ML062720227
| ML062720227 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/01/2006 |
| From: | Condra D Oak Ridge Institute for Science & Education |
| To: | Kottan J Division of Nuclear Materials Safety I |
| References | |
| FOIA/PA-2006-0140 IR-06-007, RFTA 06-001 | |
| Download: ML062720227 (55) | |
Text
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION September 1,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
FIRST INTERIM 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 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set nine, whch consisted of nine water samples received on August 15,2006 from the Indian Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for handling samples from this facility. Sample identification and collection data for the samples addressed in this report are presented in Table 1. Gamma spectroscopy, total radiostrontium (except 1697W0059),the hard-to-detect betas (iron-55, nickel-59/63, and tritium), and technetium-99 data are provided in Tables 2 through Table 5, 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.
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 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 will analyze the filtered solid portion of each sample for all the requested alpha isotopes. Upon removal of the stop work on alphas in water by the NRC, the filtrate of each water sample will be analyzed. The remaining aliquot of each sample was adjusted to a pH of approximately 2 with concentrated HN03.
Mr. Jim Kottan September 1,2006 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:WPI:db Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 S. JSirk, ORISE M. Miller, NRC Region I J. White, NRC Region I File 1697 Distribution approval and concurrence : Initials, -
Technical Management Team Member liw Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD @orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample NRC Region I Collection Collection ID Sample ID Date Time 11 1697W0051 1 MW-50El67' I 8/1/2006 I 11:30 1697W0052 MW-50 E l 42' 8/1/2006 11:15 1697W0053 MW-49 E l 25' 8/1/2006 9:28 1697W0054 MW-49 El 65' 8/1/2006 950 1697W0055 MW-49 E l 42' 8/1/2006 9:35 1697W0056 MW-58 E l 71' 8/2/2006 9:3 1 1697W0057 MW-38 8/7/2 006 13:23 11 1697W0058 I dischargecanal I 8/7/2006 I 1350 11 1697W0059 I MW-40 I 8/9/2006 I 10:35 Indian Point Power Station projects/l697/Data Tables/2006-09-01 Data Tables Set Nine
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample NRC Region I Radio iuclide Concentrationsa( )Ci/L)
ID Sample ID
____~
~
1697W0051 MW-50El 67' 1-03 f 3.1t 0.7 f 2.8 0.6 f 2.9 2.0 f 2.5 1697W0052 I MW-50El42' I 1.3 f 2.3 2.1 f 2.1 -0.3 f 2.1 -2.6 f 4.5 1697W0053 I MW-49 El 25' 1 -0.7 f 1.8 0.6 f 1.6 -0.1 f 1.7 0.2 f 1.6 1697W0054 I MW-49El 65' I 1.1 f 2.3 0.9 f 2.3 3.2 f 2.3 0.5 f 2.1 1697W0055 I MW-49El 42' 1-1.4 f 2.4 0.3 f 2.2 1.3 f 2.3 -2.1 f 4.5 1697W0056 I MW-58El 71'
~
1-0.1 f 2.5 3.0 f 2.3 2.1 f 2.2 1.1
- 2.1
~~~
1@7W0&7 ~
I ~
MW-38
~
1-0.9 f 2.5 -0.5 f 2.81 0.2 f 2.4 3.8 f 2.3 1697W0058 dischargecanal -2.0 f 2.3 -1.4 f 2.41 0.8 f 2.4 1.3 f 1.5 1697W0059 MW-40 -1.5 f 1.7 -0.6 f 1.9
%e range of MDCs for the selected radionuclides is 2.8 pCiL to 4.4 pCilL.
buncertaintiesrepresent the 95% confidence level, based on total propagated uncertainties.
Indian oint Power Station projects/l697/Data Tables/2006-09-01 Data Tables Set Nine
TABLE 3 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 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCS"(pCi/L) 1697W0051 MW-50 E l 67' 30.0 1.7b (0.8) 1697W0052 MW-50 E l 42' 4.75
- 0.77 (0.85) 1697W0053 MW-49 E l 25' 11.7
- 1.o (0.8) 1697W0054 MW-49 El 65' 16.3
- 1.2 (0.8) 1697W0055 MW-49 E l 42' 19.7
- 1.4 (0.8) 1697W0056 MW-58 E l 71' 0.65 f 0.51 (0.82) 1697W0057 MW-38 0.37
- 0.45 (0.76) 1697W0058 discharge canal 0.20
- 0.45 (0.78)
L 1697W0059' MW-40 kncertainties represent the 95% confidence level, based on total propagated uncertainties.
'The result for this sample was not available at the time of issuing the report.
Indian Point Power Station projects/l697/Data Tables/2006-09-01 Data Tables Set Nine
I I
I TABLE 4 CONCENTRATIONS OF HARD T O DETECT BETA EMITTING RADIONUCLIDES IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK V
a (P
8 2
0.
\
a
-I P
P 4
5 E
zg ?he MDCs for each radionuclide are in parentheses.
bFe-55 analyzed using proccdure AP13, Revlsion 4.
Ni-59/63 analyzed using procedure AP17, Revision 0.
PP dH-3 analyzed using procedure AP2, Revision 15.
4 52 Uncertainties represent the 95% confidence level, based on total propagated unceamnties.
E 2:
2.
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, N E W YORK I1 I I 1 ORISE Sample NRC Region I Tc-99 Concentrationsa ID Sample ID (PWL) 1697W0051 MW-50 E l 67' -3.9 k 9.1b (15.8) 1697W0052 MW-50 E l 42' 0.1 k 9.2 (15.8) 1697W0053 MW-49 E l 25' -6.3 k 9.0 (15.8) 1697W0054 MW-49 E l 65' -8.5 k 9.0 (15.8) 1697W0055 MW-49 E l 42' -8.6 k 9.0 (15.8) 1697W0056 MW-58 El 71' -5.4 L 9.1 (15.8) 1697W0057 MW-38 -4.0 & 9.1 (15.8) 1697W0058 discharge canal 4.3 k 9.3 (15.8) 1697W0059 MW-40 -5.2 k 9.1 (15.8)
Indian Point Power Station projects/l697/Data Tables/2006-09-01 Data Tables Set nine
Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road I b g of Prussia, PA 19406
SUBJECT:
FIRST INTERIM REPORT FOR REQUESTED ANALYSES OF FOUR WATER SAMPLES, SET EIGHT, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA N O . 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set eight, which consisted of four water samples received on July 24,2006 from the Indian Point Power Station in Buchanan, New York.
The samples arrived without a chain-of-custody from the licensee. Sample analysis was initiated based on your previous direction for handling samples from this facility. Sample identification and collection data for the samples addressed in this report are presented in Table 1. Gamma spectroscopy, total radiostrontium, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), and technetium-99 data are provided in Tables 2 through Table 5, 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.
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:ar Enclosures C: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TCVFN 8A23 S. Kirk, ORISE M. Miller, NRC Region I J. m t e , NRC Region I File 1697 Distribution approval and concurrence : Initials ~ -
Technical Management Team Member LSFW I
Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION B U C W A N , NEW YORK
_______ _____~
ORISE NRC Region I Collection Collection Sample ID Sample ID Time 1697W0047 MW 49-25 I 7/12/2006 NDP" 11 1697W0048 MW 49-42 I 7/12/2006 NDP MW 49-65 I 7/12/2006 NDP
~~ ~
MW 49-51 I 7/12/2006 NDP "No data provided.
Indian Point Powcr Station projects/lG97/Data Tables/2006-08-22 Data Tables Set Eight
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(pCi/L)
Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697W0047 b MW 49-25 -1.1 k 2.5 1.1 k 2.5 0.2 k 2.7 0.3 k 2.3 1697W0048 MW 49-42 -0.7 k 2.1 -1.7 k 3.5 -0.6 k 2.1 2.0 k 4.6 1697W0049 MW 49-65 1.7 k 2.5 0.2 k 2.1 -2.2 k 2.2 -0.1 k 2.1 1697W0050 MW 49-51 2.7 k 2.4 2.0 k 1.6 -0.6 k 2.3 -0.1 k 2.0 "The range of MDCs for the selected radionuclides is 3.0 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/2006-08-22 Data Tables Set Eight
TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 3.3; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample I D Sample I D TPUs, and MDCS"@Ci/L) 1697W0047
- M w-49-25 16.0 k 1.7b (1.7) I 1697W0048 M w 49-42 22.9 k 1.9 (1.6) 1697W0049 M w 49-65 18.0 k 1.7 (1.6) 1697W0050 M w 49-51 0.24 k 0.86 (1.48)
Indian Point Power Station projects/l697/Data Tables/2006-08-22 Data Tables Set Eight
'. I xTABLE4 CONCENTRATIONS OF HARD TO DETECT U.
Y BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Sample ID Sample I D Fe-55b Ni-59" Ni-63" H-3d 1697W0047 MW 49-25 28 It_- 28' (47) -9.5 f 4.8 (8.5) 11.1 k 7.7 (12.7) 12,740 k 690 (380) 1697W0048 30 k 28 (47) -20.2 f 4.7 (8.5) 19.0 k 7.9 (12.7) 8,060 k 540 (380) 1697W0049 26 f 28 (47) -9.7 k 4.8 (8.5) 10.0 k 7.7 (12.7) 4,780 k 430 (380) 1697W0050 31 k 28 (47) -8.1 k 4.9 (8.5) 4.8 2 7.5 (12.7) 30 ? 210 (380) 7-.
a
+
'%e MDCs for each radionuclide are in parenthescs.
0 bFe-55analyzed using procedure AP13, Revision 4.
W
\4
'Ni-59/63 analyzed using procedure AP17, Revision 0.
!a? dH-3 analyzed using procedure AP2, Revision 15.
3 e 'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
D
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (TC-99)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, N E W YORK II I I 1
/I Sa2;D I NRC Region I Sample I D Tc-99 Concentrationsa 1697W0047 M w 49-25 10.0 _+ 9.0b (14.9) 1697~0048 M w 49-42 -0.6 k 8.7 (14.9) 1697W0049 MW 49-65 9.4 & 9.0 (14.9) 11 1697W0050 I M W 49-51 I 8.9 -t 8.9 (14.9) 11 "The MDCs are in parentheses.
buncertaintiesrepresent the 95% confidence level, bascd on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2006-08-22Data Tables Set Bight
August 18,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
REVISION TO REPORT FOR REQUESTED ANALYSES OF THREE WATER SAMPLES, SET FOUR, COLLECTED MAY 3 AND 4,2006 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 two water samples on May 8,2006 and one water sample on May 9,2006 from the Indan Point Power Station in Buchanan, New York. The sample identifications and collection data are presented in Table 1.
The gamma spectroscopy, total radiostrontium, hard-to-detect beta emitters (carbon-14, iron-55, nickel-59/63, and tritium), and technetium-99 (Tc-99) data are provided in Tables 2 through Table 5, respectively. The pertinent procedure references are provided in the specific tables.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
At your request, the Tc-99 results for samples 1697W0030 and 1697W0031, provided to you in a June 23,2006 report, were reevaluated. The results of the reanalysis are presented in this report. The Tc-99 data for these two samples are the only changes to the data tables.
Additionally, the alpha spectroscopy (AS) results have been removed from the report pending completion of RESL Special Sample Set reevaluation. Per NRC, we have stopped work on AS in water until the investigation is complete. We are working to improve the analytical procedure related to AS and we will begin to perform these analyses for water samples provided by the NRC once development of this revised procedure is completed.
Mr. Jim Kottan August 18,2006 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:WPI:db Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. I(nox-Davin, NRC/NMSS/TWFN 8A23 S. IGrk, ORISE M. Miller, NRC Region I J. White, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 OFUSE NRC Region I Collection Collection Sample ID Sample ID Date Time 11 1697W0030 I bottomlaver I 5/3/2006 I 15:50 11 1697W0031 I bulk laver I 5/3/2006 I 16:OO lr ~~~
1697W0032 I unit 2manhole#5 I 5/4/2006 I 14:28 Indian Point Powcr Station Data Table Set Four projects/l697/Data Tables/2006-08-18
TABLE 2 NRC Region I Radionuclide Concentrationsa(pCi/L)
ORISE Sample ID Sample ID co-58 CO-60 CS-134 CS-137 1697W0030 bottom layer 2.5 f 2.2b 2.5 f 3.7 2.5 f 2.3 2,895 f 91 1697W0031 bulk layer -2.4 f 2.1 -0.1 f 2.3 1.5 f 2.8 2,870 f 90 1697W0032 unit 2 manhole #5 -0.5 f 1.5 -0.2 f 1.6 1.1 f 2.2 0.1 f 2.7 G
6
TABLE 3 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 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCsa (pCi/L) 1697W0030 bottom layer 352 f 1l b (1)
I 1697w0031 1697W0032 "MDCs are in parentheses.
bulk layer unit 2 manhole #5 349 0.18 f
11 0.55 (0.96) buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2006-08-18Data Table Sct Four
TABLE 4 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 ID C-14b Fe-55 Ni-5gd Ni-63d H-3e 1697W0030 bottom layer -6 t 16f (28) -56 f 28 (49) -9.2 t 2.6 (4.7) 24.2 ? 3.5 (4.8) 1,880 ? 310 (380) 1697W0031 bulk layer 1 k 16 (28) -43 k 28 (49) -7.2 k 2.6 (4.7) 24.4 k 3.5 (4.8) 1,800 k 310 (380) 1697W0032 unit2manhole #5 -15 k 16 (28) -60 k 28 (49) -0.6 k 2.7 (4.7) -1.4 k 2.8 (4.8) 2,210 k 330 (380)
TABLE 5 ORISE NRC Region I Tc-99 Concentrationsa Sample ID Sample ID @Ci/L) 1697W0030 bottom layer Ob k 17' (30) 1697W0031 bulk layer 13 ? 18 (30) 1697W0032 unit 2manhole #5 10.7 2 9.2 (15.3)
T h e hlDCs are in parentheses.
b-Lcro value is due to rounding.
'Uncertainties represent the 95% confidence level, based on total propagated Uncertainties.
Indian Point Power Station projects/l697/Data ?'ables/2006-08-18 Data 'Table Set Four
[(<. <t , :*
9 \I,!' T )
O R I S E I .<*; ' i '1 1 .
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
SECOND INTERIM REPORT FOR REQUESTED ANALYSES OF TWO VEGETATION A N D ASSOCIATED WATER SAMPLES, SET SEVEN, COLLECTED BETWEEN JUNE 14 AND JUNE 22,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT N O . 050-247/2006-0071 [RFTA N O . 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set seven consisting of four water samples and two vegetation samples received on June 28,2006 and two additional water samples received on June 30,2006, from the Indian Point Power Station in Buchanan, New York. The samples arrived without a chain-of-custody from the licensee. Sample analysis was initiated based on your previous direction for handling samples from t h s facility. Additionally, the water associated with each vegetation sample was filtered and analyzed per our phone conversation of July 11,2006. Sample identification and collection data for the samples addressed in this report are presented in Table 1.
Gamma spectroscopy, total radiostrontium, and nickel-59/63 data are provided in Tables 2 through Table 4,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 avdable for your review upon request. Additional reports will follow after the completion of the 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 RD C : W I:ar Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 S. IGrk, ORISE M. Miller, NRC Region I J. L h t e , NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member A' J d /6 Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK II I I I "1697W0045 and 1697W0046 are the water fractions filtered from 1697V0001and 1697V0002.
Indian Point Power Station projects/l697/Data Tables/2006-08-11 2nd Interim Data Table Set Seven
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN VEGETATION SAMPLES B GAMMA SPECTROSCOPY CP1, REVISIO 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697V0O0la Verplanck 0.09 5 O.lOb 0.08 1- 0.10 0.02 k 0.08 0.15 k 0.13 1697V0002 Lent's Cove 0.00' f. 0.03 -0.01 k 0.03 0.06 k 0.04 0.08 k 0.04 1697W0045d Lent's Cove -0.4 f. 6.5 0.3 k 4.9 0.4 k 5.7 1.3 f 4.9 1697W0046 Lent's Cove 4.4 f. 7.4 3.6 1- 7.5 1.1 1- 6.5 0.4 1- 7.1 "The range of MDCs for the selected radionuclides in the vegetation samples is 0.04 pCi/g to 0.18 pCi/g wet weight.
bUncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero value is due to rounding.
'?he range of MDCs for thc selected radionuclides in the water samples is 7.1 to 12 pCi/L.
Indian Point Power Station projects/l697/Data Tables/2006-08-11 2nd Interim Data Tablc Set Seven
TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N VEGETATION AND WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCs" @Ci/g wet Sample I D Sample ID weight for vegetation or pCi/L for water) 1697V0001 Verplanck -0.01 f O.Olb (0.02) 1697V0002 Lent's Cove 0.00' f 0.04 (0.07) 1697W0039 MW-30 72' 0.33
- 0.77 (1.32) 1697W0040 MW-30 74' 0.34 f 0.81 (1.38) 1697w0041 MW-30 78' -0.40 -t 0.75 (1.36) 1697W0042 MW-30 83' 0.40 k 0.72 (1.24) 1697W0043 MW 40' -0.66 f 0.93 (1.70) 1697W0044 MW 200' 0.96 f 0.82 (1.35)
'MDCs are in parentheses.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties
'Zero value is duc to rounding.
Indian Point Power Station projects/l697/Data Tables/200G-08-112nd Interim Data Table Sct Seven
TABLE 4 CONCENTRATIONS OF NICKEL-59 (Ni-59)
AND NICKEL-63 (Ni-63)
I N VEGETATION SAMPLES BY LIQUID SCINTILLATION ANALYSIS A p 17, REVISION 0; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa@Ci/g)
Sample ID Sample ID Ni-59 Ni-63 1697V0001 Verplanck -0.02 ? O.OZb (0.03) 0.02 & 0.03 (0.05) 1697V0002 Lents Cove -0.18 & 0.07 (0.13) 0.17 & 0.11 (0.18)
~~
T h e MDCs for each radionuclide are in parentheses.
Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2006-08-11 2nd Interim Data Table Set Seven
OAK RIDGE INSTITUTE F O R SCIENCE AND EDUCATION August 4,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
FIRST INTERIM REPORT FOR REQUESTED ANALYSES OF SIX WATER SAMPLES, SET SEVEN, COLLECTED BETWEEN J U N E 14 AND J U N E 22, 2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT N O . 050-247/2006-0071 [RFTA N O . 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Scienceand Education (ORISE) received set seven, which consisted of four water samples and two vegetation samples received on June 28,2006 and two additional water samples received on June 30,2006, from the Indian Point Power Station in Buchanan, New York. The samples arrived without a chain-of-custody from the licensee. Sample analysis was initiated based on your previous direction for handling samples from this facility. Sample identification and collection data for the samples addressed in this reportare presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), and technetium-99 data are provided in Tables 2 through Table 4, respectively. The pertinent procedure references are provided in each specific table.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC fila are available for your review upon request. Adhtional reports will follow after the completion of therequested 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:WI:ar Enclosures E. Abelquist, ORISE --
L'i cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Ihox-Davin, NRC/NMSS/TWFN 8A23 S. IGrk, ORISE M. Miller, NRC Region I J. White, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECI'ION DATA INDIAN POINT POWER STATION BUCHANAN, NEWYORK ORISE Sample NRC Region I Collection Collection ID Sample ID Date Time 1697W0039 Mw-30 72' 6/23/06 13:30 1697W0040 Mw-30 74' 6/23/06 1050 1697W0041 Mw-30 78' 6/22/06 14:lO 1697W0042 Mw-30 83' 6/22/06 11:40 1697W0043 Mw 40' 6/2 1/06 9:48 1697W0044 Mw 200' 6/20/06 10:20 Indian Point Power Station projects/l697/Data Tables/200&08-04 1st Interim Data Table Set Seven
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK "The range of MDG for the selected radionuclides is 2.6 pCi/L to 4.4 pWL.
buncertainties represent the 95% confidence level, based on total propagated uncenainties.
Indian Point Power Station projects/l697/Data Tables/2006-08-04 1st Interim Data Table Set Seven
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 ORISE Sample NRC Region I Radionuclide Concentrationsa@Ci/L)
Sample I D Fe-55b Ni-59' I Ni-63' I H-3d 1697W0039 MW-30 72' -2 k 24" (41) 4.6 k 4.4 (7.4) 9.3 k 5.8 (9.5) 396,000 k 11,000 (500) 1697W0040 MW-30 74' -9 k 24 (41) -0.3 rt 4.3 (7.4) 12.0 k 5.8 (9.5) 397,000 k 11,000 (500) 1697W0041 MW-30 78' -4 k 24 (41) O.Of k 4.3 (7.4) 12.3 rt 5.8 (9.5) 304,100 k 8,400 (400) 1697W0042 MW-30 83' 9 _+ 24 (41) 3.4 rt 4.4 (7.4) 12.2 k 5.8 (9.5) 189,100 rt 5,300 (400)
-3
- 3. I 1697WOO43 MW 40' -4 k 24 (41) -1.5 k 4.3 (7.4) 2.4 rt 5.6 (9.5) 840 k 270 (390) n
?
I & 1697W0044 MW 200' -8 k 24 (41) 4.6 rt 4.4 (7.4) -1.8 tr 5.5 (9.5) 150 k 230 (390) v 6 bFe-55analyzed using procedure AP13, Revision 4.
3z 'Ni-59/63 analyzed using procedure AP17, Revision 0 3
0 dH-3analyzed using procedure AP2, Revision 15.
O e Unccrtaintics rcprcsent the 95% confidence level, based on total propagated uncertainties.
$ fiero values are due to rounding.
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, N E W YORK ORISE Sample NRC Region I Tc-99 Concentrationsa ID Sample ID (pCi/L) 1697W0039 Mw-30 72' 5 ? 18b (30) 1697w0040 Mw-30 74' 18 k 18 (30) 1697W0041 Mw-30 78' 10 k 18 (30) 1697W0042 Mw-30 83' 14 k 18 (30) 1697W0043 Mw 40' 7 k 18 (30) 1697W0044 Mw 200' 3 k 18 (30)
Indian Point Power Station projects/l697/Data Tables/2006-08-04 1st Interim Data Table Set Seven
July 14,2006 Mr. JimKottan U.S. Nuclear Regulatory Cornmission Region I 475 Atlendale Road King of Prussia, PA 19406
SUBJECT:
FIRST INTERIM REPORT FORREQUESTED ANALYSES OF SIX WATER SAMPLES, SET SIX, COLLECTED JUNE 6 ANDJUNE 9,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-007I [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set six, consisting of six water samples on Junel5,2006 from the Indian Point Power Station in Buchanan, New York The sample identifications and collection data are presented in Table 1. The gamma spectroscopy, total radiostrontium, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), and technetium-99 data are provided in Tables 2 through Table 5, respectively. The pertinent procedure references are provided in the specific tables.
OIUSEs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request. A final report will follow after the completion of the alpha spectroscopy and plutonium-241 analysis.
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: WP1:ess Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7El8 E. Abelquist, ORISE E. Knox-Davin, NRUNMSS/TWFN 8A23 S. Kirk, ORISE M. M e r , NRC Region I J. White, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK I I ORISE Sample NRC Region I Collection Collection ID Sample ID Date Time 1697W0033 W - 4 8 23' 2" 6/9/2006 11:15 1697W0034 Mw-48 38' 1" 6/9/2006 11:30 1697WOO35 W - 4 8 River front 6/9/2006 11:30 1697W0036 MW-1 Lafarge 6/6/2006 1350 1697W0037 MW-2 Lafarge 6/6/2006 12:19 1697W0038 W - 3 Lafarge 6/6/2006 10:34 Indian Point Power Station projects/l697/Data Tables/2006-07-14 Interim Data Table Set Six
V s TABLE 2 4
CONCENTRATIONSOF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPYCPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK T h e nnge of MDCs for the selected radionuchdes IS2 7 pG/L to 4 2 pWL hvnce-ties represent the 95% confidence level, based on total propagated uncertaumes
TABLE 3 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 ONSE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs" (pCi/L) 1697W0033 MW-48 23' 2" -0.02 f 0.56b (1.01) 1697W0034 MW-48 38' 1" 0.71 f 0.55 (0.89) 1697W0035 MW-48 River front -0.11 f 0.53 (0.97) 1697W0036 MW-1 Lafarge -0.04 0.53 (0.96) 1697W0037 MW-2 Lafarge 0.54 f 0.60 (1.oo) 1697W0038 MW-3 Lafarge -0.18 f 0.56 (1.02)
Indian Point Power Station projects/l697/Data Tables/2006-07-14 Interim Data Table Set Six
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 YOFUS I
Radionuclide Concentrationsa(pCi/L)
ORISE Sample NRC Region I I
I I I ID Sample ID Fe-55b Ni-59' Ni-63' H-3d 1697W0033 MW-48 23' 2 -1 & 23e (39) -8.2 k 6.0 (10.5) -1.2 k 7.1 (12.1) 220 k 230 (380) 1697W0034 Mw-48 38' 1" 2 k 23 (39) -11.9 k 6.0 (10.5) 1.9 & 7.2 (12.1) 80 k 220 (380)
~~
1697W0035 I MW-48 River front ~
-0.2 k 7.1 (12.1) 190 f 230 (380) 1697W0036 Mw-1 Lafarge 5.1 k 7.2 (12.1) 150 k 230 (380)
Tl
- 2. 1697W0037 MW-2 Lafarcre 1.8 k 7.2 (12.1) 80 k 220 (380) sY
- 1697W0038 I MW-3 Lafarge -2 23 (39) I -8.3 f 6.0 (10.5) -1.2 7.1 (12.1) 190 f 230 (380) s o\
"The MDCs for each radionuclide are in parentheses.
F3 %e-55 analyzed using procedure AP13, Revision 4.
'P&-59/63 analyzed using procedure AP17, Revision 0.
YN dH-3analyzed using procedure AP2, Revision 15.
0 0
s7 c
'Uncenainties represent the 95% confidence level, based on total propagated uncenainties.
P
TABLE 5 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 II I I ORISE Sample NRC Region I Tc-99 Concentrationsa Sample ID (pCi/L) 1697W0033 MW-48 23' 2" 14 & 19b (32) 1697W0034 MW-48 38' 1" 9 k 19 (32) 1697W0035 MW-48 averfront 24 & 19 (32) 1697W0036 MW-1 Lafarge 23 f 19 (32) 1697W0037 MW-2 Lafarge 14 f 19 (32) 1697W0038 MW-3 Lafarge 13 f 19 (32)
Indian Point Power Station projects/l697/Data Tables/2006-07-14 Interim Data Table Set S i x
RECEIVED OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
+LjidI 2K-gif-r I July 11, 2006 $1..
Mr. Jim Kottan ::--' Jii:- t 4 Pf-1 2: 13 U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road IQng of Prussia, PA 19406
SUBJECT:
FINAL REPORT FOR ANALYSES OF O N E SOIL SAMPLE AND THIRTEEN WATER SAMPLES COLLECTED APRIL 11,2006 THROUGH APRIL 18,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION REPORT N O .
050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received one soil sample and thirteen water samples on April 25,2006 from the Indian Point Power Station in Buchanan, New York. This final letter report contains additional data for the one soil sample that was not presented in the previous interim letter reports. All of the data for the requested analyses are presented in the following tables except for iron-55 for the soil sample. ORISE does not currently have an analytical procedure for iron-55 in soil. The sample identifications and collection data are presented in Table 1. The gamma spectroscopy data, the total ra&ostrontium data, the hard-to-detect beta data (iron-55, nickel-59/63, and tritium), the technetium-99 data, the alpha spectroscopy data, the plutonium-241 data, and the carbon-14 data are in Table 2 through Table 8, respectively. The pertinent procedure references are provided in the specific tables.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request. My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerelv.
Dale Condra, Manager Laboratory RDC:WI:ess Enclosures C: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Ibex-Davin, NRC/NMSS/TWFN 8A23 S. Kirk, ORISE M. Miller, NRC Region I J. Whtte, NRC Region I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager
&.& AQC Pawe Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample NRC Region I Collection Collection ID Sample ID Date Time 1697W0026 MW-47 1" 80' 4/13/2006 11:45 2697W0027 MW-47 2" 56' 4/13/2006 1205 1697W0028 Unit 2 MH#5 4/17/2006 13:OO 1697W0029 Hudson discharge MH-1 4/18/2006 13:30 Indian Point Power Station projects/1697/Data TabIes/2006-07-11Final Data Table Sct Thrcc
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N O N E SOIL SAMPLE AND 13 WATER SAMPLES BY GAMMA SPECTROSCOPY CPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK T h e range of MDCs for the selected radionuclides for the soil sample is 0.05 pCi/g to 0.07 pCi/g and for the water samples is 2.7 pCi/L to 4.4 pCi/L.
bSoil concentrations, P U S , and MDCs are in pCi/g.
'Zero values are due to rounding.
dUncertainties represent the 95% confidence level, based on total propagated uncertainties.
Water concentrations, %PUS,and MDCs are in pCi/L
TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N O N E SOIL SAMPLE AND 13 WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13;CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCS" Sample ID Sample ID
@Ci/g or pCi/L)
~~ ~ ~
1697S0001b MH-1 Shore discharge 0.01 f 0.13' (0.23) 1697W0017d MW-40 4" 200' 0.34 f 0.49 (0.83) 1697W0018 MW-51 4" 200' 0.14 f 0.46 (0.80) 1697W0019 MW-48 1" 37.5' 0.49 f 0.48 (0.80) 11 1697W0020 I MW-48 2" 52' I 0.46 f 0.46 (0.777 11 1697W0021 MW-43 2" 28' -0.09 If: 0.46 (0.83) 1697W0022 MW-43 2" 62' 1.30 f 0.55 (0.83) 1697W0023 MW-41 1 63' 5.01 If: 0.81 (0.91) 1697W0024 MW-41 2" 41' 3.72 _+ 0.65 (0.76) 1697W0025 MW-46 4" 30' 1.23 f 0.50 (0.75) 1697W0026 MW-47 1" 80' 4.08 f 0.74 (0.88) 1697W0027 MW-47 2" 56' 1.19 ii 0.54 (0.83) 1697W0028 Unit 2 MH#5 0.12 f 0.46 (0.82) 1697W0029 Hudson discharge MH-1 0.58 & 0.55 (0.92)
Indian Point Power Station projects/l697/Data Tables/2006-07-11Final Data Table Set Three
TABLE 4 CONCENTRATIONS OF HARD T O DETECT BETA EMITTING RADIONUCLIDES I N O N E SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANWYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample NRC Region I ID Sample ID Fe-55b Ni-59" Ni-63' H-3d 1697S0001e MH-1 Shore discharge NDP~ -0.39 k O.9lg (1.58) -0.5 f 1.1 (1.9) 4.3 f 2.7 (4.4) 1697WOO 17h MW-40 4" 200' 6 f 35" (60) 4.8 f 5.9 (9.8) 4.2 k 5.9 (10.0) 100 f 230 (390) 1697W0018 I MW-51 4" 200' -4 f 35 (60) -0.9 f 5.7 (9.8) 6.1 f 6.0 (10.0) 160 k 230 (390) 1697W0019 I MW-48 1" 37.5' 11 k 35 (60) 8.8 f 5.9 (9.8) 1.7 f 5.9 (10.0) 90 f 230 (390) 9 f 35 (60) 3.9 f 5.8 (9.8) 3.6 1- 5.9 (10.0) 220 f 230 (390)
-12 & 35 (60) 6.1 f 5.9 (9.8) 3.5 k 5.9 (10.0) 230 f 230 (390) 1697W0022 MW-43 2" 62' 14 k 35 (60) 8.1 f 5.9 (9.8) 1.1 f 5.9 (10.0) 40 f 220 (390)
I I 11
~~
1697W0023 MW-41 1" 63' 21 f 36 (60) 5.1 f 5.9 (9.8) 1-2.9 f 5.9 (10.0) 440 f 250 (390) 1697W0024 I MW-41 2" 41' -3 f 35 (60) 10.6 f 6.0 (9.8) 0.4 f 5.8 (10.0) 490 f 250 (390)
-5 k 35 (60) 6.0 f 5.9 (9.8) 3.1 f 5.9 (10.0) 1,510 f 300 (390)
-1 f 35 (60) 2.0 k 5.8 (9.8) 3.6 k 5.9 (10.0) 1,980 k 320 (390) 25 f 36 (60)
~
8.9 f 5.9 (9.8) -0.2 k 5.8 (10.0) 280 f 240 (390) 1697W0028 16 f 35 (60) 21.5 f 6.3 (9.8) -1.2 f 5.8 (10.0) 120 f 230 (390) 1697W0029 I Hudson discharge MH-1 -5 f 35 (60) 1.5 f 5.8 (9.8) I 1.5 k 5.9 (10.0) 1 -210 f 210 (390) 11
%e MDCs for each radionuchde are in parentheses.
bFe-55 analyzed using procedure AP13, Revision 4.
'Ni-59/63 analyzed using procedure AP17, Revision 0.
dH-3analyzed using procedure AP2, Revision 15.
'Soil concentrations, P U S ,and MDCs are in pCi/g.
'No Data Provided. At present, OFUSE does not have an approved procedure for analyzing Fe-55 in soil samples.
gUncertaintiesrepresent the 95% confidence level, based on total propagated uncertainties.
hWater concentrations, TPUs, and iMDCs are in pCi/L.
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN O N E SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, N E W YORK ORISE N R C Region I Tc-99 Concentrations Sample I D Sample I D (pCi/g or pCi/L)
~
1697S0001b E H - 1 Shore discharge I 0.25 k 0.18' (0.30) 1697W0017d MW-40 4" 200' 2 k 19 (32) 1697W0018 MW-51 4" 200' 4 k 19 (32) 1697W0019 MW-48 1" 37.5' 10 k 19 (32) 1697W0020 MW-48 2" 52' -6 k 18 (32) 1697WOO21 1697W0022 1697W0023 MW-41 1 63' (32) 1697W0024 MW-41 2" 41' -4 k 18 (32) 1697W0025 MW-46 4" 30' 6 t 19 (32) 1697W0026 MW-47 1" 80' . 13 k 19 (32) 1697W0027 MW-47 2" 56' -6 k 18 (32) 11 1697W0029 [ HudsondischargeMH-1 1 -1 f 19 (32) 11 "The MDCs for each radionuclide are in parentheses.
bSoil concentrations, P U S , and MDCs are in pCilg.
'Uncertainties represent the 95% confidence level, based on total propagatcd uncertainties.
dWater concentrations, TPUs, and MDCs are in pCi/L.
Indian Point Power Station projects/l697/Data TabIes/2006-07-I 1 Final Data Tablc Set Threc
TABLE G CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N ONE SOIL SAMPLE AND 13 WATER SAMPLES BY ALPHA SPECTROSCOPY AJ?11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa@Ci/g or pCi/L)
Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 MH-l Shore 0.06 f 0.04' (0.05) 0.09 ? 0.04 (0.05) 0.14 f 0.05 (0.05) O.OOd f 0.01 (0.02) 1697S0001 discharge 1697W0017" Mw-40 4" 200' 0.01 f 0.08 (0.16) 0.04 f 0.04 (0.02) -0.03 k 0.08 (0.16) 0.01 f 0.05 (0.10) 1697W0018 MW-51 4" 200' 0.02 f 0.09 (0.16) 0.01 f 0.03 (0.07) 0.05 f 0.07 (0.12) 0.06 ? 0.05 (0.06) 1697W0019 Mw-48 1" 37.5' 0.14 f 0.11 (0.17) 0.00 f 0.03 (0.08) 0.05 f. 0.08 (0.14) 0.01 ? 0.05 (0.10) 1697W0020 Mw-48 2" 52' 0.07 f 0.07 (0.11) -0.03 k 0.04 (0.11) -0.02 k 0.08 (0.16) -0.01 f 0.02 (0.06) 1697W0021 Mw-43 2" 28' 0.07 f 0.10 (0.10) 0.00 k 0.04 (0.09) -0.02 k 0.08 (0.16) 0.00 f 0.04 (0.08) 1697W0022 Mw-43 2" 62' -0.05 f 0.09 (0.18) 0.00 ? 0.04 (0.09) 0.03 k 0.08 (0.15) -0.05 ? 0.06 (0.16) 1697W0023 Mw-41 1" 63' 0.08 f 0.18 (0.32) 0.02 f 0.07 (0.15) -0.02 f 0.11 (0.23) 0.02 ? 0.05 (0.08) 1697W0024 Mw-41 2" 41' 0.02 f 0.13 (0.25) 0.00 f 0.03 (0.09) -0.02 k 0.11 (0.22) -0.03 f 0.03 (0.10) 1697W0025 Mw-46 4" 30' 0.07 f 0.18 (0.32) 0.06 2 0.07 (0.11) 0.04 f 0.12 (0.23) 0.03 k 0.05 (0.09) 1697W0026 Mw-47 1" 80' 0.01 f 0.14 (0.27) 0.01 f 0.08 (0.17) -0.04 k 0.12 (0.25) 0.02 f 0.04 (0.06) 1697W0027 p p Mw-47 2" 56' p
-0.06 f p
0.15 (0.30) 0.03 f 0.06 (0.11) 0.00 f 0.02 (0.06) 1697W0028 p
Unit 2MH#5 p
-0.07 p
f 0.13 (0.28) -0.03 1- 0.13 (0.27) -0.03 f 0.05 (0.12)
Hudson discharge 1697W0029 MH-1 0.05 f 0.10 (0.18) 0.01 f 0.05 (0.10) -0.02 f 0.09 (0.18) 0.01 f 0.04 (0.08)
TABLE G (Continued)
F CONCENTMTIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa (pCi/g for soil or pCi/L for water)
Sample ID SampleID ' Pu-238 P~-3.39/3.40 u-7.34 T J-238 MH-1 Shore 1697S0001 discharge 0.03 k 0.02 (0.02) 0.01 k 0.01 (0.02) 0.48 k 0.07 (0.02) 0.56 k 0.08 (0.03) 1697W0017 MW-40 4" 200' 0.00 k 0.08 (0.16) 0.03 k 0.05 (0.08) 0.63 k 0.14 (0.14) 0.58 k 0.13 (0.07) 1697W0018 MW-51 4" 200' 0.13 k 0.09 (0.12) 0.02 k 0.06 (0.11) 4.69 k 0.53 (0.10) 2.69 k 0.36 (0.09) 1697W0019 MW-48 1" 37.5' 0.01 k 0.08 (0.15) 0.04 k 0.06 (0.10) 6.62 k 0.66 (0.11) 2.44 k 0.32 (0.12) 1697W0020 MW-48 2" 52' 0.09 k 0.08 (0.12) 0.04 t 0.04 (0.02) 0.31 'c_ 0.09 (0.05) 0.21 k 0.08 (0.05) 1697W0021 MW-43 2" 28' 0.16 k 0.08 (0.10) -0.01 k 0.05 (0.11) 0.85 k 0.17 (0.07) 0.82 k 0.17 (0.06) 1697W0022 MW-43 2" 62' 0.00 f 0.08 (0.16) 0.02 k 0.05 (0.09) 6.05 k 0.62 (0.16) 4.44 k 0.49 (0.09) 1697W0023 MW-41 1" 63' 0.17 k 0.10 (0.13) 0.06 k 0.05 (0.06) 1.63 k 0.23 (0.07) 1.25 k 0.20 (0.06) 1697W0024 MW-41 2" 41' 0.08 k 0.11 (0.19) 0.02 k 0.04 (0.09) 0.76 k 0.16 (0.08) 0.71 k 0.15 (0.05) 1697W0025 Mw-46 4" 30' 0.07 k 0.09 (0.09) 0.07 k 0.06 (0.07) 0.87 k 0.17 (0.10) 0.56 f 0.14 (0.09) 1697W0026 MW-47 1" 80' 0.05 k 0.11 (0.11) 0.06 k 0.04 (0.02) 1.22 k 0.19 (0.06) 0.99 k 0.17 (0.05) 1697W0027 MW-47 2" 56' 0.06 k 0.08 (0.08) 0.04 k 0.04 (0.02) 3.76 'c_ 0.43 (0.07) 2.45 k 0.32 (0.02) 1697W0028 Unit 2MH#5 0.13 k 0.10 (0.10) -0.01 k 0.06 (0.12) 0.20 k 0.10 (0.11) 0.20 k 0.10 (0.11)
Hudson discharge 1697W0029 MH-1 0.10 k 0.10 (0.10) 0.05 f 0.04 (0.02) 0.04 k 0.06 (0.09) 0.05 k 0.04 (0.02)
"The MDCs are in parentheses.
bSoil concentrations,TPUs, and MDCs are in pCi/g.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
dZero values are due to rounding.
'Water concentrations,TPUs, and MDCs are in pCi/L.
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 (PU-241)
I N O N E SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APIO, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK PU-241 ORISE NRC Region I Concentrationsa Sample ID Sample ID
@Ci/g or pCi/L) 1697SOOOl MH-1 Shore discharge 4.2 t 3.5" (5.8) 1697W0017d Mw-40 4" 200' 4 k 13.7 (23) 11 1697W0018 I Mw-51 4" 200' I 0' & 15.5 (27) 11 1697W0019 I MW-48 1" 37.5' I -10 t 13.8 (24) 1697W0020 Mw-48 2" 52' -9 & 13.4 (23) 1697W0021 Mw-43 2" 28' -5 t 14.2 (25) 1697W0022 MW-43 2" 62' -3 & 21.8 (38) 1697W0023 MW-41 1" 63' 6 t 15.2 (26) 1697W0024 MW-41 2" 41' -2 t 16.1 (28) 1697W0025 MW-46 4" 30' -4 & 13 (23) 1697W0026 MW-47 1" 80' 2 & 14 (25) 1697W0027 MW-47 2" 56' 2 ? 14 (24) 1697W0028 Unit 2 MH#5 0 5 14 (24) 11 1697W0029 I HudsondischargeMH-1 I 6 t 14 (23)
- rhe MDCs are in parentheses.
bSoil concentrations, TPUs, and MDCs arc in pCi/g.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data TabIes/2006-07-11 Final Data Table Set Three
TABLE 8 CONCENTRATIONS OF CARBON-14 (C-14)
IN O N E SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN P O I N T POWER STATION BUCHANAN, N E W YORK C-14 ORISE NRC Region I Concentrationsa Sample I D Sample I D
@Ci/g or pCi/L)
~~~ ~ ~~
1697S0001b MH-1 Shore discharge -0.3 k 1.3" (2.2) 1697W0017d MW-40 4" 200' 15.9 k 16.3 (27) 1697W0018 MW-51 4" 200' 17.1 5 16.3 (27) 1697W0019 MW-48 1" 37.5' 11 k 16.2 (27) 1697WO020 MW-48 2" 52' 1.39 k 16 (27)
~~
1697W0021 ~
MW-43 2" 28' 8.33 k 16.1 (27) 1697WOO22 MW-43 2" 62' 16.6 _+ 16.3 (27) 1697WOO23 MW-41 1" 63' 2.78 k 16 (27) 1697W0024 MW-41 2" 41' 8.33 k 16.1 (27) 1697W0025 MW-46 4" 30' 1697W0026 MW-47 1" 80' 0 5 16 (28) 1697W0027 MW-47 2" 56' -5 _+ 16 (28) 1697W0028 Unit 2 MH#5 -9 k 16 (28) 11 1697W0029 I HudsondischargeMH-1 I 2 _+ 16 (28) 11 "The MDCs arc in parentheses.
'Soil concentrations, P U S , and MDCs are in pCilg.
'Uncertainties represent the 95% confidence level, based on total propagatcd uncertainties.
Indian Point Power Station projects/l697/Data Tables/2006-07-ll Final Data Table Set Three
O R I S E REc E I4 ED OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION pEGla?s 1 July 7,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IOng of Prussia, PA 19406
SUBJECT:
REPORT FOR REQUESTED ANALYSES OF FOUR SOIL SAMPLES, SET FIVE, COLLECTED MAY 10,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT N O . 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak &dge Institute for Science and Education (ORISE) received set five, consisting of four soil samples, on May 17,2006 from the Indian Point Power Stationin Buchanan, New York. The sample identifications and collection data are presented in Table 1. The gamma spectroscopy, total radtostrontium, hard to detect beta emitters (carbon-14, nickel-59/63, and tritium), technetium-99, alpha spectroscopy, and plutonium-241 data are provided in Tables 2 through Table 7, respectively. The pertinent procedure references are provided in the specific tables.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are avdable for your review upon request.
ORISE does not have a procedure for analyzing iron55 in soil and cannot report any data for &on55 in soil samples at this time.
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:ess Enclosures cc: B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. Knox-Davin, NRC/NMSS/TWFN 8A23 S. IGrk, ORISE M. Miller, NRC Region I J. White, NRC Regon I File 1697 Distribution approval and concurrence : Initials Technical Management Team Member Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample NRC Region I Collection Collection ID Sample ID Date Time 1
1697S0002 Verplank 5/10/2006 11:50 1697S0003 White Beach 5/10/2006 12:lO 1697S0004 Manitou 5/10/2006 13:OO 1697S0005 Lent's Cove 5/10/2006 13:30 Indian Point Power Station projeas/l697/Data Tables/2006-07-07 Data Tables Set Five
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN SOIL SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID NRC Region I Radionuclide Concentrationsa (pCi/g) I Sample - ID CO-58 CO-60 CS-134 CS-137 I/
1 169730002 I Verplank -0.01 f 0.02b 0.01 f 0.02 0.04 f 0.03 0.21
- 0.03 1697S0003 White Beach 0.00' f 0.01 0.03 f 0.02 0.01 f 0.02 0.01 f 0.01
-0.01 f 0.03 -0.01 f 0.02 0.05 f 0.02 0.10 k 0.02
-0.03 f 0.03 -0.01 f 0.03 0.05 f 0.03 0.06 f 0.02 "The range of MDCs for the selected radionuclides is 0.02 pCi/g to 0.05 pCi/g.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero values are due to rounding.
TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN SOIL 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"(pCi/g) 1697S0002 Verplank -0.02 f 0.1Ob (0.18) 1697S0003 White Beach 0.01 f 0.11 (0.19) 1 1697S0004 1697S0005 a M D C are
~ in parentheses.
Manitou Lent's Cove 0.12 0.08 f
0.12 0.11 (0.20)
(0.19) buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station pprojects/l697/Data Tables/2006-07-07 Data Tables Set Five
-a \
9 V
9.
TABLE 4 e
CONCENTRATIONS OF HARD T O DETECT BETA EMITTING RADIONUCLIDES I N SOIL SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa(pCi/g)
ORISE Sample NRC Region I ID Sample ID C-14b Ni-59" Ni-63" H-3d 1697S0002 Verplank 0.45 k 0.87" (1.47) 0.70 k 0.95 (1.61) -1.0 k 1.1 (1.9) O.Of k 1.7 (2.9) 1697S0003 White Beach 0.59 k 0.86 (1.45) -0.71 k 0.93 (1.62) -0.5 k 1.1 (1.9) 0.8 k 1.7 (2.8) 1697S0004 Manitou 0.51 f. 0.82 (1.38) -1.26 t 0.90 (1.60) -0.3 2 1.1 (1.9) -0.4 k 1.5 (2.7) 1697S0005 Lent's Cove 0.20 k 0.92 (1.57) -0.70 k 0.91 (1.59) 0.1 t 1.1 (1.9) 0.5 k 1.8 (3.1)
"I'he MDCs for each radionuclidc arc in parenthcses.
bC-14 analyzed using proccdurc AP6, Revision 15.
'Ni-59/63 analyzed using procedure AP17, Revision 0.
dH-3analyzed using procedure AP6, Revision 15.
eUncertaintiesrepresent the 95% confidcncc level, based on total propagated unccrtainties W f,
=1 Lcro values are due to rounding.
P
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99(Tc-99)
IN SOIL SAMPLES BY LIQUID SCINTILLATIONANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample NRC Region I Tc-99 Concentrationsa ID Sample ID (PCi/d I I I I
'The MDCs are in parentheses.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projectdl 6971Data Tabled2006-07-07 Data Tables Set Five
TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SOIL SAMPLES BY ALPHA SPE(XROSC0PY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN,NEW YORK
/I 0RIS;:mple I NRCRegionI Sample ID Am-241 Radionuclide Concentrationsa(pCi/g)
Gn-242 I Gn-243/244 I Nv-237 1697S0002 Verplank 0.02 k 0.04b (0.08) 0.02 k 0.02 (0.01) 0.01 k 0.04 (0.07) 0.00' k 0.01 (0.02) 1697S0003 White Beach 0.01 k 0.04 (0.08) -0.01 f 0.02 (0.05) -0.02 f 0.03 (0.07) 0.00 0.01 (0.02) 1697S0004 Manitou -0.02 + 0.03 (0.07) -0.01 + 0.01 (0.03) -0.01 + 0.02 (0.05) -0.01 + 0.02 (0.04)
U 1697S0005 I Lent's Cove I 0.02 f 0.04 (0.07) 0.01 k 0.02 (0.03) 0.01 & 0.04 (0.07) 0.01 k 0.01 (0.02)
PP
TABLE 6 (Continued)
ORISE Sample NRC Region I Radionuclide Concentrationsa (pCi/ g)
ID Sample ID Pu-238 Pu-239/240 U-234 U-238 1697S0002 Verplank 0.01 f 0.02 (0.03) 0.01 f 0.01 (0.01) 0.42 -i: 0.07 (0.02) 0.40 f 0.07 (0.02) 1697S0003 White Beach 0.01 k 0.02 (0.03) 0.01 & 0.01 (0.02) 0.26 k 0.05 (0.03) 0.34 & 0.06 (0.03) 1697S0004 Manitou 0.00 f 0.03 (0.06) 0.00 f 0.02 (0.04) 1.42 f 0.14 (0.02) 1.37 f 0.14 (0.02) 1697S0005 Lent's Cove 0.05 f 0.03 (0.03) 0.00 -i: 0.01 (0.03) 1.53 f 0.16 (0.02) 1.41 f 0.15 (0.02)
T h e MDG are in parentheses.
%Jnce&ties represent the 95% confidencelevel, based on total propagateduucerrainties.
'Zero values are due to rounding.
TABLE 7 ORISE Sample NRC Region I Sample Pu-241Concentrationsa ID ID (PCik) 1 1697S0002 I Verplank I 1.7 & 3Sb (5.9) 11 11 I I 11 I
1697S0003 1697S0004 1697S0005 White Beach Manitou Lent's Cove 4.6 1.3
-0.3 &
4.0 6.2 4.0 (6.6)
(10.6)
(6.9)
I
~~~~ ~
'The MDG are in parentheses.
bncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2006-07-07 Data Tables Set Five