ML051730285

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E-Mail Dated 06/16/05 Regarding FSS Report 6 - FB-1700-01 Grid 179 Sample
ML051730285
Person / Time
Site: Maine Yankee
Issue date: 06/16/2005
From: Whitney M
Maine Yankee Atomic Power Co
To: Buckley J, Roberts M, Bruce Watson
NRC/NMSS/DWM/DCB, Division of Nuclear Materials Safety I
References
Download: ML051730285 (9)


Text

1John Buckley - FSS Report 6 - FB-1 700-01 Grid 179 Sample Page 1 Page 1I John Buckley- FSS Report 6 FB-1700-Oi Grid 179 Sample From: "Mike Whitney" <whitney@ maineyankee.com>

To: "mark roberts" <mcr~nrc.gov>, njohn buckley" <jtb~nrc.gov>, "Bruce Watson"

<BAW1 @nrc.gov>

Date: 6/16/05 11:31 AM

Subject:

FSS Report 6 - FB-1700-01 Grid 179 Sample Attached is the gamma spec for the concrete sample taken at Grid 179. This shows all the nuclides detected. None were plant derived.

Hopefully this gives you what you need.

Michael A. Whitney Maine Yankee Atomic Power Co.

321 Old Ferry Rd Wiscasset, ME 04578 (207) 721-9137 Brunswick office till 6/23 (207) 882-1349 Wiscasset office after 6/23 (207) 823-9646 Pager (207) 729-7871 Home office CC: <Packer@myapc.com>, "George Pillsbury' <pillsbury@ maineyankee.com>

          • GA MM A S PE C T RUM A NA LYS I S***

Report Generated On  : 12/09/04 10:02:31 AM Sample Title  : 250 mL concrete Sample Description  : XB1700-01-3-C179-VS Sample Identification  : conctete Sample Type  : CON Sample Geometry  : 250 mL concrete Peak Locate Threshold 3.00 Peak Locate Range (in channels) 1 - 4096 Peak Area Range (in channels) 50 - 4095 Identification Energy Tolerance 1.000 keV Sample Size 4.948E+002 Gm Sample Taken On  : 12/09/04 8:15:00 AM Acquisition Started  : 12/09/04 9:29:10 AM Live Time  : 2000.0 seconds Real Time  : 2000.5 seconds Energy Calibration Used Done On  : 11/29/04 Efficiency Calibration Used Done On 4/30/02

Peak Analysis Report 12/09/04 10:02:32 AM Page 2 P E A K A N A L Y S I S R E P O R T Detector Name: DET2 Sample

Title:

250 mL concrete Peak Analysis Performed on: 12/09/04 10:02:32 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 4095 Peak ROI ROI Peak Energy Net Peak Net Area Continuum No. start end centroid (keV) Area Uncert. Counts 1 142- 156 147.17 74.68 2.30E+002 137.05 3.38E+002 2 142- 156 151.83 77. 01 2.80E+002 152 . 91 2.97E+002 3 365- 374 369.96 185. 98 1.21E+002 47.61 2.08E+002 M 4 470- 487 475.20 238.56 3.51E+002 203.04 1.27E+002 m 5 470- 487 481.86 241.89 1.49E+002 86.48 9.73E+001 6 583- 593 588.66 295.24 2.25E+002 42.18 1. OOE+002 7 669- 680 674.82 338.28 4.61E+001 34.38 1. 04E+002 8 696- 707 701.95 351.84 3.34E+002 46. 92 9.55E+001 9 1013- 1025 1019.70 510.58 7.09E+001 27.34 4.71E+001 10 1158- 1170 1164.92 583.13 1. 04E+002 30.12 5. 02E+001 11 1211- 1223 1217.02 609.16 2.41E+002 37.48 4.75E+001 12 1814- 1827 1820.92 910.86 5.89E+001 25. 93 4.21E+001 13 2232- 2246 2239.19 1119.83 5.78E+001 25.59 3.92E+001 14 2913- 2927 2921.07 1460.49 5. 82E+002 48.20 7. 69E+000 15 3519- 3535 3527.95 1763.69 4. 69E+001 15.16 4. 13E+000 M = First peak in a multiplet region n = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.960 sigma

Background Subtract Report 12/09/04 10:02:32 AM Page 3 B A C K G R O U N D S U B T R A C T R E P O R T Detector Name: DET2 Sample

Title:

250 mL concrete Peak Analysis Performed on: 12/09/04 10:02:32 AM Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncert. Background Uncert. Area Uncert.

1 74.68 2.30E+002 137.05 2.30E+002 1.37E+002 2 77.01 2.80E+002 152.91 2.80E+002 1. 53E+002 3 185.98 1.21E+002 47.61 2.20E+001 2.33E+000 9.90E+001 4.78E+001 4 238.56 3.51E+002 203.04 8.85E+000 1. 90E+000 3.42E+002 2. 03E+002 5 241.89 1.49E+002 86.48 1.49E+002 8. 65E+001 6 295.24 2.25E+002 42.18 2. 25E+002 4.22E+001 7 338.28 4. 61E+001 34.38 4. 61E+001 3.44E+001 8 351.84 3. 34E+002 46.92 3.34E+002 4.69E+001 9 510.58 7.09E+001 27.34 3.08E+001 1.63E+000 4. 01E+001 2.75E+001 10 583.13 1. 04E+002 30.12 1. 04E+002 3. 01E+001 11 609.16 2.41E+002 37.48 2.41E+002 3.75E+001 12 910.86 5.89E+001 25.93 1.88E+000 5.20E-001 5.70E+001 2.59E+001 13 1119.83 5.78E+001 25.59 5.78E+001 2.56E+001 14 1460.49 5.82E+002 48.20 1.23E+001 9.33E-001 5.70E+002 4.82E+001 15 1763.69 4. 69E+001 15.16 4 .69E+001 1. 52E+001 M First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 1.960 sigma

interference Corrected Activity Report 12/09/04 10:02:33 AM Page 4

          • N U C L I D E I D E N T I F I C A T I 0 N R E P O R T ****

Sample

Title:

250 mL concrete Nuclide Library Used: C:\GENIE2K\CAMFILES\STDLIB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (M) (pci/Gm ) Uncertainty K-40 0. 984 1460.81* 10.67 1.86614E+001 1.91285E+000 TL-208 0. 733 277.35 6.80 510.84* 21.60 2.41967E-001 1.67780E-001 583 .14* 84.20 1.82174E-001 5.42817E-002 763.13 1.64 860.37 12.46 PB-212 0.779 74.81* 10.70 1.65900E+000 1.00920E+000 77.11* 18.00 1.13781E+000 6.34332E-001 87.30 8.00 238.63* 44.60 5.12680E-001 3.07165E-001 300.09 3.41 BI-214 0.456 76.86* 0.36 5.68905E+001 3.16758E+001 79.29 0.60 89.80 0.27 273.70 0.18 387.00 0.37 389.10 0.41 405.74 0.17 454.77 0.32 469.69 0.13 474.38 0.12 609.31* 46.30 8.03731E-001 1.39374E-001 665.45 1.57 703.11 0.47 719.86 0.41 752.84 0.13 768.36 5.04 786.10 0.32 806.17 1.23 821.18 0.15 904.25 0.11 934.06 3.21 964.08 0.38 1051. 96 0.32 1069.96 0.29 1120.29* 15.10 1.05625E+000 4.75309E-001 1133.66 0.26 1155.19 1.70 1207.68 0.46 1238.11 5.94 1280.96 1.48 1303 .76 0.12

Interference Corrected Activity Report 12/09/04 10:02:33 AM -Page 5 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (0) (pci/Gm ) Uncertainty BI-214 0.456 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.49 1509.23 2.22 1538.50 0.41 1543.32 0.36 1583.22 0.72 1594.73 0.27 1599.31 0.34 1661.28 1.15 1683.99 0.24 1729.59 2.88 1764.49* 15.80 1.19894E+000 4.03638E-001 1838.36 0.38 1847.42 2.04 1873.16 0.23 1896.30 0.18 2118. 55 1.17 2204.21 4.98 2293 .36 0.32 2447.86 1.56 PB-214 0.886 53.23 1.11 74.82* 6.21 2.85849E+000 1.73153E+000 77.11* 10.50 1.950532+000 1.08702E+000 87.30 4.67 241. 98* 7.49 1.34530E+000 7.88640E-001 295.21* 19.20 9.28602E-001 1.91089E-001 351. 92* 37.20 8.31198E-001 1.34194E-001 RA-226 0.992 186.21* 3.28 1.71235E+000 8.35192E-001 U-235 0.667 89.95 2.70 143.76 10.50 185.71* 54.00 1.04009E-001 5.06959E-002

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.10 Errors quoted at 1.960 sigma

Interference Corrected Activity Report 12/09/04 10:02:33 AM Page 6

          • INTERFERENCE CORR'ECTED REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pci/Gm ) Uncertainty X ANN 0.972 K-40 0.984 1.866139E+001 1.912847E+000 TL-208 0.733 1.878398E-001 5.164607E-002 PB-212 0.779 5.753267E-001 2.658472E-001 BI-214 0.456 8.581212E-001 1.219996E-001 PB-214 0.886 8.746752E-001 1.018938E-001

? RA-226 0.992 1.712349E+000 8.351915E-00'1) U

? U-235 0.667 1.040093E-001 5.069586E-00 X AM-243 1.000

? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.960 sigma U N I D E N T I F I E D P E A K S ********

Peak Locate Performed on: 12/09/04 10:02:32 AM Peak Locate From Channel: 50 Peak Locate To Channel: 4095 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second i Uncertainty 7 338.28 2.3028E-002 74.647

12' 910.86 2.8514E-002 45.50j 4 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.960 sigma

Nuclide MDA Report 12/09/04 10:02:33 AM Page 7

                      • t**************************************************************

Detector Name: DET2 Sample Geometry: 250 mL concrete Sample

Title:

250 mL concrete Nuclide Library Used: C:\GENIE2K\CAMFILES\STDLIB.NLB Nuclide Nuclide MDA Name (pci/Gm )

ANN 5.72E-002 BE-7 4.96E-001

+ K-40 7.33E-001 CR-51 5.09E-001 MN-54 8.80E-002 CO-57 5.20E-002 CO-58 7.97E-002 FE-59 1.79E-001 CO-60 9.37E-002/

ZN-65 2.79E-001 KR-85 1.73E+001 Y-88 6.63E-002 NB-94 7.74E-002 NB-95 8.88E-002 ZR-95 1.28E-001 MO-99 5.49E-002 RU-103 6.11E-002 RH-106 3.70E-0O1 CD-109 1.76E+000 AG-llOM 6.37E-002 SN-113 7.50E-002 SB-124 6.19E-002 SB-125 1.88E-001 SB-126 6.OOE-002 SN-126 1.82E-001 CS-134 9.58E-002 CS-137 7.77E-002&Z CE-139 5.22E-002 CE-144 3.84E-001 EU-152 1.54E-001 EU-154 1.12E-O01 EU-155 2.14E-001 HG-203 6.21E-002

+ TL-208 7.12E-002 BI-212 7.40E-OOl

+ PB-212 8.45E-002

+ BI-214 1.31E-001

+ PB-214 1.33E-001

+ RA-226 1.32E+000 AC-228 4.45E-001 PA-234M 1.80E+001 TH-234 1.22E+000

Nuclide MDA Report 12/09/04 10:02:33 AM Page 8 Nuclide . Nuclide MDA Name (pci/Gm )

+ U-235 7.99E-002 AM-241 2.15E-001 AM-243 1.03E-001 CM-243 2.09E-001

+ = Nuclide identified during the nuclide identification

@ = Half-life too short to be able to perform the decay correction