ML071900462
| ML071900462 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/12/2007 |
| From: | Condra D Oak Ridge Institute for Science & Education |
| To: | Kottan J NRC Region 1 |
| References | |
| FOIA/PA-2007-0324, IR-06-007, RFTA 06-001 | |
| Download: ML071900462 (11) | |
Text
I OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 12,2007 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 WBJECT:
REVISED FINAL REPORT FOR REQUESTED ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
>ear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the Indian Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for handhg samples from this fachty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Radiological and Environmental Sciences Laboratory. Sample identification and collection data for the samples addressed in &IS report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through Table 8, respectively. The pertinent procedure references are provided in each specific table.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
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 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 analyzeq the filtered solid portion of each sample for all the requested alpha isotopes. The remaining a%uot of each sample was adjusted to a pH of approximately 2 with concentrated HNOs.
T3m
,;3m 0 3 0
--?E Lh
M K Jim Kottan April 12,2007 Distribution approval and concurrence :
Technical Management Team Member Quality Manager In the oripal report the date of the letter was incorrectly reported as January 26,2006. The date has been corrected and I apologize for any inconvenience this incorrect date may have caused.
Initials,
K, My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures c:
T. Carter, NRC/FSME/DWMEP 7518 E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Regon I File 1697 S. IGk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra@orau.org
TABLE 1 ORISE Sample ID 1697WO07Oa 1 697M0033b SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time MW-42@41 9/18/2006 14:45 MW-42@41 9/18/2006 14:45
~ ~__________
1697M0035 1697W0073 1697M0036 1697W0074 1697W0071 I MW-42@43 I 9/18/2006 I 13:OO MW-42@46 9/15/2006 12:45 MW-42@48 9/15/2006 11:20 MW-42@48 9/15/2006 11 :20 MW-59@70 9/15/2006 10:20 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO 1697M0038 1697W0076 1697M0039 1697W0077 1697M0040 1697W0072 1 -
MW-42@46 I 9/15/2006 I 12:45
~
~~~
LAF-001-(003) 9/19/2006 15:49 LAF-002-(003) 9/ 19/2006 13:41 LAF-002-(003) 9/19/2006 13:41 LAF-003-(003) 9/19/2006 11:08 LAF-003-(003) 9/19/2006 11:08 1697M0037 I MW-59@70 I 9/15/2006 I 10:20 1697W0075 r LAF-001-(003)
I 9/19/2006 I 15:49 T h e Win the ORISE sample identification represents a water matrix.
'The M in the ORISE sample identification represents the filtercd fraction of the preceding water sample Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14
TABLE 2 ORISE Sample ID 1697~0070 1697W0071 1697W0072 1697~0073 1697W0074 1697WOO75 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrationsa'b (pCi/L)
Sample ID CO-58 CO-60 cs-134 cs-137 MW-42041 3
rt 11" 4
k 13 6.5 If: 9.3 13,730 k 470 MW-42043
-12 k 12 3
? 12 6.0 k 9.2 15,140 k 510 MW-42046
-1.7 k 7.7 11.7 f. 9.9 2.4 k 7.8 20,260 k 650 MW-42048 6
k 13 15 k 11 1 k 11 21,650 k 750 MW-59@70 0.1 k 3.0 0.3 f. 4.1 1.3 k 2.7
-3.8 k 4.1 LAF-001-(003) 1.2 k 2.8 3.8 k 2.9 -0.5 ? 2.4 1.2 k 2.1 1697W0076 I LAF-002-(003) I -2.4 k 3.0 I 2.2 k 4.6 I 0.7 f. 2.6 I 0.5 k 2.2 11 1697W0077 I LAF-003-(003) 1 -1.7 k 2.0 I 0.7 k 1.61 -0.8 k 1.71 -0.7 2 1.6 1 "The range of MDCs for the selected radionuclides for samples WOO70-WOO73 is 13 pCi/L to 37 pCi/L.
bThe range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.9 pCi/L to 5.0 pCi/L
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14
TABLE 3 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 "The MDCs for each radionuclide are in parentheses
'Fe-55 analyzed using procedure AP13, Revision 4
'Ni-59/63 analyzed using procedure AP17, Revision 0.
dH-3 analyzed usmg procedure AP2, Revision 15 eUncertmnhes represent the 95% confidence level, based on total propagated uncertmnhes.
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tablcs Set 14
TABLE 4 ORISE Sample ID 1697W0070 1697W0071 1697W0072 1697W0073 1697W0074 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
@Ci/L)
MW-42@4 1 4
k 18b (31)
MW-42@43 8
2 18 (31)
MW-42@46
-1 f 18 (31)
MW-42@48 5
-t-18 (31)
MW-59@70
-4.7 f 8.9 (15.6) 1697W0075 1697W0076 1697W0077 LAF-00 1-603)
-2.7
?
9.0 (15.6)
LAF-002-(003)
-0.5 f 9.1 (15.6)
LAF-003 -(003) 2.8 k 9.1 (15.6)
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14
TABLE 5 ORISE Sample ID 1697W0070 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 MW-42@41 20.2 f
2.Ob (2.3)
TPUs, and MDCS" @Ci/L) 1697W0072 1697W0073 1697W0074 1697W0075 1697W0076
~~
1697W0071 I MW-42@43 I
15.7 5
1.7 (1.9)
MW-42@46 32.8 f
2.4 (2.2)
MW-42@48 35.0 f
2.3 (2.0)
MW-59@70 0.14 k
0.50 (0.89)
LAF-001-(003) 0.10 k
0.52 (0.93)
LAF-002-(003) 0.97 f
0.55 (0.871 1697W0077 I LAF-003-(003)
I
-0.17 k
0.45 (0.83)
'MDCs are in parentheses buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14
3 8
m d
w w
Frl 3
z 2
s:
m H
z 9
e N 8
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w e m 8
+I 3 8 :
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'1 e
m 8 8
8
+I r-m E
M r-0 s r-m W
3 -
G 9
e N 8
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GF hl
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00 E
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r-m W
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G 9
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N
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8 8
5 M
+I 3
66 9
e N 8 8
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G-0, 9
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0 3
00 m
0 3 r-m 2 G 2 8
d-
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8 5;
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m 8 8 :
8 7
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r-0 s r-m W
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s g
'1 9 0 0
0 9 9 3 3 i;I-m m
3 w
Indian Point Power Station projects/l697/Data Tables/2007-04-12 Data Tables Set 14
TABLE 6 (Continued)
ORISE Sample ID 1697W0070 1697M0033 1697W0071 16971110034 F
E:
B NRC Region I Radionuclide Sample ID Pu-238 m-426341 0.08 f 0.09 (0.15) m-42@41 0.00 k 0.02 (0.04) m-426343 0.06 k 0.13 (0.23) m - 4 2 @ 4 3 0.02 fc 0.02 (0.031 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK P~-239/240 0.03 f 0.04 (0.07) 0.01 f 0.01 (0.01) 0.01 ? 0.04 (0.09)
F P.
3 U-234 U-238 1.47 k 0.26 (0.10) 1.27 k 0.24 (0.07) 0.01 k 0.01 (0.02) 0.01 k 0.01 (0.02) 1.93 k 0.29 (0.03) 1.72 k
0.27 (0.03) 1697W0072 16971110035 m-42@46 0.11 f 0.08 (0.12) 0.01 f 0.03 (0.07) 1.87 k 0.30 (0.10) 1.70 k
0.28 (0.07) m-42@46 0.01 fc 0.02 (0.04) 0.01 k 0.01 (0.02) 0.02 k 0.01 (0.01) 0.02 k
0.01 (0.01) 0.01 k 0.01 (0.02) I 0.01 k 0.01 (0.01) I 0.01 f 0.01 (0.01) 1697W0073 1697M0036 1697W0074 m - 4 2 @ 4 8
-0.01 k 0.07 (0.15) 0.03 k 0.06 (0.11) 2.10 fc 0.30 (0.06) 1.74 k
0.26 (0.06) m-42@48 0.00 fc 0.02 (0.03) 0.01 k 0.01 (0.01) 0.03 k 0.02 (0.02) 0.04 k
0.02 (0.01) m - 5 9 @ 7 0 0.04 fc 0.03 (0.04) 0.04 k 0.03 (0.02) 0.54 k 0.10 (0.07) 0.48 k
0.09 (0.05) 1697M0037 1697w0075 l697M0038 1697w0076 m - 5 9 @ 7 0 0.00 f 0.02 (0.03) 0.01 k 0.01 (0.02) 0.01 f 0.01 (0.02) 0.03 f 0.02 (0.01) mF-0O1-(003) 0.01 k 0.03 (0.05) 0.03 k 0.02 (0.02) 0.67 k 0.10 (0.02) 0.73 k
0.11 (0.02) mF-001-(003) 0.01 f 0.02 (0.03) 0.01 f 0.02 (0.02) 0.00 k 0.01 (0.02) 0.00 k 0.01 (0.01) mF-0O2-(003) 0.04 f 0.05 (0.09) 0.03 k 0.03 (0.04) 26.3 f 2.1 (0.1) 17.1 k
1.4 (0.1) 16971110039 I uF-002-(003) I 0.01 f 0.02 (0.03) I 0.02 k 0.01 (0.01) I 0.05 k 0.02 (0.01) I 0.03 fc 0.01 (0.01) 1~97woo77 1697M0040
~
~~
~~~
~~~~
~F-003-(003) 0.03 k 0.03 (0.04) 0.00 f 0.02 (0.04) 0.56 k 0.12 (0.09) 0.48 f 0.10 (0.03) uF-003-(003) 0.02 fc 0.02 (0.03) 0.02 fc 0.01 (0.02) 0.01 f 0.01 (0.02) 0.01 fc 0.01 (0.01) 3 T h e M D C ~ are in parentheses.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Zero values are due to rounding.
dSignificat figures expanded to avoid reporting a TPU of zero at the request of the inspector, cn 3
+
c
TABLE 7 ORISE Sample ID CONCENTRATIONS OF PLUTONIUM-241 IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa
@Ci/g of sediment in 100 mL or pCi/L for water)
NRC Region I Sample ID 1697W0070 1697M0033 1697W0071 M%'-42@41
-3 k
1 7b (29)
MW-42@41
-0.2 1
3.4 (5.9)
MW-42@43
-8 1
16 (28) 1697M0034 1697W0072 1697M0035 1697W0073
~~
11 1697M0036 I M W - 4 2 @ 4 8 I
-0.6 3.5 (6.0)
MW-42@43
-0.6 k
3.7 (6.4)
MW-42@46
-10 k
16 (27)
MW-42@46
-2.5 k
3.5 (6.1)
MW-42@48
-10 k
15 (27) 11 1697W0074 I
MW-59@70 I
-2.5 k
9.3 (1 6.1) 1697M0037 1697W0075 1697M0038 MW-59@70
-0.9 k
3.4 (5.9)
LAF-001-(003)
-2.7 1
7.9 (13.7)
LAF-001-(003) 1.1 1
3.5 (6.0) 1697W0076 1697M0039 1697W0077 1697M0040 Indian Point Power Station LAF-002-(003)
-6.4
?
7.8 (13.6)
LAF-002-(003) 1.4 3.6 (6.1)
LAF-003-(003)
-2.5 k
8.2 (14.2)
LAF-003-(003) 2.6 k
3.5 (5.9) projects/l697/Data Tables/2007-04-12 Data Tables Set 14
TABLE 8 ORISE NRC Region I Sample ID Sample ID 1697W0070 MW-42@41 1697W0071 MW-42@43 1697W0072 Mw-42@46 1697W0073 Mw-42@48 Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) 0.8 k
9.7b (16.4) 8.8 k
9.8 (1 6.4) 0.2
+
9.6 (16.4)
-0.6
- f.
9.6 (1 6.4) 1697W0075 1697~0076 1697~0077 Indian Point Power Station LAF-001-(003) 0.5 k
9.7 (1 6.4)
LAF-002-(003) 1.4
- f.
9.7 (1 6.4)
LAF-003-(003) 8.3 k
9.8 (16.4) projects/l697/Data Tables/2007-04-12 Data Tables Set 14