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{{#Wiki_filter: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
{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 4,2007 Mr. Jim Kottan U S . Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406


==SUBJECT:==
==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
FINAL L E T T E R REPORT F O R REQUESTED ANALYSES O F NINE WATER SAMPLES, SET NINE, FROM THE INDIAN P O I N T POWER STATION, BUCHANAN, N E W YORK
[RFTA NO. 06-0011  
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011


==Dear Mr. Kottan:==
==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
The Oak k d g e Institute for Science and Education (ORISE) received set nine, which consisted of nine water samples received on August 15,2006 from the I n l a n Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous duection for h a n d h g 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.
: 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.
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.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
The remaining aliquot of each sample was adjusted to a pH of approximately 2 with concentrated HNO3.
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.
Mr. Jim Kottan January 4,2006 Distribution approval and concurrence
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.
: 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.
Mr. Jim Kottan                                                               January 4,2006 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.  
Sincerely, Dale Condra, Manager Laboratory RDC:WI:ar Enclosures cc:     B. Watson, NMSS/DWMEP/DD/SP 7E18                   E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23                   S. IOrk, ORISE M. Roberts, NRC Region I                           J. Whte, NRC Region I File 1697 Distribution approval and concurrence :    Initials Technical Management Team Member Oualitv Manager Voice: 865.241.3242                     Fax: 865.241.3248             E-mail: Dale.Condra@orau.org
"'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
TABLE 1 ORISE                   NRC Region I                       Collection            Collection Sample ID                     Sample ID                           Date                 Time 1697W0051"         I       Mw-50 6 7 ' E l
* 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.
I   8/1/2006         I     11:30 1697M0003b                  MW-50 67' El                       8/1/2006                 11:30 1697W0052                  MW-50 42' El                       8/1/2006                 11:15 I
bFe-55 analyzed using procedure AP13, Revision
                                                                    ~~
: 4. 'Ni-59/63 analyzed using procedure AP17, Revision
1697M0004                 MW-50 42' El 1697W0053          I       MW-49 25' El
: 0. dH-3 analyzed using procedure AP2, Revision 15.  
                          -       ~~
8/1/2006         I      9:50 1697W0055                  MW-49 42' El                       8/1/2006                 9:35 1697M0007                  MW-49 42' El                        8/ 1/2006                9:35 1697W0056                  MW-58 71' El                       8/2/2006                 9:31 1697M0008                  MW-58 71' El                       8/2/2006                 9:31 1697W0057                      MW-38                         8/7/2006                 13:23 1697M0009                      MW-38                         8/7/2006                 13:23 1697W0058                Discharge Canal                       8/7/2006                 13:50 1697M0010                Discharge Canal                       8/7/2006                 13:50 1697W0059                        MW-40                        8/9/2006                 10:35 1697M0011                        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 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                                                           :ntrationsa(1 Ci/L)
Sample ID                    Sample ID                       co-58                CO-GO              cs-134            cs-137 1697W0051                    MW-50 67'El                   -0.3 k 3.1b          0.7 k 2.8 0.6 2 2.9 2.0                      t 2.5 1697W0052                    MW-50 42'El                   1.3 k 2.3            2.1 k 2.1 -0.3 4 2.1 -2.6 5 4.5 1697W0053                    MW-49 25' El                 -0.7 k 1.8            0.6 k 1.6 -0.1 k 1.7 0.2 k 1.6 1697W0054                    MW-49 65'El                   1.1 4 2.3            0.9 k 2.3 3.2 & 2.3 0.5 ? 2.1 1697W0055                    MW-49 42'El                  -1.4 k 2.4           0.3 & 2.2            1.3 4 2.3 -2.1          t 4.5
* 2.2
            ~~
1697W0056                    MW-58 71'El                   -0.1 & 2.5           3.0     k 2.3 2.1                    1.1 -t 2.1 1697W0057                        MW-38                   -0.9   t 2.5 -0.5 k 2.8 0.2 4 2.4 1 3.8 & 2.3 1697W0058                  Discharge Canal                -2.0 4 2.3 -1.4 2 2.4 0.8 4 2.4 1.3 t 1.5 1697W0059                        MW-40                    -1.5 4 1.7 0.4 t 1.7 1.0 4 1.7 -0.6 & 1.9 T h e 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.
In&an oint Power Station                                                                            projects/l697/Data Tables/2007-01-04 Data Tablcs Set Nine
 
TABLE 3 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 1                     Radionuclide Concentrations, Sample ID                Sample ID                        TPUs, and MDCS"(pCi/L) 1697W0051                MW-50 67' El                    30.0        k        1.7b              (0.81 1697W0052 1697W0053                MW-49 25' El                I    11.7        f        1.o              (0.8) 1697W0054                MW-49 65' El                 I    16.3        &        1.2 1697W0055                MW-49 42' El                      19.7        k        1.4              (0.8) 1697W0056                MW-58 71' El                    0.65        k        0.51              (0.82) 1697W0057                    MW-38                       0.37        2        0.45              (0.76) 1697W0058              Discharge Canal                  0.20        k       0.45              (0.78) 1697W0059                    MW-40                        1.2         k         1.1               (1.9)
                                                              ~~~~    ~~~~~~~            ~
                  "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 P O I N T POWER STATION BUCHANAN, N E W 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.
'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)
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
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 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) 1697W0051                        MW-50 67' El                     -3.9     + 9.1b           (15.8) 11     1697W0052               I       MW-50 4 2 ' E l              I     0.1     &     9.2       (15.8)   11 I11    1697W0053 1697W0054 1697W0055              I MW-49 25' El MW-49 65' E1 MW-49 42'El                  I
~ 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  
                                                                                                    -6.3
@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
                                                                                                    -8.5
'Zero values are due to rounding.
                                                                                                    -8.6 k
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)
k
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}}
                                                                                                              &
9.0 9.0 9.0 (15.8)
(15.8)
(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 M U G 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
 
TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N 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 ORISE          NRC Region I                Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or DCi/L for water)
Sample ID        Sample ID              Am-241                   Cm-242                 Cm-243/244                  Np-237 1697W0051       MW-50 67' El     0.02  t  0.08b (0.14)   0.01 t 0.04  (0.07)   0.02  f 0.06    (0.11) -0.12 ?      0.08  10.20) 1697M0003        MW-50 67' El      -0.01 t 0.01   (0.03)   0.00' t 0.0'1  (0.02)   0.00  t    0.01  (0.02) -0.05 t     0.02 (0.06) 1697W0052        Mw-50 42' El      0.03 t 0.09  (0.16)   -0.02 t   0.06  (0.13) -0.02 t    0.07 (0.15) -0.01   k    0.02 (0.07) 1697M0004        Mw-50 42' El      0.00 t 0.01  (0.02)   0.00 t   0.01  (0.01)   0.00  t   0.01  (0.02)   -0.02 t 0.02    (0.04) 1697W0053        MW-49 25' El      0.08 t 0.08  (0.13)   0.03 t   0.03 (0.05)   0.01  t   0.06 (0.12) -0.05 t 0.06        (0.15) 1697M0005        MW-49 25' El      0.01 t 0.01  (0.02)   0.00 t  0.01 (0.02)   0.00  t   0.01 (0.01) -0.01 t 0.02        (0.05) 1697W0054        Mw-49 65' El      0.10 5  0.10  (0.15)   0.02  t  0.02  (0.02)   0.05  t    0.07  (0.12)  0.01  ?    0.02 (0.03) 1697M0006  I    MW-49 65' El      -0.01 t 0.02   (0.05)   0.00 t   0.01 (0.03) -0.02  t   0.02  (0.04)   0.00 t     0.00 (0.01) 1697W0055  I    Mw-49 42' El      0.06 t 0.11    (0.18)   -0.01 t   0.05  (0.10)   0.00  t   0.08 (0.15) -0.14 t       0.10 (0.24) 1697M0007  I    Mw-49 42' El      0.00 t 0.01    (0.03)   0.00 5 0.01   (0.01)   0.00 k 0.01 (0.02) -0.01 t           0.01 (0.03) 1697W0056  I    MW-58 71' El      -0.02 ? 0.07    (0.15)   -0.01 t  0.04  (0.09) -0.08 ? 0.08 (0.18) -0.07 t           0.06 (0.14) 1697Mo008  I    MW-5871'El      I -0.01 ?  0.02   (0.04) 0.00 t      0.01  (0.01) -0.01 t 0.01 (0.03) 0.00 ?            0.00 (0.01) 1697W0057  I      MW-38        I 0.06  5  0.07  (0.12) I 0.03 t   0.04  (0.07)   0.00 t 0.00 (0.13) -0.08 t           0.06 (0.15) 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) -0.01 t            0.02 (0.05)
I 0.03 t 0.03 (0.02) 0.00 t             0.02 (0.05) 1 0.00  ?    0.01        1 (0.03) -0.03 ?      0.02 (0.04) 1
-
~~
1697W0059
      ~~~~
            ~ I ~~
Mu-40        I  0.02 ?  0.08  (0.15) I -0.02 k 0.02   (0.07)   0.00                   I t 0.06 (0.12) -0.13 k          0.09 (0.20) 1 1697M0011          Mu-40          0.00 t 0.02   (0.04)   0.00 2 0.01 (0.02)     0.01  ?    0.02        I (0.03) -0.01   k     0.01 (0.03'1 1
 
TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N 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( i/L for water)
Sample ID                       Sample ID                               Pu-238                     Pu-239/240               U-234                       U-238 0.05    2 0.07        (0.12)  -0.02 f 0.07    (0.15) 0.71  k    0.15  (0.02)  0.42   rt  0.12  (0.09) 0.00    k 0.02        (0.05)  0.01  k 0.02   (0.03) 0.01  k 0.01 (0.01) 0.02 k           0.01  (0.02) 1697W0052                    Mw-50 42' El                      0.05     ? 0.08         (0.13)   0.04 k 0.04 (0.03)   0.44 ?   0.13 (0.06)   0.21  k   0.09  (0.09) 1      1697M0004              I    MW-50 42'El                      0.00    k      0.01   (0.03)   0.00 ? 0.01   (0.03) 0.72 &   0.09 (0.02)   1.09  ?    0.13  (0.01) 1      1697W0053              I    MW-4925'El                      -0.04 2          0.08    (0.18)  0.01 ? 0.05   (0.10) 1.07 ?   0.19 (0.08)   0.62  k   0.14  (0.02) 11    1697M0005              I    MW-4925'El                        0.00     k 0.02        (0.04)  0.00  k 0.01   (0.03) 0.32 f 0.05 (0.02) 0.28 ?           0.05  (0.02) 1      1697W0054              I    MW-4965'El                        0.05    ? 0.07        (0.11)  0.00 f 0;04 (0.09)   1.76 5   0.26 (0.06)   0.83  k    0.17  (0.02) 1      1697M0006              I    Mw-49 65'El                      0.01    f 0.02        (0.03)  0.01 f 0.01 (0.02)     0.04 ?   0.02 (0.01)   0.04  f   0.02  (0.01) 11    1697W0055              I    Mw-49 42'El                      0.03    f 0.09        (0.16'1 -0.01 2 0.06     (0.14) 2.10 k 0.31 (0.11) 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)
  "The %DCs are in parentheses.
bUncertaintiesrepresent the 95% confidence level, based on total propagated uncertainties
  'Zero values are due to rounding.
 
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED A N D 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 I N 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}}

Revision as of 07:41, 23 November 2019

Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No.06-001)
ML070940618
Person / Time
Site: Indian Point Entergy icon.png
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)
v • d • e


Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 4,2007 Mr. Jim Kottan U S . Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406

SUBJECT:

FINAL L E T T E R REPORT F O R REQUESTED ANALYSES O F NINE WATER SAMPLES, SET NINE, FROM THE INDIAN P O I N T POWER STATION, BUCHANAN, N E W YORK

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

Dear Mr. Kottan:

The Oak k d g e Institute for Science and Education (ORISE) received set nine, which consisted of nine water samples received on August 15,2006 from the I n l a n Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous duection for h a n d h g 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.

ORISEs 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 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:WI:ar Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 S. IOrk, ORISE M. Roberts, NRC Region I J. Whte, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Oualitv Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org

TABLE 1 ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 1697W0051" I Mw-50 6 7 ' E l

~ ~~

I 8/1/2006 I 11:30 1697M0003b MW-50 67' El 8/1/2006 11:30 1697W0052 MW-50 42' El 8/1/2006 11:15 I

~~

1697M0004 MW-50 42' El 1697W0053 I MW-49 25' El

- ~~

8/1/2006 I 9:50 1697W0055 MW-49 42' El 8/1/2006 9:35 1697M0007 MW-49 42' El 8/ 1/2006 9:35 1697W0056 MW-58 71' El 8/2/2006 9:31 1697M0008 MW-58 71' El 8/2/2006 9:31 1697W0057 MW-38 8/7/2006 13:23 1697M0009 MW-38 8/7/2006 13:23 1697W0058 Discharge Canal 8/7/2006 13:50 1697M0010 Discharge Canal 8/7/2006 13:50 1697W0059 MW-40 8/9/2006 10:35 1697M0011 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 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 :ntrationsa(1 Ci/L)

Sample ID Sample ID co-58 CO-GO cs-134 cs-137 1697W0051 MW-50 67'El -0.3 k 3.1b 0.7 k 2.8 0.6 2 2.9 2.0 t 2.5 1697W0052 MW-50 42'El 1.3 k 2.3 2.1 k 2.1 -0.3 4 2.1 -2.6 5 4.5 1697W0053 MW-49 25' El -0.7 k 1.8 0.6 k 1.6 -0.1 k 1.7 0.2 k 1.6 1697W0054 MW-49 65'El 1.1 4 2.3 0.9 k 2.3 3.2 & 2.3 0.5 ? 2.1 1697W0055 MW-49 42'El -1.4 k 2.4 0.3 & 2.2 1.3 4 2.3 -2.1 t 4.5

  • 2.2

~~

1697W0056 MW-58 71'El -0.1 & 2.5 3.0 k 2.3 2.1 1.1 -t 2.1 1697W0057 MW-38 -0.9 t 2.5 -0.5 k 2.8 0.2 4 2.4 1 3.8 & 2.3 1697W0058 Discharge Canal -2.0 4 2.3 -1.4 2 2.4 0.8 4 2.4 1.3 t 1.5 1697W0059 MW-40 -1.5 4 1.7 0.4 t 1.7 1.0 4 1.7 -0.6 & 1.9 T h e 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.

In&an oint Power Station projects/l697/Data Tables/2007-01-04 Data Tablcs Set Nine

TABLE 3 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 1 Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697W0051 MW-50 67' El 30.0 k 1.7b (0.81 1697W0052 1697W0053 MW-49 25' El I 11.7 f 1.o (0.8) 1697W0054 MW-49 65' El I 16.3 & 1.2 1697W0055 MW-49 42' El 19.7 k 1.4 (0.8) 1697W0056 MW-58 71' El 0.65 k 0.51 (0.82) 1697W0057 MW-38 0.37 2 0.45 (0.76) 1697W0058 Discharge Canal 0.20 k 0.45 (0.78) 1697W0059 MW-40 1.2 k 1.1 (1.9)

~~~~ ~~~~~~~ ~

"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 P O I N T POWER STATION BUCHANAN, N E W 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 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) 1697W0051 MW-50 67' El -3.9 + 9.1b (15.8) 11 1697W0052 I MW-50 4 2 ' E l I 0.1 & 9.2 (15.8) 11 I11 1697W0053 1697W0054 1697W0055 I MW-49 25' El MW-49 65' E1 MW-49 42'El I

-6.3

-8.5

-8.6 k

k

&

9.0 9.0 9.0 (15.8)

(15.8)

(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 M U G 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

TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N 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 ORISE NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or DCi/L for water)

Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0051 MW-50 67' El 0.02 t 0.08b (0.14) 0.01 t 0.04 (0.07) 0.02 f 0.06 (0.11) -0.12 ? 0.08 10.20) 1697M0003 MW-50 67' El -0.01 t 0.01 (0.03) 0.00' t 0.0'1 (0.02) 0.00 t 0.01 (0.02) -0.05 t 0.02 (0.06) 1697W0052 Mw-50 42' El 0.03 t 0.09 (0.16) -0.02 t 0.06 (0.13) -0.02 t 0.07 (0.15) -0.01 k 0.02 (0.07) 1697M0004 Mw-50 42' El 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.01) 0.00 t 0.01 (0.02) -0.02 t 0.02 (0.04) 1697W0053 MW-49 25' El 0.08 t 0.08 (0.13) 0.03 t 0.03 (0.05) 0.01 t 0.06 (0.12) -0.05 t 0.06 (0.15) 1697M0005 MW-49 25' El 0.01 t 0.01 (0.02) 0.00 t 0.01 (0.02) 0.00 t 0.01 (0.01) -0.01 t 0.02 (0.05) 1697W0054 Mw-49 65' El 0.10 5 0.10 (0.15) 0.02 t 0.02 (0.02) 0.05 t 0.07 (0.12) 0.01  ? 0.02 (0.03) 1697M0006 I MW-49 65' El -0.01 t 0.02 (0.05) 0.00 t 0.01 (0.03) -0.02 t 0.02 (0.04) 0.00 t 0.00 (0.01) 1697W0055 I Mw-49 42' El 0.06 t 0.11 (0.18) -0.01 t 0.05 (0.10) 0.00 t 0.08 (0.15) -0.14 t 0.10 (0.24) 1697M0007 I Mw-49 42' El 0.00 t 0.01 (0.03) 0.00 5 0.01 (0.01) 0.00 k 0.01 (0.02) -0.01 t 0.01 (0.03) 1697W0056 I MW-58 71' El -0.02 ? 0.07 (0.15) -0.01 t 0.04 (0.09) -0.08 ? 0.08 (0.18) -0.07 t 0.06 (0.14) 1697Mo008 I MW-5871'El I -0.01 ? 0.02 (0.04) 0.00 t 0.01 (0.01) -0.01 t 0.01 (0.03) 0.00 ? 0.00 (0.01) 1697W0057 I MW-38 I 0.06 5 0.07 (0.12) I 0.03 t 0.04 (0.07) 0.00 t 0.00 (0.13) -0.08 t 0.06 (0.15) 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) -0.01 t 0.02 (0.05)

I 0.03 t 0.03 (0.02) 0.00 t 0.02 (0.05) 1 0.00  ? 0.01 1 (0.03) -0.03 ? 0.02 (0.04) 1

-

~~

1697W0059

~~~~

~ I ~~

Mu-40 I 0.02 ? 0.08 (0.15) I -0.02 k 0.02 (0.07) 0.00 I t 0.06 (0.12) -0.13 k 0.09 (0.20) 1 1697M0011 Mu-40 0.00 t 0.02 (0.04) 0.00 2 0.01 (0.02) 0.01  ? 0.02 I (0.03) -0.01 k 0.01 (0.03'1 1

TABLE 6 (Continued)

CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N 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( i/L for water)

Sample ID Sample ID Pu-238 Pu-239/240 U-234 U-238 0.05 2 0.07 (0.12) -0.02 f 0.07 (0.15) 0.71 k 0.15 (0.02) 0.42 rt 0.12 (0.09) 0.00 k 0.02 (0.05) 0.01 k 0.02 (0.03) 0.01 k 0.01 (0.01) 0.02 k 0.01 (0.02) 1697W0052 Mw-50 42' El 0.05  ? 0.08 (0.13) 0.04 k 0.04 (0.03) 0.44  ? 0.13 (0.06) 0.21 k 0.09 (0.09) 1 1697M0004 I MW-50 42'El 0.00 k 0.01 (0.03) 0.00  ? 0.01 (0.03) 0.72 & 0.09 (0.02) 1.09  ? 0.13 (0.01) 1 1697W0053 I MW-4925'El -0.04 2 0.08 (0.18) 0.01  ? 0.05 (0.10) 1.07  ? 0.19 (0.08) 0.62 k 0.14 (0.02) 11 1697M0005 I MW-4925'El 0.00 k 0.02 (0.04) 0.00 k 0.01 (0.03) 0.32 f 0.05 (0.02) 0.28 ? 0.05 (0.02) 1 1697W0054 I MW-4965'El 0.05  ? 0.07 (0.11) 0.00 f 0;04 (0.09) 1.76 5 0.26 (0.06) 0.83 k 0.17 (0.02) 1 1697M0006 I Mw-49 65'El 0.01 f 0.02 (0.03) 0.01 f 0.01 (0.02) 0.04  ? 0.02 (0.01) 0.04 f 0.02 (0.01) 11 1697W0055 I Mw-49 42'El 0.03 f 0.09 (0.16'1 -0.01 2 0.06 (0.14) 2.10 k 0.31 (0.11) 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)

"The %DCs are in parentheses.

bUncertaintiesrepresent the 95% confidence level, based on total propagated uncertainties

'Zero values are due to rounding.

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED A N D 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 I N 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

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