ML071900456

Orise Interim Report for Completed Analyses for Samples from Set Twenty-Three, from the Indian Point Power Station, Buchanan, Ny, Dtd 03/04/07

ML071900456
Person / Time
Site:	Indian Point
Issue date:	05/04/2007
From:	Condra D Oak Ridge Institute for Science & Education
To:	Kottan J NRC Region 1
References
FOIA/PA-2007-0324, IR-06-007, RFTA 06-001
Download: ML071900456 (10)

Text

-- r * ' n k ! 7 i .: OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION May 4,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

SUBJECT:

INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET TWENTY-THREE, 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 Ridge Institute for Science and Education (ORISE) received set 23, consisting of four water samples, associated with the Indian Point Power Station on March 9,2007. Sample analysis was initiated based on your previous direction for handling samples from thls licensee. Sample identification and collection data for the samples addressed in this report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 8, respectively. The pertinent procedure references are provided in each specific table.

ORISE's Quahty Control (QC) requirements were met for these analyses. The QC files are available for your review upon request. Adltional reports will follow after the completion of the requested analyses.

ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of t h l s radionuclide. ORISE is discontinuing the reporting of Ni-59 data until this problem can be resolved.

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:WPI:bf Enclosures C: T. Carter, NRC/FSME/DWMEP 7J8 J. Whtte, NRC Region I E. Knox-Davin, NRC/FSME/TWFN 8A23 E. Abelquist, ORISE M. Roberts, NRC Region I S Kirk, ORISE File 1697 Distribution approval and concurrence : I"&

Technical Management Team Member q ) I(

Quality Manager Ip Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK

~

I ORISE NRC Region I Sample I D Sample I D 2/27/2007 I 11:24 I 1697M0089 169773170141 1697M0090 I LAF-002-(005)

LAF-003-(005)

LAF-003-fO05)

-%q+g--ll 3/7/2007

%e Win the ORISE sample identification represents a water matrix.

bThe M in the ORISE sample identification represents a 1OomL filtered fraction of the preceding water sample.

Indian Point Power Station prqects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23

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 Radionuclide Concentrationsa (pCi/L)

Sample ID Sample I D CO-58 CO-60 cs-134 cs-137 1697W0138 ul-css-(oo2) -3.1 k 2.7b 0.5 k 2.1 -0.6 k 2.9 1.9 k 5.2 1697W0139 uF-001-(005) 2.2 k 2.5 -0.4 k 2.3 1.2 k 2.6 -0.7 k 2.1 1697W0140 uF-002-(005) -0.6 k 1.9 1.1 k 1.6 1.2 k 1.8 -0.7 k 1.5 1697W0141 UF-003-(005) -0.9 k 2.8 2.0 k 2.6 -0.3 k 3.0 -1.3 k 2.3 buncertainties represent the 9596 confidence level, based on total propagated uncertainties.

Indian Point Power Station projects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23

TABLE 3 CONCENTRATIONS OF HARD-TO-DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa @Ci/L)

ORISE NRC Region I Sample I D Sample I D Fe-55b Ni-63 H-3d 1697W0138 UI-CSS-(OO2) 66 k 48 , 79 11.1 k 3.2 , 5.0 4,960 k 470 , 390 1697W0139 LAF-O01-(005) 52 k 48 79 1.8 k 3.0 5.0 110 k 230 , 390 1697W0140 LAF-002-(005) 37, k 47 , 79 2.8 k 3.0 , 5.0 290 k 240 , 390 1697W0141 LAF-003-(005) 7 4 , ) k 48 , 79 1.0 k 3.0 , 5.0 30 k 220 , 390

~ ~~~

%e MDCs for each radionuclide are after the comma.

bFe-55 analyzed using procedure AP13, Re~~ision 4.

Ni-63 analyzed using procedure AP12, Revision 5.

dH-3 analyzed using procedure AP2, Revision 15.

Uncertainties represent the 9500 confidence level, based on total propagated uncertainties.

Zero value is due to rounding.

Indian Point Power Station projects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23

TABLE 4 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 I D Sample ID @Ci/L) 1697W0138 ul-css-(oo2) 8.6 k 7.8b . 13.0 1697W0139 LAF-001-(005) 8.8 k 7.8 13.0 1697W0140 LAF-002-(005) 3.5  ? 7.7 13.0 1697W0141 LAF-003-(005) 3.5 k 7.7 13.0 Indian Point Power Station projects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23

TABLE 5 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs" @Ci/L) 1697W0138 u1-css-(002) 16.8 f_ 1.2b 0.8 1697W0139 LAF-001-(005) 0.45

• 0.43 0.72 1697W0140 LAF-002-(005) 0.69 f 0.48 0.77 169773170141 LAF-003-(005) 0.25 0.45 0.77 buncertainties represent the 959'0 confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23

TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES APl1, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1 Sazz?D I NRC Region I Sample ID Am-241 Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or pCi/L for water)

I Cm-242 I Cm-243/244 I ND-237 1697W013Sb u 1-css-(002) 0.11 k 0.19' 0.34 0.07 k 0.10 , 0.17 0.09 k 0.18 0.32 -0.13 k 0.15 0.36 .

1697M0087d Ul-CSS-(002) O.OOe k 0.02 0.04 0.02 k 0.02 , 0.02 -0.01 2 0.02 , 0.04 0.00 k 0.01 , 0.02 1697W0139 LAF-001-(005) 0.22 k 0.17 , 0.24 0.02 k 0.06 , 0.14 0.07 k 0.07 , 0.06 0.05 k 0.11 , 0.20 1697M0088 LAF-001-(005) -0.01 k 0.02 0.04 0.01 k 0.02 , 0.03 -0.01  ? 0.01 , 0.03 0.01 k 0.01 , 0.02 1697W0140 LAF-002-fO05) 0.15 k 0.19 . 0.31 0.04 k 0.09 . 0.18 -0.26 k 0.18 . 0.43 -0.02 k 0.17 . 0.34 1 1697M0089 I LAF-002-fO05) I 0.00 k 0.02 . 0.04 I 0.01 k 0.02 . 0.02 I -0.01 k 0.02 . 0.04 I 0.00 k 0.01 . 0.02 1 1697W0141 LAF-003-(005) 0.25 2 0.17 , 0.23 -0.02 k 0.09 0.22 -0.11 k 0.13 0.31 0.03 k 0.06 , 0.12 1697M0090 LAF-003-(005) 0.00 k 0.02 , 0.03 0.01 2 0.02 , 0.02 0.00 2 0.01 0.03 -0.01 k 0.01 , 0.03

TABLE 6 (Continued)

CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES 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 pCi/L for water)

Sample ID Sample ID PU-238 P~-239/240 U-234 U-238 1697W0138 Ul-CSS-(OO2) 0.17 ? 0.15 , 0.20 0.08 k 0.10 , 0.16 1.50 k 0.34 , 0.05 1.25 f 0.31 , 0.16 1697M0087 ul-css-(oo2) 0.00 k 0.02 , 0.04 0.00 rt: 0.01 , 0.01 0.01 k 0.01 , 0.02 0.00 k 0.01 , 0.02 1697W0139 LAF-001-(005) 0.13 f 0.16 , 0.27 0.09 f 0.08 , 0.05 4.00 k 0.60 , 0.13 3.68 k 0.57 , 0.05 1697M0088 LAF-001-(005) 0.03 k 0.02 , 0.03 0.01 t 0.01 , 0.01 0.00 k 0.01 , 0.02 0.00 k 0.01 , 0.02 1697W0140 LAF-002-(005) 0.12 & 0.14 , 0.24 0.08 k 0.11 , 0.18 26.5 k 2.4 , 0.1 16.5 k 1.6 , 0.1 1697M0089 LAF-002-(005) 0.03 k 0.02 , 0.03 0.02 f 0.01 , 0.01 0.03 k 0.02 , 0.01 0.02 k 0.01 , 0.01 1697W0141 LAF-003-(005) 0.06 t 0.10 . 0.18 0.02 k 0.06 . 0.12 -0.02 k 0.12 . 0.26 0.02 t: 0.08 . 0.17 1697M0090 I LAF-003-(005) I 0.01 k 0.02 , 0.03 I 0.00 k 0.01 , 0.02 I 0.01 k 0.01 , 0.01 I 0.01 f 0.01 , 0.01

%e MDCs are after the comma.

%e W in the ORISE sample identification represents a water matrix.

4

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

P r

%e M in the ORISE sample identification represents a 100 mL fdtered fraction of the preceding water sample.

'Zero values are due to rounding.

s N

W

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa @Ci/g ORISE NRC Region I of sediment in 100 mL or Sample I D Sample I D pCi/L for water) 1697W0138b ul-css-(oo2) -10 f. 29" 5 49 1697M0087d ul-css-(oo2) -1.2

• 2.9 , 5.1 1697W0139 LAF-001-(005) 6 f. 28 7 47 1697M0088 LAF-001-(005) -1.4

• 2.8 , 4.9 1697W0140 LAF-002-(005) -4

• 29 9 51 1697M0089 LAF-002-(005) -0.5 f: 2.9 . 4.9 1697W0141 LAF-003-(005) -9

• 28 Y 49 1697M0090 LAF-003-(005) 0.9

• 3.0 , 5.0 T h e MDCs are d t e r the comma.

bThe Win the ORISE sample identification represents a water matrix.

'Uncertainties represent the 959'0 confidence lcvel, based on total propagated uncertainties.

dThe M in the ORISE sample identification represents a l 0 M filtered fraction of the preceding water sample.

Indian Point Power Station projects/l697/Data Tables/2007-05-04 Interim D a t i Tables 1697 Set 23

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 ORISE NRC Region I Radionuclide Concentrations, Sample I D Sample I D TPUs, and MDCs" @Ci/L) 1697W0138 ul-css-(oo2) 0.7 lk 9.1b 15.5 i

11 1697W0139 I LAF-001-(005) I 1.3

• 9.1 . 15.5 II I 1697W0141 1697w0140 T h e MDCs are after the comma.

LAF-002-(005)

LAF-003-[005) 3.7 5.6 k

+

9.2 9.2 -

15.5 15.5 bUncertmhes represent the 95% confidence level, based on total propagated uncertamtles.

Indian Point Power Station prqects/l697/Data Tables/2007-05-04 Interim Data Tables 1697 Set 23