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Category:Report
MONTHYEARML24155A2222024-05-28028 May 2024 Methodology Evaluation Report for Elimination of Response Time Testing Prairie Island Reactor Trip System Rev. 1 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23075A3512022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 6 of 7) ML23075A3482022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 3 of 7) ML23075A3472022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 2 of 7) L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)2022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7) ML23075A3462022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 1 of 7) ML23075A3502022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 5 of 7) ML23075A3492022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 4 of 7) ML22003A1832022-01-0303 January 2022 Refueling Outage Unit 2 R32 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML21285A2812021-10-12012 October 2021 Revised Pressure and Temperature Limits Report ML20272A2932020-09-28028 September 2020 (PINGP) Unit 1 and 2 Revised Pressure and Temperature Limits Report ML20265A0892020-09-15015 September 2020 Draft License Conversation Record L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency ML17279A1242017-09-30030 September 2017 Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel L-PI-16-058, Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation2016-07-22022 July 2016 Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation L-PI-16-054, Pressure and Temperature Limits Report, Revision 52016-06-22022 June 2016 Pressure and Temperature Limits Report, Revision 5 L-PI-16-051, 10 CFR 50.46 Emergency Core Cooling System Annual Report2016-06-22022 June 2016 10 CFR 50.46 Emergency Core Cooling System Annual Report L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 42015-05-14014 May 2015 Pressure and Temperature Limits Report (PTLR) Revision 4 ML15037A4582015-03-0606 March 2015 Staff Assessment of the Aging Management Program for Reactor Vessel Internal Components L-PI-14-131, Fifth Ten-Year Interval Snubbers Testing Program2014-12-18018 December 2014 Fifth Ten-Year Interval Snubbers Testing Program ML17297A3232014-11-14014 November 2014 Enclosure 2 (Redacted): Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal for Prairie Island Unit 1 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant ML14148A4772014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14120A1622014-05-0909 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident L-PI-14-045, Enclosure to L-PI-14-045, Transition Report, Revision 12014-04-30030 April 2014 Enclosure to L-PI-14-045, Transition Report, Revision 1 L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14030A5402014-02-27027 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14041A2042014-02-26026 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2, TAC Nos.: MF0834 and MF0835 L-PI-13-080, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-08-26026 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-PI-12-108, Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-PI-12-103, Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML13133A0632012-06-27027 June 2012 H4, Rev. 27, Offsite Dose Calculation Manual (Odcm). ML12159A2562012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 ML1021002592010-06-30030 June 2010 Seismic Fragilities for Unit #1 and Unit #2 Turbine Building Piping and Equipment ML1016901712010-06-11011 June 2010 Enclosure 6, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16275, Effects of Pipe Whip Interactions for Various Pipe Combinations for Internal Flooding Sdp. ML1016901702010-06-11011 June 2010 Enclosure 5, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16270, Screening of Pipe Whip Interactions for Sdp. ML1016901682010-06-11011 June 2010 Enclosure 3, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16090, Turbine Building Flooding SDP: Cl Turbine Building Pipe Break Analysis. ML1016901692010-06-10010 June 2010 Enclosure 4, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16154, Turbine Building Flooding SDP: Cl Turbine Building Seismic Pipe Break Analysis. L-PI-10-005, Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems2010-02-18018 February 2010 Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems ML1019703862009-12-31031 December 2009 Ground Water Investigation: an Improved Flow Net to Evaluate Pathways for a Potential Ground Water Release ML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. ML1002001322009-12-18018 December 2009 Report 0900634.402, Revision 2, Updated Leak-Before-Break Report for Prairie Island Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle. L-PI-09-115, Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology ML1008406402009-09-11011 September 2009 Advisory Brief of Prairie Island Nuclear Generating Plant Study Group to State of Minnesota, Office of Administrative Hearings for the Public Utilities Commission, Sept. 11, 2009. Submitted with Comments on Draft Generic Environmental Impac L-PI-09-021, 2008 Unit 2 180-Day Steam Generator Tube Inspection Report2009-04-27027 April 2009 2008 Unit 2 180-Day Steam Generator Tube Inspection Report 2024-05-28
[Table view] Category:Miscellaneous
MONTHYEARML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML22003A1832022-01-0303 January 2022 Refueling Outage Unit 2 R32 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections L-PI-16-058, Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation2016-07-22022 July 2016 Special Report: Timely Restoration of Operability of Explosive Gas Monitoring Instrumentation L-PI-16-051, 10 CFR 50.46 Emergency Core Cooling System Annual Report2016-06-22022 June 2016 10 CFR 50.46 Emergency Core Cooling System Annual Report ML15037A4582015-03-0606 March 2015 Staff Assessment of the Aging Management Program for Reactor Vessel Internal Components L-PI-14-131, Fifth Ten-Year Interval Snubbers Testing Program2014-12-18018 December 2014 Fifth Ten-Year Interval Snubbers Testing Program ML14148A4772014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14120A1622014-05-0909 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident L-PI-13-080, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-08-26026 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-PI-12-108, Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-PI-12-103, Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident2012-11-26026 November 2012 Final Response to NRC Request for Lnformation Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Lnsiqhts from the Fukushima Dai-ichi Accident ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML12159A2562012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML1016901712010-06-11011 June 2010 Enclosure 6, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16275, Effects of Pipe Whip Interactions for Various Pipe Combinations for Internal Flooding Sdp. ML1016901702010-06-11011 June 2010 Enclosure 5, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16270, Screening of Pipe Whip Interactions for Sdp. ML1016901682010-06-11011 June 2010 Enclosure 3, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16090, Turbine Building Flooding SDP: Cl Turbine Building Pipe Break Analysis. ML1016901692010-06-10010 June 2010 Enclosure 4, Prairie Island Nuclear Generating Plant, Units 1 and 2, Supporting Engineering Evaluations, EC 16154, Turbine Building Flooding SDP: Cl Turbine Building Seismic Pipe Break Analysis. L-PI-10-005, Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems2010-02-18018 February 2010 Ninety-Day 1R26 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal & Containment Spray Systems ML1019703862009-12-31031 December 2009 Ground Water Investigation: an Improved Flow Net to Evaluate Pathways for a Potential Ground Water Release ML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. ML1002001322009-12-18018 December 2009 Report 0900634.402, Revision 2, Updated Leak-Before-Break Report for Prairie Island Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle. L-PI-09-115, Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 Radtrad and ARCON96 Input and Output Files in Support of License Amendment Request (LAR) to Adopt the Alternative Source Term Methodology ML1008406402009-09-11011 September 2009 Advisory Brief of Prairie Island Nuclear Generating Plant Study Group to State of Minnesota, Office of Administrative Hearings for the Public Utilities Commission, Sept. 11, 2009. Submitted with Comments on Draft Generic Environmental Impac L-PI-09-021, 2008 Unit 2 180-Day Steam Generator Tube Inspection Report2009-04-27027 April 2009 2008 Unit 2 180-Day Steam Generator Tube Inspection Report ML1020302362008-12-31031 December 2008 State of Wisconsin Prairie Island Environmental Radioactivity Survey ML0834701962008-11-21021 November 2008 PINGP - License Renewal; Radon Health Risks ML0834000702008-10-24024 October 2008 PINGP License Renewal: Wisconsin Department of Health Prairie Island Environmental Survey 2006. Reference 2008c L-PI-07-057, Corrections to Emergency Core Cooling System (ECCS) Evaluation Models2007-08-23023 August 2007 Corrections to Emergency Core Cooling System (ECCS) Evaluation Models IR 05000282/20053012005-09-30030 September 2005 Er 50-282-05-301 (DRS) and 50-306-05-301 (Drs), on 08/09-19/05, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant. Initial License Examination Report ML0520901582005-08-0202 August 2005 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment L-HU-05-012, Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 22005-06-0303 June 2005 Report of Unsatisfactory Blind Performance Testing Results, Monticello Nuclear Generating Plant & Prarie Island Nuclear Generating Plant, Units 1 and 2 ML0522700732005-04-18018 April 2005 Event Notification Report for April 18, 2005 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0514604942004-04-0909 April 2004 Licensee Root Cause Report, CAP55527, Industrial Safety Issues and Poor Work Practices During Nozzle Dam Installation, with R. Alexander'S (Riii) Notes ML0318909462003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Duane Arnold, K ML0310401092003-04-0404 April 2003 Steam Generator (#22) & Pressurizer Flaw Evaluations ML0205206392002-01-25025 January 2002 Fqa Methodology & Shutdown Margin During Physics Tests Methodology 2023-09-29
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Page 1 of 8 WISCONSIN DEPARTMENT OF HEALTH SERVICES Radiation About DHS Topics A - Z Programs & Services Partners & Providers Reference Center Links:
Environmental Monitoring Radon Mammography Tanning X-ray Radioactive Materials Radiation Protection Publications:
Notice to Employees Occupational Exposure Record State of Wisconsin - 2006 Prairie Island Environmental Radioactivity Survey Wisconsin Department of Health Services Division of Public Health Bureau of Environmental Health Radiation Protection Section P.O. Box 2659 Madison, Wisconsin 53701-2659 Table of Contents Introduction WI DHS Prairie Island Environmental Monitoring Sampling Program http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 2 of 8 samples of air, precipitation, ambient gamma radiation (TLD),
surface water, fish, soil, milk, well water and vegetation that are collected from selected locations at planned sampling intervals.
Table 1 is a listing of sampling sites and includes a description, direction and distance from the monitored power plant. Table 2 provides a listing of types of samples collected, sites where samples are collected, the number of samples collected, number of samples that were missed and a listing of the required analyses. Table 3 provides an explanation of missing samples or non-routine sample analyses. Figure 1 is a map showing the location of each environmental sampling site.
Program Modifications There were no program modifications for 2006.
Laboratory Services and Quality Assurance The analysis of the samples is performed under contract with the State Laboratory of Hygiene (SLH). SLH maintains a quality assurance program. Analytical procedures provide for routine replicate analyses to verify methods and instrument operation.
Traceable sources are used to regularly calibrate the counters and daily performance checks are made between calibrations. In addition, quality control charts are maintained on the counters.
SLH participates in the Environmental Resource Associates Proficiency Testing program and has performed satisfactorily over th t i d P fi i t ti lt il bl f th http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 3 of 8 is the "a priori" lower limit of detection as defined above, LLD as picocuries per unit mass or volume, is the standard deviation of the background counting rate sb or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, S is the self-absorption correction factor, is the radioactive decay constant for the particular d
radionuclide, and for environmental samples is the elapsed time between t sample collection, or end of the sample collection period, and time of counting.
Typical values for E, V, Y and dt have been used to calculate the LLD.
Reporting of Sample Analysis Results Results for specific analyses will be reported as either a less than (<) value or an actual activity value. The reporting of results in Table 4 under the heading Range and in Tables 5-14 are a posteriori calculations based on the actual analysis performed using the actual sample values for E, V, Y and dt. Typically the reported less than (<) results are lower than the required WI DHS LLD indicating that the required WI DHS LLD has been met.
An actual activity value will be accompanied by an uncertainty term for that analysis. The uncertainty term is a plus or minus counting uncertainty term at the 2 sigma (95%) confidence interval and is printed as (+- or +/-). Examples and explanations of data reporting are:
Example Nuclide Activity reported 1 137Cs < 10 pCi/liter 2 137Cs 15 + 3 pCi/liter In example 1 we can be 95% confident that the sample activity, if any, is less than the LLD of 10 pCi/liter. In example 2 we can be 95% confident that the actual sample activity is greater than the LLD for that analysis and is between 12 and 18 pCi/liter.
Results And Discussion Air Particulate http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 4 of 8 A summary of reported activities by WI DHS for air particulate samples is included in Table 4. Results from the individual sample analyses are listed in Tables 5-6.
From the individual activities or quarterly averages for gross beta activities it may be noted that there are no significant differences between sites at different distances from the Prairie Island facility.
With no significant difference with distance from the Prairie Island site, an increase in gross beta activity attributable to the Prairie Island plant operation is not evident.
The gamma isotopic analysis of the quarterly air particulate filter composites detected only small amounts of the radioisotopes listed in Table 4. Beryllium-7 (7Be), detected in all composites, is a naturally occurring radioisotope that is constantly produced through nuclear reactions between cosmic rays and nuclei in the atmosphere and is detected in air composites from other areas of the state.
Influence by the Prairie Island nuclear generating facility on air quality is not evident from air particulate analysis.
Air Iodine A summary of reported activities by WI DHS for air iodine samples is included in Table 4. Results from the individual sample analyses are listed in Table 5.
Air iodine measurements were all below the LLD of 0.07 pCi/m3 for all sites.
Direct Radiation - Thermoluminescent Dosimeters (TLD's)
A summary of reported activities by WI DHS for direct radiation is included in Table 4. Results from the individual sample analyses are listed in Table 7.
Direct radiation (TLD) data for 2006 from the WI DHS network was comparable for all sites. Significant differences in exposure were not noticed at different distances from the Prairie Island nuclear facility. The average quarterly exposure from the ten sites located within Wisconsin was 15.5 +/- 2.0 milliroentgens. The average quarterly exposure for 2006 is at background levels and is comparable to other areas within Wisconsin.
Precipitation A summary of reported activities by WI DHS for precipitation is included in Table 4. Results from the individual sample analyses are listed in Table 8.
The gross beta activity in precipitation was within the normal range of activity when compared to previous years data.
http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 5 of 8 Surface Water http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 6 of 8 Analysis of the vegetation samples showed no unusual activities.
The gamma isotopic analysis detected only small amounts of the 7
http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 7 of 8 http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008
Page 8 of 8 Back to top l Contact us l Disclaimer l Employment l Privacy notice l Site feedback Protecting and promoting the health and safety of the people of Wisconsin The Official Internet site of the Wisconsin Department of Health Services http://dhs.wisconsin.gov/dph_beh/EnvMonitoring/PrairieIsland/2007/PIsl2Survey06.htm 12/5/2008