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See also: [[see also::IR 05000247/2006007]]


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{{#Wiki_filter:OAK RIDGE INSTITUTE  
{{#Wiki_filter: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  
FOR SCIENCE AND EDUCATION  
 
February 2,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission  
==SUBJECT:==
Regon I 475 Allendale  
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  
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  
==Dear Mr. Kottan:==
REPORT NO. 050-247/2006-0071 [RFTA  
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.
NO. 06-0011 Dear Mr. Kottan: The Oak hdge Institute for  
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.
Science and Education (ORISE) received set 14, whch consisted  
The pertinent procedure references are provided in each specific table.
of eight water samples received  
ORISE's Quality Control (QC) requirements were met for these analyses.
on September  
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.
26,2006 from the InQan Point Power Station in  
ORISE is Qscontinuing the reporting of Ni-59 data untd &Is problem can be resolved.
Buchanan, New York. Sample analysis was  
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.
initiated  
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.
based on your previous  
ORISE analyzed the filtered solid portion of each sample for all the requested alpha isotopes.
hection for handling samples from hs facihty. The final report was delayed  
MK Jim Kottan Febmay 2,2006 Distribution approval and concurrence
untd technical concerns about  
: 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.
plutonium  
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:
in water samples were resolved through analytical testing conducted  
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)
by RaQological  
I 9/19/2006 I 15:49 1697W0076 I LAF-002-(003)
and Environmental  
I 9/19/2006 I 13:41 1697M0039 I LAF-002-(003)
Sciences Laboratory.  
I 9/19/2006 I 13:41 1697W0077 I LAF-003-(003)
Sample identification  
I 9/19/2006 I 11:08 1697M0040 I LAF-003-fO03)
and collection data for the samples addressed  
I 9/19/2006 I 11:08 %e W in the ORISC sample identification represents a water matrix.
in &Is report are presented  
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)
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  
LAF-002-(003)
data are provided in Tables  
LAF-003-(003)
2 through 8, respectively.  
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   
The pertinent procedure references  
+ 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)  
are provided in each specific table.  
-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.
ORISE's Quality Control (QC) requirements  
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)  
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 -2- 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)  
-2.7 k 9.0 (15.6) LAF-002-(003)  
-0.5 k 9.1 (15.6) LAF-003-(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.
2.8 k 9.1 (15.6) %rhc MDCs are in parentheses. 'Uncertainties reprcsent  
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)
the 95% confidence  
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)  
Icvel, based on total propagated  
-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)
uncertainties.  
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)
Indian Point Power Station projects/l697/Data  
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)
Tables/2007-02-02  
LAF-001-(003)
Data Tables Set  
LAF-002-(003)
14
LAF-002-(003) 1697M0036 1697W0074 1697M0037 1697W0075 1697M0038 1697W0076 1697M0039  
TABLE 5 ORISE Sample ID 1697W0070  
-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)
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  
LAF-003-(003) "MDCs are in parenthescs  
-2.5 k 8.2 (14.2) 2.6 ? 3.5 (5.9) Radionuclide  
-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
Concentrationsa (pCi/g of  
* 9.8 (16.4) MW-42@46 0.2
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  
* 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
6.4) Mw-42@46 -10 (27) 'Uncertainties represent  
* 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}}
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
}}

Revision as of 01:38, 18 September 2019

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 Entergy icon.png
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)
v • d • e


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
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