IR 05000029/2004002

Report for Analysis of a Concrete Sample from the Yankee Nuclear Power Station, Rowe, Massachusetts [Inspection No. 50-029/2004-002] [Rfta No. 05-001]

ML051330130
Person / Time
Site:	Yankee Rowe
Issue date:	02/23/2005
From:	Condra D Oak Ridge Institute for Science & Education
To:	Kottan J J NRC Region 1
References
IR-04-002, RFTA No.05-001
Download: ML051330130 (5)

Text

ORISE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION-

": CElVED 1 $ - ,.s ; q r-1 February 23,2005 Mr. Jim Kottan U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

SUBJECT: REPORT FOR ANALYSIS OF A CONCRETE SAMPLE FROM THE YANKEE NUCLEAR POWER STATION, ROWE, MASSACHUSETTS [INSPECTION NO.

50-029/2004-0021

[RFTA NO. 05-0011

Dear Mr. Kottan:

The Environmental Survey and Site Assessment Program (ESSAP)

of the Oak Ridge Institute for Science and Education (ORISE) received a concrete sample on November 4,2004 from the Yankee Nuclear Power Station in Rowe, Massachusetts that was collected on October 25,2004. The sample was analyzed as follows: by gamma spectroscopy (GS) (Procedure CPl , Revision 14), by alpha spectroscopy (AS) (Procedure APl 1 , Revision 2; Procedure CP2, Revision 12), by liquid scintillation analysis for tritium (H-3)

and carbon-14 (C-14) (Procedure AP6, Revision 14; Procedure CP4, Revision 3), by liquid scintillation analysis for nickel-63 (Ni-63), (Non-Routine Procedure AP12, Revision 3; Procedure CP4, Revision 3) and for strontium (Sr-90)

by gas-flow proportional counting (Procedure AP4, Revision1 2; Procedure CP3, Revision 2). The GS results are presented in Table 1. The AS results are presented in Table 2. The results for H-3, C-14, Ni-63, and Sr-90 have been combined and are presented in Table 3.

The request to analyze the sample for nickel-59 and iron-55 could not be met. ESSAP does not presently have procedures available for those two radionuclides in a concrete matrix.

ESSAP's 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 Untversittes for the U S Department of Energy Please contact me at (865) 241-3242 or Wade Ivey at (865) 576-9184 should you 1iaL.e any q Lies t i on s . Distribution approval and concurrence

Technical Management Team Member Quality Manager Si nc ere1 y, Initials I Dale Coiidra Laboratory Manager Envi ron m en t a1 Survey and Site Assessment Program RDC: WPI: ar Enc losu res cc: T. McLaughlin, NRC/NMSS/TWFN 7F27 E. Abelquist, ORISE/ESSAP E. Knox-Davin, NRC/NMSS/TWFN 8A23 .I. Hickman, NRC/DWMEP/TWFN 7F27 T. Vitkus, ORISE/ESSAP File/l62 1 ORISE TABLE 1 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN A CONCRETE SAMPLE BY GAMMA SPECTROSCOPY CP1, REVISION 14 YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS ESSAP Sample ID Radionuclide

'The range of MDCs for the selected radionuclides is 0.01 pCi/g to 0.08 pCi/g. buncertainties represent the 95% confidence level, based on total propagated uncertainties.

'Zero values are due to rounding. Yankee Nuclear Power Station projects/l 621/2005-02-23 Data Tables ORISE TABLE 2 ESSAP Sample ID CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN A CONCRETE SAMPLE BY ALPHA SPECTROSCOPY PROCEDURES AP11, REVISION 2 AND CP2, REVISION 12 YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS NRC Region I Concentrationsa Radionuclide Sample ID (PCW 162 1 MOOO 1 162 1 MOOO 1 162 1 MOOO 1 STC-CB-01 Pu-2391240 o.ooc f 0.01 STC-CB-01 Am-241 0.00 f 0.02 STC-CB-01 Cm-244 0.00 f 0.02 %e range of MDCs for the selected radionuclides is 0.02 pCi/g to 0.04 pCi/g. buncertainties represent the 95% confidence level, based on total propagated uncertainties.

'Zero values are due to rounding. Yankee Nuclear Power Station projectdl62 1/2005-02-23 Data Tables ORISE TABLE 3 ESSAP Sample ID 162 1 MOO0 1 162 1 MOOOl CONCENTRATIONS OF SELECTED BETA EMITTING RADIONUCLIDES IN A CONCRETE SAMPLE YANKEE NUCLEAR POWER STATION ROWE, MASSACHUSETTS NRC Region I Concentrations and Radionuclide Sample ID MDCS' (pcvg) STC-CB-01 H-3b 28.9 f 4.2'(5.5)

STC-CB-01 C-14b 3.8 f 1.3 (2.0) 162 1 MOOOl 1621 MOOOl STC-CB-0 1 Ni-63d 0.80 f 0.93 (1.6) STC-CB-0 1 Sr-90e 0.19 f 0.45 (0.79) 'MDCs are in parenthesis.

bAnalyzed by Procedures AF'6, Revision 14 and CP4. Revision 3. 'Uncertainties represent the 95% confidence level, based on total propagated uncertainties.

dAnalyzed by Non-Routine Procedure AP12, Revision 3 and Procedure CP4, Revision 3. 'Analyzed by Procedures AP4. Revision 12 and CP3. Revision2.

Yankee Nuclear Power Station projectdl 62 I /2005-02-23 Data Tables