ML20235V141

Submits Results of Sampling of Processed Water Storage Tank 2 on 870219-25.Sample Split Into Three factors:1 Gallon for reserve,1 Liter Analyzed by Util Chemistry & Four 1 Liter Samples Sent to Radiological & Environ Sciences Lab

ML20235V141
Person / Time
Site:	Three Mile Island
Issue date:	07/21/1987
From:	Dan Collins Office of Nuclear Reactor Regulation
To:	Travers W Office of Nuclear Reactor Regulation
Shared Package
ML20235V140	List: IA-87-638, Submits Results of Sampling of Processed Water Storage Tank 2 on 870219-25.Sample Split Into Three factors:1 Gallon for reserve,1 Liter Analyzed by Util Chemistry & Four 1 Liter Samples Sent to Radiological & Environ Sciences Lab ML20235V138 ML20235V141
References
FOIA-87-638 NUDOCS 8710150005
Download: ML20235V141 (2)

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NUCLEAR REGULATORY COMMisslON

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%  ! July 21, 1987 MEMORANDUM FOR: W. D. Travers, Director TMI-2 Cleanup Project Directorate FROM: D. J. Collins, Radiation Specialist i TMI-2 Project Section

SUBJECT:

TESTING 0F PROCESSED WATER At your request, I observed the sampling of Processed Water Storage Tank #2 (PWST2) on February 19 - 25, 1987. PWST2 was placed on recirculation on February 19, and a sample was drawn in my presence on February 24, 1987. The' sample was split into three factors: one gallon retained for reserve; one liter analyzed by GPUN Chemistry under sample number 87-02569, and four one-liter samples prepared for the NRC contracted laboratory, Radiological and Environmental Sciences Laboratory (RESL) of the U.S. Department of Energy's Idaho Operations Office,  ;

Scoville, Idaho. The four one-liter samples were prepared as follows: 1) 2% HCI and wood pulp added; 2) KI (1 gram, bisulfite, pH adjusted to 7 with NH40H; 3) pH adjusted to 8 with NH40H; 4) untreated. These samples were packaged for shipment to RESL and sent on February 25, 1987. RESL recorded the samples as 14185 A, B, C, and D when they received them on March 3,1987. This tank contains approximately 430,000 gallons and has a useful capacity of 456,000 gallons.

RESL analyzed the samples and provided the listed results through the laboratory computer to Region I. A written report will be provided by RESL in the near future. Not yet provided are results for I-129.

The results shown are microcurie per milliliter of sample. The results are reported at 1 standard deviation, the first number in parentheses is the systematic error, the second number represents the total error. A negative oumber is considered to be not present, as indicated with C-14 and U-235.

Isotope Concentration Isotope Concentration _

(uCi/nd ) (uCi/ml)

Co-60 3.2 (0.5;0.5) E-7 Cs-137 8.0 (0.2;0.3) E-6 Sr-90 2.55(0.07;0.07)E-5 Sb-125 6 (2;2) E-7 C-14 -2 (3;3) E-7 Ni-63 2.0 (0.2;0.3) E-7 U-233/234 6(3;3 E-10 U-235 -1(1.5;1.5)E-10 U-238 2 (2;2 E-10 Pu-238 1.2 (0.09;0.09) E-9 Pu-239/240 1.2 (0.3;0.3) E-9 Am-241 2.4 (0.3;0.3) E-9 Cm-243/244 1 (8;8) E-11 Cm-242 4 (8;8) E-11 Tc-99 1.6(0.8;0.8)E-8 871015000S 871013 PDR FOIA SKOLNICB7-638 PDR y

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If ' # W. D. Travers -July'21, 1987' GPUN assigned sample number 87-02569 to their portion of the above sample.

Convention at this' plant is that the symbol < indicates a sample at or below the 10wer limit of detectability for the isoto'pe being analyzed. The GPUN Chemistry analyses indicates the following radioactivity concentrations in the PWST2:

Isotope Concentration Isotope Concentration (uCi/ml); ' (uCi/ml) 7.0 E-6 Co-50 2.8 E-7

~

Cs-137-Cs-134 1.5 E-7 Ce-144 <7.6 E-7 Sr-90 5,8 E-5 0.17 C0-58 <4.6 E-8 Ag-110m <6.5 E-8 Ru-106/Rh-106 <7.8 E-7.

Westinghouse taburatory PWST2 sample Decem'.ir 23, 1985, as reported to NRC in GPUH letter dated February 3, 1987 (4410-87-L-0018), indicates these results. The results are reported at two standard deviations, the number in parentheses is the error band.

Isotope Concentration '

Isotope Concentration (uC1/ml) ~(uCi/ml)

Co-60 1.8 E-7 (5.2E-8) Ag-110m <1.1 E-7' Sb-125- 3.4 E-7 (1.1 E-7) Ru-106 <5.2 E-7 Cs-134 2.1 E-7 (4.4 E-8 Ce-144 <2.8 E-7 Cs-137 4.8 E-6 (9.9 E-8 I-129 <2.8 E-7 Sr-90 2.1 E-5 (2.9 E-7 Ni-63 <5.9 E-7 C- M 3.0 E-4 (1.1 E-5) Tc-99 <2.5 E-7 U-234 <1.5 E-8 U-235 <8.7 E-9 U-238 <1.4 E-8 Pu-238 <1.1 E-8 Pu-239/240 <1.2 E-8 Am-241 <1.1 E-8 Am-242 <6.1 E-8 Cm-243/244, <8.6 E-9 Again, a symbol < indicates that an isotope was searched for and not found. From the isotope listing, I surmise that this sample was examined for compliance with the radioactive waste disposal regulations of 10 CFR 61 and the reportin9.

requirements of 10 CFR 20.311.

In order for GPUN to meet the '" achievable" values given in Table 2.2 of the PEIS, Supplement 2, PWST2 would need to be reprocessed to remove Cs-137 and Sr-90. The other isotopes listed are already at or below the " achievable" values. .

The values given by the RESL and GPUN for the February 25, 1987 sample indicate that Co-60 and Sb-125 could be the same value, in that the error band given by RESL includes the GPUN results. For Cs-137, the results are within 14% of each other. For Sr-90 the results are within a factor of 2 of one another.

/ y' I David J. Col in's Radiation S ecialist THI-2 Project Section