ML070940515

Ltr from Orise Dtd 02/02/2006, Second Interim Report for Requested Analyses of Eight Water Samples, Set Fourteen, from the Indian Point Power Station, Buchanan, New York (IR 05000247/2006007) (Rfta No.06-001)

ML070940515
Person / Time
Site:	Indian Point
Issue date:	02/02/2006
From:	Condra D Oak Ridge Institute for Science & Education
To:	Kottan J Decommissioning Branch I
References
IR-06-007, RFTA 06-001
Download: ML070940515 (11)

Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION February 2,2006 Mr. Jim Kottan U S . Nuclear Regulatory Commission Regon I 475 Allendale Road IOng of Prussia, PA 19406

SUBJECT:

SECOND INTERIM REPORT FOR REQUESTED ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK

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

Dear Mr. Kottan:

The Oak h d g e Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the InQan Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous hection for handling samples from h s facihty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by RaQological and Environmental Sciences Laboratory. Sample identification and collection data for the samples addressed in &Is 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 Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.

ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of h s ralonuclide. ORISE is Qscontinuing the reporting of Ni-59 data untd

&Is problem can be resolved.

The water samples were processed using a deviation to the sample preparation procedure, SP3, Revision 4. The water samples were frltered through 0.45 micron filter papers. An aliquot was removed for tritium and carbon-14 before aciQfication. An aliquot was removed for alpha analysis and the pH was adjusted to approximately zero using concentrated nitric acid (HN03) 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. ORISE analyzed the filtered solid portion of each sample for all the requested alpha isotopes.

M KJim Kottan Febmay 2,2006 My contact information is listed below. You may also contact Wade Ivey at 865.576.9184with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:WI:db Enclosures C: B. Watson, FSME/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN 8A23 S. IGrk, ORISE M. Roberts, NRC Region I J. Whte, NRC Region I File 1697 Distribution approval and concurrence : Initials -

Technical Management Team Member Quality Manager 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 ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 1697WO07Oa MW-42@41 9/18/2006 14:45 1697M0033b MW-42@41 9/18/2006 14:45 1697W0071 MW-42@43 9/18/2006 13:OO 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO 1697W0072 I MW-42@46 I 9/15/2006 I 12:45 1697M0035 I MW-42@46 I 9/15/2006 I 12:45 1697W0073 I MW-42@48 I 9/15/2006 I 11:20 1697M0036 MW-42@48 9/ 15/2006 11:20 169773170074 MW-59@70 9/15/2006 10:20 1697M0037 MW-59@70 9/15/2006 10:20 1697W0075 LAF-001-(003) 9/19/2006 15:49 1697M0038 I LAF-001-(003) I 9/19/2006 I 15:49 1697W0076 I LAF-002-(003) I 9/19/2006 I 13:41 1697M0039 I LAF-002-(003) I 9/19/2006 I 13:41 1697W0077 I LAF-003-(003) I 9/19/2006 I 11:08 1697M0040 I LAF-003-fO03) I 9/19/2006 I 11:08

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

bThe M in the ORISE sample identification represents the filtered fraction of the preceding water sample Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa' 5 1 Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697W0070 I MW-42@41 13.730 k 470 1697W0071 I MW-42@43 1697W0072 MW-42@46 1697W0073 MW-42@48 1697W0074 0.1 k 3.0 I 0.3 k 4.1 I 1.3 If: 2.7 1697W0075 LAF-001-(003) 1.2 k 2.8 I 3.8 f. 2.9 I -0.5 k 2.4 1697W0076 LAF-002-(003) -2.4 f. 3.0 2.2 f. 4.6 0.7 f. 2.6 0.5 k 2.2 1697W0077 LAF-003-(003) -1.7 k 2.0 0.7 k 1.6 -0.8 f. 1.7 -0.7 k 1.6 1 "The range of MDCs for the selected radionuclides for samples WOO7O-WOO73 is 13 pC1/L to 37 pCi/L "The range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.7 pCi/L to 5.0 pCi/L

'Uncertaintm represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

+

'0 5' TABLE 3 a

8 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 ORISE NRC Region I Sample I D Sample ID Fe-!Sb Ni-63" H-3d

-19 ? 19" (32) 452 ? 40 (35) 2,830 t 380 (420)

-17 k 19 (32) 435 ? 39 (35) 2,350 t 360 (420)

-3 t 19 (32) 1,207 2 85 (35) 1,500 k 320 (420) 11 1697W0073 I MW-42@,48 -2 t 19 (32) I 1.272 k 89 (35) I 1.370 ? 310 (420) 11 1697W0074 I MW-59@70 -4  ? 19 (32) -0.4 k 8.2 (14.1) 130 t 250 (420) 11 1697W0075 I LAF-001-(003) -6 t 19 (32) 0.3 & 8.2 (14.1) -94 t 230 (420) 11 . 1697W0076 I LAF-002-(003) -1 t 19 (32) 2.0 t 8.3 (14.1) -220 k 230 (420) 11 1697W0077 I LAF-003-(003) 2 If: 19 (32) I 2.6 2 8.3 (14.1) I -40 k 240 (420)

%e MDCs for each radionuclide are in parentheses.

bFe-55 analyzed using procedure AP13, Revision 4.

'Ni-63 analyzed using procedure AP17, Revision 0 dH-3analyzed using procedure AP2, Revision 15.

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

L

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 ID Sample ID (pCi/L) 1697W0074 MW-59@70 -4.7 k 8.9 (15.6) 1697W0075 LAF-001-(003) -2.7 k 9.0 (15.6) 1697W0076 LAF-002-(003) -0.5 k 9.1 (15.6) 1697W0077 LAF-003-(003) 2.8 k 9.1 (15.6)

%rhcMDCs are in parentheses.

Uncertainties reprcsent the 95% confidence Icvel, based on total propagated uncertainties.

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

TABLE 5 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 I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs" (pCi/L) 1697W0070 Mw-42@41 20.2 k 2.Ob (2.3) 1697W0071 MW-42@43 15.7 k 1.7 (1.9) 1697W0072 MW-42@46 32.8 f 2.4 (2.2) 1697W0073 MW-42@48 35.0 k 2.3 (2.0) 1697W0074 MW-59@70 0.14 k 0.50 (0.89) 1697'0170075 LAF-001-(003) 0.10 k 0.52 (0.93) 1697W0076 LAF-002-(003) 0.97  ? 0.55 (0.87) 1697W0077 LAF-003-(003) -0.17 k 0.45 (0.83)

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Sct 14

TABLE 6 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 Sample ID Cm-242 Cm-243/244 N~-237 1697W0070 m-42@41 0.03 k 0.09b (0.15) 0.01 ? 0.04 (0.07) I 0.01 & 0.08 (0.14) I 0.01 k 0.02 (0.03) 1697M0033 Mw-42@41 0.01 & 0.02 (0.04) 0.01 ? 0.01 (0.02) 0.00" & 0.02 (0.03) 0.00 k 0.02 (0.03) 1697W0071 MW-42@43 0.07 k 0.09 (0.15) 0.07 k 0.06 (0.08) 0.01 f. 0.09 (0.17) 0.01 ? 0.02 (0.03) 0.00 ? 0.01 (0.03) -0.01 k 0.02 (0.04) -0.01 f. 0.02 (0.04) 0.03 ? 0.06 (0.10) -0.03 f. 0.07 (0.14) 0.03 & 0.06 (0.11) 0.01 k 0.01 (0.02) 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.03) 0.03 k 0.03 (0.02) 0.01 f. 0.07 (0.14) -0.04 f. 0.05 (0.12) 1 1697M0036 m-42@48 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.02) -0.01 k 0.02 (0.04) 0.002 f. 0.004d (0.007) 2- 1697W0074 m-596370 0.00 k 0.05 (0.09) 0.02 f. 0.02 (0.03) -0.01 k 0.04 (0.08) 0.02 f. 0.02 (0.02) 2 1 .

1697M0037 m-59@70 -0.01 k 0.02 (0.04) 0.01 ? 0.01 (0.01) I 0.00 k 0.02 (0.03) I 0.00 f. 0.01 (0.03)

L I 1

.z

- -. 1697W0075 uF-001-(003) 0.03 f. 0.04 (0.07) 0.00 f. 0.03 (0.06) I -0.02 k 0.04 (0.08) I 0.00 f. 0.01 (0.04)

U E-' 1697M0038 , uF-001-(003) 0.02 f. 0.02 (0.03) 0.01 I

? 0.01 (0.03) -0.01 k 0.02 I (0.04) 0.002 f. 0.005 (0.007) 21 1697W0076 I LAF-002-(003) I -0.02 f. 0.05 (0.09) 0.00 f. 0.03 (0.06) 0.00 k 0.03 (0.05) 0.00 f. 0.04 (0.08)

R 1 1697M0039 I LAF-002-(003) I 0.01 f. 0.02 (0.03) 0.00 f. 0.01 (0.02) 0.00 k 0.02 (0.03) 0.00 f. 0.01 (0.03) 0.01 ? 0.02 (0.03) 0.00 f. 0.01 (0.01) -0.06 k 0.04 (0.10)

I I 0.00 k 0.01 (0.02) 0.00 f. 0.01 (0.02) 0.002 ? 0.004 (0.006) e a

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W W i 3 Indian Point Power Station projccts/l697/Data Tables/2007-02-02 Data Tables Set 14

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 NRC Region I Sample ID (pCi/g of sediment in 100 mL or pCi/L for water)

• l Mw-42@41 Mw-42@41 Mw-42@43 I -3 +_ 17b (29) 11 MW-42@43 -0.6 3.7 6.4)

Mw-42@46 -10 (27) 1697M0036 1697W0074 1697M0037 Mw-42048 MW-59@70 MW-59@70

-0.6

-2.5

-0.9 k

k k

3.5 9.3 3.4 (16.1)

(5.9)

I 1697W0075 LAF-001-(003) -2.7 k 7.9 (13.7) 1697M0038 LAF-001-(003) 1.1 k 3.5 (6.0) 1697W0076 LAF-002-(003) -6.4 If: 7.8 (13.6) 1697M0039 LAF-002-(003) 1.4 +

- 3.6 (6.1)

• l LAF-003-(003)

LAF-003-(003)

-2.5 2.6 k

?

8.2 3.5 (14.2)

(5.9)

"MDCs are in parenthescs

'Uncertainties represent the 95% confidence level, based on total propagated uncertainhes Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

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 ID TPUs, and MDCS"(pCi/L) 1697W0070 MW-42@41 0.8 k 9.7b (16.4) 1697W0071 MW-42@43 8.8

• 9.8 (16.4) 1697W0072 MW-42@46 0.2

• 9.6 (16.4) 1697W0073 MW-42@48 -0.6 k 9.6 (16.4) 1697W0074

~

MW-59@70

~

6.9 +

- 9.8 (16.4) 1697W0075 LAF-001-(003) 0.5 k 9.7 (16.4) 1697W0076 LAF-002-(003) 1.4

• 9.7 (16.4) 1697W0077 LAF-003-(003) 8.3  ? 9.8 (16.4)

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14