ML070940618
| 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
January 4,2007 Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
SUBJECT:
FINAL LETTER REPORT FOR REQUESTED ANALYSES OF NINE WATER SAMPLES, SET NINE, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION REPORT NO. 050-247/2006-0071
[RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak kdge Institute for Science and Education (ORISE) received set nine, which consisted of nine water samples received on August 15,2006 from the Inlan Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous duection for handhg 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. ORISE's 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 Distribution approval and concurrence
- Technical Management Team Member Oualitv Manager My contact information is listed below.
You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Initials Sincerely, Dale Condra, Manager Laboratory RDC:WI:ar Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Ihox-Davin, NRC/NMSS/TWFN 8A23 M. Roberts, NRC Region I File 1697 E. Abelquist, ORISE S. IOrk, ORISE J. Whte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale. Condra@orau. org TABLE 1 ORISE NRC Region I Collection Sample ID Sample ID Date Collection Time 1697W0051" I Mw-50 67'El I 8/1/2006 I 11:30 1 697M0003b 1697W0052 ~ ~~ MW-50 67' El 8/1/2006 11:30 MW-50 42' El 8/1/2006 11:15 ~~ 1697M0004 I MW-50 42' El ~~ - 1697W0055 1697M0007 1697W0056 1697M0008 1697W0057 1697M0009 1697W0058 1697M0010 1697W0053 I MW-49 25' El MW-49 42' El 8/1/2006 9:35 MW-49 42' El 8/ 1 /2006 9:35 MW-58 71' El 8/2/2006 9:31 MW-58 71' El 8/2/2006 9:31 MW-38 8/7/2006 13:23 MW-38 8/7/2006 13:23 Discharge Canal 8/7/2006 13:50 Discharge Canal 8/7/2006 13:50 8/1/2006 I 9:50 1697W0059 1697M0011 MW-40 8/9/2006 10:35 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 ORISE Sample ID CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK co-58 CO-GO NRC Region I Sample ID 1697W0051 1697W0052 1697W0053 1697W0054 1697W0055 b MW-50 67'El -0.3 k 3.1 0.7 k 2.8 MW-50 42'El 1.3 k 2.3 2.1 k 2.1 MW-49 25' El -0.7 k 1.8 0.6 k 1.6 MW-49 65'El 1.1 4 2.3 0.9 k 2.3 MW-49 42'El -1.4 k 2.4 0.3 & 2.2 ~~ 1697W0056 1697W0057 1697W0058 1697W0059 The 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.
MW-58 71'El -0.1 & 2.5 3.0 k 2.3 MW-38 -0.9 t 2.5 -0.5 k 2.8 Discharge Canal -2.0 4 2.3 -1.4 2 2.4 MW-40 -1.5 4 1.7 0.4 t 1.7 :ntrationsa (1 cs-134 0.6 2 2.9 -0.3 4 2.1 -0.1 k 1.7 3.2 & 2.3 1.3 4 2.3 2.1
- 2.2 0.2 4 2.4 0.8 4 2.4 1.0 4 1.7 Ci/L) cs-137 2.0 t 2.5 -2.6 5 4.5 0.2 k 1.6 0.5 ? 2.1 -2.1 t 4.5 1.1 -t 2.1 1 3.8 & 2.3 1.3 t 1.5 -0.6 & 1.9 In&an oint Power Station projects/l697/Data Tables/2007-01-04 Data Tablcs Set Nine TABLE 3 NRC Region 1 Sample ID MW-50 67' El CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) 30.0 k 1.7b (0.81 ORISE Sample ID MW-49 42' El MW-58 71' El MW-38 Discharge Canal MW-40 1697W0051 19.7 k 1.4 (0.8) 0.65 k 0.51 (0.82) 0.37 2 0.45 (0.76) 0.20 k 0.45 (0.78) 1.2 k 1.1 (1.9) 1697W0052 1697W0053 1697W0054 1697W0055 1697W0056 1697W0057 1697W0058 1697W0059 MW-49 25' El I 11.7 f 1 .o (0.8) MW-49 65' El I 16.3 & 1.2 ~~~~ ~~~~~~~ ~ "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 POINT POWER STATION BUCHANAN, NEW 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 ORISE Sample ID 1697W0051 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99) IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Tc-99 Concentrationsa Sample ID (pCi/L) MW-50 67' El -3.9 + 9.1b (15.8) I 11 1697W0052 I MW-50 42'El I 0.1 & 9.2 (15.8) 11 1697W0053 MW-49 25' El -6.3 k 9.0 (15.8) 1697W0054 MW-49 65' E1 -8.5 k 9.0 (15.8) 11 1697W0055 I MW-49 42'El I -8.6 & 9.0 (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 MUG 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 ORISE NRC Region I Sample ID Sample ID Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or DCi/L for water) Am-241 Cm-242 1697W0051 1697M0003 1697W0052 1697M0004 1697W0053 1697M0005 1697W0054 MW-50 67' El MW-50 67' El Mw-50 42' El Mw-50 42' El MW-49 25' El MW-49 25' El Mw-49 65' El 0.02 t 0.08b (0.14) -0.01 t 0.01 (0.03) 0.03 t 0.09 (0.16) 0.00 t 0.01 (0.02) 0.01 t 0.01 (0.02) 0.08 t 0.08 (0.13) 0.10 5 0.10 (0.15) -0.01 t 0.02 (0.05) 0.06 t 0.11 (0.18) 0.00 t 0.01 (0.03) -0.02 ? 0.07 (0.15) 1697Mo008 I MW-5871'El I -0.01 ? 0.02 (0.04) 0.01 t 0.04 (0.07) 0.00' t 0.0'1 (0.02) -0.02 t 0.06 (0.13) 0.00 t 0.01 (0.01) 0.00 t 0.01 (0.02) 0.03 t 0.03 (0.05) 0.02 t 0.02 (0.02) 0.00 t 0.01 (0.03) -0.01 t 0.05 (0.10) 0.00 5 0.01 (0.01) -0.01 t 0.04 (0.09) 0.00 t 0.01 (0.01) ~~ ~~~~ ~~ 1697M0011 Mu-40 0.00 t 0.02 (0.04) 0.00 2 0.01 (0.02) TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN 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 Cm-243/244 0.02 f 0.06 (0.11) Np-237 -0.12 ? 0.08 10.20) -0.05 t 0.02 (0.06) 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.01) -0.02 t 0.07 (0.15) 0.01 t 0.06 (0.12) 0.05 t 0.07 (0.12) -0.02 t 0.02 (0.04) 0.00 t 0.08 (0.15) 0.00 k 0.01 (0.02) -0.08 ? 0.08 (0.18) -0.01 t 0.01 (0.03) 0.00 t 0.00 (0.13) -0.01 k 0.02 (0.07) -0.02 t 0.02 (0.04) -0.05 t 0.06 (0.15) -0.01 t 0.02 (0.05) 0.01 ? 0.02 (0.03) 0.00 t 0.00 (0.01) -0.14 t 0.10 (0.24) -0.01 t 0.01 (0.03) -0.07 t 0.06 (0.14) 0.00 ? 0.00 (0.01) -0.08 t 0.06 (0.15) -0.01 t 0.02 (0.05) 1697M0006 I MW-49 65' El 1697W0055 I Mw-49 42' El 1697M0007 I Mw-49 42' El 1697W0056 I MW-58 71' El 1697W0057 I MW-38 I 0.06 5 0.07 (0.12)
I 0.03 t 0.04 (0.07) 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) 0.03 t 0.03 (0.02) I 0.00 t 0.02 (0.05) 11 0.00 ? 0.01 (0.03) 1 -0.03 ? 0.02 (0.04) 11 - 1697W0059
~ I Mu-40 I 0.02 ? 0.08 (0.15) I -0.02 k 0.02 (0.07) 0.00 t 0.06 (0.12) I -0.13 k 0.09 (0.20) 11 0.01 ? 0.02 (0.03) I -0.01 k 0.01 (0.03'1 11 TABLE 6 (Continued) CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN 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( Sample ID Sample ID Pu-238 Pu-239/240 U-234 1697W0052 Mw-50 42' El 11 1697M0004 I MW-50 42'El 11 1697W0053 I MW-4925'El 11 1697M0005 I MW-4925'El 11 1697W0054 I MW-4965'El 11 1697M0006 I Mw-49 65'El 11 1697W0055 I Mw-49 42'El 0.05 2 0.07 (0.12) -0.02 f 0.07 (0.15) 0.71 k 0.15 (0.02) 0.00 k 0.02 (0.05) 0.01 k 0.02 (0.03) 0.01 k 0.01 (0.01) 0.05 ? 0.08 (0.13) 0.04 k 0.04 (0.03) 0.44 ? 0.13 (0.06) 0.00 k 0.01 (0.03) 0.00 ? 0.01 (0.03) 0.72 & 0.09 (0.02) -0.04 2 0.08 (0.18) 0.01 ? 0.05 (0.10) 1.07 ? 0.19 (0.08) 0.00 k 0.02 (0.04) 0.00 k 0.01 (0.03) 0.32 f 0.05 (0.02) 0.05 ? 0.07 (0.11) 0.00 f 0;04 (0.09) 1.76 5 0.26 (0.06) 0.01 f 0.02 (0.03) 0.01 f 0.01 (0.02) 0.04 ? 0.02 (0.01) 0.03 f 0.09 (0.16'1 -0.01 2 0.06 (0.14) 2.10 k 0.31 (0.11) "The %DCs are in parentheses. bUncertainties represent the 95% confidence level, based on total propagated uncertainties
'Zero values are due to rounding.
i/L for water) U-238 0.42 rt 0.12 (0.09) 0.02 k 0.01 (0.02) 0.21 k 0.09 (0.09) 1.09 ? 0.13 (0.01) 0.62 k 0.14 (0.02) 0.28 ? 0.05 (0.02) 0.83 k 0.17 (0.02) 0.04 f 0.02 (0.01) 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)
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 IN SUSPENDED AND 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 IN 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