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{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION | {{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION March 30,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406 | ||
==SUBJECT:== | ==SUBJECT:== | ||
INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET EIGHTEEN, FROM | INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET EIGHTEEN, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK | ||
[RFTA NO. 06-0011 | [INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011 | ||
==Dear Mr. Kottan:== | ==Dear Mr. Kottan:== | ||
The Oak Ridge Institute for Science and Education (ORISE) received set 18, consisting of seven water samples, associated with the Indian Point Power Station on December 7 and 8,2006. Sample analysis was initiated based on your previous direction for handling samples from | |||
The pertinent procedure references are provided in each specific table. | The Oak Ridge Institute for Science and Education (ORISE) received set 18, consisting of seven water samples, associated with the Indian Point Power Station on December 7 and 8,2006. Sample analysis was initiated based on your previous direction for handling samples from t h s licensee. Sample identification and collection data for the samples addressed in t h s report are presented in Table 1. | ||
The QC fies are available for your review upon request. Additional reports wdl follow after the completion of the requested analyses. | 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 has removed the Ni-59 data due to problems with the calculation associated with the concentration of thls radionuclide. | ORISEs Quality Control (QC) requirements were met for these analyses. The QC fies are available for your review upon request. Additional reports wdl follow after the completion of the requested analyses. | ||
ORISE is discontinuing the reporting of Ni-59 data | ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of thls radionuclide. ORISE is discontinuing the reporting of Ni-59 data u n d t h s problem can be resolved. | ||
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. | My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. | ||
Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C: T. Carter, NRC/FSME/DWMEP 7518 E. IOlox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Region I | Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C: T. Carter, NRC/FSME/DWMEP 7518 E. Abelquist, O R I S E g E. IOlox-Davin, NRC/FSME/TWFN 8A23 S. IGk, ORISE v7 M. Roberts, NRC Region I J. White, NRC Regiony File 1697 Distribution approval and concurrence : InitiabA Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mad 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 1697W0116" RO-543-95' 12/5/2006 11:45 1697M006bb 1697W0116 filter 12/5/2006 11:45 1697W0117 P-1217 12/6/2006 10:45 1697M0067 1697W0117 filter 12/6/2006 10:45 1697W0118 Ft. Montgomery 12/5/2006 900 1697M0068 1697W0118 filter 12/5/2006 900 1697W0119 RO-18 12/5/2006 10:25 1697M0069 1697W0119 filter 12/5/2006 10:25 1697W0120 RO-543-50 12/5/2006 11:30 1697M0070 1697WO120 filter 12/5/2006 11:30 1697W0121 Mw-51-(011) 12/6/2006 11:45 1697M0071 1697W0121 filter 12/6/2006 11:45 1697W0122 MW-40-(010) 12/7/2006 9:37 1697M0072 1697W0122 filter 12/7/2006 937 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18 | |||
-1.5 f. 2.2 0.4 f. 2.2 -0.2 f. 2.1 P-1217 1.2 f. 2.4 0.8 f. 2.2 -0.1 f. 2.3 Ft. Montgomery 1.1 L- 1.7 0.9 k 1.7 1.0 f: 1.7 RO-18 -1.0 f. 2.4 0.9 f. 2.4 -0.7 f. 2.5 - | |||
-2 k 19 , 33 | TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BJ GAMMA SPECTROSCOPY CP1, REVISIOF 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations Sample ID Sample I D CO-58 CO-60 cs-134 b | ||
1697W0116 RO-543-95' -1.5 f. 2.2 0.4 f. 2.2 -0.2 f. 2.1 -1.8 f. 4.3 1697W0117 P-1217 1.2 f. 2.4 0.8 f. 2.2 -0.1 f. 2.3 -1.6 f. 2.0 1697W0118 Ft. Montgomery 1.1 L- 1.7 0.9 k 1.7 1.0 f: 1.7 2.3 k 2.5 1697W0119 RO-18 -1.0 f. 2.4 0.9 f. 2.4 -0.7 f. 2.5 0.2 k 3.1 | |||
-0.4 f. 2.1 1 1697W0121 MW-51-(011) -0.6 f. 2.7 1.1 f. 2.3 1.5 f. 2.5 -1.0 f. 4.5 1697W0122 MW-40-(010) -0.3 f. 1.7 0.3 f. 1.7 0.1 k 1.9 0.2 f. 1.8 "The range of MDCs for the selected radionuclides is 2.8 pCi/L to 4.4 pCi/L. | |||
bUncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18 | |||
confidence level, based on total propagated uncertainties. | |||
Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18 TABLE 4 ORISE NRC Region I Sample ID Sample ID | TABLE 3 CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa(pCi/L) | ||
ORISE NRC Region I Sample ID Sample I D Fe-55b Ni-63" H-3d 1697W0116 RO-543-95' 8 k 20' , 33 -5.0 k 5.5 9.7 200 k 210 , 360 169W0117 P-1217 -4 k 19 33 2.3 & 5.7 9.7 80 & 200 360 1697W0118 Ft.Montgomery 4 & 20 , 33 0.4 ? 5.6 . 9.7 50 k 200 . 360 1697W0119 I RO-18 I 1 k 19 . 33 I 1.9 k 5.7 . 9.7 1 110 k 210 . 360 11 1697W0120 1697W0121 1697W0122 I RO-543-50 MW-51-(011) | |||
MW-40-(010) | |||
-5 f. 19 , 33 | |||
-2 k 19 , 33 I 13 & 20 , 33 I 1.4 k 5.7 0.2 k 5.6 1.8 k 5.7 9.7 9.7 9.7 I 260 70 290 t | |||
k 220 200 220 | |||
. 360 | |||
, 360 I | |||
"The MDCs for each radionuclide are after the comma. | |||
"e-55 analyzed using procedure AP13, Revision 4. | |||
'Ni-63 analyzed using procedure AP17, Revision 0. | |||
d11-3 analyzed using procedure AP2, Revision 15. | |||
eUncertainties represent the 95% confidence level, based on total propagated uncertainties. | |||
Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18 | |||
TABLE 4 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 ORISE NRC Region I Radionuclide Sample I D Sample I D Concentrationsa (pCi/L) 1697WOl16 RO-543-95' 5.0 t 8.3b , 14.0 1697W0117 P-1217 3.4 k 8.2 , 14.0 1697W0118 Ft. Montgomery 2.7 2 8.2 , 14.0 1697W0119 RO-18 -1.8 k 8.1 , 14.0 1697W0120 RO-543-50 6.4 t 8.3 , 14.0 1697WO 121 MW-5 1-(011) -2.7 +_ 8.1 , 14.0 1697W0122 MW-40-(010) 5.2 ? 8.3 , 14.0 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Sct 18 | |||
TABLE 5 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"@Ci/L) 11 1697\)(10116 I RO-543-95' I 0.29 ? 0.36b . 0.60 11 1 1697W0117 I P-1217 I -0.09 k 0.39 , 0.69 1 1697W0118 Ft. Montgomery -0.08 & 0.34 , 0.60 1697W0119 RO-18 -0.10 k 0.37 , 0.66 1697W0120 RO-543-50 0.18 k 0.39 . 0.66 | |||
.1697W0121 MW-51-(011) 0.37 ? 0.36 , 0.61 1697W0122 Mw-40-(010) 0.61 k 0.35 , 0.56 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data 'Tables Set 18 | |||
F a TABLE 6 9 | |||
g n 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 1697W0119 RO-18 0.11 f: 0.18 , 0.31 0.00 f 0.09 , 0.20 0.07 f: 0.17 , 0.30 0.02 k 0.08 , 0.16 1697M0069 1697W0119 filter 0.01 f 0.02 , 0.04 0.00 f 0.01 , 0.02 0.00 f: 0.02 , 0.04 0.01 k 0.01 , 0.01 1697W0120 RO-543-50 0.17 k 0.21 , 0.34 -0.02 f 0.10 , 0.23 0.06 f 0.16 , 0.30 -0.02 f 0.08 , 0.20 CD . 1697M0070 1697W0120 filter 0.02 f 0.02 , 0.04 0.00 f: 0.01 , 0.02 0.01 f 0.02 , 0.03 0.00 k 0.02 , 0.06 | |||
+ | |||
2U | |||
--. 1697W0121 nnXr-51-(011) 0.09 f: 0.15 , 0.26 0.05 f 0.08 , 0.13 -0.05 f: 0.11 , 0.26 -0.06 k 0.10 , 0.26 2 16971110071 1697W0121 filter 0.01 f 0.02 , 0.04 0.01 f 0.01 , 0.02 0.00 f 0.02 , 0.04 -0.002 f 0.005 , 0.02 1697W0122 MW-40-(010) 0.23 f: 0.21 , 0.33 0.02 f 0.09 , 0.19 -0.02 f: 0.13 , 0.28 0.06 k 0.07 , 0.06 | |||
\ | |||
1697M0072 1697W0122 filter 0.01 k 0.02 , 0.04 0.00 f 0.01 , 0.03 0.00 f 0.02 , 0.04 -0.01 f 0.01 , 0.03 7 J | |||
TABLE 6 (Continued) | |||
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS O F WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, N E W YORK 5 | |||
N | |||
%e MDCs are after the comma. | |||
8 buncertainties represent the 95% confidence level, based on total propagated uncertainties. | |||
$ 'Zero values are due to rounding. | |||
dSignificantfigures expanded tn avoid repnrting a TPLT of 7ero at the request of the inspector U | |||
E 2 | |||
B E | |||
F+ | |||
W | |||
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILUTION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or pCi/L for Sample ID Sample ID water) 1697W0116 RO-543-95' -13 f. 35b , 60 1697M0066 1697W0116 filter 1.6 & 4.5 , 7.6 1697W0117 I?-1217 8 k 33 , 57 1697M0067 1697W0117 filter 1.6 | |||
* 4.5 7.7 1697W0118 Ft. Montgomery 8 | |||
* 33 , 56 1697M0068 1697W0118 filter -2.6 f. 4.9 , 8.5 1697W0119 RO-18 3 f. 35 Y 61 1697M0069 1697W0119 filter 3.5 k 4.5 7.4 1 1697W0120 I RO-543-50 1697M0070 1697W0120 filter 1 f. 10 , 17 1697W0121 MW-51-(011) 23 & 34 , 57 1697M0071 1697W0121 filter -0.3 k 4.3 , 7.4 1697W0122 MW-40-(010) 14 & 35 60 9 | |||
1697M0072 1697WO122 filter -0.2 4.2 7.2 "The MDCs are after the comma. | |||
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18 | |||
@Ci/g of sediment in 100 mL or pCi/L for water) | |||
- | |||
* 4.5 7.7 1697W0118 | |||
* 33 , 56 1697W0118 filter | |||
-2.6 f. 4.9 , 8.5 RO-18 3 f. 35 Y 61 1697W0119 filter 3.5 k 4.5 7.4 | |||
-0.3 k 4.3 , 7.4 MW-40-(010) 14 & 35 9 | |||
TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697w0116 RO-543-95' 4 k 12b . 20 1697W0117 P-1217 4 t 12 Y 20 1697W0118 Ft. Montgomery 6 k 12 Y 20 1697W0119 RO-18 0" k 12 Y 20 1697W0120 RO-543-50 4 t 12 . 20 1697W0121 MW-5 1-(011) 0 k 12 Y 20 1697W0122 Mw-40-(010) 1 k 12 . 20 "MDCs are after the comma. | |||
'Zero values are due to rounding. | buncertainties represent the 95"/0 confidence level, based on total propagated uncertainties. | ||
'Zero values are due to rounding. | |||
Indian Point Power Station projccts/l697/Data Tables/2007-03-30 Data Tables Set 18}} |
Latest revision as of 14:06, 13 March 2020
ML071900442 | |
Person / Time | |
---|---|
Site: | Indian Point |
Issue date: | 03/30/2007 |
From: | Condra D Oak Ridge Institute for Science & Education |
To: | Kottan J NRC Region 1 |
References | |
IR-06-007, RFTA 06-001 | |
Download: ML071900442 (10) | |
Text
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION March 30,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET EIGHTEEN, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set 18, consisting of seven water samples, associated with the Indian Point Power Station on December 7 and 8,2006. Sample analysis was initiated based on your previous direction for handling samples from t h s licensee. Sample identification and collection data for the samples addressed in t h s 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.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC fies are available for your review upon request. Additional reports wdl follow after the completion of the requested analyses.
ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of thls radionuclide. ORISE is discontinuing the reporting of Ni-59 data u n d t h s problem can be resolved.
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C: T. Carter, NRC/FSME/DWMEP 7518 E. Abelquist, O R I S E g E. IOlox-Davin, NRC/FSME/TWFN 8A23 S. IGk, ORISE v7 M. Roberts, NRC Region I J. White, NRC Regiony File 1697 Distribution approval and concurrence : InitiabA Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mad 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 1697W0116" RO-543-95' 12/5/2006 11:45 1697M006bb 1697W0116 filter 12/5/2006 11:45 1697W0117 P-1217 12/6/2006 10:45 1697M0067 1697W0117 filter 12/6/2006 10:45 1697W0118 Ft. Montgomery 12/5/2006 900 1697M0068 1697W0118 filter 12/5/2006 900 1697W0119 RO-18 12/5/2006 10:25 1697M0069 1697W0119 filter 12/5/2006 10:25 1697W0120 RO-543-50 12/5/2006 11:30 1697M0070 1697WO120 filter 12/5/2006 11:30 1697W0121 Mw-51-(011) 12/6/2006 11:45 1697M0071 1697W0121 filter 12/6/2006 11:45 1697W0122 MW-40-(010) 12/7/2006 9:37 1697M0072 1697W0122 filter 12/7/2006 937 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BJ GAMMA SPECTROSCOPY CP1, REVISIOF 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations Sample ID Sample I D CO-58 CO-60 cs-134 b
1697W0116 RO-543-95' -1.5 f. 2.2 0.4 f. 2.2 -0.2 f. 2.1 -1.8 f. 4.3 1697W0117 P-1217 1.2 f. 2.4 0.8 f. 2.2 -0.1 f. 2.3 -1.6 f. 2.0 1697W0118 Ft. Montgomery 1.1 L- 1.7 0.9 k 1.7 1.0 f: 1.7 2.3 k 2.5 1697W0119 RO-18 -1.0 f. 2.4 0.9 f. 2.4 -0.7 f. 2.5 0.2 k 3.1
-0.4 f. 2.1 1 1697W0121 MW-51-(011) -0.6 f. 2.7 1.1 f. 2.3 1.5 f. 2.5 -1.0 f. 4.5 1697W0122 MW-40-(010) -0.3 f. 1.7 0.3 f. 1.7 0.1 k 1.9 0.2 f. 1.8 "The range of MDCs for the selected radionuclides is 2.8 pCi/L to 4.4 pCi/L.
bUncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18
TABLE 3 CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa(pCi/L)
ORISE NRC Region I Sample ID Sample I D Fe-55b Ni-63" H-3d 1697W0116 RO-543-95' 8 k 20' , 33 -5.0 k 5.5 9.7 200 k 210 , 360 169W0117 P-1217 -4 k 19 33 2.3 & 5.7 9.7 80 & 200 360 1697W0118 Ft.Montgomery 4 & 20 , 33 0.4 ? 5.6 . 9.7 50 k 200 . 360 1697W0119 I RO-18 I 1 k 19 . 33 I 1.9 k 5.7 . 9.7 1 110 k 210 . 360 11 1697W0120 1697W0121 1697W0122 I RO-543-50 MW-51-(011)
MW-40-(010)
-5 f. 19 , 33
-2 k 19 , 33 I 13 & 20 , 33 I 1.4 k 5.7 0.2 k 5.6 1.8 k 5.7 9.7 9.7 9.7 I 260 70 290 t
k 220 200 220
. 360
, 360 I
"The MDCs for each radionuclide are after the comma.
"e-55 analyzed using procedure AP13, Revision 4.
'Ni-63 analyzed using procedure AP17, Revision 0.
d11-3 analyzed using procedure AP2, Revision 15.
eUncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18
TABLE 4 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 ORISE NRC Region I Radionuclide Sample I D Sample I D Concentrationsa (pCi/L) 1697WOl16 RO-543-95' 5.0 t 8.3b , 14.0 1697W0117 P-1217 3.4 k 8.2 , 14.0 1697W0118 Ft. Montgomery 2.7 2 8.2 , 14.0 1697W0119 RO-18 -1.8 k 8.1 , 14.0 1697W0120 RO-543-50 6.4 t 8.3 , 14.0 1697WO 121 MW-5 1-(011) -2.7 +_ 8.1 , 14.0 1697W0122 MW-40-(010) 5.2 ? 8.3 , 14.0 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Sct 18
TABLE 5 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"@Ci/L) 11 1697\)(10116 I RO-543-95' I 0.29 ? 0.36b . 0.60 11 1 1697W0117 I P-1217 I -0.09 k 0.39 , 0.69 1 1697W0118 Ft. Montgomery -0.08 & 0.34 , 0.60 1697W0119 RO-18 -0.10 k 0.37 , 0.66 1697W0120 RO-543-50 0.18 k 0.39 . 0.66
.1697W0121 MW-51-(011) 0.37 ? 0.36 , 0.61 1697W0122 Mw-40-(010) 0.61 k 0.35 , 0.56 Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data 'Tables Set 18
F a TABLE 6 9
g n 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 1697W0119 RO-18 0.11 f: 0.18 , 0.31 0.00 f 0.09 , 0.20 0.07 f: 0.17 , 0.30 0.02 k 0.08 , 0.16 1697M0069 1697W0119 filter 0.01 f 0.02 , 0.04 0.00 f 0.01 , 0.02 0.00 f: 0.02 , 0.04 0.01 k 0.01 , 0.01 1697W0120 RO-543-50 0.17 k 0.21 , 0.34 -0.02 f 0.10 , 0.23 0.06 f 0.16 , 0.30 -0.02 f 0.08 , 0.20 CD . 1697M0070 1697W0120 filter 0.02 f 0.02 , 0.04 0.00 f: 0.01 , 0.02 0.01 f 0.02 , 0.03 0.00 k 0.02 , 0.06
+
2U
--. 1697W0121 nnXr-51-(011) 0.09 f: 0.15 , 0.26 0.05 f 0.08 , 0.13 -0.05 f: 0.11 , 0.26 -0.06 k 0.10 , 0.26 2 16971110071 1697W0121 filter 0.01 f 0.02 , 0.04 0.01 f 0.01 , 0.02 0.00 f 0.02 , 0.04 -0.002 f 0.005 , 0.02 1697W0122 MW-40-(010) 0.23 f: 0.21 , 0.33 0.02 f 0.09 , 0.19 -0.02 f: 0.13 , 0.28 0.06 k 0.07 , 0.06
\
1697M0072 1697W0122 filter 0.01 k 0.02 , 0.04 0.00 f 0.01 , 0.03 0.00 f 0.02 , 0.04 -0.01 f 0.01 , 0.03 7 J
TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS O F WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, N E W YORK 5
N
%e MDCs are after the comma.
8 buncertainties represent the 95% confidence level, based on total propagated uncertainties.
$ 'Zero values are due to rounding.
dSignificantfigures expanded tn avoid repnrting a TPLT of 7ero at the request of the inspector U
E 2
B E
F+
W
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILUTION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or pCi/L for Sample ID Sample ID water) 1697W0116 RO-543-95' -13 f. 35b , 60 1697M0066 1697W0116 filter 1.6 & 4.5 , 7.6 1697W0117 I?-1217 8 k 33 , 57 1697M0067 1697W0117 filter 1.6
- 4.5 7.7 1697W0118 Ft. Montgomery 8
- 33 , 56 1697M0068 1697W0118 filter -2.6 f. 4.9 , 8.5 1697W0119 RO-18 3 f. 35 Y 61 1697M0069 1697W0119 filter 3.5 k 4.5 7.4 1 1697W0120 I RO-543-50 1697M0070 1697W0120 filter 1 f. 10 , 17 1697W0121 MW-51-(011) 23 & 34 , 57 1697M0071 1697W0121 filter -0.3 k 4.3 , 7.4 1697W0122 MW-40-(010) 14 & 35 60 9
1697M0072 1697WO122 filter -0.2 4.2 7.2 "The MDCs are after the comma.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-03-30 Data Tables Set 18
TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697w0116 RO-543-95' 4 k 12b . 20 1697W0117 P-1217 4 t 12 Y 20 1697W0118 Ft. Montgomery 6 k 12 Y 20 1697W0119 RO-18 0" k 12 Y 20 1697W0120 RO-543-50 4 t 12 . 20 1697W0121 MW-5 1-(011) 0 k 12 Y 20 1697W0122 Mw-40-(010) 1 k 12 . 20 "MDCs are after the comma.
buncertainties represent the 95"/0 confidence level, based on total propagated uncertainties.
'Zero values are due to rounding.
Indian Point Power Station projccts/l697/Data Tables/2007-03-30 Data Tables Set 18