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| | number = ML061630389 | | | number = ML061630389 |
| | issue date = 06/07/2006 | | | issue date = 06/07/2006 |
| | title = Byron Tritium Analyses (Batch BY-2006-2) | | | title = Tritium Analyses (Batch BY-2006-2) |
| | author name = Cameron J L | | | author name = Cameron J |
| | author affiliation = NRC/RGN-III/DNMS | | | author affiliation = NRC/RGN-III/DNMS |
| | addressee name = Orth S K | | | addressee name = Orth S |
| | addressee affiliation = NRC/RGN-III/DRS | | | addressee affiliation = NRC/RGN-III/DRS |
| | docket = 05000454, 05000455 | | | docket = 05000454, 05000455 |
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| =Text= | | =Text= |
| {{#Wiki_filter:MEMORANDUM TO: FROM: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 111 2443 WARRENVILLE ROAD, SUITE 2 IO LISLE, ILLINOIS 60532-4352 June 7,2006 MEMORANDUMTO: Steven K. Orth, Team Leader Plant Support Team Division of Reactor Safety FROM: Jamnes L. Cameron, Chief Decommissioning Branch Division of Nuclear Materials Safety |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 111 2443 WARRENVILLE ROAD, SUITE 2 IO LISLE, ILLINOIS 60532-4352 June 7,2006 Steven K. Orth, Team Leader Plant Support Team Division of Reactor Safety Jamnes L. Cameron, Chief Decommissioning Branch Division of Nuclear Materials Safety ANALYTICAL RESULTS OF WATER SAMPLES FROM THE VICINITY OF THE BYRON NUCLEAR POWER STATION (BATCH BY-2006-02)
| | ANALYTICAL RESULTS OF WATER SAMPLES FROM THE VICINITY OF THE BYRON NUCLEAR POWER STATION (BATCH BY-2006-02) |
| By letter dated April 27, 2006, (ML061220683), we received the results of the analysis of 41 water samples from the NRC's contract laboratory, the Oak Ridge Institute for Science and Education (ORISE). | | By letter dated April 27, 2006, (ML061220683), we received the results of the analysis of 41 water samples from the NRCs contract laboratory, the Oak Ridge Institute for Science and Education (ORISE). These were samples collected by Exelon personnel from February 3 to March 29, 2006, in the vicinity of the Byron Nuclear Power Station and provided to Region 111 for analysis for tritium. The licensee collected separate samples for their analysis at the same time they collected the samples for the NRC. |
| These were samples collected by Exelon personnel from February 3 to March 29, 2006, in the vicinity of the Byron Nuclear Power Station and provided to Region 111 for analysis for tritium. The licensee collected separate samples for their analysis at the same time they collected the samples for the NRC. We have reviewed the analysis results from ORISE and compared the results with the licensee's results for their samples. | | We have reviewed the analysis results from ORISE and compared the results with the licensees results for their samples. The enclosed Table provides the results of the analyses and an assessment of how they compared. The comparison was based on the Confirmatory Measurements Program criteria provided in Inspection Procedure 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring, dated March 15, 1994. There was agreement in the results between the ORISE and licensee analyses for all 41 samples. Six samples were also analyzed for gamma emitting nuclides. No radioactivity was identified in the samples in excess of the minimum detectable concentrations for cobalt-58, cobalt-60, cesium-134. or cesium-137. |
| The enclosed Table provides the results of the analyses and an assessment of how they compared. | |
| The comparison was based on the Confirmatory Measurements Program criteria provided in Inspection Procedure 84750, "Radioactive Waste Treatment, and Effluent and Environmental Monitoring," dated March 15, 1994. There was "agreement" in the results between the ORISE and licensee analyses for all 41 samples. Six samples were also analyzed for gamma emitting nuclides. | |
| No radioactivity was identified in the samples in excess of the minimum detectable concentrations for cobalt-58, cobalt-60, cesium-134. | |
| or cesium-137. | |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| | As Stated CONTACT: William G. Snell, DNMS 630-829-9871 |
|
| |
|
| As Stated CONTACT: William G. Snell, DNMS 630-829-9871 Tritium SamDle Results # I I Ratio: to NRC Collection Tritium Tritium Date NRC Sample ID ~CUL uncertainty MDC Licensee Sample ID pCii *uncertainty Licensee Result BY-06-2-01 thru -41 Analysis.xls Last Modified 05/25/2006@3:20 PM Page 1 of 2 Collection Date # BY-06-2-01 thru
| | Tritium SamDle Results I I Ratio: |
| -41 Analysis.xis Last Modified 05/25/2006@3:20 PM Ratio: to NRC Tritium Tritium NRC Sample ID pci/~ uncertainty MDC Licensee Sample ID pCK uncertainty Licensee Result Page 2 of 2}} | | # Collection Tritium Tritium Date NRC Sample ID ~ C U L uncertainty MDC Licensee Sample ID p C i i *uncertainty Licensee Result to NRC BY-06-2-01 thru -41 Analysis.xls Last Modified 05/25/2006@3:20PM Page 1 of 2 |
| | |
| | Ratio: |
| | Collection Tritium Tritium |
| | # NRC Sample ID p c i / ~ uncertainty MDC Licensee Sample ID pCK uncertainty Licensee Result Date to NRC BY-06-2-01 thru -41 Analysis.xis Last Modified 05/25/2006@3:20 PM Page 2 of 2}} |
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 111 2443 WARRENVILLE ROAD, SUITE 2 IO LISLE, ILLINOIS 60532-4352 June 7,2006 MEMORANDUMTO: Steven K. Orth, Team Leader Plant Support Team Division of Reactor Safety FROM: Jamnes L. Cameron, Chief Decommissioning Branch Division of Nuclear Materials Safety
SUBJECT:
ANALYTICAL RESULTS OF WATER SAMPLES FROM THE VICINITY OF THE BYRON NUCLEAR POWER STATION (BATCH BY-2006-02)
By letter dated April 27, 2006, (ML061220683), we received the results of the analysis of 41 water samples from the NRCs contract laboratory, the Oak Ridge Institute for Science and Education (ORISE). These were samples collected by Exelon personnel from February 3 to March 29, 2006, in the vicinity of the Byron Nuclear Power Station and provided to Region 111 for analysis for tritium. The licensee collected separate samples for their analysis at the same time they collected the samples for the NRC.
We have reviewed the analysis results from ORISE and compared the results with the licensees results for their samples. The enclosed Table provides the results of the analyses and an assessment of how they compared. The comparison was based on the Confirmatory Measurements Program criteria provided in Inspection Procedure 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring, dated March 15, 1994. There was agreement in the results between the ORISE and licensee analyses for all 41 samples. Six samples were also analyzed for gamma emitting nuclides. No radioactivity was identified in the samples in excess of the minimum detectable concentrations for cobalt-58, cobalt-60, cesium-134. or cesium-137.
Enclosure:
As Stated CONTACT: William G. Snell, DNMS 630-829-9871
Tritium SamDle Results I I Ratio:
- Collection Tritium Tritium Date NRC Sample ID ~ C U L uncertainty MDC Licensee Sample ID p C i i *uncertainty Licensee Result to NRC BY-06-2-01 thru -41 Analysis.xls Last Modified 05/25/2006@3:20PM Page 1 of 2
Ratio:
Collection Tritium Tritium
- NRC Sample ID p c i / ~ uncertainty MDC Licensee Sample ID pCK uncertainty Licensee Result Date to NRC BY-06-2-01 thru -41 Analysis.xis Last Modified 05/25/2006@3:20 PM Page 2 of 2
