condra D Oak Ridge Institute for Science & Education
To:	Snell W NRC/RGN-III
References
DE-AC05-060R23100 IR-09-003
Download: ML103230097 (6)

Text

November 17,2010 Mr. Willlam Snell U. S. Nuclear Regulatory Commission Regon I11 2443 Warrenville Road Lisle, IL 60532-4351 ORISE CONTRACT N O . DE-AC05-060R23100

SUBJECT:

LETTER REPORT FOR ANALYTICAL RESULTS FOR FOUR SOIL SAMPLES FROM T H E UNIVERSITY OF MICHIGAN FORD REACTOR, A N N ARBOR, MICHIGAN

[INSPECTION REPORT NOS. 05000002/2009003]

(RFTA NO. 10-OOl), DCN: 2026-LR-01-0

Dear Mr. Snell:

The Oak Ridge Institute for Science and Education (ORISE) received four soil samples on September 22,2010 from the Ford Reactor at the University of Michgan in Ann Arbor, Michigan. The samples were analyzed according to the 303 form supplied with the samples. The sample identification numbers are presented in Table 1. The gamma spectroscopy data are in Table 2. The gross alpha and gross beta data are in Table 3 . The tritium, carbon-14, and iron-55 data are in Table 4. The pertinent procedure references are included with the data tables.

ORISE's Quality Control (QC) requirements were met for these analyses. The Q C files are available for your review upon request. X deviation to procedure APl6-Determination of Iron-55 in Soil and Other Solid Matrices-was required. The deviation was documented in the task file and a copy of the deviation is included in the letter report.

My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:WI:jc Enclosures C: T. Carter, NRC/FSME/DWMEP T-8F5 T. Patterson, NRC/FSME/TWFN 8D42 File 2026 Electronic: S. Roberts, ORISE T. Vitkus, ORISE 1 Distribution atmroval and concurrence : I Initials Technical Review Quality Review RECEIVED NOV 1 9 2010

\'ace: 865231.3242 1;as: 865.231.3238 E<-m~ilUalc.CotidraOorau.org

'.O. Box 117 I Oak Ridge, TN 37831 I www.orise.orau.gov

hlo&fications to procedure AP16:

AP16, Revision 1: DETERMINATION OF IRON-55 IN SOIL AND OTHER SOLID MATRICES

1) Replace step 4.6.5 with Add 3 drops of 4900 HF to Qssolve the precipitate, heat in a water bath briefly if needed.

2) Replace step 4.6.6 with Carefully transfer the solution to a plastic scinullation vial with a transfer pipette. Rmse the centrifuge tube with 1mL of DI water and transfer to the scintdlation vial and add 12 mL o f scintdlation cocktail. Mix the solution with vigorous shaking.

3) Replace steps 5.1.5 and 5.2.6 as in amendment 1 above.

4) Replace steps 5.1.6 and 5.2.7 as in amendment 2 above.

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION INFORMATION FORD REACTOR, UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN ORISE N R C Region I11 Collection Collection Date Sample ID Sample ID Time 2026S0001 UM-01 9/15/10 NDP~

2026S0002 UM-02 9/15/10 NDP 2026S0003 UM-03 9/16/10 NDP 2026S0004 UM-04 9/16/10 NDP Iord Reactor - University of Michigan 2026-LR-01-U

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N SOIL SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 17 FORD REACTOR, UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN ORISE NRC Region I11 Radionuclide Concentrations, TPUs, and MDCS" (pCi/g)

Sample ID Sample I D Mn-54 CO-60 Ag-108m Ag-llOm Ba-133 2026S0001 UM-01 -0.03 5 0.03b , 0.05 0.02 -t 0.04 , 0.06 0.24 -t 0.03 , 0.03 0.01 2 0.02 , 0.05 -0.17' -t 0.05 , 0.06 2026S0002 UM-02 0.01 +_ 0.04 , 0.06 0.20 & 0.03 , 0.04 2.37 -t 0.16 , 0.05 -0.04 -t 0.03 , 0.07 -0.51 -t 0.07 , 0.12 2026S0003 UM-03 -0.02 +_ 0.03 , 0.05 0.34 -t 0.03 , 0.03 2.06 k 0.15 , 0.04 -0.15 -t 0.04 , 0.06 -0.30 -t 0.05 , 0.08 2026S0004 UM-04 -0.02 ? 0.03 , 0.04 -0.01 -t 0.03 , 0.05 0.10 -t 0.01 , 0.02 -0.01 2 0.02 , 0.03 -0.06 & 0.03 , 0.04 ORISE N R C Region I11 Radionuclide Concentrations, TPUs, a n d M D C s " (pCi/g)

Sample ID Sample ID cs-134 cs-137 Eu-152 Eu-154 2026S0001 UM-0 1 0.04 ? 0.03 , 0.06 0.02 k 0.01 , 0.03 -0.02 k 0.04 , 0.07 -0.01 +_ 0.03 , 0.05 2026S0002 UM-02 O.OOd ? 0.05 , 0.07 0.04 ? 0.02 , 0.05 0.04 k 0.07 , 0.12 0.00 ? 0.05 , 0.08 2026S0003 UM-03 0.01 +_ 0.03 , 0.06 0.16 k 0.02 , 0.03 0.02 k 0.05 , 0.09 0.03 k 0.03 , 0.06 2026S0004 UM-04 0.01 ? 0.02 , 0.04 0.02 k 0.01 , 0.03 -0.01 k 0.03 , 0.05 0.00 -t 0.02 , 0.04 bl.liiccrtaintics represent the 95% confidence level, based o n total propagated uncertainties.

'Statistically negative concentrations arc due to the force fit routine in ( h b c r r a ' s , \ p a (;anima Software.

"Zero values arc due t o rounding o r sample and background counts being equal.

Iwrd Kcactor - University of Michigan 2026-1 k01-0

TABLE 3 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA I N SOIL SAMPLES BY GAS FLOW PROPORTIONAL, COUNTING AP1, REVISION 16; CP3, REVISION 2 FORD REACTOR, UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN

~~~~~ ~

RadionuclideConcentrations,TPUs, and ORISE NRC Region I11 Sample ID MDCS" (pCi/g)

Sample ID Gross Abha Gross Beta 2026S0001 UM-01 2.2 F 2.7b , 4.6 17.9 F 4.6 , 6.4 2026S0002 UM-02 3.6 f 2.7 , 4.2 18.5 f 4.4 , 5.9 2026S0003 UM-03 1.5 k 2.5 , 4.4 23.6 k 4.7 , 6.0 2026S0004 UM-04 1.4 k 2.4 . 4.2 25.7 5 4.9 . 6.0 "I'hc MLICs arc after thc c o m a .

"Uncertaintics represent the 95" (1 confidence level, based on total propagated uncertaintica Ford Reactor - University o f Michigan L026-LK-OI -\I

TABLE 4 CONCENTRATIONS OF LOW ENERGY BETA RADIONUCLIDES IN SOIL SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP6, REVISION 18; AP16, REVISION 1";CP4, REVISION 3 FORD REACTOR, UNIVERSITY OF MICHIGAN ANN ARBOR, MICHIGAN ORISE NRC Region I11 Radionuclide Concentrations, TPUs, and MDCsb (pCi/g)

Sample ID Sample ID C-14 Fe-55 H-3 2026S0001 UM-01 2.2 k 1.3' , 2.2 3.1 ? 2.2 , 3.7 -0.7 k 2.1 , 3.6 2026S0002 UM-02 13.7 2 1.6 , 1.8 3.4 k 2.3 , 3.7 -1.2 _+ 1.7 , 3.0 2026S0003 UM-03 0.3 2 1.4 , 2.4 3.1 ? 2.3 , 3.7 -0.7 _+ 2.3 , 4.0 2026S0004 UM-04 1.6 ? 1.3 , 2.2 2.0 ? 2.1 , 3.5 -2.0 2 2.1 , 3.6 Ford Reactor - U n l v e r s q o f hlichlgan 2026-LR-01-0