ML071900438
| ML071900438 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| 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: ML071900438 (10) | |
Text
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Distribution approval and concurrence :
Technical Management Team Member Oualitv Manager Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406 Initials v -
- 1.
/A'*
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET SEVENTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set 17, consisting of 12 water samples, associated with the Indian Point Power Station on December 4, 2006. Sample analysis was initiated based on your previous direction for handling samples from this licensee. Sample identification and collection data for the samples addressed in this report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 8, respectively. The pertinent procedure references are provided in each specific table.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request. Additional reports will 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 this radionuclide. ORISE is dscontinuing the reporting of Ni-59 data untd ths 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.
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C:
T. Carter, NRC/FSME/DWMEP 7J18 E. Abelquist, ORISE E. &ox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Regon I File 1697 S. Kirk, ORISE J. White, NRC Regon I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org
TABLE 1 ORISE NRC Region I Sample ID Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Collection Collection Date Time 1697M0022 1697WO 1 15 1697M0023 Indian Point Power Station 1697W0114 Filter 12/4/2006 13:38 LAF-003-(004) 12/4/2006 10:02 1697W0115 Filter 12/4/2006 10:02 projects/l697/Data Tables/2007-04-12 Data Tables Set 17
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK T h e range of MDCs for the selected radionuclide for all samples except W0107 is 2.7 pCi/L to 4.7 pCi/L.
bThe range of MDCs for the selected radionuclide for sample W0107 is 34 pCi/L to 180 pCi/L.
Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
dZero values are due to rouding.
Indian Point Power Station projects/1697/Data Tables/2007-04-12 Data Tables Set 17
TABLE 3 B
CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES LIQUID SCINTILLATION ANALYSIS CP4, REVISIO INDIAN POINT POWER STATION BUCHANAN, NEW YORK "I'he MDCs for each radionuclide are after the comma.
%e-55 analyzed using procedure AP13, Revision 4.
'Ni-63 analyzcd using procedure AP17, Revision 0.
dH-3 analyzed using procedure AP2, Revision 15.
'Uncertainties represent the %0/0 confidence level, based on total propagated uncertainties fZero value is due to rounding.
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 17
TABLE 4 ORISE Sample ID CONCENTRATIONS OF TECHNETIUM-99 IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide (PCi/L)
NRC Region I Sample ID Concentrationsa 1697W0104 1697W0106 1697W0107 b-1697W0103 I Future LP Hotwell Sump I 6.8 k 9.1. 15.3 Sooting Settling Pit 12.6 k 9.3 15.3 CSB Sewage Pit 7.8
- f. 9.1 15.3 U-1 West Pool 29.5 k 9.8. 15.3 1697W0109 1697W0110 1697W0108 I MW-48-23-(009)
I 4.7 k 9.0. 15.3 MW-48-38-(009) 7.1 k 9.1 15.3 MW-38-(018) 5.9 k 9.0. 15.3 1697W0112 1697W0113 1697W0111 I MW-60-(001)
I 8.4 k 9.1
. 1 5. 3 MW-62-(001) 3.9 k 9.0 15.3 LAF-O01-(004) 1.6 k 8.9. 15.3 1697W0114 I LAF-002-(004) 1 8.9 k 9.1. 15.3 1697W0115 I LAF-003-(004)
I 10.2 k 9.2
, 15.3 "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/2007-04-12 Data Tables Set 17
TABLE 5 ORISE Sample ID 1697W0103 NRC Region I Radionuclide Concentrations, TPUs, Sample ID and MDCS" @Ci/L)
- f.
0.40b 0.56 1697W0104 1697W0106 1697W0107 1697W0108 Sooting Settltng Pit 0.02
- f.
0.31 0.55 CSB Sewage Pit 2.44
- f.
0.42 0.53 U-1 West Pool 1,775
-I 54 Y
4 MW-48-23-(009) 0.13 k
0.33 0.58 1697W0109 1697W0110 1697W0111 1697W0112
%e MDCs are after the comma.
hUncertainties represent the 95% confidence level, based on total propagated uncertainties.
MW-48-38-(009)
-0.10
- f.
0.32 0.57 MW-38-(018) 0.19
- f.
0.50 0.87 MW-60-(001) 0.41
- f.
0.54 0.92 MW-62-(001) 0.70
- f.
0.54 0.87 Indian Point Power Station 1697W0113 1697W0114 1697W0115 projects/l697/Data Tables/2007-04-12 Data Tables Set 17 LAF-001-(004) 0.32
- f.
0.52 0.89 LAF-002-(004) 0.36
- f.
0.48 0.82 LAF-003-(004) 0.13 k
0.48 0.85
TABLE 6 ORISE Sample ID 1697W0103 1697M0012 1697W0104 s
NRC Region I Radionuclide Concentrationsa @Ci/g of sediment in 100 mL or pCi/L for water)
Sample ID Am-241 Cm-242 Cm-243/244 Np-237 FutureLPHotwellSump 0.11 f 0.20~, 0.35 0.05 f 0.12, 0.22
-0.10 f 0.14, 0.32 0.00' 0.09, 0.20 1697W0103 Filter 0.01 f 0.03, 0.04 0.00 f 0.01, 0.03 0.01 f 0.02, 0.04 0.01 f 0.01, 0.02 Sooting Setthng Pit 0.25 f 0.25, 0.40 -0.04 f 0.14, 0.29 0.05 f 0.19, 0.34 0.08 f 0.08, 0.06 G
s 1697M0013 1697W0106 I -
1697WO104 Filter 0.01
& 0.03, 0.05 0.01 f 0.01, 0.02 0.01 0.02, 0.04
-0.04 f 0.02, 0.05 CSB Sewage Pit
-0.04 f 0.10, 0.24 0.06 k 0.09, 0.15
-0.04 0.06, 0.19 0.02 f 0.04, 0.06 1697W0107 1697M0015 1697W0108 1697M0016 1697M0014 I 1697W0106 Filter I 0.02 f 0.01, 0.01 I 0.01
& 0.01, 0.02 1-0.002~ & 0.004, 0.015 I -0.02 f 0.02, 0.05 11 U-1 West Pool 1.11 f 0.97, 1.50 0.07 k 0.46, 0.93 0.14 f 0.65, 1.23 1697W0107 Filter 0.05 k 0.03, 0.04 0.00 f 0.01, 0.02 0.02 f 0.02, 0.03 MW-48-23-(009) 0.11 f 0.23, 0.40 -0.02 f 0.07, 0.18 0.03 k 0.16, 0.31 1697W0108 Filter 0.01 k 0.02, 0.04 0.01
& 0.01, 0.01 0.00 f 0.02, 0.04 1697M0019 1697W0112 1697M0020 1697W0113
-0.02 f 0.08 0.00 k 0.01 1697W0111 Filter 0.01 f 0.02, 0.04 MW-62-(001) 0.14 k 0.15, 0.24 1697W0112 Filter 0.02 k 0.01, 0.01 LAF-001-(004) 0.00 f 0.19, 0.36
~
~~
1697W0109 I MW-48-38-(009)
I 0.25
& 0.22, 0.35 I 0.02 k 0.06, 0.13 r 0.02 f 0.17, 0.32 I 0.06 f 0.08, 0.14 11 1697M0022 1697W0115 1697M0023 1697M0017 I 1697W0109 Filter I 0.03 f 0.03, 0.04 I -0.01 f 0.01, 0.03 I -0.01 f 0.02, 0.04 I 0.00 f 0.01, 0.02 11 1697W0114 Filter
-0.01 f 0.02, 0.05 0.01 f 0.01, 0.01 0.02 f 0.02, 0.04 LAF-003-(004) 0.10 f 0.11, 0.15 0.10 f. 0.09, 0.06
-0.06 f 0.09, 0.24 1697W0115 Filter
-0.01 k 0.02, 0.05 0.00 k 0.01, 0.03 0.01 k
0.02, 0.04 1697W0110 I MW (0 1 8)
I 0.39 k 0.24. 0.32 I -0.02 f 0.09. 0.22 I -0.06 f 0.20. 0.41 I -0.19 f 0.14. 0.37 11 1697M0018 I 1697WOllOFilter I 0.01 f 0.02. 0.04 I 0.02 & 0.02. 0.02 I 0.01
? 0.02. 0.04 I 0.00 k 0.01. 0.02 11 1697W0111 I MW-60-(001)
I 0.18 k 0.21. 0.35 I 0.09 f 0.14. 0.24 I 0.07 f 0.20. 0.36 I 0.04 f 0.10. 0.20 11
~~
1697M0021 I 1697W0113 Filter I 0.01
& 0.02, 0.04 0.00 f 0.01, 0.02 I 0.01 0.02. 0.04 0.09 k 0.11 0.17 0.09 k 0.17 0.29 0.01 k 0.01 0.03
-0.01 f 0.02 0.04 0.00 f 0.01, 0.02 0.09 f 0.10. 0.14 0.00 f 0.01. 0.01
-0.10 f 0.19, 0.41 0.01 f 0.01, 0.02
-0.35 f 0.20
TABLE 6 (Continued)
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 2
R \\
- c.
a
-4 \\
+
tl 4
a 2 2 2 n
51 N
0 0
N 4
a 4
E CTI "The MDCs are after the comma.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero values are due to rounding.
dSignificant figures expanded to avoid reporting a TPU of zero at the request of the inspector.
L
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 (pCi/g of sediment in 100 mL or pCi/L for water)
NRC Region I Sample ID 1697~0103 1697M0012 1697~0104 1697M0013 Future LP Hotwell Sump
-8 k
33b Y
57 Sooting Settling Pit 1
rt 32 Y
54 1697W0103 Filter
-1.6 k
3.5 6.1 1697WO104 Filter
-1.7 k
3.5 6.1
~
~
~
1697W0106 CSB Sewage Pit 3
rt 33 57 1697M0014 1697W0106 Filter
-2.8 k
3.4 5.9 1697M0015 1697W0107 Filter
-2.6 k
3.3 5.7 1697W0107 U-1 West Pool 70 130 210 l r 1697%108 1-MW-48-23-(009)
I 6
rt 34 59 II 1697M0016 1697W0109 1697M0017 1697W0110 1697WO108 Filter 1.o
+
3.7 6.3 MW-48-38-(009) 17 k
32 Y
54 1697W0109 Filter 0.7 k
3.6 6.2 MW-38-(018) 20 k
35 58 1697M0018 1697W0111 1697M0019 1697W0110 Filter 2.0
+
3.5 5.9 MW-60-(001) 3 k
35 60 1697W0111 Filter 0.4 k
3.3 5.7 1697W0112 1697M0020 11-1697M0022 1697W0114Filter I
1.3 k
3.4 5.7 II
~
~
~
~~
5.8 Mw-62-(001)
-9 k
30 1697W0112 Filter
-1.6 k
3.3 1697W0113 1697M0021 1697W0114 Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 17 LAF-001-(004) 14 k
30 9
51 1697W0113 Filter
-1.7 k
3.3 5.7 LAF-002-(004)
-1 31 54 1697W0115 1697M0023 LAF-003-(004) 3 k
30 7
52 1697W0115 Filter 0.4 k
3.5 6.0
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 MDCs are after the comma.
Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 17