ML070940515: Difference between revisions

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| author name = Condra D
| author name = Condra D
| author affiliation = Oak Ridge Institute for Science & Education
| author affiliation = Oak Ridge Institute for Science & Education
| addressee name = Kottan J J
| addressee name = Kottan J
| addressee affiliation = NRC/RGN-I/DNMS/DB
| addressee affiliation = NRC/RGN-I/DNMS/DB
| docket = 05000247
| docket = 05000247
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| page count = 11
| page count = 11
}}
}}
See also: [[followed by::IR 05000247/2006007]]
See also: [[see also::IR 05000247/2006007]]


=Text=
=Text=

Revision as of 02:36, 13 July 2019

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


See also: IR 05000247/2006007

Text

OAK RIDGE INSTITUTE

FOR SCIENCE AND EDUCATION

February 2,2006 Mr. Jim Kottan US. Nuclear Regulatory Commission

Regon I 475 Allendale

Road IOng of Prussia, PA 19406 SUBJECT: SECOND INTERIM REPORT FOR REQUESTED

ANALYSES OF EIGHT WATER SAMPLES, SET FOURTEEN, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW YORK [INSPECTION

REPORT NO. 050-247/2006-0071 [RFTA

NO. 06-0011 Dear Mr. Kottan: The Oak hdge Institute for

Science and Education (ORISE) received set 14, whch consisted

of eight water samples received

on September

26,2006 from the InQan Point Power Station in

Buchanan, New York. Sample analysis was

initiated

based on your previous

hection for handling samples from hs facihty. The final report was delayed

untd technical concerns about

plutonium

in water samples were resolved through analytical testing conducted

by RaQological

and Environmental

Sciences Laboratory.

Sample identification

and collection data for the samples addressed

in &Is report are presented

in Table 1. Gamma spectroscopy, the hard-to- detect betas (iron-55, nickel-63, and tritium), technetium-99, total radiostrontium, alpha spectroscopy, plutonium-241, and carbon-14

data are provided in Tables

2 through 8, respectively.

The pertinent procedure references

are provided in each specific table.

ORISE's Quality Control (QC) requirements

were met for these

analyses.

The QC files are available for your review upon request. ORISE has removed the Ni-59 data

due to problems with the calculation associated with

the concentration

of hs ralonuclide.

ORISE is Qscontinuing the reporting of

Ni-59 data untd &Is problem can be resolved.

The water samples

were processed

using a deviation

to the sample preparation procedure, SP3, Revision 4. The water samples were

frltered through 0.45 micron filter papers. An aliquot was removed for tritium

and carbon-14 before

aciQfication.

An aliquot was removed for alpha analysis and the pH was adjusted to approximately zero using concentrated

nitric acid (HN03) and a few drops of hydrofluoric

acid (HF). A pH of zero and a few drops of HF should ensure

that any plutonium that

may be in the sample

remains in solution.

ORISE analyzed the filtered solid portion of each sample for all the requested alpha isotopes.

MK Jim Kottan -2- Febmay 2,2006 Distribution

approval and concurrence

Technical Management Team

Member Quality Manager My contact information

is listed below. You may also contact Wade Ivey at 865.576.9184

with any questions

or comments.

Initials - - Sincerely, Dale Condra, Manager Laboratory

RDC:WI:db

Enclosures

C: B. Watson, FSME/DWMEP/DD/SP

7E18 E. Abelquist, ORISE E. IOlox-Davin, NRC/FSME/TWFN

8A23 M. Roberts, NRC Region I File 1697 S. IGrk, ORISE J. Whte, NRC Region I Voice: 865.241.3242 Fax: 865.241.3248 E-mail:

Dale.Condra@orau.org

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 1697WO07Oa

1 697M0033b

1697W0071

MW-42@41 9/18/2006

14:45 MW-42@41 9/18/2006

14:45 MW-42@43 9/18/2006

13:OO 1697M0034

I MW-42@43 I 9/18/2006

I 13:OO 1697M0036

169773170074

1697M0037

1697W0075

1697W0072

I MW-42@46 I 9/15/2006

I 12:45 MW-42@48 9/ 15/2006 11:20

MW-59@70 9/15/2006

10:20 MW-59@70 9/15/2006

10:20 LAF-001-(003)

9/19/2006

15:49 1697M0035

I MW-42@46 I 9/15/2006

I 12:45 1697W0073

I MW-42@48 I 9/15/2006

I 11:20 1697M0038

I LAF-001-(003)

I 9/19/2006

I 15:49 1697W0076

I LAF-002-(003)

I 9/19/2006

I 13:41 1697M0039

I LAF-002-(003)

I 9/19/2006

I 13:41 1697W0077

I LAF-003-(003)

I 9/19/2006

I 11:08 1697M0040

I LAF-003-fO03)

I 9/19/2006

I 11:08 %e W in the ORISC sample identification represents

a water matrix.

bThe M in the ORISE sample identification represents the filtered fraction

of the preceding water sample Indian Point Power

Station projects/l697/Data

Tables/2007-02-02

Data Tables Set

14

TABLE 2 CONCENTRATIONS

OF SELECTED GAMMA EMITTING RADIONUCLIDES

IN WATER SAMPLES

BY GAMMA SPECTROSCOPY

CP1, REVISION 15 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Sample ID Sample ID 1697W0070

I MW-42@41 1697W0071

I MW-42@43 1697W0072

1697W0073

1697W0074

1697W0075

1697W0076

1697W0077

MW-42@46 MW-42@48 LAF-001-(003)

LAF-002-(003)

LAF-003-(003)

Radionuclide

Concentrationsa'

CO-58 CO-60 cs-134 0.1 k 3.0 I 0.3 k 4.1 I 1.3 If: 2.7 1.2 k 2.8 I 3.8 f. 2.9 I -0.5 k 2.4 -2.4 f. 3.0 2.2 f. 4.6 0.7 f. 2.6 -1.7 k 2.0 0.7 k 1.6 -0.8 f. 1.7 "The range

of MDCs for the selected radionuclides

for samples WOO7O-WOO73

is 13 pC1/L to 37 pCi/L "The range of MDCs for the selected radionuclides

for samples WOO74-WOO77

is 2.7 pCi/L to 5.0 pCi/L 'Uncertaintm represent the

95% confidence

level, based on total propagated uncertainties

cs-137 13.730 k 470 51 0.5 k 2.2 -0.7 k 1.6 11 Indian Point Power

Station projects/l697/Data Tables/2007-02-02 Data Tables Set 14

+ 0' 5' a 8 Fe-!Sb -19 ? 19" (32) -17 k 19 (32) -3 t 19 (32) TABLE 3 Ni-63" H-3d 452 ? 40 (35) 2,830 t 380 (420) 435 ? 39 (35) 2,350 t 360 (420) 1,207 2 85 (35) 1,500 k 320 (420) CONCENTRATIONS

OF HARD TO DETECT BETA EMITTING RADIONUCLIDES

IN WATER SAMPLES

BY LIQUID SCINTILLATION ANALYSIS CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK -4 ? 19 (32) -6 t 19 (32) -1 t 19 (32) ORISE NRC Region I Sample ID Sample ID -0.4 k 8.2 (14.1) 130 t 250 (420) 0.3 & 8.2 (14.1) -94 t 230 (420) 2.0 t 8.3 (14.1) -220 k 230 (420) 11 1697W0073

I MW-42@,48

11 1697W0074

I MW-59@70 11 1697W0075

I LAF-001-(003)

11 . 1697W0076

I LAF-002-(003)

11 1697W0077

I LAF-003-(003)

-2 t 19 (32) I 1.272 k 89 (35) I 1.370 ? 310 (420) 2 If: 19 (32) I 2.6 2 8.3 (14.1) I -40 k 240 (420) %e MDCs for each radionuclide are in parentheses.

bFe-55 analyzed using procedure

AP13, Revision 4. 'Ni-63 analyzed using procedure

AP17, Revision 0 dH-3 analyzed using

procedure

AP2, Revision 15. 'Uncertainties represent

the 95% confidence

level, based on total propagated uncertainties

L P

TABLE 4 ORISE Sample ID CONCENTRATIONS

OF TECHNETIUM-99 (Tc-99) IN WATER SAMPLES

BY LIQUID SCINTILLATION

ANALYSIS AP5, REVISION 16; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Tc-99 Concentrationsa

Sample ID (pCi/L) 1697W0074

1697W0075

1697W0076

1697W0077

MW-59@70 -4.7 k 8.9 (15.6) LAF-001-(003)

-2.7 k 9.0 (15.6) LAF-002-(003)

-0.5 k 9.1 (15.6) LAF-003-(003)

2.8 k 9.1 (15.6) %rhc MDCs are in parentheses. 'Uncertainties reprcsent

the 95% confidence

Icvel, based on total propagated

uncertainties.

Indian Point Power Station projects/l697/Data

Tables/2007-02-02

Data Tables Set

14

TABLE 5 ORISE Sample ID 1697W0070

1697W0071

1697W0072

CONCENTRATIONS

OF TOTAL RADIOSTRONTIUM

IN WATER SAMPLES BY LOW BACKGROUND

BETA COUNTING AP4, REVISION 13; CP3, REVISION 2 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide

Concentrations, Sample ID TPUs, and MDCs" (pCi/L)

Mw-42@41 20.2 k 2.Ob (2.3) MW-42@43 15.7 k 1.7 (1.9) MW-42@46 32.8 f 2.4 (2.2) 1697W0073

1697W0074

1697'0170075

1697W0076

1697W0077

MW-42@48 35.0 k 2.3 (2.0) MW-59@70 0.14 k 0.50 (0.89) LAF-001-(003)

0.10 k 0.52 (0.93) LAF-002-(003)

0.97 ? 0.55 (0.87) LAF-003-(003)

-0.17 k 0.45 (0.83) Indian Point

Power Station projects/l697/Data

Tables/2007-02-02

Data Tables Sct 14

TABLE 6 Cm-242 CONCENTRATIONS OF

SELECTED ALPHA EMITTING RADIONUCLIDES

IN SUSPENDED

AND DISSOLVED

FRACTIONS

OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Cm-243/244

N~-237 ORISE NRC Region I Sample ID 0.01 ? 0.01 (0.02) 0.07 k 0.06 (0.08) 0.00 ? 0.01 (0.03) 0.03 ? 0.06 (0.10) 0.01 k 0.01 (0.02) 1697W0070

m-42@41 0.03 k 0.09b (0.15) 1697M0033

Mw-42@41 0.01 & 0.02 (0.04) 1697W0071

MW-42@43 0.07 k 0.09 (0.15) 0.00" & 0.02 (0.03) 0.00 k 0.02 (0.03) 0.01 f. 0.09 (0.17) 0.01 ? 0.02 (0.03) -0.01 k 0.02 (0.04) -0.01 f. 0.02 (0.04) -0.03 f. 0.07 (0.14) 0.03 & 0.06 (0.11) 0.00 ? 0.02 (0.04) 0.00 ? 0.01 (0.03) 11 1697M0036

0.03 k 0.03 (0.02) 0.00 ? 0.01 (0.02) 0.02 f. 0.02 (0.03) m-42@48 0.00 ? 0.02 (0.04) 1697W0074

m-596370 0.00 k 0.05 (0.09) 2 1697M0037

m-59@70 -0.01 k 0.02 (0.04) .z 1697W0075

uF-001-(003)

0.03 f. 0.04 (0.07) , uF-001-(003)

0.02 f. 0.02 (0.03) E 2 - 1. L --. 1697M0038

U -' 0.01 f. 0.07 (0.14) -0.04 f. 0.05 (0.12) -0.01 k 0.02 (0.04) 0.002 f. 0.004d (0.007) -0.01 k 0.04 (0.08) 0.02 f. 0.02 (0.02) 2 11 1697W0076

I LAF-002-(003)

I -0.02 f. 0.05 (0.09) 0.00 f. 0.03 (0.06) 0.00 f. 0.01 (0.02) 0.01 ? 0.02 (0.03) 0.00 k 0.01 (0.02) R 11 1697M0039

I LAF-002-(003)

I 0.01 f. 0.02 (0.03) 0.00 k 0.03 (0.05) 0.00 f. 0.04 (0.08) 0.00 k 0.02 (0.03) 0.00 f. 0.01 (0.03) 0.00 f. 0.01 (0.01) -0.06 k 0.04 (0.10) 0.00 f. 0.01 (0.02) 0.002 ? 0.004 (0.006) I I e a 2 cn e P 0.01 ? 0.04 (0.07) I 0.01 & 0.08 (0.14) I 0.01 k 0.02 (0.03) 0.01 ? 0.01 (0.01) I 0.00 k 0.02 (0.03) I 0.00 f. 0.01 (0.03) I 1 0.00 f. 0.03 (0.06) I -0.02 k 0.04 (0.08) I 0.00 f. 0.01 (0.04) 0.01 ? 0.01 (0.03) I -0.01 k 0.02 (0.04) I 0.002 f. 0.005 (0.007)

i3 cn 8 d W Indian Point

Power Station F hl : 8 i +I 3 8 - F 01 9 9 9 +I 3 0 + 8 - fl + 9 0. 3 8 8 8 L 8 8 8 +I i - G hl +I 0 - 3 hl F M M 0 3 r- s\ W i T 7 C 5 7 C C t 7 C C - /- 7 C 5 r C C + r C C - r n C s 7 c C + 7 C C - G s C h C C + h C c - M 8 f d- M 0 3 r. c\ W 3 projccts/l697/Data

Tables/2007-02-02

Data Tables Set 14

TABLE 7 Mw-42048 MW-59@70 CONCENTRATIONS OF

PLUTONIUM-241

IN SUSPENDED

AND DISSOLVED FRACTIONS

OF WATER SAMPLES

BY LIQUID SCINTILLATION

ANALYSIS AP10, REVISION 2; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK (16.1) I -0.6 k 3.5 -2.5 k 9.3 ll* MW-59@70 LAF-001-(003)

LAF-001-(003)

LAF-002-(003)

LAF-002-(003)

1697M0036

1697W0074

1697M0037

1697W0075

1697M0038

1697W0076

1697M0039

-0.9 k 3.4 (5.9) -2.7 k 7.9 (13.7) 1.1 k 3.5 (6.0) -6.4 If: 7.8 (13.6) 1.4 - + 3.6 (6.1) ll* LAF-003-(003)

LAF-003-(003) "MDCs are in parenthescs

-2.5 k 8.2 (14.2) 2.6 ? 3.5 (5.9) Radionuclide

Concentrationsa (pCi/g of

sediment in 100 mL or pCi/L for water) NRC Region I Sample ID Mw-42@41 I -3 +_ 1 7b (29) 11 Mw-42@41 Mw-42@43 MW-42@43 -0.6 3.7

6.4) Mw-42@46 -10 (27) 'Uncertainties represent

the 95% confidence

level, based on total propagated uncertainhes Indian Point

Power Station projects/l697/Data

Tables/2007-02-02

Data Tables Set 14

TABLE 8 ORISE Sample ID 1697W0070

1697W0071

1697W0072

1697W0073

1697W0074

CONCENTRATIONS

OF CARBON-14

IN WATER SAMPLES

BY LIQUID SCINTILLATION

ANALYSIS AP9, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK NRC Region I Radionuclide

Concentrations, Sample ID MW-42@41 0.8 k 9.7b (16.4) MW-42@43 8.8 * 9.8 (16.4) MW-42@46 0.2 * 9.6 (16.4) MW-42@48 -0.6

k 9.6 (16.4) MW-59@70 6.9 - + 9.8 (1 6.4) TPUs, and MDCS" (pCi/L)

1697W0075

1697W0076

1697W0077 ~ ~ LAF-001-(003)

0.5 k 9.7 (16.4) LAF-002-(003)

1.4 * 9.7 (16.4) LAF-003-(003)

8.3 ? 9.8 (1 6.4) Indian Point Power Station

projects/l697/Data

Tables/2007-02-02

Data Tables Set 14

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