ML071900458
ML071900458 | |
Person / Time | |
---|---|
Site: | Indian Point |
Issue date: | 05/03/2007 |
From: | Condra D Oak Ridge Institute for Science & Education |
To: | Kottan J J NRC Region 1 |
References | |
FOIA/PA-2007-0324, IR-06-001, RFTA 06-001 | |
Download: ML071900458 (10) | |
Text
I@ ORISE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION May 3,2007 Mi. Jim Kottan U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
REVISED INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET SIXTEEN, 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 16, consisting of 10 water samples, associated with the Indian Point Power Station on November 27,2006.
Sample analysis was initiated based on your previous direction for handling samples from this licensee. Sample identification and collection data for the samples addressed in this report are presented in Table
- 1. C Tarnma spectroscopy, the hard-to-detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 8, respectively.
The pertinent procedure references are provided in each specific table. ORISE's Quality Control (QC) requirements were met for these analyses.
The QC files are available for your review upon request. Additional reports will follow after the completion of the requested analyses.
ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of this ralonuclide.
ORISE is discontinuing the reporting of Ni-59 data until hs problem can be resolved.
In the original report the date of the letter was incorrectly reported as March 15,2006. The date has been corrected and I apologize for any inconvenience this incorrect date may have cawed. 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:WI:bf - Enclosures C: T. Carter, FSME/DWMEP 7518 J. White, NRC Region I' -3 ."-m t--l a -... c L .. v\ E. Knox-Davin, NRC/FSME/TWFN 8A23 M. Roberts, NRC Region I File 1697 E. Abelquist, ORISE S. Kirk, ORISE F- 4TP Distribution approval and concurrence
- Technical Management Team Member Quality Manager Initials , Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org TABLE 1 ORISE Sample ID 1697W0093" SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time MW-42-48' 1 1 /16/2006 10:52 ~ 1697M0056b 1697W0094 1697M0057 1697W0095 1697M0058 1697WOO93 filter 11 /16/2006 10:52 MW-42-43' 11/16/2006 14:24 1697W0094 filter 11 /16/2006 14:24 MW-42-45.5' 11/16/2006 13:02 1697W0095 filter 11 /16/2006 13:02 ~ 1697W0096 1697M0059 1697W0097 1697M0060 1697W0098 MW-42-41 ' 11 /17/2006 8:44 1697W0096 filter 11 /17/2006 8:44 MW-59-31-(001) 11/16/2006 11:05 1697W0097 filter 11/16/2006 11:05 MW-59-45-(001) 11/16/2006 11:18 ~ 1697M0061 1697YV0099 1697M0062 1697W0100 1697M0063 1697W0101
%e Win the ORISE sample identFfication represents a water mat&. bThe M in the ORISE sample identification represents the filtered fraction of the preceding water sample. 1697W0098 filter 11/16/2006 11:18 MW-59-68-(001) 11/16/2006 11:30 1697W0099 filter 11 /16/2006 11:30 MW-58-26-(001) 11/16/2006 13:25 1697W0100 filter 11/16/2006 13:25 MW-58-65-(001) 11/16/2006 13:18 Indian Point Power Station ~ 1697M0064 1697W0102 1697M0065 projects/l697/Data Tables/2007-05-03 Revised Data Tables Set 16 1697W0101 filter 11/16/2006 13:18 MW-39-200-(005) 11/17/2006 13:49 1697W0102 filter 11/17/2006 13:47 TABLE 2 ORISE Sample ID 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 Sample ID CO-58 11 1697W0093 I MW-42-48' CO-60 cs-134 cs-137
-1.5 k 3.2' -0.1 k 3.2 0.9 k 2.3 -2.8 k 3.9 -0.2 k 2.0 11 1697W0099 I MW-59-68-(001) 3.8 k 3.1 3.9 k 2.9 7730 k 250 d 2.3 k 3.5 0.0 k 3.2 8380 k 270 2.7 k 2.4 1.3 k 2.3 8270 k 260 1.9 k 3.4 2.0 k 3.8 8270 IfI 280 1.8 k 2.1 3.3 k 2.2 1.9 k 4.8 11 1697W0100 I MW-58-26-(001) 1697W0094 1697W0095 1697W0096
1697W0097 1697W0098 11 1697W0101 I MW-58-65-(001) ~~~ ~ MW-42-43' MW-42-45.5' MW-42-41' MW-59-31-(001)
MW-59-45-(001) 11 1697W0102 I Mw-39-200-(005)
-1.1 k 1.7 I 0.3 k 1.7 I 1.6 k 1.7 I 1.6 k 2.0 11 1.3 k 2.4 I 0.2 k 2.3 I 3.3 k 2.6 I 0.3 k 2.3 11 1.3 k 2.4 I 1.5 k 2.5 I 2.4 k 2.5 I -0.7 k 2.2 11 2.0 k 2.3 I 1.0 k 2.3 I -1.2 k 2.3 I 1.6 k 3.7 11 ~~~ ~~ 0.2 k 2.3 I -1.0 k 2.8 I 0.7 k 2.4 -1.2x2.611
%e range of MDCs for the selected radionuclide samples WOO93 through WOO96 is 3.9 pCi/L to 10 pCi/L. bThe range of MDCs for the selected radionuclide samples WOO97 through W0102 is 2.7 pCi/L to 4.5 pCi/L. 'Uncertainties represent the 95?0 confidence level, based on total propagated uncertainties.
dZero value is due to roundmg. Indian Point Power Station projects/l697/Data Tables/2007-05-03 Revised Data Tables Set 16 TABLE 3 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 YORK NRC Region I Sample ID Fe-55b 5 k 40" , 68 Of k 40 68 19 k 40 68 -3 k 40 . 68 11 1697W0093 I MW-42-48' Ni-63" H -3* 249 k 23 , 24 2,200 k 350 , 420 295 k 25 , 24 2,100 k 340 , 420 290 k 25 , 24 2,590 k 370 , 420 201 k 21 , 24 2,060 k 340 , 420 11 1697W0094 I MW-42-43' I 11 1697W0095 1 MW-42-45.5'
~~ _______ 1697W0096 MW-42-41' 1697W0097 MW-59-31-(001)
~~ 1697W0099 1697W0100 11 1697W0098 I MW-59-45-(001)
MW-59-68-(001)
MW-58-26-(001) 3 k 20 , 34 8 & 20 , 34 -5 k 20 , 34 11 1697W0101 I MW-58-65-(001) 0.1 k 5.6 , 9.5 10 k 240 , 420 0.5 k 5.6 , 9.5 120 k 250 , 420 -3.0 k 5.5 , 9.5 10 k 240 , 420 - 11697wo102 I MW-39-200-(005) 44 20 ~ 34 1 1.4 k 5.6 I 9.5 1 70 k 240 I -10 k 20 34 4.8 k 5.7 9.5 130 k 250 8 k 20 . 34 1.2 k 5.6 9.5 90 k 240 420 %e MDCs for each radionuclide are after the comma. bFe-55 analyzed using procedure AP13, Revision 4. 'Ni-63 analyzed using procedure AP17, Revision 0.
dH-3 analyzed using procedure AP2, Revision
- 15. 'Uncertainties represent the 95% confidence led, based on total propagated uncertainties.
fZero value is due to rounding. Indian Point Power Station projects/l697/Data Tables/2007-05-03 Revised. Data Tables Set 16 TABLE 4 Sample ID 1697W0093 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 Sample ID @Ci/L) MW-42-48' 8 k 15b , 26 I[ ORISE I NRCRegionI I Tc-99Concentration.s" 11 The MDCs are after the comma. buncertainties represent the 95010 confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-05-03 Revised Data Tables Set 16 TABLE 5 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 Sample ID 1697W0093 1697W0094 1697W0095 1697W0096 1697W0097 1697W0098 1697W0099 1697W0100 1697W0101 1697W0102 NRC Region I Sample ID MW-42-48' MW-42-43' MW-42-45.5' MW-42-41' MW-59-3 1 -(001) MW-59-45-(001)
MW-59-68-(001)
~~ MW-58-26-(001)
MW-58-65-(001)
MW-39-200-(005)
Radionuclide Concentrations, TPUs, and MDCS" @Ci/L) 8.9 k 2.gb . 4.2 11.2 f 2.5 , 3.5 11.9 f 2.2 , 2.9 8.8 f 2.6 . 3.7 0.32
- 0.34 , 0.56 0.25 f 0.33 , 0.56 0.56 ? 0.33 , 0.53 0.37 k 0.32 . 0.54 0.12 f 0.31 , 0.54 1.97 f 0.41 , 0.55 The MDCs are after the comma. buncertainties represent the 959'0 confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tables/2007-05-03 Revised Data Tables Set 16 TABLE 6 ORISE Sample ID 1697W0093 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 NRC Region I Radionuclide Concentrationsa
@Ci/g of sediment in 100 mL or pCi/L for water) Sample ID Am-241 Cm-242 Cm-243/244 Np-237 MW-42-48' 0.02 f 0.14b 0.28 0.25 f 0.16 . 0.16 0.00' f 0.10 . 0.23 0.02 f 0.14 . 0.28 1697M0056 1697W0093 filter 1677W0094 MW-42-43' 1697M0057 1697W0094filter 0.00 f 0.02 0.03 0.00 f 0.01 0.02 0.00 f 0.01 0.02 0.00 f 0.01 0.02 0.06 f 0.15 , 0.28 0.06 f 0.07 0.06 -0.06 f 0.09 0.26 0.07 f 0.10 0.14 0.01 f 0.02 0.03 0.01 k 0.01 . 0.01 0.00 f 0.01 . 0.02 0.00 f 0.01 . 0.01 1697W0095 MW-42-45.5' 1697M0058 1697W0095 fiter 1697W0096 MW-42-41'
~~ 0.15 f 0.16 0.24 0.03 f 0.17 0.34 0.00 f 0.16 0.34 0.12 f 0.11 0.15 0.00 k 0.01 0.03 0.002d f 0.004 0.006 0.002 f 0.004 0.006 0.00 f 0.01 , 0.03 0.08 f 0.16 0.30 0.03 f 0.14 . 0.30 0.00 f 0.08 . 0.21 0.06 f 0.09 . 0.16 4 e P . e m \o 8 4 z 2 Li 0 0 Y 8 ;d 5 B U a 3 e 01 a 2 v) L m 1677M0059 1697W0096 filter 0.01 f 0.01 0.02 0.01 f 0.01 0.01 0.00 f 0.01 , 0.02 -0.02 f 0.02 0.04 1697W0097 MW-59-31-(001) 0.19 f 0.17 0.23 0.24 f 0.17 0.18 0.07 f 0.11 0.18 -0.06 f 0.16 0.34 1697M0060 1697W0097 filter 0.01 f 0.02 0.03 0.00 f 0.01 0.02 0.002 f 0.004 0.01 -0.02 f 0.02 0.04 1697W0078 MW-59-45-(001) 0.16 f 0.13 0.08 0.16 f 0.13 0.08 0.03 f 0.12 0.25 -0.53 f 0.29 0.73 1697M0061 1697W0098 filter 0.01 f 0.02 0.03 0.00 f 0.01 0.02 -0.01 f 0.02 0.03 0.00 f 0.01 , 0.02 169773170099 MW-59-68-(001) 0.11 f 0.16 , 0.27 0.20 f 0.17 0.21 0.06 f 0.08 0.08 -0.07 f 0.14 0.33 -0.01 f 0.01 0.03 1697M0062" 1697W0099 filter e 1697W0100 MW-58-26-(001) 0.04 f 0.22 0.42 -0.10 f 0.16 0.36 -0.02 f 0.25 0.47 0.02 f 0.04 0.06 1677M0063 1697W0100 filter 0.01 f 0.01 0.02 0.002 f 0.004 , 0.006 0.002 f 0.004 0.006 0.01 f 0.01 0.01 1697W0101 MW-58-65-(001)
-0.16 f 0.24 , 0.51 0.11 f 0.26 0.28 -0.31 f 0.26 0.58 0.02 f 0.12 0.24 1677M0064 1677W0101 filter 0.01 f 0.02 0.04 0.00 f 0.01 0.02 0.00 f 0.02 , 0.03 0.00 f 0.01 0.03 1697W0102 MW-39-200-(005) 0.05 f 0.12 0.23 0.05 f 0.10 0.18 0.00 f 0.07 0.18 0.05 f 0.09 0.18 1697M0065 1697W0102 filter 0.02 f 0.02 0.03 0.00 f 0.01 0.02 0.00 f 0.02 , 0.04 0.00 k 0.01 0.03 e e TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ~ 0.002 & 0.004 0.007 0.13 & 0.10 , 0.06 0.08 & 0.08 . 0.06 0.01 k 0.01 , 0.01 0.01 k 0.01 0.02 0.00 f 0.01 0.02 1.38 & 0.35 0.15 1.36 k 0.34 0.06 0.01 & 0.01 0.02 0.01 f 0.01 , 0.02 1.24 f 0.32 . 0.14 1.19 & 0.31 . 0.06 __________~~~
0.08 & 0.08 0.06 0.01 & 0.01 0.01 0.04 f 0.08 , 0.15 1.50 f 0.33 0.12 1.59 f 0.34 0.05 0.01 f 0.01 0.01 0.01
- 0.01 0.01 0.53 k 0.20 , 0.06 0.64 f 0.22 , 0.06 0.00 f 0.01 0.02 0.02 k 0.08 , 0.17 0.00 & 0.01 . 0.02 ~~ 0.04 & 0.02 0.01 0.04 k 0.02 0.02 1.66 f 0.37 , 0.06 1.58 & 0.37 0.14 0.16 k 0.04 , 0.01 0.16 k 0.04 , 0.01 0.01 f 0.01 0.01 0.11 k 0.10 0.07 0.00 k 0.01 0.02 0.02 & 0.05 . 0.07 0.03 & 0.02 0.02 0.05 & 0.02 , 0.02 1.06 f 0.28 0.05 1.18 f 0.30 0.13 0.02 k 0.01 0.02 0.02 k 0.01 0.01 1.74 & 0.38 . 0.14 1.57 & 0.36 . 0.05 Radionucli de Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water) II ORISE NRC Region I Sample ID Sample ID PU-238 P~-239/240 I U-234 I U-238 II 0.15 & 0.15 0.22 0.07 k 0.07 . 0.05 I 1.30 f 0.31 . 0.05 I 1.43 & 0.35 . 0.28 11 0.00 f 0.01 0.02 -0.13 k 0.16 , 0.37 11 1697M0057 I 1697W0094 fdter 0.01 f 0.01 , 0.01 11 1697W0095 I MW-42-45.5'
-0.02 & 0.09 . 0.21 1697M0058 1697W0095 fdter 1697W0096 MW-42-41' I 1697M0059 1697W0096 filter -0.01 k 0.01 . 0.03 I 0.01 f 0.01 . 0.01 I 0.01 f 0.01 . 0.02 11 0.02 k 0.02 0.04 0.04 & 0.10 0.20 0.00 f 0.01 , 0.03 11 1697W0097 I MW-59-31-(001) 0.00 k 0.19 . 0.37 -0.01 2 0.02 . 0.04 0.00 k 0.01 . 0.01 I 0.04 & 0.02 . 0.03 I 0.06 k 0.02 . 0.01 11 W 1697M0060 1697W0097 filter 3 0 1697W0098 MW-59-45-(001) t: . - 1697M0061 1697W0098 fdter s B 1697W0099 MW-59-68-(001) 4 1697M0062 1697W0099 filter 1697W0100 Mw-58-26-(001)
E 1697M0063 1697W0100 fdter 1697W0101 MW-58-65-(001) 2 z r 1697M0064 1697W0101 fdter 2 2 1697W0102 MW-39-200-(005)
U 1697M0065 1697W0102 filter z o\ W a s 0 0 W E Ihe MDCs are after the comma Uncertamttes represent the 95% confidence level, based ob rA 3 - 'Zero values are due to rounding dSigmficant figureb expanded to avoid rcportmg a TPU o %e yield QC for the Am and Cm data for this sample f o\ 0.00 k 0.13 0.30 I 0.46 k 0.23 . 0.28 I 0.40 & 0.20 . 0.21 11 0.28 & 0.24 0.35 0.01 k 0.02 0.03 0.07 & 0.14 , 0.25 0.02 f 0.02 . 0.03 0.02 k 0.16 0.32 0.08 & 0.10 . 0.16 I 1.44 & 0.35 . 0.20 I 1.13 k 0.31 . 0.17 11 ~~ 0.01 k 0.02 0.03 0.24 & 0.20 , 0.29 0.01 f 0.01 . 0.03 0.09 k 0.18 . 0.31 0.02 & 0.02 . 0.03 0.00 & 0.01 . 0.02 I 0.02 k 0.02 . 0.04 I 0.03 k 0.03 , 0.01 11 MI total propagated uncertainties.
f ai zero at the request of the inspector.
led and the data cannot be rcported 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 1697M0056 1697W0094 1697M0057 1697W0095 11 1697W0093 I 1697W0093 filter
-1.0 k 3.7 6.3 MW-42-43' 5 k 38 Y 66 1697W0094 fiter -2.7 k 3.2 , 5.5 MW-42-45.5'
-10 k 39 6 13 MW-42-48' ~~ ~ ~~ ~~~
1697M0058 1697W0095 filter 1697W0096 MW-42-41' 1697M0059 1697W0096 filter 1697W0097 MW-59-31-(001) 1697W0098 MW-59-45-(001) 1697M0061 1697WOO98 filter 1697W0099 MW-59-68-(001) 1697M0060 1697W0097 filter 1.7 k 3.7 6.2 9 k 40 > 69 0.4 k 3.4 5.8 -22 k 38 Y 66 -0.9
- 3.5 6.0 -32 k 68 117 -0.7 k 3.3 5.7 -29 k 41 70 1697M0062 1697W0100 1697M0063 1697W0101 1697W0099 filter
-0.1 k 3.5 1697W0100 filter 0.6 k MW-58-65-(001)
-12 k 43 MW-58-26-(001) 8
- 40 1697M0064 1697W0102 1697M0065 Indian Point Power Station 1697W0101 filter 3.0 k 3.6 MW-39-200-(005) 20 k 42 1697W0102 fiter 1.3
- 3.4 5.7 projects/l697/Data Tables/2007-05-03 Revised Data Tables Set 16 TABLE 8 NRC Region I Sample ID MW-42-48' MW-42-43' MW-42-45.5' CONCENTRATIONS OF CARBON-14 IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, TPUs, and MDCs" @Ci/L)
-4.4 k 9.2b 15.8 3.4
- 9.3 15.8 -4.9 k 9.2 . 15.8 11 1697W0095 MW-59-31-(001)
MW-59-45-(001) 11 1697W0096
-0.4 k 9.2 , 15.8 -1.1 k 9.2 - 15.8 1697W0098 MW-58-26-(001)
MW-58-65-(001)
MW-39-200-(005) 11 1697W0099 2.7 k 9.3 15.8 7.1
- 9.4 , 15.8 -0.3
- 9.2 . 15.8 MW-42-41' I 1.1 k 9.3 . 15.8 MW-59-68-(001)
I 4.2
- 9.3 . 15.8 'MDCs are after the comma. buncertainties represent the 95?/0 confidence level, based on total propagated uncertainties Indnn Point Power Station projects/l697/DataTables/2007-05-03 Revised Data Tables Set 16