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
September 1,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
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 Distribution approval and concurrence :
Technical Management Team Member Quality Manager Initials, -
liw 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. Ihox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Region I File 1697 E. Abelquist, ORISE S. JSirk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD @orau.gov
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1697W0052 1697W0053 1697W0054 1697W0055 1697W0056 1697W0057 11 1697W0051 1
MW-50El67' I 8/1/2006 I 11:30 MW-50 El 42' 8/1/2006 11:15 MW-49 El 25' 8/1/2006 9:28 MW-49 El 65' 8/1/2006 950 MW-49 El 42' 8/1/2006 9:35 MW-58 El 71' 8/2/2006 9:3 1 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
~~~
~
~
~
1697W0058 dischargecanal
-2.0 f 2.3 1697W0059 MW-40
-1.5 f 1.7 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 ID Sample ID Radio CO-58
_ _ _ _ ~
~
1697W0051 7 MW-50El 67' 1-03 f 3.1t 1697W0052 I MW-50El42' I 1.3 f 2.3 1697W0053 I MW-49 El 25' 1 -0.7 f 1.8 1697W0054 I MW-49El 65' I 1.1 f 2.3 1697W0055 I MW-49El 42' 1-1.4 f 2.4 1697W0056 I MW-58El 71' 1-0.1 f 2.5
~
1@7W0&7 I MW-38 1-0.9 f 2.5 iuclide Concentrationsa (
Co-60 I Cs-134 0.7 f 2.8 0.6 f 2.9 2.1 f 2.1 -0.3 f 2.1 0.6 f 1.6 -0.1 f 1.7 0.9 f 2.3 3.2 f 2.3 0.3 f 2.2 1.3 f 2.3 3.0 f 2.3 2.1 f 2.2
-0.5 f 2.81 0.2 f 2.4
-1.4 f 2.41 0.8 f 2.4
)Ci/L)
CS-137 2.0 f 2.5
-2.6 f 4.5 0.2 f 1.6 0.5 f 2.1
-2.1 f 4.5 1.1
- 2.1 3.8 f 2.3 1.3 f 1.5
-0.6 f 1.9
%e range of MDCs for the selected radionuclides is 2.8 pCiL to 4.4 pCilL.
buncertainties represent 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 ORISE NRC Region I Sample ID Sample ID 1697W005 1 MW-50 El 67' 1697W0052 MW-50 El 42' 1697W0053 MW-49 El 25' 1697W0054 MW-49 El 65' 1697W0055 MW-49 El 42' 1697W0056 MW-58 El 71' 1697W0057 MW-38 1697W0058 discharge canal 1697W0059' MW-40 L
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 Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) 30.0 1.7b (0.8) 4.75 0.77 (0.85) 11.7 1.o (0.8) 16.3 1.2 (0.8) 19.7 1.4 (0.8) 0.65 f
0.51 (0.82) 0.37 0.45 (0.76) 0.20 0.45 (0.78) 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 TO DETECT BETA EMITTING RADIONUCLIDES IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK V a 2
(P 8 P
5 E z g
P 5
E
- 2.
- 0.
a
-I
\\
P 4
?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.
dH-3 analyzed using procedure AP2, Revision 15.
Uncertainties represent the 95% confidence level, based on total propagated unceamnties.
P 4 2
2:
TABLE 5 ORISE Sample ID 1697W005 1 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 (PWL)
MW-50 El 67'
-3.9 k 9.1b (15.8)
I1 I
I 1
1697W0052 1697W0053 1697W0054 1697W0055 1697W0056 1697W0057 1697W0058 1697W0059 MW-50 El 42' 0.1 k
9.2 (15.8)
MW-49 El 25'
-6.3 k
9.0 (15.8)
MW-49 El 65'
-8.5 k 9.0 (15.8)
MW-49 El 42'
-8.6 k
9.0 (15.8)
MW-58 El 71'
-5.4 L
9.1 (15.8)
MW-38
-4.0 9.1 (15.8) discharge canal 4.3 k 9.3 (15.8)
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 NO. 06-0011 Distribution approval and concurrence :
Technical Management Team Member Quality Manager
Dear Mr. Kottan:
Initials
~
LSFW I
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 M. Miller, NRC Region I File 1697 S. Kirk, ORISE J. m t e, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION ORISE Sample ID 1697W0047 11 1697W0048
~~
~
"No data provided.
B U C W A N, NEW YORK NRC Region I Collection Sample ID MW 49-25 I 7/12/2006 M W 49-42 I 7/12/2006 MW 49-65 I 7/12/2006 MW 49-51 I 7/12/2006
_ _ _ _ _ ~
Collection Time NDP" NDP NDP NDP Indian Point Powcr Station projects/lG97/Data Tables/2006-08-22 Data Tables Set Eight
TABLE 2 ORISE Sample ID 1697W0047 1697W0048 1697W0049 1697W0050 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID CO-58 CO-60 cs-134 cs-137 b
MW 49-25
-1.1 k 2.5 1.1 k 2.5 0.2 k 2.7 0.3 k 2.3 MW 49-42
-0.7 k 2.1 -1.7 k 3.5 -0.6 k 2.1 2.0 k 4.6 MW 49-65 1.7 k 2.5 0.2 k 2.1 -2.2 k 2.2 -0.1 k 2.1 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 ORISE Sample ID 1697W0047 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 NRC Region I Radionuclide Concentrations, Sample ID Mw 49-25 16.0 k
1.7b (1.7)
I TPUs, and MDCS" @Ci/L) 1697W0048 Mw 49-42 1697W0049 Mw 49-65 1697W0050 Mw 49-51 22.9 k
1.9 (1.6) 18.0 k
1.7 (1.6) 0.24 k
0.86 (1.48)
Indian Point Power Station projects/l697/Data Tables/2006-08-22 Data Tables Set Eight
I Fe-55b Ni-59" Ni-63" xTABLE 4 H-3d U.
Y 28 It_- 28' (47) 30 k 28 (47) 26 f 28 (47) 31 k 28 (47)
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
-9.5 f 4.8 (8.5) 11.1 k 7.7 (12.7) 12,740 k 690 (380)
-20.2 f 4.7 (8.5) 19.0 k 7.9 (12.7) 8,060 k 540 (380)
-9.7 k 4.8 (8.5) 10.0 k 7.7 (12.7) 4,780 k 430 (380)
-8.1 k 4.9 (8.5) 4.8 2 7.5 (12.7) 30
? 210 (380)
ORISE NRC Region I Sample ID Sample ID 1697W0047 MW 49-25 1697W0048 1697W0049 1697W0050 7
a
'%e MDCs for each radionuclide are in parenthescs.
bFe-55 analyzed using procedure AP13, Revision 4.
'Ni-59/63 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.
0 W
4
\\
+
!? a 3
e D
1697W0047 1697~0048 1697W0049 Indian Point Power Station Mw 49-25 10.0
_+
9.0b (14.9)
Mw 49-42
-0.6 k 8.7 (14.9)
MW 49-65 9.4 9.0 (14.9)
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (TC-99)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 BUCHANAN, NEW YORK INDIAN POINT POWER STATION II I
I 1
NRC Region I Tc-99 Concentrationsa
/I S a 2 ; D I Sample ID 11 1697W0050 I M W 49-51 I 8.9
-t 8.9 (14.9) 11 "The MDCs are in parentheses.
buncertainties represent the 95% confidence level, bascd on total propagated uncertainties.
projects/l697/Data Tables/2006-08-22 Data 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-1 4, 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 Distribution approval and concurrence :
Technical Management Team Member Quality Manager Initials August 18,2006 My contact information is listed below. You may also contact Wade Ivey at 865.576.91 84 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:WPI:db Enclosures cc:
B. Watson, NMSS/DWMEP/DD/SP 7E18 E. I(nox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Region I File 1697 E. Abelquist, ORISE S. IGrk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 OFUSE NRC Region I Collection Sample ID Sample ID Date Collection 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 projects/l697/Data Tables/2006-08-18 Data Table Set Four
TABLE 2 ORISE Sample ID 1697W0030 1697W003 1 1697W0032 Radionuclide Concentrationsa (pCi/L)
NRC Region I Sample ID co-58 CO-60 CS-134 CS-137 bottom layer 2.5 f
2.2b 2.5 f 3.7 2.5 f
2.3 2,895 f
91 2,870 f
90 unit 2 manhole #5
-0.5 f
1.5
-0.2 f
1.6 1.1 f 2.2 0.1 f 2.7 bulk layer
-2.4 f
2.1
-0.1 f 2.3 1.5 f 2.8 G
6
TABLE 3 ORISE Sample ID 1697W0030 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 TPUs, and MDCsa (pCi/L) bottom layer 352 f
1 lb (1)
I (0.96) bulk layer 349 f
11 1697w0031 1697W0032 unit 2 manhole #5 0.18 0.55 "MDCs are in parentheses.
buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2006-08-18 Data Table Sct Four
TABLE 4 ORISE Sample ID 1697W0030 1697W0031 1697W0032 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)
NRC Region I Sample ID C-14b Fe-55 Ni-5gd Ni-63d H-3e 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) 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) 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 Sample ID Sample ID 1697W0030 bottom layer 1697W0031 bulk layer 1697W0032 unit 2manhole #5 Tc-99 Concentrationsa
@Ci/L)
Ob k 17' (30) 13
?
18 (30) 10.7 2 9.2 (15.3)
T h e hlDCs are in parentheses.
Lcro value is due to rounding.
b-
'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
[(<
9. < t,: * \\I,!' T
)
O R I S E I
.<*; i '1 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION 1
Distribution approval and concurrence :
Technical Management Team Member Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406 Initials A' J d /6
SUBJECT:
SECOND INTERIM REPORT FOR REQUESTED ANALYSES OF TWO VEGETATION AND ASSOCIATED WATER SAMPLES, SET SEVEN, COLLECTED BETWEEN JUNE 14 AND JUNE 22,2006 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 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 ths 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 M. Miller, NRC Region I File 1697 S. IGrk, ORISE J. Lhte, NRC Region I Voice: 86 5.24 1.3242 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 1697V0001 and 1697V0002.
Indian Point Power Station projects/l697/Data Tables/2006-08-11 2nd Interim Data Table Set Seven
B ORISE Sample ID TABLE 2 Radionuclide Concentrations NRC Region I Sample ID CO-58 CO-60 cs-134 cs-137 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN VEGETATION SAMPLES GAMMA SPECTROSCOPY CP1, REVISIO 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697V0O0la 1697V0002 1697W0045d 1697W0046 Verplanck 0.09 5 O.lOb 0.08 1- 0.10 0.02 k 0.08 0.15 k 0.13 Lent's Cove 0.00' f. 0.03 -0.01 k 0.03 0.06 k 0.04 0.08 k 0.04 Lent's Cove
-0.4 f. 6.5 0.3 k 4.9 0.4 k 5.7 1.3 f 4.9 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 ORISE Sample ID 1697V0001 1697V0002 1697W0039 1697W0040 1697w0041 1697W0042 1697W0043 1697W0044 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, TPUs, and MDCs" @Ci/g wet weight for vegetation or pCi/L for water)
NRC Region I Sample ID Verplanck
-0.01 f
O.Olb (0.02)
Lent's Cove 0.00' f
0.04 (0.07)
MW-30 72' 0.33 0.77 (1.32)
MW-30 74' 0.34 f
0.81 (1.38)
MW-30 78'
-0.40
-t 0.75 (1.36)
MW-30 83' 0.40 k
0.72 (1.24)
MW 40'
-0.66 f
0.93 (1.70)
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-08-11 2nd Interim Data Table Sct Seven
TABLE 4 ORISE NRC Region I Sample ID Sample ID CONCENTRATIONS OF NICKEL-59 (Ni-59)
AND NICKEL-63 (Ni-63)
I N VEGETATION SAMPLES BY LIQUID SCINTILLATION ANALYSIS Ap 17, REVISION 0; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa @Ci/g)
Ni-59 Ni-63 1697V0001 1697V0002 Verplanck
-0.02
?
O.OZb (0.03) 0.02 & 0.03 (0.05)
Lents Cove
-0.18 0.07 (0.13) 0.17 & 0.11 (0.18)
~~
The 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 FOR SCIENCE AND EDUCATION Distribution approval and concurrence :
Technical Management Team Member Quality Manager August 4,2006 Initials 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 JUNE 14 AND JUNE 22, 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 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 L' i cc:
B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE --
E. Ihox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Region I File 1697 S. IGrk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
ORISE Sample ID 1697W0039 1697W0040 1697W0041 1697W0042 1697W0043 1697W0044 TABLE 1 NRC Region I Collection Collection Sample ID Date Time Mw-30 72' 6/23/06 13:30 Mw-30 74' 6/23/06 1050 Mw-30 78' 6/22/06 14:lO Mw-30 83' 6/22/06 11:40 Mw 40' 6/2 1/06 9:48 Mw 200' 6/20/06 10:20 SAMPLE IDENTIFICATIONS AND COLLECI'ION DATA INDIAN POINT POWER STATION BUCHANAN, NEWYORK 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 ORISE Sample 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 NRC Region I Radionuclide Concentrationsa @Ci/L)
Sample ID Fe-55b Ni-59' I
Ni-63' I
H-3d 1697W0039 1697W0040 1697W0041 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)
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)
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)
-3 3.
n ?
I v
6 3
z 3 O
e bFe-55 analyzed using procedure AP13, Revision 4.
'Ni-59/63 analyzed using procedure AP17, Revision 0 dH-3 analyzed using procedure AP2, Revision 15.
0 Unccrtaintics rcprcsent the 95% confidence level, based on total propagated uncertainties.
fiero values are due to rounding.
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) 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)
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)
TABLE 4 ORISE Sample NRC Region I ID Sample ID 1697W0039 Mw-30 72' 1697w0040 Mw-30 74' 1697W0041 Mw-30 78' 1697W0042 Mw-30 83' 1697W0043 Mw 40' 1697W0044 Mw 200' 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 Tc-99 Concentrationsa (pCi/L) 5
?
18b (30) 18 k 18 (30) 10 k 18 (30) 14 k 18 (30) 7 k
18 (30) 3 k 18 (30)
Indian Point Power Station projects/l697/Data Tables/2006-08-04 1st Interim Data Table Set Seven
July 14,2006 Distribution approval and concurrence :
Technical Management Team Member Quality Manager 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 Initials
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 M. M e r, NRC Region I File 1697 S. Kirk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample ID 1697W0033 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time W - 4 8 23' 2" 6/9/2006 11:15 I
I 1697W0034 1697 WOO3 5 1697W0036 1697W0037 1697W0038 Mw-48 38' 1" 6/9/2006 11:30 W - 4 8 River front 6/9/2006 11:30 MW-1 Lafarge 6/6/2006 1350 MW-2 Lafarge 6/6/2006 12:19 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 4 TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK The nnge of MDCs for the selected radionuchdes IS 2 7 pG/L to 4 2 pWL hvnce-ties represent the 95% confidence level, based on total propagated uncertaumes
TABLE 3 ONSE NRC Region I Sample ID Sample ID 1697W0033 MW-48 23' 2" 1697W0034 MW-48 38' 1" 1697W0035 MW-48 River front 1697W0036 MW-1 Lafarge 1697W0037 MW-2 Lafarge 1697W0038 MW-3 Lafarge 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 Radionuclide Concentrations, TPUs, and MDCs" (pCi/L)
-0.02 f
0.56b (1.01) 0.71 f
0.55 (0.89)
-0.11 f
0.53 (0.97)
-0.04 0.53 (0.96) 0.54 f
0.60 (1.oo)
-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 ORISE Sample ID 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 NRC Region I Sample ID I
-1.2 k 7.1 (12.1) 1.9
& 7.2 (12.1)
-0.2 k 7.1 (12.1) 5.1 k 7.2 (12.1) 1.8 k 7.2 (12.1)
-1.2 7.1 (12.1)
H-3d 220 k 230 (380) 80 k 220 (380) 190 f 230 (380) 150 k 230 (380) 80 k 220 (380) 190 f 230 (380) 1697W0033 1697W0034 1697W0035 I MW-48 River front MW-48 23' 2
Mw-48 38' 1"
~~
1697W0036 1697W0037 1697W0038 I MW-3 Lafarge
~
Mw-1 Lafarge MW-2 Lafarcre Radionuclide Concentrationsa (pCi/L)
I I
I Fe-55b I
Ni-59'
-1 & 23e (39)
-8.2 k 6.0 (10.5) 2 k 23 (39)
-11.9 k 6.0 (10.5)
-2 23 (39) I -8.3 f 6.0 (10.5)
Tl 2.
s 3
s Y -
o\\
"The MDCs for each radionuclide are in parentheses.
%e-55 analyzed using procedure AP13, Revision 4.
'P&-59/63 analyzed using procedure AP17, Revision 0.
dH-3 analyzed using procedure AP2, Revision 15.
'Uncenainties represent the 95% confidence level, based on total propagated uncenainties.
F Y
N 0
0 s 7
c P
TABLE 5 ORISE Sample 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 (pCi/L)
II I
I 1697W0033 1697W0034 1697W0035 1697W0036 1697W0037 1697W0038 MW-48 23' 2" 14 19b (32)
MW-48 38' 1" 9
k 19 (32)
MW-48 averfront 24 19 (32)
MW-1 Lafarge 23 f 19 (32)
MW-2 Lafarge 14 f
19 (32)
MW-3 Lafarge 13 f 19 (32)
Indian Point Power Station projects/l697/Data Tables/2006-07-14 Interim Data Table Set Six
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION RECEIVED 2K-gif-r I July 11, 2006
$1..
+ L j i d I Distribution approval and concurrence :
Technical Management Team Member Quality Manager Mr. Jim Kottan ::--'
Jii:- t 4 U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road IQng of Prussia, PA 19406 Pf-1 2: 13 Initials
.& AQC Pawe
SUBJECT:
FINAL REPORT FOR ANALYSES OF ONE 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 NO.
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 M. Miller, NRC Region I File 1697 S. Kirk, ORISE J. Whtte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample NRC Region I Collection ID Sample ID Date Collection Time Indian Point Power Station 1697W0026 MW-47 1" 80' 4/13/2006 2697W0027 MW-47 2" 56' 4/13/2006 1697W0028 Unit 2 MH#5 4/17/2006 1697W0029 Hudson discharge MH-1 4/18/2006 projects/1697/Data TabIes/2006-07-11 Final Data Table Sct Thrcc 11:45 1205 13:OO 13:30
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN ONE SOIL SAMPLE AND 13 WATER SAMPLES BY GAMMA SPECTROSCOPY CPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK The 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 ORISE Sample ID CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N ONE 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, TPUs, and MDCS"
@Ci/g or pCi/L)
NRC Region I Sample ID
~~
~
~
1697S0001b MH-1 Shore discharge 1697W001 7d MW-40 4" 200' 1697W0018 MW-51 4" 200' 1697W0019 MW-48 1" 37.5' 0.01 f
0.13' (0.23) 0.34 f
0.49 (0.83) 0.14 f
0.46 (0.80) 0.49 f
0.48 (0.80) 11 1697W0020 I
MW-48 2" 52' I
0.46 f
0.46 (0.777 11 1697W0021 1697W0022 1697W0023 1697W0024 1697W0025 1697W0026 MW-43 2" 28'
-0.09 If:
0.46 (0.83)
MW-43 2" 62' 1.30 f
0.55 (0.83)
MW-41 1 63' 5.01 If:
0.81 (0.91)
MW-41 2" 41' 3.72
_+
0.65 (0.76)
MW-46 4" 30' 1.23 f
0.50 (0.75)
MW-47 1" 80' 4.08 f
0.74 (0.88) 1697W0027 1697W0028 1697W0029 Indian Point Power Station MW-47 2" 56' 1.19 ii 0.54 (0.83)
Unit 2 MH#5 0.12 f
0.46 (0.82)
Hudson discharge MH-1 0.58 0.55 (0.92) projects/l697/Data Tables/2006-07-11 Final Data Table Set Three
TABLE 4 Ni-59" CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES Ni-63' H-3d IN ONE SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANWYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
-0.39 k O.9lg (1.58) 4.8 f 5.9 (9.8)
-0.9 f 5.7 (9.8)
ORISE Sample NRC Region I ID Sample ID
-0.5 f 1.1 (1.9) 4.3 f 2.7 (4.4) 4.2 k 5.9 (10.0) 100 f 230 (390) 6.1 f 6.0 (10.0) 160 k 230 (390) 1697S0001 e MH-1 Shore discharge 1 697 WOO 1 7h MW-40 4" 200' 8.8 f 5.9 (9.8) 3.9 f 5.8 (9.8) 6.1 f 5.9 (9.8) 8.1 f 5.9 (9.8) 1697W0018 I MW-51 4" 200' 1.7 f 5.9 (10.0) 90 f 230 (390) 3.6 1-5.9 (10.0) 220 f 230 (390) 3.5 k 5.9 (10.0) 230 f 230 (390) 1.1 f 5.9 (10.0) 40 f 220 (390) 1697W0019 I MW-48 1" 37.5' 10.6 f 6.0 (9.8) 6.0 f 5.9 (9.8) 2.0 k 5.8 (9.8) 8.9 f 5.9 (9.8) 21.5 f 6.3 (9.8) 1697W0022 MW-43 2" 62' 0.4 f 5.8 (10.0) 490 f 250 (390) 3.1 f 5.9 (10.0) 1,510 f 300 (390) 3.6 k 5.9 (10.0) 1,980 k 320 (390)
-0.2 k 5.8 (10.0) 280 f 240 (390)
-1.2 f 5.8 (10.0) 120 f 230 (390)
~~
1697W0023 I
MW-41 1" 63' 1697W0024 I MW-41 2" 41' 1697W0028 Fe-55b NDP~
6 f 35" (60)
-4 f 35 (60) 11 k 35 (60) 9 f 35 (60) 14 k 35 (60)
-12 & 35 (60) 21 f 36 (60)
-3 f 35 (60)
-5 k 35 (60)
-1 f 35 (60) 25 f 36 (60)
~
16 f 35 (60)
-5 f 35 (60) 5.1 f 5.9 (9.8) 1-2.9 f 5.9 (10.0) I 440 f 250 (390) 11 1697W0029 I Hudson discharge MH-1
%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-3 analyzed 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.
gUncertainties represent the 95% confidence level, based on total propagated uncertainties.
hWater concentrations, TPUs, and iMDCs are in pCi/L.
1.5 f 5.8 (9.8) I 1.5 k 5.9 (10.0) 1 -210 f 210 (390) 11
1697W0025 1697W0026 1697W0027 TABLE 5 MW-46 4" 30' 6
t 19 (32)
MW-47 1" 80' 13 k 19 (32)
MW-47 2" 56'
-6 k
18 (32)
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, NEW YORK ORISE NRC Region I Tc-99 Concentrations Sample ID Sample ID (pCi/g or pCi/L) 1 697S0001b E H - 1 Shore discharge I 0.25 k 0.1 8' (0.30)
~
1697W001 7d 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) 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 ORISE NRC Region I Sample ID Sample ID MH-l Shore 1697S0001 discharge 1697W0017" Mw-40 4" 200' 1697W0018 MW-51 4" 200' 1697W0019 Mw-48 1" 37.5' 1697W0020 Mw-48 2" 52' 1697W0021 Mw-43 2" 28' 1697W0022 Mw-43 2" 62' 1697W0023 Mw-41 1" 63' 1697W0024 Mw-41 2" 41' 1697W0025 Mw-46 4" 30' 1697W0026 Mw-47 1" 80' 1697W0027 Mw-47 2" 56' 1697W0028 Unit 2MH#5 1697W0029 MH-1 p
p p
Hudson discharge 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 Radionuclide Concentrationsa @Ci/g or pCi/L)
Am-241 Cm-242 Cm-243/244 Np-237 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) 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) 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) 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) 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) 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)
-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) 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) 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) 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) 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)
-0.06 f 0.15 (0.30) 0.03 f 0.06 (0.11) 0.00 f 0.02 (0.06) p p
p p
-0.07 f 0.13 (0.28)
-0.03 1- 0.13 (0.27) -0.03 f 0.05 (0.12) 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)
ORISE NRC Region I Sample ID SampleID MH-1 Shore 1697S0001 discharge 1697W0017 MW-40 4" 200' 1697W0018 MW-51 4" 200' 1697W0019 MW-48 1" 37.5' 1697W0020 MW-48 2" 52' 1697W0021 MW-43 2" 28' 1697W0022 MW-43 2" 62' 1697W0023 MW-41 1" 63' 1697W0024 MW-41 2" 41' 1697W0025 Mw-46 4" 30' 1697W0026 MW-47 1" 80' 1697W0027 MW-47 2" 56' 1697W0028 Unit 2MH#5 1697W0029 MH-1 Hudson discharge F
Radionuclide Concentrationsa (pCi/g for soil or pCi/L for water)
Pu-238 P~-3.39/3.40 u-7.34 T J-238 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) 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) 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) 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) 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) 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) 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) 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) 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) 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) 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) 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) 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) 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)
CONCENTMTIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK "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 ONE SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APIO, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID 1697SOOOl 1697W0017d PU-241 NRC Region I Sample ID Concentrationsa
@Ci/g or pCi/L)
MH-1 Shore discharge 4.2 t 3.5" (5.8)
Mw-40 4" 200' 4
k 13.7 (23) 11 1697W0018 I Mw-51 4" 200' I 0'
& 15.5 (27) 1697W0020 1697W0021 1697W0022 1697W0023 11 1697W0019 I MW-48 1" 37.5' I -10 t 13.8 (24)
Mw-48 2" 52'
-9
& 13.4 (23)
Mw-43 2" 28'
-5 t 14.2 (25)
MW-43 2" 62'
-3
& 21.8 (38)
MW-41 1" 63' 6 t 15.2 (26) 1697W0024 1697W0025 1697W0026 1697W0027 1697W0028 MW-41 2" 41'
-2 t 16.1 (28)
MW-46 4" 30'
-4
& 13 (23)
MW-47 1" 80' 2
& 14 (25)
MW-47 2" 56' 2
? 14 (24)
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 ORISE Sample ID 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 POINT POWER STATION BUCHANAN, NEW YORK C-14 NRC Region I Sample ID Concentrationsa
@Ci/g or pCi/L) 1697S0001b 1697W001 7d 1697W0018 1697W0019
~~
~~~
~
MH-1 Shore discharge
-0.3 k 1.3" (2.2)
MW-40 4" 200' 15.9 k 16.3 (27)
MW-51 4" 200' 17.1 5 16.3 (27)
MW-48 1" 37.5' 11 k 16.2 (27) 1697WO020 1697W0021 MW-48 2" 52' 1.39 k 16 (27)
MW-43 2" 28' 8.33 k 16.1 (27)
~~
~
1697WOO22 1697WOO23 1697W0024 MW-43 2" 62' 16.6 _+ 16.3 (27)
MW-41 1" 63' 2.78 k 16 (27)
MW-41 2" 41' 8.33 k 16.1 (27) 11 1697W0029 I HudsondischargeMH-1 I 2
_+
16 (28) 11 1697W0025 1697W0026 "The MDCs arc in parentheses.
'Soil concentrations, P U S, and MDCs are in pCilg.
0 5 16 (28)
MW-46 4" 30' MW-47 1" 80'
'Uncertainties represent the 95% confidence level, based on total propagatcd uncertainties.
1697W0027 1697W0028 Indian Point Power Station MW-47 2" 56'
-5
_+
16 (28)
Unit 2 MH#5
-9 k 16 (28) projects/l697/Data Tables/2006-07-ll Final Data Table Set Three
O R I S E Distribution approval and concurrence :
Technical Management Team Member Quality Manager July 7,2006 Initials RE c E I 4 ED OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION pEGla?s 1 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 NO. 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 M. Miller, NRC Region I File 1697 S. IGrk, ORISE J. White, NRC Regon I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1697S0002 1697S0003 1697S0004 1697S0005 1
Verplank 5/10/2006 11 :50 White Beach 5/10/2006 12:lO Manitou 5/10/2006 13:OO 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 CO-58
-0.01 f 0.02b 0.00' f 0.01
-0.01 f 0.03
-0.03 f 0.03 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN SOIL SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK CO-60 CS-134 CS-137 0.01 f 0.02 0.04 f 0.03 0.21
- 0.03 0.03 f 0.02 0.01 f 0.02 0.01 f 0.01
-0.01 f 0.02 0.05 f 0.02 0.10 k 0.02
-0.01 f 0.03 0.05 f 0.03 0.06 f 0.02 NRC Region I Sample ID ORISE Sample ID 1
I/
169730002 I
Verplank 1697S0003 White Beach Radionuclide Concentrationsa (pCi/g)
II "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 ORISE NRC Region I Sample ID Sample ID 1697S0002 Verplank 1697S0003 White Beach 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 Radionuclide Concentrations, TPUs, and MDCS" (pCi/g)
-0.02 f
0.1Ob (0.18) 0.01 f
0.11 (0.19) 1 1697S0004 Manitou 0.12 f
0.12 (0.20) 1697S0005 Lent's Cove 0.08 0.11 (0.19) a M D C ~
are in parentheses.
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
ORISE Sample ID V
- 9. e Radionuclide Concentrationsa (pCi/g)
NRC Region I Sample ID C-14b Ni-59" Ni-63" H-3d
\\
1697S0002 1697S0003 1697S0004 1697S0005 TABLE 4 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)
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)
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)
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)
W
=1 P
CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES IN SOIL SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK "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-3 analyzed using procedure AP6, Revision 15.
eUncertainties represent the 95% confidcncc level, based on total propagated unccrtainties Lcro values are due to rounding.
f,
TABLE 5 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN SOIL SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID Tc-99 Concentrationsa (PCi/d NRC Region I Sample ID 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
/I 0RIS;:mple I
NRCRegionI Sample ID 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 Radionuclide Concentrationsa (pCi/g)
Am-241 Gn-242 I
Gn-243/244 I
Nv-237 1697S0002 1697S0003 1697S0004 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)
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)
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 I 0.02 f 0.04 (0.07) 1697S0005 I
Lent's Cove P
P 0.01 k 0.02 (0.03) 0.01
& 0.04 (0.07) 0.01 k 0.01 (0.02)
TABLE 6 (Continued)
ORISE Sample ID NRC Region I Radionuclide Concentrations a ( pCi/ g)
Sample ID Pu-238 Pu-239/240 U-234 U-238 1697S0002 1697S0003 1697S0004 1697S0005 The MDG are in parentheses.
%Jnce&ties represent the 95% confidence level, based on total propagated uucerrainties.
'Zero values are due to rounding.
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)
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)
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)
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)
TABLE 7 ORISE Sample NRC Region I Sample ID ID Pu-241 Concentrationsa (PCik) 11 1697S0002 I Verplank I
1.7
& 3Sb (5.9) 11 I
11 1697S0003 I White Beach I
4.6 4.0 (6.6) 11 1697S0004 Manitou 1.3 6.2 (10.6) I 1697S0005 Lent's Cove
-0.3 4.0 (6.9)
~~~~
~
'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