ML061880387
| ML061880387 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/23/2006 |
| From: | Condra D Oak Ridge Institute for Science & Education |
| To: | Kottan J Division of Nuclear Materials Safety I |
| References | |
| FOIA/PA-2006-0244, IR-06-007, RFTA 06-001 | |
| Download: ML061880387 (83) | |
Text
June 23,2006 Mr. Jim Kottan US. Nuclear Regulatoq Commission Regon I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
REPORT FOR REQUESTED ANALYSES OF THREE WATER SAMPLES, SET FOUR, COLLECTED MAY 3 AND 4,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received two water samples on May 8,2006 and one water sample on Map 9,2006 from the Indian Point Power Station in Buchanan, New York. The sample identifications and collection data are presented in Table 1. The gamma spectroscopy, total radiostrontium, hard to detect beta emitters (carbon-14, iron-55, nickel-59/63, tritium), technetium-99, alpha spectroscopy, and plutonium-241 data are provided in Tables 2 through Table 7, respectively. The pertinent procedure references are provided in the specific tables.
ORISE's QC requirements were met for these analyses. The QC fdes are available for your review upon request.
My contact information is listed below. You map also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory Enclosures cc:
B. Watson, NMSS/DWMEP/DD/SP 7E18 E. Abelquist, ORISE E.'IOlox-Davin, NRC/NMSS/TLVFN SA23 M. Miller, NRC Regon I File 1697 S. IGrk, ORISE J. White, NRC Region I Distribution approval and concurrence :
Technical Management Team Member Quality Manager Initials Voice: 8 6 5.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1697W0031 1697W0032 I
I I
li 1697W0030 i bottom laver I 5/3/2006 I 1550 bulk layer 5/3/2006 16:OO unit 2 manhole #5 5/4/200 6 14:28 Indian Point Powcr Station projccts/l697/Data 'Tabl~~/2006-06-23 Data 'I'ablc Sct Four
3
- 0.
B' ORISE Sample ID 1697W0030 1697W003 1 1697W0032 e
- 2.
2 NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID co-58 CO-60 CS-134 (3-137 bottom layer 2.5
+-
2.2b 2.5 f
3.7 2.5 f
2.3 2,895 rf:
91 bulk layer
-2.4
+-
2.1
-0.1 f
2.3 1.5 f
2.8 2,870 f
90 unit 2 manhole #5
-0.5
+-
1.5
-0.2 f
1.6 1.1 f
2.2 0.1 f
2.7 TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK kJncertainties represent the 95% confidence level, based on total propagated uncertainties
TABLE 3 ORISE Sample ID 1697W0030 NRC Region I Radionuclide Concentrations, Sample ID TPUs, and MDCs" (pCi/L) bottom layer 352 t
1 lb (1) 11 1697W0031 I bulklayer I
349 t
11 (1)
II 11 1697W0032 I unit 2 manhole #5 I 0.18
+-
0.55 (0.96) 11
'MDCS are in parentheses bUncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data Tablcs/2006-06-23 Data Tablc Set Pour
TABLE 4 ORISE NRC Region I Sample ID Sample ID Radionuclide Concentrations" (pCi/L)
C-14b Fe-55" Ni-59d Ni-63d H-3' 1697W0030 1697W0031 1697W0032 "I'hc MDCs for cach radionuclide are in parcnthcscs.
'C-14 analyzcd using procedure AP9, Rcvision 3
'Fc-55 analyzcd using procedure AP13, Rcvision 4.
'Ni-j9/63 analyzed using procedure AP17, Rcvision 0.
'H-3 analyzcd using procedure AP2, Rcvision 15.
'Uncertainties represent the 95% confidcncc Icvcl, based on total propagated uncertainties P
bottom layer
-6 f. 16' (28)
-56 f 28 (49)
-9.2 f. 2.6 (4.7) 24.2 k 3.5 (4.8) 1,880 k 310 (380) bulk layer 1 f 16 (28)
-43
? 28 (49)
-7.2 f 2.6 (4.7) 24.4 k 3.5 (4.8) 1,800 k 310 (380) unit2 manhole #5
-15 f. 16 (28)
-60 k 28 (49)
-0.6 f 2.7 (4.7)
-1.4
- f. 2.8 (4.8) 2,210
- f. 330 (380)
TABLE 5 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 SampleID.
@Ci/L)
II I
I il 1
1697W0030 bottom layer 1.9 k 8.9b (15.3) 1697W0031 bulk laver 240 k 21 (15) 11 1697W0032 I unit2 manhole #5 I 10.7
?
9.2 (15.3) 11 Ihc hlDCs arc in parenthcscs bUnccrtainties represent the 9!i?n confidence Ic~cl, based on total propagated uncertainties.
Indian Point Power Station projects/l697/Data ?ablcs/2006-06-23 Data Iablc Set Four
TABLE 6 ORISE Sample ID NRC Region I Sample ID 1697W0030 I
bottom laver Am-241
-0.01 k 0.12' (0.25) 0.01 rt 0.11 (0.22) 0.04 k 0.20 (0.38) 1697W0031 I bulk layer Cm-242 Cm-243 / 244 Np-237 0.03 k 0.06 (0.11) -0.01 k 0.11 (0.22) 0.03 k 0.05 (0.08) 0.01 k 0.06 (0.12) 0.00' k 0.09 (0.18) -0.06 k 0.06 (0.15)
-0.14 k 0.13 (0.34) 0.02 k 0.15 (0.30) -0.05 k 0.04 (0.12) 1697W0032 I unit 2 manhole #5 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa (pCi/L)
i I
TABLE 6 (Continued)
ORISE NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID Sample ID Pu-238 Pu-239/240 U-234 U-238 1697W0030 bottom layer 0.09 -I-0.09 (0.15) 0.01 k 0.03 (0.06) 0.43
& 0.12 (0.08) 0.51 t: 0.13 (0.07) 1697W0031 bulk layer 0.07 -I- 0.10 (0.16) 0.00 i 0.05 (0.11) 0.41 i 0.13 (0.13) 0.41
_+
0.12 (0.08) 1697W0032 unit 2 manhole #5 0.11 i 0.09 (0.15) 0.05 & 0.05 (0.08) 0.32 k 0.11 (0.11) 0.33 k 0.11 (0.09) hUnccrtaintics rcprcscnt thc 95% confidence level, based on total propagatcd unccrtaintics
%ro vducs arc due to rounding.
TABLE 7 ORISE NRC Region I Sample Sample ID ID 1697W0030 bottom layer 1697W0031 bulk layer 1697W0032 umt 2 manhole #5 Pu-241 Concentrationsa (pCi/L)
-2 k
13b (23) 2 k 15 (26) 3 13 (23)
Indian Point I'owcr Station projccts/l697/llata 'I'ablcs/2006-06-23 Data 'l'ablc Set I'our
P&_t,Ll T P \\ l q I L-c:,
LA1 i
,-. 1,? -
-J OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Distribution approval and concurrence :
Technical Management Team Member Quality SIanager June 21,2006 Mr. Jim Kottan US. Nuclear Regulatory Comssion Region I 475 Allendale Road IOng of Prussia, PA 19406 c -
- j f 1. f rl
, I 1,: 3 F6I 2: 17 MAD &f+
00 @c(t(le
SUBJECT:
SECOND INTERIM REPORT FOR COMPLETED ANALYSES OF ONE SOIL SAMPLE AND THIRTEEN WATER SAMPLES COLLECTED APRIL 11,2006 THROUGH APRIL 18,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received one soil sample and 13 water sampIes on April 25,2006 from the In&an Point Power Station in Buchanan, New York.
This is the second interim letter report containing addtional data for the requested analyses for the one soil sample and thirteen water samples that have been completed. The sample identifications and collection data are presented in Table 1. The technetium-99 data, the alpha spectroscopy data, the plutonium-241 data, and the carbon-14 data are in Table 2 through Table 5, respectively. The pertinent procedure references are provided in the specific tables.
ORISEs QC requirements were met for these analyses. The QC files are available for y o u review upon request.
My contact information is listed below. You map also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerelv.
Dale Condra, Manager Laboratory RD C:wPI: ar Enclosures C:
B. Watson, NRC/NMSS/TWFN 7 E18 E. Abelquist, ORISE E. Ibox-Davin, NRC/NMSS/TWFN 8x23 M. Miller, NRC Regon I File 1697 S. I e k, ORISE J. Whte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
ORISE Sample ID Collection Date 11 1697W0018 Collection Time 11 1697W0019 MH-1 Shore discharge MW-40 4" 200' MW-51 4" 200' 1697W0021 1697W0024 4/18/2006 13:30 411 1/2006 18:15 4/11/2006 17:OO 11 1697W0025 MW-47 2" 56' Unit 2 MH#5 Hudson discharge MH-1 11 1697W0026 4/13/2006 12:05 4/17/2006 13:OO 4/18/2006 13:30 1697W0027 1697W0028 :
1697W0029 TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Sample ID MW-48 1" 37.5' I 4/12/2006 I 1O:OO 11 MW-48 2" 52' I 4/12/2006 I 9 5 8 11 MW-43 2" 62' 4/12/2006 MW-46 4" 30' I 4/12/2006 I 17:15 11 MW-47 1" 80' I 4/13/2006 I 11:45 11 Indian Point Pomcr Station 1697/Data 'l'ables/2006-06-21 2nd Interim Data Tables Set 'Three
TABLE 2 ORISE Sample ID CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN ONE SOIL SAMPLE AND 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Tc-99 Concentrationsa Sample ID (pCi/g or pCi/L) 1 1697S0001 MH-1 Shore dscharge 0.25 t 0.18b (0.30) 1697W0017 Mw-40 4" 200' 2
t 19 (32) 11 1697W0018 1
Mw-51 4" 200' I 4 k
19 (32) 11
-~
~~
~
~
1697W0019 Mw-48 1" 37.5' 10 k 19 (32) 1697W0020 MW-48 2" 52'
-6 t 18 (32) 1697W0021 MW-43 2" 28' 5
t 19 (32) 1697W0022 1697W0023 1697W0024 MW-43 2" 62' 6
t 19 (32)
MW-41 1" 63' 1
k 19 (32)
MW-41 2" 41'
-4 k
18 (32) 1697W0026 1697W0027 1697'370028 I 1697W0029 I HudsondischargeMH-1 I
-1 k
19 (32) I "I'he MDCs are in parcnthescs "Unccrtantics represent the 35% confidcncc level, based on total propagatcd unccrtaintics.
MW-47 1" 80' 13 k 19 (32)
MW-47 2" 56'
-6 2 18 (32)
Unit 2 MH#5 2
I 19 (32)
Indian Point I'owcr Station 1697/13ata ?'ablcs/2006-06-21 2nd Intcrim Data l'ablcs Sct 'I'hrcc
I 3
3 g L
c\\
U
-4
\\ ;
E E) e:
c c
c 2
Y I\\)
0 0
0
- 0.
3 3
0 -
5 3
6 r; z TABLE 3 ORISE NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697WOO 17 MW-40 4" 200' 0.01 k 0.08b (0.16) 0.04 2 0.04 (0.02) -0.03 f 0.08 (0.16) 0.01 f 0.05 (0.10) 1697WOO 18 0.05 2 0.07 (0.12) 0.06 f 0.05 (0.06) 1697WOO 19 MW-48 1" 37.5' 0.14 k 0.11 (0.17) 0.00' 2 0.03 (0.08) 0.05 f 0.08 (0.14) 0.01 f 0.05 (0.10) 1697W0020 MW-48 2" 52' 0.07 t 0.07 (0.11)
-0.03 f 0.04 (0.11) -0.02 f 0.08 (0.16) -0.01 f 0.02 (0.06) 1697W002 1 MW-43 2" 28' 0.07 t 0.10 (0.17) 0.00 f 0.04 (0.09) -0.02 f 0.08 (0.16) 0.00 f 0.04 (0.08) 1697W0022 MW-43 2" 62'
-0.05 f 0.09 (0.18) 0.00 2 0.04 (0.09) 0.03 f 0.08 (0.15) -0.05 f 0.06 (0.16) 1697W0023 MW-41 1" 63' 0.08 f 0.18 (0.33) 0.02 k 0.07 (0.15) -0.02 2 0.11 (0.23) 0.02 2 0.05 (0.08) 1697W0024 MW-41 2" 41' 0.02 t 0.13 (0.25) 0.00 f 0.03 (0.09) -0.02 k 0.11 (0.22) -0.03 t 0.03 (0.10) 1697W0025 MW-46 4 30' 0.07 If: 0.18 (0.32) 0.06 k 0.07 (0.11) 0.04 0.12 (0.23) 0.03 -t 0.05 (0.09) 1697W0026 MW-47 1" 80' 0.01 t 0.14 (0.26) 0.01 t 0.08 (0.17) -0.04 f 0.12 (0.25) 0.02 f 0.04 (0.06) 1697W0027 MW-47 2" 56'
-0.06 k 0.15 (0.30) 0.03 2 0.06 (0.11) 0.03 f 0.13 (0.24) 0.00 2 0.02 (0.06) 1697W0028 Unit 2 MH#5
-0.07 f 0.13 (0.28) 0.04 k 0.05 (0.04) -0.03 f 0.13 (0.27) -0.03 t- 0.05 (0.12)
Hudson discharge 1697W0029 MH-1 0.05 k 0.10 (0.18) 0.01 f 0.05 (0.10) -0.02 f 0.09 (0.18) 0.01 k 0.04 (0.08)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN 13 WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
TABLE 3 (Continued)
ORISE Sample ID 1697WOO 17 1697WOO 18 1697WOO 19 1697W0020 1697W002 1 1697W0022 1697W0023 m
- 1.
a
?
NRC Region I Radionuclide Concentrationsa (pCi/L)
Sample ID PU-238 Pu-239/240 U-234 U-238 MW-40 4" 200' 0.00
? 0.08 (0.16) 0.03 t- 0.05 (0.08) 0.63 k 0.14 (0.05) 0.58 f 0.13 (0.07)
MW-51 4" 200' 0.13 t- 0.09 (0.12) 0.02 2 0.06 (0.11) 4.69 k 0.53 (0.10) 2.69 t- 0.36 (0.09)
MW-48 1" 37.5' 0.01 L 0.08 (0.15) 0.04 5 0.06 (0.10) 6.62 k 0.66 (0.11) 2.44 L 0.32 (0.12)
MW-48 2 52' 0.09
? 0.08 (0.12) 0.04 2 0.04 (0.02) 0.31 'r 0.09 (0.05) 0.21 t- 0.08 (0.05)
MW-43 2" 28' 0.16 t- 0.08 (0.10)
-0.01 t- 0.05 (0.11) 0.85 k 0.17 (0.07) 0.82 'r 0.17 (0.06)
MW-43 2"62' 0.00 ? 0.08 (0.16) 0.02 t 0.05 (0.09) 6.05 f 0.62 (0.16) 4.44 f 0.49 (0.09)
MW-41 1" 63' 0.17 k 0.10 (0.13) 0.06 t- 0.05 (0.06) 1.63 t- 0.23 (0.07) 1.25 t- 0.20 (0.06)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION l2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697W0024 1697W0025
~
MW-41 2 41' 0.08 f~ 0.11 (0.19) 0.02 k 0.04 (0.09) 0.76
-t 0.16 (0.08) 0.71 k 0.15 (0.05)
MW-46 4" 30' 0.07 k 0.09 (0.15) 0.07 2 0.06 (0.07) 0.87 t 0.17 (0.10) 0.56 t 0.14 (0.09) 1697W0026 1697W0027 MW-47 1 80' 0.05 k 0.11 (0.19) 0.06 k 0.04 (0.02) 1.22 k 0.19 (0.06) 0.99 k 0.17 (0.05)
MW-47 2" 56' 0.06 t- 0.08 (0.14) 1697W0029 "I'hc MDCs zrc in parcnthcscs.
"Unccrtaintics rcprcscnt thc 95% confidence level, based on total propagatcd unccrtaintics.
'Zero valucs arc duc to rounding.
Hudson discharge MH-1 0.10 f. 0.10 (0.16) 0.05 k 0.04 (0.02) 0.04 &
0.06 (0.09) 0.05 k 0.04 (0.02)
TABLE 4 ORISE Sample ID CONCENTRATIONS OF PLUTONIUM-241 (Pu-241)
IN l3 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Pu-241 NRC Region I Sample ID Concentrationsa (DCi/L) 1697W0017 1697W0018 1697WOOl9 1697W0020 1697W0021 1697W0022 1697W0023 u
I MW-40 4" 200' 4
k 14b (23)
MW-51 4" 200' 0" k 15 (27)
MW-48 1" 37.5'
-10 ? 14 (24)
MW-48 2" 52'
-9 k 13 (23)
MW-43 2" 28'
-5 If: 14 (25)
MW-43 2" 62'
-3 k 22 (38)
MW-41 1" 63' 6
? 15 (26) 1697W0024 1697W0025 1697W0026 1697W0027 1697W0028 1697W0029 "I'he hlDCs are in parentheses.
'Uncertainties represent the 95% confidcncc Icvel, based on total propagated uncertainties.
'Zero values are duc to rounding.
MW-41 2" 41'
-2
_+
16 (28)
MW-46 4" 30'
-4 k 13 (23)
MW-47 I" 80' 2
k 14 (25)
MW-47 2" 56' 2
If: 14 (24)
Unit 2 MH#5 0
- f. 14 (24)
Hudson discharge MH-1 6
k 14 (23)
Indian Point Poucr Station 1697/llata 'l'ablcs/2006-06-21 2nd Interim Data Tables Set 'lhrec
TABLE 5 ORISE Sample ID CONCENTRATIONS OF CARBON-14 (C-14)
IN 13 WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK C-14 NRC Region I Sample ID Concentrationsa
@ W L )
1697WOOl7 1697W0018 17 k 16 (27)
MW-40 4" 200' MW-51 4" 200' 1697W0019 1697W0020 1697W0021 MW-48 1" 37.5' 11 & 16 (27)
MW-48 2" 52' 1 ? 16 (27)
MW-43 2" 28' 8 ? 16 (27) 1697W0022 1697W0023
-9 k 16 (28) 1697W0027 MW-47 2" 56' 1697W0028 Unit 2 MH#5 3
k 16 (27)
MW-43 2" 62' MW-41 1" 63' "I'hc hlDCs are in parcnthcses.
'Uncertainties represent thc 9596 confidence level, based on total propagated unccrtaintics.
'7.cro valucs arc due to rounding.
1697W0024 1697W0025 1697W0026 MW-41 2" 41' 8 & 16 (27)
MW-46 4" 30' 0'
t 16 (28)
MW-47 1" 80' 0
t 16 (28)
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I -
7 1
. \\ '!
I..
Distribution approval and concurrence :
Quahe Manager Techmcal Management Team Member hlr. Jim Kottan U.S.
Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406 Initials
'l"uK A'*
SUBJECT:
FINAL REPORT FOR REQUESTED ANALYSES OF SIX WATER SAMPLES, SET TWO, COLLECTED APRIL 7,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear hllr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received six water samples on April 12, 2006 from the Indian Point Power Station in Buchanan, New York. This is the final letter report suinmarizing previously issued interim reports for the requested analyses for the six water samples. The sainple identifications and collection data are presented in Table 1. The gamma spectroscopy, strontium, iron-55, nickel-59/63, tritium, technetium-99, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Table 2 through Table 8, respectively. The pertinent procedure references are provided in the specific tables.
In the second interim report, the Cm-242 data for ORISE sample 1697W0013 was incorrectly reported.
A second issue arose when the uranium data reported by the licensee and our lab did not agree. A review of all the alpha spectroscopy data was initiated. All the alpha isotopic data was overestimated by a factor of five due to a transcription error in the sample quantity used for each calculation. We have initiated non-conformances to address both issues.
ORISE's QC requirements were met for these analyses. The QC files are available for your revlew upon request.
hIy contact information is listed below. You may also contact Wade Ioey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:\\YPI: ar Enclosures C:
B. Watson, NrVlSS/DW%I?EP/DD/SP 7E18 E. Xbelquist, OKISE E. Ihox-Davin, NRC/NhlSS/T\\VFN 8A23 M. Mdler, NRC Region I File 1697 S. IGrk, ORISE J. Wute, NRC Region I Voice: 865.241.3242 Fax 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 Collection I
NRCRegionl Sample ID I
Date ORISE SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Collection Time
~
1697W0011 1697W0012 1697W0013 1697WOO 14 1697WOO 15 1697W0016 Mw-42 LV41' (2")
4/7/2006 16:30 MW-42 LV43' (2")
4/7/2006 15:35 Mw-42 LV45.5' (2")
4/7/2006 14:37 MW-42 LV48' (2")
4/7/2006 12:45 MW-42 HV5 1' (2")
4/7/2006 17:50 MW-42 78' (1")
4/7/2006 17:20 Indian Point Poircr Station projects/l697/Data Tables/2006-06-16 Final Data Table Set Two
TABLE 2 ORISE Sample ID 1697W0011 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide C NRC Region I Sample ID CO-58 CO-60 b
MW-42 LV41' (2")
-3 f 13 70 ? 30 CS-134 6 f 16 CS-137 49,200 -e 1,600 1697W0012 1697'6170013 1697WOO 14 1697W0015 57 2 17
~
~
~
MW-42 Lv43' (2")
1.7 f 9.8 MW-42LV45.5'(2")
3.0 9.1 MW-42 LV48' (2")
11 f 18 MW-42 HY51' (2")
7 + 17
~-
63 rt 25 39 rt 26 63 ? 24 1
- 10 0" f 11
-9 f 18 4 -t 18 5 f 15 2 rt 10 mcentrationsa (DC~/L) 51,400 -e 1,600 51,400 1,700 52,500 f 1,700 35,900 f 1,200 61 f 17 1697W0016 MW-42 78' (1")
11.5 rt 9.6
TABLE 3 1697WOOll 1697WOO 12 1697W0013 MW-42LV41'(2")
175.9 r 6.3b (1.3)
MW-42LV43'(2")
161.6
- 5.8 (1.2)
MW-42 LV45.5' (2")
149.0
- 5.4 (1.2)
I
~
1697W0014 MW-42LV48' (2")
146.7
- 5.3 (1.2) 1697W0015 MW-42HV511(2")
184.4 6.4 (1.2) 1697W0016 MW-42 78' (1")
0.63 f 0.75 (1.26)
"MDCs are in parentheses buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian Point Power Station projects/l697/Data Tablcs/2006-06-16 Final Data 'I'ablc Sct Two
M 3
- 0.
ORISE Sample ID 1697W0011 1697W0012 1697W0013 1697W0014 I
1697W0015 1697W0016 TABLE 4 I
Radionuclide Concentrationsa (pCi/L)
NRC Region I Sample ID Fe-55b Ni-59" Ni-63" H-3d MW-42LV41'(2")
18 k 34' (57) -321 k 13 (21) 5,730 f 350 (20) 1,860 4 310 (390)
MW-42LV43'(2")
118 4 37 (57) 1 4 13 (22) 5,910 k 370 (20) 2,050 k 320 (390)
MW-42LV45.5'(2") t 33 (57)
-88 k 10 (22) 5,980 f 370 (20) 2,030 k 320 (390)
MW-42LV48'(2")
-9 4 33 (57) -423 4 16 (23) 6,740 k 420 (20) 1,880 k 320 (390)
MW-42 HV51'(2")
Of k 33 (57) -220 +_ 10 (20) 5,260 k 320 (20) 2,160
-t_ 330 (390)
MW-42 78' (1")
-6 4 33 (57) 10.0 ? 6.3 (10.3) 18.9 k 6.5 (10.4) 340 k 240 (390)
Indian Point Power Station ORISE Sample ID TABLE 5 NRC Region I Sample ID CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697W0011 I MW-42 LV41' (2")
p1697WO015 I MW-42 HV51' (2")
1697W0016 I MW-42 78' (1")
Tc-99 Concentrations 3 k 18 (31) 1 ? 18 (31)
"Ikc hiDCs for each radionuckde are in parentheses
'Uncertaintics represent the 95% confidence level, based on total propagated uncertainties.
projects/l697/Data Tables/2006-06-16 Final Data 'Table Set Two
I 3
G g' ORISE NRC Region I Radionuclide Concentrationsa @Ci/L)
Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0011 MW-42Lv41' (2")
0.09 t 0.15b (0.25) 0.01 k 0.08 (0.17) 0.03 k 0.09 (0.17) -0.01 k 0.05 (0.10) 1697W0012 MW-42Lv43' (2")
0.06 t 0.17 (0.31) 0.00' k 0.09 (0.19) 0.02 t 0.13 (0.25) -0.04 f 0.05 (0.12) 1697WOO13 MX+42 LV45-5' (2")
0.05 t 0.13 (0.23) 0.01 k 0.06 (0.12) -0.11 f 0.10 (0.22) 0.00 k 0.04 (0.09) 1697W0014 MW-42Lv48' (2)
0.07 f 0.14 (0.25) 0.01 k 0.06 (0.13) 0.04 k 0.12 (0.22) 0.03 t 0.04 (0.06) 1697woo15 m - 4 2 H V 5 1 ' (2")
-0.03 t 0.15 (0.30)
-0.07 t 0.07 (0.20) -0.10 t 0.14 (0.30) 0.01 f 0.04 (0.08) 1 1697W0016 MW-4278' (1")
0.06 f 0.16 (00.30) 0.00 t 0.09 (0.20) -0.05 f 0.17 (0.35) 0.01 f 0.04 (0.09)
'j 8.
TABLE 6
I 3
3 r$
ORISE NRC Region I Sample ID Sample ID 1697W0011 MW-42Lv41' (2")
TABLE 6 (Continued)
Radionuclide Concentrationsa (pCi/L)
Pu-238 Pu-239/240 U-234 U-238 0.13 1- 0.08 (0.11) 0.04 1- 0.05 (0.09) 1.28 k 0.20 (0.05) 1.35 & 0.21 (0.08)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697W0014 m - 4 2 L v 4 8 ' (2")
0.18 k 0.09 (0.12) 0.05 rf: 0.05 (0.07) 1.55 k 0.23 (0.02) 1.33 k 0.21 (0.02) 1697TVo015 m - 4 2 H V 5 1 ' (2")
0.08 -I 0.07 (0.10) 0.03 -I 0.05 (0.08) 1.52 k 0.24 (0.02) 1.27 ? 0.22 (0.09) 1 1697W0016
Indian Point Power Station 1697W0015 1697W0016 TABLE 7 Mw-42 HV51' (2")
-6 k 14 (24)
Mw-42 78' (1")
-2
- 21 (37)
CONCENTRATIONS OF PLUTONIUM-241 (Pu-241)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK I
ORISE I NRC Region1 I a I Concentrations Sample ID O W L )
Sample ID 11 1697W0011 I MW-42 LV41' (2") I -3 k 14b (24) 11 (1
1697W0012 I MW-42 LV43' (2")
1 -1 k 14 (24) (1 I-rMW-42 Lv45.51 (211) I 14 (24) 11 11
~ 1697W0014 I MW-42LV48' (2") I -2 k 14 (24) 11
~
~~~
~
"fie hlDCs are in parentheses.
buncertainties represent the 950'0 confidence IC\\-el, based on total propagated uncertainties projects/l697/Data Tables/2006-06-16 Final Data Table Set Two
Indian Point Power Station ORISE Sample ID TABLE 8 C-14 NRC Region I Sample ID Concentrationsa (pCi/L)
CONCENTRATIONS OF CARBON-14 (C-14)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697W0012 1697W0013 1697W0014 1697W0015 1697W0016 MW-42 LV43' (2")
-6 k 16 (27)
MW-42 LV45.5' (2")
-1 k 16 (27)
Mw-42 LV48' (2")
-4 k 16 (27) hIW-42 HV51' (2")
1 k 16 (27)
MW-42 78' (1")
-4 k 16 (27) 11 1697W0011 I W-42LV4l1(2") I 6 k 1 6 ~ (27)
'fie AiDCs are in parentheses.
'Uncertainties represent the 95% confidence level, based on total propagated uncertainties projects/lG97/Data Tablcs/2006-06-16 Final Data 'I'able Set Two
r' -(.', ' I 7
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATlOl 4I June 13,2006 hlr. Jim Kottan US. Nuclear Regulatoq Commission Region I 475 Xllendale Road IOng of Prussia, PA 19406
SUBJECT:
FINAL REPORT FOR REQUESTED ANALYSES OF TEN WATER SAMPLES, SET ONE, COLLECTED MARCH 22,2006 TO MARCH 24,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear hfr. Kottan:
The Oak h d g e Institute for Science and Education (ORISE) received ten water samples on IvIarch 31,2006 from the I n l a n Point Power Station in Buchanan, New York. This is the final letter report summarizing two previously issued interim reports for the requested analyses for the ten water samples. The sample identifications and collection data are presented in Table 1. The gamma spectroscopy, strontium, iron-55, nickel-64, tritium, technetium-99, alpha spectroscopy, and plutonium-241 data are in Table 2 through Table 7, respectively. The pertinent procedure references are provided in the specific tables.
The analytical request for carbon-1 4 (C-14) could not be completed. The mater samples were filtered and acidified before an aliquot for the (2-14 analysis was taken from each sample. Any C-14 present in the water samples would be osilzed to COz which would out gas from the samples. We apologze for the error and all laboratory staff members have been reminded to take a separate aliquot for the C-14 analysis froin each water sample from I n l a n Point before acidification.
ORISE's QC requirements were met for these analyses. The QC files are available for your review upon request. At present, OliISE does not participate in a performance evaluation program that includes plutonium-241, neptunium, and curium isotopes, but the Nuclear Regulatory Commission's Intercomparison Testing Program is being expanded to include these radonuclides.
Mr. Jim Kottan Distribution approval and concurrence :
Quality Manager Technical Management Team Member Initials V k L. -
June 13,2006 My contact information is listed below. You may also contact Wade Ioey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, hlanager Laboratory RDC:WPI:db Enclosures C:
B. Watson, NMSS/DWnlEP/DD/SP 7E18 E. &os-Davin, NRC/NMSS/TWFN 8x23 M. Miller, NRC Region I File 1697 E. Abelquist, ORISE S. IOrk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample NRC Region I Collection ID Sample ID Date SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Collection Time 1697W0001 1697W0002 1697W0003 1697W0004 1697W0005 MW-50 42' 3/22/2006 14:30 MW-50 67' 3/22/2006 14:40 MW-49 25' 3/22/2006 16:50 MW-49 42' 3/22/2006 16:45 MW-49 65.5' 3/22/2006 16:45 11 1697W0006 I MW-42 49' I 3/23/2006 I 11:15
-1 69%0008p MW-36 26' 3/23 12006 16:00 1697W0009 MW-36 41' 3/24/2006 13:15 3/23/2006 16:00 1697W0010 MW-36 52' 11 1697W0007 I MW-42 78' I 3/24/2006 I 9:45 Indian Point I'on.cr Station
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK The range of MDCs for the selected radionuclides is 2.8 pCi/nL to 5.4 pCi/mL.
kncertainties represent the 95% confidence levcl, based on total propagated uncenaintics.
TABLE 3 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 aMDCs are in parentheses.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian h i n t l'o\\vcr Station 1G37/I)ata 'lhblcs/2006-06-13 1st Intcrim Data 'l'ablc
's, s.
3 ORISE Sample NRC Region I ID Sample ID 1697W0001 hIw-50 42' TABLE 4 Radionuclide Concentrationsa (pCi/L)
-14 k 72' (124) 4.2 k 5.2 (8.8) 5.4 f 5.4 (9.0) 8,190 k 550 (400)
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 1697W0002 1697W0003 1697WOOO4 hIw-50 67'
-10 2 72 (124)
-2.4 2 5.0 (8.8) 9.9 I 5.5 (9.0) 9,490 f 590 (400)
MW-49 25'
-48 2 72 (124) 3.4 I 5.2 (8.8) 6.3 k 5.4 (9.0) 14,240 ? 740 (400)
Mw-49 42'
-30 It 72 (124) 7.3 f 5.3 (8.8) 5.6 f 5.4 (9.0) 9,130 k 580 (400)
L CI P' -
\\
0..
5 E:
13 3 0
CI 0
CI
~
~
~~~~
~~
~~~~~~~~~~~
1697W0005 Mw-49 65.5'
-33 f 72 (124) 2.0 k 5.2 (8.8) 7.9
& 5.5 (9.0) 6,290 2 490 (400) 1697W0006 MW-42 49'
-19 I 72 (124) 71.9 f 7.8 (8.8) 1392 ? 86 (9) 2,290 2 340 (400) 1697W0007 MW-42 78'
-36 & 72 (124) 2.8 5.2 (8.8) 53.4 ? 7.3 (9.0) 510 2
250 (400) 1697W0008 Mw-36 26'
-39 k 72 (124)
-3.9 f 5.0 (8.8) 67.3 k 8.0 (9.0) 35,100 f 1,300 (400) 1697W0009 MW-36 41' 24 k 73 (124) 0.1 k 5.1 (8.8) 47.4 ? 7.0 (9.0) 56,200 f 1,800 (400) 1697W0010 MW-36 52'
-44 2 72 (124)
-0.3 f 5.1 (8.8) 10.3 f 5.5 (9.0) 26,900 k 1,100 (400)
TABLE 5 ORISE Sample ID 1697W0001 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)
MW-50 42'
-3 t 18b (31) 1697W0003 1697W0004 11 1697W0002 I hIw-50 67' I
-6 2
18 (31)
Mw-49 25'
-1 2
18 (31)
Mw-49 42' 1
f 18 (31) 1697W0006 1697W0007 1697W0008 11 1697W0005 I MW-49 65.5' I
-7 k 18 (31)
Mw-42 49'
-6 k 18 (31) hIw-42 78'
-14 k
18 (31)
Mw-36 26' 6
k 18 (31) 11 1697W0009 I hW-3641' I
9
?
19 (31)
I 1697W0010 1
hW-36 52' I
14 f 19 (31)
"I'hc > I l X s arc in parentheses.
"Unccrraintics rcprcscnt the 95":) confidence IcvcI, bascd on total propagatcd uncertaintics.
Indian Point Pmvcr Station 1697/Data 'l'ablcs/2006-06-13 1st Intonm Data 'l'able
TABLE G CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
TABLE 6 (Continued)
Pu-239/ 240 0.03 k 0.15 (0.33) 0.14 ? 0.31 (0.56) 0.03 ? 0.11 (0.25) 0.20 k 0.18 (0.12)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK U-234 U-238 0.80 k 0.34 (0.30) 0.65 I 0.35 (0.41) 0.44 k 0.31 (0.40) 0.54 k 0.30 (0.28) 1.03 k 0.41 (0.39) 0.57 k 0.35 (0.46) 2.18 k 0.54 (0.23) 0.83 4 0.32 (0.09) 1.58 & 0.55 10.44) 0.94 k 0.41 (0.30)
Pu-238 ORISE Sample NRC Region I Sample ID 1697W0002 1697W0003 MW-50 67 0.46 k 0.47 (0.76)
MW-49 25 0.65 ? 0.48 (0.721 0.16 ? 0.30 (0.54) 0.08 k 0.26 (0.51) 0.29 k 0.22 (0.12) 0.00 4 0.18 (0.41) 0.08 k 0.19 (0.37) 1.31 k 0.61 (0.76) 1.03 4 0.48 (0.53) 1.89 k OS8 (0.45) 1.38 &
0.48 (0.35) 0.76 ? 0.38 (0.40) 0.47 4 0.28 (0.28) 0.17 ? 0.32 (0.56) 0.24 k 0.28 (0.46) 1.66 k 0.59 (0.66) 0.86 k 0.37 (0.32)
Radionuclide Concentrationsa (pCi/L)
II 1 697 WOO08 1697W0009 MY+-36 26 0.37 k 0.44 (0.72)
MW-36 41 0.11 ? 0.43 (0.79) 1697W0010 MW-36 52 0.15 k 0.42 (0.76)
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 (Pu-241)
I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK a,, 1 he h1DCs arc in parcnthcscs.
'Unccrtaintics represent thc 9j0.;, confidence Icvel, based on total propagated uncertaintics.
'Zero \\.aiucs arc duc to rounding.
Indian Point I'os.cr Statmn 1697,'lIata 'l'ablcs/2006-06-13 1st Inrcrim Data 'lhblc
P OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
?EGfOW 1 Distribution approval and concurrence :
Technical Llanagement Team hlember Ouahh; hfanaeer hIay 36,2006 Initials f/ i-I t
hlr. Jim Kottan US.
Nuclear Regulatory Commission Region I 475 Xllendale Road IOng of Prussia, PA 19406
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES OF SIX WATER SAMPLES COLLECTED APRIL 7,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear hfr. Kottan:
The Oak hdge Institute for Science and Education (ORISE) received six water samples on April 12, 2006 from the Indian Point Power Statlon in Buchanan, New York This letter report contains data for the analyses that hare been completed to date The sample identlhcafions and collecuon data are presented in Table 1, the technetiun~99 data are presented in Table 2, the alpha spectroscopy data are presented in Table 3 and the plutonium-241 data arc presented in Table 4 The pertincnt procedure references are provided in the specific tables ORISEs QC requiremcnts were met for these analyses. The QC files are arailable for your review upon request.
As more analytical data becomes available, additional interim letter reports \\vi11 be issued as needed. 1-1 final report will be issued when all requested analyses arc completed.
hTy contact informatlon is listed below. You may also contact Wade Ivey at 865.576.9183 lvih any questlons or comments.
Sincerely, Dale Condra, hlaniger Laboratory RDC:\\YTI:ar Enclosurcs C:
T. hfclaughhn, NRC/NhlSS/lTYFN 7F27 E. Zlbelquist, ORISE E. I(nos-Da\\-in, NRC/NhISS/T\\WN 8A23 M. Miller, NliC Region I File 1697 S. IOrk, OKISE J. \\illite, NRC Region I Voice: 865.231.3232 Fax: 865.24 1.3248 E-mail: CondraD@or;lu.gov
TABLE 1 11
~
ORISE SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I I Collection I Collection 1697W0012 1697W0013 1697W0014 Time I
Date I
Sample ID I1 Samp*elD I MW-42 LV43' (2")
4/7/2006 15:35 MW-42 LV45.5' (2")
4/7/2006 14:37 MW-42 LV48' (2")
4/7/2006 12:45 11 1697WOOl1 I
MW-42LV41'(2") I 4/7/2006 I 16:30 11 1697W0015 I MW-42HV511(2") I 4/7/2006 1
17:50 11 1697W0016 I MW-42 78'")
I 4/7/2006 I
17:20 Indian Point Pomcr Station 1697/Data 'l'ablcs/2006-05-26 2nd Interim Data 'I'ablc Set Two
TABLE 2
- 1.
CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697WOO15 Mw-42 HV51' (2")
11 2 19 (31) 1697W0016 Mw-42 78' (1")
13 2 19 (31)
Tc-99 NRC Region I Sample ID Concentrationsa
@Ci/L)
ORISE Sample ID r 6 9 7 E O l l 1 MW-42 LV41' (2")
1 8 2 19b (31) 1 1697W0012 Mw-42 LV43' (2")
5 k 18 (31) 1697W0013 MW-42 LV45.5' (2")
3 k 18 (31) 1697W0014 hIW-42 LV48' (2")
1 k 18 (31)
The hIDCs for each radionuclide are in parentheses.
'Uncertainties represent the 3596 confidence le\\-el, based on total propagated uncertainties.
Indian Point Power Station 1697/Data Tablcs/2006-05-26 2nd Interim Data Table Set l'wo
3 3
Ej-ORISE Sample ID 1697W0011 TABLE 3 NRC Region I Sample ID Am-241 MW-42 LV41' (2")
0.37 f- 0.73" (1.27)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Cm-242 Cm-243 /244 0.06 t- 0.42 (0.84) 0.12 -t 0.43 (0.84) 0.00' f 0.44 (0.95) 0.08 -t 0.64 (1.25) 0.00 f 0.00 (0.62) -0.56 t- 0.49 (1.12) 0.07 t- 0.31 (0.66) 0.21
-t 0.60 (1.11)
-0.35 f 0.37 (0.99) -0.48 -t 0.71 (1.52) 0.00 f 0.46 (0.99) -0.24 t- 0.87 (1.74)
Np-237
-0.07 f 0.23 (0.52)
-0.22 f 0.25 (0.62) 0.00 f 0.21 (0.46) 0.15 f 0.19 (0.29) 0.04 f 0.19 (0.39) 0.06 f 0.21 (0.45)
TABLE 3 (Continued)
ORISE NRC Region I Sample ID Sample ID 1697W0011 m - 4 2 L v 4 1 ' (2")
1697W0012 m - 4 2 L v 4 3 ' (2")
1697W0013 m-42Lv45.5' (2")
1697W0014 m - 4 2 L v 4 8 ' (2")
1697W0015 m-42HV51' (2")
1697W0016 m - 4 2 78' (1")
Radionuclide Concentrationsa (pCi/L)
Pu-238 Pu-239/240 U-234 U-238 0.64 t 0.41 (0.55) 0.18 ? 0.26 (0.44) 6.4 f 1.0 (0.2) 6.7 T 1.1 (0.4) 0.69 t 0.39 (0.49) 0.29 f. 0.27 (0.40) 7.4
& 1.2 (0.4) 7.6 f 1.2 (0.4) 0.45 t 0.39 (0.60)
-0.07 i: 0.24 (0.54) 8.6 1.3 (0.5) 6.7 2 1.1 (0.6) 0.88 t 0.47 (0.58) 0.23 f. 0.24 (0.37) 7.7 f 1.1 (0.1) 6.6 t 1.0 (0.1) 0.42 -t 0.35 (0.51) 0.14 k 0.22 (0.39) 7.6 t 1.2 (0.1) 6.3 f 1.1 (0.4) 0.41 If: 0.43 (0.65)
-0.06 f 0.26 (0.65) 8.4
+L 1.3 (0.6) 8.2
? 1.3 (0.5) 5 e
g a
"The MDCs arc in parentheses.
"Uncertainties represent the 95% confidence Icvcl, basccl on total propaptcd unccrtaintics IJ c
s VI Zcro values arc due to rounding
TABLE 4 ORISE Sample ID CONCENTRATIONS OF PLUTONIUM-241 (Pu-241)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Pu-241 NRC Region I Sample ID Concentrationsa (pCi/L) 1697W0011 1697W0012 1697W0013 1697W0014 1697W0015 MW-42 LV41' (2")
-15 k (119)
Mw-42 LV43' (2")
-5
_+ 69 (119)
MW-42 LV45.5' (2")
22 k 70 (120)
MW-42 LV48' (2")
-11 & 69 (119)
MW-42 HV51' (2")
-28 k 68 (118) 1 6 9 7 ~ 0 0 1 6 ~
1 MW-42 78' I
llo (180)
T h c MDCs arc in parenthcscs.
bUncertmxies represent thc 95'4 confidence l e d, based on total propagated uncertainties.
Indian Point Power Station 1697/Data Tables/2006-05-26 2nd Interim Data Table Sct Two
Distribution approval and concurrence :
Technical Management Team Member Quahty Manager RECEIVE0 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
"'cy!;{
2 3 '
~
1
- Initials, Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES OF ONE SOIL SAMPLE AND THIRTEEN WATER SAMPLES COLLECTED APRIL 11,2006 THROUGH APRIL 18,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Insutute for Science and Education (ORISE) received one soil sample and 13 water samples on April 25, 2006 from the Indian Point Power Station in Buchanan, New York. This letter report contains data for the analyses that have been completed to date. The sample identifications and collection data are presented in Table 1, the gamma spectroscopy data are presented in Table 2, the total radiostrontium data are presented in Table 3, the hard to detect beta data for the 13 mater samples are presented in Table 4. The pertinent procedure references are provided in the specific tables.
ORISE's QC requirements were met for these analyses. The QC files are available for your review upon request.
As more analytical data becomes available, additional interim letter reports will be issued as needed. A final report will be issued when all requested analyses are completed.
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:\\VPI:ar Enclosure C:
T. Mclaughlin, NRC/NMSS/nVFN 7F27 E. Xbelquist, ORISE E. Ihox-Davin, NRC/NhfSS/TWFN 82123 M,
Mdler, NRC Region I File 1697 S. IOrk, ORISE J. White, NRC Regon I Voice: 865.241.3242 Fax 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 Collection Date SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Collection Time NRC Region I Sample ID 1697S0001 1697W0017 1697W0018 1 697W0019 MH-1 Shore discharge 4/18/2006 13:30 MW-40 4" 200' 4/11/2006 18:15 MW-51 4" 200' 4/11/2006 17:OO MW-48 1" 37.5' 4/12/2006 1o:oo 1697W0023 1697W0024 1697W0025 11 1697W0020 I
MW-48 2" 52' I
4/12/2006 1
9:58 11 MW-41 1" 63' 4/12/2006 14:45 MW-41 2" 41' 4/12/2006 15:OO MW-46 4" 30' 4/12/2006 17:15 11 1697W0021 I MW-43 2" 28' I 4/12/2006 I 12:45 11 1697W0027 1697W0028 1 6 9 7 ~ 0 0 2 9 11 1697W0022 I MW-43 2" 62' 1 4/12/2006 I 11:55 11 MW-47 2" 56' 4/13/2006 12:05 Unit 2 MH#5 4/17/2006 13:OO Hudson discharge MH-1 4/18/2006 13:30 11 1697W0026 I
MW-47 1" 80' I 4/13/2006 I 11:45 11
TABLE 2 NRC Region I Sample ID MH-1 Shore discharge MW-40 4" 200'
/I ORISE Sample ID Radionuclide Concentrationsa (pCi/g or pCi/L)
CO-58 CO-60 CS-134 CS-137 0.00' 0.03d 0.00 f 0.04 0.00 f 0.04 0.06 f 0.04
-0.1 2.6 2.3 f
2.1 1.0 35 2.1 2.0 f-4.4 I
1 697WOO 1 8 MW-5 1 4" 200' MW-48 1" 37.5' MW-48 2" 52' 1697W0020 0.8 f
2.5
-0.4 f
2.1 2.1 2.2 0.9 f
2.4
-3.3 5
1.7 0.0 f
2.0
-2.3 f
2.5 0.5 f
1.9 0.4 k
2.8 0.5 f
2.3 1.8
-i.
2.7 0.9 f-2.1 11 1697W0022 MW-43 2" 28' MW-43 2" 62' 1697WOO24 1697W0027 1.3 f
2.5
-0.6 f
2.6
-0.5 f
2.4 0.3 2.2 1.9 f
2.9 0.6 f
1.7
-3.0 f
2.5 0.0 f
1.6 11 1697W0028 MW-41 1" 63' MW-41 2" 41' MW-46 4" 30' 1697W0029
-0.2 f
2.6 0.3 f 2.3 0.0 f
2.3 2.1 f
2.1 0.0 f
2.7 0.1 f 2.6
-1.6 f
2.6 0.6 f-2.0
-1.5 k
2.2 3.1 f 3.2 0.5 2.2
-0.2 f-4.1 MW-47 1" 80' MW-47 2" 56'
-1.2 f
2.6 1.4 2.5 1.9 f
2.5 0.6 f
2.2
-2.8 f
2.7 1.9 f
2.3 0.6 f
2.9
-0.1 f
2.5 Unit 2 MH#5 Hudson discharge MH-1 0.0 f
2.3 1.7 f
2.3 1.3 f
2.3 1.0 f
2.8
-0.5 k
2.1 1.1 f
2.2 0.7 f
2.2
-3.6
+
4.0 The range of MDCs for the selected radionuclides for the soil sample is 0.05 pC2g lo 0.07 pCi/g and for the water samples is 2.7 p C f i to 4.4 pCi/L.
Soil concenEations. TPUs, and MDCs are in pCi/g.
b
'Zero values arc due to rounding.
'Uncertainties represent the 95% confidence level. based on total propagated uncertainties.
eWatcr concentrations, TPUs, and MDCs are in pCiiL.
TABLE 3 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN ONE SOIL SAMPLE AND 13 WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK a M D C ~
are in parentheses.
bSoil concentrations, TPUs, and MDCs are in pCi/g
'Uncertainties reprcsent the 95% conlidcnce level, based on total propagated uncertainties dWatcr concentrations, TPUs, and MDCs are in pCi/L.
Indian I'rxnt l'm\\-cr Station
TABLE 4 ORISE Sample ID CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Fr-ii" NRC Region I Sample ID I
I 1697W0020 1697W0021 1697W0022 MW-48 2" 52' 9
Ifr 35 (60)
MW-43 2" 28'
-12 k 35 (60)
MW-43 2" 62' 14 2 35 (60) 1697W0017 1
MW-40 4" 200' I 6 t 35' (60) j.9 t 5.8 (9.8) 6.1 k 5.9 (9.8) 1697W0018 I MW-51 4" 200' I -4 f. 35 (60) 3.6 1-5.9 (10.0) 220 t 230 (390) 3.5 f 5.9 (10.0) 230 i: 230 (390) 1697W0019 1
MW-48 1" 37.5' 1 11 k 35 (60) 2.0 t 5.8 (9.8) 8.9 i: 5.9 (9.8) 21.5 f 6.3 (9.8) 1.5 f 5.8 (9.8) 3.6 k 5.9 (10.0) 1,980 t 320 (390)
-0.2 f 5.8 (10.0) 280 f 240 (390)
-1.2 t 5.8 (10.0) 120 k 230 (390) 1.5 t 5.9 (10.0)
-210 f 210 (390) 1697W0023 I
MW-41 1" 63' 1 21 ip 36 (60) 1697W0024 I MW-41 2" 41' I -3 t 35 (60) 1697W0025 1
MW-46 4" 30' I -5 f 35 (60)
"Ihc MDCs for each radionuclide are in parenthcscs.
"1:c-55 analyzed using procedure 121'13, Revision 4.
'Ni-S0/63 analyzed using proccdurc A1'17, Revision 0.
"I 1-3 analyzed using procedurc h1'2, Kcvision 15.
"Uncertaintics rcprcscnt the 95% confidence Icvcl, based on total propagatcd unccrtainties.
Radionuclide Concentrationsa (pCi/L)
Ni-59" Ni-63" H-3d 4.8 t 5.9 (9.8) I 4.2 k 5.9 (10.0) 1 100 i 230 (390)
-0.9 t 5.7 (9.8) I 6.1 t 6.0 (10.0) I 160 t 230 (390) 8.8 k 5.9 (9.8) I 1.7 f 5.9 (10.0) I 90 f 230 (390) 8.1 f 5.9 (9.8) I 1.1 t 5.9 (10.0') I 40 t 220 (390)
T. ~ T 5.9
( 9. 8 T 2. 9 T 5.9 r
440 -&
250 (390) 10.6 f 6.0 (9.8) I 0.4 k 5.8 (10.0) I 490 f 250 (390) 6.0 f 5.9 (9.8) I 3.1
- f. 5.9 (10.0) I 1,510 t 300 (390)
hlay 12, 2006 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION hlr. Jim Kottan US.
Nuclear Rcgulatoq Commission Region I 175 ;Illendale Road King of Prussia, PA 19106
SUBJECT:
I N T E R I M REPORT F O R C O M P L E T E D ANALYSES OF SIX WATER SAMPLES COLLECTED APRIL 7,2006 FROM THE INDIAN P O I N T POWER STATION, BUCHANAN, N E W YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear hlr. Kottan:
'l'hc Oak Ridge Institute for Science and Education (ORISE) recei.iTed six waters samples on April 12, 2006 from the Indian Point Power Station in Buchanan, New York. 'Yhs letter rcport contains data for the analyses that ha7.c been completed to date. The sample identifications and collection data are presented in Table 1, the gamma spectroscopy data are presented in Table 2, the total radiostrontium data are prescnted in Table 3, the hard to detect beta data are prcscrited in Table 4.
The pertinent procedure references are provided in thc specific tables.
OKISE's QC requirements were met for these analyses. The QC files arc a7dable for \\-our review upon request.
more analytical data becomes ar%lablc, additional interim letter reports 1s.111 bc issucd as nceded.
-4 final report will be issued when all requested analyses are completed.
AIy contact information is listed below. You may also contact \\Yade I ~ e y at 865.576.9184
\\\\rith any quesuons or comments.
Sincerely, Dale Condra, Llanager Laboratoq Enclosures C:
T. hlclauglhn, NRC/N;\\ISS/~lTVN 7F27 E Xbelquist, ORISE E. Icnox-Damn, NRC/NLISS/'TT'IW 8_\\23 hI. hldler, NRC Region I Fde 1697 S Kirk, ORISG J. \\T'hite, NRC Region I T'oicc: 865.211.3212 Fax: 865241.3248
&mad: CondraD@orau.gov
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Indian Point I h v c r Station 1697/llata 'l'ablcs/3006-05-1? 1st Intcrim Ilata 'l'ablcs Sct 'I'Kc
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CPl, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID "The rangc of MDCs for the selected radionuclldes is 10 pCi/L to 82 pCi/l..
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero value is due to rounding.
3 i"
d 13 e -
TABLE 3 ORISE Sample ID 1697W0011 1697W0012 1697W0013 1697WOO 14 1697W0015 1697W0016 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES BY LOW BACKGROUND BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide NRC Region I Concentrations, Sample ID TPUs, and MDCS" MW-42 LV41' (2")
175.9
- 6.3b (1.3)
( P C W MW-42LV43'(2I1) 161.6
- 5.8 (1.2)
MW-42 LV45.5' (2")
149.0
- 5.4 (1.2)
MW-42 LV48' (2")
146.7 f 5.3 (1.2)
MW-42 HV51' (2")
184.4 f 6.4 (1.2)
MW-42 78'(1")
0.63
- 0.75 (1.26)
Indian Point Power Station 1697/Data TabIes/200G-05-12 1st Interim Data Tables Set Two
ORISE Sample ID NRC Region I Sample ID 1697W0013 1697W0014 MW-42 LV45.5' (2")
MW-42 LV48' (2")
5,980 f 370 (20) 6,740 f 420 (20) 2,030 k 320 (390) 1,880 k 320 (390)
F n
5 TABLE 4
'j
- 0.
n 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 Radionuclide C mcentrationsa (pCi/L)
Fe-55b Ni-59" Ni-63' H-3d 11 1697W0011 I MW-42 LV41' (2")
5,730 k 350 (20) I 1,860 f 310 (390) 11 1697W0012 I MW-42 LV43' (2")
118 f 37 (57) 1 k 13
- 02) 5.910 f 370 (20) I 2.050 k 320 (390)
~~
-4 k 33 (57)
-9 k 33 (57)
-88 k 10 (22)
-423 k 16 (23) 11 1697W0015 I MW-42 HV51' (2")
Of
-t. 33 (57) -220 -t 10 (20) 5.260 k 320 (20) I 2.160 k 330 (390) 11 1697W0016 I MW-42 78' (1")
-6 k 33 (57) 10.0 k 6.3 (10.3) 18.9 k 6.5 (10.4) I 340 k 240 (390)
"I'hc MDCs for each radionuclidc arc in parentheses.
bFc-55 analyzcd using procedure AP13, Revision 4.
'Ni-59/63 analyzcd using procedure AP17, Revision 0.
dH-3 analyzed using procedure AP2, Revision 15.
eUncertaintics represent the 95% confidcncc lcvcl, bascd on total propagated uncertainties.
fZero value is due to rounding.
L y1 n
RECEf 'br ED OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION REG!ON 1 Distribution approval and concurrence :
Technical Management Team Member Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406 Initials A
53 K
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES OF TEN WATER SAMPLES COLLECTED MARCH 22,2006 TO MARCH 24,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Educadon (ORISE) received ten waters samples on March 31, 2006 from the Indian Point Power Station in Buchanan, New York. This letter report contains data for technetium-99 (Tc-99), alpha spectroscopy, and plutonium-241 (Pu-241). The sample identifications and collection data are presented in Table 1, the Tc-99 data are presented in Table 2, the alpha spectroscopy data are presented in Table 3, and the Pu-241 data are presented in Table 4. The pertinent procedure references are provided in the specific tables.
ORISE's QC requirements were met for these analyses. The QC fdes are avdable for your review upon request. At present, ORISE does not participate in a performance evaluation program that includes plutonium-241, neptunium, and curium isotopes, but the Nuclear Regulatory Commission's Intercomparison Testing Program is being expanded to include these radionuclides.
Ths is the final interim report for this sample set. A final report combining the two interim reports w d be issued by the end of May.
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:ar Enclosure C:
T. McLaugWsn, NRC/NMSS/TWFN 7F27 E. iibelquist, ORISE E. Knox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Region I File 1697 S. IGk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
TABLE 1 ORISE Sample SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCI-IANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1697W0001 1697W0002 1697W0003 1697W0004 Mw-50 42' 3/22/2006 14:30 Mw-50 67' 3/22/2006 1440 Mw-49 25' 3/22/2006 16:50 Mw-49 42' 3/22/2006 1645 1697%0005 1697WOOO6 1697W0007 1697W0008 11 1697W0009 I Mw-3641' I 3/24/2006 I 13:15 Mw-49 65.5' 3/22/2006 16:45 Mw-42 49' 3/23/2006 11:15 Mw-36 26' 3/23/2005 16:00 MW-42 78' 3/24/2006 9:45 11 1697W0010 I
Mw-36 52' I 3/23/2006 I 16:OO Indian Point Power Station projects/l697/Data Tables/2006-05-10 2nd Interim Data Table Set Onc
Indian Point Power Station ORISE Sample ID 1697W0001 TABLE 2 NRC Region I Tc-99 Concentrationsa Sample ID (pCi/L)
MW-50 42'
-3 k 18b (31)
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 1697W0002 1697W0003 1697W0004 1697W0005 1697W0006 1697W0007 1697W0008 MW-50 67'
-6 k 18 (31)
MW-49 25'
-1 k 18 (31)
MW-49 42' 1
k 18 (31)
MW-49 65.5'
-7 k 18 (31)
MW-42 49'
-6 k 18 (31)
MW-42 78'
-14 k 18 (31)
MW-36 26' 6
k 18 (31) 1697W0009 1697W0010 MW-36 41' 9
k 19 (31)
MW-36 52' 14 k 19 (31) projccts/l697/Data Tablcs/2006-05-10 2nd Interim Data 'rablc Sct One
- j. e:
9 n a 8
- g.
c?
P VI TABLE 3 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
Ij 5'
n V a B '=
4 c\\
L2 3
E 0
Q --.
P
+I z --.
e 0 r -
TAB= 3 (Continued)
ORISE Sample NRC Region I Radionuclide Concentrationsa @Ci/L)
ID Sample ID Pu-238 Pu-239/240 U-234 U-238 1697W0001 MW-50 42' 0.51 k 0.46 (0.72) 0.03 f 0.15 (0.33) 0.80 k 0.34 (0.30) 0.65 f 0.35 (0.41) 1697W0002 MW-50 67' 0.08 f 0.24 (0.47) 1697W0003 MW-49 25' 0.65 If: 0.48 (0.72) 0.14 k 0.31 (0.56) 1.03 f 0.41 (0.39) 0.57 f 0.35 (0.46) 1697W0004 MW-49 42' 0.40 k 0.41 (0.65) 0.03 L 0.11 (0.25) 2.18 rt 0.54 (0.23) 0.83 f 0.32 (0.09) 1697W0005 MW-49 65.5' 0.20 f 0.18 (0.12) 1.58 f 0.55 (0.44) 0.94 k 0.41 (0.30) 1697W0006 MW-42 49' 0.20 f 0.40 (0.71) 0.16 k 0.30 (0.54) 1.31 k 0.61 (0.76) 1.03 f 0.48 (0.53) 1697w0007 MW-42 78' 0.33 k 0.45 (0.76) 0.08 f 0.26 (0.51) 1.89 k 0.58 (0.45) 1.38 f 0.48 (0.35) 1697W0008 MW-36 26' 0.37 f 0.44 (0.72) 0.29 f 0.22 (0.12) 0.76 f 0.38 (0.40) 0.47 f 0.28 (0.28) 1697W0009 MW-36 41' 0.11 f 0.43 (0.79) 0.17 f 0.32 (0.56) 1697W0010 MW-36 52' 0.15 If: 0.42 (0.76) 0.08 f 0.19 (0.37) 1.66 f 0.59 (0.66) 0.86 f 0.37 (0.32)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK
TABLE 4 ORISE Sample ID CONCENTRATIONS OF PLUTONIUM-241 (Pu-241)
IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Pu-241 Concentrationsa Sample ID
@Ci/L)
I
_ _ _ _ _ ~
~
11 1697W0001 I MW-5042' I
6 k 77b (131) 1697W0003 MW-49 25'
-42 k 74 (129) 1697W0004 MW-49 42' 8
k 79 (135) 11 1697W0002 I MW-5067' I
39 k 78 (132) 1697W0006 1697W0007 1697W0008
~~
MW-42 49' 15 k
78 (134)
MW-42 78' 8
k 84 (143)
MW-36 26'
-12 k 80 (138) 11 1697W0005 I Mw-49 65.5' I -18 k 83 (142) 1697W0009 1697W0010 MW-36 41'
-29 k
78 (135)
MW-36 52' 0'
k 79 (136)
Indian Point Power Station projects/l697/Data Tables/2006-05-10 2nd Interim Data Table Set One
May 2,2006 Distribution approval and concurrence :
Quality Manager Technical Management Team Member OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Initials WCA & 3'5K Q7-P Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406
SUBJECT:
INTERIM REPORT FOR COMPLETED ANALYSES OF TEN WATER SAMPLES COLLECTED MARCH 22,2006 TO MARCH 24,2006 FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received ten waters samples on March 31, 2006 from the Indian Point Power Station in Buchanan, New York. This letter report contains data for the analyses that have been completed to date. The sample identifications and collection data are presented in Table 1, the gamma spectroscopy data are presented in Table 2, the total radiostrontium data are presented in Table 3, the hard to detect beta emitter (iron-55, nickel-59/63, and tritium) data are presented in Table 4. The pertinent procedure references are provided in the specific tables.
ORISE's QC requirements were met for these analyses. The QC files are available for your review upon request.
As more analytical data becomes avdable, additional interim letter reports wd be issued as needed. A final report will be issued when all requested analyses are completed.
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:WI:ar Enclosures C:
T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 M. M e r, NRC Regon I File 1697 S. IGk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondraD@orau.gov
ORISE Sample ID TABLE 1 NRC Region I Collection Collection Sample ID Date Time SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1697WOOO 1 1697W0002 1697W0003 1697W0004 I
I I
li MW-50 42' 3/22/2006 14:30 MW-50 67' 3/22/2006 14:40 MW-49 25' 3/22/2006 16:50 MW-49 42' 3/22/2006 16:45
~
1697W0005 1697 WOO06 1697W0007 1697W0008 1697W0009 MW-49 65.5' 3/22/2006 16:45 MW-42 49' 3/23/2006 11:15 MW-42 78' 3/24/2006 9:45 MW-36 26' 3/23/2006 16:00 MW-36 41' 3/24/2006 13:15 11 1697W0010 I MW-3652' I 3/23/2006 I 16:OO 11 Indian Point Power Station projects/l697/Data Tables/2006-05-2 1st Interim Data Table
TABLE 2
?
U.
3 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE Sample ID
'The range of MDCs for the selected radionuclides is 2.8 pCi/mL to 5.4 pCilmL kncertainties represent the 95% confidence level, based on total propagated uncertainties.
6;' e
TABLE 3 ORISE NRC Region I Sample ID Sample ID 1697W0001 MW-50 42' 1697W0002 MW-50 67' 1697W0003 MW-49 25' 1697W0004 MW-49 42' 1697W0005 MW-49 65.5' Radionuclide Concentrations, TPUs, and MDCsa (pCi/L) 24.5 f
1.8b (1 -2) 30.6 1.7 (0.8) 16.7 1.3 (0.9) 22.5 f
1.4 (0.8) 21.5 1.5 (0.8)
~
(0.8) 1697W0006 MW-42 49' 60.5 f
2.7 1697W0007 MW-42 78' 0.37 f
0.45 (0.75) 1697W0008 MW-36 26' 1.69 f
0.60 (0.86) 1697W0009 MW-36 41' 4.04 f
0.79 (0.96) 1697W0010 MW-36 52' 5.71 f
0.78 (0.80) i a M D C ~
are in parentheses.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Po\\vcr Station projects/l697/Data Tablcs/2006-05-2 1st Intcrim Data Table
TABLE 4 ORISE Sample ID 1697W0001 1697W0002 1697W0003 CONCENTRATIONS OF HARD TO DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa (pCi/L)
NRC Region I Sample ID Fe-55b Ni-59' Ni-G3c H-3d MW-50 42'
-14 f 72" (120) 4.2 f 5.2 (8.8) 5.4 k 5.4 (9.0) 8,190 k 550 (400)
MW-50 67'
-10 f 72 (120)
-2.4 k 5.0 (8.8) 9.9 k 5.5 (9.0) 9,490 f 590 (400)
MW-49 25'
-48 k 72 (120) 3.4
? 5.2 (8.8) 6.3 k 5.4 (9.0) 14,240 t 740 (400) x E.
tl 1697W0004 1697W0005 1697W0006 MW-49 42'
-30 k 72 (120) 7.3 k 5.3 (8.8) 5.6 f 5.4 (9.0) 9,130 f 580 (400)
Mw-49 65.5'
-33 k 72 (120) 2.0 f 5.2 (8.8) 7.9
& 5.5 (9.0) 6,290 f 490 (400)
Mw-42 49'
-19 f 72 (120) 71.9 f 7.8 (8.8) 1392 & 86 (9) 2,290 k 340 (400) 1697W0007 1697W0008 1697W0009 1697W0010 Mw-42 78'
-36 f 72 (120) 2.8 f 5.2 (8.8) 53.4 t 7.3 (9.0) 510 k 250 (400)
MW-36 26'
-39 f 72 (120)
-3.9 f 5.0 (8.8) 67.3 f 8.0 (9.0) 35,100
+_ 1,300 (400)
MW-36 41' 24 f 73 (120) 0.1 f 5.1 (8.8) 47.4 f 7.0 (9.0) 56,200 f: 1,800 (400)
MW-36 52'
-44 & 72 (120)
-0.3 f 5.1 (8.8) 10.3 f 5.5 (9.0) 26,900 f 1,100 (400)
T h e MDCs for each radionuclide are in parentheses.
b17e-55 analyzed using proccdurc AP13, Revision 4.
'Ni-59/63 analyzed using procedure AP12, Revision 5.
dH-3 analyzed using procedure A1'2, Revision 15.
'Uncertainties represent thc 95% confidence level, based on total propagated uncertainties.
O R P S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION April 27,2006 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road IQng of Prussia, PA 19406
SUBJECT:
INTERIM REPORT FOR ADDITIONAL ANALYSES O N SELECTED WATER SAMPLES FROM THE INDIAN POINT POWER STATION, B U C W A N, NEW YORK
[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. O6-001]
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received a request from you on March 23, 2006 to analyze four of the oripal seven water samples received on October 28, 2005 from the Indian Point Power Station in Buchanan, New York. The analytical request also included eight water samples collected from monitoring well 0 37 on February 28, 2006 and March 10,2006.
The previous practice at ORISE was to wait until all analytical requests and the associated Quality Controls (QC) for a sample set were completed before submitting the required letter report. Due to the priority of the present project, ORISE will submit interim letter reports as each analytical request is completed and submit a final report after all work for a sample set has been completed.
Four of the oripal seven water samples and four of the eight samples from hlw 37 were analyzed for Ni-63 by liquid scintillation analysis (Procedures AP12, Revision 4 and CP4, Revision 3). In adhtion, americium-241, curium-242, curium-243/244, plutonium-238, and plutonium-239/240 were analyzed by alpha spectroscopy (AS) (Procedures APll, Revision 3 and CP2, Revision 12). The sample identifications and collection data are presented in Table 1, the Ni-63 data are presented in Table 2, and the AS data are presented in Table 3.
ORISEs QC requirements were met for these analyses. The QC files are available for your review upon request.
As more analytical data becomes available, additional letter reports wLu be issued as needed.
Mr. Jim Kottan Distribution approval and concurrence :
Quality Manager Technical Management Team Member Initials q7E-K u
April 27,2006 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: WI:ar Enclosures c:
T. McLaughlin, NRC/NMSS/TWFN 7F27 E. IOlox-Davin, NRC/NMSS/TWFN 8A23 M. M e r, NRC Region I File 1677 E. Abelquist, ORISE S. IQrk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail: CondmD@orau.gov
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time
'No collection time provided.
Indian Point Power Station project 1677/Data Tables/2006-0425 Ni-63 Alpha Spec Interim Data Table 1677
ORISE Sample ID 1677W0001 TABLE 2 NRC Region I Radionuclide Concentrations, Sample ID Unit 2 SFP 2.820.000 f 160.000 (67)
TPUs, and MDCs" (pCi/L)
CONCENTRATIONS OF Ni-63 IN SELECTED WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP12, REVISION 4; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 11 1677W0002 I Unit 1 West SFP I 333,000 L-19,000 (23) 1677 WOO03 Unit 1 SFDS 11 f
11 (19) 1677W0006 NCD Composite 86 2
13 (36) 1677W0039 Mw-37 40'
-1 L-11 (19) 1677W0040 Mw-37 22' 5
f 11 (19) 1677W0041 Mw-37 57' 5
f 11 (19) 11 (19)
"MDCs are in parenthesis.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station project 1677/Data Tables/2006-04-25 Ni-63 Alpha Spec Interim Data Table 1677
I ORISE Sample ID TABLE 3 NRC Region I Sample ID z
b L.,
9.30 f l.lb 3.40 f 0.65 CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN WATER SAMPLES BY ALPHA SPECTROSCOPY AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 50.0 f 4.6 59.2 f 4.8 24.0 f 2.2 4.26 k 0.63 0.55 k 0.39 0.39 f 0.23 0.63 k 0.31 0.55 k 0.24
-~
~
1677W0003 Unit 1 SFDS 1677W0006 NCD Composite 11 1677W0001 I Unit2SFP 0.28 f 0.30 0.07 f 0.20 0.00 k 0.28 11 1677W0002 I Unit 1 West SFP
~
-0.19 f 0.34 -0.05 k 0.24 0.02 2 0.17 0.00' -t 0.13 0.04 f 0.20 -0.09 f 0.14 0.05 f 0.19 -0.05
_+ 0.08 0.13 k 0.13 -0.06 & 0.17 -0.11 f 0.22 0.16 f 0.11 I
11 1677W0035 I Mw-37 22' Mw-37 32' 1677w0036 1677W0037 Mw-37 40' 0.11 f 0.24 0.30 f 0.31
-0.20 k 0.21 11 1677W0038 I Mw-3757' 0.00 f 0.10 0.11 2 0.23 0.09 f 0.20 0.04 k 0.10 0.12 f 0.21 0.13 f 0.24 -0.02 f 0.22 0.05 f 0.07 0.30 f 0.20 -0.04
_+ 0.15 -0.12 _+ 0.18 0.04 f 0.11 Radionuclide Concentrations* (pCi/L)
II Am-241 1
Cm-242 I Cm-243/244 I Pu-238 1 Pu-239/240 11
%e average MDCs for these radionuclides range from 0.05 pCi/L to 0.52 pCi/L.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero value is due to rounding.
+
CA 4
4
RECEIVED REGION 1 Distribution approval and concurrence :
Technical Management Team Member Quality Manager O R I S E Initials OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF FIFTH SET OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION NO. 050-247/2005-0111 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received four water samples on March 6, 2006 from the Indian Point Power Station in Buchanan, New York. The sample identifications and collection data are presented in Table 1. The samples were analyzed by g a m a spectroscopy (GS)
(Procedure CP1, Revision 15), for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15; Procedure CP4, Revision 3), and for total radiostrontium (Sr) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS, H-3, and Sr results are presented in Tables 2 through 4, respectively.
After discussing the preliminary results of the Sr analysis with you on March 20,2006, you requested that the samples be reanalyzed to confirm the Sr data. The reanalysis began on March 21,2006 and finished on March 29,2006. The Sr reanalysis data are reported in Table 4. The uncertainties and minimum detectable concentrations are higher due to the sample volumes available for the reanalysis.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are avadable for your review upon request.
My contact information is listed below. You may also contact Wade hey at 865.576.9184 with any questions or comments.
Sincerelv.
Dale Condra, Manager Laboratory RDC:WI:ar Enclosures C:
T. McLaughlm, NRC/NMSS/TWFN 7F27 E. AbeIquist, ORISE E. Ihox-Davin, NRC/NMSS/TWFN 8A23 M. M e r, NRC Region I File 1677 S. Kirk, ORISE J. White, NRC Region I Voice: 86 5.241.3242 Fax: 865.241.3248 E-ma& CondraD@orau.gov
TABLE 1 ORISE Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Collection Sample ID Date Time 1677W0035 Mw-37 22' 2/28/2006 10:20 1
11 1677W0038 I
Mw-37 57' I 2/28/2006 I 13:35 1677W0036 Mw-37 32' 2/28/2006 12:oo 1677W0037 Mw-37 40' 2/28/2006 11:40 Indian Point Power Station projects/l677/Data Tables/2006-04-04 Data Tables
TABLE 2 I ORISE Sample ID CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK co-58 CO-GO cs-134 6.1 f 5.3b 5.4 t-5.6 3.3 k 5.5 cs-137
-0.4 k 4.8 1677W0035
~~
-1.4 k 4.5
-2.8 & 5.9 1677W0036
~
1.2 rt 4.8 1.7 & 5.2 1.1 k 4.2
-4.3 k 6.3 5.9 k 6.8 3.8 k 6.0 1677WOO37 1677W0038 NRC Region I Sample ID Mw-37 22' Mw-37 32' Mw-37 40' Mw-37 57'
-2.0 k 4.9 I 7.2 t-5.3 I 4.7 rt 5.7 I 0.4 t-4.811 "The rangc of MDCs for the selected radionuclides is 7.2 pCi/L to 11 pCi/L.
'Uncertainties represent thc 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data TabIes/2006-04-04 Data Tables
NRC Region I ORISE Sample ID Sample ID TABLE 3 Radionuclide Concentiations, TPU~,
and MDCS" @Ci/L)
CONCENTRATIONS OF TRITIUM I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK 1677W0035 m - 3 7 22' 14,470 +.
360b 1677W0036 MW-37 32' 1677W0037 MW-37 40' 1677W0038 MW-37 57' 15,850
- 380 (200)
'MDCs are in parenthesis.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data Tables/2006-04-04 Data Tables
TABLE 4 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK BY GAS-FLOW PROPORTIONAL COUNTING 1677W0036 1677W0037 1677W0038 1677W0035R' Sample ID 1677W0035 m - 3 7 22' W - 3 7 32' Mw-37 40' Mw-37 57' Mw-37 22' Radionuclide Concentrations, TPUs, and MDCS" (pCi/L) 2.3 f 1.2b (2.0) 26.4 f 2.1 (2.0) 21.8 k 1.8 (1.9) 25.5 k 2.1 (2.2) 3.7 k 1.9 (3.1) 11 1677W0036R I Mw-37 32' I 24.2 k 2.8 (3.2) 11 1677W0037R I Mw-37 40' I 21.8 f 4.0 (5.4)
~~~
11 1677W0038R I m - 3 7 57' I 28.5 k 2.9 1'3.2)
'MDCs are in parenthesis buncertainties represent the 95% confidence level, based on total propagated uncertainties.
%e samples with thc R cstension were reanalyzed at the inspector's request.
Indian Point Powcr Station projects/l677/Data Tables/2006-04-04 Data Tables
Distribution approval and concurrence :
Technical Management Team Member Quality Manager O R I S E Initials,
Mr. Jim Kottan U.S. Nuclear Regulatory Commission Regon I 475 Allendale Road IGng of Prussia, PA 19406 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION
SUBJECT:
REPORT FOR ANALYSIS OF SIXTH SET OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION REPORT NO. 050-247/2005-0111 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received four water samples on March 15,2006 from the Indian Point Power Station in Buchanan, New York. The sample identifications and collection data are presented in Table 1. The samples were analyzed by gamma spectroscopy (GS) (Procedure CP1, Revision 15), for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15; Procedure CP4, Revision 3), and for total radiostrontium (Sr) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS, H-3, and Sr results are presented in Tables 2 through 4, respectively.
ORISE's Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:wPI:ar Enclosures C:
T. McLaughlin, NRC/NMSS/TYVFN F27 E. iibelquist, ORISE E. Ibox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Regon I File 1677 S. IGk, ORISE J. White, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E - m d CondraD@orau.gov
TABLE 1 ORISE Sample ID 1677W0039 1677W0040 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Collection Sample ID Date MW-37 40' 3/10/2006 m - 3 7 22' 3/10/2006 1677W0041 I MW-3757' I
3/10/2006
~~
~~
1677W0042 I
MW-37 32' I 3/10/2006 Collection Time 10:25 10:35 11:45 1250 Indian Point Power Station projects/l677/Data Tables/2003-04-04 Data Tables
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 Radionuclide Concentrationsa (pCi/L)
Sample ID CO-58 CO-60 CS-134 I cs-i37 1677W0039 1677W0040 1677W0041 b
MW-3740' 1.3 k 3.7 2.2 3.2 -3.9 k 5.5 2.7 2 3.1 MW-37 22' 0.6 k 3.5 -1.7 2 3.1 0.1 k 3.3 2.3 -I-2.9 MW-37 57' 0.8 k 3.8 -1.1 +: 3.9 -1.1 k 4.1 2.5 -I-3.6 1677W0042 I MW-3732' 1-1.9 k 2.41-1.7 k 2.610.1 k 2.81-1.1 t-2.4 "rhe range of MDCs for the selected radionuclides is 3.9 pCi& to 6. I pCi/L.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data Tables/2006-04-04 Data Tables
TABLE 3 ORISE Sample ID 1677W0039 1677 WOO40 1677W0041 1677W0042 CONCENTRATIONS OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide and MDCsa (pCi/L)
NRc Region I Concentrations, TPU~,
Sample ID MW-3740' 16,140
- 400b (200)
MW-37 22' 22,950 +-
490 (200)
MW-37 57' 15,940 f 390 (200)
MW-37 32' 28,840
- 570 (200)
Indian Point Power Station projects/l677/Data Tables/2006-04-04 Data Tables
TABLE 4 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM IN WATER SAMPLES AP4, REVISION 13; CP3, REVISION 2 1M)IAN POINT POWER STATION BUCHANAN, NEW YORK BY GAS-FLOW PROPORTIONAL COUNTING ORISE Sample ID Radionuclide and MDCsa M X L )
mc Region I Concentrations, TPU~,
Sample ID
.I 11 1677W0039 i m - 3 7 4 0 ' i 17.6 1.9b (1.6) 11 1677W0040 I MW-3722' I 4.9 f 1.3 (1.6) 11 1677W0041 I MW-37 57' I 26.6 f 2.2 (1.5) 11 1677W0042 I MW-3732' I 21.6 2.0 (1.6)
"MDCs are in parenthesis.
buncertainties represent the 95% confidence level, based on total propagated uncertainties.
Indian Point Power Station projects/l677/Data Tables/2004-04-04 Data Tables
O R I S E Distribution approval and concurrence :
Techcal Management Team Member Quality Manager OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Initial?
Y 2M MAR 20 RI I: 47 March 14,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission Region I 475 Allendale Road ISing of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF FOURTH SET OF WATER SAMPLES FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK
[INSPECTION NO. 050-247/2005-0111 [RFTA NO. 06-0011
Dear Mr. Kottan:
The Oak Ridge Institute for Science and Education (ORISE) received 17 water samples on February 13, 2006 from the Indian Point Power Station in Buchanan, New York. The sample identifications and collection data are presented in Table 1. The samples were analyzed by gamma spectroscopy (GS)
(Procedure CP1, Revision 15), for tritium (H-3) by liquid scintillation analysis (Procedure AP2, Revision 15; Procedure 0 4, Revision 3), and for total radiostrontium (Sr) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS, H-3, and Sr results are presented in Tables 2-4, respectively.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are avadable for your review upon request.
My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:WI:ar Enclosures C:
T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISE E. Knox-Davin, NRC/NMSS/TWFN 8A23 M. Miller, NRC Region I J. Noggle, NRC Region I S. IGrk, ORISE J. Cy/?llte, NRC Region I File 1677 Voice: 865.241.3242 Fax: 865.241.3248 E-ma& CondraD@orau.gov
TABLE 1 Collection Date SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Collection Time ORISE Sample ID 1677W0018 1677W0019 NRC Region 1 Sample ID MW-48 02/08/2006 1010 Mw-38 02/08/2006 1115 1677W0021 1677W0022 1677W0023 Gypsum Plant Stream 02/08/2006 1240 Algonquin Outfall 02/08/2006 1240 MW-31 02/07/2006 0940 11 1677W0020 I TrapRockQuarry 1 02/08/2006 1 1200 1677w0024 1677W0025 1677W0026 Mw-30 02/07/2006 1140 Mw-32 02/07/2006 1345 m - 3 5 02/07/2006 1440 1677W0027 1677W0028 1677W0029 1677W0030 1677W0031 Mw-34 02/07/2006 1515 Mw-33 02/07/2006 1600 Mw-111 02/07/2006 1610 Mw-36 02/07/2006 1700 MH-1 Storm Drain Area 02/08/2006 1250 11 1677W0032 I Middleofsite I 02/08/2006 I 1300 1677W0033 1677W0034 Off of Unit 2 02/08/2006 1300 N. Property Boundary 02/08/2006 1300 Indian Point Power Station projects/l677/Data Tables/2006-03-14 Data Tables
TABLE 2 NRC Region I I
Sample ID 11 O R I S ~ ~ a m p l e CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Conc Co-58 I
CO-60 1677W0018 1677W0019 Mw-48
-4.0 k 7.2b 4.3 k 6.2 Mw-38
-2.0 & 5.8 0.6 k 5.4 1677W0020 1677W0021 Trap Rock Quarry 2.2 k 4.4 0.2 k 4.7 GvpsumPlant Stream 4.7 k 6.3 1.8 5.7 1677W0022 1677W0023 Algonquin Outfall 1.7 k 7.6 5.2 k 5.6 Mw-3 1
-1.2 k 5.8
-4.4 2 6.4 1677W0024 1677W0025 Mw-30
-4.9 & 4.7 1.0 rt 5.9 Mw-32
-1.0 k 5.9
-1.6 k 5.8
- ntrationsa (F cs-134 1677WOO26 1677W0027 3.0 k 5.7 Mw-35
-7.5 _+ 7.4 5.9 f 5.9 Mw-34
-1.1 k 5.3 1.3 k 5.4 1.8 k 6.0 2.7 k 6.2 3.2 k 8.0 1677W0028 1677W0029 1677W0030 1677W0031 1677WOO32
-0.5 k 6.2 0.4 k 6.4 Mw-33
-2.3 k 4.6 1.8 k 4.8 Mw-111
-2.0 k 5.7 3.0 k 5.7 Mw-36
-1.5 k 7.4 4.2 rt 6.6 MH-1 StormDrain Area
-0.4 L 5.0 4.0 k 6.5 Middle of Site
-2.2 k 4.5 2.0 k 4.7
-1.0 k 4.9
-4.1 If: 6.6 1677W0033 1677W0034 0.3
_+ 5.8
-2.8 k 5.5 Off of unit 2
-0.9 k 5.8 1.1 k 5.6 N. Property Boundary
-1.4 ? 4.6
-1.6 k 4.7
-1.6 k 4.9 3.5 k 6.6 1.9 & 5.5
-1.8
_+ 5.4
-3.0 k 4.8
-2.6 k 6.3 0.3 k 4.8 3/L) cs-137
-2 k 10
-0.1 & 4.9 1.2 5 4.4 8.1 5 5.3 13.9 k 7.2 1.2 k 5.2
-0.5 rt 5.2
-1.3 If: 5.2
-4
_+
11
-1.7 5 5.3
-0.1 k 4.5 3.7 rt 5.3
-6 k 10
-0.7 & 4.9
-2.0 5 4.4 2.3 5 5.1 1.6 2 4.3 Indian Point Power Station projects/t677/Data Tables/2006 14 Data Tablcs
TABLE 3 ORISE Sample ID CONCENTRATIONS OF TRITIUM IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 15; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Tritium Concentrations, TPUs, and MDCS" (pCi/L)
NRC Region I Sample ID 1677WOO 18 1677WOO 19 1677W0020 1677W002 1
\\*
Mw-48 70 f 120b (200)
Mw-38 310 f 130 (200)
Trap Rock Quarry
-140 k
110 (200)
Gvpsum Plant Stream
-210 f 110 (200) 1677W0022 1677W0023 1677W0024 1677W0025 Algonquin Outfall
-110 f 120 (200)
Mw-31 32,910 f 470 (200)
Mw-30 491,400 f 5,100 (200)
Mw-32 17,900
?I 310 (200) 1677W0026 1677W0027 1677W0028 1677W0029 Indian Point Power Station Mw-35 84,530 f 990 (200)
Mw-34 174,700 k 1,900 (200)
Mw-33 222,700 ~t: 2,400 (200)
Mw-111 242,400 2,600 (200) projects/l677/Data Tables/2006-03-14 Data Tables 1677W0030 1677W003 1 1677W0032 1677W0033 1677W0034 Mw-36 21,710 f 350 (200)
MH-1 Storm Drain Area
-80 f 120 (200)
Middle of Site
-170 k
110 (200) o f f of unit 2
-60 120 (200)
N. Property Boundary
-100 f 120 (200)
TABLE 4 1677W0018 1677W0019 1677W0020 CONCENTRATIONS OF TOTAL RADIOSTRONTIUM I N WATER SAMPLES AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK BY GAS-FLOW PROPORTIONAL COUNTING Mw-48 0.6 f i. i b (1.9) 0.4 f 1.0 (1.7)
Trap Rock Quarry 0.4 f 1.1 (1.8)
Mw-38 ORISE Sample ID 1677W0021 1677W0022 1677W0023 Total Radiostrontium Concentrations, TPUs, and MDCS" (pCi/L)
NRC Region I Sample ID Gypsum Plant Stream 1.1 f 1.1 (1.8)
MW-31 0.2 f 1.1 (2.0)
Algonquin Outfall 0.8 f 1.1 (1.9) 1677W0025 1677W0026 1677W0027 MW-32 0.2 f 1.1 (1.9)
Mw-35
-0.1 f 1.1 (1.8)
MW-34 0.3 f 1.0 (1.7) 1677W0029 1677W0030
~
~~
11 1677W0028 I Mw-33 7
1.0 f 1.2 (2.0)
Mw-111 1.9 f 1.2 (1.9)
Mw-36 2.4 f 1.2 (1.9) 1677W0032 1677W0033 1677W0034 Middle of Site 0.7 f 1.1 (1.8)
Off of unit 2 0.2 f 1.3 (2.3)
N. Property Boundary 0.9 k 1.0 (1.7)
Indian Point Power Station projects/l677/Data Tables/2006-03-14 Data Tablcs