ML070940515
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 US. 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 NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak hdge 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 hs 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 hs 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.
MK Jim Kottan Febmay 2,2006 Distribution approval and concurrence
- Technical Management Team Member Quality 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:db Enclosures C: B. Watson, FSME/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Region I File 1697 S. IGrk, ORISE J. Whte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail:
Dale.Condra@orau.org TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1697WO07Oa 1 697M0033b 1697W0071 MW-42@41 9/18/2006 14:45 MW-42@41 9/18/2006 14:45 MW-42@43 9/18/2006 13:OO 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO 1697M0036 169773170074 1697M0037 1697W0075 1697W0072 I MW-42@46 I 9/15/2006 I 12:45 MW-42@48 9/ 15/2006 11:20 MW-59@70 9/15/2006 10:20 MW-59@70 9/15/2006 10:20 LAF-001-(003) 9/19/2006 15:49 1697M0035 I MW-42@46 I 9/15/2006 I 12:45 1697W0073 I MW-42@48 I 9/15/2006 I 11:20 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 Sample ID Sample ID 1697W0070 I MW-42@41 1697W0071 I MW-42@43 1697W0072 1697W0073 1697W0074 1697W0075 1697W0076 1697W0077 MW-42@46 MW-42@48 LAF-001-(003)
LAF-002-(003)
LAF-003-(003)
Radionuclide Concentrationsa' CO-58 CO-60 cs-134 0.1 k 3.0 I 0.3 k 4.1 I 1.3 If: 2.7 1.2 k 2.8 I 3.8 f. 2.9 I -0.5 k 2.4 -2.4 f. 3.0 2.2 f. 4.6 0.7 f. 2.6 -1.7 k 2.0 0.7 k 1.6 -0.8 f. 1.7 "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 cs-137 13.730 k 470 51 0.5 k 2.2 -0.7 k 1.6 11 Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14
+ 0' 5' a 8 Fe-!Sb -19 ? 19" (32) -17 k 19 (32) -3 t 19 (32) TABLE 3 Ni-63" H-3d 452 ? 40 (35) 2,830 t 380 (420) 435 ? 39 (35) 2,350 t 360 (420) 1,207 2 85 (35) 1,500 k 320 (420) 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 -4 ? 19 (32) -6 t 19 (32) -1 t 19 (32) ORISE NRC Region I Sample ID Sample ID -0.4 k 8.2 (14.1) 130 t 250 (420) 0.3 & 8.2 (14.1) -94 t 230 (420) 2.0 t 8.3 (14.1) -220 k 230 (420) 11 1697W0073 I MW-42@,48 11 1697W0074 I MW-59@70 11 1697W0075 I LAF-001-(003) 11 . 1697W0076 I LAF-002-(003) 11 1697W0077 I LAF-003-(003)
-2 t 19 (32) I 1.272 k 89 (35) I 1.370 ? 310 (420) 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-3 analyzed using procedure AP2, Revision 15. 'Uncertainties represent the 95% confidence level, based on total propagated uncertainties L P TABLE 4 ORISE Sample ID 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) 1697W0074 1697W0075 1697W0076 1697W0077 MW-59@70 -4.7 k 8.9 (15.6) LAF-001-(003)
-2.7 k 9.0 (15.6) LAF-002-(003)
-0.5 k 9.1 (15.6) LAF-003-(003) 2.8 k 9.1 (15.6) %rhc MDCs 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 ORISE Sample ID 1697W0070 1697W0071 1697W0072 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 NRC Region I Radionuclide Concentrations, Sample ID TPUs, and MDCs" (pCi/L)
Mw-42@41 20.2 k 2.Ob (2.3) MW-42@43 15.7 k 1.7 (1.9) MW-42@46 32.8 f 2.4 (2.2) 1697W0073 1697W0074 1697'0170075 1697W0076 1697W0077 MW-42@48 35.0 k 2.3 (2.0) MW-59@70 0.14 k 0.50 (0.89) LAF-001-(003) 0.10 k 0.52 (0.93) LAF-002-(003) 0.97 ? 0.55 (0.87) 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 Cm-242 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Cm-243/244 N~-237 ORISE NRC Region I Sample ID 0.01 ? 0.01 (0.02) 0.07 k 0.06 (0.08) 0.00 ? 0.01 (0.03) 0.03 ? 0.06 (0.10) 0.01 k 0.01 (0.02) 1697W0070 m-42@41 0.03 k 0.09b (0.15) 1697M0033 Mw-42@41 0.01 & 0.02 (0.04) 1697W0071 MW-42@43 0.07 k 0.09 (0.15) 0.00" & 0.02 (0.03) 0.00 k 0.02 (0.03) 0.01 f. 0.09 (0.17) 0.01 ? 0.02 (0.03) -0.01 k 0.02 (0.04) -0.01 f. 0.02 (0.04) -0.03 f. 0.07 (0.14) 0.03 & 0.06 (0.11) 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.03) 11 1697M0036 0.03 k 0.03 (0.02) 0.00 ? 0.01 (0.02) 0.02 f. 0.02 (0.03) m-42@48 0.00 ? 0.02 (0.04) 1697W0074 m-596370 0.00 k 0.05 (0.09) 2 1697M0037 m-59@70 -0.01 k 0.02 (0.04) .z 1697W0075 uF-001-(003) 0.03 f. 0.04 (0.07) , uF-001-(003) 0.02 f. 0.02 (0.03) E 2 - 1. L --. 1697M0038 U -' 0.01 f. 0.07 (0.14) -0.04 f. 0.05 (0.12) -0.01 k 0.02 (0.04) 0.002 f. 0.004d (0.007) -0.01 k 0.04 (0.08) 0.02 f. 0.02 (0.02) 2 11 1697W0076 I LAF-002-(003)
I -0.02 f. 0.05 (0.09) 0.00 f. 0.03 (0.06) 0.00 f. 0.01 (0.02) 0.01 ? 0.02 (0.03) 0.00 k 0.01 (0.02) R 11 1697M0039 I LAF-002-(003)
I 0.01 f. 0.02 (0.03) 0.00 k 0.03 (0.05) 0.00 f. 0.04 (0.08) 0.00 k 0.02 (0.03) 0.00 f. 0.01 (0.03) 0.00 f. 0.01 (0.01) -0.06 k 0.04 (0.10) 0.00 f. 0.01 (0.02) 0.002 ? 0.004 (0.006) I I e a 2 cn e P 0.01 ? 0.04 (0.07) I 0.01 & 0.08 (0.14) I 0.01 k 0.02 (0.03) 0.01 ? 0.01 (0.01) I 0.00 k 0.02 (0.03) I 0.00 f. 0.01 (0.03) I 1 0.00 f. 0.03 (0.06) I -0.02 k 0.04 (0.08) I 0.00 f. 0.01 (0.04) 0.01 ? 0.01 (0.03) I -0.01 k 0.02 (0.04) I 0.002 f. 0.005 (0.007) i3 cn 8 d W Indian Point Power Station F hl : 8 i +I 3 8 - F 01 9 9 9 +I 3 0 + 8 - fl + 9 0. 3 8 8 8 L 8 8 8 +I i - G hl +I 0 - 3 hl F M M 0 3 r- s\ W i T 7 C 5 7 C C t 7 C C - /- 7 C 5 r C C + r C C - r n C s 7 c C + 7 C C - G s C h C C + h C c - M 8 f d- M 0 3 r. c\ W 3 projccts/l697/Data Tables/2007-02-02 Data Tables Set 14 TABLE 7 Mw-42048 MW-59@70 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 (16.1) I -0.6 k 3.5 -2.5 k 9.3 ll* MW-59@70 LAF-001-(003)
LAF-001-(003)
LAF-002-(003)
LAF-002-(003) 1697M0036 1697W0074 1697M0037 1697W0075 1697M0038 1697W0076 1697M0039
-0.9 k 3.4 (5.9) -2.7 k 7.9 (13.7) 1.1 k 3.5 (6.0) -6.4 If: 7.8 (13.6) 1.4 - + 3.6 (6.1) ll* LAF-003-(003)
LAF-003-(003) "MDCs are in parenthescs
-2.5 k 8.2 (14.2) 2.6 ? 3.5 (5.9) Radionuclide Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water) NRC Region I Sample ID Mw-42@41 I -3 +_ 1 7b (29) 11 Mw-42@41 Mw-42@43 MW-42@43 -0.6 3.7 6.4) Mw-42@46 -10 (27) '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 ORISE Sample ID 1697W0070 1697W0071 1697W0072 1697W0073 1697W0074 CONCENTRATIONS OF CARBON-14 IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrations, Sample ID MW-42@41 0.8 k 9.7b (16.4) MW-42@43 8.8
- 9.8 (16.4) MW-42@46 0.2
- 9.6 (16.4) MW-42@48 -0.6 k 9.6 (16.4) MW-59@70 6.9 - + 9.8 (1 6.4) TPUs, and MDCS" (pCi/L) 1697W0075 1697W0076 1697W0077 ~ ~ LAF-001-(003) 0.5 k 9.7 (16.4) LAF-002-(003) 1.4
- 9.7 (16.4) LAF-003-(003) 8.3 ? 9.8 (1 6.4) Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14