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


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{{#Wiki_filter:OAK RIDGE INSTITUTE  
{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 19,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road I<ing of Prussia, PA 19406
FOR SCIENCE AND EDUCATION  
 
January 19,2006 Mr. Jim Kottan US. Nuclear Regulatory  
==SUBJECT:==
Commission  
FINAL REPORT FOR REQUESTED ANALYSES OF THREE WATER SAMPLES, SET TWELVE, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
Region I 475 Allendale  
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Road I<ing of Prussia, PA 19406 SUBJECT: FINAL REPORT FOR REQUESTED  
 
ANALYSES OF THREE WATER SAMPLES, SET TWELVE, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION  
==Dear Mr. Kottan:==
REPORT NO. 050-247/2006-0071  
 
[RFTA NO. 06-0011 Dear Mr. Kottan: The Oak &dge Institute for  
The Oak &dge Institute for Science and Education (ORISE) received set twelve, whtch consisted of three water samples received on September 20, 2006 from the I n l a n Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for handlrng samples from thts fachy. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Ralologcal and Environmental Sciences Laboratory. Sample identification and collection data for the samples addressed in thts report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), technetium-99, total ralostrontium, 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.
Science and Education (ORISE) received set twelve, whtch consisted of three 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  
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 fiter papers.
20, 2006 from the Inlan Point Power Station in Buchanan, New  
An aliquot was removed for tritium and carbon-14 before acilfication. 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. The remaining aliquot of each sample was adjusted to a pH of approximately 2 with concentrated HN03.
York. Sample analysis was initiated based  
 
on your previous direction  
Mr. Jim Kottan                                                           Janzlaly 19,2006 My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
for handlrng samples from thts fachy. The final report was delayed untd technical concerns  
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C:     B. Watson, FSME/DWMEP/DD/SP 7E18                     E. Abelquist, ORISE E. ICnox-Davin, NRC/FSME/TWFN 8A23                   S. IGrk, ORISE M. Roberts, NRC Regon I                             J. White, NRC Region I File 1697 Distribution approval and concurrence :  InitialS;-"\
about plutonium  
Technical Management Team Member                      &A      ZCL Quality Manager                                      " C i -n/
in water samples were resolved  
Voice: 865.241.3242               Fax: 865.241.3248             E-mad: Dale.Condra@orau.org
through analytical testing conducted  
 
by Ralologcal  
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID                  Sample ID                                              Time 11    1697W0067"                MW-54206'                I    9/7/2006           I      13:OO 1697M0030b                MW-54 206'                   9/7/2006                   13:OO MW-65 80'                   9/8/2006                    9:40 1697M0031                  MW-65 80'              I   9/8/2006           I       9:40 MW-5685'               I   9/8/2006           I       11:15 1      1697M0032                  MW-5685'               I   9/8/2006           I       11:15 "l'he W in the ORISE sample identification represents a water matrix bThe M in the OFUSE sample identification represents the filtered fraction of the preceding water sample.
and Environmental  
Indian Point Power Station                                                                       projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve
Sciences Laboratory.  
 
Sample identification  
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE                  NRC Region I                         Radionuclide Concentrationsa (pCi/L)
and collection data for the samples addressed in  
Sample ID                  Sample ID                     CO-58               CO-60             cs-134           cs-137 1697W0067                  MW-54 206'                 -2.1 k 2.0b 1.0 k 1.8 -0.3                     k 2.0 0.6 -I 1.6 1697W0068                  MW-65 80'                 -2.7 k 2.9 0.3 k 2.4 -0.3 k 2.5 0.2 & 2.2 1697W0069                  MW-56 85'                 -1.0 k 3.0 2.8 k 2.2 -0.6 ? 2.3 8.1 & 3.0 T h e range of MDCs for the selected radionuclides is 2.8 pCi/L to 4.7 pCi/L.
thts report are presented  
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), technetium-99, total  
Indian Point Power Station                                                                     projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve
ralostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables  
 
2 through Table 8, respectively.  
TABLE 3 Radionuclide Concentrationsa(pCi/L)
The pertinent procedure references are provided  
ORISE                NRC Region I Sample ID                 Sample ID                        Fe-55b                     Ni-59"                 Ni-63"                         H-3d 1697W0067           i   MW-54 206'             i                           i
in each specific table.  
                                                        -15 k 19' (32) -3.3 k 5.0 (8.7) 5.9 k 8.4 (14.1) i                          i 2,180     k 350 (420) I 1697W0068           I     MW-65 80'                                           I 1-15 k 19 (32) -2.6 k 5.0 (8.7) 3.2 k 8.3 (14.1)   I                          I -120 k 230 (42O)Il 1697W0069           I     MW-56 85'                                           I 1-10 k 19 (32) -9.3 k 4.9 (8.7) 5.2 k 8.3 (14.1)   I                           I  900 k 290 (420)l m c  MDCs for each radionuclide are in parentheses.
ORISE's Quality Control (QC) requirements  
"I'e-55 analyzed using procedure AP13, Revision 4.
were met for these  
'Ni-59/63 analyzed using procedure AP17, Revision 0.
analyses.  
d11-3 analyzed using procedure AP2, Revision 15.
The QC files are available  
"Uncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station                                                             projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve
for your review upon request. The water samples were processed  
 
using a deviation  
TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
to the sample preparation procedure, SP3, Revision 4. The water samples were filtered through 0.45  
I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Tc-99 ORISE      NRC Region I Sample ID     Sample ID        Concentrationsa (pCi/L) 1697W0067     MW-54 206'   -1.2 k 9.0b (15.6) 1697W0068      MW-65 80'     -1.8 k 9.0               (15.6) 1697W0069      MW-56 85'     3.5 & 9.2               (15.6)
micron and 0.1 micron fiter papers. An aliquot was removed for tritium and carbon-14 before  
Indian Point Power Station                                 projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve
acilfication.  
 
An aliquot was removed for alpha  
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 Radionuclide ORISE                NRC Region I                      Concentrations, Sample ID                  Sample ID                    TPUs, and MDCS" 1697W0067                MW-54 206'                 14.8             1.2b     (o.ij 1697W0068                  MW-65 80'                 0.56       ? 0.49         (0.80) 1697W0069                  MW-56 85'                 2.96       ? 0.76         (1.01)
analysis and the pH was adjusted to approximately zero  
T h e MDCs u e in parcntheses
using concentrated  
                          'Uncertainhes rcpresent the 95"h confidence level, based on total propagated uncertamhes.
nitric acid (HN03) and a few drops of hydrofluoric  
Indian Point Power Station                                                                  projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve
acid (HF'). A pH of zero and a few drops of HF should ensure  
 
that any plutonium that  
TABLE 6 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 ORISE    NRC Region I       Radionuclide Concentrationsa(pCi/g of sediment in 100 mL or pCi/L for water)
may be in the sample remains  
Sample ID    Sample ID Am-241                Cm-242            Cm-243/244              Np-237 1697wo067    Mw-54206'  O.OOb f 0.12'   (0.26) 0.10 k 0.10 (0.15) 0.00 f     0.12   (0.26) 0.04 f   0.10   (0.20) 1697M0030    Mw-54206'   0.01 f 0.02 (0.03) 0.00 k 0.01 (0.03) 0.00 f         0.01 (0.03) 0.00 k     0.01   (0.02) 1697W0068    Mw-65 80'   0.04 f 0.15 (0.28) 0.00 ? 0.06 (0.15) 0.04 f         0.10 (0.19) -0.02 k   0.08 (0.20) 16971110031  Mw-65 80'   0.01 k 0.02 (0.03) 0.00 f 0.01 (0.02) 0.00 k         0.01 (0.03) 0.01 f     0.01   (0.02) 1697W0069    Mw-56 85'   0.04 f 0.13 (0.26) -0.06 rf: 0.13 (0.31) 0.04 f     0.10 (0.20)   0.04 rf: 0.08   (0.15) 1697M0032    Mw-56 85'  0.01 f 0.02 (0.03) 0.01 k 0.01 (0.01) 0.00 f         0.01 (0.02)   0.01 f 0.01     fO.011
in solution.  
 
ORISE analyzed the filtered solid  
TABLE 6 (Continued)
portion of each sample for  
ORISE               NRC Region I                         Radionuclide Concentrationsa(pCi/g of sediment in 100 mL or pCi/L for water)
all the requested alpha isotopes.  
Sample ID                 Sample ID                            Pu-238                       P~-239/240           U-234               U-238 1697&'0067                 Mw-542061pp0.13                    k 0.19        (0.32)    0.05 k 0.10 (0.17) 7.38 k 0.90 (0.20) 4.11 _+   0.61 (0.05) 1697~0030                  MW-54206'               0.02       k   0.02     (0.03)     0.00 k 0.01 (0.01) 0.02 k 0.02 (0.02) 0.01 +_   0.01 (0.01) 1697W0068                  Mw-65 80'               0.11       k 0.13         (0.22)     0.00 k 0.05 (0.14) 7.63 k 0.92 (0.20) 4.64 +_ 0.67 (0.05) 1697M0031                  Mw-b5 80'               0.01       k   0.01     (0.01) 0.01 k 0.01 (0.01) 1.43 k 0.14 (0.02) 1.03 k 0.11 (0.02) 1697W0069                  Mw-5685'               0.06       k 0.14         (0.26)     0.12 k 0.10 (0.06) 1.17 k 0.33 (0.16) 1.37 _+   0.36 (0.16) 1697M0032                  MW-56 85'             -0.01 k         0.01     (0.03)     0.01 k 0.01 (0.02) 0.09 k 0.03 (0.02) 0.12 k   0.03 (0.01)
The remaining aliquot of each sample  
L h
was adjusted to a pH of approximately 2  
a  %e MDCs are in parentheses.
with concentrated  
-4..
HN03.
U  bZero values are due to rounding 5
Mr. Jim Kottan -2- Janzlaly 19,2006 Distribution
3  'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
approval and concurrence
E
: Technical
-z..
Management
Ec s
Team Member Quality Manager My contact information  
L
is listed below.  
 
You may also contact Wade Ivey  
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AJ?lO, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I                        Radionuclide Concentrationsa ORISE
at 865.576.91
                                                                                        @Ci/g of sediment in 100 mL or Sample ID                      Sample ID pCi/L for water) 1697W0067                      MW-54 206'                         15          +
84 with any questions  
                                                                                                      -        15b              (25) 1697M0030                      MW-54 206'                         0.0'        &        3.5              (6.0) 1697W0068                      MW-65 80'                           3
or comments.  
* 14             (23)
InitialS;-"\
I
A& ZCL "Ci -n/ Sincerely, Dale Condra, Manager Laboratory  
                        ~~
RDC:wPI:km  
1      1697M0031                       MW-65 80'                 I     1.3         k       3.3             (5.5) 1697W0069                      MW-56 85'                          17         k         16             (27) 1697M0032                      MW-56 85'                         2.3         k       3.6             (6.1)
Enclosures  
                  *MDCs are in parentheses.
C: B. Watson, FSME/DWMEP/DD/SP  
                  'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.
7E18 E. Abelquist, ORISE E. ICnox-Davin, NRC/FSME/TWFN  
                  'Zero value is due to rounding.
8A23 M. Roberts, NRC Regon I File 1697 S. IGrk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248  
Indian Point Power Station                                                                     projects/l697/Data 'Tables/2006-01-19 Data Tables Set Twelve
E-mad: Dale. Condra@orau. org
 
TABLE 1 MW-54 206' MW-65 80'
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 ID       Sample ID      TPUs, and MDCsa (pCi/L) 11 1697W0067  I  MW-54206'    I  -2      k        1lb 1697W0068       MW-65 80'      -2      t        11 1697W0069       MW-56 85'        1      k        11           (18)
SAMPLE IDENTIFICATIONS  
Indian Point Power Station                                   projccts/l697/Data ?hbles/2006-01-19 Data 'Tables Set Twelve}}
AND COLLECTION  
DATA INDIAN POINT POWER STATION 9/7/2006 13:OO 9/8/2006 9:40 ORISE Sample ID 11 1697W0067" 1 697M0030b
1697M0031
11 1697M0032
BUCHANAN, NEW YORK Sample ID Time MW-54206'  
I 9/7/2006 I 13:OO MW-65 80' I 9/8/2006 I 9:40 MW-5685' I 9/8/2006 I 11:15 MW-5685' I 9/8/2006 I 11:15 "l'he W in the ORISE sample identification represents  
a water matrix bThe M in the OFUSE sample identification represents  
the filtered fraction  
of the preceding  
water sample. Indian Point Power  
Station projects/l697/Data  
Tables/2006-01-19  
Data Tables Set Twelve
TABLE 2 ORISE Sample ID 1697W0067
1697W0068
1697W0069
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 (pCi/L) Sample ID CO-58 CO-60 cs-134 cs-137 MW-54 206' -2.1 k 2.0b 1.0 k 1.8 -0.3 k 2.0 0.6 -I 1.6 MW-65 80' -2.7 k 2.9 0.3 k 2.4 -0.3 k 2.5 0.2 & 2.2 MW-56 85'  
-1.0 k 3.0 2.8 k 2.2 -0.6 ? 2.3 8.1 & 3.0 The range of MDCs for the selected radionuclides  
is 2.8 pCi/L to 4.7 pCi/L. buncertainties  
represent  
the 95% confidence  
level, based on total propagated uncertainties. Indian Point Power Station  
projects/l697/Data  
Tables/2006-01-19  
Data Tables Set Twelve
TABLE 3 ORISE Sample ID Radionuclide Concentrationsa (pCi/L) NRC Region I Sample ID Fe-55b Ni-59" Ni-63" H-3d  
1697W0067  
i MW-54 206' i -15 k 19' (32) i -3.3 k 5.0 (8.7) i 5.9 k 8.4 (14.1) i 2,180 k 350 (420) 1697W0068  
I MW-65 80' 1-15 k 19 (32) I -2.6 k 5.0 (8.7) I 3.2 k 8.3 (14.1) I -120 k 230 (42O)Il I 1697W0069  
I MW-56 85'  
1-10 k 19 (32) I -9.3 k 4.9 (8.7) I 5.2 k 8.3 (14.1) I 900 k 290 (420)l mc MDCs for each radionuclide are  
in parentheses. "I'e-55 analyzed using  
procedure  
AP13, Revision 4. 'Ni-59/63 analyzed using  
procedure AP17, Revision  
0. d11-3 analyzed using  
procedure  
AP2, Revision 15. "Uncertainties represent the  
95% confidence level, based on total propagated  
uncertainties  
Indian Point Power Station  
projects/l697/Data  
Tables/2006-01-19  
Data Tables Set Twelve
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 Tc-99 NRC Region I Sample ID Concentrationsa (pCi/L) 1697W0067  
1697W0068
1697W0069
b MW-54 206' -1.2 k 9.0 (15.6) MW-65 80' -1.8 k 9.0 (15.6) MW-56 85' 3.5 & 9.2 (15.6) Indian Point Power Station projects/l697/Data  
Tables/2006-01-19  
Data Tables Set Twelve
Indian Point
Power Station ORISE Sample ID TABLE 5 Radionuclide
NRC Region I Concentrations, Sample ID TPUs, and MDCS" 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 1697W0067
1697W0068
1697W0069
MW-54 206' 14.8 1.2b (o.ij MW-65 80' 0.56 ? 0.49 (0.80) MW-56 85' 2.96 ? 0.76 (1.01) The MDCs ue in parcntheses  
'Uncertainhes  
rcpresent  
the 95"h confidence  
level, based on total propagated uncertamhes.  
projects/l697/Data  
Tables/2006-01-19  
Data Tables Set Twelve
TABLE 6 ORISE Sample ID 1697wo067
1697M0030
1697W0068
16971110031
1697W0069
1697M0032
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 Sample ID Mw-54206'
O.OOb f 0.12' (0.26) 0.10 k 0.10 (0.15) 0.00 f 0.12 (0.26) 0.04 f 0.10 (0.20) Mw-54206'  
0.01 f 0.02 (0.03) 0.00 k 0.01 (0.03) 0.00 f 0.01 (0.03) 0.00 k 0.01 (0.02) Mw-65 80' 0.04 f 0.15 (0.28) 0.00 ? 0.06 (0.15) 0.04 f 0.10 (0.19) -0.02 k 0.08 (0.20) Mw-65 80' 0.01 k 0.02 (0.03) 0.00 f 0.01 (0.02) 0.00 k 0.01 (0.03) 0.01 f 0.01 (0.02) Mw-56 85' 0.04 f 0.13 (0.26) -0.06 rf: 0.13 (0.31) 0.04 f 0.10 (0.20) 0.04 rf: 0.08 (0.15) Radionuclide Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water) Am-241 Cm-242
Cm-243/244
Np-237 Mw-56 85' 0.01 f 0.02 (0.03) 0.01 k 0.01 (0.01) 0.00 f 0.01 (0.02) 0.01 f 0.01 fO.011
TABLE 6 (Continued)  
ORISE Sample ID NRC Region I Radionuclide Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water) Sample ID Pu-238 P~-239/240 U-234 U-238  
1697&'0067  
1697~0030
1697W0068
1697M0031
1697W0069
1697M0032
L h 4 -.. a U %e MDCs are in parentheses.  
bZero values are due to
rounding 'Uncertainties represent
the 95% confidence
level, based on total propagated uncertainties.  
5 3 E E z c s -.. L Mw-542061pp0.13
k 0.19 (0.32) 0.05 k 0.10 (0.17) 7.38 k 0.90 (0.20) 4.11 _+ 0.61 (0.05) MW-54206'  
0.02 k 0.02 (0.03) 0.00 k 0.01 (0.01) 0.02 k 0.02 (0.02) 0.01 +_ 0.01 (0.01) Mw-65 80' 0.11 k 0.13 (0.22) 0.00 k 0.05 (0.14) 7.63 k 0.92 (0.20) 4.64 +_ 0.67 (0.05) Mw-b5 80' 0.01 k 0.01 (0.01) 0.01 k 0.01 (0.01) 1.43 k 0.14 (0.02) 1.03 k 0.11 (0.02) Mw-5685' 0.06 k 0.14 (0.26) 0.12 k 0.10 (0.06) 1.17 k 0.33 (0.16) 1.37 _+ 0.36 (0.16) MW-56 85' -0.01 k 0.01 (0.03) 0.01 k 0.01 (0.02) 0.09 k 0.03 (0.02) 0.12 k 0.03 (0.01)
TABLE 7 ORISE Sample ID 1697W0067
1697M0030
1697W0068
CONCENTRATIONS
OF PLUTONIUM-241
IN SUSPENDED
AND DISSOLVED FRACTIONS
OF WATER SAMPLES BY LIQUID SCINTILLATION
ANALYSIS AJ?lO, 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 MW-54 206' MW-54 206' MW-65 80' 3 * 14 (23) 15 - + 1 5b (25) 0.0' & 3.5 (6.0) 1697W0069
1697M0032
~~ 11 1697M0031  
I MW-65 80'  
I 1.3 k 3.3 (5.5) 17 k 16 (27) MW-56 85' MW-56 85' 2.3 k 3.6 (6.1) *MDCs are in parentheses. 'Uncertainties represent the  
95% confidence  
level, based on total propagated uncertainties. 'Zero value  
is due to rounding. Indian Point Power Station  
projects/l697/Data  
'Tables/2006-01-19  
Data Tables Set Twelve
TABLE 8 ORISE Sample ID 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 TPUs, and MDCsa (pCi/L) 1697W0068  
1697W0069  
11 1697W0067
I MW-54206'
I -2 k 1lb MW-65 80' -2 t 11 MW-56 85' 1 k 11 (1 8) Indian Point Power Station  
projccts/l697/Data  
?hbles/2006-01-19  
Data 'Tables Set Twelve
}}

Latest revision as of 07:41, 23 November 2019

Ltr from Orise Dtd 01/19/2006, Final Report for Requested Analyses of Three Water Samples, Set Twelve, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No.06-001)
ML070940574
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 01/19/2006
From: Condra D
Oak Ridge Institute for Science & Education
To: Kottan J
Decommissioning Branch I
References
IR-06-007, RFTA 06-001
Download: ML070940574 (11)
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Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION January 19,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road I<ing of Prussia, PA 19406

SUBJECT:

FINAL REPORT FOR REQUESTED ANALYSES OF THREE WATER SAMPLES, SET TWELVE, 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 twelve, whtch consisted of three water samples received on September 20, 2006 from the I n l a n Point Power Station in Buchanan, New York. Sample analysis was initiated based on your previous direction for handlrng samples from thts fachy. The final report was delayed untd technical concerns about plutonium in water samples were resolved through analytical testing conducted by Ralologcal and Environmental Sciences Laboratory. Sample identification and collection data for the samples addressed in thts report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-59/63, and tritium), technetium-99, total ralostrontium, 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 and 0.1 micron fiter papers.

An aliquot was removed for tritium and carbon-14 before acilfication. 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. The remaining aliquot of each sample was adjusted to a pH of approximately 2 with concentrated HN03.

Mr. Jim Kottan Janzlaly 19,2006 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:km Enclosures C: B. Watson, FSME/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E. ICnox-Davin, NRC/FSME/TWFN 8A23 S. IGrk, ORISE M. Roberts, NRC Regon I J. White, NRC Region I File 1697 Distribution approval and concurrence : InitialS;-"\

Technical Management Team Member &A ZCL Quality Manager " C i -n/

Voice: 865.241.3242 Fax: 865.241.3248 E-mad: Dale.Condra@orau.org

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID Sample ID Time 11 1697W0067" MW-54206' I 9/7/2006 I 13:OO 1697M0030b MW-54 206' 9/7/2006 13:OO MW-65 80' 9/8/2006 9:40 1697M0031 MW-65 80' I 9/8/2006 I 9:40 MW-5685' I 9/8/2006 I 11:15 1 1697M0032 MW-5685' I 9/8/2006 I 11:15 "l'he W in the ORISE sample identification represents a water matrix bThe M in the OFUSE sample identification represents the filtered fraction of the preceding water sample.

Indian Point Power Station projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve

TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrationsa (pCi/L)

Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697W0067 MW-54 206' -2.1 k 2.0b 1.0 k 1.8 -0.3 k 2.0 0.6 -I 1.6 1697W0068 MW-65 80' -2.7 k 2.9 0.3 k 2.4 -0.3 k 2.5 0.2 & 2.2 1697W0069 MW-56 85' -1.0 k 3.0 2.8 k 2.2 -0.6 ? 2.3 8.1 & 3.0 T h e range of MDCs for the selected radionuclides is 2.8 pCi/L to 4.7 pCi/L.

buncertainties represent the 95% confidence level, based on total propagated uncertainties.

Indian Point Power Station projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve

TABLE 3 Radionuclide Concentrationsa(pCi/L)

ORISE NRC Region I Sample ID Sample ID Fe-55b Ni-59" Ni-63" H-3d 1697W0067 i MW-54 206' i i

-15 k 19' (32) -3.3 k 5.0 (8.7) 5.9 k 8.4 (14.1) i i 2,180 k 350 (420) I 1697W0068 I MW-65 80' I 1-15 k 19 (32) -2.6 k 5.0 (8.7) 3.2 k 8.3 (14.1) I I -120 k 230 (42O)Il 1697W0069 I MW-56 85' I 1-10 k 19 (32) -9.3 k 4.9 (8.7) 5.2 k 8.3 (14.1) I I 900 k 290 (420)l m c MDCs for each radionuclide are in parentheses.

"I'e-55 analyzed using procedure AP13, Revision 4.

'Ni-59/63 analyzed using procedure AP17, Revision 0.

d11-3 analyzed using procedure AP2, Revision 15.

"Uncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve

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 Tc-99 ORISE NRC Region I Sample ID Sample ID Concentrationsa (pCi/L) 1697W0067 MW-54 206' -1.2 k 9.0b (15.6) 1697W0068 MW-65 80' -1.8 k 9.0 (15.6) 1697W0069 MW-56 85' 3.5 & 9.2 (15.6)

Indian Point Power Station projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve

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 Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCS" 1697W0067 MW-54 206' 14.8 1.2b (o.ij 1697W0068 MW-65 80' 0.56  ? 0.49 (0.80) 1697W0069 MW-56 85' 2.96  ? 0.76 (1.01)

T h e MDCs u e in parcntheses

'Uncertainhes rcpresent the 95"h confidence level, based on total propagated uncertamhes.

Indian Point Power Station projects/l697/Data Tables/2006-01-19 Data Tables Set Twelve

TABLE 6 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 ORISE NRC Region I Radionuclide Concentrationsa(pCi/g of sediment in 100 mL or pCi/L for water)

Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697wo067 Mw-54206' O.OOb f 0.12' (0.26) 0.10 k 0.10 (0.15) 0.00 f 0.12 (0.26) 0.04 f 0.10 (0.20) 1697M0030 Mw-54206' 0.01 f 0.02 (0.03) 0.00 k 0.01 (0.03) 0.00 f 0.01 (0.03) 0.00 k 0.01 (0.02) 1697W0068 Mw-65 80' 0.04 f 0.15 (0.28) 0.00 ? 0.06 (0.15) 0.04 f 0.10 (0.19) -0.02 k 0.08 (0.20) 16971110031 Mw-65 80' 0.01 k 0.02 (0.03) 0.00 f 0.01 (0.02) 0.00 k 0.01 (0.03) 0.01 f 0.01 (0.02) 1697W0069 Mw-56 85' 0.04 f 0.13 (0.26) -0.06 rf: 0.13 (0.31) 0.04 f 0.10 (0.20) 0.04 rf: 0.08 (0.15) 1697M0032 Mw-56 85' 0.01 f 0.02 (0.03) 0.01 k 0.01 (0.01) 0.00 f 0.01 (0.02) 0.01 f 0.01 fO.011

TABLE 6 (Continued)

ORISE NRC Region I Radionuclide Concentrationsa(pCi/g of sediment in 100 mL or pCi/L for water)

Sample ID Sample ID Pu-238 P~-239/240 U-234 U-238 1697&'0067 Mw-542061pp0.13 k 0.19 (0.32) 0.05 k 0.10 (0.17) 7.38 k 0.90 (0.20) 4.11 _+ 0.61 (0.05) 1697~0030 MW-54206' 0.02 k 0.02 (0.03) 0.00 k 0.01 (0.01) 0.02 k 0.02 (0.02) 0.01 +_ 0.01 (0.01) 1697W0068 Mw-65 80' 0.11 k 0.13 (0.22) 0.00 k 0.05 (0.14) 7.63 k 0.92 (0.20) 4.64 +_ 0.67 (0.05) 1697M0031 Mw-b5 80' 0.01 k 0.01 (0.01) 0.01 k 0.01 (0.01) 1.43 k 0.14 (0.02) 1.03 k 0.11 (0.02) 1697W0069 Mw-5685' 0.06 k 0.14 (0.26) 0.12 k 0.10 (0.06) 1.17 k 0.33 (0.16) 1.37 _+ 0.36 (0.16) 1697M0032 MW-56 85' -0.01 k 0.01 (0.03) 0.01 k 0.01 (0.02) 0.09 k 0.03 (0.02) 0.12 k 0.03 (0.01)

L h

a %e MDCs are in parentheses.

-4..

U bZero values are due to rounding 5

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

E

-z..

Ec s

L

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AJ?lO, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide Concentrationsa ORISE

@Ci/g of sediment in 100 mL or Sample ID Sample ID pCi/L for water) 1697W0067 MW-54 206' 15 +

- 15b (25) 1697M0030 MW-54 206' 0.0' & 3.5 (6.0) 1697W0068 MW-65 80' 3

  • 14 (23)

I

~~

1 1697M0031 MW-65 80' I 1.3 k 3.3 (5.5) 1697W0069 MW-56 85' 17 k 16 (27) 1697M0032 MW-56 85' 2.3 k 3.6 (6.1)

  • MDCs are in parentheses.

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

'Zero value is due to rounding.

Indian Point Power Station projects/l697/Data 'Tables/2006-01-19 Data Tables Set Twelve

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 ID Sample ID TPUs, and MDCsa (pCi/L) 11 1697W0067 I MW-54206' I -2 k 1lb 1697W0068 MW-65 80' -2 t 11 1697W0069 MW-56 85' 1 k 11 (18)

Indian Point Power Station projccts/l697/Data ?hbles/2006-01-19 Data 'Tables Set Twelve

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