ML071900445
| ML071900445 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/20/2007 |
| 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: ML071900445 (7) | |
Text
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION 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 A SAMPLE FROM SET NINETEEN, 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 19, consisting of one water sample, associated with the Indian Point Power Station on December 20,2006. Sample analysis was initiated based on your previous direction for handling samples from this licensee. Sample identification and collection data for the sample 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 avadable for your review upon request.
The Ni-59 data was not reported due to problems with the calculation associated with the concentration of this radionuclide. Reporting of Ni-59 data has been discontinued until this problem can be resolved.
In addition, this sample was not filtered due to the high level of activity and lack of suspended solids in the sample. After removing the tritium and carbon-14 aliquot, the sample was acidified before proceeding with the other requested analyses.
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 758 E. Abelquist, ORISE E. Knox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Region I File 1697 S. Kirk, ORISE J. White, NRC Regon I Voice: 865.241.3242 Fax: 865.241.3248 E-mad: Dale.Condra @orau.org
TABLE 1 ORISE Sample ID 1697W0123 SAMPLE IDENTIFICATION AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time u1-vc sump 11/15/2006 NDP" Indian Point Power Station projects/l697/Data Tables/2007-04-20 Data Tables Set 19
1697W0123 TABLE 2 CO-58 CO-60 0.4E+03
& 1.5E+0?jb, 2.6E+03 2.2E+03 k 1.3E+03, 2.8E+03 cs-134 cs-137 24.6E+03 & 3.1E+03, 1.6E+03 46.2E+05 2 1.5E+05, 0.07E+05 U1-VC Sump CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN A WATER SAMPLE BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK It I
I NRC Region I 11 S a 2 ; D I Sample ID Radionuclide Concentrationsa (pCi/L)
"The MDCs are after the comma.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-04-20 Data Tables Set 19
TABLE 3 CONCENTFUTIONS OF HARD-TO-DETECT BETA EMITTING RADIONUCLIDES IN A WATER SAMPLE BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK I
I II Radionuclide Concentrationsa @Ci/L)
I( ORISE I NRCRegionI I Ni-63" 11 Sample ID I Sample ID I Fe-55b I
H-3d II 11 1697W0123 I U1-VCSump 150 k 47', 79 I 31.5E+04 k 2.2E+04, 0.1E+04 I 7.9E+07 k 0.26E+07, 0.00006E+07 11
?'he MDCs for each radionuclide are after the comma.
bFe-55 analyzed using procedure AP13, Revision 4.
'Ni-63 analyzed using procedure AP17, Revision 0 dH-3 analyzed using procedure AP2, Revision 15.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
TABLE 4 ORISE Sample ID 1697W0123 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN A WATER SAMPLE BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Tc-99 Concentrationsa U 1 -VC Sump 90
- f. 2ob,
30 Sample ID
@Ci/L)
ORISE Sample ID 1697W0123 TABLE 5 Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) u 1 -vc sump 1.633
- 74b.
16 NRC Region I Sample ID CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN A WATER SAMPLE BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
~
~~
~______
"The MDC is after the comma bUncert;unttes represent the 95% confidence level, based on total propagated uncertamhes Indian Point Power Station projects/l697/Data Tables/2007-04-20 Data Tables Set 19
TABLE 6 r
ORISE NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID Sample ID CONCENTRATIONS OF SELECTED ALPHA EMITTING WIONUCLIDES IN A WATER SAMPLE AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697W0123 Am-241 Cm-242 Cm-243/244 Np-237 0.36 fI 0.63b, 1.10 0.07 k 0.32, 0.69 0.22 0.56, 1.04
-0.38 k 0.40, 1.09 0.68 k 0.76, 1.22 0.08 k 0.15, 0.23 0.14 k 0.28, 0.53 0.14 k 0.20, 0.21 U1-VC Sump Pu-238 P~-239/240 U-234 U-238 3
w
?
ORISE Sample ID 1697W0123 TABLE 7 NRC Region I Radionuclide Concentrations, Sample ID TPUs, and MDCS" (pCi/L)
U 1 -VC Sump 900 130b 20 CONCENTRATIONS OF PLUTONIUM-241 IN A WATER SAMPLE BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK (I
NRC Region I Radionuclide Concentrationsa (pCi/L)
I Sample ID ORISE 1697W0123 u1-vc sump 50 rfl 12Ob 210 I
I
%e MDC is after the comma.
buncertainties represent the 95% confidence level, based on total propagated uncertamties.
TABLE 8 CONCENTRATIONS OF CARBON-14 IN A WATER SAMPLE BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Indian Point Power Station projects/l697/Data Tables/2007-04-20 Data Tables Set 19