ML070940534

From kanterella
Jump to navigation Jump to search
Ltr from Orise Dtd 03/15/2006, Interim Report for Completed Analyses for Samples from Set Sixteen, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No.06-001)
ML070940534
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/15/2006
From: Condra D
Oak Ridge Institute for Science & Education
To: Kottan J
Decommissioning Branch I
References
IR-06-007, RFTA 06-001
Download: ML070940534 (9)
v • d • e


Text

IB EECEIVED S 07?!fJY

_ - \-.

1 OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road IGng of Prussia, PA 19406

SUBJECT:

INTERIM REPORT FOR COMPLETED ANALYSES FOR SAMPLES FROM SET SIXTEEN, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW YORK

[INSPECTION REPORT NO. 050-247/2006-0071 [RFTA NO. 06-0011

Dear Mr. Kottan:

The Oak Ridge Institute for Science and Education (ORISE) received set 16, consisting of 10 water samples, associated with the Indian Point Power Station on November 27,2006. Sample analysis was initiated based on your previous direction for handling samples from t h s licensee. Sample identification and collection data for the samples addressed in this report are presented in Table 1. Gamma spectroscopy, the hard-to-detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 8, respectively. The pertinent procedure references are provided in each specific table.

ORISEs Quality Control (QC) requirements were met for these analyses. The QC fdes are available for your review upon request. Additional reports wdl follow after the completion of the requested analyses.

ORISE has removed the Ni-59 data due to problems with the calculation associated with the concentration of t h s radionuclide. ORISE is discontinuing the reporting of Ni-59 data untd t h s problem can be resolved.

My contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:wPI:km Enclosures C: T. Carter, FSME/DWMEP 7J18 E. Abelquist, ORISE E. Ihox-Davin, NRC/FSME/TWFN SA23 S. I b k , ORISE M. Roberts, NRC Regon I J. White, NRC Regon I File 1697 Distribution approval and concurrence : Initials , -

Technical Management T e a m Member I-Quality Manager Voice: 865.241.3242 Fax: 865.241.3248 E - m d Dale.Condi-a@orau.org

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK II I I I ORISE NRC Region I Collection Collection Sample ID Sample ID Date Time 11 1697W0093" I MW-42-48' I 11/16/2006 I 10:52 1697M0056b 1697W0093 filter 11/16/2006 10:52 1697W0094 MW-42-43' 11/16/2006 14:24 1697M0057 1697W0094 frlter 11/16/2006 14:24 1697W0095 MW-42-45.5' 11/16/2006 13:02 11 1697M0058 I 1697W0095 filter I 11/16/2006 I 13:02 1697W0096 MW-42-41' 11/ 17/2006 8:44 1697M0059 1697W0096 filter 11/17/2006 844 1697w0097 MW-59-31-(001) 11/16/2006 11:05 1697M0060 1 6 9 7 ~ 0 0 9 7filter 11/16/2006 11:05 1697W0098 Mw-59-45-(001) 11/16/2006 11:18 1 1697M0061 1697W0098 filter 11/16/2006 11:18 1697W0099 MW-59-68-(001) 11/16/2006 11:30 1697M0062 1697W0099 filter 11/16/2006 11:30 1 169773330100 MW-58-26-(001) 11/16/2006 13:25 11 1697M0063 I 1697W0100filter I 11/16/2006 I 13:25 1697W0101 MW-58-65-(001) 11/16/2006 13:18 1697M0064 1697W0101 filter 11/16/2006 13:18 1697W0102 MW-39-200-(005) 11/17/2006 13:49 1697M0065 1697W0102 filter 11/17/2006 13:47 T h e W i n the ORISE samplc identification represents a water matrix bThe M in the ORISE sample identification represents the filtered fraction of the preceding water sample.

Indian Point Power Station projects/l697/Tables/2007-02-16Data Tables Set 15

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'b@Ci/L)

Sample ID Sample ID CO-58 CO-60 cs-134 cs-137 1697W0093 MW-42-48' -1.5 f 3.2" 3.8 k 3.1 3.9 f 2.9 7730 f 250 d

1697~0094 MW-42-43' -0.1 +_ 3.2 2.3 f 3.5 0.0 f 3.2 8380 k 270 1697W0095 MW-42-45. 5' 0.9 k 2.3 2.7 f 2.4 1.3 f 2.3 8270 It 260 1697W0096

~~~~

MW-42-41' I -2.8 f 3.9 1.9 k 3.4 I 2.0 k 3.8 I 8270 f 280 1697W0097 MW-59-31-(001) -0.2 k 2.0 1.8 It 2.1 3.3 k 2.2 1.9 f 4.8 1697W0098 MW-59-45-(001) -1.1 k 1.7 0.3 It 1.7 1.6 & 1.7 1.6 k 2.0 1697W0099 MW-59-68-(001) 1.3 f 2.4 0.2 k 2.3 3.3 k 2.6 0.3 k 2.3 1697W0100 MW-58-26-(001) 1.3 f 2.4 1.5 k 2.5 2.4 k 2.5 -0.7 f 2.2 1697W0101 MW-58-65-(001) 2.0 f 2.3 1.0 Ifr 2.3 -1.2 k 2.3 1.6 f 3.7 1697W0102 MW-39-200-(005) 0.2 k 2.3 -1.0 k 2.8 0.7 f 2.6 -1.2 k 2.6 T h e range of MDCs for the selected radionuclide samples WOO93 through WOO96 is 3.9 pCi/L to 10 pCi/L.

bThe range of MDCs for the selected radionuclide samples WOO97 through W0102 is 2.7 pCi/L to 4.5 pCi/I,.

'Uncertainties represent the 95% confidence level, based on total propagated uncertainties dZcro value is due to rounding.

Indian oint Power Station projects/1697/Tables/2006-03-15Data Tables Set 16

TABLE 3 CONCENTRATIONS OF HARD T O DETECT BETA EMITTING RADIONUCLIDES I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Sample ID Sample I D Fe-55b Ni-63" H-3d 1697W0093 MW-42-48' 5 k 40" , 68 249 k 23 , 24 2,200 k 350 , 420

. 681 295 k 25 . 24 12.100 k 340 . 4201) 111 1697w0094 1697W0095 1697W0096 I MW-42-43' MW-42-45.5' MW-42-41' Of k 40 19 f. 40

-3 k 40

~~

, 68 290 f. 25 , 24 2,590 k 370 , 420

, 68 201 k 21 , 24 2,060 340 , 420 11 1697W0097 I MW-59-31-(001) 4 k 20 ~~

. 34 1.4 k 5.6 . 9.5 70 k 240 , 420 11 1697W0098 I MW-59-45-[001) -10 f. 20 , 34 4.8 k 5.7 , 9.5 130 & 250 ,

11 1697W0099 I MW-59-68-(001) 8 f. 20 , 34 1.2 k 5.6 , 9.5 90 k 240 , 420 11 1697W0100 I MW-58-26-(001) 3 k 20 . 341 0.1 f. 5.6 . 9.5 I 10 k 240 . 420

~~~~ ~

11 1697W0101 I MW-58-65-[001) 8 f. 20 , 34 0.5 & 5.6 , 9.5 120 k 250 , 420 I 1697W0102 I MW-39-200-(005) -5 k 20 , 34 -3.0 f. 5.5 , 9.5 10 k 240 , 420 "The MDCs for each radionuclide are after the comma.

bFe-55 analyzed using procedure AP13, Revision 4.

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

dH-3analyzed using procedure AP2, Revision 15.

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

'Zero value is due to rounding.

Indian oint Power Station projects/l697/Tables/2006-03-15Data Tables Set 16

TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 (Tc-99)

I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Tc-99 Concentrationsa Sample ID (PCi/ L)

I 1697W0093 1697W0094 MW-42-48' MW-42-43' 8

5 k 15b ,

k 15 . 26 I I11 1697W0096 1697W0097 1697W0098 I MW-42-4 1' MW-59-31-(001)

MW-59-45-(001) I 17 9.2 2.3 k

k k

16 7.8 7.6 26 13.0 13.0 11 I 1697W0099 1697W0100 1697W0101 MW-59-68-(001)

MW-58-26-(001)

MW-58-65-(001) 2.8 9.8 6.6 k

k k

7.6 7.8 7.7

, 13.0

. 13.0

, 13.0 1697W0102 MW-39-200-(005) 9.2 k 7.8 , 13.0

~__________

"The MDCs are after the comma.

bUncertatntles represent the 95% confidence level, based on total propagated uncertatnnes Indian oint Power Station projects/l697/Tables/2006-03-15Data Tables Set 16

TABLE G J

?i CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES

-11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionu :fide Concentrationsa (pCi/g of sediment in 100 mL or pCi/L for water)

Sample ID Sample ID Am-241 Cm-242 I Cm-243 /244 I ND-W7 1697W0093 I MW-42-48' I 0.02 f: 0.14b . 0.28 0.25 k 0.16 . 0.16 I 0.00' k 0.10 0.23 I 0.02 f. 0.14 . 0.28 1697M0056 1697W0093 filter 0.00 f: 0.02 , 0.03 0.00 k 0.01 , 0.02 0.00 k 0.01 , 0.02 0.00 k 0.01 , 0.02 1697W0094 MW-42-43' 0.06 k 0.15 . 0.28 0.06 k 0.07 . 0.06 -0.06 k 0.09 . 0.26 0.09 k 0.10 . 0.14 1697M0057 1697W0094 filter 0.01 k 0.02 , 0.03 0.01 k 0.01 , 0.01 0.00 f: 0.01 , 0.02 0.00 f: 0.01 , 0.01 1697W0095 MW-42-45.5' 0.15 k 0.16 . 0.24 0.03 f: 0.17 . 0.34 0.00 f. 0.16 . 0.34 0.12 f. 0.11 . 0.15 1697M0058 I 1697W0095 filter I 0.00 ? 0.01 ~ 0.03 0.002d f: 0.004 , 0.006 0.002 f. 0.004 , 0.006 0.00 f. 0.01 , 0.03 1697W0096 MW-42-41' 0.08 k 0.16 , 0.30 0.03 k 0.14 , 0.30 0.00 f. 0.08 , 0.21 0.06 f. 0.09 , 0.16 1697M0059 1697W0096 filter 0.01 k 0.01 . 0.02 0.01 k 0.01 . 0.01 0.00 f: 0.01 . 0.02 -0.02 f. 0.02 . 0.04 1697W0097 MW-59-31-(001) 0.19 k 0.17 , 0.23 0.24 f: 0.17 , 0.18 0.07 k 0.11 , 0.18 -0.06 f. 0.16 , 0.34 1697M0060 1697W0097 filter 0.01 k 0.02 , 0.03 0.00 k 0.01 . 0.02 0.002 f. 0.004 . 0.01 -0.02 k 0.02 . 0.04 1697W0098 MW-59-45-fOOl) 0.16 f: 0.13 - 0.08 0.16 k 0.13 , 0.08 0.03 k 0.12 , 0.25 -0.53 k 0.29 , 0.73 1697M0061 1697W0098 filter 0.01 k 0.02 , 0.03 0.00 f: 0.01 , 0.02 -0.01 k 0.02 , 0.03 0.00 k 0.01 , 0.02 1697w0099 MW-59-684001) 0.11 f. 0.16 . 0.27 0.20 k 0.17 . 0.21 0.06 k 0.08 - 0.08 -0.07 f: 0.14 - 0.33 e e e 1697M0062' 1697W0099 filter -0.01 f: 0.01 , 0.03 1697W0100 MW-58-26-f001', 0.04 2 0.22 . 0.42 -0.10 k 0.16 - 0.36 -0.02 k 0.25 . 0.47 0.02 f. 0.04 . 0.06 1697M0063 1697W0100filter 0.01 & 0.01 , 0.02 0.002 f. 0.004 , 0.006 0.002 k 0.004 , 0.006 0.01 f. 0.01 , 0.01 1697W0101 MW-58-65-(001', -0.16 f. 0.24 . 0.51 0.11 f. 0.16 . 0.28 -0.31 & 0.26 . 0.58 0.02 k 0.12 . 0.24 1697M0064 1697W0101 filter 0.01 f. 0.02 , 0.04 0.00 k 0.01 , 0.02 0.00 k 0.02 , 0.03 0.00 k 0.01 , 0.03 1697W0102 MW-39-200-(005) 0.05 k 0.12 . 0.23 0.05 k 0.10 . 0.18 0.00 k 0.07 . 0.18 0.05 k 0.09 . 0.18 1697M0065 I 1697W0102 filter 1 0.02 k 0.02 , 0.03 0.00  ? 0.01 , 0.02 I 0.00  ? 0.02 , 0.04 1 0.00 k 0.01 , 0.03

TABLE 6 (Continued)

CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK w

VI

%e MDCs are after the comma.

b kncertainties represent the 95% confidence level, based on total propagated uncertaindes.

5 'Zero values are due to rounding.

tl e dSigniGcant figures expanded to avoid reporting a TPU of zero at the request of the inspector.

%e yield QC for the Am and Cm data for this sample failed and the data cannot be reported.

K+

0

TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N SUSPENDED AND DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrationsa @Ci/g ORISE NRC Region I of sediment in 100 mL or pCi/L for Sample I D Sample ID water) 1697W0093 I MW-42-48' I 28

  • 41b 68 1697W0094 I MW-42-43' I 5 +

- 38 66 1697M0057 1697W0094 filter -2.7 f 3.2 , 5.5 1697W0095 MW-42-45.5' -10 k 39 68 16971110058 I 1697W0095 filter I 1.7 'f- 3.7 6.2 1697W0096 MW-42-41' 9 2 40 7 69 1697M0059 1697W0096 fiter 0.4 & 3.4 , 5.8 1697W0097 Mw-59-31-(001) -22

  • 38 66 1697M0060 1- 1697W067 filter I -0.9 f 3.5 6.0 1697W0098 I MW-59-45-(001) I -32 f 68 , 117 1697M0061 1697W0098 filter -0.7 k 3.3 , 5.7 1697W0099 MW-59-68-(001) -29 k 41 70 Y

1697M0062 1697W0099 filter -0.1 3.5 6.0 1697W0100 I MW-58126-(001) -Ip 8

  • 40 68 1697M0063 1697WO100 filter 0.6 k 3.2 , 5.5 1697W0101 M W - 5 8-65-(001) -12 2 43 74 1697M0064 I 1697W0101 filter I 3.0
  • 3.6 5.9 1697M0065 I 1697W0102 filter I 1.3 k 3.4 5.7 "I'he MDCs are after the c o r n .

buncertainties represent the 95% confidence level, based on total propagated uncertainties Indian oint Power Station projects/1697/Tables/2006-03-15Data Tables Sct 16

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 MDCs" (pCi/L) 1697W0093 MW-42-48' -4.4 k 9.2b , 15.8 1697~0094 MW-42-43' 3.4 +

- 9.3 . 15.8 11 1697W0095 I MW-42-45.5' I -4.9 9.2 . 15.8 1 1697W0096 I MW-42-41' I 1.1 k 9.3 , 15.8 1697W0097 MW-59-31-(001) -0.4 k 9.2 , 15.8 1697W0098 MW-59-45-(001) -1.1 +_ 9.2 , 15.8 1697W0099 MW-59-68-(001) 4.2 +

- 9.3 . 15.8 1 1697W0100 I Mw-58-26-(001) I 2.7 k 9.3 , 15.8 I 1697W0101 1697W0102 MW-58-65-(001)

MW-39-200-(005) 7.1

-0.3 k

k 9.4 9.2 15.8 15.8 "MDCs are after the comma.

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

Indian oint Power Station projects/1697/Tables/2006-~~-15Data Tables Set 16

Retrieved from "https://kanterella.com/w/index.php?title=ML070940534&oldid=2578123"