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See also: [[see also::IR 05000247/2006007]]


=Text=
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{{#Wiki_filter:OAK RIDGE INSTITUTE  
{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION February 2,2006 Mr. Jim Kottan U S . Nuclear Regulatory Commission Regon I 475 Allendale Road IOng of Prussia, PA 19406
FOR SCIENCE AND EDUCATION  
 
February 2,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission  
==SUBJECT:==
Regon I 475 Allendale  
SECOND INTERIM REPORT FOR REQUESTED ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
Road IOng of Prussia, PA 19406 SUBJECT: SECOND INTERIM REPORT FOR REQUESTED  
[INSPECTION REPORT N O . 050-247/2006-0071 [RFTA NO. 06-0011
ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION  
 
REPORT NO. 050-247/2006-0071 [RFTA  
==Dear Mr. Kottan:==
NO. 06-0011 Dear Mr. Kottan: The Oak hdge Institute for  
 
Science and Education (ORISE) received set 14, whch consisted  
The Oak h d g e Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the InQan Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous hection for handling samples from h s facihty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by RaQological 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-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.
of eight water samples received  
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
on September  
ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of h s ralonuclide. ORISE is Qscontinuing the reporting of Ni-59 data untd
26,2006 from the InQan Point Power Station in  
&Is problem can be resolved.
Buchanan, New York. Sample analysis was  
The water samples were processed using a deviation to the sample preparation procedure, SP3, Revision 4. The water samples were frltered through 0.45 micron filter papers. An aliquot was removed for tritium and carbon-14 before aciQfication. 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 analyzed the filtered solid portion of each sample for all the requested alpha isotopes.
initiated  
 
based on your previous  
M KJim Kottan                                                           Febmay 2,2006 My contact information is listed below. You may also contact Wade Ivey at 865.576.9184with any questions or comments.
hection for handling samples from hs facihty. The final report was delayed  
Sincerely, Dale Condra, Manager Laboratory RDC:WI:db Enclosures C:     B. Watson, FSME/DWMEP/DD/SP 7E18                   E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN 8A23                 S. IGrk, ORISE M. Roberts, NRC Region I                           J. Whte, NRC Region I File 1697 Distribution approval and concurrence : Initials -
untd technical concerns about  
Technical Management Team Member Quality Manager Voice: 865.241.3242               Fax: 865.241.3248           E-mail: Dale.Condra@orau.org
plutonium  
 
in water samples were resolved through analytical testing conducted  
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE                  NRC Region I                       Collection             Collection Sample ID                     Sample ID                          Date                 Time 1697WO07Oa                     MW-42@41                       9/18/2006                 14:45 1697M0033b                    MW-42@41                         9/18/2006                 14:45 1697W0071                    MW-42@43                         9/18/2006                 13:OO 1697M0034           I         MW-42@43                     I   9/18/2006         I     13:OO 1697W0072          I         MW-42@46                     I 9/15/2006           I     12:45 1697M0035          I        MW-42@46                    I  9/15/2006           I      12:45 1697W0073          I        MW-42@48                    I  9/15/2006         I      11:20 1697M0036                    MW-42@48                        9/ 15/2006               11:20 169773170074                  MW-59@70                        9/15/2006                10:20 1697M0037                    MW-59@70                        9/15/2006                10:20 1697W0075                  LAF-001-(003)                       9/19/2006                 15:49 1697M0038          I     LAF-001-(003)                  I   9/19/2006         I     15:49 1697W0076          I     LAF-002-(003)                  I   9/19/2006         I     13:41 1697M0039          I     LAF-002-(003)                   I   9/19/2006         I     13:41 1697W0077          I     LAF-003-(003)                   I   9/19/2006         I     11:08 1697M0040          I     LAF-003-fO03)                   I   9/19/2006         I     11:08
by RaQological  
                        %e W in the ORISC sample identification represents a water matrix.
and Environmental  
bThe M in the ORISE sample identification represents the filtered fraction of the preceding water sample Indian Point Power Station                                                                          projects/l697/Data Tables/2007-02-02 Data Tables Set 14
Sciences Laboratory.  
 
Sample identification  
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                 NRC Region I                            Radionuclide Concentrationsa' 5      1 Sample ID                    Sample ID                      CO-58                CO-60            cs-134              cs-137 1697W0070            I      MW-42@41                                                                            13.730 k 470 1697W0071            I      MW-42@43 1697W0072                    MW-42@46 1697W0073                    MW-42@48 1697W0074                                               0.1 k 3.0          I 0.3  k 4.1    I 1.3    If: 2.7 1697W0075                 LAF-001-(003)                   1.2 k      2.8 I 3.8    f. 2.9 I -0.5    k  2.4 1697W0076                LAF-002-(003)                 -2.4 f. 3.0 2.2 f. 4.6 0.7 f.                   2.6      0.5     k 2.2 1697W0077                LAF-003-(003)                  -1.7 k 2.0 0.7 k 1.6 -0.8 f.                     1.7     -0.7     k 1.6     1 "The range of MDCs for the selected radionuclides for samples WOO7O-WOO73 is 13 pC1/L to 37 pCi/L "The range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.7 pCi/L to 5.0 pCi/L
and collection data for the samples addressed  
    'Uncertaintm represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station                                                                     projects/l697/Data Tables/2007-02-02 Data Tables Set 14
in &Is report are presented  
 
in Table 1. Gamma spectroscopy, the hard-to- detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14  
  +
data are provided in Tables  
'0 5'                                                                               TABLE 3 a
2 through 8, respectively.  
8 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                    NRC Region I Sample I D                    Sample ID                            Fe-!Sb                   Ni-63"                  H-3d
The pertinent procedure references  
                                                                      -19 ? 19" (32)               452 ?   40   (35)   2,830 t 380 (420)
are provided in each specific table.  
                                                                      -17 k 19 (32)                435 ?   39   (35)   2,350 t 360 (420)
ORISE's Quality Control (QC) requirements  
                                                                      -3    t 19 (32) 1,207 2 85               (35)   1,500 k 320 (420) 11    1697W0073              I      MW-42@,48                    -2 t 19 (32) I 1.272 k 89                (35) I 1.370 ?  310 (420) 11    1697W0074              I      MW-59@70                      -4    ? 19 (32)             -0.4 k 8.2 (14.1)   130  t 250 (420) 11    1697W0075              I    LAF-001-(003)                  -6    t 19 (32)            0.3 &  8.2 (14.1)   -94 t  230 (420) 11 . 1697W0076              I     LAF-002-(003)                   -1    t 19 (32)             2.0 t 8.3 (14.1) -220 k      230 (420) 11    1697W0077             I     LAF-003-(003)                   2     If: 19 (32)       I 2.6 2 8.3 (14.1) I -40 k     240 (420)
were met for these  
    %e MDCs for each radionuclide are in parentheses.
analyses.  
bFe-55 analyzed using procedure AP13, Revision 4.
The QC files are available for your review upon request. ORISE has removed the Ni-59 data  
    'Ni-63 analyzed using procedure AP17, Revision 0 dH-3analyzed using procedure AP2, Revision 15.
due to problems with the calculation associated with  
      'Uncertainties represent the 95% confidence level, based on total propagated uncertainties P
the concentration  
L
of hs ralonuclide.  
 
ORISE is Qscontinuing the reporting of  
TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
Ni-59 data untd &Is problem can be resolved.  
I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE                    NRC Region I                     Tc-99 Concentrationsa Sample ID                     Sample ID                                (pCi/L) 1697W0074                     MW-59@70                       -4.7     k     8.9     (15.6) 1697W0075                    LAF-001-(003)                     -2.7     k     9.0     (15.6) 1697W0076                    LAF-002-(003)                     -0.5     k     9.1     (15.6) 1697W0077                    LAF-003-(003)                     2.8     k     9.1     (15.6)
The water samples  
                          %rhcMDCs are in parentheses.
were processed  
Uncertainties reprcsent the 95% confidence Icvel, based on total propagated uncertainties.
using a deviation  
Indian Point Power Station                                                                           projects/l697/Data Tables/2007-02-02 Data Tables Set 14
to the sample preparation procedure, SP3, Revision 4. The water samples were  
 
frltered through 0.45 micron filter papers. An aliquot was removed for tritium  
TABLE 5 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N 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) 1697W0070          Mw-42@41       20.2   k       2.Ob             (2.3) 1697W0071          MW-42@43         15.7 k         1.7             (1.9) 1697W0072          MW-42@46         32.8 f         2.4             (2.2) 1697W0073         MW-42@48         35.0 k         2.3             (2.0) 1697W0074          MW-59@70       0.14   k       0.50           (0.89) 1697'0170075    LAF-001-(003)     0.10 k       0.52           (0.93) 1697W0076        LAF-002-(003)     0.97 ?       0.55           (0.87) 1697W0077        LAF-003-(003)     -0.17 k       0.45           (0.83)
and carbon-14 before  
Indian Point Power Station                                       projects/l697/Data Tables/2007-02-02 Data Tables Sct 14
aciQfication.  
 
An aliquot was removed for alpha analysis and the pH was adjusted to approximately zero using concentrated  
TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE    NRC Region I Sample ID                                  Cm-242                Cm-243/244                 N~-237 1697W0070    m-42@41          0.03 k 0.09b (0.15)   0.01 ? 0.04  (0.07) I  0.01  &  0.08  (0.14) I  0.01 k   0.02  (0.03) 1697M0033   Mw-42@41         0.01 & 0.02   (0.04) 0.01 ? 0.01  (0.02)   0.00" & 0.02   (0.03)   0.00 k   0.02 (0.03) 1697W0071    MW-42@43        0.07 k 0.09   (0.15) 0.07 k 0.06 (0.08)     0.01 f. 0.09  (0.17)   0.01 ?  0.02 (0.03) 0.00 ? 0.01 (0.03) -0.01 k 0.02        (0.04)   -0.01 f. 0.02 (0.04) 0.03 ? 0.06 (0.10) -0.03 f. 0.07      (0.14)   0.03 &  0.06  (0.11) 0.01 k 0.01 (0.02) 0.00 ? 0.02         (0.04)   0.00 ?   0.01  (0.03) 0.03 k 0.03 (0.02) 0.01 f. 0.07        (0.14)   -0.04 f. 0.05  (0.12) 1  1697M0036    m-42@48          0.00 ?  0.02   (0.04) 0.00 ? 0.01 (0.02) -0.01 k 0.02       (0.04) 0.002 f. 0.004d (0.007) 2-       1697W0074    m-596370        0.00 k 0.05    (0.09) 0.02 f. 0.02 (0.03) -0.01 k 0.04      (0.08) 0.02 f. 0.02      (0.02) 2 1    .
nitric acid (HN03) and a few drops of hydrofluoric  
1697M0037    m-59@70        -0.01 k 0.02    (0.04) 0.01 ? 0.01 (0.01) I 0.00 k 0.02       (0.03) I 0.00 f. 0.01   (0.03)
acid (HF). A pH of zero and a few drops of HF should ensure  
L I                        1
that any plutonium that  
.z
may be in the sample  
-  -. 1697W0075    uF-001-(003)     0.03 f. 0.04  (0.07) 0.00 f. 0.03 (0.06) I -0.02 k 0.04     (0.08) I 0.00 f. 0.01    (0.04)
remains in solution.  
U E-'    1697M0038 , uF-001-(003)     0.02 f. 0.02  (0.03) 0.01                I
ORISE analyzed the filtered solid portion of each sample for all the requested alpha isotopes.
                                                                  ? 0.01 (0.03) -0.01 k 0.02              I (0.04) 0.002 f. 0.005 (0.007) 21    1697W0076 I LAF-002-(003) I -0.02 f. 0.05  (0.09) 0.00 f. 0.03 (0.06) 0.00 k 0.03       (0.05)   0.00 f. 0.04  (0.08)
MK Jim Kottan -2- Febmay 2,2006 Distribution
R  1  1697M0039 I LAF-002-(003)  I  0.01 f. 0.02  (0.03) 0.00 f. 0.01 (0.02) 0.00 k 0.02        (0.03)   0.00 f. 0.01 (0.03) 0.01 ? 0.02 (0.03) 0.00 f. 0.01       (0.01)   -0.06 k   0.04  (0.10)
approval and concurrence
I                I 0.00 k 0.01 (0.02) 0.00 f. 0.01        (0.02)  0.002 ?  0.004 (0.006) e a
: Technical Management Team
cn 2
Member Quality Manager My contact information  
e P
is listed below. You may also contact Wade Ivey at 865.576.9184
 
with any questions  
F   T hl 7 C
or comments.  
5 i  7 C
Initials - - Sincerely, Dale Condra, Manager Laboratory  
8   C
RDC:WI:db  
                            +I t 3   7 8   C C
Enclosures  
F  /-
C: B. Watson, FSME/DWMEP/DD/SP  
01 7 9   C i3          9   5 8
7E18 E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN  
cn d
8A23 M. Roberts, NRC Region I File 1697 S. IGrk, ORISE J. Whte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail:  
W 3
Dale.Condra@orau.org
9 0
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS  
                            +I r
AND COLLECTION  
C C
DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection  
                                +
Collection  
                            +   r C
Sample ID Date Time 1697WO07Oa  
8   C
1 697M0033b
                          -fl r
1697W0071
                            +   n 9   C
MW-42@41 9/18/2006  
: 0. s 3   7 c
14:45 MW-42@41 9/18/2006  
8   C
14:45 MW-42@43 9/18/2006  
                            +I +
13:OO 1697M0034  
i   7 8  C C
I MW-42@43 I 9/18/2006  
G  G C
I 13:OO 1697M0036
8 L
169773170074
s hl  h 8  C C
1697M0037
                            +I +
1697W0075
0   h C
1697W0072
8  c 3   M 8 8 hl F f M   d-M   M 0  0 3
I MW-42@46 I 9/15/2006  
r-3 r.
I 12:45 MW-42@48 9/ 15/2006 11:20
s\ c\
MW-59@70 9/15/2006  
W  W i   3 Indian Point Power Station        projccts/l697/Data Tables/2007-02-02 Data Tables Set 14
10:20 MW-59@70 9/15/2006  
 
10:20 LAF-001-(003)  
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N 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 NRC Region I Sample ID                        (pCi/g of sediment in 100 mL or pCi/L for water)
9/19/2006  
          *l                                            Mw-42@41 Mw-42@41 Mw-42@43 I      -3        +_        17b              (29)    11 MW-42@43                            -0.6                 3.7              6.4)
15:49 1697M0035
Mw-42@46                            -10                                    (27) 1697M0036 1697W0074 1697M0037 Mw-42048 MW-59@70 MW-59@70
I MW-42@46 I 9/15/2006  
                                                                                              -0.6
I 12:45 1697W0073
                                                                                            -2.5
I MW-42@48 I 9/15/2006  
                                                                                              -0.9 k
I 11:20 1697M0038
k k
I LAF-001-(003)  
3.5 9.3 3.4 (16.1)
I 9/19/2006  
(5.9)
I 15:49 1697W0076
I 1697W0075                        LAF-001-(003)                         -2.7        k         7.9             (13.7) 1697M0038                        LAF-001-(003)                          1.1       k         3.5             (6.0) 1697W0076                        LAF-002-(003)                        -6.4         If:       7.8             (13.6) 1697M0039                        LAF-002-(003)                          1.4       +
I LAF-002-(003)  
                                                                                                          -         3.6             (6.1)
I 9/19/2006  
          *l                                          LAF-003-(003)
I 13:41 1697M0039
LAF-003-(003)
I LAF-002-(003)  
                                                                                            -2.5 2.6 k
I 9/19/2006  
                                                                                                          ?
I 13:41 1697W0077
8.2 3.5 (14.2)
I LAF-003-(003)
(5.9)
I 9/19/2006
            "MDCs are in parenthescs
I 11:08 1697M0040
            'Uncertainties represent the 95% confidence level, based on total propagated uncertainhes Indian Point Power Station                                                                          projects/l697/Data Tables/2007-02-02 Data Tables Set 14
I LAF-003-fO03)
 
I 9/19/2006
TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE        NRC Region I      Radionuclide Concentrations, Sample I D        Sample ID          TPUs, and MDCS"(pCi/L) 1697W0070        MW-42@41          0.8    k        9.7b          (16.4) 1697W0071        MW-42@43          8.8
I 11:08 %e W in the ORISC sample identification represents
* 9.8          (16.4) 1697W0072        MW-42@46          0.2
a water matrix.
* 9.6          (16.4) 1697W0073        MW-42@48          -0.6    k          9.6          (16.4) 1697W0074
bThe M in the ORISE sample identification represents the filtered fraction
                                  ~
of the preceding water sample Indian Point Power
MW-59@70
Station projects/l697/Data
                                              ~
Tables/2007-02-02
6.9    +
Data Tables Set
                                                                  -          9.8          (16.4) 1697W0075        LAF-001-(003)      0.5    k          9.7          (16.4) 1697W0076        LAF-002-(003)      1.4
14 
* 9.7            (16.4) 1697W0077        LAF-003-(003)       8.3    ?          9.8          (16.4)
TABLE 2 CONCENTRATIONS
Indian Point Power Station                                       projects/l697/Data Tables/2007-02-02 Data Tables Set 14}}
OF SELECTED GAMMA EMITTING RADIONUCLIDES
IN WATER SAMPLES
BY GAMMA SPECTROSCOPY
CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Sample ID Sample ID 1697W0070
I MW-42@41 1697W0071
I MW-42@43 1697W0072
1697W0073
1697W0074  
1697W0075  
1697W0076
1697W0077
MW-42@46 MW-42@48 LAF-001-(003)  
LAF-002-(003)  
LAF-003-(003)
Radionuclide
Concentrationsa'
CO-58 CO-60 cs-134 0.1 k 3.0 I 0.3 k 4.1 I 1.3 If: 2.7 1.2 k 2.8 I 3.8 f. 2.9 I -0.5 k 2.4 -2.4 f. 3.0 2.2 f. 4.6 0.7 f. 2.6 -1.7 k 2.0 0.7 k 1.6 -0.8 f. 1.7 "The range  
of MDCs for the selected radionuclides  
for samples WOO7O-WOO73  
is 13 pC1/L to 37 pCi/L "The range of MDCs for the selected radionuclides  
for samples WOO74-WOO77  
is 2.7 pCi/L to 5.0 pCi/L 'Uncertaintm represent the  
95% confidence  
level, based on total propagated uncertainties  
cs-137 13.730 k 470 51 0.5 k 2.2 -0.7 k 1.6 11 Indian Point Power  
Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14   
+ 0' 5' a 8 Fe-!Sb -19 ? 19" (32) -17 k 19 (32) -3 t 19 (32) TABLE 3 Ni-63" H-3d 452 ? 40 (35) 2,830 t 380 (420) 435 ? 39 (35) 2,350 t 360 (420) 1,207 2 85 (35) 1,500 k 320 (420) 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 -4 ? 19 (32) -6 t 19 (32) -1 t 19 (32) ORISE NRC Region I Sample ID Sample ID -0.4 k 8.2 (14.1) 130 t 250 (420) 0.3 & 8.2 (14.1) -94 t 230 (420) 2.0 t 8.3 (14.1) -220 k 230 (420) 11 1697W0073
I MW-42@,48
11 1697W0074
I MW-59@70 11 1697W0075
I LAF-001-(003)  
11 . 1697W0076
I LAF-002-(003)  
11 1697W0077  
I LAF-003-(003)  
-2 t 19 (32) I 1.272 k 89 (35) I 1.370 ? 310 (420) 2 If: 19 (32) I 2.6 2 8.3 (14.1) I -40 k 240 (420) %e MDCs for each radionuclide are in parentheses.  
bFe-55 analyzed using procedure  
AP13, Revision 4. 'Ni-63 analyzed using procedure  
AP17, Revision 0 dH-3 analyzed using  
procedure  
AP2, Revision 15. 'Uncertainties represent  
the 95% confidence  
level, based on total propagated uncertainties  
L P 
TABLE 4 ORISE Sample ID 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) 1697W0074  
1697W0075
1697W0076
1697W0077
MW-59@70 -4.7 k 8.9 (15.6) LAF-001-(003)  
-2.7 k 9.0 (15.6) LAF-002-(003)  
-0.5 k 9.1 (15.6) LAF-003-(003)  
2.8 k 9.1 (15.6) %rhc MDCs are in parentheses. 'Uncertainties reprcsent  
the 95% confidence  
Icvel, based on total propagated  
uncertainties.  
Indian Point Power Station projects/l697/Data  
Tables/2007-02-02  
Data Tables Set  
14 
TABLE 5 ORISE Sample ID 1697W0070
1697W0071
1697W0072
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 MDCs" (pCi/L)  
Mw-42@41 20.2 k 2.Ob (2.3) MW-42@43 15.7 k 1.7 (1.9) MW-42@46 32.8 f 2.4 (2.2) 1697W0073  
1697W0074
1697'0170075
1697W0076
1697W0077
MW-42@48 35.0 k 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 ? 0.55 (0.87) LAF-003-(003)  
-0.17 k 0.45 (0.83) Indian Point  
Power Station projects/l697/Data  
Tables/2007-02-02  
Data Tables Sct 14
TABLE 6 Cm-242 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 Cm-243/244  
N~-237 ORISE NRC Region I Sample ID 0.01 ? 0.01 (0.02) 0.07 k 0.06 (0.08) 0.00 ? 0.01 (0.03) 0.03 ? 0.06 (0.10) 0.01 k 0.01 (0.02) 1697W0070
m-42@41 0.03 k 0.09b (0.15) 1697M0033  
Mw-42@41 0.01 & 0.02 (0.04) 1697W0071
MW-42@43 0.07 k 0.09 (0.15) 0.00" & 0.02 (0.03) 0.00 k 0.02 (0.03) 0.01 f. 0.09 (0.17) 0.01 ? 0.02 (0.03) -0.01 k 0.02 (0.04) -0.01 f. 0.02 (0.04) -0.03 f. 0.07 (0.14) 0.03 & 0.06 (0.11) 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.03) 11 1697M0036
0.03 k 0.03 (0.02) 0.00 ? 0.01 (0.02) 0.02 f. 0.02 (0.03) m-42@48 0.00 ? 0.02 (0.04) 1697W0074
m-596370 0.00 k 0.05 (0.09) 2 1697M0037
m-59@70 -0.01 k 0.02 (0.04) .z 1697W0075
uF-001-(003)
0.03 f. 0.04 (0.07) , uF-001-(003)
0.02 f. 0.02 (0.03) E 2 - 1. L --. 1697M0038
U -' 0.01 f. 0.07 (0.14) -0.04 f. 0.05 (0.12) -0.01 k 0.02 (0.04) 0.002 f. 0.004d (0.007) -0.01 k 0.04 (0.08) 0.02 f. 0.02 (0.02) 2 11 1697W0076
I LAF-002-(003)  
I -0.02 f. 0.05 (0.09) 0.00 f. 0.03 (0.06) 0.00 f. 0.01 (0.02) 0.01 ? 0.02 (0.03) 0.00 k 0.01 (0.02) R 11 1697M0039
I LAF-002-(003)  
I 0.01 f. 0.02 (0.03) 0.00 k 0.03 (0.05) 0.00 f. 0.04 (0.08) 0.00 k 0.02 (0.03) 0.00 f. 0.01 (0.03) 0.00 f. 0.01 (0.01) -0.06 k 0.04 (0.10) 0.00 f. 0.01 (0.02) 0.002 ? 0.004 (0.006) I I e a 2 cn e P 0.01 ? 0.04 (0.07) I 0.01 & 0.08 (0.14) I 0.01 k 0.02 (0.03) 0.01 ? 0.01 (0.01) I 0.00 k 0.02 (0.03) I 0.00 f. 0.01 (0.03) I 1 0.00 f. 0.03 (0.06) I -0.02 k 0.04 (0.08) I 0.00 f. 0.01 (0.04) 0.01 ? 0.01 (0.03) I -0.01 k 0.02 (0.04) I 0.002 f. 0.005 (0.007)
i3 cn 8 d W Indian Point
Power Station F hl : 8 i +I 3 8 - F 01 9 9 9 +I 3 0 + 8 - fl + 9 0. 3 8 8 8 L 8 8 8 +I i - G hl +I 0 - 3 hl F M M 0 3 r- s\ W i T 7 C 5 7 C C t 7 C C - /- 7 C 5 r C C + r C C - r n C s 7 c C + 7 C C - G s C h C C + h C c - M 8 f d- M 0 3 r. c\ W 3 projccts/l697/Data
Tables/2007-02-02
Data Tables Set 14 
TABLE 7 Mw-42048 MW-59@70 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 (16.1) I -0.6 k 3.5 -2.5 k 9.3 ll* MW-59@70 LAF-001-(003)
LAF-001-(003)  
LAF-002-(003)  
LAF-002-(003)  
1697M0036
1697W0074
1697M0037
1697W0075
1697M0038
1697W0076
1697M0039
-0.9 k 3.4 (5.9) -2.7 k 7.9 (13.7) 1.1 k 3.5 (6.0) -6.4 If: 7.8 (13.6) 1.4 - + 3.6 (6.1) ll* LAF-003-(003)  
LAF-003-(003) "MDCs are in parenthescs
-2.5 k 8.2 (14.2) 2.6 ? 3.5 (5.9) Radionuclide
Concentrationsa (pCi/g of
sediment in 100 mL or pCi/L for water) NRC Region I Sample ID Mw-42@41 I -3 +_ 1 7b (29) 11 Mw-42@41 Mw-42@43 MW-42@43 -0.6 3.7
6.4) Mw-42@46 -10 (27) 'Uncertainties represent
the 95% confidence
level, based on total propagated uncertainhes Indian Point
Power Station projects/l697/Data
Tables/2007-02-02
Data Tables Set 14 
TABLE 8 ORISE Sample ID 1697W0070
1697W0071
1697W0072
1697W0073
1697W0074
CONCENTRATIONS
OF CARBON-14
IN WATER SAMPLES
BY LIQUID SCINTILLATION
ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide
Concentrations, Sample ID MW-42@41 0.8 k 9.7b (16.4) MW-42@43 8.8 * 9.8 (16.4) MW-42@46 0.2 * 9.6 (16.4) MW-42@48 -0.6
k 9.6 (16.4) MW-59@70 6.9 - + 9.8 (1 6.4) TPUs, and MDCS" (pCi/L)
1697W0075
1697W0076
1697W0077 ~ ~ LAF-001-(003)
0.5 k 9.7 (16.4) LAF-002-(003)
1.4 * 9.7 (16.4) LAF-003-(003)  
8.3 ? 9.8 (1 6.4) Indian Point Power Station  
projects/l697/Data  
Tables/2007-02-02  
Data Tables Set 14
}}

Latest revision as of 17:00, 13 March 2020

Ltr from Orise Dtd 02/02/2006, Second Interim Report for Requested Analyses of Eight Water Samples, Set Fourteen, from the Indian Point Power Station, Buchanan, New York (IR 05000247/2006007) (Rfta No.06-001)
ML070940515
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/02/2006
From: Condra D
Oak Ridge Institute for Science & Education
To: Kottan J
Decommissioning Branch I
References
IR-06-007, RFTA 06-001
Download: ML070940515 (11)
v • d • e


Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION February 2,2006 Mr. Jim Kottan U S . Nuclear Regulatory Commission Regon I 475 Allendale Road IOng of Prussia, PA 19406

SUBJECT:

SECOND INTERIM REPORT FOR REQUESTED ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, 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 h d g e Institute for Science and Education (ORISE) received set 14, whch consisted of eight water samples received on September 26,2006 from the InQan Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous hection for handling samples from h s facihty. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by RaQological 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-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.

ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of h s ralonuclide. ORISE is Qscontinuing the reporting of Ni-59 data untd

&Is problem can be resolved.

The water samples were processed using a deviation to the sample preparation procedure, SP3, Revision 4. The water samples were frltered through 0.45 micron filter papers. An aliquot was removed for tritium and carbon-14 before aciQfication. 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 analyzed the filtered solid portion of each sample for all the requested alpha isotopes.

M KJim Kottan Febmay 2,2006 My contact information is listed below. You may also contact Wade Ivey at 865.576.9184with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:WI:db Enclosures C: B. Watson, FSME/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN 8A23 S. IGrk, ORISE M. Roberts, NRC Region I J. Whte, 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: Dale.Condra@orau.org

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 1697WO07Oa MW-42@41 9/18/2006 14:45 1697M0033b MW-42@41 9/18/2006 14:45 1697W0071 MW-42@43 9/18/2006 13:OO 1697M0034 I MW-42@43 I 9/18/2006 I 13:OO 1697W0072 I MW-42@46 I 9/15/2006 I 12:45 1697M0035 I MW-42@46 I 9/15/2006 I 12:45 1697W0073 I MW-42@48 I 9/15/2006 I 11:20 1697M0036 MW-42@48 9/ 15/2006 11:20 169773170074 MW-59@70 9/15/2006 10:20 1697M0037 MW-59@70 9/15/2006 10:20 1697W0075 LAF-001-(003) 9/19/2006 15:49 1697M0038 I LAF-001-(003) I 9/19/2006 I 15:49 1697W0076 I LAF-002-(003) I 9/19/2006 I 13:41 1697M0039 I LAF-002-(003) I 9/19/2006 I 13:41 1697W0077 I LAF-003-(003) I 9/19/2006 I 11:08 1697M0040 I LAF-003-fO03) I 9/19/2006 I 11:08

%e W in the ORISC sample identification represents a water matrix.

bThe M in the ORISE sample identification represents the filtered fraction of the preceding water sample Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

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 NRC Region I Radionuclide Concentrationsa' 5 1 Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697W0070 I MW-42@41 13.730 k 470 1697W0071 I MW-42@43 1697W0072 MW-42@46 1697W0073 MW-42@48 1697W0074 0.1 k 3.0 I 0.3 k 4.1 I 1.3 If: 2.7 1697W0075 LAF-001-(003) 1.2 k 2.8 I 3.8 f. 2.9 I -0.5 k 2.4 1697W0076 LAF-002-(003) -2.4 f. 3.0 2.2 f. 4.6 0.7 f. 2.6 0.5 k 2.2 1697W0077 LAF-003-(003) -1.7 k 2.0 0.7 k 1.6 -0.8 f. 1.7 -0.7 k 1.6 1 "The range of MDCs for the selected radionuclides for samples WOO7O-WOO73 is 13 pC1/L to 37 pCi/L "The range of MDCs for the selected radionuclides for samples WOO74-WOO77 is 2.7 pCi/L to 5.0 pCi/L

'Uncertaintm represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

+

'0 5' TABLE 3 a

8 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 NRC Region I Sample I D Sample ID Fe-!Sb Ni-63" H-3d

-19 ? 19" (32) 452 ? 40 (35) 2,830 t 380 (420)

-17 k 19 (32) 435 ? 39 (35) 2,350 t 360 (420)

-3 t 19 (32) 1,207 2 85 (35) 1,500 k 320 (420) 11 1697W0073 I MW-42@,48 -2 t 19 (32) I 1.272 k 89 (35) I 1.370 ? 310 (420) 11 1697W0074 I MW-59@70 -4  ? 19 (32) -0.4 k 8.2 (14.1) 130 t 250 (420) 11 1697W0075 I LAF-001-(003) -6 t 19 (32) 0.3 & 8.2 (14.1) -94 t 230 (420) 11 . 1697W0076 I LAF-002-(003) -1 t 19 (32) 2.0 t 8.3 (14.1) -220 k 230 (420) 11 1697W0077 I LAF-003-(003) 2 If: 19 (32) I 2.6 2 8.3 (14.1) I -40 k 240 (420)

%e MDCs for each radionuclide are in parentheses.

bFe-55 analyzed using procedure AP13, Revision 4.

'Ni-63 analyzed using procedure AP17, Revision 0 dH-3analyzed using procedure AP2, Revision 15.

'Uncertainties represent the 95% confidence level, based on total propagated uncertainties P

L

TABLE 4 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, NEW YORK ORISE NRC Region I Tc-99 Concentrationsa Sample ID Sample ID (pCi/L) 1697W0074 MW-59@70 -4.7 k 8.9 (15.6) 1697W0075 LAF-001-(003) -2.7 k 9.0 (15.6) 1697W0076 LAF-002-(003) -0.5 k 9.1 (15.6) 1697W0077 LAF-003-(003) 2.8 k 9.1 (15.6)

%rhcMDCs are in parentheses.

Uncertainties reprcsent the 95% confidence Icvel, based on total propagated uncertainties.

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

TABLE 5 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N 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) 1697W0070 Mw-42@41 20.2 k 2.Ob (2.3) 1697W0071 MW-42@43 15.7 k 1.7 (1.9) 1697W0072 MW-42@46 32.8 f 2.4 (2.2) 1697W0073 MW-42@48 35.0 k 2.3 (2.0) 1697W0074 MW-59@70 0.14 k 0.50 (0.89) 1697'0170075 LAF-001-(003) 0.10 k 0.52 (0.93) 1697W0076 LAF-002-(003) 0.97  ? 0.55 (0.87) 1697W0077 LAF-003-(003) -0.17 k 0.45 (0.83)

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Sct 14

TABLE 6 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Sample ID Cm-242 Cm-243/244 N~-237 1697W0070 m-42@41 0.03 k 0.09b (0.15) 0.01 ? 0.04 (0.07) I 0.01 & 0.08 (0.14) I 0.01 k 0.02 (0.03) 1697M0033 Mw-42@41 0.01 & 0.02 (0.04) 0.01 ? 0.01 (0.02) 0.00" & 0.02 (0.03) 0.00 k 0.02 (0.03) 1697W0071 MW-42@43 0.07 k 0.09 (0.15) 0.07 k 0.06 (0.08) 0.01 f. 0.09 (0.17) 0.01 ? 0.02 (0.03) 0.00 ? 0.01 (0.03) -0.01 k 0.02 (0.04) -0.01 f. 0.02 (0.04) 0.03 ? 0.06 (0.10) -0.03 f. 0.07 (0.14) 0.03 & 0.06 (0.11) 0.01 k 0.01 (0.02) 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.03) 0.03 k 0.03 (0.02) 0.01 f. 0.07 (0.14) -0.04 f. 0.05 (0.12) 1 1697M0036 m-42@48 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.02) -0.01 k 0.02 (0.04) 0.002 f. 0.004d (0.007) 2- 1697W0074 m-596370 0.00 k 0.05 (0.09) 0.02 f. 0.02 (0.03) -0.01 k 0.04 (0.08) 0.02 f. 0.02 (0.02) 2 1 .

1697M0037 m-59@70 -0.01 k 0.02 (0.04) 0.01 ? 0.01 (0.01) I 0.00 k 0.02 (0.03) I 0.00 f. 0.01 (0.03)

L I 1

.z

- -. 1697W0075 uF-001-(003) 0.03 f. 0.04 (0.07) 0.00 f. 0.03 (0.06) I -0.02 k 0.04 (0.08) I 0.00 f. 0.01 (0.04)

U E-' 1697M0038 , uF-001-(003) 0.02 f. 0.02 (0.03) 0.01 I

? 0.01 (0.03) -0.01 k 0.02 I (0.04) 0.002 f. 0.005 (0.007) 21 1697W0076 I LAF-002-(003) I -0.02 f. 0.05 (0.09) 0.00 f. 0.03 (0.06) 0.00 k 0.03 (0.05) 0.00 f. 0.04 (0.08)

R 1 1697M0039 I LAF-002-(003) I 0.01 f. 0.02 (0.03) 0.00 f. 0.01 (0.02) 0.00 k 0.02 (0.03) 0.00 f. 0.01 (0.03) 0.01 ? 0.02 (0.03) 0.00 f. 0.01 (0.01) -0.06 k 0.04 (0.10)

I I 0.00 k 0.01 (0.02) 0.00 f. 0.01 (0.02) 0.002 ? 0.004 (0.006) e a

cn 2

e P

F T hl 7 C

5 i 7 C

8 C

+I t 3 7 8 C C

F /-

01 7 9 C i3 9 5 8

cn d

W 3

9 0

+I r

C C

+

+ r C

8 C

-fl r

+ n 9 C

0. s 3 7 c

8 C

+I +

i 7 8 C C

G G C

8 L

s hl h 8 C C

+I +

0 h C

8 c 3 M 8 8 hl F f M d-M M 0 0 3

r-3 r.

s\ c\

W W i 3 Indian Point Power Station projccts/l697/Data Tables/2007-02-02 Data Tables Set 14

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N 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 NRC Region I Sample ID (pCi/g of sediment in 100 mL or pCi/L for water)

  • l Mw-42@41 Mw-42@41 Mw-42@43 I -3 +_ 17b (29) 11 MW-42@43 -0.6 3.7 6.4)

Mw-42@46 -10 (27) 1697M0036 1697W0074 1697M0037 Mw-42048 MW-59@70 MW-59@70

-0.6

-2.5

-0.9 k

k k

3.5 9.3 3.4 (16.1)

(5.9)

I 1697W0075 LAF-001-(003) -2.7 k 7.9 (13.7) 1697M0038 LAF-001-(003) 1.1 k 3.5 (6.0) 1697W0076 LAF-002-(003) -6.4 If: 7.8 (13.6) 1697M0039 LAF-002-(003) 1.4 +

- 3.6 (6.1)

  • l LAF-003-(003)

LAF-003-(003)

-2.5 2.6 k

?

8.2 3.5 (14.2)

(5.9)

"MDCs are in parenthescs

'Uncertainties represent the 95% confidence level, based on total propagated uncertainhes Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

TABLE 8 CONCENTRATIONS OF CARBON-14 I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample I D Sample ID TPUs, and MDCS"(pCi/L) 1697W0070 MW-42@41 0.8 k 9.7b (16.4) 1697W0071 MW-42@43 8.8

  • 9.8 (16.4) 1697W0072 MW-42@46 0.2
  • 9.6 (16.4) 1697W0073 MW-42@48 -0.6 k 9.6 (16.4) 1697W0074

~

MW-59@70

~

6.9 +

- 9.8 (16.4) 1697W0075 LAF-001-(003) 0.5 k 9.7 (16.4) 1697W0076 LAF-002-(003) 1.4

  • 9.7 (16.4) 1697W0077 LAF-003-(003) 8.3  ? 9.8 (16.4)

Indian Point Power Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

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