ML061630389: Difference between revisions
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{{#Wiki_filter:MEMORANDUM TO: FROM: | {{#Wiki_filter:MEMORANDUM TO: | ||
FROM: | |||
==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) | 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) | ||
By letter dated April 27, 2006, (ML061220683), we received the results of the analysis of 41 water samples from the | By {{letter dated|date=April 27, 2006|text=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 | 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, | |||
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 | |||
Tritium SamDle Results I | |||
-41 Analysis.xis Last Modified 05/25/2006@3:20 PM Ratio: to NRC Tritium Tritium NRC Sample ID | I Ratio: | ||
to NRC Collection Tritium Tritium Date NRC Sample ID | |||
~ C U L 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 -41 Analysis.xis Last Modified 05/25/2006@3:20 PM Ratio: | |||
to NRC Tritium Tritium NRC Sample ID p c i / ~ uncertainty MDC Licensee Sample ID pCK uncertainty Licensee Result Page 2 of 2}} | |||
Latest revision as of 08:31, 15 January 2025
| ML061630389 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/07/2006 |
| From: | Jamnes Cameron Division of Nuclear Materials Safety III |
| To: | Steven Orth Division of Reactor Safety III |
| References | |
| FOIA/PA-2010-0209 | |
| Download: ML061630389 (3) | |
Text
MEMORANDUM TO:
FROM:
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)
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:
to NRC Collection Tritium Tritium Date NRC Sample ID
~ C U L 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 -41 Analysis.xis Last Modified 05/25/2006@3:20 PM Ratio:
to NRC Tritium Tritium NRC Sample ID p c i / ~ uncertainty MDC Licensee Sample ID pCK uncertainty Licensee Result Page 2 of 2