ML070940618

Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No.06-001)

ML070940618
Person / Time
Site:	Indian Point
Issue date:	01/04/2007
From:	Condra D Oak Ridge Institute for Science & Education
To:	Kottan J Decommissioning Branch I
References
IR-06-007, RFTA 06-001
Download: ML070940618 (11)

Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 4,2007 Mr. Jim Kottan U S . Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406

SUBJECT:

FINAL L E T T E R REPORT F O R REQUESTED ANALYSES O F NINE WATER SAMPLES, SET NINE, FROM THE INDIAN P O I N T POWER STATION, BUCHANAN, N E W YORK

[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011

Dear Mr. Kottan:

The Oak k d g e Institute for Science and Education (ORISE) received set nine, which consisted of nine water samples received on August 15,2006 from the I n l a n Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous duection for h a n d h g samples from thls fachty. The final letter report was delayed untd problems associated with americium and plutonium in water were resolved by the Intercomparison Test Program conducted by the Ralological and Environmental Sciences Laboratory. Sample identification and collection data for the samples addressed in this report are presented in Table

1. Gamma spectroscopy, total rdostrontium, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), technetium-99, alpha spectroscopy, plutonium-241, and carbon-1 4 data are provided in Tables 2 through 8, respectively. The pertinent procedure references are provided in each specific table.

ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.

The water samples were processed using a deviation to the sample preparation procedure, SP3, Revision 4. The water samples were filtered through 0.45 micron and 0.1 micron filter papers.

An aliquot was removed for tritium and carbon-14 before acilfication. An aliquot was removed for alpha analysis and the pH was adjusted to approximately zero using concentrated nitric acid (HNO3) and a few drops of hydrofluoric acid (HF). A pH of zero and a few drops of HF should ensure that any plutonium that may be in the sample remains in solution. The remaining aliquot of each sample was adjusted to a pH of approximately 2 with concentrated HNO3.

Mr. Jim Kottan January 4,2006 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:ar Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 S. IOrk, ORISE M. Roberts, NRC Region I J. Whte, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Oualitv Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org

TABLE 1 ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 1697W0051" I Mw-50 6 7 ' E l

~ ~~

I 8/1/2006 I 11:30 1697M0003b MW-50 67' El 8/1/2006 11:30 1697W0052 MW-50 42' El 8/1/2006 11:15 I

~~

1697M0004 MW-50 42' El 1697W0053 I MW-49 25' El

- ~~

8/1/2006 I 9:50 1697W0055 MW-49 42' El 8/1/2006 9:35 1697M0007 MW-49 42' El 8/ 1/2006 9:35 1697W0056 MW-58 71' El 8/2/2006 9:31 1697M0008 MW-58 71' El 8/2/2006 9:31 1697W0057 MW-38 8/7/2006 13:23 1697M0009 MW-38 8/7/2006 13:23 1697W0058 Discharge Canal 8/7/2006 13:50 1697M0010 Discharge Canal 8/7/2006 13:50 1697W0059 MW-40 8/9/2006 10:35 1697M0011 MW-40 8/9/2006 10:35 "The W in the ORISE sample identification represents a water matrix.

"'l'he M in the ORISE sample identification represents the filtered fraction of the preceding water sample Indian Point Power Station projccts/l697/Data Tables/2007-01-04 Data Tables Set Nine

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I :ntrationsa(1 Ci/L)

Sample ID Sample ID co-58 CO-GO cs-134 cs-137 1697W0051 MW-50 67'El -0.3 k 3.1b 0.7 k 2.8 0.6 2 2.9 2.0 t 2.5 1697W0052 MW-50 42'El 1.3 k 2.3 2.1 k 2.1 -0.3 4 2.1 -2.6 5 4.5 1697W0053 MW-49 25' El -0.7 k 1.8 0.6 k 1.6 -0.1 k 1.7 0.2 k 1.6 1697W0054 MW-49 65'El 1.1 4 2.3 0.9 k 2.3 3.2 & 2.3 0.5 ? 2.1 1697W0055 MW-49 42'El -1.4 k 2.4 0.3 & 2.2 1.3 4 2.3 -2.1 t 4.5

• 2.2

~~

1697W0056 MW-58 71'El -0.1 & 2.5 3.0 k 2.3 2.1 1.1 -t 2.1 1697W0057 MW-38 -0.9 t 2.5 -0.5 k 2.8 0.2 4 2.4 1 3.8 & 2.3 1697W0058 Discharge Canal -2.0 4 2.3 -1.4 2 2.4 0.8 4 2.4 1.3 t 1.5 1697W0059 MW-40 -1.5 4 1.7 0.4 t 1.7 1.0 4 1.7 -0.6 & 1.9 T h e range of MDCs for the selected radionuclides is 2.8 pCi/L to 4.4 pCi/L hUnccrtainties represent the 95"h confidence level, based on total propagated uncertainties.

In&an oint Power Station projects/l697/Data Tables/2007-01-04 Data Tablcs Set Nine

TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region 1 Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697W0051 MW-50 67' El 30.0 k 1.7b (0.81 1697W0052 1697W0053 MW-49 25' El I 11.7 f 1.o (0.8) 1697W0054 MW-49 65' El I 16.3 & 1.2 1697W0055 MW-49 42' El 19.7 k 1.4 (0.8) 1697W0056 MW-58 71' El 0.65 k 0.51 (0.82) 1697W0057 MW-38 0.37 2 0.45 (0.76) 1697W0058 Discharge Canal 0.20 k 0.45 (0.78) 1697W0059 MW-40 1.2 k 1.1 (1.9)

~~~~ ~~~~~~~ ~

"MDCs arc in parentheses "UnccrtamhLs rcprescnt the 95% confidence level, baaed on total propagated uncertanbea Indian Point Power Station projects/l697/Data 'l'ablcs/2007-01-04 Data Tables Set Ninc

TABLE 4 CONCENTRATIONS OF HARD-TO-DETECT BETA EMITTING RADIONUCLIDES IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN P O I N T POWER STATION BUCHANAN, N E W YORK

%e MDCs for each radionuclide are in parentheses.

bFe-55 analyzed using procedure AP13, Revision 4.

'Ni-59/63 analyzed using procedure AP17, Revision 0.

dH-3 analyzed using procedure AP2, Revision 15.

'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.

TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)

I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Tc-99 Concentrationsa Sample ID Sample ID (pCi/L) 1697W0051 MW-50 67' El -3.9 + 9.1b (15.8) 11 1697W0052 I MW-50 4 2 ' E l I 0.1 & 9.2 (15.8) 11 I11 1697W0053 1697W0054 1697W0055 I MW-49 25' El MW-49 65' E1 MW-49 42'El I

-6.3

-8.5

-8.6 k

k

&

9.0 9.0 9.0 (15.8)

(15.8)

(15.8) 11 1697W0056 MW-58 71' El -5.4 k 9.1 (15.8) 1697W0057 MW-38 -4.0 k 9.1 (15.8) 1697W0058 Discharge Canal 1697W0059 MW-40 -5.2 2 9.1 (15.8)

"The M U G are in parentheses.

"Unccrtaintics rcpreseiit the 95'5'0 confidcnce level, based on total propagated unccrtaindes Indian Point Power Station projccts/l697/Data 'l'ables/2007-01-04 Data Tables Set Nine

TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N S JSPENDED AND DISSOLVED FRACTIONS OF WATER S dPLES BY ALPHA SPECTROSCOPY APl1, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or DCi/L for water)

Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0051 MW-50 67' El 0.02 t 0.08b (0.14) 0.01 t 0.04 (0.07) 0.02 f 0.06 (0.11) -0.12 ? 0.08 10.20) 1697M0003 MW-50 67' El -0.01 t 0.01 (0.03) 0.00' t 0.0'1 (0.02) 0.00 t 0.01 (0.02) -0.05 t 0.02 (0.06) 1697W0052 Mw-50 42' El 0.03 t 0.09 (0.16) -0.02 t 0.06 (0.13) -0.02 t 0.07 (0.15) -0.01 k 0.02 (0.07) 1697M0004 Mw-50 42' El 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.01) 0.00 t 0.01 (0.02) -0.02 t 0.02 (0.04) 1697W0053 MW-49 25' El 0.08 t 0.08 (0.13) 0.03 t 0.03 (0.05) 0.01 t 0.06 (0.12) -0.05 t 0.06 (0.15) 1697M0005 MW-49 25' El 0.01 t 0.01 (0.02) 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.01) -0.01 t 0.02 (0.05) 1697W0054 Mw-49 65' El 0.10 5 0.10 (0.15) 0.02 t 0.02 (0.02) 0.05 t 0.07 (0.12) 0.01  ? 0.02 (0.03) 1697M0006 I MW-49 65' El -0.01 t 0.02 (0.05) 0.00 t 0.01 (0.03) -0.02 t 0.02 (0.04) 0.00 t 0.00 (0.01) 1697W0055 I Mw-49 42' El 0.06 t 0.11 (0.18) -0.01 t 0.05 (0.10) 0.00 t 0.08 (0.15) -0.14 t 0.10 (0.24) 1697M0007 I Mw-49 42' El 0.00 t 0.01 (0.03) 0.00 5 0.01 (0.01) 0.00 k 0.01 (0.02) -0.01 t 0.01 (0.03) 1697W0056 I MW-58 71' El -0.02 ? 0.07 (0.15) -0.01 t 0.04 (0.09) -0.08 ? 0.08 (0.18) -0.07 t 0.06 (0.14) 1697Mo008 I MW-5871'El I -0.01 ? 0.02 (0.04) 0.00 t 0.01 (0.01) -0.01 t 0.01 (0.03) 0.00 ? 0.00 (0.01) 1697W0057 I MW-38 I 0.06 5 0.07 (0.12) I 0.03 t 0.04 (0.07) 0.00 t 0.00 (0.13) -0.08 t 0.06 (0.15) 1697M0009 I Mu-38 I 0.01 t 0.02 (0.03) I 0.01 t 0.01 (0.01) -0.01 t 0.01 (0.03) -0.01 t 0.02 (0.05)

I 0.03 t 0.03 (0.02) 0.00 t 0.02 (0.05) 1 0.00  ? 0.01 1 (0.03) -0.03 ? 0.02 (0.04) 1

-

~~

1697W0059

~~~~

~ I ~~

Mu-40 I 0.02 ? 0.08 (0.15) I -0.02 k 0.02 (0.07) 0.00 I t 0.06 (0.12) -0.13 k 0.09 (0.20) 1 1697M0011 Mu-40 0.00 t 0.02 (0.04) 0.00 2 0.01 (0.02) 0.01  ? 0.02 I (0.03) -0.01 k 0.01 (0.03'1 1

TABLE 6 (Continued)

CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or p( i/L for water)

Sample ID Sample ID Pu-238 Pu-239/240 U-234 U-238 0.05 2 0.07 (0.12) -0.02 f 0.07 (0.15) 0.71 k 0.15 (0.02) 0.42 rt 0.12 (0.09) 0.00 k 0.02 (0.05) 0.01 k 0.02 (0.03) 0.01 k 0.01 (0.01) 0.02 k 0.01 (0.02) 1697W0052 Mw-50 42' El 0.05  ? 0.08 (0.13) 0.04 k 0.04 (0.03) 0.44  ? 0.13 (0.06) 0.21 k 0.09 (0.09) 1 1697M0004 I MW-50 42'El 0.00 k 0.01 (0.03) 0.00  ? 0.01 (0.03) 0.72 & 0.09 (0.02) 1.09  ? 0.13 (0.01) 1 1697W0053 I MW-4925'El -0.04 2 0.08 (0.18) 0.01  ? 0.05 (0.10) 1.07  ? 0.19 (0.08) 0.62 k 0.14 (0.02) 11 1697M0005 I MW-4925'El 0.00 k 0.02 (0.04) 0.00 k 0.01 (0.03) 0.32 f 0.05 (0.02) 0.28 ? 0.05 (0.02) 1 1697W0054 I MW-4965'El 0.05  ? 0.07 (0.11) 0.00 f 0;04 (0.09) 1.76 5 0.26 (0.06) 0.83 k 0.17 (0.02) 1 1697M0006 I Mw-49 65'El 0.01 f 0.02 (0.03) 0.01 f 0.01 (0.02) 0.04  ? 0.02 (0.01) 0.04 f 0.02 (0.01) 11 1697W0055 I Mw-49 42'El 0.03 f 0.09 (0.16'1 -0.01 2 0.06 (0.14) 2.10 k 0.31 (0.11) 0.77 2 0.18 (0.11) 0.03  ? 0.02 (0.01) 1.54  ? 0.24 (0.02) 0.49 f 0.07 (0.02) 0.10 k 0.05 (0.02) 0.03 f 0.02 (0.02'1 0.17 k 0.08 (0.07) 0.06 f 0.02 (0.02) 0.65 5 0.15 (0.06'1 0.41  ? 0.06 (0.01)

"The %DCs are in parentheses.

bUncertaintiesrepresent the 95% confidence level, based on total propagated uncertainties

'Zero values are due to rounding.

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED A N D DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK

'MDCs arc in parentheses "Uncertainties represent the 95% confidence level, based on total propagatcd unccrtainhcs Indian Point Power Station projects/l697/Data Tables/2007-01-04 Data l'ables Set Nine

TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK

'M1)Cs arc in parcntheses.

"Uncertainties represent the 95% confidence lcvel, bawd on total propagated unccrtainties Indian Point Power Station projects/l697/Data Tables/2007-01-04 Data Tables Set Nine