ML061530402
| ML061530402 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe, 05000001 |
| Issue date: | 12/09/2005 |
| From: | Condra D Oak Ridge Institute for Science & Education |
| To: | Kottan J NRC Region 1 |
| References | |
| IR-05-002 | |
| Download: ML061530402 (5) | |
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O R I S E O A K RIDGE INSTITUTE F O R S C I E N C E AND E D U C A T I O N December 09,2005 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSIS OF CONCRETE AND SOIL SAMPLES FROM THE YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS
[INSPECTION NO. 50-029/2005-0021 [RFTA NO. 05-001/06-0011
Dear Mr. Kottan:
The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) received one concrete sample on June 27,2005, one concrete sample on July 28, 2005, and four soil samples on June 29,2005 from the Yankee Nuclear Power Station in Rowe, Massachusetts. The sample identifications and sampling dates are in Table 1.
The soil and concrete samples were analyzed by gamma spectroscopy (GS) (Procedure CP1, Revision 15). The concrete samples were also analyzed by liquid scintillation analysis for tritium (H-3) and carbon-14 (C-14) (Procedure AP6, Revision 15; Procedure CP4, Revision 3), by liquid scintillation analysis for nickel-59/63 (Ni-59/63), (Non-Routine Procedure AP17, Revision 0; Procedure CP4, Revision 3), by liquid scintillation analysis for iron-55 (Fe-55), (Non-Routine Procedure AP16, Revision 0; Procedure CP4, Revision 3) and for strontium-90 (Sr-90) by gas-flow proportional counting (Procedure AP4, Revision 13; Procedure CP3, Revision 2). The GS results are presented in Table 2. The results for H-3, C-14, Fe-55, Ni-59/63, and Sr-90 have been combined and are presented in Table 3.
The completion of all analyses was delayed due to the request to develop analytical procedures to measure Fe-55 and Ni-59/63 in solid matrices. The Fe procedure received the require approvals on September 29, 2005 and the Ni procedure received the required approvals on November 10, 2005.
ESSAPs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
P. 0. BOX 1 17, OAK RIDGE, TENNESSEE 3783 1-01 17 Operated by Oak Ridge Associated Universities for the U.S. Department of Energy
Mr. Jim Kottan December 09, 2005 Distribution approval and concurrence :
Technical Management Team Member Quality Manager Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you have any questions.
Initials I nl) u p r Sincerely, Dale Condra Laboratory Manager Environmental Survey and Site Assessment Program RDC:WPI:ar Enclosures cc:
T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISEESSAP E. Knox-Davin, NRC/NMSS/TWFN SA23 J. Hickman, NRC/DWhXEP/TWFN 7F27 File/1621 S. Kirk, ORISEESSAP
ORISE TABLE 1 ESSAP Sample ID SAMPLE IDENTIFICATIONS AND COLLECTION DATES ROWE, MASSACHUETTS iNKEE NUCLEAR POWER STATION NRC Region I Collection Collection Sample ID Date Time TDS-100-GR-S TDS-20 1 -GR-S2 TBN-02-001 TBN-02-005 CWP-2 CWP-7 6/23/2005 9:30 7/21/2005 9:20 4/28/2005 1o:oo 4/28/2005 14:OO 4/16/2005 950 4/27/2005 14:OO Yankee Nuclear Power Station I
1621S0020 1621S0021 projectdl 621/Reports/2005-12-09 Data Tables
ORISE TABLE 2 ESSAP Sample ID 1621M0002
+d 0
d 8 5 g.
J NRC Region I Radionuclide Concentrations (
Sample ID CO-60 Ag-108m Sb-125 CS-137 TDS-100-GR-S 0.05 +- 0.04b -0.02 f 0.02 0.01 f 0.05 0.09 f 0.05 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN TWO CONCRETE SAMPLES AND FOUR SOIL SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS 1621M0003 TDS-201-GR-S2 1621S0018A TBN-02-001 1621SOO 18B TBN-02-001 162130019 TBN-02-005 162 1 SO020 CWP-2 1621S002 1 CWP-7 0.01 -+ 0.02 0.01 f 0.01 81.5 -I 2.7 1.33 f 0.25 87.8 f 2.9 1.27 f 0.23 3.80 k 0.24 0.09 f 0.06 0.19 f 0.09 -0.02 rt 0.04 0.02 f 0.03 -0.01 ~ f : 0.01 0.01 0.041 0.03 +- 0.03 0.17 f 0.501 6.31 f 0.59 0.40 f 0.53 17.29 f 0.65 0.05 f 0.131 0.65 -c 0.12 0.03 f 0.141 1.00 f 0.15 e
2?
F P-buncertainties represent the 95% confidence level, based on total propagated uncertainties.
'Zero values are due to rounding.
s W
0.03 f 0.04 10.13 f 0.03 Ci/g dry weight)a
_ _ _ _ _ ~
Eu-152 I
Eu-154 0.07 -c 0.061 0.02 f 0.02
- 5.
3 Concentrations and MDCsa (pCi/g)
ESSAP Sample NRC Region I Sr-90' ID Sample ID H-3b C-14b Fe-55' Ni-59d Ni-63d 162 1 MOO02 TDS-100-GR-S 23.9 4.1f (5.5) 55.6 k 3.0 (3.1) 2.8 & 3.6 (6.1)
-1.0 k 1.1 (1.8) 0.5 k 1.1 (1.9)
-0.15 k 0.23 (0.43) 162 1 MOO03 TDS-201-GR-S2 23.8 f 4.1 (5.5) 70.6 k 3.4 (3.1) 5.5 k 3.7 (6.1) 0.5 -C 1.1 (1.9)
-0.2
- 1.1 (1.9)
-0.04 & 0.23 (0.42)