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{{#Wiki_filter:I OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 12,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 WBJECT: REVISED FINAL 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
{{#Wiki_filter:I OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 12,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 WBJECT:         REVISED FINAL REPORT FOR REQUESTED ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[RFTA NO. 06-0011 >ear Mr. Kottan: The Oak Ridge Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the Indian Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for handhg samples from this fachty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Radiological and Environmental Sciences Laboratory.
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
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-59/63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through Table 8, respectively.
>ear Mr. Kottan:
The pertinent procedure references are provided in each specific table.
The Oak Ridge Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the Indian Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for h a n d h g samples from this fachty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Radiological 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-59/63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through Table 8, respectively. The pertinent procedure references are provided in each specific table.
ORISE's Quality Control (QC) requirements were met for these analyses.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
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 filter papers. An aliquot was removed for tritium and carbon-14 before acidification.
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 filter papers. An aliquot was removed for tritium and carbon-14 before acidification. 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 analyzeq the filtered solid portion of each sample for all the requested alpha isotopes. The remaining a%uot of each sample was adjusted to a pH of approximately2 with concentrated HNOs.                     T 3 m
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.
                                                                                        ,;3m
ORISE analyzeq the filtered solid portion of each sample for all the requested alpha isotopes.
                                                                                    -
The remaining a%uot of each sample was adjusted to a pH of approximately 2 with concentrated HNOs. T3m ,;3m - 030 --?E Lh MK Jim Kottan April 12,2007 Distribution approval and concurrence
Lh 0 3 0
: Technical Management Team Member Quality Manager In the oripal report the date of the letter was incorrectly reported as January 26,2006. The date has been corrected and I apologize for any inconvenience this incorrect date may have caused.
                                                                                        --?E
Initials , K, My contact information is listed below.
You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures c: T. Carter, NRC/FSME/DWMEP 7518 E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Regon I File 1697 S. IGk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org TABLE 1 ORISE Sample ID 1697WO07Oa 1 697M0033b SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time MW-42@41 9/18/2006 14:45 MW-42@41 9/18/2006 14:45 ~ ~__________
1697M0035 1697W0073 1697M0036 1697W0074 1697W0071 I MW-42@43 I 9/18/2006 I 13:OO MW-42@46 9/15/2006 12:45 MW-42@48 9/15/2006 11:20 MW-42@48 9/15/2006 11 :20 MW-59@70 9/15/2006 10:20 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO 1697M0038 1697W0076 1697M0039 1697W0077 1697M0040 1697W0072 1- MW-42@46 I 9/15/2006 I 12:45 ~ ~~~ LAF-001-(003) 9/19/2006 15:49 LAF-002-(003) 9/ 19/2006 13:41 LAF-002-(003) 9/19/2006 13:41 LAF-003-(003) 9/19/2006 11:08 LAF-003-(003) 9/19/2006 11:08 1697M0037 I MW-59@70 I 9/15/2006 I 10:20 1697W0075 r LAF-001-(003)
I 9/19/2006 I 15:49 The Win the ORISE sample identification represents a water matrix.
'The M in the ORISE sample identification represents the filtercd fraction of the preceding water sample Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14 TABLE 2 ORISE Sample ID 1697~0070 1697W0071 1697W0072


1697~0073 1697W0074 1697WOO75 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrationsa'b (pCi/L)
M KJim Kottan                                                                      April 12,2007 In the o r i p a l report the date of the letter was incorrectly reported as January 26,2006. The date has been corrected and I apologize for any inconvenience this incorrect date may have caused.
Sample ID CO-58 CO-60 cs-134 cs-137 MW-42041 3 rt 11" 4 k 13 6.5 If: 9.3 13,730 k 470 MW-42043 -12 k 12 3 ? 12 6.0 k 9.2 15,140 k 510 MW-42046 -1.7 k 7.7 11.7 f. 9.9 2.4 k 7.8 20,260 k 650 MW-42048 6 k 13 15 k 11 1 k 11 21,650 k 750 MW-59@70 0.1 k 3.0 0.3 f. 4.1 1.3 k 2.7 -3.8 k 4.1 LAF-001-(003) 1.2 k 2.8 3.8 k 2.9 -0.5 ? 2.4 1.2 k 2.1 1697W0076 I LAF-002-(003)
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
I -2.4 k 3.0 I 2.2 k 4.6 I 0.7 f. 2.6 I 0.5 k 2.2 11 1697W0077 I LAF-003-(003) 1 -1.7 k 2.0 I 0.7 k 1.61 -0.8 k 1.71 -0.7 2 1.6 1 "The range of MDCs for the selected radionuclides for samples WOO70-WOO73 is 13 pCi/L to 37 pCi/L.
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures c:      T. Carter, NRC/FSME/DWMEP 7518                              E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN 8A23                          S. IGk, ORISE M. Roberts, NRC Regon I                                    J. White, NRC Region I File 1697 Distribution approval and concurrence :          Initials ,
bThe range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.9 pCi/L to 5.0 pCi/L 'Uncertainties represent the 95% confidence level, based on total propagated uncertainties. Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14 TABLE 3 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 "The MDCs for each radionuclide are in parentheses
Technical Management Team Member Quality Manager K,
'Fe-55 analyzed using procedure AP13, Revision 4 'Ni-59/63 analyzed using procedure AP17, Revision
Voice: 865.241.3242                    Fax: 865.241.3248              E-mail: Dale.Condra@orau.org
: 0. dH-3 analyzed usmg procedure AP2, Revision 15 eUncertmnhes represent the 95% confidence level, based on total propagated uncertmnhes. Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tablcs Set 14 TABLE 4 ORISE Sample ID 1697W0070 1697W0071 1697W0072 1697W0073 1697W0074 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 @Ci/L) MW-42@4 1 4 k 18b (31) MW-42@43 8 2 18 (31) MW-42@46 -1 f 18 (31) MW-42@48 5 -t- 18 (31) MW-59@70 -4.7 f 8.9 (15.6) 1697W0075 1697W0076 1697W0077 LAF-00 1-603) -2.7 ? 9.0 (15.6) LAF-002-(003)
 
-0.5 f 9.1 (15.6) LAF-003 -(003) 2.8 k 9.1 (15.6) Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14 TABLE 5 ORISE Sample ID 1697W0070 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 MW-42@41 20.2 f 2.Ob (2.3) TPUs, and MDCS" @Ci/L) 1697W0072 1697W0073 1697W0074 1697W0075 1697W0076
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        I          MW-42@43                    I  9/18/2006          I      13:OO 1697M0034        I          MW-42@43                    I  9/18/2006          I      13:OO
~~ 1697W0071 I MW-42@43 I 15.7 5 1.7 (1.9) MW-42@46 32.8 f 2.4 (2.2) MW-42@48 35.0 f 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 f 0.55 (0.871 1697W0077 I LAF-003-(003)
                            ~
I -0.17 k 0.45 (0.83) 'MDCs are in parentheses buncertainties represent the 95% confidence level, based on total propagated uncertainties. Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14 3 8 m d w w Frl 3 z 2 s: m H - z 9 e N 8 +I w 8 - G w e m 8 +I 3 8 : 8 8 - 65 W +I r- - fl u) '1 e m 8 8 8 +I r- - m E M r- 0 s r- m W 3 - - - G 9 e N 8 +I w 9 0 G 9 e - N 8 +I 3 7 _I 6 9 ? w 8 8 : +I 0 - 5i hl 8 +I 3 - m 3 N 5 -
1697W0072
* m 0 0 r- m W E 3 - - - c 9 e 0 5 d- 0 8 +I N 0 8 - Gi 9 e N 8 +I w 7 - i;j 9 e l-4 8 8 2 8 8 8 +I 0 - GF hl +I 0 - 00 E W m 0 0 r- m W E 3 - - G 9 e 0 u) 0 8 +I N 0 8 2 8 - G N +I l-4 7 2 8 8 - 5 M +I 3 - 66 9 e N 8 8 +I N - G- 0, 9 O w 0 3 - 00 m 0 3 r- m 2 - - G 2 8 d- +I 0 8 2 8 - 5; m +I 0 8 - s 9 e m 8 8 : 8 7 +I 0 - 6 u) +I hl - 3 e 0 0 01 0 3 - W r- 0 s r- m W 3 - sg '1 90 00 99 33 i;I- mm 3w Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14 TABLE 6 (Continued)
                              ~__________
ORISE Sample ID 1697W0070 1697M0033 1697W0071 16971110034 F E: B NRC Region I Radionuclide Sample ID Pu-238 m-426341 0.08 f 0.09 (0.15) m-42@41 0.00 k 0.02 (0.04) m-426343 0.06 k 0.13 (0.23) m-42@43 0.02 fc 0.02 (0.03'1 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 P~-239/240 0.03 f 0.04 (0.07) 0.01 f 0.01 (0.01) 0.01 ? 0.04 (0.09) F P. 3 U-234 U-238 1.47 k 0.26 (0.10) 1.27 k 0.24 (0.07) 0.01 k 0.01 (0.02) 0.01 k 0.01 (0.02) 1.93 k 0.29 (0.03) 1.72 k 0.27 (0.03) 1697W0072 16971110035 m-42@46 0.11 f 0.08 (0.12) 0.01 f 0.03 (0.07) 1.87 k 0.30 (0.10) 1.70 k 0.28 (0.07) m-42@46 0.01 fc 0.02 (0.04) 0.01 k 0.01 (0.02) 0.02 k 0.01 (0.01) 0.02 k 0.01 (0.01) 0.01 k 0.01 (0.02)
1-          MW-42@46                    I 9/15/2006          I     12:45 1697M0035                    MW-42@46                        9/15/2006                12:45 1697W0073                    MW-42@48                      9/15/2006                  11:20 1697M0036                    MW-42@48                      9/15/2006                  11:20 1697W0074                    MW-59@70                        9/15/2006                10:20 1697M0037        I         MW-59@70                    I  9/15/2006          I      10:20 1697W0075        r      LAF-001-(003)
I 0.01 k 0.01 (0.01)
                                                          ~  ~~~
I 0.01 f 0.01 (0.01) 1697W0073 1697M0036 1697W0074 m-42@48 -0.01 k 0.07 (0.15) 0.03 k 0.06 (0.11) 2.10 fc 0.30 (0.06) 1.74 k 0.26 (0.06) m-42@48 0.00 fc 0.02 (0.03) 0.01 k 0.01 (0.01) 0.03 k 0.02 (0.02) 0.04 k 0.02 (0.01) m-59@70 0.04 fc 0.03 (0.04) 0.04 k 0.03 (0.02) 0.54 k 0.10 (0.07) 0.48 k 0.09 (0.05) 1697M0037 1697w0075 l697M0038 1697w0076 m-59@70 0.00 f 0.02 (0.03) 0.01 k 0.01 (0.02) 0.01 f 0.01 (0.02) 0.03 f 0.02 (0.01) mF-0O1-(003) 0.01 k 0.03 (0.05) 0.03 k 0.02 (0.02) 0.67 k 0.10 (0.02) 0.73 k 0.11 (0.02) mF-001-(003) 0.01 f 0.02 (0.03) 0.01 f 0.02 (0.02) 0.00 k 0.01 (0.02) 0.00 k 0.01 (0.01) mF-0O2-(003) 0.04 f 0.05 (0.09) 0.03 k 0.03 (0.04) 26.3 f 2.1 (0.1) 17.1 k 1.4 (0.1) 16971110039 I uF-002-(003)
I  9/19/2006          I      15:49 1697M0038                LAF-001-(003)                      9/19/2006                15:49 1697W0076                LAF-002-(003)                      9/ 19/2006                13:41 1697M0039                LAF-002-(003)                      9/19/2006                13:41 1697W0077                LAF-003-(003)                      9/19/2006                11:08 1697M0040                LAF-003-(003)                      9/19/2006                11:08 T h e Win the ORISE sample identification represents a water matrix.
I 0.01 f 0.02 (0.03) I 0.02 k 0.01 (0.01) I 0.05 k 0.02 (0.01) I 0.03 fc 0.01 (0.01) 1~97woo77 1697M0040 ~ ~~ ~~~ ~~~~ ~F-003-(003) 0.03 k 0.03 (0.04) 0.00 f 0.02 (0.04) 0.56 k 0.12 (0.09) 0.48 f 0.10 (0.03) uF-003-(003) 0.02 fc 0.02 (0.03) 0.02 fc 0.01 (0.02) 0.01 f 0.01 (0.02) 0.01 fc 0.01 (0.01) 3 The MDC~ are in parentheses.
                        'The M in the ORISE sample identification represents the filtercd fraction of the preceding water sample Indian Point Power Station                                                                          projects/l697/Data Tables/2007-04-12 Data Tables Set 14
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
 
Zero values are due to rounding. dSignificat figures expanded to avoid reporting a TPU of zero at the request of the inspector, cn 3 +c TABLE 7 ORISE Sample ID 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 Radionuclide Concentrationsa
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE                    NRC Region I                             Radionuclide Concentrationsa'b(pCi/L)
@Ci/g of sediment in 100 mL or pCi/L for water) NRC Region I Sample ID 1697W0070 1697M0033 1697W0071 M%'-42@41
Sample ID                      Sample ID                        CO-58                CO-60          cs-134              cs-137 1697~0070                    MW-42041                        3    rt 11"          4   k 13 6.5 If:          9.3 13,730        k    470 1697W0071                      MW-42043                    -12 k 12              3    ? 12 6.0 k            9.2 15,140 k          510 1697W0072                      MW-42046                    -1.7   k 7.7 11.7          f. 9.9 2.4 k          7.8 20,260 k          650 1697~0073                      MW-42048                      6    k 13          15    k 11 1 k              11 21,650 k            750 1697W0074                      MW-59@70                    0.1 k 3.0            0.3    f. 4.1 1.3 k          2.7 -3.8 k            4.1 1697WOO75                    LAF-001-(003)                 1.2 k 2.8           3.8    k 2.9 -0.5 ?          2.4      1.2 k        2.1 1697W0076              I    LAF-002-(003)              I -2.4    k 3.0 2.2 I        k 4.6 I 0.7 f.       2.6 I 0.5 k            2.2  1 1697W0077              I    LAF-003-(003)               1 -1.7    k 2.0 0.7  I        k 1.61 -0.8 k         1.71 -0.7 2            1.6 1 "The range of MDCs for the selected radionuclides for samples WOO70-WOO73 is 13 pCi/L to 37 pCi/L.
-3 k 1 7b (29) MW-42@41 -0.2 1 3.4 (5.9) MW-42@43 -8 1 16 (28) 1697M0034 1697W0072 1697M0035 1697W0073
bThe range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.9 pCi/L to 5.0 pCi/L
~~ 11 1697M0036 I MW-42@48 I -0.6 & 3.5 (6.0) MW-42@43 -0.6 k 3.7 (6.4) MW-42@46 -10 k 16 (27) MW-42@46 -2.5 k 3.5 (6.1) MW-42@48 -10 k 15 (27) 11 1697W0074 I MW-59@70 I -2.5 k 9.3 (1 6.1) 1697M0037 1697W0075 1697M0038 MW-59@70 -0.9 k 3.4 (5.9) LAF-001-(003)  
    'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
-2.7 1 7.9 (13.7) LAF-001-(003) 1.1 1 3.5 (6.0) 1697W0076 1697M0039 1697W0077 1697M0040 Indian Point Power Station LAF-002-(003)  
Indian Point Power Station                                                                         projects/l697/Data Tables/2007-04-12 Data Tables Set 14
-6.4 ? 7.8 (13.6) LAF-002-(003) 1.4 & 3.6 (6.1) LAF-003-(003)  
 
-2.5 k 8.2 (14.2) LAF-003-(003) 2.6 k 3.5 (5.9) projects/l697/Data Tables/2007-04-12 Data Tables Set 14 TABLE 8 ORISE NRC Region I Sample ID Sample ID 1697W0070 MW-42@41 1697W0071 MW-42@43 1697W0072 Mw-42@46 1697W0073 Mw-42@48 Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) 0.8 k 9.7b (16.4) 8.8 k 9.8 (1 6.4) 0.2 - + 9.6 (16.4) -0.6 f. 9.6 (1 6.4) 1697W0075 1697~0076 1697~0077 Indian Point Power Station LAF-001-(003) 0.5 k 9.7 (1 6.4) LAF-002-(003) 1.4 f. 9.7 (1 6.4) LAF-003-(003) 8.3 k 9.8 (16.4) projects/l697/Data Tables/2007-04-12 Data Tables Set 14}}
TABLE 3 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 "The MDCs for each radionuclide are in parentheses
'Fe-55 analyzed using procedure AP13, Revision 4
'Ni-59/63 analyzed using procedure AP17, Revision 0.
dH-3 analyzed usmg procedure AP2, Revision 15 eUncertmnhes represent the 95% confidence level, based on total propagated uncertmnhes.
Indian Point Power Station                                                  projects/l697/Data Tables/2007-04-12 Data Tablcs Set 14
 
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              @Ci/L) 1697W0070        MW-42@4 1        4    k 18b            (31) 1697W0071        MW-42@43          8    2      18        (31) 1697W0072        MW-42@46        -1    f      18        (31) 1697W0073        MW-42@48          5    -t-     18      (31) 1697W0074        MW-59@70        -4.7    f      8.9     (15.6) 1697W0075      LAF-00 1-603)    -2.7    ?      9.0     (15.6) 1697W0076      LAF-002-(003)    -0.5    f 9.1          (15.6) 1697W0077      LAF-003-(003)     2.8   k 9.1          (15.6)
Indian Point Power Station                                      projects/l697/Data Tables/2007-04-12 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"@Ci/L) 1697W0070                      MW-42@41                            20.2        f      2.Ob            (2.3)
                                                                                      ~~
1697W0071              I      MW-42@43                    I        15.7      5        1.7            (1.9) 1697W0072                      MW-42@46                            32.8        f       2.4            (2.2) 1697W0073                      MW-42@48                            35.0       f        2.3            (2.0) 1697W0074                      MW-59@70                            0.14        k       0.50            (0.89) 1697W0075                    LAF-001-(003)                        0.10        k      0.52            (0.93) 1697W0076                    LAF-002-(003)                        0.97        f      0.55            (0.871 1697W0077              I    LAF-003-(003)                 I      -0.17      k      0.45            (0.83)
                'MDCs are in parentheses buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station                                                                        projects/l697/Data Tables/2007-04-12 Data Tables Set 14
 
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Indian Point Power Station              projects/l697/Data Tables/2007-04-12 Data Tables Set 14
 
TABLE 6 (Continued)
F E:
B                                                                                      CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES F                                                                                      AP11, REVISION 3; CP2, REVISION 12 P.
3                                                                                        INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE                  NRC Region I                                  Radionuclide Sample ID                    Sample ID                              Pu-238                        P~-239/240              U-234                  U-238 1697W0070                  m-426341                  0.08      f 0.09 (0.15)             0.03  f 0.04 (0.07) 1.47 k 0.26    (0.10)   1.27 k   0.24 (0.07) 1697M0033                  m-42@41                    0.00 k 0.02 (0.04)                   0.01 f 0.01 (0.01) 0.01 k 0.01     (0.02)   0.01 k    0.01 (0.02) 1697W0071                  m-426343                  0.06 k 0.13 (0.23)                   0.01 ? 0.04 (0.09) 1.93 k 0.29      (0.03)   1.72 k   0.27 (0.03) 16971110034                m-42@43                    0.02      fc 0.02         (0.031  0.01 k 0.01 (0.02) I 0.01 k 0.01   (0.01) I 0.01 f    0.01 (0.01) 1697W0072                  m-42@46                    0.11 f 0.08                (0.12)   0.01 f 0.03 (0.07) 1.87 k 0.30      (0.10)  1.70 k   0.28 (0.07) 16971110035                m-42@46                    0.01       fc    0.02       (0.04)   0.01 k 0.01 (0.02) 0.02 k 0.01      (0.01)   0.02 k    0.01 (0.01) 1697W0073                  m-42@48                  -0.01      k     0.07      (0.15)   0.03 k 0.06 (0.11) 2.10 fc 0.30    (0.06)   1.74 k    0.26 (0.06) 1697M0036                  m-42@48                    0.00      fc   0.02       (0.03)   0.01 k 0.01 (0.01) 0.03 k 0.02      (0.02)   0.04 k    0.02 (0.01) 1697W0074                  m-59@70                  0.04        fc   0.03      (0.04)   0.04 k 0.03 (0.02) 0.54 k 0.10      (0.07)  0.48 k    0.09 (0.05) 1697M0037                  m-59@70                  0.00        f    0.02      (0.03)    0.01 k 0.01 (0.02) 0.01 f 0.01      (0.02)   0.03 f    0.02 (0.01) 1697w0075                mF-0O1-(003)               0.01        k    0.03      (0.05)   0.03 k 0.02 (0.02) 0.67 k 0.10      (0.02)   0.73 k   0.11 (0.02) l697M0038                mF-001-(003)                0.01        f    0.02      (0.03)   0.01 f 0.02 (0.02) 0.00 k 0.01      (0.02)   0.00 k   0.01 (0.01) 1697w0076                  mF-0O2-(003)                0.04 f            0.05      (0.09)    0.03 k 0.03 (0.04) 26.3 f 2.1        (0.1)   17.1 k    1.4  (0.1) 16971110039          I    uF-002-(003) I 0.01 f                        0.02      (0.03)  I 0.02 k 0.01 (0.01) I 0.05 k 0.02
                                                                                                                      ~ ~~  ~~~ ~~~~
(0.01) I 0.03 fc  0.01 (0.01) 1~97woo77                  ~ F - 0 0 3 - ( 0 0 3 ) 0.03 k               0.03      (0.04)   0.00 f 0.02 (0.04) 0.56 k 0.12      (0.09)   0.48 f    0.10 (0.03) 1697M0040                  uF-003-(003)                0.02        fc 0.02          (0.03)    0.02 fc 0.01 (0.02) 0.01 f 0.01    (0.02)   0.01 fc  0.01 (0.01) 3 cn    T h e M D C ~are in parentheses.
3
+   c buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Zero values are due to rounding.
dSignificat figures expanded to avoid reporting a TPU of zero at the request of the inspector,
 
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 NRC Region I      Radionuclide Concentrationsa ORISE Sample ID          Sample ID      @Ci/g of sediment in 100 mL or pCi/L for water) 1697W0070          M%'-42@41          -3    k        17b            (29) 1697M0033          MW-42@41          -0.2  1        3.4            (5.9) 1697W0071          MW-42@43          -8    1          16            (28) 1697M0034          MW-42@43          -0.6  k        3.7            (6.4) 1697W0072          MW-42@46          -10    k          16            (27) 1697M0035          MW-42@46          -2.5  k        3.5            (6.1) 1697W0073          MW-42@48          -10    k          15            (27)
                                    ~~
1      1697M0036  I      MW-42@48      I  -0.6  &        3.5            (6.0) 1    1697W0074  I      MW-59@70      I  -2.5  k        9.3            (16.1) 1697M0037          MW-59@70          -0.9  k        3.4            (5.9) 1697W0075          LAF-001-(003)      -2.7  1        7.9            (13.7) 1697M0038        LAF-001-(003)      1.1  1        3.5            (6.0) 1697W0076          LAF-002-(003)      -6.4  ?        7.8            (13.6) 1697M0039        LAF-002-(003)      1.4  &        3.6            (6.1) 1697W0077        LAF-003-(003)      -2.5  k        8.2            (14.2) 1697M0040        LAF-003-(003)      2.6    k        3.5            (5.9)
Indian Point Power Station                                      projects/l697/Data Tables/2007-04-12 Data Tables Set 14
 
TABLE 8 ORISE NRC Region I      Radionuclide Concentrations, Sample ID  Sample ID        TPUs, and MDCS"(pCi/L) 1697W0070  MW-42@41        0.8    k        9.7b          (16.4) 1697W0071  MW-42@43        8.8    k          9.8          (1 6.4) 1697W0072  Mw-42@46        0.2    +
                                                        -          9.6          (16.4) 1697W0073  Mw-42@48        -0.6  f.        9.6          (1 6.4) 1697W0075 LAF-001-(003)    0.5    k          9.7          (1 6.4) 1697~0076 LAF-002-(003)     1.4   f.         9.7           (1 6.4) 1697~0077 LAF-003-(003)     8.3   k         9.8           (16.4)
Indian Point Power Station                            projects/l697/Data Tables/2007-04-12 Data Tables Set 14}}

Revision as of 04:42, 23 November 2019

Orise Revised Final Report for Requested Analyses of Eight Water Samples, Set Fourteen, from the Indian Point Power Station, Buchanan, Ny, Dtd 04/12/07
ML071900462
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/12/2007
From: Condra D
Oak Ridge Institute for Science & Education
To: Kottan J
NRC Region 1
References
FOIA/PA-2007-0324, IR-06-007, RFTA 06-001
Download: ML071900462 (11)
v • d • e


Text

I OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 12,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 WBJECT: REVISED FINAL 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

>ear Mr. Kottan:

The Oak Ridge Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the Indian Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for h a n d h g samples from this fachty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Radiological 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-59/63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through Table 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.

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 filter papers. An aliquot was removed for tritium and carbon-14 before acidification. 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 analyzeq the filtered solid portion of each sample for all the requested alpha isotopes. The remaining a%uot of each sample was adjusted to a pH of approximately2 with concentrated HNOs. T 3 m

,;3m

-

Lh 0 3 0

--?E

M KJim Kottan April 12,2007 In the o r i p a l report the date of the letter was incorrectly reported as January 26,2006. The date has been corrected and I apologize for any inconvenience this incorrect date may have caused.

My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures c: T. Carter, NRC/FSME/DWMEP 7518 E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN 8A23 S. IGk, ORISE M. Roberts, NRC Regon I J. White, NRC Region I File 1697 Distribution approval and concurrence : Initials ,

Technical Management Team Member Quality Manager K,

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 I MW-42@43 I 9/18/2006 I 13:OO 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO

~

1697W0072

~__________

1- MW-42@46 I 9/15/2006 I 12:45 1697M0035 MW-42@46 9/15/2006 12:45 1697W0073 MW-42@48 9/15/2006 11:20 1697M0036 MW-42@48 9/15/2006 11:20 1697W0074 MW-59@70 9/15/2006 10:20 1697M0037 I MW-59@70 I 9/15/2006 I 10:20 1697W0075 r LAF-001-(003)

~ ~~~

I 9/19/2006 I 15:49 1697M0038 LAF-001-(003) 9/19/2006 15:49 1697W0076 LAF-002-(003) 9/ 19/2006 13:41 1697M0039 LAF-002-(003) 9/19/2006 13:41 1697W0077 LAF-003-(003) 9/19/2006 11:08 1697M0040 LAF-003-(003) 9/19/2006 11:08 T h e Win the ORISE sample identification represents a water matrix.

'The M in the ORISE sample identification represents the filtercd fraction of the preceding water sample Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa'b(pCi/L)

Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697~0070 MW-42041 3 rt 11" 4 k 13 6.5 If: 9.3 13,730 k 470 1697W0071 MW-42043 -12 k 12 3  ? 12 6.0 k 9.2 15,140 k 510 1697W0072 MW-42046 -1.7 k 7.7 11.7 f. 9.9 2.4 k 7.8 20,260 k 650 1697~0073 MW-42048 6 k 13 15 k 11 1 k 11 21,650 k 750 1697W0074 MW-59@70 0.1 k 3.0 0.3 f. 4.1 1.3 k 2.7 -3.8 k 4.1 1697WOO75 LAF-001-(003) 1.2 k 2.8 3.8 k 2.9 -0.5 ? 2.4 1.2 k 2.1 1697W0076 I LAF-002-(003) I -2.4 k 3.0 2.2 I k 4.6 I 0.7 f. 2.6 I 0.5 k 2.2 1 1697W0077 I LAF-003-(003) 1 -1.7 k 2.0 0.7 I k 1.61 -0.8 k 1.71 -0.7 2 1.6 1 "The range of MDCs for the selected radionuclides for samples WOO70-WOO73 is 13 pCi/L to 37 pCi/L.

bThe range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.9 pCi/L to 5.0 pCi/L

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

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

TABLE 3 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 "The MDCs for each radionuclide are in parentheses

'Fe-55 analyzed using procedure AP13, Revision 4

'Ni-59/63 analyzed using procedure AP17, Revision 0.

dH-3 analyzed usmg procedure AP2, Revision 15 eUncertmnhes represent the 95% confidence level, based on total propagated uncertmnhes.

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tablcs Set 14

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 @Ci/L) 1697W0070 MW-42@4 1 4 k 18b (31) 1697W0071 MW-42@43 8 2 18 (31) 1697W0072 MW-42@46 -1 f 18 (31) 1697W0073 MW-42@48 5 -t- 18 (31) 1697W0074 MW-59@70 -4.7 f 8.9 (15.6) 1697W0075 LAF-00 1-603) -2.7  ? 9.0 (15.6) 1697W0076 LAF-002-(003) -0.5 f 9.1 (15.6) 1697W0077 LAF-003-(003) 2.8 k 9.1 (15.6)

Indian Point Power Station projects/l697/Data Tables/2007-04-12 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"@Ci/L) 1697W0070 MW-42@41 20.2 f 2.Ob (2.3)

~~

1697W0071 I MW-42@43 I 15.7 5 1.7 (1.9) 1697W0072 MW-42@46 32.8 f 2.4 (2.2) 1697W0073 MW-42@48 35.0 f 2.3 (2.0) 1697W0074 MW-59@70 0.14 k 0.50 (0.89) 1697W0075 LAF-001-(003) 0.10 k 0.52 (0.93) 1697W0076 LAF-002-(003) 0.97 f 0.55 (0.871 1697W0077 I LAF-003-(003) I -0.17 k 0.45 (0.83)

'MDCs are in parentheses buncertainties represent the 95% confidence level, based on total propagated uncertainties.

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

- - - -

z G c G G s'1 g 9 9 e e 0

9 e

0 9

e 2 5

d- u) d-N N 0 0

88 8 88

+I +I +I +I +I w w N N 0 9 0 0 9 0 8 0 8 88

-- - --

G G Gi G 5; 3 w e 9 e

9 e 2 2 8

m d

m 88 N N 8

N 88 m

w +I +I +I +I +I 3 w l-4 87 7 7 8 3 0

- _ I - --

s

65 6 9

?

i;j 9

e 5

2 9 e

W w l-4 M m 88 8 88

+I +I +I +I +I r- 0 0 3 0 88 8 88

-- - - -

5i

fl u) GF 66 6

'1 e 2 9 e

m hl hl N u) w 88 8 88 2

Frl

+I r-

+I 3

+I +I +I hl 87 0 N s:3 8 8 m -- - --

z H m m 00 G- 3 O 0 83 8 0, w

e 01 E5 E N

0 0 0 0 9 0 9 9 33 33 M

r-sE 0

r-m W

3

--

-

  • m 0

0 r-m W

3 W

m 0

0 E

r-m W

3

-

--

00 m

0 3

r-m 2

-

W r-s 0

r-m W

3 i;I-m 3

m w

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

TABLE 6 (Continued)

F E:

B CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES F AP11, REVISION 3; CP2, REVISION 12 P.

3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Sample ID Sample ID Pu-238 P~-239/240 U-234 U-238 1697W0070 m-426341 0.08 f 0.09 (0.15) 0.03 f 0.04 (0.07) 1.47 k 0.26 (0.10) 1.27 k 0.24 (0.07) 1697M0033 m-42@41 0.00 k 0.02 (0.04) 0.01 f 0.01 (0.01) 0.01 k 0.01 (0.02) 0.01 k 0.01 (0.02) 1697W0071 m-426343 0.06 k 0.13 (0.23) 0.01 ? 0.04 (0.09) 1.93 k 0.29 (0.03) 1.72 k 0.27 (0.03) 16971110034 m-42@43 0.02 fc 0.02 (0.031 0.01 k 0.01 (0.02) I 0.01 k 0.01 (0.01) I 0.01 f 0.01 (0.01) 1697W0072 m-42@46 0.11 f 0.08 (0.12) 0.01 f 0.03 (0.07) 1.87 k 0.30 (0.10) 1.70 k 0.28 (0.07) 16971110035 m-42@46 0.01 fc 0.02 (0.04) 0.01 k 0.01 (0.02) 0.02 k 0.01 (0.01) 0.02 k 0.01 (0.01) 1697W0073 m-42@48 -0.01 k 0.07 (0.15) 0.03 k 0.06 (0.11) 2.10 fc 0.30 (0.06) 1.74 k 0.26 (0.06) 1697M0036 m-42@48 0.00 fc 0.02 (0.03) 0.01 k 0.01 (0.01) 0.03 k 0.02 (0.02) 0.04 k 0.02 (0.01) 1697W0074 m-59@70 0.04 fc 0.03 (0.04) 0.04 k 0.03 (0.02) 0.54 k 0.10 (0.07) 0.48 k 0.09 (0.05) 1697M0037 m-59@70 0.00 f 0.02 (0.03) 0.01 k 0.01 (0.02) 0.01 f 0.01 (0.02) 0.03 f 0.02 (0.01) 1697w0075 mF-0O1-(003) 0.01 k 0.03 (0.05) 0.03 k 0.02 (0.02) 0.67 k 0.10 (0.02) 0.73 k 0.11 (0.02) l697M0038 mF-001-(003) 0.01 f 0.02 (0.03) 0.01 f 0.02 (0.02) 0.00 k 0.01 (0.02) 0.00 k 0.01 (0.01) 1697w0076 mF-0O2-(003) 0.04 f 0.05 (0.09) 0.03 k 0.03 (0.04) 26.3 f 2.1 (0.1) 17.1 k 1.4 (0.1) 16971110039 I uF-002-(003) I 0.01 f 0.02 (0.03) I 0.02 k 0.01 (0.01) I 0.05 k 0.02

~ ~~ ~~~ ~~~~

(0.01) I 0.03 fc 0.01 (0.01) 1~97woo77 ~ F - 0 0 3 - ( 0 0 3 ) 0.03 k 0.03 (0.04) 0.00 f 0.02 (0.04) 0.56 k 0.12 (0.09) 0.48 f 0.10 (0.03) 1697M0040 uF-003-(003) 0.02 fc 0.02 (0.03) 0.02 fc 0.01 (0.02) 0.01 f 0.01 (0.02) 0.01 fc 0.01 (0.01) 3 cn T h e M D C ~are in parentheses.

3

+ c buncertainties represent the 95% confidence level, based on total propagated uncertainties.

Zero values are due to rounding.

dSignificat figures expanded to avoid reporting a TPU of zero at the request of the inspector,

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 NRC Region I Radionuclide Concentrationsa ORISE Sample ID Sample ID @Ci/g of sediment in 100 mL or pCi/L for water) 1697W0070 M%'-42@41 -3 k 17b (29) 1697M0033 MW-42@41 -0.2 1 3.4 (5.9) 1697W0071 MW-42@43 -8 1 16 (28) 1697M0034 MW-42@43 -0.6 k 3.7 (6.4) 1697W0072 MW-42@46 -10 k 16 (27) 1697M0035 MW-42@46 -2.5 k 3.5 (6.1) 1697W0073 MW-42@48 -10 k 15 (27)

~~

1 1697M0036 I MW-42@48 I -0.6 & 3.5 (6.0) 1 1697W0074 I MW-59@70 I -2.5 k 9.3 (16.1) 1697M0037 MW-59@70 -0.9 k 3.4 (5.9) 1697W0075 LAF-001-(003) -2.7 1 7.9 (13.7) 1697M0038 LAF-001-(003) 1.1 1 3.5 (6.0) 1697W0076 LAF-002-(003) -6.4  ? 7.8 (13.6) 1697M0039 LAF-002-(003) 1.4 & 3.6 (6.1) 1697W0077 LAF-003-(003) -2.5 k 8.2 (14.2) 1697M0040 LAF-003-(003) 2.6 k 3.5 (5.9)

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

TABLE 8 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697W0070 MW-42@41 0.8 k 9.7b (16.4) 1697W0071 MW-42@43 8.8 k 9.8 (1 6.4) 1697W0072 Mw-42@46 0.2 +

- 9.6 (16.4) 1697W0073 Mw-42@48 -0.6 f. 9.6 (1 6.4) 1697W0075 LAF-001-(003) 0.5 k 9.7 (1 6.4) 1697~0076 LAF-002-(003) 1.4 f. 9.7 (1 6.4) 1697~0077 LAF-003-(003) 8.3 k 9.8 (16.4)

Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14

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