NRC 2008-0098, 2007 Annual Monitoring Report (Revised)
| ML090080466 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/19/2008 |
| From: | Meyer L Florida Power & Light Energy Point Beach |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| NRC 2008-0098 | |
| Download: ML090080466 (169) | |
Text
a FPL Energy.
Point Beach Nuclear Plant FPL Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 December 19, 2008 NRC 2008-0098 10 CFR 50.36a 10 CFR 72.44 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266, 50-301, and 72-005 Renewed License Nos. DPR-24 and DPR-27 2007 Annual Monitoringq Report (Revised)
In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the revised Annual Monitoring Report for PBNP, Units 1 and 2, for the period January 1 through December 31, 2007.
The revised Annual Monitoring Report contains additional information in regard to the effluent impact upon the public as well as previously submitted information regarding plant releases, solid waste shipments, results from the radiological environmental monitoring program and miscellaneous reportable items during 2007. The report also covers the results of radiological monitoring of the PBNP Independent Spent Fuel Storage Installation (ISFSI) as required by 10 CFR 72.44.
This letter contains no new commitments and no revisions to existing commitments.
Very truly yours, FPL Energy Point Beach, LLC arryS Meyer Site Vice President Enclosure cc:
Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW American Nuclear Insurers WI Division of Public Health, Radiation Protection Section A~(g
~
I An FPL Group company
ANNUAL MONITORING REPORT 2007 (REVISED)
FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2),72-005 (ISFSI)
RENEWED LICENSE DPR-24 and DPR-27 January 1, 2007, through December 31, 2007
TABLE OF CONTENTS Summary 1
Part A: Effluent Monitoring 1.0 Introduction 3
2.0 Radioactive Liquid Releases 4
3.0 Radioactive Airborne Releases 9
4.0 Radioactive Solid Waste Shipments 13 5.0 Nonradioactive Chemical Releases 16 6.0 Circulating Water System Operation 17 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 18 Part C: Radiological Environmental Monitoring 8.0 Introduction 19 9.0 Program Description 20 10.0 Results 32 11.0 Discussion 36 12.0 REMP Conclusion 43 Part D: Groundwater Monitoring 13.0 Program Description 44 14.0 Results 45 15.0 Groundwater Summary 52 Appendix 1: Environmental, Inc. Midwest Laboratory, "Final Report-for Point Beach Nuclear Plant."
Appendix 2: Environmental, Inc. Midwest Laboratory, monthly groundwater results Appendix 3: University of Waterloo (Ontario) Environmental Isotope Laboratory, precipitation V,
LIST OF TABLES Table 2-1 Comparison of 2007 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 2-2 Summary of Circulating Water Discharge Table 2-3 Isotopic Composition of Circulating Water Discharges (Curies)
Table 2-4 Subsoil System Drains - Tritium Summary Table 3-1 Comparison of 2007 Airborne Effluent. Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 3-2 Radioactive Airborne Effluent Release Summary Table 3-3 Isotopic Composition of Airborne Releases Table 3-4 Total Particulate Curies Reported in Table 3-2 in Years 2000 - 2005 Corrected for F-18 Table 4-1 Quantities and Types of Waste Shipped from PBNP Table 4-2 2007 Estimated Solid Waste Major Radionuclide Composition Table 4-3 2007 PBNP Radioactive Waste Shipments Table 6-1 Circulating Water System Operation for 2007 Table 9-1 PBNP REMP Sample Analysis and Frequency Table 9-2 PBNP REMP Sampling Locations Table 9-3 ISFSI Sampling Sites Table 9-4 Minimum Acceptable Sample Size Table 9-5 Deviations from Scheduled Sampling and Frequency Table 9-6 Sample Collection for the State of Wisconsin Table 10-1 Summary of Radiological Environmental Monitoring Results for 2007 Table 10-2 ISFSI Fence TLD Results for 2007 Table 11-1 Average Indicator TLD Results from 1993-2007 Table 11-2 Average ISFSI Fence TLD Results (mR/7days)
Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days),
Table 11-4 Average Gross Beta Measurements in Air Table 11-5 Average Gross Beta Concentrations in Soil Table 14-1 Intermittent Streams and Bogs Table 14-2 2007 Beach Drain Tritium Table 14-3 U2 Facade Subsurface Drainage Sump H-3 Table 14-4 Yard Manhole Tritium Table 14-5 2007 Subsurface Drainage System H-3 Table 14-6 2007 Fagade Well Water Tritium Table 14-7 2007 Well Water Tritium Table 14-8 Precipitation H-3 4
6 7
18 10 10 1-1 12 13 14 15 17 22 23 27 27 28 29 34 36 36 37.
37 38 42 45 47 48 48 49 50 51 52 LIST OF FIGURES Figure 9-1 Figure 9-2 Figure 9-3 Figure 11-1 Figure 13-1 PBNP REMP. Sampling Sites Map of REMP. Sampling Sites Located Around PBNP Enhanced Map Showing REMP Sampling Sites Closest to PBNP 2007 Airborne Gross Beta Concentration (pCi/m 3) vs. Time Groundwater Monitoring Locations 24 25 26 39 46 ii
SUMMARY
The Annual Monitoring Report for the period from January 1, 2007 through December 31, 2007, is submitted in accordance with Point Beach Nuclear Plant (PBNP) Units 1 and 2, Technical Specification 5.6.2 and filed under Dockets 50-266 and 50-301 for Facility Operating Licenses DPR-24 and DPR-27, respectively. It also contains results of monitoring in'support of the Independent Spent Fuel Storage Installation (ISFSI) Docket 72-005. The report presents the results of effluent and environmental monitoring programs, solid waste shipments, nonradioactive chemical releases, and circulating water system operation.
During 2007, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:
Liquid Atmospheric Tritium (Ci) 588 86.2 1Particulate (Ci) 0.081 0.00003 Noble Gas (Ci) 0.656
(-)Noble gases in the liquids are added to the atmospheric release totals.
1Atmospheric particulate includes radioiodine (i-1 31, i-133).
For the purpose of compliance with the effluent design objectives of Appendix I to 10 CFR 50, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as-low as reasonably achievable (ALARA). The maximum annual calculated'doses in millirem (mrem) or millirad (mrad) areshown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I.
LIQUID RELEASES Dose Category Whole body dose Organ dose Calculated Dose 0.0062 mrem 0.0063 mrem Appendix I Dose 6 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Organ dose Noble gas beta air dose Noble gas gamma ray air dose Noble gas dose to the skin Noble gas dose to the whole body Calculated Dose 0.0344 mrem 0.00009 mrad 0.00025 mrad 0.00035 mrem 0.00023 mrem Appendix I Dose 30 mrem 40 mrad 20 mrad 30 mrem 10 mrem The results show that during 2007, the doses from PBNP effluents were a small percentage (0.11% at the most) of the Appendix I design objectives. Therefore, operation of PBNP' continues to be ALARA.
1
A survey of land use with respect to the location of dairy cattle was made pursuant to Section 2.5 of the PBNP Environmental Manual. As in previous years, no dairy cattle were found to be grazing at the site boundary. Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative.
The 2007 Radiological Environmental Monitoring Program (REMP) collected 823 samples for radiological analyses and 116 sets of thermoluminescent dosimeters (TLDs) to measure ambient radiation in the vicinity of PBNP and the ISFSI. Air monitoring from six different sites showed only background radioactivity from naturally occurring radionuclides. Terrestrial monitoring consisting of soil, vegetation, and milk found no influence from PBNP. Similarly, samples from the aquatic environment, consisting of lake and well water, fish, and algae, revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, the data show no plant effect on its environs.
There were no dry storage units added to the ISFSI in 2007. The total number remains at 25 dry storage casks. Sixteen are the ventilated, vertical storage casks (VSC-24) and nine are the NUHOMS, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSI showed no environmental impact from its operation.
The environmental monitoring conducted during 2007 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.
2
1.0 INTRODUCTION
The PBNP effluent monitoring program is designed to comply with federal regulations for ensuring the safe operation of PBNP with respect to releases of radioactive material to the environment and its subsequent impact on the public. Pursuant to 10 CFR 50.34a, operations should be conducted to keep the levels of radioactive material in effluents to unrestricted areas ALARA. In 10 CFR 50, Appendix I, the Nuclear Regulatory Commission (NRC) provides the numerical values for what it considers to be the appropriate ALARA design objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limits specified in 40 CFR 190.
10 CFR 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP. Airborne releases of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA. Prior to release, results of isotopic analyses are used to adjust the release rate of discrete volumes of liquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) such that the concentrations of radioactive material in the air and water beyond PBNP are below the PBNP Technical Specification concentration limits for liquid effluents and release rate limits for gaseous effluents.
Solid wastes are shipped offsite for disposal at NRC licensed facilities. The amount of radioactivity in the solid waste is determined prior to shipment in order to determine the proper shipping configuration as regulated by the Department of Transportation and the NRC.
Under the General License granted pursuant to 10 CFR 72.210, is an ISFSI. The release of radioactive materials from the operation of the ISFSI must also comply with the limits of Part 20 and Part 50 Appendix I design objectives. Per 10 CFR 72.44(d)(3),
the results of radiological effluent monitoring are to be reported annually. The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process will be assessed and quantified as part of the PBNP Radiological Effluent Control Program.
Holders of a Part 72 license are allowed to submit the report required by 72.44(d)(3) concurrent with the effluent report required by 10 CFR 50.36a (a)(2). (
Reference:
64 FR 33178) 3
will be assessed and quantified as part of the PBNP Radiological Effluent Control Program.
2.0 RADIOACTIVE LIQUID RELEASES The radioactive liquid release path to the environment is via the circulating water discharge. A liquid waste treatment system in conjunction with administrative controls is used to minimize the impact on the environment and maintain doses to the public ALARA from the liquid releases.
2.1 Doses From Liquid Effluent Doses from liquid effluent are calculated using the methodology of the Offsite Dose Calculation Manual (ODCM). These calculated doses use parameters such as the amount of radioactive material released, the total volume of liquid, the total volume of dilution water, and usage factors (e.g., water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. For compliance with 10 CFR 50, Appendix I design objectives, the annual dose is calculated to the hypothetical maximally exposed individual (MEI). The MEI is assumed to reside at the site boundary in the highest x/Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the MEI represents an individual with reasonable deviations from the average for the general population in the vicinity of PBNP. A comparison of the calculated doses to the 10 CFR 50, Appendix I design objectives is presented in Table 2-1. The conservatively calculated dose to the MEI is a very small fraction of the Appendix I design objective.
Table 2-1 Comparison of 2007 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem]
Highest Total Calculated Dose
% of Design
[mrem]
Objective 6 (whole body) 0.0062 0.10 %-
20 (any organ) 0.0063 0.03 %
4.
2.2 2007 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis and presented in Table 2-2. These releases are composed of processed waste, wastewater effluent, and blowdown from Units 1 and 2. The wastewater effluent consists of liquid from turbine hall sumps, plant well house backwashes, sewage treatment plant effluent, water treatment plant backwashes, and the Unit 1 and 2 facade sumps.
2.3 2007 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3. The noble gases released in liquids are reported with the airborne releases in Section 3. The isotopic distribution shows little change from 2006, with tritium down slightly from 2006 and close to 2005 value. Tritium continues to be the major radionuclide released via liquid discharges.
2.4 Beach Drain System Releases Tritium Summary The quarterly results of monitoring the beach drains are presented in Table 2-4.
These six drains are sampled once a month. The total monthly flow is calculated assuming that the flow rate at the time of sampling persists for the whole month.
During 2007, no tritium was observed in any of the beach drains at the effluent LLDs used to detect and quantify tritium released from discreet volumes such as hold up tanks and waste distillate tanks. However, these drains are subject to ground water inleakage so they are sampled as part of the ground water monitoring program. Results range from not detected (46 +/- 104 pCi/I) to a high of 683 +/- 102 pCi/I. Most results are in the 200 - 300 pCi/I range. Based on these environmental analyses of beach drain discharges and the associated monthly flows, 2.12 Ci of tritium would be added to the 588 Ci released via discharges for which permits are used. All of the ground water monitoring results are presented in Part D of this Annual Monitoring Report.
2.5 Changes to the Waste Liquid Treatment System in 2007 The wastewater treatment system serving the radiologically controlled area of the plant was modified by replacing the evaporator system with ion exchange system. The Advanced Liquid Processing System (ALPS) was added to the liquid waste treatment system in 2007. The ODCM (Figure 2-1) has been revised to reflect this change.
5
Table 2-2 Summary of Circulating Water Discharge January 1, 2007, through December 31, 2007 Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci)
Gamma Scan (+Fe-55) 5.55E-03 3.82E-04 2.17E-02 1.83E-02 7.33E-03 1.17E-02 6.50E-02 2.72E-03 2.25E-04 1.32E-03 2.15E-04 3.38E-03 7.68E-03 8.05E-02 Gross Alpha O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 3.51E-06 3.51E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 0.OOE+00 O.OOE+00 3.51E-06 Tritium 8.03E+01 6.44E+00 1.09E+02 2.60E+01 3.84E+01 3.44E+01 2.94E+02 2.71E+01 1.56E+01 8.58E+01 9.78E+00 5.82E+01 9.65E+01 5.88E+02 Strontium (89/90/92) 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+0O 9.36E-05 O.OOE+00 9.36E-05 Total Vol Released (gal)
Processed Waste 5.63E+04 1.72E+04 1.06E+05 1.06E+05 1.06E+05 4.42E+04 4.36E+05 6.39E+04 2.61E+04 4.24E+04 8.23E+03 3.16E+04 4.17E+04 6.50E+05 Waste Water Effluent*
4.55E+06 3.46E+06 4.71 E+06 3.61 E+06 3.66E+06 2.75E+06 2.27E+07 2.96E+-06 3.79E+06 3.99E+06 4.67E+06 5.01 E+06 5.23E+06 4.84E+07 U1 SG Blowdown 1.57E+06 1.54E+06 1.70E+06 8.80E+03 2.39E+06 1.88E+06 9.09e+06 2.68E+06 2.66E+06 2.33E+06 2.68E+06 2.46E+06 2.66E+06 2.46E+07 U2SG Blowdown 2.62E+06 2.40E+06 2.14E+06 1.58E+06 2.63E+06 2.07E+06 1.34E+07 2.12E+06 2.58E+06 2.08E+06 2.49E+06 2.46E+06 2.61E+06 2.78E+07 Total Gallons 8.80E+06 7.42E+06 8.66E+06 5.31E+06 8.78E+06 6.74E+06 4.57E+07 7.83E+06 9.07E+06 8.45E+06 9.85E+06 9.97E+06 1.05E+07 1.01E+08 Total cc 3.33E+10 2.81E+10 3.28E+10 2.01E+10 3.32E+10 2.55E+10 1.73E+11 2.96E+10 3.43E+10 3.20E+10 3.73E+10 3.77E+10 3.97E+10 3.84E+11 Vol of dilution water (cc)**
6.62E+13 5.98E+13 8.06E+13 5.74E+13 1.04E+14 1.OOE+14 4.68E+14 1.15E+14 1.15E+14 1.11E+14 1.13E+14 1.08E+14 6.68E+13 1.10E+15 Avg diluted discharge conc (pJCi/cc)
Gamma Scan (+Fe-55) 8.38E-11 6.39E-12 2.69E-10 3.19E-10 7.05E-11 1.17E-10 2.37E-11 1.96E-12 1.19E-11 1.90E-12 3.13E-11 1.15E-10 Gross Alpha O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 0.OOE+00 3.51E-14 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+0 0.OOE+00 Tritium 1.21E-06 1.08E-07 1.35E-06 4.53E-07 3.69E-07 3.44E-07 2.36E-07 1.36E-07 7.73E-07 8.65E-08 5.39E-07 1.44E-06 Strontium (89190/92)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 8.67E-13 O.OOE+00 Max Batch Discharge Conc (pCi/cc)
Tritium 4.62E-05 8.45E-06 3.66E-05 1.22E-05 1.78E-05 1.46E-05 1.02E-05 9.98E-06 1.54E-05 7.90E-06 1.27E-05 2.OOE-05 Gamma Scan 5.57E-09 2.32E-10 8.32E-09 1.01E-08 4.18E-09 1.64E-08 3.23E-09 2.04E-10 2.16E-10 6.46E-12 8.98E-10 1.97E-09
- The waste water effluent system replaced the Retention Pond which was taken out of service in September 2002.
- Circulating water discharge from both units.
Note: Dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries.
6
Table 2-3 Isotopic Composition of Circulating Water Discharges (Ci)
January, 2007 through December 31, 2007 Total
_Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 8.03E+01 6.44+00 1.09E+02 2.60E+01 3.84E+01 3.44E+01 2.94E+02 2.71E+01 1.56E+01 8.58E+01 9.78E+00 5.82E+01 9.65E+01 5.88E+02 F-18 1.53E-04 2.12E-04 3.11E-04 1.71E-04 3.11E-04 1.45E-04 1.30E-03 5.53E-04 4.62E-05 1.16E-04 2.07E-04 0.00E+00 2.29E-04 2.45E-03 Cr-51 4.11E-04 0.OOE+00 7.19E-04 6.67E-04 4.43E-04 5.33E-04 2.77E-03 9.02E-05 0.00E+00 0.OOE+00 0.00E+00 9.62E-05 1.46E-04 3.1OE-03 Mn-54 3.34E-05 0.00E+00 2.36E-05 7.65E-06 7.90E-06 8.90E-05 8.14E-05 2.87E-05 0.00E+00 0.OOE+00 0.00E+00 3.09E-06 1.11E-05 1.24E-04 Fe-55 0.OOE+00 0.OOE+00 4.43E-04 0.00E+00 3.06E-04 5.02E-03 5.77E-03 1.96E-04 0.00E+00 2.57E-04 0.OOE+00 0.OOE+00 0.OOE+00 6.22E-03 Fe-59 0.00E+00 0.00E+00 0.OOE+00 9.57E-05 2.29E-05 7.42E-05 1.93E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.93E-04 Co-57 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 2.21E-04, 4.14E-05 7.51E-04 8.29E-04 3.12E-03 9.23E-04 5.88E-03 1.91E-04 8.37E-06 5.30E-05 0.00E+00 2.71E-05 9.99E-05 6.26E-03 Co-60 6.53E-04 8.20E-05 7.03E-04 8.39E-04 4.05E-04 1.18E-03 3.86E-03 5.92E-04 1.10E-04 1.38E-04 6.39E-06 2.01E-04 5.40E-04 5.45E-03 Zn-65 0.OOE+00 0.OOE+00 4.62E-06 0.OOE+00 0.OOE+00 0.OOE+00 4.62E-06 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 4.62E-06 As-76 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.99E-05 0.OOE+00 1.99E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.99E-05 Sr-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.b0E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 9.36E-05 0.00E+00 9.36E-05 Nb-95 8.04E-05 0.00E+00 3.OOE-05 3.06E-05 8.79E-05 2.34E-05 2.52E-04 0.OOE+00 0.00E+00 3.71E-08 0.OOE+00 0.00E+00 1.86E-05 2.71E-04 Nb-97 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.83E-06 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 1.83E-06 Zr-95 3.30E-05 0.OOE+00 0.OOE+00 3.12E-06 9.21E-06 0.OOE+00 4.53E-05 0.00E+00 0.00E+00 O0OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.53E-05 Ag-110m 1.52E-04 3.21E-05 2.15E-04 1.75E-04 1.63E-04 2.68E-03 3.42E-03 1.OOE-03 6.05E-05 9.92E-05 1.60E-06 8.23E-05 7.89E-05 4.74E-03 Sn-113 1.21E-05 0.00E+00 6.76E-06 1.01E-05 3.36E-05 5.32E-05 1.16E-04 0.OOE+00 0.00E+00 1.16E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.17E-04 Sn-117m 1.46E-04 0.OOE+00 5.20E-05 1.19E-04 1.49E-03 2.90E-04 2.10E-03 1.41E-04 0.00E+00 2.35E-05 0.OOE+00 1.23E-06 6.53E-06 2.27E-03 Sb-122 0.OOE+00- 0.OOE+00 0.00E+00 1.27E-06 0.OOE+00 0.OOE+00 1.27E-06 1.20E-05 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1.33E-05 Sb-124 0.OOE+00 0.OOE+00 1.36E-04 0.OOE+00 3.19E-06 1.16E-04 2.55E-04 3.48E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.90E-04 Sb-125 3.63E-03 4.42E-06 1.83E-02 1.53E-02 9.00E-04 5.82E-04 3.87E-02 1.29E-04 0.OOE+00 6.12E-04 0.OOE+00 2.86E-03 6.54E-03 -4.88E-02 1-131 0.OOE+00 0.OOE+00 1.40E-05 0.OOE+00 0.OOE+00 0.00E+00 1.40E-05 0.OOE+00 0.00E+00 2.34E-05 0.OOE+00 0.OOE+00 0.OOE+00 3.74E-05 1-133 2.06E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.06E-05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.06E-05 Te-132 0.00E+00 0.00E+00 1.05E-05 3.66E-06 0.OOE+00 0.00E+00 1.42E-05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 9.04E+06 2.32E-05 Cs-137 1.11E-05 1.OQE-05 4.39E-06 4.66E-05 8.99E-06 1.94E-05 1.00E-04 3.83E-06 0.00E00 0.OOE+00.
0.OOE+00 0.00E+00 5.81E-07 1.04E-04 Ru-103 0.00E+00 0.OOE+00 0.00E+00 2.68E-06 0.OOE+00 0.OOE+00 2.68E-06 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 2.68E-06 Ru-106 0.OOE-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.49E-04 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 2.49E-04 Ba-140 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 000E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
.0.00E+00 0.O0E+00 1.79E-05 0.OOE+00 1.79E-05 W-187 0.OOE-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-131 0.OOE-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-1 33, Xe-1 35, etc.) are added to the atmospheric release summaries.
7
Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2007, through December 31, 2007 S-1 S-3 S-7 S-8 S-9 S-10 1st Qtr H-3 (Ci)
O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 Flow (gal) 2.15E+06 5.23E+05 0.OOE+00 6.70E+04 O0OOE+00 0.OOE+00 2nd Qtr H-3 (Ci)
O.OOE+00 O.OOE+00 O.00E+00 O.OOE+0 0.OOE+00 0.OOE+0O Flow (gal) 3.50E+05 1.97E+05 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+0O 3rd Qtr H-3 (Ci)
O.
00E+00 0.00E+O 0 O.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 Flow (gal) 3.13E+05 1.44E+05 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 4th Qtr H-3 (Ci) 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Flow (gal) 2.35E+05 1.OOE+05 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 2.6 Land Application of Sewage Sludge The Wisconsin Department of Natural Resources has approved the disposal of PBNP sewage by land application on various FPL Energy Point Beach, LLC properties surrounding the plant. This sewage sludge, which may contain trace amounts of radionuclides, is to be applied in accordance'with methodologies approved by the NRC on January 13, 1988, pursuant to 10 CFR 20.302(a). The approved methodology requires analyses prior to every disposal. Based upon an investigation, of the source of the radionuclides, a combination of engineering modifications and administrative controls has eliminated plant generated radiological inputs to the sewage. This was verified by sludge analyses using the environmental lower level of detection (LLD) criteria. No byproduct radionuclides were foundin the sludge after the controls and modifications were completed. Sludge is routinely monitored and no radionuclides attributable to PBNP have been found.
There was no disposal of sewage by land application during 2007. All disposals were done at the Manitowoc Sewage Treatment Plant.
8
3.0 RADIOACTIVE AIRBORNE RELEASES The release paths to the environment contributing to radioactive airborne release totals during this reporting period were the Auxiliary Building Vent Stack, the Drumming Area Vent Stack, the Letdown Gas Stripper, the Unit 1 Containment Purge Stack, and the Unit 2 Containment Purge Stack. A gaseous radioactive effluent treatment system in conjunction with administrative controls is used to minimize the impact on the environment from the airborne releases and maintain doses to the public ALARA.
3.1 Doses From Airborne Effluent Doses from airborne effluent are calculated for the MEI following the methodology contained in the PBNP ODCM. These calculated doses use parameters such as the amount of radioactive material released, the concentration at and beyond the site boundary, the average site weather conditions, the locations of the exposure pathways (e.g., cow milk, vegetable gardens and residences), and usage factors (e.g., breathing rates, food consumption). In addition to the MEI doses, the energy deposited in the air by noble gas beta particles and gamma rays is calculated and compared to the corresponding Appendix I design objectives. A comparison of the annual Appendix I design objectives for atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology is listed in Table 3-1. The doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA.
3.2 Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2007 are summarized in Table 3-2.
3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2007, from which the airborne doses were calculated, are presented in Table 3-3. When both the equipment hatch and the Elevation 66' hatch are open during an outage, there is a measurable, convective flow out the upper hatch. Because this air is not filtered, whatever is measured in containment air is assumed to be carried out the hatch, through the fagade, and into the environment thereby contributing to the particulate effluent and the calculated dose.
3.4 Corrections to Tables 3-2 and 3-3 (2000 through 2005)
During the years 2000 through 2005, F-1 8 was reported in Table 3-3 "Isotopic Composition of Airborne Releases," and used to calculate the total particulate curies released in Table 3-2, "Radioactive Airborne Effluent Release Summary."
Because particulate F-1 8 does not have to be used for dose calculations due to its short half-life, it should not have been reported in either table during those years. The curies of airborne particulates released have been recalculated. The originally reported values and the corrected particulate values are presented in Table 3-4.
9
Table 3-1 Comparison of 2007 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Appendix I Design January-December Percent of Appendix I Category Objective,
Calculated Dose Design Objective Particulate 30 mrem/organ 0.0344 mrem 0.115 Noble gas 40 mrad (beta air) 0.00009 mrad 0.000225 Noble gas 20 mrad (gamma air) 0.00025 mrad 0.00125 Noble gas 30 mrem/skin 0.00035 mrem 0.00117 Noble gas 1.0 mrem (whole body) 0[00023 mrem 0.0023 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2007, through December 31, 2007 Total Jan Feb Mar Apr May Jun J-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) 5.38E-05 O.OOE+00 2.04E-03 1.33E-03 2.56E-03 1.89E-03 7.87E-03 2.07E-04 O.OOE+00 3.48E-04 O.OOE+00 2.30E-04 3.89E-04 9.05E-03 Total Noble Gas (Ci)l 4.15E-02 5.OOE-02 5.15E-02 4.17E-02 5.36E-02 6.60E-02 3.04E-01 5.80E-02 4.12E-02 4.37E-02 5.72E-02 8.66E-02 6.53E-02 6.56E-01 Total Radioiodines (Ci) 1.08E-05 O.OOE+00 O.OOE+00 5.16E-06 O.OOE+00 O.OOE+00 1.60E-05 O.OOE+00 O.OOE+00 1.44E-05 O.OOE+00 O.OOE+00 O.OOE+00 3.04E-05 Total Particulate (Ci)2 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.65E-10 O.OOE+00 1.65E-10 Alpha (Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEOO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Strontium(Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 All other beta+ gamma (Ci) O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+OO OO.E+00 1.65E-10 O.OOE+00 1.65E-10 Total Tritium (Ci) 1.01E+01 6.05E+00 6.87E+00 9.36E+00 6.41E+00 4.56E+00 4,34E+01 4.73E+00 5.59E+00 6.43E+00 9.18E+00 8.60E+00 8.29E+00 8.62E+01 Max NG Hrly Rel.(Ci/sec) 4.08E-08 4.14E-08 4.07E-08 3.67E-08 7.12E-10 7.65E-08 I 6.63E-08 3.76E-08 3.95E-08 5.87E-08 2.85E-07 5.07E-08_
Total noble gas (airborne + liquid releases),
2 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or F-1 8. F-1 8 and other airborne particulates with half-lives <-8 days do not to be considered for dose calculations. Airborne radioiodines only include 1-131 and 1-133.
10
TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2007 through December 31, 2007 Jan Feb Mar Apr May Jun Semi-Jul Aug Sep Oct Nov Dec Total Nuclide (Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(Ci)
Annual (Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(Ci),
H-3 1.01 E+01 6.05E+00 6.87E+00 9.36E+00 6.41 E+00 4.56E+00 4.34E+01 4.73E+00 5.59E+00 6.43E+00 9.18E+00 8.60E+00 8.29E+00 8.62E+01 Ar-41 4.14E-02 4.92E-02 4.72E-02 3.83E-02 4.24E-02 4.31E-02 2.62E-01 4.60E-02 4.03E-02 4.05E-02 5.04E-02 5.21E-02 5.50E-02 5.46E-01 Kr-85 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.07E-04 0.OOE+00 2.07E-04 Kr-87 0.OOE+00 0.OOE+-00
.0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.64E-04.
0.OOE+00 4.64E-04 Kr-88 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.02E-03 0.OOE+00 2.02E-03 Xe-133 1.73E-04 8.28E-04 3.55E-03 3.38E-03 1.02E-02 2.27E-02 4!08E-02 1.20E-02 8.14E-04 2.75E-03 6.71E-03 2.65E-02 9.90E-03 9.95E-02 Xe-133m 0.OOE+00 0.OOE+00 2.86E-05 0.OOE+00 3.47E-05 0.OOE+00 6.33E-05 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.11E-04 0.00E+00 3.74E-04.
Xe-135 0.OOE+00 0.OOE+00 6.45E-04 1.46E-05 9.52E-04 1.79E-04 1.79E-03 2.43E-05 1.07E-04 4.23E-04 1.19E-04 1.95E-03 3.79E-04 4.79E-03 Xe-135m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.20E-05 0.OOE+00 9.01E-04 0.OOE+00 9.53E-04 Xe-138 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.17E-03 0.OOE+00 2.17E-03 Cr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Mn-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-57 0.OOE+00 0.OOE+00 0.O0E+0Q 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Zr-95 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ag-110m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E4-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sn-113 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sb-124 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
.0.OOE+00 0.OOE+00 0.00E+00.
0.OOE+00 0.OOE+00 Sb-1 25 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 1-131 7.08E-07 0.OOE+00 0.OOE+00 5.16E-06 0.OOE+00 0.OOE+00 5.87E-06 0.OOE+00 0.OOE+00 1.55E-06 0.OOE+00 0.OOE+00 0.OOE+00 7.42E-06 1-133 1.01E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.01E-05 0.OOE+00 0.OOE+00 1.29E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.30E-05 Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.65E-10 0.OOE+00 1.65E-10 Note: The Noble Gases listed above include the liquid contribution.
11
Table 3-4 Total Particulate Curies Reported in Table 3-2 in Years 2000 - 2005 Corrected for F-18 Jan Feb Mar Apr May Jun 2000 (Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(Ci)
Total Particulates 2(Ci) 2.91E-05 4.34E-06 2:.06E-06 l.OOEo o.ooE+00 1.1 OE-08I 2000 Corrected 2.91E-05 4.34E-06 1.01E-06 0.OOE+00 0.00E+00 1.10E-08 2001 Annual (Ci)
NR Jul Aug (Ci)
(Ci)
.OOE+00 I
.OOE+00 IO.OOE+001 0.00E+00I E
Sep (Ci) 6.35E-11 6.35E-11I Oct (Ci) 2.33E-05 2.33E-051 Nov (Ci) 8.67E-061 Dec (Ci) 6.38E-11 6.38E-1 1 Total (Ci) 6.68E-05 6.64E-05 Total Particulates 2(Ci) 5.66E-11 1 9.49E-04 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 5.08E-14 I NR I 2.85E-09 I 6.22E-04 I 1.03E-06 I 7.58E-08 I 2.50E-09 I 0.OOE+00 I 1.57E-03 2001 Corrected 5.66E-11 1.13E-05 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 1.03E-06 0.OOE+00 4.07E-10 0.OOE+00 1.23E-05 2002 Total Particulates 2(Ci) I 0.00E-001 0.OOE+00I o.ooE+001 5.50E-061 4.08E-061 2.09E-101 NR I0.00E+00I 0.OOE+00 1.25E-071 3.77E-061 3o04E-071 o.oIE+00o 1.38E-05o o
12002 Corrected I 0.00E+00 0.OOE+'00 0.OOE+00 5.50E-06 1.25E-10 0.OOE+00 0.00E+00 0.OOE+00 1.25E-07 3.77E-06 3.04E-07 0.OOE+00 9.70E-06 2003 Total Particulates 2(Ci) 0.OOE+00 I.OOE+00 I.OOE+00 I-o3.12E-05 I 1.10E-05 I 3.62E-05 I NR I 8.57E-06 I.OOE+00 I o.OOE+00 I 0.OOE+00 I o.OOE+00 I 0.OOE+00 I 8.80E-05 2003 Corrected 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 8.56E-06 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 -8.56E-06 2004 ITotal ParticulateS2(Ci) 0.OOE+00 I1.28E-10 I1.17E-06 I1.84E-08 1.39E-08 8.94E-12 I1.20E-06 I 0.OOE+00 I.OOE+00 I.OOE+00 I.OOE+00 I.OOE+00 I0.OOE+0o 1.20E-06 2004 Corrected 0.00E+00 0.OOE+00 0.OOE+00 1.84E-08 1.39E-08 8.94E-12 3.23E-08 0.OOE+00 0.OOE+00 0OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.23E-08 2005 Total Particulates 2(Ci)
O.OOE+00 1.27E-07 0.OOE+00 0.OOE+00 8.89E-10 1.13E-05 1.14E-05 6.95E-05 5.OOE-01 1.01E-07 2.60E-04 3.95E-08 5.35E-04 5.01E-01 12005 Corrected I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 3.15E-06 3.15E-06 6.96E-07 8.98E-07 7.86E-08 6.59E-05 3.95E-08 0.OOE+00 7.08E-05 I 2 Total is the sum of alpha, strontium, and others NR = not reported in Table 3-2 those years.
4 12
4.0
- RADIOACTIVE SOLID WASTE SHIPMENTS 4.1 Types, Volumes, and Activity of Shipped Solid Waste The following types, -volumes, and activity of solid waste were, shipped from PBNP for offsite disposal or burial during 2007. No types C or D were shipped.
No irradiated fuel was shipped offsite. The volume, activity, and type of waste are listed in Table 4-1.
Table 4-1 Quantities and Types of Waste Shipped from PBNP Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc.
4.100 m3 30.122 Ci 145.00 ft3 B. Dry compressible waste, contaminated equipment, etc 248 m3 0.235 Ci 8752 ft 3
C. Irradiated components, control rods, etc.
0.00 m3 N/A Ci 0.00 ft3 D. Other 0.00 m3 N/A Ci 0.00 ft3 '
4.2 Maior Nuclide Composition (by Type of Waste)
The major radionuclide content of the 2007 solid waste was determined' by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-2.
13
Table 4-2 2007 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B TYPE C TYPE D
- Percent Percent Percent
- Percent Nuclide Abundance Nuclide Abundance Nuclide Abundance Nuclide Abundance Ni-63 73.7%
Ni-63 23.7%
Co-60 14.5%
Co-58 15.8%
Cs-1 37 5.9%
Fe-55 15.0%
Fe-55 3.0%
Co-60 13.0%
Ni-59 0.8%
Nb-95 12.7%
Sb-125 0.6%
Ag-11Om 5.3%
Co-57 0.5%
Zr-95 4.3%
Cs-134 0.5%
Sb-125 4.2%
Mn-54 0.1%
Cr-51
,1.9%
Ag-11Om 0.1%
Ru-106 1.8%
Sr-90 0.1%
Mn-54 1.8%
Pu-241 0.1%
H-3 0.2%
Ce-144 0.1%
Cs-137 0.2%
Co-58 0.1%
Tc-99 0.0%
Am-241 0.0%
Zn-65 0.0%
Pu-238 0.0%
Pu-241 0.0%
Cm-243 0.0%
Ce-144 0.0%
H-3 0.0%
Sr-90 0.0%
Cm-244 0.0%
Am-241 0.0%
Tc-99 0.0%
Cm-242 0.0%
Pu-239 0.0%
Cm-243 0.0%
Pu-240 0.0%
Cm-244 0.0%
Sr-89 0.b%
Pu-238 0.0%
1-129 0.0%
Pu-239 0.0%
Cm-242 0.0%
Pu-240 0.0%
14
4.3 Solid Waste Disposition There were nine solid waste shipments from PBNP during 2007. The dates and destinations are shown in Table 4-3.
Table 4-3 2007 PBNP Radioactive Waste Shipments Date Destination 1/9/2007 Oak Ridge, TN 2/19/2007 Erwin, TN 4/10/2007; Oak Ridge, TN 4/10/2007 Oak Ridge, TN 4/29/2007 Oak Ridge, TN
-5/3/2007 Oak Ridge, TN 5/14/2007 Memphis, TN 7/17/2007 Oak Ridge, TN 11/28/2007 Erwin, TN 15
5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2007, to June 30, 2007, included 5.96E+05 gallons of neutralized wastewater. The wastewater contained 4.06E+00 pounds of suspended solids and 2.86E+02 pounds of dissolved solids.
Scheduled chemical waste releases to the circulating water system from July 1, 2007, to December 31, 2007, included 7.53E+05 gallons of neutralized wastewater. The wastewater contained 1.32E+01 pounds of suspended solids and 2.62E+04 pounds of dissolved solids.
Scheduled chemical waste releases are based on the average analytical results obtained from' sampling a representative number of neutralizing tanks.
5.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for January 1, 2007, to'June 30, 2007, included 2.36E+07 gallons of clarified wastewater. The wastewater contained 2.34E+03 pounds of suspended solids.
Miscellaneous chemical waste releases from the Wastewater Effluent (based on effluent analyses) to the circulating water for July 1, 2007, to December 31, 2007, included 2.59E+07 gallons of clarified wastewater. The wastewater contained 2.68E+03 pounds of suspended solids.
Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2007, to June 30, 2007, included 2.57E+05 pounds of sodium bisulfite and 2.40E+05 pounds of sodium hypochlorite.
Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2007, to December 31, 2007, included 4.39E+05 pounds of sodium bisulfite and 4.21 E+05 pounds of sodium hypochlorite.
16
6.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 6-1.
Table 6-1 Circulating Water System Operation for 2007 UNIT JAN FEB MAR APR*
MAY JUN Average Volume Cooling 1
282.2 282.2 350.9 156.2 425.6 390.5 Water Discharge [million gal/day]**
2 282.2 282.2 336.5 494.4 468.3 490.4 Average Cooling Water 1
37.0 37.6 38.4 42.8 48.0 48.3 Intake Temperature [OF]
2 37.0 37.6 38.2 41.1 47.5 48.9 Average Cooling Water 1
69.3 70.0 67.0 43.7 63.5 60.1 Discharge Temperature [OF]
2
.70.1 70.7 66.7 60.3 67.0 68.1 Average Ambient Lake Temperature [OF]
35ýO 36.5 36.9 40.6 46.1 46.1 Unit 1 outage 4/2 - 5/5.
- For days with cooling water discharge flow.
Table 6-1 (continued)
Circulating Water System Operation for 2007 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1
489.6 489.6 489.6 485.9 456.0-281.9 Water Discharge [million gal/day]**
2 489.6 489.6 489.6 479.4 490.5 286.8 Average Cooling Water 1
55.1 65.3 52'.8 53.5 43.1 36.9 Intake Temperature [OF]
2 55.7 65.9 53.2 53.9 43.1 37.3 Average Cooling Water 1
73.9 84.4 71.7 72.8 63.8 69.0 Discharge Temperature [OF]
2 74.6 85.4 72.3 73.6 62.3 70.6 Average Ambient Lake Temperature [OF]
52.4 60.7 48.6 50.8 40.2 34.0
- For days with cooling water discharge flow.
17
Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The ODCM was revised in 2007 to include the modification (ALPS - Advanced Liquid Processing System) to the liquid waste treatment system.
The wastewater treatment system that serves the radiologically controlled area of the plant has been modified by replacing the evaporator system with an ion exchange system.
7.2 Interlaboratory Comparison Program Environmental, Inc, Midwest Laboratory, the analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples, participated in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) as well as in the interlaboratory comparison studies administered by Environmental Resources Associates (ERA) during 2007. The ERA environmental crosscheck' program replaces the Environmental Measurements Laboratory (EML) Quality Assessment Program which was discontinued. The results of these comparisons can be found in Appendix A of the AMR.
7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2007.
18
Part C RADIOLOGICAL ENVIRONMENTAL MONITORING
8.0 INTRODUCTION
The objective of the PBNP REMP is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To this end, the REMP collects and analyzes air, water, milk, soil, vegetation, and fish samples for radionuclides and uses TLDs to determine the ambient radiation background.
These measurements also serve as a check of the efficacy of PBNP effluent controls. The REMP fulfills the requirements of 10 CFR 20.1302, PBNP General Design Criterion (GDC) 17, GDC 64 of Appendix A to 10 CFR 50, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant.
Therefore, the REMP collects samples from various environmental media in order to provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure.
A subset of the PBNP REMP samples, consisting of air, soil, and vegetation, also fulfills 10CFR 72.44(d)(2) for operation of the ISFSI. Additionally, TLDs provide the means to measure changes in the ambient environmental radiation levels at sites near the ISFSI and at the PBNP site boundary to ensure that radiation levels from the ISFSI are maintained within the dose limits of 10 CFR 72.104. Because the ISFSI is within the PBNP site boundary, radiation doses from PBNP and the ISFSI, combined, must be used to assess compliance with 10 CFR 72.122 and 40 CFR 190. Therefore, radiological environmental monitoring for the ISFSI is provided by selected sampling sites, which are part of the PBNP REMP.
For the aquatic environment, the samples include water as well as the biological integrators, such as fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In contrast, the filamentous algae periphyton is attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; whereas analysis of fish and filamentous algae yield concentrations integrated over time.
The air-grass-cow-milk exposure pathway unites the terrestrial and atmospheric environments. This pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses, and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remain conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary, the highest depositional sector. In addition, soil samples are collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP.
19
For the measurement of ambient environmental radiation levels that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs situated around PBNP and the ISFSI.
9.0 PROGRAM DESCRIPTION 9.1 Results Reportingq Convention The vendor used by PBNP to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required LLD as specified in Table 2-2 of the Environmental Manual for each sample.
The report provided by the vendor (see Appendix 1) contains values, which can be either negative, positive or zero plus/minus the two sigma counting uncertainty, which provides the 95% confidence level for the measured value.
The LLD is an a priori concentration value that specifies the performance capability of the counting system used in the analyses of the REMP samples.
The parameters for the a priori LLD are chosen such that only a five percent chance exists of falsely concluding a specific radionuclide is present when it is not present at the specified LLD. Based on detector efficiency and average background activity, the time needed to count the sample in order to achieve the desired LLD depends upon the sample size. Hence, the desired LLD may be achieved by adjusting various parameters. When a suite of radionuclides are required to be quantified in an environmental sample such as lake water, the count time used is that required to achieve the LLD for the radionuclide with the longest counting time. Therefore, in fulfilling the requirement for the most difficult to achieve radionuclide LLD, the probability of detecting the other radionuclides is increased because the counting time used is longer than that required to achieve the remaining radionuclide LLDs.
The REMP results in this report are reported as averages of the measurements made throughout the calendar year plus/minus the associated standard deviation. If all net sample concentrations are equal to or less than zero, the result is reported as "Not Detectable" (ND), indicating no detectable level of activity present in the sample. If any of the net sample concentrations indicate a positive result statistically greater than zero, all of the data reported are used to generate the reported statistics. Because of the statistical nature of radioactive decay, when the radionuclide of interest is not present in the sample, negative and positive results centered about zero will be seen. Excluding validly measured concentrations, whether negative or as small positive values below the LLD, artificially inflates the calculated average value. Therefore, all generated data are used to calculate the statistical values (i.e., average, standard deviation) presented in this report. The calculated average may be a negative number.
Just because a result is statistically greater than zero does not necessarily indicate that the radionuclide is present in an environmental sample. False positives may be obtained by fluctuations in background during the counting process. This phenomenon is most prevalent for concentrations at or near the LLD. Therefore, other information such as PBNP emissions records and 20
radionuclide half-life must be used to evaluate whether the result is real or a statistical artifact.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A key interpretive aid in assessment of these effects is the design of the PBNP REMP, which is based upon the indicator-control concept.
Most types of samples are collected at both indicator locations and at control locations. A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuation in radiation levels arising from other sources.
9.2 Sampling Parameters Samples are collected and analyzed at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1, 9-2, and 9-3. (The latter two figures show sampling locations not shown in preceding figures due to space limitations. The location of the former retention pond, retired and remediated to NRC unrestricted access criteria, is indicated in Figure 9-3). The list of PBNP REMP sampling sites used to determine environmental impact around the ISFSI is found in Table 9-3. The minimum acceptable sample size is found in Table 9-4. In addition, Table 9-1 indicates the collection and analysis frequency of the ISFSI fence TLDs.
9.3 Deviations from Required Collection Frequency Deviations from the collection frequency given in Table 9-1 are allowed because of hazardous conditions, automatic sampler malfunction, seasonal unavailability, and other legitimate reasons (Section 2.2.6 of the Environmental Manual).
Table 9-5 lists the deviations from the scheduled sampling frequency that occurred during the reporting period.
9.4 Assistance to the State of Wisconsin The Radiation Protection Unit of the Wisconsin Department of Health and Family Services maintains a radiological environmental monitoring program to confirm the results from the PBNP REMP. As a courtesy to the State of Wisconsin, PBNP personnel also collect certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located.
9.5 Proqram Modifications No changes were made to the REMP during 2007. Changes to the Ground Water Monitoring Program are discussed in Part D.
21
Table 9-1 PBNP REMP Sample Analysis and Frequency Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05 TLD Quarterly Exposure
-06, -07, -08, -09, -12
-14, -15, -16, -17, -18,
-20, -22, -23, -24, -25,
-26, -27, -28, -29, -30,
-31, -32, -38, -39, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3x/yr as available
-08, -09, -20, Gamma Isotopic Analysis Algae E-05, -12 Gross Beta 3x/yr as available Gamma Isotopic Analysis Fish E-1 3 Gross Beta 3x/yr as available Gamma Isotopic Analysis (Analysis of edible.
portions only)
Well Water E-10 Gross Beta, H-3 Quarterly Sr-89, 90,1-131 Gamma Isotopic Analysis (on total solids)
Lake Water E-01, -05, -06, -33 Gross Beta Monthly / Quarterly composite of monthly collections 1-131 Monthly Gamma Isotopic Analysis Monthly (on total solids)
Milk E-11, -40, -21 Sr-89, 90 Monthly 1-131 Gamma Isotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)
-08, -20 1-131 Weekly (charcoal)
Gamma Isotopic Analysis Quarterly (on composite particulate filters)
Soil E-01, -02, -03, -04, Gross Beta 2x/yr Gamma Isotopic
-06, -08, -09, -20, Analysis Shoreline Sediment E-01, -05, -0.6, -12, -33, Gross Beta 2x/yr Gamma Isotopic Analysis ISFSI Ambient North, East, South, Radiation West' TLD Quarterly Exposure.
Fence Sections 22
Table 9-2 PBNP REMP Sampling Locations Location Code Location Description E-01 Primary Meteorological Tower South of the Plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on E-06 Telephone pole E-07 WPSC Substation on County V, about 0.5 Miles West of Hwy 42 E-08 G.J. Francar Pr~operty at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-1 1 Dairy Farm about 3.75 Miles West of Site
- E-12 Discharge Flume/Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-1 5 Southwest Corner of Site E-16 WSW, Hwy 42, a residence about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection E-1 8 Northwest of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles Southwest, at Silver Lake College E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road E-25, South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 -Miles WSW E-28 TLD site on western most pole between the 2nd and 3rd parking lots.
E-29 Area of North Meteorological Tower.
E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads.
E-31 On utility pole North side of Tapawingo Road closest to the gate at the West property line.
E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers.
Lake Michigan shoreline accessed from the SE corner of KNPP parking lot. Sample South of E-33 creek.
E-38 Tree located at the West end of the area previously containing the Retention Pond.
E-39 Tree located at the East end of the area previously, containing the Retention Pond.
E-40 Local Dairy Farm, W side of Hwy 42, about 1.8 miles north of the Nuclear Rd intersection E-TC Transportation Control; Reserved for TLDs 23
It.
M1 M]
f2 M1
-9 C4-C 13 POINT BEACH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SITES 0
1 MILE KILOMETER 0
Figure 9-1 PBNP REMP Sampling Sites 24
S.I TE MAP POINT BEACH NUCLEAR PLANT FIGURE 2-lb SCAL E 069 am 16 I4 I
FEET 40 1200 2000 MONITORING STATIONS STLtD 13 TLD & AIR Ah.
OTHER COS FILE 10T48 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 25
FImUIf 2-ic LAKE E-29
'MICH [IAN FORMER RErU4rTIO BA I TRAJNING LEtNVIRMiEJJTA MIOTORINC SIATIOtJS
.0 LOrL A -FDREl Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 26
Table 9-3
'ISFSI Sampling Sites Ambient Radiation Monitoring (TLD)
Soil, Vegetation, and Airborne Monitoring E-03 E-02 E-28 E-03 E-29 E-04 E-30 E-31 E-32 Table 9-4 Minimum Acceptable Sample Size Sample Type Size Vegetation 100-1000 grams Lake Water 8 liters Air Filters 250 m3 (volume of air)
Well Water 8 liters Milk 8 liters Algae 100-1000 grams Fish (edible portions) 1000 grams I
Soil 500-1000 grams Shoreline Sediment 500-1000 grams 27
Table 9-5 Deviations from Scheduled Sampling and Frequency Sample Location.
Collection Reason for not conducting Plans for Preventing Recurrence Type Date REMP as required AP/AI.
E-02 10/25/2007, Pump Not Running Unknown Reason E-02 10/31/2007 Pump Not Running Unknown Reason Lake E-05 2/15/07 Lake Frozen Samples Collected Next Month After Thaw Water E-06 2/15/07 Lake Frozen Samples Collected Next Month After Thiaw Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 Weekly, Composited Monthly Air Filters E-07 Weekly E-08 Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-1 1 Monthly E-1 9 Well Water E-10 Twice per year 28
9.6 Analytical Parameters The types of analyses and their frequencies are given in Table 9-1. The LLDs for the various analyses are found in the Section 10 (Table 10-1) with the summary of the REMP results. All environmental LLDs listed in Table 2-2 of the Environmental Manual (also in Table 10-1) were achieved during 2007.
9.7 Description of Analytical Parameters in Table 9-1 9.7.1 Gamma isotopic analysis Gamma isotopic analysis consists of a computerized scan of the gamma ray spectrum from 80 keV to 2048 keV. Specifically included in the scan are Mn-54, Fe-59, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, other detected nuclear power plant produced radionuclides also are noted.
The above radionuclides detected by gamma isotopic analysis are decay corrected to the time of collection. Frequently detected, but not normally reported in this Annual Monitoring Report, are the naturally occurring radionuclides Ra-226, Bi-214, Pb-212, TI-208, Ac-228, Be-7, and K-40.
9.7.2 Gross Beta Analysis
- Gross beta analysis is a non-specific analysis that consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick method of screening samples for the presence of elevated activity that may require additional, immediate analyses.
9.7.3 Water Samples Water samples include both Lake Michigan and well water. The Lake Michigan samples are collected along the shoreline at two locations north and two locations south of PBNP. The well water is sampled from the on-site PBNP well. Gross beta and gamma isotopic analytical results for water are obtained by measurements on the solids remaining after evaporation of the unfiltered sample to dryness. Hence, the results are indicated as "on total solids" in Table 10-1.
9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity-that may require immediate investigation. *Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-134,and Cs-137. Charcoal canisters for radioiodine are counted as soon as possible so the 1-131 will undergo only minimal decayprior to analyses. The weekly charcoal canisters are screened for 1-131 by 29
counting them at the same time to achieve a lower LLD. If a positive result is obtained, each canister is counted individually.
In order to ensure that the air sampling pumps are operating satisfactorily, a gross leak check is performed weekly. The pumps are changed out annually for calibration and maintenance beyond what can be accomplished in the field.
9.7.5 Vegetation Vegetation samples consist predominantly of green, growing plant material (grasses and weeds most likely to be eaten by cattle if they were present at the sampling site). Care is taken not to include dirt associated with roots by cutting the vegetation off above the soil line.
9.7.6 Environmental Radiation Exposure The 2007 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material (calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them.
Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data were obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. As seen in 2001, the Environmental Inc. TLD cards typically produce a slightly higher measured exposure value, although within the uncertainty of that value recorded by the TLD chips.
The reported field exposure is the arithmetic average of the four exposure values obtained minus the exposure received while the field TLD is in storage and transit.
The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per seven days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from the laboratory. The doses recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose.
30
9.7.7 ISFSI Ambient Radiation Exposure Although the ISFSI fence TLDs are not considered part of the REMP because of their location directly on site, their results can be used indirectly to determine whether the operation of the ISFSI is having an impact on the ambient environmental radiation beyond the site boundary.
Impacts are determined by comparison of fence TLD results to the results of the monitoring at PBNP site boundary and other selected locations.
10.0 RESULTS Summary of 2007 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2007, through December 31, 2007, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, and vegetation as well as TLDs. The results are summarized in Table 10-1.
Table 10-1 contains the following information:
Sample: Type of the sample medium
==
Description:==
Type of measurement LLD:
a priori lower limit of detection N:
Number of samples analyzed Average:
Average value +/- the standard deviation of N samples High:
'Highest measured value +/- it's associated 2 sigma counting error Units:
Units of measurement For certain analyses, an LLD, which is lower than that required by REMP, is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11). Blank values have not been subtracted from the results presented in Table 10-1. A complete listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in the Appendix.
In Table 10-1, no results are reported as <LLD. A ND radionuclide is one for which none of the individual measurements was statistically different from zero. When one or more of the measured radionuclide concentrations was positive and statistically different from zero, the average reported in Table 10-1 is the average +/- one standard deviation.
Both the positive and negative results were used to calculate the average and standard deviation. Some of the reported averages are negative because many of the measured concentrations for that sample category were negative. The highest positive value and its 2-sigma error are reported only when one or more measured values are statistically greater than zero based on counting statistics.
31
The method of determining averages follows.the recommendation made in NUREG-0475 (1978) "Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report," and in Health Physics Society Committee Report HPSR-1 (1980) "Upgrading Environmental Radiation Data" released as document EPA 520/1-80-012 and in more recent documents such as ANSI N42.23-1996, "Instrument Quality Assurance for Radioassay Laboratories;" ANSI N13.30-1996, "Performance Criteria for Radiobioassay;" DE91-013607, "Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance" and NUREG-1576 "Multi-Agency Radiological Laboratory Analytical Protocols Manual."
Table 10-2 contains the ISFSI fence TLD results.
32
Table 10-1 Summary of Radiological Environmental Monitoring Results for 2007 Average +/- Standard Sample Description N
LLD (a)
Deviation (b)
High + 2 sigma Units TLD Environmental Radiation 112 1 mrem 1.08 +/- 0.20 1.68 +/- 0.09 mR/7days Control (E720) 4 1 mrem 1.05 +/- 0.15 1.21 +/- 0.10 mR/7days Air Gross Beta 263 0.01 0.025 +/- 0.009 0.054 +/- 0.004 pCi/m3 Control (E-20) Gross beta 53 0.01 0.026 +/- 0.009 0.057 +/- 0.004 pCi/m3 1-131 263 0.030 (0.07)
ND pCi/m3 Control (E-20) 1-131 53 0.030 (0.07)
ND pCi/m3 Cs-1 34 20 0.05 ND pCi/m3 Control (E-20) Cs-134 4
0.05 ND pCi/m3 Cs-137 20 0.06 0.0000 +/- 0.0003 0.0007
+/- 0.0006 pCi/m3 Control (E-20) Cs-137 4-
- 0.06 ND pCi/m3 Other gamma emitters 20 0.1 0.0001 +/- 0.0004 0.0005
+/- 0.0004 pCi/m3 Control (E-20) Other 4
0.1 0.0003, +/- 0.0004 0.0007 + 0.0004 pCi/m3 Milk Sr-89 36 5
ND pCi/L Sr-90 36 1
0.8 +/- 0.4 2.0 + 0.5 pCi/L 1-131 36 0.5 ND pCi/L Cs-134 36 5 (15)
ND pCi/L Cs-137 36 5 (15)
ND
, pCi/L Ba-La-140 36 5 (15)
ND pCi/L Other gamma emitters 36 15 ND pCi/L Well Gross beta 4
4.,
1.4 +/- 1.4 2.9 + 1.4 pCi/L Water H-3 4
500 (3000)
IND pCi/L Sr-89 4
10 0.1 +/- 0.3 0.5 + 0.4 pCi/L Sr-90 4
1 (2)
ND pCi/L 1-131 4
0.5 (2)
ND pCi/L Mn-54 4
10(15)
ND pCi/L Fe-59 4
30 ND pCi/L Co-58 4
15 ND '
pCi/L Co-60 4
15 ND pCi/L Zn-65 4
30 ND pCi/L Zr-Nb-95 4
15 ND pCi/L Cs-134 4
15 ND pCi/L Cs-137 4
18 ND pCi/L Ba-La-140 4,
15 ND pCi/L Other gamma emitters 4
30 ND pCi/L Algae Gross beta 6
0.25 6.35 +/- 2.44 9.58 +/- 0.71 pCi/g Co-58 6
0.25
-0.010 +/- 0.018 0.019 +/- 0.014 pCi/g Co-60 6
0.25 0.007 +/- 0.011 0.017 +/- 0.012 pCi/g Cs-134 6
0.25 ND pCi/g Cs-137 6
0.25 0.014 + 0.013 0.026 + 0.018 pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.
(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equivalent to zero.
33
Table 10-1 (continued)
Summary of Radiological Environmental Monitoring Results for 2007 Average +/- Standard Sample Description N
LLD (a)
Deviation (b)
High +/- 2 sigma
- Units Lake Water Gross beta 46 4
2.9 +/- 1.5 9.7 +/- 1.3
' pCi/L 1-131 46 0.5 (2)
ND pCi/L Mn-54 46 10(15) 0.2 +/- 1.3 2.7 +/- 2.0 pCi/L Fe-59 46 30
-0.3 +/- 2.7 9.4 +/- 6.5 pCi/L Co-58 46 15 0.3 +/- 1.5 3.2 + 2.5 pCi/L Co-60 46 15 ND pCi/L Zn-65 46 30 ND pCi/L.
Zr-Nb-95 46 15 0.2 +/- 1.5 3.3 + 2.2 pCi/L Cs-134 46 10(15)
ND pCi/L Cs-1 37 46 10(18) 0.1 +/- 1.6 3.4 + 2.5 pCi/L Ba-La-140 46 15 0.0 +/- 3 8.3 + 4.5 pCi/L Ru-103 (Other gamma) 46 30 ND pCi/L Sr-89 16 5
0.00 +/- 0.56 1.34 0.99 pCi/L Sr-90 16 1 (2) 0.29 +/- 0.19 0.56 +/-+ 0.41 pCi/L H-3 16 500 (3000) 17 +/- 82 171 +/- 96 pCi/L Fish Gross beta 9
0.5 4.18 +/- 0.80 5.29 +/- 0.11 pCi/g Mn-54 9
0.13 ND pCi/g Fe-59 9
0.26 ND pCi/g Co-58 9
0.13 0.004 +/- 0.007 0.016 + 0.008 pCi/g Co-60 9
0.13 ND pCi/g Zn-65 9
0.26 0.000 +/- 0.019 0.027 + 0.015 pCi/g Cs-1 34 9
0 13
-0.002 +/- 0.005 0.007 +/- 0.006 pCi/g Cs-1 37 9
0.15 0.029 +/- 0.013 0.049-0.014 pCi/g SOther gamma emitters 9
0.5 ND pCi/g Shoreline Gross beta 10 2
14.27 +/- 3.62 19.90 + 1.51 pCi/g Sediment Cs-137 10 0.15 0.020+/- 0.012 0.041 +/- 0.020 pCi/g Soil Gross beta 16 2
31.00 + 5.41 38.35 +/- 2.87 pCi/g Cs-137 16 0.15 0.20 +/- 0.08 0.35 +/- 0.04 pCi/g Vegetation Gross.beta 24 0.25 8.00 +/- 1.79 11.72 + 0.33 pCi/g 1-131-24 0.06 0.000 + 0.013 0.029 + 0.011 pCi/g Cs-1 34 24 0.06 ND pCi/g Cs-1 37 24 0.08 0.011 +/- 0.025 0.110 + 0.030 pCi/g Other gamma emitters 24 0.06 ND pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.
(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero.
Other gamma emitters typically refer to Co-60 if not specifically called out in the analyses.
See explanation on page 1 of the Environmental Inc report which is Appendix A of this Annual Monitoring Report.
34
Table 10-2 ISFSI Fence TLD Results for 2007 Fence Location Average +/- Standard Deviation North 2.72
+/- 0.39 mR/7 days East 2.23
+/- 0.32 mR/7 days South 1.34
+/- 0.14 mR/7 days West 5.47
+/- 0.55 mR/7 days 11.0 DISCUSSION 11.1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring four - five miles from the plant, at special interest areas, and at one control location, roughly 17 miles southwest of the plant. The average of the indicator TLD cards is 1.08 mR/7-days and 1.05 mR/7-days at the control location. These results are not significantly different from each other nor from those observed from 2001 through 2006 (tabulated below in Table 11-1). The change in TLD types in 2001 accounts for the increase in average TLD readings (i.e., prior to third quarter 2001 TLD LiF chips were used versus the TLD cards -
see Section 9.7.6 for additional information) from 2000 to 2001. Therefore, the operation of the plant has had no effect on the ambient gamma radiation.
Table 11-1 Average Indicator TLD Results from 1993 - 2007 Year Average +/- St. Dev*
Units 1993 0.82
+/-
0.15 mR/7 days 1994 0.90
+
0.12 mR/7 days 1995 0.87
+
0.13 mR/7 days 1996 0.85
+/-
0.12 mR/7 days 1997 0.87
+
0.11 mR/7 days 1998 0.79
+/-
0.13 mR/7 days 1999 0.79
+/-
0.21 mR/7 days 2000 0.91
+/-
0.15 mR/7 days 2001 1.06
+
0.19 mR/7 days 2002 1.17
+/-
0.21 mR/7 days 2003 1.10
+/-
0.20 mR/7 days 2004 1.10
+
0.22 mR/7 days 2005 1.04
+
0.21 mR/7 days 2006 1.14
+
0.21 mR/7 days 2007 1.08
+/-
0.20 mR/7 days
- St. Dev = Standard Deviation There were no new cask additions in 2007 with no significant change in the average annual ISFSI fence TLD results (Table 11-2) The North and West fence TLDs continue to record higher doses than the South and East fence TLDs (Table 11-2) corresponding to the location of the storage units at the NW corner of the site. Compared to the~background site (E-20), most of the indicator sites 35
for the ISFSI (Table 11-3) show increases with the placement of casks at the ISFSI with the highest values at E-03 which is the closest to the ISFSI
[see Figs. 9-1 and 9-2 for locations]. The results near the site boundary (E-31, E-32) are comparable to the background site E-20, within the associated measurement error, indicating no measurable increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI.
Table 11-2 Average ISFSI Fence TLD Results (mR/7 days)
TLD FENCE LOCATION North East South West 1995 1.29 1.28 1.10 1.26 1996 2.12 1.39 1.10 1.68 1997 2.05 1.28 1.00 1.66 1998 2.08 1.37 1.02 1.86 1999 2.57 1.84 1.11 3.26 2000 2.72 2.28 1.25 5.05 2001 2.78 2.54 1.36 6.08 2002 2.79 2.74 1.42 6.46 2003 2.70 2.60 1.50 6.88 2004 2.61 2.12 1.41 6.50 2005 2.54
.2.05 1.44 5.63 2006 2.73 2.35 1.38 5.80 2007 2.72 2.73 1.34 5.47 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7 days)
Sampling Site E-03 E-28 E-29 E-30 E-31"*
E-32*
E-20***
Pre-Operation 0.93 0.87 0.87 0.81 0.93 0.98 0.88 1996 0.87 0.78 0.81 0.79 0.93 1.00 0.78 1997 0.91 0.89 0.84 0.84 0.89 0.97 0.79 1998 0.82' 0.68 0.80 0.82 0.91 0.85 0.77 1999 0.88 0.83 0.76 0.80 0.90 0.99 0.78 2000 0.98 0.88 0.92 0.99 0.98 1.06 0.90 2001 1.31 0.95 1.07 1.02 1.10 1.04 1.03 2002 1.45 0.91 1.22 1.10 1.26 1.25 1.14 2003 1.29 0.82 0.94 1.02 1.20 1.15 0.99 2004 1.35 0.80
.0.96 1.05 1.23 1.18 1.06 2005 1.30 0.72 0.96 0.98 1.15 1.04 1.00 2006 1.44 0.80 1.19 1.07 1:21 1.07 1.11 2007 1.37 0.78 1.07 1ý.05 1.18 0.97.
1.05
- Pre-Operation data are the averages of the years 1992 through 3d quarter of 1995.
- Sites E-31 and E-32 are located at the Site Boundary to the West and South-West of the ISFSI.
- E-20 is located approximately 17 miles WSW of the ISFSI.
36
11.2
'Milk Except for Sr-90, the annual average radionuclide concentrations in milk continue to be statistically not different from zero. These results are not statistically different from previous years going back to 1997. The Sr-90 in milk results of the cycling in the biosphere after the atmospheric weapons tests of the
'50s, '60s, and '70s and the Chernobyl accident. Although these tests also ihtroduced Cs-1 37 into the environment, Cs-1 37 binds more strongly to soils and therefore less likely to get into cows and milk. As summarized in Table 3-2, the only 2007 airborne release of Sr-90 from PBNP occurred in November. There were no airborne Sr-90 releases in 2005 and 2006. The 2007 average Sr-90 (0.8
+/- 0.4) is equivalent to previous years: 0.9 +/- 0.3 pCi/L in 2006, 0.9 + 0.4 pCi/L in 2005, 1.1 +/- 0.4 in 2004, 1.1 +/- 0.4 in 2003, 1.1 + 0.7 in 2002, 1.2 +/- 0.5 in 2001, 1.2 +/- 0.6 in 2000, 1.0 +/- 0.3 in 1999, 1.1 +/- 0.5 in 1998, and 1.2 +/- 0.5 in 1997.
These results are common throughout the Great Lakes region and North America. Therefore, it is concluded that the milk data for 2007 show no radiological effects of the plant operation.
11.3 Air The average annual gross beta concentrations (plus/minus the one-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.025 +/- 0.009 pCi/m3 and 0.026 +/- 0.009 pCi/m3, respectively, and are similar to levels observed from 1993 through 2006 (Table 11-4).
Table 11-4 Average Gross Beta Measurements in Air Year Average (pCi/m3) 1993 0.022 1994 0.022 1995 0.021 1996 0.021 1997 0.021 1998 0.022 1999 0.024 2000 0.022 2001 0.023 2002 0.023 2003 0.023 2004 0.021 2005 0.024 2006 0.021 2007 0.025 The gross beta concentration variation over the year usually reveals higher concentrations in the fall and winter as compared to the spring and summer.
This is present again during 2007. However, for 2007 as in 2006, another high period during July-September also is apparent (Figure 11-1). This pattern will be checked for reoccurrence during 2008. Similarly to 2005 and 2006, there is more scatter in the data for the spring and summer months.
37
Figure 11-1 2007 Airborne Gross Beta Concentration (pCi/m 3) vs. Time 2007 Airborne Gross Beta S0.060 0.050
~
- a. 0.040 Series I 0 000 Series2 0.020 -
Series3 0.010 x *, Series4 0 0..
) Series5 10 01 04 08 11 02 eSeries6 06 07 07 07 07 08 Date In 2005, the new method of evaluating airborne 1-131 was instituted. Instead of counting each charcoal. cartridge separately,all six cartridges for the week are counted as one sample in a predetermined geometry to screen the samples for I-131. If any airborne radioiodine were detected, each sample cartridge is counted individually. With no detectable 1-131, the reported analytical result is the minimum detectable activity (MDA) conservatively calculated using the smallest of the six sample volumes. The reported MDAs ranged from 0.003 to 0.029 pCi/m 3. Because the analysis LLD is based on counting only one cartridge, the use of six cartridges or roughly six times the sample volume with the same count time as would be needed to achieve the desired LLD for only one sample, the actual LLD is about six times lower than the programmatic value given in Table 10-1. Similarly, the actual MDA is about one-sixth of that reported, or in the range of 0.0005 to 0.005 pCi/mi3. Therefore, because no 1-131 was detected, it is concluded that the release of small amounts of radioiodine during January, April, and September (Table 3-2) had no measurable impact on the environment.
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Neither the indicator nor the control locations show results which, on average, are significantly different than zero. The two small, positive values for Cs-1 37 occurred for the second and third quarter composites. Because PBNP released no Cs-137 until November of 2007 (Table 3-2), these results are false positives. Similarly, the three positive Co-60 ("other" category) results also are determined to be false positives because no airborne Co-60 was released during 2007. Be-7 was measured in quarterly composites of all-indicator samples with an average of 0.075 pCi/m 3. This is comparable to the average of 0'074 pCi/m 3 at the control site. Be-7 is not required to be measured by the PBNP REMP; however, it serves as a means to monitor the internal consistency of the vendor's analytical program and for comparisons to radionuclides that may be in PBNP airborne effluent.
38
In summary, the air data for 2007 demonstrate the operation of PBNP did not have an impact on the surrounding environment.
11.4 Lake Water For the suite of REMP-specified gamma emitting radionuclides listed in Table 10-1, reported concentrations continue to occur as small negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Only 46 lake water samples were collected because environmental conditions precluded sample collection at site E-05 and E-06 during February. Of the 46 lake water samples analyzed during 2007, 1 of 46 was statistically greater than zero for Fe-59 and Cs-1 37; 2 of 46 were positive for Mn-54, Co-58, and Zr/Nb-95; and finally, 5 of 46 for Ba/La-140. No Ba/La-140, Zr-Nb-95, Fe-59 or Mn-54 were released by PBNP during the months they were detected. Additionally, most of these results were north of PBNP which is upstream of the local lake current direction. Hence it is concluded that these are false positives. Although both Co-58 and Cs-1 37 were released during the months they were detected in Lake Michigan, both occurrences were north of the plant. Therefore, based on these results and their occurrences, it is concluded that the discharge of these radionuclides has a minimal impact.
Aliquots of the monthly samples are composted quarterly and analyzed for Sr-89/90 and for tritium. Sr-90 still persists in Lake Michigan from radioactive fallout. Therefore it is not surprising that positive results still occur. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. The quarterly composite lake water samples collected and analyzed for H-3 in 2007 range from ND to 171 pCi/I. This concentration is close to the MDA and occurred at a site several miles north of PBNP. As stated above, the lake current in this area is from the north to the south. Finally, there was one occurrence of Sr-89. Because no Sr-89 was released by PBNP and it occurred north of the plant, it is concluded that the result is a false positive. These results indicate a minimal impact upon the waters of Lake Michigan from PBNP liquid discharges.
11.5 Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water with concentration factor over a thousand for certain radionuclides. Three of the six samples had small, positive concentrations of Co-58 (1 of 6), Co-60 (1 of 6), and Cs-1 37 (3 of 6).
One occurrence of Cs-1 37 and the single occurrence of the cobalts were near the PBNP discharge and therefore may be related to PBNP discharges.
Because the Cs-1 37 also occurred north of the plant, the Cs-1 37 could easily be Cs-1 37 remaining in the lake from atmospheric weapons tests. Typically, the only fission product observed in algae is Cs-1 37 with averages over years 1995-2004 of 0.034, 0.050, 0.030, 0.027, 0.031, 0.027, 0.019, 0.019, 0.010, and 0.018 pCi/g; all of which are less than the LLD (0.25 pCi/g). This year's average Cs-1 37 of 0.014 pCi/g is consistent with previous results which show a 39
slowly decreasing concentration. The concentrations of naturally occurring Be-7 and K-40 are higher: 0.65 and 2.97 pCi/g, respectively. These results indicate only a minor, if any, effect by PBNP upon the environs.
11.6 Fish No specified fission/corrosion radionuclide concentrations in fish greater than the required LLD were found in 2007. Statistically positive Cs-137 concentrations were found irn 8 of the 9 fish. The highest Cs-137 value of 0.049 is comparable to the 0.055 pCi/g found in 2006 but is lower than the high of 0.172 pCi/g in 2005. But, all three of these values are considerably less than the high of 2.8 pCi/g as seen in PBNP samples obtained in the mid-1 970s during the Chinese weapons tests. However, the Cs-1 37 results in fish are consistent with accumulation due to the recycling of atmoslpheric weapons testing fallout Cs-1 37 in Lake Michigan. Again, the aforementioned resuspension events make the Cs-1 37 more readily available to be associated with items eaten by the fish. By comparison, the concentration of naturally occurring K-40 (1.58-4.41 pCi/g) is about 30-80 times higher than the highest Cs-1 37 concentration. The small, positive values of Zn-65, Co-58, and Cs-134 may be false positives. PBNP did not discharge any Cs-1 34 in 2007. Therefore, the fish may have picked this radionuclide anywhere in the lake as there are other nuclear plants on Lake Michigan. Therefore, it is concluded that there is no indication of a plant effect..
11.7 WellWater There was only one well water result statistically greater than zero. In the second quarter, Sr-89 was statistically above zero. This result is concluded to be a false positive. First, PBNP discharged no Sr-89 in either liquid or airborne effluent during 2007. Second, the impermeability of the clay layer which separates the surface ground water from the aquifer from which the PBNP well water is obtained and the relatively short Sr-89 half-life precludes surface water from reaching the lower aquifer. Finally, the most likely effluent radionuclide to be able to reach the drinking water aquifer is H-3 and it was not detected. As previously mentioned, small, positive results may occur due to the statistical nature of radioactive decay, when there is no radionuclide present. Therefore, it is concluded that the one Sr-89 result does not indicate that PBNP effluents are getting into the aquifer supplying drinking water to PBNP.
11.8 Soil Cs-1 37 is present in the soils throughout North America and the world.- The main contributor to this worldwide distribution is the weapons testing in the 1950s and 1960s with lesser amounts from Chinese atmospheric nuclear tests in the 1970s and the 1986 Chernobyl accident. Soil is an integrating sample me'dia in that it is a better indicator of long term buildup of Cs-1 37 as opposed to current deposition for local sources. The main modifiers of soil Cs-1 37 concentration levels are erosion and radioactive decay. The PBNP REMP results indicate that low levels of Cs-137 from fallout continue to be present in soil samples at about 40
1% of the levels of naturally occurring K-40. All of the 16 samples have Cs-1 37 concentrations statistically greater than zero ranging from.0.04 +/- 0.03 to 0.35 +/- 0.04 pCi/g. Although higher that the averages from the 1990s, the current gross beta results also areconsistent with the last few years(Table 11-5). Also, the results are quite uniform with the result close to the plant (E-01: 33.23 +/-
2.91) not being different from the background site some 17 miles away in the lowest x/Q sector (E-20: 35.15 +/- 2.96). Therefore, there is no indication of a plant effect.
Table 11-5 Average Gross Beta Concentrations in Soil Year Activity (pCi/g) 1993 23.6 1994 19.4 1995 18.0 1996 19.4 1997 22.8 1998
.20.0 1999 23.1 2000 22.1 2001 23.5 2002 21.9 2003 22.5 2004 24.3 2005 29.1 2006 27.4 2007 31.0 11.9 Shoreline Sediment Shoreline sediment consists of sand and other sediments washed up on the Lake Michigan shore. As in soil samples, the only non-naturally occurring radionuclide found in these samples is Cs-1 37. Eight of the ten samples have Cs-1 37 concentrations statistically different from zero. The Cs-1 37 concentrations of the shoreline sediment are about one-tenth of that found in soils. This is expected becauseCs-137 in the geological media is bound to clay as opposed to the sand found on the beach. Wave action winnows clay particles from the beach leaving the heavier sand; hence the lower Cs-1 37 concentrations in beach samples. In contrast to K-40 which is actually part of the minerals making up the clay and sand, Cs-1 37 isattached to soil/sand particle surfaces.
Therefore it is not surprising that Cs-1 37 is present at concentrations 1% or less of the naturally occurring concentrations of K-40. Because Lake Michigan sediments are a known reservoir of fallout Cs-137, the shoreline sediment data indicate no radiological effects from plant operation.
41
11.10 Vegetation The naturally occurring radionuclides Be-7 and K-40 are found in all of the vegetation samples. In contrast, of the three programmatically specified radionuclide 1-131, Cs-1 34, and Cs-1 37, only Cs-1 37 was detected in 6 of the 24 samples. Three of the occurrences were at site E-06. All the positive Cs-137 results were below the required LLD at concentrations about 100 times lower than Be-7 and K-40 concentrations. The source of Be-7 is atmospheric deposition. It is continuously formed in the atmosphere by cosmic ray spallation of oxygen, carbon, and nitrogen atoms. In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. Cs-1 37 can represent both pathways. Fresh Cs-1 37 fallout is associated, like Be-7, with deposition on the plant surface. Old fallout from the
'50s and '60s is now being incorporated into growing plants in the same manner as potassium because it is in the same chemical family as potassium. Cs-1 37 has been consistently present in vegetation from E-06, a campground area in the Point Beach State Forest. As has been demonstrated at other sites in the United States which are far from any nuclear plants, 1950s and 1960s fallout Cs-137 is present in the ash produced by burning the wood in fireplaces. Typically, campground fires are put out using water and the ashes are spread on the ground. The ash acts as a fertilizer, releasing the cesium and potassium into the soil where they are available for uptake by growing plants and trees. Hence, the Cs-1 37 results from E-06 demonstrate that Cs-1 37 fallout from the Chernobyl accident and from atmospheric weapons tests continues to be recycled in the environment by the spreading of wood ash at camp sites.
Based on the 2007 vegetation sampling results, it is concluded that no effect from PBNP effluents are indicated.
11.11 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2007. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. It continues to be conservative for the purpose of calculating doses via the grass-cow-milk pathway to ensure that the milk sampling locations remain as conservative as practicable.
12.0 REMP CONCLUSION Based on the analytical results from the 823 environmental samples and from 116 sets of TLDs that comprised the PBNP REMP for 2007, PBNP effluents had no discernable, permanent effect on the surrounding environs. These results demonstrate that PBNP continues to have good controls on fuel integrity and on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a.
42
13.0 Program Description The PBNP monitors groundwater for tritium. During 2007 the sampling program consisted of six beach drains, five intermittent creek and bog locations, four drinking water wells, four fagade wells, nine yard electrical manholes, six new ground water monitoring wells, and 15 manholes for the subsurface drainage (SSD) system under the plant and along the outside of the foundation walls.
In the 1980s, the beach drains entering Lake Michigan were found to contain tritium. The beach drains are the discharge points for yard drainage system which carries storm water runoff and are known to be infiltrated by groundwater as observed by discharges even when no rain has occurred. In the 1980s, the source of H-3 for this pathway was postulated to be spent fuel pool leakage into the groundwater under the plant based on the observation that after modifications were made to the pool, the tritium concentrations decreased below delectability. Beach drain effluents continue to be monitored and are accounted for in the monthly effluent quantification process. Because the beach drains are susceptible to groundwater in-leakage from other sources such as the area around the former retention pond which is known to contain H-3, the beach drains are monitored as part of the groundwater monitoring program.
The intermittent streams and the Energy Information Center (EIC) well were added to the
,groundwater monitoring program in the late 1990s when it was discovered that tritium diffusion from the then operable, earthen retention pond was observable in the intermittent streams which transverse the site in a NW to SE direction. These streams pass on the east and west sides of the former retention pond and empty into Lake Michigan about half a mile south of the plant near the site's meteorological tower. The intermittent stream samples track H-3 in the surface groundwater.
The groundwater monitoring program also includes two bogs or ponds on site. One is located about 400 feet SSE of the former retention pond; the other, about 1500 feet N.
In addition to the main plant well, three other drinking water wells also are monitored. The Site Boundary Control Center well located at the plant entrance, the Warehouse 6 well on the north side of the plant, and the EIC well located south of the plant. These wells do not draw water from the top 20 - 30 feet of soil which is known to contain H-3. These wells monitor the deeper (200 - 350 feet), drinking water aquifer from which the main plant well draws its water. The two soil layers are separated by a gray, very dense till layer of low permeability identified by hydrological studies.
Manholes in the plant yard and for the subsurface drainage SSD system under the plant are available for obtaining ground water samples. The plant yard manholes for accessing electrical conduits are susceptible to ground water in-leakage. Therefore, a number of 43
number of these were sampled. The SSD were designed to control the flow of water under the plant and around the perimeter of the foundation walls. Where possible, water in the SSD manholes was sampled. The SSD system flows to a sump in the Unit 2 facade. A monthly composite from this sump is analyzed as well as part of the program.
In the 1990s, two wells were sunk in each units fagade to monitor the groundwater levels and look evidence of concrete integrity as part of the ISI IWE Containment Inspection Program required by 10 CFR 50.65. These wells are stand pipes which are sampled periodically for chemical analyses. Beginning in 2007, samples for the groundwater program were drawn as well. These wells are sample at least three times a year.
The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1.
14.0 Results 14.1 Streams and Bogs The results from the groundwater monitoring associated with the former retention pond are presented in Table 14-1.
For the most part, the creek results are barely above the detection level. There are more positive values for the East Creek than for the West Creek or for the confluence of the two creeks south of the plant near Lake Michigan. GW-08 is a bog near the former retention pond.
Table 14-1 Intermittent Streams and Bogs H-3 Concentration (pCi/I)
Month GW-01(E-01)
GW-02 GW-03 BOGS MDA Creek Confluence East Creek West Creek GW-07 GW-08 Jan
+
+
+
Feb
+
+
+
Mar 87
+/-
92 225 98 116 +/-
94
+
169 Apr
-79
+/-
79 93
+/-
87
-77
+/-
79
+/-
+/-
157 May 98
+/-
80 102
+
88 72
+
87 223
+ 94 398
+/-
101 169 Jun
-1
+
75 73
+
79 129
+/- 82
+/-
+/-
143 Jul 126
+/- 107 103
+/-107 30
+/-
104
+/-
+/-
153 Aug 88
+/-
86 103 87 164
+/-
90
+/-
166 Sep
+/-
+
+/-
+/-
Oct
+/-
+
+
+/-
+/-
Nov
+/-
+/-
+
+/-
+/-
Dec
+
+
+/-
+
+/-
A blank indicates no sample was available. Streams are sampled monthly; bogs, annually.
Values are presented as the measured value and the 95% confidence level counting error.
ND = not statistically different from zero at the 95%
confidence level.
44
Figure 13-1 Groundwater Monitoring Locations 45
The value H-3 concentration for 2007 is about an order of magnitude lower than the 2000 - 3300 pCi/I obtained before the retention pond was remediated. The creek values are generally lower as well.
In the late '90s, the East Creek H-3 concentrations would reach 300 - 350 pCi/l. Only the two bog results and the March GW-02 sample are above the MDA.
14.2 Beach Drains and SSD Sump The results for the beach drains (Table 14-2) show low H-3 concentrations with a few in the 300 - 700 pCi/I range. The southern drain, S-3, exhibits the most consistent and uniform H-3 concentration. Based on the flow direction of the intermittent streams around the former retention pond, this is the drain most susceptible to contain tritiated groundwater in-leakage from the area around the former retention pond. The northern most beach drain is S-1. This drain is connected to the SSD sump and also is impacted by groundwater in-leakage.
The monthly SSD sump composite results show little correlation to the S-1 results (Table 14-3). Except for the November S-1 result, the SSD sump tritium concentrations are usually higher than the S-1 results for the same period. This could be the result of groundwater in-leakage to the S-1 drain lines which would dilute any SSD sump contributions to this drain line. Beach drains S-7 and S-10 are fed by runoff from the Unit 2 and Unit 1 roofs respectively. Hence, no flow is expected unless there is precipitation. S-8 and S-9 drain the small yard area between the plant and the lake. It is not know why the only occurrence of water flow from either S-8 or S-9 should have a measurable amount of, H-3. However, it may be associated with groundwater in-leakage as electrical manholes M-1 and M-2 in the area have been found to contain low concentrations of H-3.
Table 14-2 2007 BEACH DRAIN TRITIUM H-3 Concentration (pCi/l)
Month S-1 S-7 S-8 S-9 S-10
. S-3 Jan 168
+/- 90 NF +/-
NF
+
NF +/-
NF +
174
+/- 90 Feb NF +/-
NF
- NF
+/-
NF +/-
NF +
NF +/-
Mar 683
+/- 102 NF.+/-+
443 96 NF +/-
NF +
269
+/- 89 Apr 174
+/- 90 NF +/-
NF
+/-
NF +/-
NF+
120
+/- 88 May 208
+/- 102 NF +/-
N F NF +/-
NF+
165 +/- 100 Jun NF +/-
NF +/-
NF NF +/-
NF+
336
+/- 98 Jul 243
+/- 103 NF +/-
NF NF +/-
NF+
270
+/- 88 Aug 246
+/-
91 NF
+/-
NF NF. +/-
NF
+
358
+/-
96 Sep NE NF
+/-
NE
+/-
NF N
NF +
299
+/- 96 Oct 112
+/- 107 NF +/-
N N F +/-
NF+
46
+/- 104 Nov 588
+/- 104N NE
+/-
NF +/-
NF+
234
+/- 90 Dec 321
+/- 91 NF +/-
N
+/-
F +/-
NF+
238
+/- 87 Average=
305 2281 Stddev=
198 76 NF = no sample due to no flow 46
Table 14-3 U2 FAQADE SUBSURFACE DRAIN SUMP H-3 1
H-3 Concentration (pCi/I)
Month
.pCi/I 2a Jan
+/-
Feb
+/-
Mar
+/-
Apr
+/-
May
+/-
Jun 491
+/-
120 Jul 708
+/-
127 Aug 519
+/-
120 Sep 529
+/-
105 Oct 288
+/-
109 Nov 363
+/-
108 Dec 489
+/-
110
'Sampling began in June 2007 Samples are monthly composites 14.3 Electrical Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage as is evident by very low concentrations of H-3 (Table 14-4). MH-1 and MH-2 are located in the area drained by beach drains S-8 Table 14 YARD MANHOLE TRITIUM Activity (pCi/I)
Man Hole pCi/I
+/-
2a MH-1 157
+/-
101 MH-2 148
+/-
101 MH-3 145
+/-
100 MH-4 52
+/-
86 MH-5 150
+/-
101 MH-9 127
+/-
100 MH-10 304
+/-
106 MH-14 121
+/-
100 MH-19 165
+/-
91 Average 152
+/-
122 and S-9. MH-1 0 is located on the west side of the plant and more in line with groundwater flow from the area of the former retention pond. Conduit in this 47
manhole runs to the southwest in the direction of the former retention pond and the area which groundwater testing for the pond remediation effort found H-3 concentrations up to 14,000 pCi/I. As shown below, the groundwater monitoring well in this area (GW-1 5, Fig. 13-1) also has the highest H-3 concentration of any of the monitoring wells.
14.4 Subsurface Drainage System and Facade Wells Samples of groundwater under the plant are obtained via SSD system manholes and via the fagade wells (Table 14-5). The sampling locations are identified by the plant's column locations designations.
Table 14-5 2007 SUBSURFACE DRAINAGE SYSTEM TRITIUM Turbine Bldg 1 SSD Location Activity Col #
pCi/I 2o F5.1 309 97 A12.1 809
+/-
116 E9.5 411 102 EF1 3 1501 140 F13.1 451
+/-
111 E13.1 558 114 F6 242
+
104 F7 382
+/-
109 F9.9 363 108 F8 432 110 B6.1 4 317
+
98 EXTERNAL 2
SSD Location pCi/I 2a SW corner Ul fagade 317 98 NW corner U2 fagade 405 101 NE NSB 221 94 Near LIN Tank 213
+
93 8 SSD manholes were dry, 1 was welded shut, 4 could not be accessed due to electrical concerns, and one could not be lifted due to equipment malfunction.
2 3 were dry and 3 could not be opened due unavailability of lifting equipment 3 This sample was analyzed for Fe-55, Sr-89/90, and gamma scanned. No activity was found.
Gamma scan of manhole debris revealed Cs-i 37(1.75 +/-
0.15 pCi/g) and Co-60 (0.26 +/- 0.05 pCi/g). No other radionuclides were found 48
The alphanumeric IDs run from A - S (east to west)and 1 - 22 (south to north) in the plant. The internal SSD system is designed to channel groundwater away from the foundation periphery to a central sump for each unit. The external SSD system drains to the lake. As indicated in the Table 14-5 notes, some of the SSD manholes were dry. In others, the upstream manholes contained higher H-3 concentrations than the downstream manholes. The sample with the highest H-3 concentration was analyzed for Fe-55, Sr-90, and gamma emitters.
None was found. Additionally, one of the manholes contained organic debris.
The debris contained low levels of Co-60 and Cs-137. No other gamma emitters were found.
Although there are SSD manholes in each unit's fagade, no samples were obtained from them because these manholes were sealed due to flooding concerns. Instead, groundwater under the fagades is obtained from the fagade wells which are part of the containment inspection program. These results are found in Table 14-6.
Table 14-6 2007 FACADE WELL WATER TRITIUM H-3 Concentration (pCi/I)
UNIT 1 UNIT 2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B Jan Feb Mar 1019+/-133
-20+/-93 4207+/-213 Apr May 168+/-101 Jun 1381+/-143 2678+/-177 Jul 183+/-100 47+/-94 Aug Sep 1525+/-144 223+/-107 Oct Nov Dec 1356+/-134 194+/-93 77+/-94 407+/-107 Based on the current knowledge of the condition of the SSD system it is not possible to' come to a conclusive interpretation concerning the tritiated water under the plant other than to say that there are areas of groundwater that have higher H-3 concentrations than others. This is especially evident in the facades where the fagade well results can vary by one to two orders of magnitude from one side of the containment to the other. The data suggest that the water in the SSD system may not be flowing as designed and, because, only long-lived gamma emitters were found, the activity is not of recent origin but indicative of the 1970s when spent fuel pool leakage was known to exist.
49
14.5 Potable Water and Monitorina Wells In addition to the main plant well (Section 11.7), nine other wells are monitored for H-3. These consist of three potable water wells, GW-04, GW-05, and GW-06, and six H-3 groundwater monitoring wells, GW-1 1 through GW-1 6 installed in 2007 (Figure 13-1). The monitoring wells are located at the periphery of the area affected by diffusion from the former retention pond and known spent fuel pool leakage during the 1970s. Two of the potable water wells are for buildings close to the plant (GW-04 and GW-05) whereas the other (GW-06) is at the Site Boundary Control Center some 3200 feet from the former retention pond. The potable water wells are from the deep aquifer whereas the monitoring wells are in the shallow (< 30 feet), surface water aquifer above the thick, impermeable clay layer separating the two.
The EIC well is sampled monthly and the other two potable wells, quarterly. The potable water wells have no H-3. Although there are several results for which the measured concentrations meet the detected Table 14-7 2007 WELL WATER TRITIUM H-3 Concentration (pCi/I)
EIC Warehous SBCC WELL e 6 Well Well MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Month GW-04 GW-05 GW-06 GW-11 GW-12 GW-13 GW-14 GW-15 GW-16 Jan Feb 31+/-88 Mar 76+/-92 21 +/-90
-89+/-85 Apr
-156+/-75 64+/-86 100+/-87 May 185+/-92 Jun 43+/-77 Jul
-9+/-80 21 +/-78 56+/-79 Aug 124+/-88 248+/-102 93+/-96 136+/-98 189+/-100 Sep 36+/-101 224+/-101 15+/-92 Oct 65+/-81 65+/-81 39+/-80 Nov
-70+/-79 Dec
-107+/-97 116+/-96
-199+/-90 85+/-95 75+/-94 329+/-104 186+/-99 April gamma scans, 1-131, and Sr analyses of GW-05 and GW-06 found no activity July gamma scans, 1-131, and Sr analyses of GW-05 and GW-06 found no activity criterion, they are not high enough to satisfy the criterion for meeting the determination limit because the error is a significant fraction of the net value.
Analyses for gamma emitters, 1-131, and Sr-90 did not find any of these radionuclides in GW-05 and GW-06 well water.
The monitoring wells were sampled only twice during 2007. The results are from samples taken during well installation and then again during the final month the wells were bailed to remove the clay sediment in-leakage before the wells were put on their monthly sampling schedule. The highest H-3 concentration occurred 50
in the well nearest the location of the former retention pond. This well is near the area where the pond pre-remediation groundwater survey found a tritium concentration of 14,000 pCi/I.
14.6 Miscellaneous Samplinq In addition to groundwater, analyses have been made of rainwater. Rainwater H-3 measurements were undertaken in order to obtain information on potential background levels of tritium. Another reason for sampling the rainwater is 'to determine whether it is possible to see the outwash of atmospheric H-3 releases from Point Beach. Therefore, a sampler was placed at the Site Boundary Control Center (E-04), which is located in the highest x/Q sector. Only the sample collected early in October is statistically greater than zero at the 95%
confidence level (Table 14-8).
Table 14-8 Precipitation H-3 Date TU 1 o pCi/I 1
6/6/2007 14
+
8 44.1
+/-
25.8 8/9/2007
<6
+
8
<19.2
+/-
25.8 9/5/2007 9
+
8 29.0
+/-
25.8 10/3/2007 17
+
8 56.0
+/-
25.8 10/18/2007 14
+
8 44.8
+/-
25.8 TU = tritium unit = 3.221 pCi/I 15.0 Groundwater Summary Groundwater monitoring indicates that low levels of tritium continue to occur in the upper soil layer but not in the deep, drinking water aquifer. These results also indicate that the low levels of tritium are restricted to a small, well defined area close to the plant. The fagade wells have the highest results followed by the SSD system. The beach drains appear to be slightly lower than the SSD system. Except for the monitoring well in the, vicinity of the former retention pond, the monitoring well tritium concentrations are not different from zero.
Results will continde to be evaluated to determine whether additional groundwater monitoring sites are needed.
51
APPENDIX.1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant Reporting Period: January - December 2007
.ii:!.=. Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 (847) 564-0700 fax.(847) 564-4517 FINAL REPORT TO FPL ENERGY RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
FOR THE POINT BEACH NUCLEAR PLANT, TWO RIVERS, WISCONSIN-PREPARED AND SUBMITTED BY ENVIRONMENTAL INCORPORATED MIDWEST LABORATORY Project Number: 8006
(~V VP A
Reporting Period: January-December, 2007 Reviewed and Approved by_
Date O2-OS-2-o00 Distribution:
K. Johansen
Section POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Page List of Tables i.i......................
I INTRO DUCTIO N..................................................................
1 LISTING OF MISSED SAMPLES.........................................
2 1.0 2.0 Appendices A
B C
D Interlaboratory Comparison Program Results.....................
A-1 Data Reporting Conventions................................................
B-1 Sampling Program and Locations.......................................
C-1 Graphs of Data Trends..........................
D-1 ii
POINT BEACH NUCLEAR PLANT LIST OF TABLES Title PaQe Airborne Particulates and Iodine-1 31 Location E-01, Meteorological Tower................................................
4 Location E-02, Site Boundary Control Center.....................................
5 Location E-03, West Boundary..........................................................
6 Location E-04, North Boundary.......................................
7 Location E-08, G. J. Francar Residence............................................
8 Location E-20, Silver Lake College.............................
.......................... 9 Airborne Particulates, Gamma Isotopic Analyses 10 Milk 11 W e ll W a te r...........................................................
............................................. 17,
'La ke W ate r.......................................................................................................
18 Lake Water, Analyses on Quarterly Composites....................
22 F is h..............................................................................................................
.. 2 5 Shoreline Sedim ents.......................................................................................
.28 S o il....................................................................................................
.... 30 Vegetation..............................................................
32 A quatic Vegetation.......................................................................................
35 Gamma Radiation, as Measured by TLDs...................................................
36 iii
POINT BEACH NUCLEAR PLANT
1.0 INTRODUCTION
The following constitutes the final 2007 Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of analyses are presented in the attached tables. Data tables reflect sample analysis results for both Technical 'Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons.
For gamma isotopic analyses, the spectrum covers an energy range from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La;140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, TI-208, Pb-212, Bi-214, Ra-226 and Ac-228. Unless noted otherwise, the results reported under "Other Gammas" are for Co-60 and may be higher or lower for other radionuclides.
All concentrations, except gross beta, are decay corrected to the time of collection.
All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples.
I
POINT BEACH NUCLEAR PLANT 2.0 LISTING OF MISSED SAMPLES Expected Collection Sample Type Location Date Reason LW E-05 02-15-07 Water frozen.
LW E-06 02-15-07 Water frozen.
AP/AI E-02 10-25-07 Pump not running.
AP/AI E-02 10-31-07 Pump not running.
NOTE: Page 3 is intentionally left out.
2
POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: E-01, Meteorological Tower Units: pCi/m3 Collection: Coniinuous, weekly exchange.
Date Vol.
Collected (M3)
Gross Beta 1-131 Date Vol.
Collected (M3)
Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-07 01-10-07 01-17-07 01-24-07 01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 351 254 304 302 301 304 303 257 346 302 306 300 302 0.028 +/- 0.003 0.031 +/- 0.004 0.019 +/- 0.003 0.038 +/- 0.004 0.027 _ 0.004 0.030 +/- 0.004 0.026 + 0.004 0.027 +/- 0.004 0.018 +/-0.003 0.016 +/- 0.003 0.027 +0.004 0.028 +/- 0.004 0.016 +/- 0.003
< 0.014
< 0.021
< 0.018
< 0.008
< 0.018
< 0.023
< 0.013
< 0.011
< 0.013
?< 0.010
< 0.010
< 0.013-
< 0.019 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-15-07 08-22-07 08-28-07 09-05-07 09-12-07 09-19-07 09-26-07 10-03-07 3rd Quarter Mean +/- s.d.
386 328 334 332 336 330 321 258 368 322 314 313 305 0.022 +/- 0.003 0.014 +/-0,003 0.018 +/- 0,003 0.028 +/- 0.004 0.025 +/- 0.003 0.020 +/- 0.003 0.012 +/- 0.003 0.019 +/- 0.003 0.032 +/- 0.004 0.022 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.004 0.031 +/- 0.004
< 0.006
< 0.012
< 0.008
< 0.010
< 0.014
< 0.007
< 0.011
< 0.017
< 0.007
< 0.008
< 0.012
< 0.018
< 0.014 1st Quarter Mean +/- s.d.:
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07
.05-08-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07 06-20-07 06-27-07 07-03-07 0.025 +/- 0.006
< 0.015 0.023 +/- 0.006
< 0.011 302 313 337 259 302 279 404 286 335 331 365 330 329 286 0.012 + 0.003 0.019 +0.003 0.021 +/- 0.003 0.018 +/- 0.004 0.014 +/- 0.003 0.016 +/- 0.004 0.013 +/-0.003 0.017 +/- 0.004 0.017 + 0.003 0.019 +/- 0.003 0.021 +/-0.003 0.029 +/- 0.004 0.025 +/- 0.003 0.011 +/- 0.003
< 0.007
< 0.014
< 0.010
< 0.011
< 0.009
< 0.010
<0.022
< 0.011
< 0.009
< 0.020
< 0.013
< 0.011
< 0.011
< 0.019 10-11-07 10- 18-07 10-25-07 10-31-07 11-07-07 11-15-07 11-21-07 11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
356 303 349 258 308 344.
259 303 308 307 311 314 358 0.023 +/- 0.003 0.025 +/- 0.004 0.020 +/- 0.003 0.024 +/- 0.004 0.019 +/- 0.003 0.021 +/-0.003 0.022 +/- 0.004 0.027 +/- 0.004 0.025 +/- 0.004 0.041 +/- 0.004 0.046 +/- 0.004 0.045 +/- 0.004 0.034 +/- 0.003
< 0.009
< 0.015
< 0.007
< 0.012
< 0.008
< 0.021
< 0.017
< 0.007
<0.005
< 0.003
< 0.016
< 0.014
< 0.007 2nd Quarter Mean +/- s.d.
0.018 +/-+0.005
< 0.013 0.029 +/- 0.010 < 0.011 0.024 +/- 0.008 < 0.012 Cumulative Average 4
POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: E-02, Site Boundary Control Center Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Vol.
Collected (Mi)
Gross Beta 1-131 Date Vol.
Collected (m3)
Gross Beta 1-131 Required LLD 0.010 01-04-07 01-10-07 01-17-07 01-24-07 01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 1st Quarter Mean + s.d.
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07 05-09-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07 06-20-07 06-27-07 07-03-07 2nd Quarter Mean +/- s.d.
341 351 305 292 293 295 290 253 336 292 297 290 293 0.030 +/- 0.004 0.030 +/- 0.004 0.016 +/- 0.003 0.041 +/- 0.004 0.035 +/- 0.004 0.034 + 0.004 0.017 +/- 0.004 0.028 +/- 0.004 0.020 +/- 0.003 0.020 +/- 0.004 0.030 +/- 0.004 0.024 +/- 0.004 0.017 +0.004 0.030
< 0.015
< 0.021
< 0.018
< 0.008
< 0.018
< 0.024
< 0.014
< 0.011
< 0.013
< 0.010
< 0.010
< 0.013
< 0.019 Required LLD 0.010 0.030 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-15-07 08-22-07 08-28-07 09-05-07 09-12-07 09-19-07 09-26-07 10-03-07 351 298
.303 302 305 300 302 254 341 301 304 303 296 0.025 +/- 0.003 0.016 +/- 0.003 0.019 +/- 0.003 0.035 +/- 0.004 0.034 t 0.004 0.027 +/- 0.004 0.015 +/- 0.003 0.008 +/- 0.003 0.032 +/- 0.004 0.023 +/- 0.004 0.025 +/- 0.004 0.033 +/- 0.004 0.031 +/- 0.004
< 0.007
< 0.013
< 0.009
< 0.012
< 0.016
< 0.008
< 0.012
< 0.017
< 0.008
< 0.009
<0.013
< 0.019
< 0.014 0.026 +/- 0.008 < 0.015 293 304 326 252 293 315 323 260 305 300 307 300 300 260 0.009 +/- 0.003 0.019 +/- 0.004 0.022 +/- 0.003 0.015 +/- 0.004 0.015 +/- 0.003 0.019 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.004 0.020 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.004 0.027 +/- 0.004 0.027 +/- 0.004 0.009 +0.003
< 0.008
< 0.014
< 0.010
< 0.012
< 0.010
< 0.008
< 0.015
< 0.012
< 0.010
< 0.022
< 0.016
< 0.013
< 0.012
< 0.021 3rd Quarter Mean +/- s.d.
10-11-07 10-18-07 10-25-07 10-31-07 11-07-07 11-15-07 11-21-07 11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
0.025 +/- 0.008 < 0.012 191 0.039 +/- 0.005 < 0.017 293 0.022 + 0.004 < 0.016 NSa NSa 303 345 259 303 302 303 301 304 346 0.021 +/- 0.003 0.026 +/- 0.003 0.017 +/- 0.004 0.026 +/- 0.004 0.024 +/- 0.004 0.037 0 0.004 0.050 +/- 0.004 0.041 +/- 0.004 0.030 _ 0.003
< 0.008
< 0.021
< 0.017
< 0.007
< 0.005
< 0.003
< 0.016
< 0.015
< 0.007 0.018 +/- 0.006
< 0.013 0.030 +/-0.010
< 0.012 0.025 +/- 0.009
< 0.013 Cumulative Average a "NS" = No sample; see Table 2.0, Listing of Missed Samples.
5
POINT BEACH NUCLEAR PLANT Airbomre particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: E-03, West Boundary Units: pCi/m3 Collection: Continuous, weekly exchange.
Date Vol.
Collected (M3)
Gross Beta 1-131 Date Vol.
Collected (M3)
Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-07 01-10-07 01-17-07 01-24-07*
01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 340 247 300 297 292 295 290 253 336 293 297 290 294 0.026 +/- 0.003 0.027 +/- 0.004 0.018.+/- 0.003 0.038 +/- 0.004 0.029 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.004 0.029 +/- 0.004 0.020 +/- 0.003 0.016 +/- 0.003 0.031 +/- 0.004 0.024 +/- 0.004 0.017 +/- 0.003
< 0.015
< 0.021
< 0.018
< 0.008
< 0.018
< 0.024
< 0.014
< 0.011
<0.013
< 0.010
< 0.010
< 0,013
< 0.019 1st Quarter Mean _ s.d.
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07 05-08-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07
- 06-20-07 06-27-07 07-03-07 2nd Quarter Mean +/- s.d.
0.026 +/- 0.006
< 0.015 293 301 328 251 293 269 369 260 305 301 307 300 300 260 0.013 +/- 0.003 0.020 +/- 0.004 0.021 +/- 0.003 0.015 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.004 0.015 +/- 0.003 0.018 +/- 0.004 0.016 +/- 0.003 0.018 +/- 0.003 0.022 +/- 0.004 0.026 +/- 0.004 0.025 +/- 0.004 0.006 +/- 0.003
< 0.008
< 0.014
<0.010
< 0.012
< 0.010
< 0.010
< 0.029
< 0.012
< 0.010
< 0.022
< 0.016
< 0.013
< 0.012
< 0.021 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-1.5-07 08-22-07 08-28-07 09-05-07 09-12-07 09-19-07 09-26 10-03-07 3rd Quarter Mean +/- s.d.
10-11-07 10-18-07 10-25-07 10-31-07 11-07-07 11-15-07 11-21-07 11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
0.023 +/- 0.007
< 0.012 350 299 303 302 305 301 301 259 337 302 303 303 319 0.018 +/- 0.003 0.013 +/- 0.003 0.018 +/- 0.003 0.029 +/- 0.004 0.034 +/- 0.004 0.020 +/- 0.003 0.012 +/- 0.003 0.021 +/- 0.004 0.034 +/- 0.004 0.023 +/- 0.004 0.025 + 0.004 0.031 +/- 0.004 0.022 +/- 0.003
< 0.007
< 0.013
< 0.009
< 0.012
< 0.016
< 0.008
< 0.012
< 0.016
< 0.008
< 0.009
< 0.013
< 0.019
< 0.013 190 294 305 255 303 345 259 303 303 303 301 304 345 0.041 +/- 0.005 0.022 + 0.004 0.018 +/- 0.003 0.025 +/- 0.004 0.019 +/- 0.003 0.025 +/- 0.003 0.027 +/- 0.004 0.028 +/- 0.004 0.027 +/- 0.004 0.044 +/- 0.005 0.051 +/- 0.004 0.048 +/- 0.005 0.036 +/- 0.004
< 0.017
< 0.016
< 0.008
< 0.012
< 0.008
< 0.022
< 0.017
< 0.007
< 0.005
< 0.003
< 0.016
< 0.015
< 0.007 0.018 +/- 0.005
< 0.014 0.032 +/- 0.011
< 0.012 0.024 +/- 0.009
< 0.013 Cumulative Average 6
POINT BEACH NUCLEAR PLANT
'Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: E-04, North Boundary Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Vol.
Collected (M 3)
Gross Beta 1-131 Date Vol.
Collected (M3)
Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010
.0.030 01-04-07 01-10-07 01-17-07 01-24-07 01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 1st Quarter Mean +/- s.d.
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07 05-09-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07 06-20-07 06-27-07 07-03-07 2nd Quarter Mean +/- s.d.
360 261 308 325 320 312 320 286 381 332 325 307 334 0.027 +/- 0.003 0.029 +/- 0.004 0.018 0.003 0.038 t 0.004 0.029 +/- 0.004 0.034 +/- 0.004 0.025 +/-0.004 0.024 +/- 0.004
.0.018 +/- 0.003 0.012 +0.003 0.024 +/- 0.003 0.020 +/- 0.003 0.017 +/- 0.003
< 0.014
< 0.020
< 0.018
< 0.008
< 0.017
< 0.022
< 0.012'
< 0.010
< 0.012
< 0.009
< 0.010
< 0.012
< 0.017 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-15-07 08-22-07 08-28-07 09-05-07 09-12-07 09-19-07 09-26-07 10-03-07 385 328 334 331 336 331 320 291 382 342 343 342 338 0.022 +/- 0.003 0.011 +/- 0.003 0.021 +/- 0.003 0.027 +/- 0.004 0.029 +/- 0.004 0.020 +/- 0.003 0.015 +-0.003 0.021 +/- 0.004 0.033 +/- 0.003 0.022 +/- 0.003 0.026 +/- 0.003 0.029 +/- 0.004 0.032 +/- 0.004
< 0.006
< 0.012
< 0.008
< 0.010
< 0.014
< 0.007
< 0.011
< 0.015
< 0.007
< 0.008
< 0.011
< 0.017
< 0.013 0.024 +/- 0.007 < 0.014 335 316 347 276 332 353 357 286 335 331 338 330 330 286 0.010 +/- 0.003 0.021 +/- 0.004 0.023 +/- 0.003 0.018 +/- 0.004 0.015 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.018 + 0.004 0.021 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.037 +/- 0.004 0.028 +/- 0.004 0.010 + 0.003
< 0.007
< 0.014
< 0.009
< 0.011
< 0.009
< 0.007
< 0.015
< 0.011
< 0.009
< 0.020
< 0.014
< 0.011
< 0.011
< 0.019 3rd Quarter Mean +/- s.d.
10-11-07 10-18-07 10-25-07 10-31-07 11-07-07 11-15-07
.11-21-07 11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
0.024 +/- 0.006
< 0.011 190 333 344 260 309 350 264 308 308 308 340 343 390 0.033 +/- 0.005 0.018 +/- 0.003 0.017 +/- 0.003 0.027 +/- 0.004 0.018 +/- 0.003 0.024 +/- 0.003 0.020 +/- 0.004 0.029 +/- 0.004 0.026 '+/- 0.004 0.048 +/- 0.005 0.048 +/- 0.004 0.045 +/- 0.004 0.035 +/- 0.003
< 0.017
< 0.014
< 0.007
< 0.012
.< 0.008
<0.016
<0.016
< 0.007
< 0.005
< 0.003
< 0.014
< 0.013
< 0.006 0.020 +/- 0.007 < 0.012 0.030 +/- 0.011 <0.011 Cumulative Average 0.024 +/- 0.009 < 0.0 12 7
POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: E-08, G.J. Francar Residence Units: pCi/m 3 Collection: Continuous, weekly exchange.
Date Vol.
Collected (m3)
Gross Beta 1-131 Date Vol.
Collected (M 3)
Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-07 01-10-07 01-17-07 01-24-07 01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 1st Quarter Mean +/- s.d.
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07 05-11-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07 06-20-07 06-27-07 07-03-07.
2nd Quarter Mean +/- s.d.
351 255 300 305 301 303 303 257 346 302 306 299 304 0.030 +/- 0.004 0.031 +/- 0.004 0.017 +/- 0.003 0.036 +/- 0.004 0.051 +/- 0.005 0.032 +/- 0.004 0.024 +/- 0.004 0.024 +/- 0.004 0.019 +/- 0.003 0.018 +/- 0.004 0.031 + 0.004 0.025 +/- 0.004 0.020 +/- 0.004
< 0.014
< 0.021
< 0.018
< 0.008
< 0.018
< 0.023
< 0.013
< 0.011
< 0.013
< 0.010
< 0.010
< 0.013
<.0.018 0.028 +/- 0.009 < 0.015 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-15-07 08-22-07 08-29-07 09-05-07 09-12-07 09-19-07 09-26-07 10-03-07 3rd Quarter Mean +/- s.d.
10-11-07 10-18-07 10-25-07 10-31-07 11-07-07 11-15-07 11-21-07
.11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
350 299 303 301 305 301 301 306 305 311 313 310 286 0.025 +/- 0.003 0.017 +/- 0.003 0.020 +/- 0.003 0.033 +/- 0.004 0.037 +/- 0.004 0.022 +/- 0.004 0.014 +/- 0.003 0.019 +/- 0.003 0.035 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.004 0.029 +/- 0.004 0.033 +/- 0.004
< 0.007
< 0.013
< 0.009
< 0.012
< 0.016
< 0.008
< 0.012
< 0.013
< 0.009
< 0.009
< 0.012
< 0.019
< 0.015 0.026 +/- 0.007
< 0.012 305 302 320 250 302 407 357 260 305 302 306 299 300 261 0.011 +/- 0.003 0.019 +/- 0.004 0.022 +/- 0.004 0.017 +/- 0.004 0.015 +/- 0.003 0.014 +/- 0.003 0.016 +/- 0.003 0.022 +/- 0.004 0.021 +/- 0.004 0.021 0 0.003 0.025 +/- 0.004 0.032 +/- 0.004 0.027 +/- 0.004 0.010 +/- 0.003
< 0.007
< 0.014
< 0.010
< 0.012
< 0.009
< 0.006
< 0.019
< 0.012
< 0.010
< 0.022
< 0.016
< 0.013
< 0.012
< 0.021 190 305 310 265 311 355 267 312 312 313 310 313 356 0.037 +/- 0.005 0.024 +/- 0.004 0.017 +/- 0.003 0.027 +/- 0.004 0.018 +/- 0.003 0.025 +/- 0.003 0.021 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.004 0.043 +/- 0.004 0.054 +/- 0.004 0.042 +/- 0.004 0.034 +/- 0.003
< 0.017
< 0.015
< 0.008
< 0.012
< 0.008
< 0.024
< 0.016
< 0.007
< 0.005
< 0.003
< 0.016
< 0.014
< 0.007 0.019 +/- 0.006
< 0.013 0.030 +/- 0.011
< 0.012 0.026 +/- 0.010
< 0.013 Cumulative Averane 8
POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters,. analyses for gross beta and iodine-131.
Location: E-20, Silver Lake Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Vol.
Collected (M 3)
Gross Beta 1-131 Date Vol.
Collected (M3)
Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.010 0.030 01-03-07 01-10-07 01-17-07 01-24-07 01-31-07 02-07-07 02-14-07 02-20-07 02-28-07 03-07-07 03-14-07 03-21-07 03-28-07 1 st Quarter Mean + s.d.
04-04-07 04-11-07 04-19-07 04-25-07 05-02-07 05-10-07 05-17-07 05-23-07 05-30-07 06-06-07 06-13-07 06-20-07 06-27-07 07-03-07 2nd Quarter Mean +/- s.d.
303 261 301 303 305 300 304 257 345 303 304 299 304 0.027 +/- 0.004 0.035 +/- 0.004 0.019 +/- 0.003 0.034 +/- 0.004 0.028 +/-10.004 0.031 +0.004 0.025 + 0.004 0.031 +/- 0.005 0.039 + 0.004 0.038 +/- 0.004 0.027 +/- 0.004 0.023 +/- 0.004 0.018 +/-0.004
< 0.017
< 0.020
< 0.018
< 0.008
< 0.017
< 0.023
< 0.013
< 0.011
< 0.013
< 0.010
< 0.010
< 0.013
< 0.018.
0.029 +/- 0.007
< 0.015 07-11-07 07-18-07 07-25-07 08-01-07 08-08-07 08-15-07 08-22-07 08-30-07 09-05-07 09-12-07 09-19-07 09-26-07 10-03-07 3rd Quarter Mean +/- s.d.
10-11-07 10-18-07 10-25-07 10-31-07 11-07-07 11-15-07 11-21-07 11-28-07 12-05-07 12-12-07 12-19-07 12-26-07 01-03-08 4th Quarter Mean +/- s.d.
350 301 299 301 307 299 301 345 259 303 303 300 305 0.026 +/- 0.003 0.019 +/- 0.003 0.020 + 0.003 0.032 +/- 0.004 0.031 +/- 0.004 0.023 +/- 0.004 0.016 +/- 0.003 0.021 +/- 0.003 0.033 +/- 0.005 0.023 +/- 0.004 0.023 +/- 0.003 0.032 +/- 0.004 0.030 +/- 0.004
< 0.007
< 0.013
< 0.009
<0.012
< 0.015
< 0.008
< 0.012
< 0.011
< 0.010
< 0.009
< 0.013
< 0.019
< 0.014 0.025 +/- 0.006
< 0.012 308 301 343 257 303 361 284 260 306 302 308 298 299 261 0.014 +/- 0.003 0.019 +/- 0.004 0.020 +/- 0.003 0.015 +/- 0.004 0.020 +/-.0.004 0.018 +/- 0.003 0.016 +/- 0.004 0.017 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 0.022 +/- 0.004 0.028 +/- 0.004 0.021 +/- 0.003 0.012 +/- 0.003
< 0.007
< 0.014
< 0.009
< 0.011
< 0.009
< 0.007
< 0.015
< 0.012
< 0.010
< 0.022
< 0.015
< 0.013
< 0.012
< 0.021 192 303 300 262 301 345 258 303 304 304 300 303 344 0.037 +/- 0.005 0.021 +/- 0.004 0.021 +/- 0.004 0.035 +/- 0.005 0.016 +/- 0.003 0.026 + 0.003 0.020 +/- 0.004 0.029 +/- 0.004 0.025 +/- 0.004 0.048 +/- 0.005 0.057 +/- 0.004 0.050 +/- 0.005 0.042 0 0.004
< 0.017
< 0.015
< 0.008
< 0.012
< 0.008
< 0.017
< 0.017
< 0.007
< 0.005
< 0.003
< 0.016
< 0.015
< 0.007 0.019 +/- 0.004
< 0.013 0.033 +/- 0.013 <0.011 Cumulative Average 0.026 +/- 0.009
< 0.013 9
POINT BEACH NTUCT EAR PT ANT GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE FILTERS (Concentration pCi/m3) "
Locatior Lab Code Be-7 Cs-1 34 Cs-137 Other Gammasa Volume Reg. LLD 0.01 0.01 (0.10) m 1st Quarter E-01 E-02 E-03 E-04 E-08 E-20 EAP-2184
- 2185
- 2186
- 2187
- 2188
- 2189 0.060 +/- 0.012 0.069 +/- 0.013 0.064 +/- 0.012 0.054 +/- 0.011 0.066 +/- 0.013 0.055 +/- 0.012 0.0002 +/- 0.0005
-0.0001 +/- 0.0005 0.0001 +/- 0.0004
-0.0001 +/- 0.0005
-0.0002 +/- 0.0003 0.0001 +/- 0.0003 0.0001 +/- 0.0005
-0.0005 +/- 0.0006
-0.0002 +/- 0.0005 0.0001 +/- 0.0005
-0.0003 +/- 0.0004
-0.0001 +/- 0.0005
-0.0002+/- 0.0006 3932
-0.0001 +/- 0.0005 3928 0.0004 +/- 0.0003 3824 0.0002 +/- 0.0004
.4171 0.0004 +/- 0.0006 3932
-0.0004 +/- 0.0005 3889 2nd Quarter E-01 E-02 E-03 E-04 E-08 E-20 EAP-4654
- 4655
-4656,7
-4658
-4659
- 4660 0.091 +/- 0.016 0.095 +/- 0.016 0.099 +/- 0.011 0.103 +/- 0.016 0.101 +/- 0.019 0.099 +/- 0.016
-0.0002 +/- 0.0005
-0.0005 +/- 0.0005 0.0004 +/- 0.0005 0.0004 +/- 0.0006
-0.0001 +/- 0.0005
-0.0001 +/- 0.0006
-0.0001 +/- 0.0005 0.0007+/- 0.0006
-0.0003 +/- 0.0005
-0.0003 +/- 0.0005
-0.0001 +/- 0.0005
-0.0002 +/- 0.0005 0.0003 +/- 0.0005 0.0005 +/- 0.0004
-0.0009 +/- 0.0008 0.0005 +/- 0.0006 0.0002 +/- 0.0005 0.0005 +/-.0.0004 4458 4138 4137 4552 4276 4191 3rd Quarter E-01 E-02 E-03 E-04 E-08 E-20 EAP-7418
- 7419
-7420
- 7421
- 7422
-7423 0.082 +/- 0.015 0.078 +/- 0.015 0.062 +/- 0.013 0.079 +/- 0.016 0.091 +/- 0.016 0.079 +/- 0.018 0.0001 +/- 0.0005 0.0002 +/- 0.0005
-0.0005 +/- 0.0005
-0.0003 +/- 0.0005 0.0003 +/- 0.0005
-0.0003 +/- 0.0005
-0.0006 +/- 0.0004
-0.0001 +/- 0.0005
-0.0003 +/- 0.0004 0.0006 +/- 0.0005 0.0002 +/- 0.0005 0.0002 +/- 0.0005 0.0003 +/- 0.0005
-0.0001 +/- 0.0006
-0.0001 +/- 0.0006 0.0004 +/- 0.0003
-0.0003 +/- 0.0005 0.0007 +/- 0.0004 4247 3960 3984 4403 3991 3973 4th Quarter E-0 1 E-02 E-03.
E-04 E-08 E-20 EAP-8913
- 8914
- 8915
- 8916
- 8917
- 8918 0.083 +/- 0.016 0.052 +/- 0.011 0.061 +/- 0.013 0.054 +/- 0.011 0.050 +/- 0.014 0.061 +/- 0.015
-0.0004 +/- 0.0005 0.0002 +/- 0.0004
-0.0001 +/- 0.0003 0.0002 +/- 0.0004
-0.0004 +/- 0.0005 0.0003 +/- 0.0004
-0.0003 +/- 0.0003
-0.0001 +/- 0.0004 0.0000 +/- 0.0004 0.0001 +/- 0.0005
-0.0003 +/- 0.0004 0.0002 +/- 0.0004
-0.0006 +/- 0.0005 4078
-0.0001 +/- 0.0004 3250 0.0005 +/- 0.0005 3810 0.0001 +/- 0.0005 4047 0.0004 +/- 0.0005 3919 0.0004 +/- 0.0005 3819 aSee Introduction 10
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (monthly Collections)
Sample Description and Concentration (pCifL)
Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-137 Ba-La-140 Other Gammasa E-11 Funk Dairy Farm 01-09-07 02-14-07 EMI-85 EMI-965
-0.1 +/- 0.9
-0.7 +/- 0.8 0.4 +/- 0.3 1.0 +/- 0.3 0.14 +/- 0.21
-0:04 +/- 0.24 1376 +/-120 1399 +/-118
-0.8 +/- 2.6 1.1 +/- 2.4 1.7 +/- 3.0
-1.2 +/- 2.7 0.3 +/- 2.4 0.4 +/- 2.2
-3.3 +/- 2.9
-0.8 +/- 2.4 03-14-07 EMI-1403
-1.2 +/- 0.8 1.2 +/- 0.4
-0.01 +/- 0.15 1400 +/-112 1.3 +/- 1.6
-0.1 +/-2.0 0.2 +/-2.1 1.3 +/-2.4 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Collection Date Lab Code Sr-89 Sr-90 1-13 1 K-40 Cs-I 34 Cs-137 Ba-La-I 40 Other Gammas a 04-11-07 EM1-1938
-0.2 +/- 1.0 1.1 +/-0.4
-0.11 +/- 0.19 1417 +/- 109
-2.7 +/- 2.4
-0.3 +/- 2.6 0.8 +/- 2.0 0.2 +/- 2.5 05-09-07 EMI-2678 0.4 +/- 1.0 0.2 +/- 0.3
-0.01 +/- 0.23 1284 +/- 117 0.2 +/- 2.5
-1.3 +/- 2.9 2.0 +/- 2.3 0.4 +/- 2.6 06-13-07 EMI-3585 0.0 +/- 0.7 0.6 +/- 0.3
-0.19 +/- 0.17 1363 +/- 125
-2.3 +/- 2.4
-3.0 +/- 2.8
-1.2 +/- 2.6 3.0 +/- 3.1 Required LLD 5;0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.
11
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)
Sample Description and Concentration (pCi/L)
Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-1 37 Ba-La-140 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa E-1 1 Funk Dairy Farm 07-11-07 08-08-07 EMI-4199 EMI-5222
-0.8 +/- 1.0 0.3 +/- 0.9 0.8 +/- 0.4 0.7 +/- 0.3 0.13 +/- 0.21 0.12 +/- 0.13 1385 +/- 117 1344 +/- 112 0.0 +/- 1.6 0.3 +/- 1.4 0.5 +/- 1.8 0.0 +/- 1.9 0.5 +/- 2.2
-0.3 +/- 1.6
-0.3 +/- 2.4
-1.3 +/- 2.0 10-10-07 11-14-07 EMI-6822 EMI-7850 0.1 +/- 1.0 0.5 +/- 0.8 0.8 +/- 0.4 0.7 +/- 0.3 0.02 +/- 0.18
-0.01 +/- 0.16 1373 +/- 128 1250 +/- 98 1.5 +/- 2.3
-4.5 +/- 2.3
-1.2 +/- 2.6 0.9 +/- 2.4 1.4 +/- 2.5
-0.5 +/- 1.8 0.8 +/- 2.8 0.3 +/- 2.1 09-I12-07 EMI-6028
-0.8 +/- 0.8 0.8 +/- 0.3
-0.18 +/- 0.19 1401 +/- 131 0.7,+/- 2.3 1.0 +/- 2.8 2.3 +/- 2.5
-3.2 +/- 3.1 12-12-07 EMI-8331
-1.1 +/-1.1 1.6 +/- 0.4 0.07 +/- 0.13 1294 +/- 78
-2.4 +/- 1.8
-1.5 +/- 2.0
-0.4 +/- 1.8 0.3 +/- 1.6 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.
12
-I-_.---_
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)
Sample Description and Concentration.(pCi/L)
Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-1 37 Ba-La-140 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37, Ba-La-l 40 Other Gammasa E-21 Strutz Dairy Farm 01-09-07 02-14-07 EMI-86 EMI-966 0.9 +/- 1.1
-0.2 +/- 0.7 0.4 +/- 0.4 0.5 +/- 0.3 0.14 +/- 0.16
-0.15 +/- 0.27 1186+/-11 1499 109
-1.9 +/- 1.9
-6.2 +/- 2.5
-0.7 +/- 2.0
-0.7 +/- 2.7 0.7 +/- 1.6 0.3.+/- 1.9 0.6 +/- 2.7
-0.5 +/- 2.4 04-11-07 05-09-07 EMI-1939 EMI-2679 0.3 +/- 0.8 0.2 +/- 1.1 0.4 +/- 0.3 0.5 +/- 0.4 0.16 +/- 0.23
-0.05 +/- 0.23 1218 +/- 102 1401 +/- 114.
-1.2 +/- 1.6
-0.2 +/- 1.5
-1.4 +/- 2.0
-0.4 +/- 2.0 1.3 +/- 2.0 0.7 +/- 1.2 1.1 +/- 1.8 0.1 +/- 1.9 03-14-07 EMI-1404
-0.1 +/-0.8 0.6 +/- 0.3
-0.10 +/- 0.15 1414 + 131 0.4 +2.1 0.6 +/- 2.7
-0.2 +/- 1.6
-0.4 +/- 2.7 06-13-07 EMI-3586
-0.8 -+/- 0.8 0.5 +/- 0.3'
-0.09 +/- 0.18 1423 +/-111 0.5 +/- 1.3 0.4 +/- 1.8 1.1 +/- 1.8
-0.2 +/- 1.9 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.
13
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)
Sample Description and Concentration (pCi/L)
Collection Date-Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La1 40 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-I 37 Ba-La-140 Other Gammasa E-21 Strutz Dairy Farm 07-1 1-07 08-08-07 EMI-4200 EMI-5223
-0.6 +/- 0.8
-0.6 +/- 0.9 0.8 t 0.4 0.9 t 0.3 0.17 +/- 0.22
-0.32 +/- 0.17 1391 +/- 129 1347 +/-119
-2.7 t 2.5
-2.1 +/- 2.4 1.5 +/- 3.0 0.7 +/- 2.6 1.5 +/- 2.8 0.9 +/- 2.1 2.3 +/- 2.9 1.3 +/- 2.6 10-10-07 11-14-07 EMI-6823 EMI-7851' 0.0 +/- 0.8 0.2 +/- 0.8 0.6 +/- 0.3 0.5 +/- 0.3 0.05 +/- 0.16
-0.11 +/- 0.18 1383 +/- 119 1387 +/-.97
-3.1 +/- 2.5
-0.5 +/- 1.4
-4.9 +/- 3.0 0.6 +/- 1.7
-1.5 +/- 2.4 1.2 +/- 1.9 2.7 +/- 2.3 0.1 +/- 1.9 09-12-07 EMI-6029 0.1 +/- 0.8 0.6 +/- 0.3
-0.10. + 0.21 1573 +/- 128
-7.4 + 3.3
-2.5 +/-3.3
-2.0 + 2.6
-1.4 +/-2.4 12-12-07 EMI-8332
-0.9 +/- 1.0 1.0 +/- 0.4
-0.16 +/- 0.17 1358 +/- 111
-0.4 +/- 1.6
-0.2 +/- 1.9 1.0 +/- 1.7 0.0 +/- 2.1 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.
14
'I L
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)
Sample Description and Concentration (pCi/L)
Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-140 Other Gammasa 01-09-07 EMI-87 0.5 + 1.0.
1.0 +/- 0.4
-0.30 +/- 0.18 1404 +/- 117 0.1 +/-1.6 0.4 +/- 1.9
-2.3 +/- 2.0
-0.5 +/- 1.8 E-40 Barta 02-14-07 EMI-967
-0.6 +/- 0.9 1.0 +/- 0.4
-0.19 +/- 0.20 1330 +/- 112
-0.4 +/- 1.4
-0.3 +/- 1.8
-0.4 +/- 2.0
-1.7 +/- 2.0 03-14-07 EMI-1405
-1.5 +/- 1.0 1.7 +/- 0.4
-0.21 +/- 0.17 1370 +/- 111
-0.3 +/- 2.9
-1.3 +/- 2.9
-1.7 +/- 2.2
-2.7 +/- 2.6 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-140 Other Gammasa 04-11-07 EMI-1940 0.6 +/- 0.9 0.6 +/- 0.3
-0.05 +/- 0.20 1547 +/- 127
-3.7 +/- 2.7 1.5 +/- 2.7
-3.8 +/- 2.5
-0.2 +/- 2.5 05-09-07 EMI-2630 0.3 +/- 1.2 0.8 +/- 0.4
-0.01 +/- 0.19 1403 +/- 114
-3.6 +/- 2.1 1.3 +/- 2.6
-1.3 +/- 1.9 1.9 +/- 2.5 06-13-07 EMI-3587
-0.5 +/- 0.9 0.5 +/- 0.3 0.13 +/- 0.17 1277 +/- 127
-0.6 +/- 2.3
-0.2 +/- 2.8 1.7 +/- 1.9
-5.7 +/- 3.3 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.
15
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLESC (Monthly Collections)
Sample Description and Concentration (pCifL)
Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-140 Other Gammasa 07-11-07 EMI-4201
-1.4 +/- 1.0 1.4 +/-_0.5
-0.08 +/- 0.19 1464 +/- 126 0.1 +/-2.5 0.4 +/- 2.5 1.4 +/- 1.4
-1.3 +/- 2.6 E-40 Barta 08-08-07 EMI-5224
-0.8 +/- 1.0 1.1 +/-_0.4
-0.11 +/-0.16, 1335 +/- 110
-0.9 +/- 2.4 0.9 +/- 2.7
-1.5 +/- 1.8 0.6 +/- 2.0 09-12-07 EMI-6030,1 0.0 +/- 1.0 1.0 +/- 0.3
-0.01 +/- 0.22 1359 +/- 84 0.4 +/- 1.5
-1.7 +/- 3.0 0.3 +/- 1.3
-0.5 +/- 2.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-137 Ba-La-i 40 Other Gammas a 10-10-07 EMI-6824
-0.6 +/- 0.9 0.8 +/- 0.3 0.05 +/- 0.20 1436 +/- 118 0.2 +/- 1.5 1.1 +/- 2.1
-0.2 +/- 2.0 2.3 +/- 2.3 11-14-07 EMI-7852
-0.5 +/- 0.9 1.3 +/- 0.4
-0.02 +/- 0.20 1373 +/- 109 0.3 +/- 1.8
-1.6 +/- 2.3 1.0 +/- 1.7.
-0.3 +/- 2.3 12-12-07 EMI-8333
-2.8 +/- 1.3 2.0 +/- 0.5 0.12 +/- 0.20 1384 +/- 80 0.0 +/- 1.0 1.0 +/- 1.3
-0.2 +/- 1.2
-0.7 +/- 1.4 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 aSee Introduction.
16
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN WELL WATER SAMPLES, E-10 (Quarterly Collections)
Units: pCi/L 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Req.
LLD Collection Date 01-09-07 04-11 -07 07-12-07 10-25-07 Lab Code EWW-178 EWW-2009 EWW-4298,9 EWW-7505 Gross Beta 0.6 +/- 1.8
-0.1 +/- 1.8 2.0 + 0.5 2.9 +/- 1.4 4.0 H-3 76.3 +/- 85.9
-3.8 +/- 99.1 23,1 + 77.7
-34.6 +/- 85.3 500 Sr-89
-0.1 +/- 0.6 0.5 +/- 0.4
-0.1 +/- 0.7 0.0 +/- 0.8 5.0 Sr-90 0.0 +/- 0.2
-0.1 +/- 0.2 0.0 +/- 0.3 0.0 +/- 0.3 1.0 1-131
-0.27 +/- 0.19 0.03 + 0.18
-0.08 + 0.22 0.16 +/- 0.24 0.5 Mn-54
-2.1 +/-3.4 1.1 +/-2.2
-1.6 +/-3.2 1.2 +/-2.0 10 Fe-59
-0.3 +/- 5.0
-0.2 +/- 3.6 1.6 +/- 7.1 2.1 +/- 3.6 30 Co-58
-1.5 +/- 3.1 0.4 +/- 2.0
-1.2 +/- 2.6.
-1.0 +/- 2.0 10 Co-60 0.2 +/- 2.9 1.1 +/- 2.0
-1.0 +/- 3.8
-1.9 +/- 2.2 10 Zn-65 2.6 +/- 5.9
-5.2 +/- 5.0
-12.8 +/- 10.0
-4.6 +/- 4.3 30 Zr-Nb-95
-1.2 +/- 3.1
-0.8 +/- 2.3
-3.5 +/-3.8
-0.7 +/- 2.4 15 Cs-134
-1.6 +/-+3.1
-3.5 +/--2.1
-1.1 +/-3.0
-1.7 +/--2.4 10 Cs-137 0.5 +/- 3.0
-1.9 +/- 2.3 2.3 +/- 3.6 0.5 +/- 2.4 10 Ba-La-140
-0.9 +/- 3.3
-2.7 +/- 2.6
-0.6 +/- 4.4
-1.9 +/- 2.3 15 Other Gammasa
-1.6 +/- 3.2
-2.3 +/- 2.1
-2.5 +/- 3.1
-0.5 +/- 2.2 30 a Ru-103 17 II~-
I
POINT BEACH Lake water, analyses for gross beta, iodine-131 and.gamma emitting isotopes.
Location: E-01 (Meteorological Tower)
Collection: Monthly composites Units: pCi/L Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammas0 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-I 34 Cs-137 Ba-La-140 Other Gammas' Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa ELW-1 82 01-09-07 2.2 t 0.4
-0.22,+ 0.17 25.6 +/- 23.0
-1.2 +/- 2.1 2.2 +/- 5.9 0.8 +/- 2.7 0.5 +/- 1.9
-1.1
+/- 6.4 1.1 +/- 2.6 0.7 +/- 2.3 3.4 +/- 2.5 1.0 +/- 3.0
-1.4 +/- 2.5 ELW-2763 05-09-07 4.7 +/- 0.7
-0.15 +/- 0.24 9.6 +/- 15.4 0.6 +/- 1.4
-0.4 +/- 3.4
-0.7 +/- 1.9 0.2 +/- 2.1
-4.4 +/- 4.8 0.2 +/- 2.1 0.2 +/- 1.9
-1.2 +/- 2.2 2.1 +/-2.6 0.6 +/- 1.9 ELW-6349 09-19-07 1.9 _ 0.3 0.16 +/- 0.18 5.7 +/- 17.8 1.2 +/- 1.8
-0.3 +/- 3.9
-1.0 +/- 1.8
-1.2 +/- 1.9
-4.9 +/- 4.3
-0.9 +/- 2.0 0.9 +/- 1.7 1.5 +/- 2.1 0.7 +/- 1.1
-1.6 +/- 1.7 ELW-958 02-15-07 2.0 +/- 0.6
-0.02 +/- 0.22 50.0 +/- 18.2 0.6 +/- 1.7 0.2 +/- 3.4 1.5 +/- 1.7
-0.2 +/- 1.8
-0.7. +/- 3.9
-1.1 +/- 2.0 0.2 +/- 2.1
-3.6 +/- 2.5
-0.7 +/- 2.0
-0.3 +/- 2.1 ELW-3640 06-13-07 1.4 + 0.4
-0.15 +/- 0.20
-3.5 +/- 12.0 0.9 +/- 1.7
-3.2 +/- 3.4
-0.9 +/- 1.6
-0.4 +/- 1.5
-1.2 +/- 2.6 1.3 +/- 1.4
-0.9 +/- 1.7 1.8 +/- 1.9
-2.3 t 2.3 0.7 +/- 1.4 ELW-1395 03-13-07 3.6 +/- 0.7 0.09 +/- 0.18 24.7 +/- 19.1 1.2 +/- 2.7
-2.0 +/- 4.7
-0.7 +/- 2.4
-2.1 +/- 2.9 2.9 +/- 4.7 1.6 +/- 2.4 0.6 +/- 1.9 0.3 +/- 2.4
-3.0 +/- 3.6
-0.7 +/- 2.3 ELW-4293 07-12-07 2.3 +/- 0.6
-0.01 +/- 0.21 2.0 +/- 24.3
- -0.6
+/- 2.9 3.4 +/- 5.5 2.6 +/- 2.7.
-1.4 +/- 4.0 0.9 +/- 8.2 1.0 +/- 2.7
-3.9 +/- 3.4
-5.3 +/- 3.5 5.2 +/- 3.7
-1.2 +/- 3.1 ELW-7876 11-14-07 4.1 +/- 1.1 0.08 +/- 0.18 3.9 +/- 14.3
-0.8 + 1.5 0.1 +/- 3:1
-1.1
+/- 1.6 0.7 +/- 1.3
-0.3 +/- 3.2 1.7 +/- 1.9
-0.6 +/- 1.9
-3.0 +/- 2.0 0.5 +/- 1.5
-1.5 +/- 1.6 ELW-1957 04-11-07 2.1 +/- 0.3
-0.26 +/- 0.22
-1.6 +/- 15.7
-1.2 +/- 1.9
-4.7 +/- 4.1 1.2 +/- 2.1
-1.2 +/- 2.4
-5.0 +/- 4.3 0.4 +/- 2.2
-0.7 +/- 1.7 1.5 +/- 2.3
-0.8 +/- 2.3
-1.3:+/- 1.9 ELW-5464 08-16-07 1.6 +/-' 1.1 0.14 +/- 0.17
-23.9 +/- 24.0 0.2 +/- 3.2
-2.3 +/- 5.9
-3.0 +/- 2.5
-3.5 +/- 3.7
-0.1 +/- 6.5
-3.9 +/- 3.1
-6.8 +/- 3.4
-1.0 +/- 4.0 0.4 +/- 4.0
-2.3 2.7 ELW-8373 12-13-07 3.0 +/- 0.9
-0.14 +/- 0.18
-11.2 +/- 15.7
-0.3 +/- 1.5
-3.2 +/- 3.0
-0.3 + 1.7
-0.2 +/- 1.6
-1.7 + 3.3
-0.8 +/- 1.8
-2.0 +/- 2.0 0.8 +/- 1.9
-1.7 _ 1.8
-0.3 +/- 1.7 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0.
0.5 10 30 10 10 30 15 10 10 15 30 ELW-6861 10-09-07 2.1 +/- 1.0 0.03 + 0.23 J7.4 +/-22.6
-1.5 + 2.4 0.9 +/- 6.4
.2.4 +/- 2.6
-1.4 +/- 3.4 2.3 +/- 5.2
-1.2 +/- 2.4
-2.0 +/- 2.8 2.5 +/- 2.9 2.9 +/- 3.2 1.4 +/- 2.7 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 -
18
POINT BEACH Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.
Location: E-05 (Two Creeks Park)
Collection: Monthly composites Units: pCi/L Lab Code
-Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammas8 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa ELW-183 01-09-07 3.7 +/- 0.5
-0.19 +/- 0.17
-6.8 +/- 26.1 1.3 +/- 5.0
-1.5 +/- 5.8 0.0 +/- 2.9 0.4 +/- 3.3
-2.1 +/- 6.5 1.6 +/- 2.3 0.3 +/- 2.9
-0.7 +/- 3.3
-4.3 +/- 3.7 0.5 +/- 3.2 ELW-2764 05-09-07 4.2 +/- 0.7
-0.12 +/- 0.24
-9.9 +/- 10.9
-0.7 +/- 1.3 0.3 +/- 2.7
-0.1
+/- 1.2 0.1 +/-1.3 0.4 +/- 2.7
-0.2 +/- 1.5 0.6 +/- 1.3 0.6 +/- 1.4
-2.7 +/- 1.8
-1.4 +/- 1.2 ELW-6053 09-11-07 1.4 +/- 0.3 0:08 + 0.21 10.6 +/- 14.5 2.3 +/- 1.9
-2.0 +/- 3.4
-0.3 +/- 1.6
-0.5 +/- 1.8 0.6 +/- 3.6
-3.0 +/- 1.9
-0.8 +/- 1.3 0.3 _ 1.6 0.7 +/- 1.1
-2.0 +/- 1.9 NSb ELW-1396 03-13-07 4.3 +/- 0.7
-0.01
- -5.6
-0.9 0.3 0.6 0.8
-2.0
-1.4 0.3
-0.9
-0.5
-0.4
+/-
+/-
+/-
+/-
+/-
+
+/-
+/-
+/-
+/-
+/-
+/-
0.14 13.1 1.4 3.1 1.6 1.9 3.1 2.0 1.3 1.6 2.0 1.6 ELW-3641 06-13-07 1.4 +/- 0.3
-0.01 +/- 0.23 1.1 +/- 20.0 0.6 +/- 1.9 2.4 +/- 3.8 1.7 + 2.0
-0.2 +/- 2.0.
-3.4 +/- 4.2 1.4 +/- 2.0
-2.3 +/- 2.2
-0.2 +/- 2.2 1.7 +/- 2.2
-1.6 +/- 2.0 ELW-6862 10-09-07 2.6 +/- 1.0 0.01 +/- 0.19
-2.4 +/- 22.7 1.9 +/- 3.3 0.5 +/- 5.0 0.9 +/- 2.1 1.0 +/- 2.6 0.2 +/- 7.8 1.5 +/- 2.5
-6.4 +/- 3.7
-0.7 _ 3.3
-3.4 +/- 4.1 1.0 + 2.5 ELW-4294 07-12-07 1.8 +/- 0.5
-0.01 +/- 0.17 1.5 +/- 28.4 1.4 +/- 3.3 1.4 -
6.5
-1.5 +/- 3.1 1.8 +/- 4.6
-0.4 +/- 6.5 2.5 +/- 3.4
-0.5 +/- 2.5 2.7 +/- 2.8
-4.3.+/- 4.1
-2.2 +/- 3.4 ELW-7877 11-14-07 2.2 +/--1.0
-0.11 +/- 0.16
-7.7 +/- 11.3 0.9 +/- 1.2
-1.0 +/- 2.1 0.1 +/- 1.2 1.6 +/- 1.4
-0.3 +/- 2.6
-1.2 +/- 1.5 0.1 : 1.2 0.3 +/- 1.2
-2.7 +/- 1.4
-0.3 +/- 1.4 ELW-1958 04-11-07 2.7 +/- 0.4
-0.35 +/- 0.21
-9.1 + 16.0
-0.3 +/- 1.9 2.8 +/- 3.2
-0.1 +/- 1.8 1.1 +/- 1.6
-1.8 +/- 3.8 2.6 +/- 1.9
-0.5 +/- 1.8
-1.4 +/- 2.2
-2.6 +/- 2.3
-0.5 +/- 1.9 ELW-5465 08-16-07 3.7 +/- 1.1 0.02 +/- 0.20 4,5 +/- 18.8 0.7 +/- 1.8
-0:8 +/- 4.4
-2.0 +/- 2.0 0.9 +/- 1.8
-2.4 +/- 4.4
-0.9 +/- 2.1 0.1 +/- 1.9 1.8 +/- 2.5 0.3 +/- 2.6
-0.1 +/- 1.8 ELW-8374 12-13-07 3.2 + 0.9 0.13 +/- 0.16 18.2 + 16.7 0.3 +/- 1.8 3.0 +/- 3.8 0.6. +/- 1.8 0.9 +/- 1.8
-3.3 +/- 3.8 0.9 +/- 1.8
-1.0 +/- 2.1 1.6 +/- 2.0
-4.9 +/- 2.4
-0.8 +/- 1.8 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0 0.5 10 30 i0 10 30 15 10 10 15 30 4.0 0.5 10 30 10 10 30 15 10-10 15 30 a RU-103
,",NS, = No sample; see Table 2.0, Listing of Missed Samples.
19
POINT BEACH Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.
Location: E-06 (Coast Guard Station)
Collection: Monthly composites Units: pCiIL Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65, Zr-Nb-95 Cs-134 Cs-1 37 Ba-La-140 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa ELW-184 01-09-07 2.6 +/- 0.4
-0.09 +/- 0.15
-9.6 +/- 25.7 0.8 +/- 2.6 3.2 +/- 5.7 3.0 + 2.4 0.7 - 3.3
-4.1 +/- 5.8 1.0 +/- 2.7
-1.5 +/- 2.4 0.5 +/- 2.9
-3.8 +/- 2.9
-3.6 + 3.1 ELW-2765 05-09-07 2.5 +/- 0.6 0.08 +/- 0.22
-33.3 23.8 2.7 +/- 2.8
-2.4 +/- 4.9 2.2 + 3.2 0.6 +/- 3.0 0.5 +/- 6.7 1.3 +/- 2.2 0.3 +/- 2.5
-1.4 + 2.8
-2.4 +/- 3.1 0.7 + 2.9 ELW-6054 09-11-07 1.5 +/- 0.3 0.02 + 0.17
-13.2 +/- 23.2
-0.8 2.4 1.2 +/- 4.8
-0.3 +/- 3.1
-2.0 +/- 3.2
-1.0 t 6.9 0.7 +/- 3.2
-1.0 +/- 3.5 0.4 +/- 3.3 4.6 +/- 3.0 0.2 +/- 2.5 NSb ELW-3642 06-13-07 1.6 +/- 0.4.
-0.14 +/- 0.19 6.4 +/-.18.4 0.4 +/- 2.3
-1.3 +/- 3.9
-0.3 +/- 2.1
-1.7 +/- 2.1
-1.1
+/- 4.7
-0.3 +/- 2.4
-0.4 +/- 2.0
-0.8 +/- 2.2
-1.2 +/- 2.8
-1.2 +/- 2.1 ELW-6863 10-09-07 2.0 +/- 1.0 0.03 +/- 0.19 6.1 +/- 14.2 2.7 +/- 2.0
-0.7 +/- 3.4
-1.3 +/- 1.7
-0.5 +/- 2.3
-6.4 +/- 4.1 0.8 +/- 2.1
-1.7 +/- 1.6
-0.2 +/- 2.3 1.7 +/- 2.6
-1.7 +/- 2.1 ELW-1397 03-13-07 3.1 +/- 0.7
-0.03 +/- 0.14
-3.1 +/- 17.1 0.3 +/- 2.1 0.4 +/- 3.3 2.7 +/- 2.0 0.6 +/- 2.1 2.1 +/- 3.8
-0.2 + 2.1
-3.3 + 2.0 0.5 +/- 2.5
-2.0 +/- 2.5 0.3 +/- 1.8 ELW-4295 07-12-07 1.7 + 0.6 0.18 +/- 0.21 13.8 + 26.4
-2.7 +/- 3.5 9.4
.6.5
-2.8 +/- 3.5 1.1 + 2.4 2.2 +/-6.2
- 1.6 +/- 3.5
-0.3 + 3.3 0.3 +/- 3.6 8.3 +/- 4.5 0.3 + 3.5 ELW-7878 11-14-07 2.1 +/- 1.0 0.10 +/- 0.15 5.7 +/- 14.3
-0.2 +/- 1.5 0.1 +/- 2.7 0.2
.1.7 0.0 +/- 1.6
-4.0 1 3.7 1.3 + 1.8 0.0 +/- 1.5
-0.7 +/- 2.0
-0.9
_ 1.6 0.9 + 1.7 ELW-1959 04-11-07 2.5 +/- 0.4
-0.08 +/- 0.21
-1.5 +/- 16.3 0.3 +/- 2.2
-1.0 +/- 4.4
-0.2 +/- 2.3
-1.2 +/- 2.0
-4.2 +-4.1
-0.4 +/- 2.4
-1.1 +/-1.8 1.7 +/- 2.0
-2.9 + 2.5 0.5 +/- 1.9 ELW-5466 08-16-07 9.7 +/- 1.3c 0.12 +/- 0.26 8.8 +/- 19.6
-1.0 +/- 2.1
-2.8 +/- 3.7 1.5 +/- 2.3 0.8 +/- 2.1
-3.9 +/- 4.2 3.3 +/- 2.2
-2.4 +/- 2.2 1.0 +/- 2.7
-2.6 +/- 2.5
-2.1
+/- 2.1 ELW-8375 12-13-07 4.1
+/- 0.9
-0.06 + 0.17 4.1
+/- 12.6 0.4.+/- 1.6
-0.5 + 2.3
-0.2 + 1.4 1.0 +/- 1.4
-0.8
+/- 2.7
-0.9 +/- 1.5 0.2 +/- 1.3 0.0 +/- 1.4
-1.5
+/- 1.7
-0.9 +/- 1.4 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 bNS" = No sample; see Table 2.0, Listing of Missed Samples.
c Gross beta repeated with a result of 7.3+/-0.8 pCj/L. Reanalysis after filtering = 6.4+/-2.0 pC i/L.
20 II.
POINT BEACH Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.
Location: E-33 (Nature Conservancy)
Collection: Monthly composites Units: pCi/L Lab Code Date Collected Gross beta 1-131 Be-7.
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1i34 Cs-137 Ba-La-140 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-i40 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other Gammasa ELW-185
- 01-09-07 3.5 +/- 0.5
-0.07 +/- 0.18 4.2 +/- 27.2
-0.2 +/- 2.6 0.7 +/- 6.0 1.6 +/- 2.7
-3.6 +/- 3.3
-3.5 +/- 6.0 0.8 +/- 2.9
-0.1 +/- 3.4 0.7 +/- 3.7 2.5 +/- 3.8 1.5 +/- 2.8 ELW-2766 05-09-07 2.0 +/- 0.6
-0.23 +/- 0.24
-11.1 +/- 19.8
-1.6 +/- 2.9
-9.1 +/- 6.2 3.2 +/- 2.5 1.9 +/- 3.8
-8.0 +/- 6.2
-3.0 +/- 2.8
-2.7 +/- 3.0
-0.5 +/- 3.0
-5.5 +/- 4.2
-1.0 +/- 2.8 ELW-6350 09-19-07 2.7 +/- 0.4 0.09 +/- 0.21
-11.6 +/- 17.9
-0.2 +/- 1.7 0.2 +/- 3.8
'0.2 +/- 1.9 1.8 +/- 1.7
-0.9 +/- 4.0
-0.7 +/- 2.0 0.9 +/- 1.6
-1.8 +/- 2.1 3.0 +/- 2.0 1.0 +/- 1.9 ELW-959 02-15-07 2.3 +/- 0.6
-0.14 +/- 0.19 0.6 +/- 12.9 0.8 +/- 1.3 1.3 +/- 2.5 0.1 +/- 1.5
-0.2 +/- 1.5
-2.6 +/- 2.7
-0.3 +/-.1.7 1.1 +/- 1.2
-1.0 +/- 1.4 0.7 +/- 1.3
-0.9 +/- 1.3 ELW-3643 06-13-07 1.3 +/- 0.3 0.02 +/- 0.18
-7.0 +/- 14.4
-0.3 +/- 1.8
-0.2 +/- 3.0 1.8 +/- 1.7
-0.4 1 1.2
-1.8 +/- 3.2
-0.3 +/- 1.7
-0.8 +/- 1.5
-0.4 +/- 1.6
-1.1 +/- 2.0 0.7 +/- 1.7 ELW-6864 10-09-07 2.1 +/- 1.0 0.17 +/- 0.25 5.3 +/- 17.3 1.0 +/- 2.0
-2.0 +/- 3.3 0.6 +/- 2.1 1.0 +/- 1.9
-0.2 +/- 3.5
-0.2 +/- 2.2
-2.2 +/- 2.2 1.3 +/- 2.2 2.9 +/- 1.9
-2.3 +/- 2.0 ELW-1398 03-13-07 6.4 +/- 0.8 0.03 +/- 0.12
-8.6 +/- 19.1 0.2 +/- 2.3 1.5 +/- 3.9 2.0 +/- 1.8 0.6 +/- 1.6
-4.3 +/- 4.3
-0.9 +/- 1.9 0.0 +/- 2.1 0.5 +/- 2.2 5.8 +/- 3.6 0.5 +/- 2.0 ELW-4296 07-12-07 3.8 +/- 0.7 0.08 +/- 0.16 7.2 +/- 18.0 0.5 +/- 1.8
-4.3 +/- 4.3 2.0 +/- 2.1 1.1 +/- 2.O
-2.1 +/- 4.3 0.2 +/- 2.4 0.1 +/- 2.2 1.3 +/- 2.4 0.1 +/- 2.8
-0.7 +/- 1.9 ELW-7879 11-14-07 2.2 + 1.0 0.04 +/- 0.14 9.8 + 16.8 0.4 +/- 1.9
-3.6 +/- 4.0 0.9 +/- 1.9 0.2 +/- 1.8
-1.6 + 3:3 0.9 + 2.0 1.1 +/- 1,9
-1.8
+/- 2,3
-0.4 +/- 2,4 0.0 +/- 2.0 ELW-1 960 04-11-07 2.8 +/- 0.4 0.02 +/- 0.22
- -27.8 +/- 29.0 1.8 +/- 3.3
-2.2 +/- 7.3
-0.3 +/- 3.4 1.6 +/-4.1
-2.9 +/- 6.8 1.6 +/- 3.7
-1.3 +/- 2.9 1.0 +/- 3.1 2.3 +/- 3.5 0.4 +/- 3.0 ELW-5467 08-16-07 2.5 +/- 1.0 0.06 t 0.19
-18.5 +/- 26.4
-4.0 +/- 3.3 1.0 +/- 6.2
-4.0 +/- 3.3
-0.7 +/- 3.7 0.7 +/- 6.4 0.5 +/- 3.2
-1.1
+/- 3.0 0.6 +/- 3.5 0.3 +/- 3.2
-0.3 +/- 3.4 ELW-8376 12-13-07 1.0 +/- 0.4 0.08 +/- 0.16 9.2 -1 13.4
-0.2 +/- 1.4 0.5 +/- 2.9
-0.9 +/- 1.6"
-0.6 +/- 1.8
-2.3 +/- 3.2
-1.3 +/- 1.7
-1.1
+/- 1.5 1.1 +/- 1.7
-4.4
. 2.0
-0.4 +/- 1.7 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 21
POINT BEACH Lake water, analyses for tritium, strontium-89 and strontium-90.
Collection: Quarterly composites of weekly grab samples Units: pCi/L Location E-01 (Meteorological Tower)
Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code ELW-2222 ELW-4276 ELW-7137 ELW-8631 H-3 71 +/-92 74 +/- 96
-70 +/- 97 51 +/- 82 Sr-89 0.38 +/- 1.22
-0.33 +/- 1.21
-1.04 +/- 1.13
-0.33 +/- 0.83 Sr-90 0.27 +/- 0.32 0.21 +/- 0.38 0.50 +/- 0.29 0.31 +/- 0.34 Location E-05 (Two Creeks Park)
Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code ELW-2223 ELW-4277,8 ELW-7138 ELW-8632 H-3 171 +/-96 56 +/-95
-123 +/-_95 29 +/-:81 Sr-89
-0.27 +/- 1.04 0.24 +/- 0.89 0.72 +/- 1.12 1.34 +/- 0.99 Sr-90 0.38 +/- 0.29 0.19 +/- 0.28 0.17 +/- 0.26
-0.30 +/- 0.30 Location E-06 (Coast Guard Station)
Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code ELW-2224 ELW-4279 ELW-7139 ELW-8633 H-3 45 +/- 91 64 +/- 95
-132 +/- 95 33 +/- 81 Sr-89
-0.03 +/- 0.96
-0.71 +/- 0.90 0.16 +/- 1.02
-0.16 +/- 0.95 Sr-90 0.25 +/- 0.26 0.28 +/-.0.31 0.31 +/- 0.26 0.56 +/- 0.41 Location E-33 (Nature Conservancy)
Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code ELW-2225 ELW-4280 ELW-7140 ELW-8634,5 H-3
-43 +/- 88 79 +/- 96
-68 +/- 97 31 +/- 81 Sr-89
-0.32 +/- 1.02 0.37 +/- 1.16
-0.19 +/- 1.09 0.21 +/- 0.69 Sr-90 0.32 +/- 0.28 0.45 +/- 0.35 0.35 +/- 0.27 0.32 +/- 0.28 Note: pages 23 and 24 are intentionally left out.
22
POI)TNT BPACH NTICTLFAR PLANT Fish, analyses for gross beta and gamma emitting isotopes.
Location: E-13 Collection: 3x/Iyear Units:
pCi/g wet Sample Description and Concentration Required LLD Collection Date Lab Code
- Type Ratio (wet/dry wt.)
Gross Beta K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-1 34 Cs-i 37 Other Gammas" Collection Date Lab Code Type Ratio (wet/dry wt.)
Gross Beta K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Other Gammasa 01-27-07 EF-1409 Brown Trout 3.12 4.27 +/- 0.13 2.50 +/- 0.35 0.001 +/- 0.008
-0.002 +/- 0.014
.0.011 +/-0.008
-0.001 +/- 0.007 0.027 +/- 0.015 0.001 +/- 0.008 0.016 +/-0.010
-0.019 +/- 0.007 08-16-07 EF-5404 Brown Trout 3.12 5.29 +/- 0.1.1 3.45 +/- 0.41
-0.002 +/- 0.009
-0.022 +/- 0.016 0.007 +/- 0;008 0.002 +/- 0.010
-0.006 +/- 0.020 0.007 +/- 0.006 0.031 +/- 0.016
-0.001 +/- 0.007 02-10-07 EF-1410 Rainbow Trout 2.97 5.16 +/-0.13 3.22 +/- 0.38
-0.007 +/- 0.008
-0.026 +/- 0.012 0.016 +/- 0.008 0.000 +/- 0.008 0.012 +/- 0.018 0.000 +/- 0.005 0.039 +/- 0.016
-0.003 +/- 0.006.
08-16-07 EF-5405 Salmon 2.05 4.64 +/- 0.10 2.79 +/- 0.37 0.003 +/- 0.008
-0.009 +/- 0.019 0.000 +/- 0.019 0.002 +/- 0.008
-0.032 +/- 0.020 0.000 +/- 0.007 0.049 +/- 0.014
-0.006 +/- 0.007 03-03-07 EF-1411 Brown Trout 3.20 4.48 +/- 0.16 3.1.8 +/- 0.39
-0.007 +/- 0.010
-0.010 +/- 0.018 0.004 +/- 0.008 0.005 +/- 0.010
-0.002 +/- 0.021
-0.006 +/- 0.009 0.031 +/- 0.012
-0.002 +/- 0.008 12-11-07 EF-8327 Lake Trout 2.61 3.28 +/- 0.06 2.58 +/- 0.47
-0.014 +/- 0.014
-0.033 +/- 0.025 0.001 +/- 0.013
-0.004 +/- 0.016 0.002 +/- 0.029
-0.004 +/- 0.011 0.013 +/- 0.016
-0.014 +/- 0.010 08-16-07 EF-5403 Brown Trout 3.22 +/- 0.08 2.28 +/- 0.35
-0.002 +/- 0.009
-0.017 +/- 0.019 0.007 +/- 0.007
-0.003 +/- 0.009
-0.011 +/- 0.021 0.003 +/- 0.010 0.043 +/- 0.024
-0.002 +/- 0.008 12-11-07 EF-8328,29 Lake Trout 5.11 3.99 +/- 0.06 2.76 +/- 0.29
-0.014 +/- 0.014 0.012 +/- 0.017
-0.010 +/- 0.008
-0.007 +/- 0.009
-0.015 +/- 0.020
-0.010 +/- 0.008 0.018 +/- 0.011
-0.014 +/- 0.010 0.5 0.13 0.26 0.13 0.13 0.26 0.13 0.15 0.5
" Ru-103 25
Pfl)TNJT 1P PA (HMT TC1.VA R PT A NT Fish, analyses for gross beta and gamma emitting isotopes.
Location: E-13 Collection: 3x year Units: pCi/g wet Sample Description and Concentration (pCi/g wet)
Required LLD Collection Date 12-11-07 Lab Code EF-8330 Type Lake Trout Ratio (wet/dry wt.)
4.68 Gross Beta 3.28 +/- 0.07 0.5 K-40 2.25 +/- 0.41 Mn-54
-0.003 +/- 0.011 0.13 Fe-59
-0.010 +/- 0.022 0.26 Co-58 0.000 +/- 0.011 0.13 Co-60 0.005 +/- 0.012
'0.13 Zn-65 0.023 +/- 0.022 0.26 Cs-134
-0.005 +/- 0.009 0.13 Cs-137 0.023 +/- 0.013 0.15 Other Gammasa
-0.013 +/- 0.009 0.5 a Ru-103 NOTE: Page 27 is intentionally left out.
26
POINT BEACH NUJCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)
Sample Description and Concentration (pCi/g dry)
Collection Date Lab Code 4/11/2007 ESS-2011 4/11/2007 ESS-2012 E-05 4/11/2007 ESS-2013 Required LLD -
Location E-01 E-06 Gross Beta 8.94 +/- 1.76 16.82 +/- 2.03 Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 0.047 +/- 0.055 4.55 +/- 0.32 0.016 +/- 0.009 0.078 +/- 0.021 0.24 +/- 0.026 0.19 +/- 0.028 0.48 +/- 0.20 0.30 +/- 0.060 0.050 +/- 0.040 7.14 +/- 0.40 0.012 +/- 0.006 0.035 +/- 0.011 0.10 + 0.017 0.08 +/- 0.029 0.36 +/- 0.13 0.20 0.054 16.23 +/- 2.30 0.020 +/- 0.064 8.65 +/- 0.51 0.041 +/- 0.020 0.043 +/- 0.019 0.09 +/- 0.017 0.09 +/- 0.031 0.32 +/- 0.14 0.07 +/- 0.039 2.0 0.15 Collection Date Lab Code Location 4/11/2007 ESS-2014 4/11/2007 ESS-2015 E-33 E-12 Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 14.43 +/- 2.01 0.039 +/- 0.055 7.84 +/- 0.45 0.019 +/- 0.010 0.038 +/- 0.017 0.10 +/- 0.018 0.09 +/- 0.025 0.32 +/- 0.14 0.13 +/- 0.063 13.85 +/- 2.19 0.042 +/- 0.053 6.09 +/- 0.39 0.022 +/- 0.012 0.043 +/- 0.017 0.12 +/- 0.039 0.07 +/- 0.023 0.31 +/- 0.12 0.17 +/- 0.048 2.0 0.15 28
PC)MNT RVA (R XTT TIPA R PT.A 11T RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)
Sample Description and Concentration (pCilg dry)
Collection Date Lab Code 10/9/2007 ESS-6869 Location E-01 Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 12.13 +/- 2.09 0.078 +/- 0.061 5.75 +/- 0.40 0.033 +/- 0.014 0.085 +/- 0.023 0.24 +/- 0.058 0.18 +/- 0.031 0.32 +/- 0.14 0.25 +/- 0.072 10/9/2007 ESS-6870,1 E-05 19.90 +/- 1.51 0.106 +/- 0.076 9.95 +/- 0.66 0.016 +/- 0,012 0.053 +/- 0.015 0.13 +/- 0.016 0.18 +/- 0.033 0.19 +/- 0.17 0.22 +/- 0.064 10/9/2007 ESS-6872 Required LLD 11.43 +/- 1.63 0.064 +/- 0.065 6.39 +/- 0.59 0.007 +/- 0.012 0.034+/- 0.012 0.08 +/- 0.020 0.13 +/- 0.037 0.31 +/- 0.15 0.14 +/- 0.077 2.0 0.15
- E-06 Collection Date Lab Code Location 10/9/2007 ESS-6873 10/9/2007 ESS-6874 E-33 E-12 Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 18.61 +/- 2.11 0.057 +/- 0.057 8.54 +/- 0.50 0.001 +/- 0.007 0.059 +/- 0.018 0.14 +/- 0.031 0.10 +/- 0.028 0.43 +/- 0.15 0.22 +/- 0.069 10.31 +/- 1.51 0.143 +/- 0.060 7.32 +/- 0.05 0.032 +/- 0.018 0.046 +/- 0.019 0.13 +/- 0.051 0.10 +/- 0.024 0.28 +/- 0.13 0.15 +/- 0.041 2.0 0.15 29 41.
POINIT BEACH NUJCLEAR PL.ANJT RADIOACTIVITY IN SOIL SAMPLES
.(Semiannual Collections)
Sample Description and Concentration (pCi/g dry)
Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 5/31/2007 ESO-3415 E-01 33.23 + 2.91
-0.04 + 0.14 15.46 1.10 0.22 +/- 0.048 0.19 +0.044 0.49 +/- 0.053 0.39 + 0.083 0.94 +/- 0.38 0.59 +/- 0.18 5/31/2007 ESO-3419 E-04 28.72 +/- 2.24 0.15 +/- 0.09 17.34 +/- 0.82 0.15 +/- 0.027 0.18 +/- 0.032 0.48 +/- 0.047 0.33 +/- 0.044 0.98 +/- 0.28 0.74 +/- 0.13 5/31/2007 ESO-3422 E-09 35.96 +/- 2.47 0.12 +/- 0.09 21.16 +/- 0.93 0.17 +/- 0.033 0.20 +/- 0.029 0.50 +/- 0.041 0.42 +/- 0.056 1.08 +/- 0.31 0.56 +/- 0.10 5/31/2007 ESO-3416,7 E-02 22.67 +/- 1.66 0.17 +/- 0.08 12.31 +/- 0.52 0.15 +/- 0.023 0.11 +/- 0.016 0.33 +/- 0.023 0.21 +/- 0.033 0.58 +/- 0.19 0.42 +/- 0.07 5/31/2007 ESO-3420 E-06 26.76 +/- 2.10 0.09 +/- 0.10 15.10 +/- 0.93 0.22 +/- 0.038 0.12.+/- 0.035 0.27 +/- 0.038 0.24 +/- 0.053 0.53 +/- 0.31 0.45 +/- 0.13 5/31/2007 ESO-3423 E-20 35.15 +/- 2.96
-0.03 +/-,0.15 13.80 +/- 1.21 0.04 +/- 0.025 0.18 +/- 0.046 0.44 +/- 0.052 0.33 +/- 0.101 1.06 +/-.0.41 0.51 +/- 0.16 5/31/2007 ESO-3418 E-03 34.82 +/- 2.43 0.02 +/- 0.11 21.34 1 0.94 0.35 +/- 0.037 0.27 +/- 0.042 0.87 +/- 0.116 0.48 +/- 0.055 1.73 +/- 0.35 0.83 +/- 0.14 Required LLD 2.0 0.15 5/31/2007 ESO-3421 E-08 25.32 +/- 2.01 0.03 +/- 0.08 13.24 +/-+0.69 0.24 +/- 0.031 0.09 +/- 0.026 0.32 +/- 0.083 0.15 +/- 0.037 0.83 +/- 0.24 0.33 +/- 0.07 2.0 0.15
.2.0 0.15 30
POINT BEACH NIUCLEAR PLANT RADIOACTIVITY IN SOIL SAMPLES (Semiannual Collections)
Sample Description and Concentration (pCi/g dry)
Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 10/26/2007 ESO-7506 E-01 29.30 +/- 2.86 0.01 +/- 0.08 14.04 +/- 0.74 0.12 +/- 0.027 0.14 +/- 0.028 0.43 +/- 0.093 0.32 +/- 0.046 0.67 +/- 0.26 0.46 +/- 0.08 10/26/2007 ESO-7510 E-04 23.91 +/- 3.19 0.03 +/- 0.09 13.88 +/- 0.75 0.26 +/- 0.034 0.15 +/- 0.029 0.46 +/- 0.093 0.35 +/- 0.044 0.79 +/- 0.28 0.51 +/- 0.11 10/26/2007 ESO-7513 E-09 38.35 +/- 2.87 0.17 +/- 0.09 20.25 +/- 0.87 0.14 +/- 0.026 0.20 +/- 0.031 0.57 +/- 0.041 0.43 +/- 0.051 0.89 +/- 0.29 0.66 +/-0.15 10/26/2007 ESO-7507 E-02 37.61 + 2.79 0.14 +/- 0.08 19.32 +/- 0.82 0.14 +/-0.029 0.20 1 0.037 0.65 +/- 0.094 0.45 +/- 0.047 0.94 +/- 0.28 0.58 +/- 0.12 10/26/2007 ESO-7511 E-06 23.76 +/- 3.62 0.08 +/- 0.06 13.02 +/- 0.63 0.27 +/- 0.029 0.10 +/- 0.023 0.31 +/- 0.028 0.30 +/- 0.036 0.75 +/- 0.02 0.39 +/- 0.09 10/26/2007 ESO-7514 E-20 35.71 +/- 2.76 0.04 +/- 0.10 18.07 +/- 0.88 0.15 +/- 0.033 0.16 +/- 0.029 0.57 +/- 0.111 0.40 +/- 0.056 1.18 +/- 0.47 0.58 +/- 0.13 10/26/2007 ESO-7508,9 E-03 35.84 +/- 2.05
-0.04 +/- 0.10 17.14 +/- 0.67 0.29 +/- 0.033 0.19 +/- 0.028 0.56 +/- 0.031 0.44 +/- 0.043 0.99 +/- 0.25 0.69 +/- 0.09
.10/26/2007 ESO-7512 E-08 28.92 +/- 2.80 0.06 +/- 0.09 13.57 +/- 0.74 0.25 + 0.038 0.09 +/- 0.018 0.28 +/- 0.037 0.24 +/- 0.043 0.57 +/- 0.03 0.30 +/- 0.08 Required LLD 2.0 0.15 2.0.
0.15 2.0 0.15 31
PhINT R ACI4 \\H TC 1P A R P1 ANTT RADIOACTIVITY IN VEGETATION SAMPLES (Tni-Annual Collections)
Sample Description and Concentration (pCilg wet)
Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta E-01 5/31/2007 EG-3301 3.87 9.38 +/- 0.41 E-02 5/31/2007 EG-3302 3.93 9.69 +/- 0.33 E-03 5/31/2007 EG-3303 4.52 7.19 +/- 0.22 Req. LLD 0.25 Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" 1.00 +/- 0.41 4.77 +/- 0.77
-0.004 +/- 0.017
-0.016 +/- 0.017 0.001 +/- 0.019
-0.018 +/- 0.019 0.87 +/- 0.32 5.48 +/- 0.69 0.004 +/- 0.013 0.002 +/- 0.017 0.009 +/- 0.015
-0.005 +/- 0.019 0.41 +/-0.18 6.02 +/- 0.88
-0.025 +/- 0.020
-0.008 +/- 0.019
-0.005 1 0.021
-0.023 +/- 0.027 0.060 0.060 0.080 0.060 Location Collection Date Lab Code E-04 5/31/2007 EG-3304 E-06 5/31/2007 EG-3305 E-08 5/31/2067 EG-3306 Req. LLD Ratio (wet/dry) 5.64 4.73 4.02 Gross Beta 7.46 +/- 0.16 7.36 +/- 0.17 9.58 +/- 0.22 0.25 Be-7 K-40 1-131 Cs-1 34 Cs-137 Other Gammaso 0.68 +/- 0.26 5.58 +/- 0.59 0.008 +/- 0.011
-0.008 +/- 0.011 0.008 +/- 0.010
-0.006 +/- 0.012 0.48 +/- 0.26 5.76 +/- 1.18
-0.022 +/- 0.018
-0.015 +/- 0.020 0.027 +/- 0.020 0.035 +/- 0.018 1.02 +/- 0.36 6.86 +/- 0.65
-0.001 +/- 0.016
-0.020 +/- 0.016 0.025 +/- 0.015 0.010 +/- 0.015 0.060 0.060 0.080 0.060 Location Collection Date Lab Code E-09 5/31/2007 EG-3307 E-20 5/31/2007 EG-3308 Req. LLD Ratio (wet/dry) 4.39 4.46 Gross Beta 8.03 +/- 0.16 7.29 +/- 0.16 0.25 Be-7 K-40 1-131 Cs-134 Cs-1 37 Other Gammas4 0.66 +/- 0.26 5.52 +/- 0.63
-0.009 +/- 0.014
-0.007 +/- 0.012 0.017 +/- 0.015 0.002 +/- 0.014 0.82 +/- 0.20 7.18+/-' 0.44 0.003 +/- 0.012 0.003 +/- 0.012 0.002 +/- 0.014 0.007 +/- 0.014 0.060 0.060 0.080 0.060 a See Introduction.
32
POTNT B1EACH NUCLE.AR PTLANT RADIOACTIVITY IN VEGETATION SAMPLES (Tri-Annual Collections)
Sample Description and Concentration (pCi/g wet)
Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta Be-7 K-40
.1-131 Cs-1 34 Cs-1 37 Other Gammas' Location Collection Date.
Lab Code Ratio (wet/dry)
Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas' Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other GammasW E-01 7/26/2007 EG-4768 4.08 9.87 + 0.21 0.57 +/- 0.16 7.23 +/- 0.52 0.010 +/- 0.008
-0.005 +/- 0.008 0.005 +/- 0.010
-0.006 +/- 0.011 E-04 7/26/2007 EG-4771 5.81 7.16 +/- 0.15 0.51 +/- 0.17 6.05 + 0.64 0.005 + 0.012
-0.017 + 0.014 0.001 +0.014
-0.007 + 0.016 E-09 7/26/2007 EG-4774 3.21 8.80 +/- 0.23 1.22 + 0.23 6.95 +/--0.59
-0.005 +/- 0.008
-0.005 +/- 0.008 0.002 +/- 0.008 0.011 +/- 0.010 E-02 7/25/2007 EG-4769 3.49 7.71 +/- 0.18 2.23 +/- 0.23 6.31 +/- 0.55 0.029 +/- 0.011
-0.008 +/- 0.011
-0.002-+/- 0.012 0.001 +/- 0.008 E-06 7/26/2007 EG-4772 3.08 6.97 +/- 0.16 1.06 +/- 0.28 4.84 +/- 0.53
-0.014 +/- 0.014-0.002 +/- 0.013 0.051 +/- 0.026
-0.004 +/- 0.008 E-20 7/26/2007 EG-4775 2.92 11.72 +/- 0.33 1.45 + 0.28 5.51 +/- 0.55
-0.021 +/- 0.012
-0.002 +/- 0.012 0.005 +/- 0.013 0.007 +/- 0.012 E-03 7/26/2007 EG-4770 3.67 8.84 +/- 0.18 0.48 +/- 0.18 7.88 +/- 0.51
-0.001 +/- 0.009 0.001 +/- 0.009 0.001 +/- 0.010 0.008 +/- 0.009 E-08 7/26/2007 EG-4773 5.25 8.42 +/- 0.20 0.54 +/- 0.22 6.60 +/- 0.69 0.008 +/- 0.011
-0.001 +/- 0.011
-0.001 +/- 0.012 0.009 +/- 0.019 Req. LLD 0.25 0.060 0.060 0.080 0.060 Req. LLD 0.25
.0.060 0.060 0.080 0.060 Req. LLD 0.25 0.060 0.060 0.080 0.060 a See Introduction.
33
PC)TNTTrR 1~A rT-XTIJCT P AR PT.A Xff RADIOACTIVITY IN VEGETATION SAMPLES (Tri-Annual Collections)
Sample Description and Concentration (pCi/g wet)
Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta Be-7 K-40 1-131 Cs-134 Cs-1 37 Other Gammas" Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas' Location Collection Date Lab Code Ratio (wet/dry)
Gross Beta, Be-7 K-40 1-131 Cs-134 Cs-137 Other Gammasb E-01 10/2612007 EG-7518 4.13 5.35 +/- 0.15 2.98 +/- 0.32 4.82 +/- 0.61
-0.010 +/- 0.012
-0.008 +/- 0.011
-0.010 +/- 0.013 0.005 +/- 0.014 E-04 10/26/2007 EG-7521 3.96 4.94 +/- 0.13 2.82 +/- 0.35 5.52 +/- 0.48 0.002 +/- 0.011
-0.010 +/- 0.011 0.002 +/- 0.010
-0.007 +/- 0.011 E-09 10/26/2007 EG-7524 4.37 8.95 +/- 0.24 3.88 + 0.38 5.80 +/- 0.58
-0.010 +/- 0.010 0.006 +/- 0.009
-0.002 +/- 0.010
-0.012 +/- 0.010 E-02
- 10/26/2007 EG-7519 4.66 8.24 +/- 0.21 2.52 +/- 0.36 7.00 +/- 0.64 0.010 +/- 0.013
-0.005 +/- 0.013 0.019 +/- 0.013
.0.005 +/- 0.011 E-06 10/26/2007 EG-7522 3.28 6.32 +/-0.16 2.44 +/- 0.32 5.81 +/- 0.63 0.017 + 0.014 0.008 +/- 0.010 0.110 +/- 0.030
-0.005 +/- 0.011 E-03 10/26/2007 EG-7520 3.87 9.78 +/- 0.20 2.72 +/- 0.36 6.70 +/- 0.67 0.008 +/- 0.011 0.009 +/- 0.010 0.001 +/- 0.013
-0.008 +/- 0.015 E-08 10/26/2007 EG-7523 5.55 3.62 +/- 0.08 1.49 +/- 0.29 3.44 +/- 0.39
.0.000 +/- 0.009 0.002 +/- 0.008 0.005 +/- 0.010 0.008 +/- 0.009 Req. LLD 0.25 0.060 0.060 0.080 0.060 Req. LLD 0.25 0.060 0.060 0.080 0.060
. E-20 10/26/2007 EG-7525 Req. LLD 4.60 9.22 +/- 0.21 3.15 +/- 0.50 5.87 + 0.80 0.018 +/- 0.019
-0.009 +/- 0.015
-0.008 +/- 0.019 0.015 +/- 0.023 0.25 0.060 0.060 0.080 0.060 a See Introduction.
34
PC1TXTT R7AC'1-WNTT TC'LFPA PT.A NTT Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.
Collection: Semiannual Units: pCi/o wet Sample Description and Concentration Collection Date Lab Code Location Ratio (wet wt./dry wt.)
Gross Beta Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Collection Date Lab Code Location Ratio (wet wt./dry wt.)
Gross Beta Be-7 K-40 Co-58 Co-60 Cs-134 Cs-i 37 Collection Date Lab Code Location Ratio (wet wt./dry wt.)
Gross Beta Be-7 K-40 Co-58 Co-60 Cs-1 34 Cs-137 06-06-07 ESL-3503 E-05 7.29 4.89 +/- 0.29 0.56 +/- 0.24 2.51 +/- 0.65
-0.025 +/- 0.032 0.003 +/- 0.034 0.005 +/- 0.033 0.018 +/- 0.036 08-09-07 ESL-5292 E-05 4.42 5.25 +/- 0.36 1.30 +/- 0.32 2.32 +/- 0.44 0.005 +/- 0.012 0.016 +/- 0.017
-0.030 +/- 0.016 0.026 +/- 0.018 10-04-07 ESL-6771 E-05 3.54 9.58 +/- 0.71 0.17 +/- 0.10 3.04 +/- 0.41
-0.014 +/-+o.011 0.001 +/- 0.012
-0.009 +/- 0.011 0.022 +/- 0.013 06-06-07 ESL-3504 E-12 1.59 7.86 +/- 0.98 0.27 +/- 0.21 4.98 +/- 0.92
-0.013 +/- 0.023 0.013 +/- 0.033 0.001 +/- 0.023
-0.009 +/- 0.025 08-09-07 ESL-5293 E-1 2 3.34 2.87 +/- 0.27 0.66 +/- 0.28 1.96 +/- 0.89
-0.029 +/- 0.035
-0.010 +/- 0.023 0.001 +/- 0.029 0.009 +/- 0.038 10-04-07 ESL-6772 E-12 3.62 7.64 +/- 0.59 0.95 +/- 0.36 3.02 +/- 0.49 0.019 +/- 0.014 0.017 +/- 0.012
-0.027 +/- 0.015 0.020 +/- 0.017 Required LLD 0.25 0.25 0.25 0.25 0.25 Required LLD 0.25 0.25 0.25 0.25 0.25 Required LLD 0.25 0.25 0.25 0.25 0.25 35
POINT BEACH NTUCLE AR PLANT AMBIENT GAMMA RADIATION (TLD) 1st. Quarter, 2007 Date Annealed:
12-18-06 Days in the field 91 Date Placed:
01-03-07 Days from Annealing Date Removed:
04-04-07 to Readout:
116 Date Read:
04-13-07 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-12 E-14 E-15 E-16 E-17 E-18 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 Control E-20 Mean+/-s.d.
91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 91 14.3 +/- 1.1 18.2 +/- 0.4 20.7 +/- 1.4
.17.1 +/- 1.4 15.7 +/- 0.8 16.6 +/- 0.8 16.7 +/- 0.9 16.4 +/- 0.7 19.0 +/- 0.7 14.4 +/- 0.2 18.1 +/- 0.6 19.0 +/- 0.6 17.3 +/- 0.4 18.5 +/- 0.5 18.7 +/- 0.8 19.1 +/- 1.5 17.6 +/- 0.4 18.2 +/- 0.5 17.3 +/- 0.3 16.0 +/- 0.2 16.9 +/- 0.3 14.0 +/- 0.2 17.9 +/- 0.8 16.3 +/- 0.7 17.4 +/- 0.6 17.0 +/- 0.6 16.7 +/- 0.8 15.4 +/-0.7 16.4 +/- 1.1 17.1 +/- 1.5 9.8 +/- 1.2 13.7 +/- 0.7 16.2 +/- 1.5 12.6 +/- 1.5 11.2 +/-1.0 12.1 +/- 1.0 12.2 +/- 1.1 11.9 +/- 0.9 14.5 +/- 0.9 9.9 +/- 0.6 13.6 +/- 0.8 14.5 +/- 0.8 12.8 +/- 0.7 14.0 +/- 0.7 14.2 +/- 1.0 14.6 +/- 1.6 13.1 +/- 0.7 13.7 +/- 0.7 12.8 +/- 0.6 11.5 +/- 0.6 12.4 +/- 0.6 9.5 +/- 0.6 13.4 +/- 1.0 11.8 +/- 0.9 12.9 +/- 0.8 12.5 +/- 0.8 12.2 t 1.0 10.9 +/- 0.9 11.9 +/- 1.2 12.6 +/- 1.5 0.75 +/- 0.09 1.05 +/- 0.05 1.24 +/- 0.12 0.97 +/- 0.12 0.86 +/- 0.07 0.93 +/- 0.07 0.93 +/- 0.08 0.91 +/- 0.07 1.11 +/-0.07 0.76 +/- 0.04 1.04 +/- 0.06 1.11 +/- 0.06 0.98 +/- 0.05 1.07 +/- 0.06 1.09 +/- 0.07 1.12 +/- 0.12 1.00 +/- 0.05 1.05 +/- 0.06 0.98 +/- 0.05 0.88 +/- 0.04 0.95 +/- 0.05 0.73 +/- 0.04 1.03 +/- 0.07 0.90 +/- 0.07 0.99 +/- 0.06 0.96 +/- 0.06 0.93 +/- 0.07 0.83 +/- 0.07 0.91 +/- 0.09 0.97 +/- 0.11 91 Date Annealed Date Read ITC-1 ITC-2 In-Transit Exposure 12-18-06 03-09-07 01-08-07 04-13-07 Total mR 3.2 +/- 0.3 6.2 +/- 0.4 3.4 +/- 0.2 5.4 +/- 0.1 36
POINT BEACH NU JCLEAR PLANT AMBIENT.GAMMA RADIATION (TLD) 2nd Quarter, 2007 Date Annealed:
03-09-07 Days in the field 92 Date Placed:
04-04-07 Days from Annealing Date Removed:
07-05-07 to Readout:
140.
Date Read:
07-27-07 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-12 E-14 E-1 5 E-16 E-17 E-18 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 Control.
E-20 Mean+/-s.d.
92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 19.3 +/- 0.7 26.0 +/- 1.4.
26.7 +/- 2.1 22.6 +/- 0.4 24.3 +/- 0.6 21.9 +/- 0.6 21.1 +/- 1.3 22.5 +/- 0.8 24.7 +/- 1.6 18.5 +/-0.6 23.2 +/- 1.5 28.8 +/- 0.5 23.2 +/- 1.1 23.7 +/- 1.2 24.7 +/- 0.6 25.3 +/--0.4 26A +/- 1.3 24.3 +/- 1.4 25.8 +/- 2.1 22.0 +/- 0.5 24.6 +/- 0.6 20.0 +/- 0.8 24.6 +/- 0.9 23.9 +/- 0.5 26.4 +/- 2.0 21.6 +/- 0.5 22.3 +/- 0.6 20.8 +/- 0.7 22.7 +/- 0.8 23.5 +/- 2.4 12.5 +/- 1.2 19.2 +/- 1.7 19.9 +/- 2.3
.15.8 +/- 1.1 17.5 +/- 1.2 15.1 +/- 1.2 14.3 +/- 1.6 15.7 +/- 1.3 1.7.9+/-1.9 11.7 +/- 1.2 16.4 +/- 1.8 22.0 +/- 1.1 16.4 +/- 1.5 16.9 +/- 1.6 17.9 +/- 1.2 18.5 +/- 1.1 19.6 +/- 1.6 17.5 +/- 1.7
.19.0 +/- 2.3 15.2 +/- 1.1 17.8 +/- 1.2 13.2 +/- 1.3 17.8 +/- 1.4 17.1 +/- 1.1 19.6 +/- 2.2 14.8 +/- 1.1 15.5 +/- 1.2 14.0 +/- 1.2 15.9 +/- 1.3 16.7 +/-2.4 0.95 +/- 0:09 1.46 +/- 0.13 1.52 +/- 0.18 1.20 +/- 0.08 1.33 +/-*0.09 1.15 +/- 0.09 1.09 +/- 0.13 1.20 +/- 0.10 1.36 +/- 0.14 0.89 +/- 0.09 1.25 +/- 0.14 1.68 +/- 0.09 1.25 +/- 0.11 1.29 +/- 0.12 1.36 +/- 0.09 1.41 +/- 0.08 1.49 +/- 0.13 1.33 +/- 0.13 1.45 +/- 0.18 1.16 +/- 0.09 1.36 +/- 0.09 1.01 +/- 0.10 1.36 +/- 0.10 1.30 +/- 0.09 1.49 + 0.17 1.13 +/- 0.09 1.18 +/- 0.09 1.07 +/- 0.09 1.21 +/- 0.10 1.27 +/- 0.17 Date Annealed Date Read ITC-1 ITC-2 In-Transit Exposure 03-09-07 06&07-07 04-13.07 07-30-07 Total mR 6.2 +/- 0.4 5.4 +/- 0.1 8.2 +/- 0.9 7.3 +/- 0.2 37
POINT BEACH N1 ICLEAR PLANT AMBIENT GAMMA RADIATION (TLD) 3rd Quarter, 2007 Date Annealed:
06-07-07 Days in the field 92 Date Placed:
07-05-07 Days from Annealing Date Removed:
10-05-07 to Readout:
130 Date Read:
10-15-07 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-12 E-14 E-15 E-116 E-1 7 E-18 E-22 E-23 E-24 E-25 E-26 E-27.
E-28 E-29 E-30 E-31 E-32 E-38 E-39 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 92 16.0 +/- 1.0 20.9 +/- 0.3 24.6 +/- 1.3 19.8 +/- 1.5 18.7 +/- 1.1 19.1 +/- 1.0 19.0 +/- 1.0 18.6 +/- 0.5 22.3 +/- 0.5 15.7 +/- 0.3 21.0 +/- 0.8 22.4 +/- 0.7 19.8 +/- 0.6 20.9 +/- 0.7 22.1 +/- 0.9 21.7 +/- 1.4 21.8 +/- 0.6 21.5 +/- 1.7 20.3 +/- 0.5 18.3 +/-0.4 20.3 +/- 0.3 15.1 +/- 0.3 20.2 +/- 0.9 18.4 +/- 1.2 20.3 +/- 0.6 18.0 +/- 0.6 20.2 +/- 1.5 17.8 +/- 0.7 19.1 +/- 1.1 19.8 +/- 2.1 9.3 +/- 1.5 14.2 +/- 1.1 17.9 +/- 1.7 13.1 +/- 1.8 12.0 +/- 1.5 12.4 +/- 1.5 12.31+/- 1.5 11.9 +/- 1.2 15.6 +/- 1.2 9.0 +/-1.1 14.3 +/- 1.3 15.7 +/- 1.3 13.1 +/- 1.2 14.2 +/- 1.3 15.4 +/- 1.4 15.0 +/- 1.8 15.1 +/- 1.2 14.8 +/- 2.0 13.6 +/- 1.2 11.6 +/- 1.1 13.6 +/- 1.1 8.4 +/- 1.1 13.5 +/- 1.4 11.7 +/- 1.6 13.6 +/-1.2 11.3 +/- 1.2 13.5 +/- 1.8 11.1 +/- 13 12.4 +/- 1.5 13.1 +/- 2.1 0.71 +/- 0.11 1.08 +/- 0.08 1.36 +/- 0.13 0.99 +/- 0.14 0.91 +/- 0.12 0.94 +/- 0.11 0.93 +/- 0.11 0.90 +/- 0.09 1.19 +/- 0.09 0.68 +/- 0.08 1.09 +/-,0.10 1.19 +/- 0.10 0.99 +/- 0.09 1.08 +/- 0.10 1.17 +/- 0.11 1.14 +/- 0.13 1.15 +/- 0.09 1.12 +/- 0.15 1.03 +/- 0.09 0.88 +/- 0.09 1.03 +/- 0.08 0.64 +/- 0.08 1.03 +/- 0.11 0.89 +/- 0.12 1.03 +/- 0.09 0.86 +/- 0.09 1.03 +/- 0.14 0.84 +/- 0.10 0.94 +/- 0.12 0.99 +/- 0.16 Control E-20 92 Mean+/-s.d.
Date Annealed Date Read ITC-1 ITC-2 In-Transit Exposure 06-07-07 09-14-07 07-30-07 10-10-07 Total mR 8.2 +/- 0.9 5.6 +/- 0.5 7.3 +/- 0.2 5.8 +/- 0.1 38
POINT BEACH NIJCTIFAR PLANT AMBIENT GAMMA RADIATION (TLD) 4th Quarter, 2007 Date Annealed:
09-14-07 Days in the field 97 Date Placed:
10-05-07 Days from Annealing Date Removed:
01-10-08 to Readout:
129 Date Read:
01-21-08 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 97-18.4 +/- 1.4 12.2 +/- 1.6 0.88 +/- 0.12 E-2 97 25.7 +/- 1.5 19.5 +/- 1.7 1.41 +/- 0.13 E-3 97 24.9 +/- 1.7 18.7 +/- 1.9 1.35 +/- 0.14 E-4 97 20.8 +/- 0.6 14.6 +/- 1.1 1.06 +/- 0.08 E-5 97 22.8 +/- 0.5 16.6 +/- 1.0 1.20 +/- 0.07 E-6 97 20.4 +/- 0.5 14.2 +/- 1.0 1.03 +/- 0.07 E-7 97 19.9 +/- 0.3 13.7 +/- 0.9 0.99 +/- 0.07 E-8 97 20.9 +/- 0.7 14.7 +/- 1.1 1.06 +/- 0.08 E-9 97 23.3 +/- 1.4 17.1 +/- 1.6 1.24 +/- 0.12 E-12 97 19.0 +/- 1.5 12.8 +/- 1.7 0.93 +/- 0.13 E-14 97 21.4 +/- 1.3 15.2 +/- 1.6 1.10 +/- 0.11 E-15 97 23.7 +/- 0.9 17.5 +/- 1.3 1.26 +/- 0.09 E-16 97 20.4 +/- 0.9 14.2 +/- 1.3 1.03 +/- 0.09 E-17 97 20.7 +/- 1.4 14.5 +/- 1.6 1.05 +/- 0.12 E-18 97 22.2 +/- 0.5 16.0 +/- 1.0 1.16 +/- 0.07 E-22 97 22.4 +/- 0.4 16.2+/- 1.0 1.17 +/- 0.07 E-23 97 23.7 +/- 0.9 17.5 +/- 1.3 1.26 +/- 0.09 E-24 97 21.1 +/- 0.4 14.9 +/- 1.0 1.08 +/- 0.07 E-25 97 23.2 +/- 0.4 17.0 +/- 1.0 1.23 +/- 0.07 E-26 97 19.8 +/- 0.5 13.6 +/- 1.0 0.98 +/- 0.07 E-27 97 23.7 +/- 0.7 17.5 +/- 1.1 1.26 +/- 0.08 E-28 97 16.7 +/- 0.3 10.5 +/- 0.9 0.76 +/- 0.07 E-29 97 18.1 +/- 0.8 11.9 +/- 1.2 0.86 +/- 0.09 E-30 97 21.3 +/- 0.6 15.1 +/- 1.1 1.09 +/- 0.08 E-31 97 23.0 +/- 1.4 16.8 +/- 1.6 1.21 +/- 0.12 E-32 97 19.3 +/- 0.5 13.1 +/- 1.0 0.95 +/- 0.07 E-38 97 19.5 +/- 0.6 13.3 +/- 1.1 0.96 +/- 0.08 E-39 97 19.0 +/- 0.7 12.8 +/- 1.1 0.93 +/--0.08 Control E-20 97 21.9 +/- 1.6 15.7 +/- 1.8 1.13 +/- 0.13 Mean+/-s.d.
21.3 +/- 2.1 15.1 +/- 2.1 1.09 +/- 0.14 In-Transit Exposure Date Annealed 09-14-07 12-05-07 Date Read 10-10-07.
01-22-08 Total mR ITC-1 5.6 +/- 0.5 7.2 +/- 0.7 ITC-2 5.8 +/- 0.1 6.1 +/- 0.1 39
Environmental, Inc.
Midwest Laboratory
-an Alleg ny Technologies Co.
700 Landweh Road
- Nortibrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in intercompanson studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January through December, 2007
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides
- known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possibleproblems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits.
Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve month!
Acceptance is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explaineddirectly below the result.
Al
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters Strontium_89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium Iodine-131, Iodine-1 2 9 b Uranium-238, Nickel-63 b Technetium-99b Iron-55b 5 to 100 pCifliter or kg
> 100 pCi/liter or kg 5 to 50 pCi/liter or kg
> 50 pCi/liter or kg 2 to 30 pCi/liter or kg
> 30 pCi/liter or kg
-- 0.1 g/liter or kg 520 pCi/liter
> 20 pCi/liter
-5 100 pCi/liter
> 100 pCi/liter
-< 4,000 pCi/liter
> 4,000 pCi/liter
> 0.1 pCi/liter 2 0.1 pCi/liter, gram, or sample
- 5 55 pCi/liter
> 55 pCi/liter 5 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter
> 100 pCi/liter 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value
+1o" =
169.85 x (known) 0,0 933 10% of known value 15% of known value 10% of known value 6.0 pCi/liter 10% of known value 6.0 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value Othersb a From EPA publication. "Environmental Radioactivity Laboratory Intercomparison Studies Program. Fiscal Year, 1981-1982. EPA-600/4-81-004.
b Laboratorl limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1121 STW-1 121 STW-1122 STW-1 122 STW-1122 STW-1122 STW,-1122 STW-1 123 STW-1 123 STW-1124 STW-1125 STW-1 125 STW-1 125 STW-1125 STW-1127 STW-1127 STW-1128 STW-1 128 STW-1 128 STW-1128 STW-1128 STW-1 129 STW-1 129 STW-1130 STW-1130 ST'w-1130 STW-1131 STW-1131, STW-1132 STW-1132 STW-1132 STW-1132 STW-1132 STW-1133 STW-1 133 STW-1134 STW-1 135 STW-1135 STW-1 135 STW-1135 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 07/09/07
.07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09107
.07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 10/05/07 10/05/07 1.0/05/07 10/05/07 10/05/07 10/05107 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Ra-226 Ra-228 Uranium 30.7 +/- 4.3 39.3 +/- 1.8 30.0 +/- 2.4 118.5 +/-+3.9 52.6 +/- 2.3 49.5 +/- 3.8 91.7 +/- 6.3 33.8 +/- 3.5 24.2 +/- 2.3 19.2 +/- 1.2 7540.0 +/- 255.0 13.0 +/-0.6 19.9 +/- 2.7 4.5 +/- 0.2 51.7 +/- 5.0 21.4 +/- 2.3 19.4 +/- 2.2 32.8 +/- 2.0 67.0 +/- 2.9 61.6 +/- 3.8 55.6 +/- 7.5.
19.2 +/- 1.6 9.1 +/- 0.9 7.0 +/- 0.5 9.2 +/- 2.3 23.9 +/- 1.1 27.3 +/- 3.3
.17.7 + 1.2 12.2 +/- 3.3 23.8 +/- 1.4 70.5 +/- 4.2 178.2 +/- 3.3 263.9 +/- 6.9 54.7 +/- 2.1 11.9 +/- 0.9 33.0 +/- 1.5 9965.0 +/- 250.0 12.7 +/- 0.2
- 19.6 +/-.2.4 27.3 +/- 1.1 35.4 42.1 29.3 119.0 54.3 50.3 88.6 56.5 25.3 18.9 8060.0 13.4
-18.2 4.6 58.2 19.0 19.4 33.5 68.9 61.3 54.6 27.1 11.5 7.7 9.1 25.1 27.4 18.2 12.6 23.2 71.1 180.0 251.0 58.6 9.7 28.9 9700.0 12.9 17.9 27.5 26.7 -44.1 33.4 - 50.8 20.6 - 38.0 109.0 - 129.0 45.6 - 63.0 41.6 -59.0 73.3 -104.0 32.0 -81.0 16.6 - 34.0
,13.7 - 24.1 6660.0 - 9450.0 9.9 -16.9 10.3 -26.1 0.0 -9.8 49.5 -66.9 10.3 -27.7 10.7 -28.1 24.8 - 42.2 60.2 - 77.6 52.6 - 70.0 45.2 -64.0 15.4 -38.8 2.8 -20.2 5.7-9.7 5.2 -13.1 19.9 -30.3 19.3 -33.9 12.9 -21.6 8.6 - 15.5 19.9 -28.3 58.0 - 78.2 162.0 - 200.0 226.0 - 294.0 30.6 - 72.9 4.3 - 18.2 24.0 - 33.8 8430.0 - 10700.0 9.6 - 14.9 12.0 -21.5 22.1 -30.8 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Results obtained by Environmental. Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmentat Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laborator, precision (1 sigma, 1 determination) and control limits as provided by ERA.
Al-1
TABLE A-1. Interiaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resulte Resultc Limits Acceptance Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.
A fourth analysis was performed, result of analysis, 24.89 pCi/L.
A1-2
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4 : Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+/-2 sigma Limits Acceptance Environmental. Inc.
2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 7/13/2007 30 cm.
7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/1312007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 40 cm.
50 cm.
60 cm.
70 cm, 80 cm.
90 cm.
100 cm.
110 cm.
120 cm.
150 cm.
54.25 30.51 19.53 13.56 9.96 7.63.
6.03 4.88 4.03 3.39 2.17 60.56 +/- 5.54 34.23 +/- 0.96 17.95 +/- 1.86 16.61 +/- 0.60 9.72 +/- 0.90 7.79 +/- 0.33 5.53 +/- 0.72 5.32 +/- 0.17 3.49 +/- 0.14 2.64 + 0.14 2.13 +/- 0.87 37.98 - 70.53 21.36 -139.66 13.67 -25.39 9.49 - 17.63 6.97 - 12.95 5.34 - 9.92 4.22 - 7.84 3.42 - 6.34 2.82 - 5.24 2.37 -.4.41 1.52 -2.82 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.
2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007' 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 30 cm.
40 cm.
60 cm.
70 cm.
80 cm.
90 cm.
110 cm.
120 cm.
120 cm.
150 cm.
54.37 30.59
,13.59 9.99 7.65 6.04 4.04 3.4 3.4 2.17 1.51 65.47 +/- 5.25 37.43 +/- 2.18 15.18 +/- 0.50 12.18 +/- 0.46 8.74 +/- 0.39 5.89 +/- 0.25 4.13 +/- 0.41 2.92 +/- 0.13 2.91 +/- 0.31 1.95 +/- 0.72 1.38 +/- 0.05 38.06 - 70.68 21.41 -39.77 9,51 - 17.67 6.99 - 12.99 5,36 - 9.95 4.23 - 7.85 2.83 -5.25 2.38 - 4.42 2.38 - 4.42 1.52 -2.82 1.06 - 1.96 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 2007-2 11/12/2007 180 cm.
A2-1
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits 0 Acceptance W-30707 W-30707 SPAP-1566 SPAP-1566 SPW-1 568 SPW-1678 SPW-1 595 SPW-1 595 SPW-1595 SPW-i 595A SPW-1595B SPMI-1597 SPMI-1597 SPMI-1597 SPMI-1597A SPMI-1597B SPCH-2839 SPW-2847 SPW-2847 SPW-2847 SPMI-2849 SPMI-2849 SPMI-2849 SPCH-2922 SPW-2847 SPW-2847 SPW-2847 SPMI-2849 SPW-2909e SPW-2911 SPAP-2913 SPAP-2915 SPAP-2915 SPF-2922 SPF-2922 SPW-3223 W-60507 W-60507 SPW-4327 SPW-5476 W-92107 W-92107 3/7/2007 3/7/2007 3123/2007 3/23/2007 3/23/2007 3/28/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/18/2007 5/18/2007 5/18/2007 5/18/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/24/2007 6/5/2007 6/5/2007 7/18/200 7 811712007 9/21/2007 9/21/2007 Gr. AIpha Gr. Beta Cs-1 34 Cs-1 37 H-3 Tc-99 Cs-134 Cs-137 1-131(G) 1-131 1-131 Cs-1 34 Cs-137 1-131(G) 1-131 1-131 1-131(G)
Cs-1 34 Cs-1 37 1-131(G)
Cs-1 34 Cs-137 1-131(G) 1-131(G) 1-131 Sr-89 Sr-89 1-131 Fe-55 H-3 Gr. Beta Cs-1 34 Cs-1 37 Cs-134 Cs-137 Ni-63 Gr. Alpha Gr. Beta Tc-99 Ni-63 Gr. Alpha Gr. Beta 19.51 +/- 0.40 67.45 +/- 0.49 25.35 +/- 1.31 107.52 +/- 3.02 65595.00 +/- 672.00 28.44 +/- 1.12 54.48 +/- 2.12 59:03 +/- 2.94 83.11 +/- 3.51 78.40 +/- 1.10 78.97 +/- 1.10 54.03 +/- 2.15 59.81 +/- 4.75 83.97 +/- 4.07 79.53 t 1,03 83.51 +/- 1.05
- 78.70 +/- 7.36 55.43 +/- 1.68 59.86 +/- 2.71 63.95 +/- 2.69 51.37 t 1.65 60.42 +/- 4.31 62.44 +/- 3.14 80.00 +/- 6.40 60.14 +/- 0.89 104.93 +/- 6.64 46.72 +/- 1.97 67.97 +/- 0.88 11137.00 +/- 316.00 65023.00 +/- 679.00 55.27 +/- 8.51 22.53 +/- 1.12 111.14 +/- 3.57 0.52 +/- 0.03 2.58 +/- 0.07 2233.10 +/- 10.32 20.93 +/- 0.42 60.50 +/- 0.46
.20.08 65.73 27.82 116.48 71118.00 32.35 54.99 58.19 82.07 82.07 82.07 54.99 58.19 82.07 82.07 82.07 70.40 52.85 58.03 70.87 52.85 58.03 70.87 70.40 70.87 121.90 46.08 70.87 14271.50 70485.00 52.65 26.42 116.06 0.53 2.32 2135.90 20.08 65.73 10.04 -30.12 55.73 - 75.73 17.82 -37.82 104.8.3 - 128.13 56894.40 -85341.60 20.35 -44.35 44.99 - 64.99 48.19 -68.19 72.07 - 92.07 65.66 - 98.48 65.66 -98.48 44.99 - 64.99 48.19 - 68.19 72.07 - 92.07 65.66 - 98.48 65.66 - 98.48 60.40 -80.40 42.85 - 62.85 48.03 -68.03 60.87 - 80.87 42.85 -62.85
- 48.03 -68.03 60.87 - 80.87 41.60 - 99.20 56.70 - 85.04 97.52 - 146.28 36.08 - 56.08 56.70 - 85.04 11417.20 - 17125.80 56388.00 - 84582.00 42.12 -73.71 16.42 -36.42 104.45 - 127.67 0.32 -0.74 1.39 -3.25 1281.54 -2990.26 10.04 -30.12 55.73 - 75.73 20.35 - 44.35 1281.54 - 2990.26 10.04 -30.12 55.73 - 75.73 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass' Pass Pass Pass 25.58 +/- 1.11
- 1925.18 t 9.62 23.02 +/- 0.44 61.48 -0.47 32.35 2135.90 20.08 65.73 A3-1
TABLE A-3. In-House "Spike' Samples Concentration (pCi/L)2 Lab Code Date Analysis Laboratory results Known Control 2s, n=lb Activity Limitsc Acceptance SPW-6880 10/102007. Tc-99 30.97 +/- 1.21 32.35 20.35 - 44.35 Pass w-111007 11/10/2007 Gr. Alpha 22.43 +/- 0.42 20.08 10.04 -30.12 Pass w-1 11007 11/10/2007 Gr. Beta 64.49 +/- 0.48 65.73 55.73 - 75.73 Pass SPAP-7742 11/13/2007 Cs-134 21.18 +/- 1.29 22.41 12.41 -32.41 Pass SPAP-7742 11/13/2007 Cs-137 113.61 +/- 3.16 114.76 103.28 -126.24 Pass SPAP-7744 11/13/2007 Gr. Beta 53.41 +/- 0.13 52.03 41.62 -72.84 Pass SPMI-7746 11/13/2007 Cs-134 42.20 +/- 1.48 44.83 34.83 - 54.83 Pass SPMI-7746 11/13/2007 Cs-1 37 56.05 +/- 2.83 57.40 47.40 - 67.40 Pass SPMI-7746 11/13/2007 Sr-90 41.02.+/- 1.61 45.54 36.43 - 54.65 Pass SPW-7748 11(13/2007 Cs-134 43.11 +/- 1.52 44.80 34.80 - 54.80 Pass SPW-7748 11113/2007 Cs-137 59.28 +/- 3.50 57.40 47.40 - 67.40 Pass SPW-7748 11/13/2007 Sr-90 37.23 +/- 1.51 45.54 36.43 -54.65 Pass SPW-7752 11/13/2007 Fe-55
.12935.10 +/- 357.00 12640.50 10112.40 - 15168.60 Pass SPW-7758 11/13/2007 H-3 65405.00 +/- 712.50 68618.00 54894.40 - 82341.60 Pass SPF-7760 11/13/2007 Cs-134 0.45 +/- 0.02 0.45 0.27 -0.63 Pass SPF-7760 11/13/2007 Cs-137 2.45 +/- 0.07 2.29 1.37 -3.21 Pass SPW-8034 11/13/2007 NiW63 2194.06 +/- 10.77 2129.03.
1277.42 -2980.64 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/rm3), and solid samples (pCi/g).
b Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation),
CH (charcoal canister), F (fish).
Results are based on single determinations.
Contro! limits are based on Attachment A, Page A2 of this report.
e Sample recount, 12557 +/- 335.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)2 Lab Code Sample Date Analysisb Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 a)
W-30707 W-30707 SPAP-1567 SPW-1567 SPW-1568 SPW-1596 SPW-1596 SPW-1596 SPW-1596 SPMI-1598 SPMI-1598 SPMI-1598 SPMI-1598 SPCH-2839 SPW-2848 SPW-2848 SPW-2848 SPMI-2850 SPMI-2850 SPMI-2850 SPW-2848 SPW-2848 SPW-2848 SPMI-2850 SPMI-2850 SPMI-2850 d SPAP-2914 SPAP-2916 SPAP-2916 SPF-2923 SPF-2923 SPW-3224 W-60507 W-60507 SPW-4328 SPN-5477 W-92107 W-92107 water 317/2007 water 3/7/2007 Air Filter 3/23/2007 Air Filter 3/23/2007 water 3/23/2007 water 4/5/2007 water
.4/5/2007 water 4/5/2007 water 4/5/2007 Milk 4/5/2007 Milk 4/5/2007 Milk 4/5/2007 Milk 4/5/2007 Charcoal Canister 5/17/2007 water 5/17/2007 water 5/17/2007 water 5/17/2007 Milk 5/17/2007 Milk 5/17/2007 Milk
-5/17/2007 water 5/18/2007 water 5/18/2007 water 5/18/2007 Milk 5/18/2007 Milk 5/18/2007 Milk 5/18/2007 Air Filter 5/22/2007 Air Filter 5/22/2007 Air Filter 5/22/2007 Fish 5/22/2007 Fish 5/22/2007 water 5/24/2007 water 6/5/2007 water 6/5/2007 water 7/18/2007 water 8/17/2007 water 9/21/2007 water 9/21/2007 Gr. Alpha Gr. Beta Cs-134 Cs-137 H-3 Cs-134 Cs-137 131 1-131(G)
Cs-134 Cs-137 1-131 1-131(G) 1-131(G)
Cs-134 Cs-137 1-131(G)
Cs-134 Cs-137 1-131(G) 1-131 Sr-89 Sr-90 1-131 Sr-89 Sr-90 Gr. Beta Cs-134 Cs-137 Cs-1i34 Cs-137 Ni-63 Gr. Alpha Gr. Beta Tc-99 Ni-63 Gr. Alpha Gr. Beta 0.40 0.75 0.79 1.01 176.10 3.28 3.45 0.27 2.91 3.30 5.08 0.26 4.10 2.24 3.14.
1.37 5.34 3.32 2.60 4.77 0.34 0.81 0.53 0.45 0.96 0.58 0.004 2.84 2.24 8.71 8.35 1.61 0.43 0.77 6.41 1.48 0.41 0.75 0.01 +/- 0.28 0.06 +/- 0.53
-26.16 +/- 91.62 0.02 +/- 0.18
-0.10 +/- 0.17
-0.06 +/- 0.19'
-0.02 +/- 0.65 0.01 +/- 0.25 0.20 +/- 0.26
-0.73 +/- 1.02 0.96 +/- 0.38
-0.002 +/- 0.002
-0.30 +/- 0.84
-0.01 +/- 0.30 0.01 +/- 0.54
-3.12 +/- 3.84 4.38 +/- 1.01 0.09 +/- 0.29
-0.26 +/- 0.51 2
4 100 100 200 10 10 0.5 20 10 10 0.5 20 9.6 10 10 20 10 10 20 0.5 5
1 0.5 5
1 0.01 100 100 100 100 20 2
4 10 20 2
4 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a)
Acceptance Type LLD ActivityC Criteria (4.66 a)
SPW-6881 water 10/10/2007 Tc-99 6.82
-6.58 +/- 4.04 10 SPAP-7743 Air Filter 11/13/2007 Gr. Beta 0.003
-0.002 +/-.0.002 0.01 SPMI-7745 Milk 11/13/2007 Cs-134 2.16 10 SPMI-7745 Milk 11/13/2007 Cs-137 3.46 10 SPMI-7745 Milk 11/13/2007 1-131(G) 5.89 20 SPMI-7745 Milk 11/1312007 Sr-90 0.59 0.73 + 0.35 1
SPW-7747 water 11/13/2007 Cs-134 2.39 10 SPW-7747 water 11/1312007 Cs-137 3.53 10 SPW-7747 water 11/13/2007 1-131(G) 12.51 20 SPW-7747 water 11/13/2007 Sr-90 0.71
-0.04 +/- 0.32 1
SPW-7751 water 11/13/2007 Fe-55 15.50
-4.18 +/- 9.20 1000 SPW-7757 water 11/1312007 H-3 151.35
-14.98 +/- 78.85 200 SPF-7759.
Fish 11/13/2007 Cs-134 5.50 100 SPF-7759 Fish 11/13/2007 Cs-137 5.10 100 SPW-8033 water 11/13/2007 Ni-63 1.45
-0.19 +/- 0.87, 20 W-1 20607 water 12/6/2007 Gr. Alpha 0.40 0.02 +/- 0.28 2
W-120607 water 12/6/2007 Gr. Beta 0.77
-0.70 +/- 0.51 4
h Liquid sample results are reported in pCifLiter. air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b 1-131(G); iodine-131 as analyzed by gamma spectroscopy'.
Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.
Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.
A4-2
TABLE A-5. In-House "DupIicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance E-20, 21 1/2/2007.
E-20, 21 1/2/2007 CF-41, 42 1/2/2007 CF-41, 42 1/2/2007 CF-41, 42 1/2/2007 P-9516, 9517 1/3/2007 LW-9579, 9580 1/4/2007 DW-70085, 70086 119/2007 DW-70037, 70038 1/11/2007 DW-70054, 70055 1/18/2007 DW-701221 70123 1/18/2007 DW-70122, 70123 1/18/2007 DW-70098, 70099 1/25/2007 DW-70110, 70111 1/25/2007 SWU-676, 677 1/30/2007 DW-70148, 70149 1/30/2007 SW-600, 601 2/1/2007 SW-601, 602 2/1/2007 DW-1138, 1139 2/9/2007 MI-721, 722 2/13/2007 SW-847, 848 2/13/2007 SW-847, 848 2/13/2007 DW-70175, 70176 2/14/2007 DW-70187, 70188 2/14/2007 SWU-1162, 1163 2/27/2007 DW-70205, 70206 2/28/2007 PW-1117, 1118 3/1/2007 PW-1117, 1118 3/1/2007 W-2122, 2123 3/5/2007 W-2122, 2123 3/5/2007 W-2085, 2086 3/6/2007 W-2085, 2086 3/6/2007 DW-70232, 70233 3/8/2007 WW-1477, 1478 3/12/2007 WW-1498, 1499 3/15/2007 W-2140, 2141 3/19/2007 W-2140, 2141 3/19/2007 DW-1626, 1627 3/21/2007 MI-1647, 1648 3/21/2007 DW-70248, 70249 3/21/2007 W-2150,2151 3/26/2007 W-2150, 2151 3/26/2007 LW-1941, 1942 3/31/2007 Gr. Beta K-40 Gr. Beta K-40 Sr-90 H-3 Gr. Beta Gr. Alpha Gr. Alpha Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha K-40 Gr. Beta H-3 K-40 Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta Gr. Alpha Gr. Beta H-3 K-40 Gr. Alpha Gr. Alpha Gr. Beta Gr. Beta 1.76 +/- 0.07 1.49 +/- 0.24 18.02 +/- 0.41 11.68 +/- 1.12 0.039 +/- 0.011 270.78 +/- 91.74 0.91 +/- 0.31 7.95 +/- 1.20 55.47 +/-_3.99 2.68 +/- 0.88 4.30 +/- 1.14 4.22 +/- 0.70 3.27 +/- 0.90 2.19 t 0.92 1.77 +/- 0.39 4.65 +/- 1.37 1.24 +/- 0.12 0.89 +/- 0.37 2707.00 +/- 161.00 1330.40 +/- 117.60 3.82 +/- 1.67 7.33 +/- 1.37 11.72 +/- 1.68 6.79 +/- 1.18 3.63 +/- 0.69 0.88 +/- 0.80 3.79 +/- 1.91 7.12 +/- 1.40 6.10 +/- 4.16 10.65 +/- 2.15 2.51 +/- 2.29 11.02 +/- 1.85 4.75 + 1.28 6.41 +/- 1.48 0.83 +/- 0.31 2.31 +/- 1.57 4.26 +/- 1.00 4973.00 +/- 209.00 1448.80 +/- 120.20 11.10 +/- 1.18 3.56 +/- 2.20 9.26 +/- 1.00 1.35 +/- 0.43 1.70 -+0.06 1.57 +/- 0.27 18.81 +/- 0.42 12.67 +/- 0.97 0.026 +/- 0.010 301.18 +/- 92.99 0.93 +/- 0.30 7.92-+/- 1.42 52.87 +/- 4.02 1.88 +/- 0.78 6.25- +/- 1.16 5.33 +/- 0.75 1.97 +/-0.92 1.69 +/- 0.79 2.11 +/- 0.39 5.20 +/- 1.81 1.20 +/- 0.12 1.02 +/- 0.25 2700.00 +/- 161.00 1316.40 +/- 116.50 2.61 +/- 1.24 5.89 +/- 0.90 8.84 +/- 1.32 6.47 +/- 1.08 2.61 +/- 0.44 1.31 +/- 0.79 3.62 +/- 2.09 7.20 +/- 1.39 3.80 +/- 4.30 13.11 +/- 2.42 1.10 +/- 2.78 9.50 +/- 2.01 5.98 +/- 1.31 4.10 +/- 1.25 0.97 +/- 0.33 1.33 +/- 1.64 5.58 +/- 1.02 5190.00 +/- 213.00 1439.30 +/- 126.00 9.90 1.16 3.30 +/- 1.81 10.17 +/- 1.90 1.36 +/- 0.41 1.73 +/- 0.05 1.53 +/- 0.18 18.42 +/- 0.29 12.18 +/- 0.74 0.033 +/- 0.007
.285.98 +/- 65.31 0.92 +/- 0.22 7.94 +/- 0.93 54.17 +/- 2.83 2.28 +/- 0.59 5.28 +/- 0.81 4.78 +/- 0.51 2.62 +/- 0.64 1.94 :t 0.61 1.94 +/- 0.28 4.93 +/- 1.14 1.22 +/- 0.08 0.96 +/- 0.22 2703.50 +/- 113.84 1323.40 +/- 82.77 3.22 +/- 1.04 6.61 +/- 0.82 10.28 +/- 1.07 6.63 +/- 0.80 3.12 +/- 0.41 1.10 +/- 0.56 3.71 +/- 1.42 7.16 +/- 0.99 4.95 +/- 2.99 11.88 +/- 1.62 1.81 +/- 1.80 10.26 +/- 1.37 5.37 +/- 0.92 5.26 +/- 0.97 0.90 +/- 0.22 1.82 +/- 1.14 4.92 +/- 0.71 5081.50 +/- 149.21 1444.05 +/- 87.07 10.50 +/- 0.83 3.43 +/- 1.42 9.72 +/- 1.07 1.36 +/- 0.30 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)o Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-1824, 1825 MI-1824, 1825 AP-2170, 2171 WW-1850, 1851 AP-2198, 2199 AP-2370, 2371 DW-70300, 70301 DW-70300, 70301 DW-70335, 70336 DW-70335, 70336 SW-898, 1899 SW-1898, 1899 SW-1898, 1899 DW-70346, 70347 DW-70346, 70347 DW-70376, 70377 DW-703"76, 70377 DW-70311, 70312 WW-2349, 2350 WW-2461, 2462 LW-2437, 2438 LW-2917, 2918 SO-2583, 2584 SO-2583, 2584 SO-2583, 2584 SO-2583, 2584 SO-2583, 2584 SO-2583, 2584 S-2620, 2621 MI-2610, 2611 W-4469, 4470 SS-2697, 2698 SS-2697, 2698 MI-2790, 2791 W-4505, 4506 DW-3219, 3220 SO-3416, 3417 SO-3416. 3417 SO-3416, 3417 F-3561, 3562 SL-3311,.3312 SL-3311. 3312 4/2/2007 4/2/2007 4/2/2007 4/3/2007 4/3/2007 4/3/2007 4/4/2007 4/4/2007 4/5/2007 4/5/2007 4/10/2007 4/10/2007 4/10/2007 4/11/2007 4/11/2007 4/11/2007 4/11/2007 4/12/2007 4/17/2007 4/25/2007 4/26/2007 4t3012007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/2/2007 5/3/2007 5/7/2007 518/2007 5/8(2007 5/14/2007 5/14/2007 5/26/2007 5/31/2007 5/31,2007 5/31,12007 5/31/2007 614/2007 6/4/2007 K-40 Sr-90 Be-7 H-3 Be-7 Be-7 Gr; Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta H-3 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha H-3 Gr. Beta Gr. Beta Be-7 Cs-137 K-40 Gr. Alpha Gr. Beta Sr-90 H-3 K-40 Gr. Beta Cs-137 K-40 K-40 Gr. Beta 1-131 Cs-137 Gr. Beta K-40 K-40 Be-7 1316.10 +/- 110.60 1.20 +/- 0.50 0.08 +/- 0.01
-5.83 +/- 102.29 0.08 +/- 0.01 0.07 +/- 0.01 3.78 +/- 0.89 2.93 +/- 0.61 24.37 +/- 2,89 20.26 t 1.37 3.86 +/- 1,40 6.31 +/- 1.36 241.99 +/- 93.35 1.83 +/- 1.08 4.62 +/- 0.72 1.81 +/- 0.80 1.84 +/- 0.62 10.82 +/- 1.50 0.71 +/- 0.56 190.30 +/- 100.31 2.71 +/- 0.50 1.97 +/- 0.79 544.99 +/- 247.70 119.22 +/- 36.61 17825.00 +/- 749.90 11.49 +/- 3.96 31.02 +/- 3.74 0.086 +/- 0.024 277.90 +/- 126.70 1549.20 +/- 184.20 10.60 +/- 1.90 0.06 +/- 0.02 8.03 +/- 0.57 1694.30 +/- 126.20 3,30 +/- 1.70 0.62 +/- 0.32 0.15 +/- 0.03 22.88 +/- 2.33 12.26 -t 0.80 3.06 +/- 0.39 0.61 +/- 0.29 5,78 +/- 0.67 1229.80 +/- 110.50 1.10 +/- 0.36 0.08 +/- 0.01 150.05 +/- 80.14 0.08 +/- 0.01 0.07 +/- 0.01 3.66 +/-0.96 2.91 +/-0.64 22.72 +/-2.91 18.33 +/- 1.34 4.78 +/- 1.51 7.03 +/- 1.42 318.10 + 96.48 2.54 + 1.04 4.01 +/- 0.71 1.66 +/- 0.86 2.24 +/- 0.61 13.20 +/- 1.56 0.62 +/- 0.52 115.95 +/- 97.65 2.15 +/- 0.45 2.78 _ 0.81 601.13 +/- 192.20 87.46 +/- 23.97 17672.00 +/- 724.30 8.04 +/- 3.88 26.10 -3.40 0.068 - 0.025 304.40 +/- 101.00 1388.80 - 128.20 11.10 +/- 1.80 0.05 +/- 0.03 7.36 +/- 0.68 1627.60 +/- 128.80 3.90 +/- 1.50 0.69 +/- 0.31 0.15 +/- 0.03 22.46 + 2.37 12.36 +/- 0.65 3.37 +/- 0.45 0.55 +/- 0.25 4.87 +/- 0.25 1272.95 +/- 78.17 1.15 +/- 0.31 0.08 +/- 0.01 72.11 +/-64.97 0.08 +/- 0.01 0.07 +/- 0.01 3,72 +/- 0.65 2.92 +/- 0.44 23.55 +/- 2,05 19.30 +/- 0.96 4.32 +/- 1.03 6.67 +/- 0.98 280.04 +/-67.12 2.19 +/- 0.75 4.32 +/- 0.51 1.74 +/- 0.59 2.04 +/- 0.44 12.01 +/- 1.08 0.66 +/- 0.38 153.13 +/- 70.00 2.43 +/- 0.34 2.38 +/- 0.57 573.06 +/- 156.76 103.34 +/- 21.88 17748.50 +/- 521.29 9.77 +/- 2.77 28.56 +/- 2.53 0.077 +/- 0.017 291.15 +/- 81.02 1469.00 +/--112.21 10.85 +/-t 1.31 0.05 +/- M02 7.70 +/- 0.44 1660.95 t 90.16 3.60 +/- 1.13 0.66 +/- 0.22 0.15 - 0.02 22.67 +/- 1.66 12.31 +/- 0.52 3.21 +/- 0,30 0.58 +/- 0.19 5.33 +/- 0.36 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2
TABLE A-5. In-House "Duplicate* Samples
- Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SL-3992, 3993 SL-3992, 3993 SL-3992, 3993 W-5087, 5088 SW-3710, 3711 W-4062, 4063 W-4062, 4063 AP-4448, 4449 SG-3735, 3736 SG-3735, 3736 SG-3735, 3736
.SG-3735, 3736 LW-4175, 4176 6/4/2007 6/4/2007 6/4/2007 6/11/2007 6/14/2007 6/28/2007 6/28/2007 6/28/2007 6/30/2007 6/30/2007 6/30/2007 6/30/2007 6/30/2007 Be-7 Gr. Beta K-40 Gr. Beta H-3 Gr. Alpha Gr. Beta Be-7 Be-7 Cs-1 37 Gr. Beta K-40 Gr. Beta 0.75 +/- 0.19 13.61 +/- 1.12 2.43 +/- 0.36 8.70 +/- 1.90 9571.51 +/- 287.22 0.76 +/- 0.63 0.97 +/- 0.53 0.10 +/- 0.02 0.84 +/- 0:12 0.07 + 0.01 29.51 +/- 2.22 9.41 +/- 0.31 2.18 +/- 0.60 0.74 +/- 0.32 14.06 -1.08 2.29 +/- 0.40 7,70 +/- 1.90 9879.21 +/-291.42 0.32 +/-0.66 0.58 +/- 0.57 0.09 +/- 0.02 0.82 +/- 0.18 0.07 +/- 0.01 30.81 +/- 2.22 8.90 +/- 0.48 1.93 +/- 0.68 0.75 +/- 0,19 13.84 +/- 0.78 2.36 +/- 0.27 8.20 +/- 1.34 9725.36 +/- 204.59 0.54 +/- 0.45 0.78 +/- 0.39 0.10 +/- 0.01 0.83 +/- 0.11 0.07 +/- 0.01 30.16 +/- 1.57 9.16 +/- 0.29 2.06 +/- 0.45 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass SG-5422, 5423 SG-5422, 5423 AP-4656, 4657 AP-4763, 4764 SG-5430, 5431 SG-54301 5431 SG-5430, 5431 SG-5430, 5431 SG-5430, 5431 WW-4298, 4299 DW-70612, 70613 WW-4918, 4919 MI-4742, 4743 VE-4939, 4940 VE-4939, 4940 VE-4939, 4940 SG-6274, 6275 SG-6274, 6275 SW-5218. 5219 SG-6284, 6285 SG-6284, 6285 SG-6284, 6285 SG-6284, 6285 WW-5310.5311 SW-5393. 5394 SW-5393, 5394 W-5468, 5469 7/2/2007 7/2/2007 7/3/2007 7/3/2007 7/11/2007 7/11/2007 7/1112007 7111/2007 7/11/2007 7/12/2007 7/23/2007 7/25/2007 7/26/2007 8/1/2007 8/1/2007 8/1/2007 8/6/2007 8/6/2007 8/7/2007 8/8/2007 8/8/2007 8/8/2007 8/8/2007 8/9/2007 8/14/2007 8/14/2007 8/15/2007 Gr. Alpha Gr. Beta Be-7 Be-7.
Be-7 Cs-1 37 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Alpha H-3 K-40 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta 1-131 Cs-137 Gr. Alpha Gr. Beta K-40 H-3 Gr. Beta H-3 H-3 10.31 +/- 1.98 18.59 +/- 1.46 0.09 +/- 0.02 0.11 +/- 0.02 10.17 +/- 0.48 0.050 +/-.0.010 17.86 +/- 2.78 26.19 _. 1.74 7.69 +/- 0.30 1.74 +/- 0.74 4.54 +/- 1.11 240.43 +/- 111.12 1820.30 +/- 134.10 0.39 +/- 0.21 5.50 +/- 0.14 3.36 +/- 0.45 16.68 +/- 3.29 40.93 +/- 2.74 1.31 +/- 0.24 0.043 +/- 0.006 9.38 +/- 2.93 33.46 +/- 2.84 16.15 +/- 0.24 644.00 +/- 106.00 2.32 +/- 1.31 190.06 +/- 86.80 262.58 +/- 108.43 10.57 +/- 1.99 20.97 +/- 1.49 0.10 +/- 0,02 0.10 +/- 0.02 10.06 +/- 0.51 0.059 +/- 0.011 15.74 +/- 2.70 25.04 +/- 1.86 7.65 +/- 0.28 2.22 +/- 0.80 4.19 +/- 0.97 216.68 +/- 110.27 1802.90 +/- 199.50 0.45 +/- 0.20 5.76 +/- 0.13 3.36 +/- 0.21 19.26 +/- 3.39 42.42 +/- 2.66 1.42 +/- 0.24 0.051 +/- 0.007 13.61 +/- 3.38 32.87 +/- 2.93 16.23 +/- 0.25 831.00 +/- 113.00 1.71 +/- 1.27 69.05 +/- 80.88 346.53 +/- 111.42 10.44 +/- 1.40 19.78 +/- 1.04 0.10 +/- 0.01 0.11 +/- 0.01 10.12 +/- 0.35 0.055 +/- 0.007 16.80 +/- 1.94 25.62 +/- 1.27 7.67 +/- 0.21 1.98 +/- 0.55 4.37 +/- 0.74 228.56 +/- 78.27 1811.60 +/- 120.19 0.42 +/-0.15 5.63 +/- 0.10 3.36 +/- 0.25 17.97 +/- 2.36 41.68 +/- 1.91
.1.37. +/- 0.17 0.047 +/- 0.005 11.50 +/- 2.24 33.17 +/- 2.04 16.19 +/- 0.17 737.50 +/- 77.47 2.02 +/- 0.92 129.55 +/- 59.32 304.55 +/- 77.74 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass.
Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Result Lab Code Date Analysis First Result Second Result Acceptance VE-5553, 5554 WW-5643, 5644 SWU-5799, 5800 DW-70752, 70753 VE-5917, 5918 VE-5917, 5918 VE-5917, 5918 MI-6009, 6010 MI-6030, 6031 MI-6030, 6031 DW-70718, 70719 DW-70718, 70719 SO-6156, 6157 SO-64841 6485 SO-6484, 6485 SO-6484, 6485 WW-6469, 6470 E-6647, 6648 E-6647, 6648 WW-6656, 6657 TD-7080, 7081 SG-6891, 6892 SG-6891, 6892 AP-7191, 7192 WW-6786, 6787 WW-6786, 6787 VE-6828, 6829 VE-6828, 6829 VE-6828, 6829 SS-6870, 6871 SS-6870, 6871 LW-7507, 7508 MI-6933, 6934 MI-6933, 6934 MI-7059, 7060 F-7213, 7214 F-7213, 7214 WW-7408,.7409 DW-70856, 70857 SO-7508, 7509 SO-7508, 7509 SO-7508. 7509 8/22/2007 8/2212007 8/28/2007 8/31/2007 9/4/2007 9/4/2007 914/2007 9fl 11/2007 9/12/2007 9/1.2/2007 9/12/2007 9/12/2007 9/14/2007 9/17/2007 9/17/2007 9/17/2007 9/21/2007 10/1/2007 10/1/2007 10/112007 10/2/2007 10/3/2007 10/3/2007 10/3/2007 10/862007 10/8/2007 10/8/2007 10/8/2007 10/8/2007 10/9/2007 10!9/2007 10/11/2007 10/16/2007 10/16/2007 10/17/2007 10/24/2007 10124/2007 10/24/2007 10i'24/2007 10/26(2007 10/26/2007 K-40 H-3 Gr. Beta Gr. Alpha Be-7 K-40 Gr. Beta K-40 K-40 Sr-90 Gr. Alpha Gr. Beta H-3 Cs-137 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Gr. Beta H-3 Gr. Alpha Gr. Beta Be-7 H-3 H-3 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 K-40 H-3 K-40 H-3 Gr. Alpha Cs-137 Gr. Beta
. 1.89 t 0.33 259.00 +/- 110.00 2.64 :t 1.18 14.41 +/- 1.48 0.94 +/- 0.17 3.73 +/- 0.37 2.71 +/- 0.10 1348.90 +/- 113.40 1242.70 +/- 118.00 1.00 +/- 0.38 23.04 +/- 3.71 16.1.3 +/- 1.59 181.99 + 90.67 0.01 +/-0.00 24.20 - 2.60 11.52 +/- 1.16 27.19 +/- 2.51 1.82 _ 0.10 1.48 +/- 0.24 2.80 + 0.97 332.00 +/- 229.00 12.93 +/- 2.12 18.08 +/- 1.41 0.09 +/- 0.01 13333 +/-322 13188 +/- 322 0.06 +/- 0.04 5.55 +/- 0.21 5.45 +/- 0.43 18.10+/- 2.08 10.19 +/- 0.66 1.40 +/- 0.56 1386.60 +/- 104.70 1.73 +/- 0.52 1424.80 +/- 106.60 6.83 + 0.22 3.13 +/- 0.51 340.71 + 90.45 11.03 +/- 1.56 0.30 - 0.04 34.43 +/- 2.72 16.84 +/- 0.84 1.89 +/- 0.22 266.00 +/- 110.00 3.62 +/- 1.06 12.90 +/- 1.50 0.83 +/- 0.20 3.58 +/- 0.36 2.69 +/-0.10 1388.10 +/- 116.40 1475.60 +/- 119.60 0.90 +/- 0,34 23.22 +/- 3.61 17.36 +/- 1.69 232.19 +/- 92.95 0.01 +/- 0.00 23.30 +/- 2.30 10.89 +/- 1.10 24.23 +/- 2.29 1.93 +/- 0.11 1.31 +/- 0.23 1.95 +/- 0.87 383.00 +/- 191.00 13.52 +/- 2.07 18.27. +/- 1.36 0.09 +/- 0.01
.13532 +/- 324 13556 +/-326
.0.06 +/- 0.05 5.20 +/- 0.22 5.20 +/- 0.49 21.71 +/- 2.19 9.72 +/- 0.68 1.44 +/- 0.54 1331.20 +/- 106.70 2.17 +/- 0.57 1448.60 +/- 115.30 7.24 +/- 0.22 3.16 +/- 0.48 346.22 +/- 90.67 10.71 :1.34 0.29 + 0.05 37.25 +/- 3.07 17.43. _1.05 1.89 +/- 0.20 262.50 +/- 77.78 3.13 +/- 0.79 13.66 +/- 1.05 0.89 +/- 0.13 3.66 +/- 0.26 2.70 +/- 0.07 1368.50 +/- 81.25 1359.15 +/- 84.01 0.95 +/- 0.26 23.13 +/- 2.59 16.75 t 1.16 207.09 +/- 64.92 0.01 +/- 0.00 23.75 +/- 1.74 11.20 +/- 0.80 25.71 +/- 1.70 1.88 +/- 0.07 1.40 +/- 0.17 2.38 +/- 0.65 357.50 +/- 149.10 13.23 +/- 1.48 18.18 +/- 0.98 0.09 +/- 0.01 13433 +/-228 13372 +/- 229 0.06 +/- 0.03 5.38 +/- 0.10 5.32 +/- 0.33 19.90 +/- 1.51 9.95 +/- 0.47 1.42 +/- 0.39 1358.90 +/- 74.74 1.95 +/- 0.39 1436.70 +/- 78.51 7.03 +/- 0.16 3.15 +/- 0.35 343.46 - 64.03 10.87 +/- 1.07 0.29 + 0.03 35.84 +/- 2.05 17.14 +/- 0.67 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
- Pass, Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 10,2612007 K-40 A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SS-7529, 7530 SS-7529, 7530 SW-7589, 7590 SWU-7733, 7734 MI-7618, 7619 VE-7666, 7667 VE-7666,.7667 VE-7666, 7667 DW-7853, 7854 MI-7874, 7875 WW-8142, 8143 DW-8094, 8095 F-8328, 8329 WW-8378, 8379 10/29/2007 10/29/2007 10/30/2007 10/30/2007 10/31/2007 11/5/2007 11/5/2007 1115/2007 11/9/2007 1-1/14/2007 11/28/2007 11/29/2007 12/11/2007 12/11/2007 Cs-1 37 K-40 Gr. Beta Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 1-131 K-40 Gr. Beta Gr. Beta Gr. Beta H-3 0.12 +/- 0.03 11.85 +/- 0.68 1.75 +/- 0.29 1.66 +/-.1.01 1376.80 +/- 114.30, 0.07 +/- 0.04 6.03 +/- 0.15 5.82 +/- 0.36 1.61 + 0.40 1407.70 + 101.30 9.51 _ 2.21 1.60 0.58 3.97 +/- 0.08 296.00 +/- 103.00 0.12 +/- 0.02 11.75 +/- 0.58 1.24 +/- 0.26 2.43 +/- 1.13 1426.70+/- 128.80 0.16 +/- 0.05 6.13 +/- 0.15 5.74 +/- 0.36 1.08 +/- 0.39 1362.60 +/- 114.50 7.86 +/- 2.01 1.25 +/- 0.54 4.00 +/- 0.08 407.00 +/- 107.00 0.12 +/- 0.02 11.80 +/- 0.45 1.50 +/- 0.1.9 2.05 - 0.76 1401.75 +/- 86.10 0.11 +/- 0.03 6.08 +/- 0.10 5.78 +/- 0.25 1,35 +/- 0.28 1385.15 +/- 76.44 8.68 +/- 1.49 1.43 +/- 0.40 3.99 +/- 0.05 351.50 +/- 74.26 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi!Filter). food products, vegetation, soil, sediment (pCi/g).
A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentrationb Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW--1110 01/01/07 Gr. Alpha STW-1 110 01/01/07 Gr. Beta 0.45 +/- 0.08 0.90 +/- 0.14 0.33 0.85 0.00 -0.65 0.43 - 1.28 STW-1111 STW-1111 STVV-1111 SfW-1111 STW-!111 STW-1111 STW-1111 STW-131111 STW-I 111 STW-1111 STW-1111 SfTW-1111 STW-1111, STW-1111 STW-I 1111 STW-1111 STSO-1112' STSO-1 112 STSO-1 112 STSO-1 112 STSO-1 112 STSO-1 112 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Am-241 Co-57 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 2.80 +/- 0.21 151.60 +/- 10.00 79.20 +/- 8.00 168.70 +/- 12.10 130.30 +/- 19.90 262.20 +/- 9.10 130.60 +/- 11.50 127.80 +/- 3.60 127.80 +/- 3.60 2.03 +/- 0.17 2.27 +/- 0.17 9.60 +/- 1.40 8.80 +/- 1.50 2.44 +/- 0.21 2.44 +/- 0.21 123.70 +/- 17.00 46.40 +/- 9.00 501.20 +/- 2.90 285.90 +/- 2.10 325.90 +/- 7.40 855.70 +/- 4.60 750.90 +/- 4.70 0.27 +/- 0.04 0.57 +/- 0.05 0.10 +/- 0.03 3.51 +/- 0.07 2.98 +/- 0.10 4.02 +/- 0.16 2.75 +/- 0.12 3.94 +/- 0.12 0.07 +/- 0.01 0.08 +/- 0.01 0.58 +/- 0.18 0.09 +/- 0.01 0.09 +/- 0.01 2.70 +/- 0.10 1.71 143.70 83.50 163.00
.129.30 283.00 123.80 130.40 130.40 2.25 2.22 8.87 88.00 2.49 2.48 114.80 34.80 471.20 274.70 327.40 799.70 685.20 1.20 -2.22 100.60 - 18.6.80 58.50 -108.60 114.10 -211.90 90.50 -168.10 198.10 - 367.90 86.70 - 160.90 91.30- 169.50 91.30 - 169.50 1.58 -2.93 1.55 -2.89 6.21 -11.53 7.40 - 13.70 1.74-3.24 1.74 -3.22 80.40 - 149.20 24.40 -45.20 329.80 -612.60 192.30 -357.10 229.20 - 425.60 559.80 - 1039.60 479.60 - 890.80 Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1113 01,/01/07 Gr. Alpha STAP-1113 01/01/07 Gr. Beta STAP-1114 STAP-1 114 STAP-1114 STAP-1114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1114 STAP-1 114 STAP-1 114 STAP-1114 STAP-1114 01/01(07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239!40 S.r-90 U-233/4 U-238 Zn-65 0.60 0.44 0.10 2.89 2.91 4.20 2.57 3.52 0.07 0.08 0.61 0.10 0.10 2.68.
0.00 - 1.20 0.22 - 0.66 0.07 -0.13 2.02 - 3.75 2.03 - 3.78 2.94 - 5.45 1.80 -3.34 2.46 - 4.57 0.05 -0.09 0.06 -0.11 0.43 - 0.79 0.07 -0.13 0.07 -0.13 1.88 - 3.49 A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)R.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 -10.64 Pass STVE-1115 01/01/07 Co-60 6.50 +/- 0.20 5.82 4.08 -7.57 Pass STVE-1115 01/01/07 Cs-134 6.90 +/- 0.30 6.21 4.35 -8.07 Pass STVE-1115 01/01/07 Cs-137
.8.20 +/- 0.30 6.99 4.90 -9.09 Pass STVE-1115 01/01/07 Mn-54 10.10 +/- 0.30 8.46 5.91 -10.98 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bqlkg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
e Result of reanalysis, 2.08 +/- 0.13 pCi/L.
The test samples were recounted on lower background detectors. Result of the recounts: 41.4 +/- 6.3 Bq/kg.
A6-2
TABLE A-7. Interiaboratory Comparison Crosscheck :program, Environmental Resource Associates (ERA)3.
Concentration (pCi/L)
Lab Code b Date Analysis Laboratory ERA Control-Result c Result d Limits Acceptance STAP-i 116 03/19/07 Gr. Alpha STAP-I 116 03/19/07 Gr. Beta 34.64 +/- 2.56 93.41 +/- 3.20 25.8 79.5 12.4 -39 48.8 -116 STAP-1 117 STAP-1 117 STAP-1 117 STAP-1 117 e STAP-1 117 STAP-1117 STAP-1 117 STAP-il 17 STAP-1 117 STAP-1117, STAP-1 117 STAP-1 117 STAP-1 117 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118 STSO-1 118 STSO-1 118 STSO-1118' STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118 STSO-1 118'
,03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 Am-241 Co-60 Cs-134 Cs-137 Fe-55 Mn-54 Pu-238 PuT239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Ac-228 Am-241 Bi-212 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Uranium Zn-65 56.04 +/- 3.90 1610.00 +/- 8.40 1340.40 +/- 48.84 345.30 +/- 8.20
< 134.0
< 5.0 43.32 +/- 2.28 35.23 +/- 2.24 156.10 +/- 6.60 42.22 +/- 1.84 42.00 +/- 1.84 85.79 +/- 3.60 363.80 +/- 11.90 3097.77 +/- 94.96 1000.70 +/- 156.10 2467.87 +/- 114.33 7847.40 +/- 86.60 7910.60 +/- 356.88 4635.00 +/- 99.10 12201.60 +/- 423.20
< 34.0
.2046.80 +/- 127.20 4142.80 +/- 110.40 1099.20 +/- 73.10 1586.10 +/- 82.00 6163.30 +/- 791.60 4329.40 +/- 569.10 3236.70 +/- 106.00 3425.20 +/- 134.00 6787.80 +/- 240.00 6787.80 +/- 240.00 0.00 +/- 0.00 57.5 1300.0 1120.0 255.0 0.0 0.0 37.4 31.6 156.0 47.8 47.4 97.3
- 245.0 2790.0 927.0 2500.0 7330.0 7560.0 4300.0 11100.0 0.0 1730.0 3330.0 857.0 1360.0 7500.0 3590.0 3620.0 3590.0 7380.0 7380.0 0.0 33.1 -80 1010.0 - 1620 732.0- 1380 192.0 -336 25.7 - 49 22.9 -41 66.6 -246 30.1 -71 30.2 - 68 49.5 - 155 208:0 -412 1790.0 -3930 548.0 - 1200 658.0 - 3730 5340.0 - 9820 4850.0 - 9070 3290.0 - 5580 8050.0 - 15000 1120.0 -2430 1980.0 -4980 490.0 - 1200 928.0 - i810 2610.0 - 12400 2190.0 -4560 2280.0 -4520 2190.0 -4560 4210.0 -9930 4210.0 -9930 0.0 -0 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
" A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code b Date Analysis Laboratory
- ERA, Control Result c Result d Limits Acceptance STVE-1 119 03/19/07 Am-241 3249.60 +/- 150.30 3550.0 2020.0 - 4890 Pass STVE-1119 03/19/07 Cm-244 1860.70 +/- 91.50 1840.0 905.0 -2870 Pass STVE-1119 03/19/07 Co-60 2827.90 +/- 62.40 2600.0 1760.0 -3720 Pass STVE-1119 03/19/07 Cs-1 34 654.80 +/- 48.40 579.0 308.0 -822 Pass STVE-1119 03/19/07 Cs-1 37 3307.30 +/- 58.80 2920.0 2150.0 -4060 Pass STVE-1 119 03/19/07 K-40 40814.20 +/- 618.80 37900.0 27200.0 - 53600 Pass STVE-1 119' 03/19/07 Mn-54
< 27.6 0.0 Pass S-VE-1119 03/19/07 Pu-238 2762.00,+/- 251.10 2430.0 1250.0 -3600 Pass STVE-1119 03/19/07 Pu-239/40 2156.60 +/- 83.40 1900.0 1180.0 - 2600 Pass STVE-1119 03/19/07 Sr-90 8999.70 +/- 580.90 8890.0 4900.0 -11800 Pass STVE-1119 03/19/07 U-233/4 2821.90 +/- 73.50 2940.0 1930.0 -3920 Pass STVE-1119 03/19/07 U-238 2896.10 +/- 50.70 2910.0 2090.0 -3610 Pass S1VE-1119 03/19/07 Uranium 5718.00 +/- 124.15 5980.0 4110.0 - 7770 Pass S'VE-1119 03/19/07 Zn-65 474.30 +/- 45.70 366.0 267.0 -500 Pass STW-1120 03/19/07 Am-241 133.50 +/- 10.60 179.0 123.0 -243 Pass STW-1120 03/19/07 Co-60 541.40 +/- 9.00 536.0 467.0 -631 Pass STW-1120 03/19/07 Cs-134 1623.80 +/- 66.10 1750.0 1290.0 - 2020 Pass STW-1120 03/19/07 Cs-137 1839.10 +/- 17.90 1850.0 1570.0 - 2220 Pass STW-1120 03/19/07 Fe-55 829.50 +/- 226.80 671.0 392.0 -896 Pass STW-1120 03/19/07 Mn-54
< 8.1 0.0 Pass STWV-1120 03/19/07 Pu-238 123.30 +/- 4.30 116.0 87.6 - 144 Pass STW-1120 -
03/19/07 Pu-239/40 95.10 +/- 3.80 90.9 70.3 - 113 Pass STW-1120 03/19/07-Sr-90 949.40 +/- 16.70 989.0 630.0 - 1320 Pass STW-1120 03/19/07 U-233/4 164.20 +/- 6.58 192.0 145.0 -247 Pass STW-1120 03/19/07 U-238 169.20 +/- 8.22 190.0 145.0 -236 Pass STW-1120 03/19/07 Uranium 339.60 +/- 10.66 391.0 282.0 -521 Pass STW-1120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 - 2410 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
eAhigh bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry. Result of recalculation. Cs-137, 305.8 +/- 6.0 pCi/filter.
flncluded in the testing series as a "false positive". No activity expected.
A7-2
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L the lower limit of.detection based on 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x: +/- Sl and x2 +/- s2 Reported result:
x +/-s; where x (1/2) (Xl+x2)ands= (1/2) 4+s 3.2.
Individual results:
<-1
<L2 Reported result: <L, where L lower of 1-and L2 3.3.
Individual results:
x +/- s, <L Reported result:
x +/- s if.x >L; <L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2 xn are defined as follows:
-x x )2 s=.x n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1.
If the, number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number fo!loWing those to be retained is equal to cr greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-2
POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations C-1
POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No.
Codes (and Type)a (and Frequency)b (and Frequency)b Airborne Filters 6
E-1-4, 8, 20 Weekly GB, GS, on OC for each location Airborne Iodine 6
E-1-4, 8,20 Weekly 1-131 Ambient Radiation 22 E-1-9, 12, 14-18, 20, Quarterly Ambient Gamma (TLD's) 22-32, 34-36, 38,39 Lake Water 5
E-1, 5, 6,33 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water 1
E-10 Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 8
E-1-4, 6, 9, 20 3x / year GB, GS as available Shoreline Silt 5
E-1, 5, 6,12, 33 2x year GB, GS Soil 8
E-1-4, 6, 8, 9, 20 2x/ year GB, GS Milk 3
E-11,40,21 Monthly GS, 1-131, Sr-89-90 Algae 2
E-5, 12 3x I year GB, GS as available Fish 1
E-13 3x/year GB, GS (in edible portions)'
as available SPECIAL COLLECTIONS AND ANALYSES Airborne Filters 4 per month Sr-89, Sr-90 1 per quarter Sr-89, Sr-90 (comp.)
Liquid 1 per month GA, Sr-89, Sr-90 Subsoil Water 4 per quarter GA, GB, H-3, GS Miscellaneous Water Samples.
4-5 per year Sr-89, Sr-90 a Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.
b Analysis type is coded as follows: GB = gross beta, GA = gross alpha, GS = gamma spectroscopy, H-3 = tritium, Sr-89 = strontium-89, Sr-90 = strontium-90, 1-131 = iodine-131. Analysis frequency is coded as follows:
MC = monthly composite, QC = quarterly composite.
C-2
POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends D-1
POINT BEACH Air Particulates - Gross Beta Location E-1, monthly averages 2005-2009 0.05 0.04-O0.02
..-%-T-----
0.01 0-
-r T---r-2005 2006
-2007 2008 2009 2010 Year Location E-2, monthly averages 2005-2009 0.05 0.1 0041....
0
~
2005 2006 2007 2008 2009 2010 Year D-2
POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2005-2009 E
0L 0.04 10 0.04 0.03 0.02 0.01 K 0
2005 2006 2007 2008 2009 2010 Year Location E-4, monthly averages 2005-2009 0.05 0.04 {"
- 0.02
.r-0.01 H-0 41-2005 2006 2007 2008 2009 2010 Year D-3
POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2005-2009 0.05 O
OQ
'I 0.04 0.01 0 -
1T 2005 2006 2007 2008 2009 2010 Year Location E-20, monthly averages 2005-2009 0.05
.0.04 c~0.032 0.01 2005 2006 2007 2008 2009 2010 Year D-4
Environmental, Inc. Midwest Laboratory Groundwater Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 2007
APPENDIX 2 Environmental, Inc. Midwest Laboratory Groundwater Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 2007
- Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700. fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-753 Point Beach Nuclear Plant DATE:
03-08-2007 Wisconsin Electric Power Company SAMPLES RECEIVED:
01-09-2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Below are the results of the analyses for tritium in two Water samples.
Sample Description Beach Drain S-1 S-3 S-3 Collection Date 01-04-07 01-04-07 01-04-07 Lab Code EW-179 EW-180 EW-181a Isotope Concentration / LLD (pCi/L)
H-3 168 90/
174 +/- 90/
116 88/.
-<166
< 166
< 166 a Denotes a duplicate.
The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
Sincerely, Br a ro, M.S.
Lab rato anager I/
Il APPROVED BY Tony Coorlim, Quality Assurance
- . Environm ental, Inc.
Midwest Laboratory an Allegheny Technologres Co.
700 Lanjweh-Roac. Norfirrook IL 60162-2O10 ph (847) 554-0700 laý (8.17 584-4517 Dr. Kjell Johansen FPL Energy LABORATORY REPORT NO.:
8006-100-813 Point Beach Nuclear Plant DATE:
02-19-2008 6610 Nuclear Road SAMPLES RECEIVED:
02-12-2008 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below is the result of the analysis for tritium in one water samples collected February 7, 2008.
Sample Lab Concentration J LLD (pCi/L)
Description Code H-3 S-I (Beach Drain)
EXW-514 302 + 77 / < 153 The error given is the probable counting error at the 95% confidence level. The less than (<)value,. is based on 4.66 sigma counting error for the background sample.
Sincereal Br ia M.S.
Lab at y M nager E-mail: KjellJohansen@fpl.com APPROVED BY
- '~
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co. "
700 Landwehr Road
- Northbrook. IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.':
8006-100-754 Point Beach Nuclear Plant DATE:
03-30-2007 Wisconsin Electric Power Company SAMPLES RECEIVED:
03-16-2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Below are the results of the analyses for tritium in three water samples.
Sample Description Beach Drain S-1 S-3 S-8 Collection Date 03-13-07 03-13-07 03-13-O7 Lab Code EXW-1464 EXW-1465 EXW-1466 Isotope Concentration / LLD (pCi/L)
H-3 683 102/
269 +/- 89/
443 +/-96/
< 140
< 145
< 145 The error given is the probable counting error at 95% confidence level and LLD values are counting error for the background sample.
based on 4.66 sigma
(
I 4
APPROVED BY Tony Coorlim, Quality Assurance
Environmental, Inc.
Midwest Laboratory an Allegheny Tachnologles Co.
700 Landwehr Road
- Nonrlbrook, IL 60062-2310 ch. (847) 564-0700
- fax (847)564.4517 Dr. KjelI A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-762 Point Beach Nuclear Plant DATE:
05-10-2007 Wisconsin Electric Power Company SAMPLES RECEIVED:
04-27-2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Below are the results of the analyses for tritium in two water samples.
Sample Description Beach Drain S-1 S-3 Collection Date 04-25-07 04-25-07 Lab Code EXW-2443 EXW-2444 Isotope Concentration / LLD (pCi/L)
H-3 174 +/- 901 120 +/- 88/
< 157
< 157 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
Sincerely, N~J APPROVED BY Tony Coorlim, Quality Assurance
Environmental, Inc.
Midwest Laboratory S
an Allegheny Technologies Co.
700 Lajdwehr Road - Northbrook. It 60062-2310 ph. (847) 564.0700
- fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-764 Point Beach Nuclear Plant DATE:
05-22-2007 6610 Nuclear Road SAMPLES RECEIVED:
05-15-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in two water samples.
Sample Description Beach Drain S-1 S-3 Collection Date 05-11-07 05-11-07 Lab Code EXW-2767 EXW-2768 Isotope Concentration / LLD (pCi/L)
H-3 208:t 102/,< 179 165i 100/< 179 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
SIncer Br ni Gr b, M. S Lab rat ry anager APPROVED BY At
-"J Tony &roorlim, Quality Assurance
I Environmental, Inc.
Midwest Laboratory aAlegheny Technologies Co.
700 Landwehr Road, Nortllbraok, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-769 Point Beach Nuclear Plant DATE:
06-21-2007 Wisconsin Electric Power Company SAMPLES RECEIVED:
06-11-2007 6610 Nuclear Road.
PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Below is the result of the analysis for tritium in one water sample.
Sample Description Beach Drain S-3 Collection Date 06-06-07 Lab Code EXW-3502 Isotope Concentration / LLD (pCVL)
H-3 336 +/-98 1169 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
Sincerely,
(
SI APPROVED BY Tony Coorlim, Quality Assurance N
O il ý ý ý ý I ý ý I; ý ý ý i, ýý
ýý
.Environmental, Inc..
Midwest Laboratory an AJlegheny Technologes Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-772 DATE:
07/30/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
07/06/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD S-1, Beach Drain EXW-4047 07/03/07 243 +/- 103
< 176 S-3, Beach Drain EXW-4048 07/03/07 270 +/- 88
< 143 The error given is the probable counting error at the 95% confidence level.
Less than (<) values are based on a 4.66 sigma counting error for the background sample.
SA Coorlim Quality Assurance La inager
Environmental, Inc.
Midwest Laboratory an A109tnliy TtehnlogalS to.
Dr. Kjell Johansen Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 LABORATORY REPORT NO.:
DATE:
SAMPLES RECEIVED:
PURCHASE ORDER NO.:
8006-100-776 09/07/2007 08/14/2007 Sample ID Lab Code Collection Date H-3 (pCiIL)
LLD Fagade Subsoil Sump Composite EXW-5147 07/03/07 708 + 127
< 189 S-1, Beach Drain EXW-5296 08/09/07 246 h 91
< 152 S-3, Beach Drain EXW-5297 08109/07 358 96
< 152 The error given is the probable counting error at the 95% confidence level.
Less than (<) values are based on a 4.66 sigma counting error for the background sample.
SA Coorlim Quality Assurance C6-b b
Manager QL I oBrt ji
Environmental, Inc.
Midwest Laboratory in MleheryT!0s Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-782 DATE:
09/24/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/17/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD S-3 EXW-5914 09/05/07 299 +/- 96
< 165 GW-1 1 EXWW-6038 08/27/07 248 : 102
< 185 GW-12 EXWW-6039 08/29107 93 :E 96
< 185 GW-13 EXWW-6040 08/29/07 70 +/- 95
<185 GW-13 (duplicate)
EXWW-6041 08/29/07 136 :a98
< 185 GW-14 EXWW-6042 08/11/07 189 +/- 100
< 185 GW-15 EXWW-6043 09/04/07 224 : 101
< 185 GW-16 EXWw-6044 09/04/07 15 +/- 92
< 185 2Z-361B EXWW-6177 03/10/07 4207 +/- 213
< 189 2Z-361B (Duplicate)
EXWW-6178 03/10/07 4205 +/-213 -
< 189 2Z-361A EXWW-6179 03/10/07
-20 +/- 93
< 189 1 Z-361A EXWW-6180 03/10/07 1019 +/- 133
< 189 1Z-361B EXWW-6181 05/07/07 168 +/- 101
< 188 2Z-361B EXWW-6182 06/26/07 2678 +/-177
< 186 IZ-361A EXWW-6183 06/26/07 1381 +/-143
< 186 2Z-361A EXWW-6184 07/27/07 47 +/- 94
< 185 1Z-361B EXWW-6185 07/27/07 183 +/-100
< 185 Faqade, Subsoil Sump
- EXWW-6192 09/01/07 529 +/- 105
< 165 The error given is the probable counting error at the 95% confidence level.
Less than (<)val es are based on a 4.66 sigma counting error for the background sample.
SA Coorfim Quality Assurance 2
'y ManaGrob baoManager
Environmental, Inc.
.Midwest Laboratory SAllegheny Techno~ogies Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-785 DATE:
10/16/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/28/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD GW-04 EXWW-6544 09/26/07 36 +/- 101
< 189 S-1 (Beach Drain)
EXWW-6773 10/04/07 112 +/- 107
< 195 S-3 (Beach Drain)
EXWW-6774 10/04/07 46 +/- 104
< 195 Approval v/ESfGL 0 CT 2007 7 9
- ACCCUNTS PAYABLE - PBNP C
IV #
R&c Notice T The error given is the probable counting error at the 95% confidence level.
Less than (<) value. are based on a 4.66 sigma counting error for the background sample.
J SA Coorlim Quality Assurance
(
ýaZraoýia Grob
',jry Manager
, Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Norlthbrook. IL 60062-2310 ph. (847) 564-0700. fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-792 Point Beach Nuclear Plant DATE:
12-28-2007 6610 Nuclear Road SAMPLES RECEIVED:
11-12-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are theresults of the analyses for tritium in two water samples.
Sample Description Beach Drain S-1 S-3 Collection bate 11-08-07 11-08-07 Lab Code EXW-7730 EXW-7731 Isotope Concentration / LLD (pCi/L)
H-3 588 104/< 151 234 90/< 151 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
Tony Coorlim, Quality Assurance APPROVED BY
-U,> Environmental, Inc.
Midwest Laboratory an Allegheny Technotogies Co.
700 Landwehr Road. Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-797 Point Beach Nuclear Plant DATE:
12-21-2007 6610 Nuclear Road SAMPLES RECEIVED:
12-06-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in two water samples.
Sample Description Beach Drain s-1
-S-3 Collection Date 12-04-07 12-04-07 Lab Code EXW-8200 EXW-8201 Isotope Concentration I LLD (pCi/L)
H-3 321 91/< 145 238 87/< 145 The error given is the probable counting error at 95%
counting error for the background sample.
confidence level and LLD values are based on 4.66 sigma APPROVED BY Tony Coorlim, Quality Assurance
Environmental, Inc.
Midwest Laboratory
~an Allegheny Technologies Co.
700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-757 Point Beach Nuclear Plant DATE:
04-03-07 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
03-06-07 6610 Nuclear Road Two Rivers, Wisconsin 54241
Dear Mr. Corell:
Below is the result of the analysis for tritium in one water sample.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA EC 02-10-07 EWW-1199 31 88
<181 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered is the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
cc: K. Johansen Sincerely, Ellen Saar Prolct Coa*nator L brniatýr Maa.S.
Lborat *Manager APPROVED BY
Environmental, Inc.
Midwest Laboratory anAllegheny Technologies Co.
700 Landwehr Road. Northbrock. IL 60062-2310 ph, (847) 564-070 0
- fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-756 Point Beach Nuclear Plant DATE:
04-17-2007 Wisconsin Electric Power Company SAMPLES RECEIVED:
03-30-2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Below are the results of tritium analyses on six water samples.
Sample Lab Concentration/LLD Collection Description Code H-3 (pCi/L)
Date GW-01 (Bridge)
EWW-1750 87 +/- 92 1< 169 03-28-07 GW-02 (East Creek)
EWW-1751 225 +/- 98 / < 169 03-28-07 GW-03 (West Creek)
EWW-1752 116 +/- 94 /< 169 03-28-07.
GW-04 (Energy Center)
EWW-1753 76 +/-92 / < 169 03-28-07 GW-05 (Warehouse 6)
EWW-1754 21 +/- 90 / < 169 03-28-07 GW-06 (SBCC)
EWW-1755
-89 +/- 85 1.< 169 03-28-07 GW-06 (SBCC)
EWW-1756"
-10 +/- 88 / <169 03-28-07 a Denotes a duplicate.
The less than, (<), value is based on 4.66 counting error for background sample. The error given is the probable counting error at 95% confidence level.
APPROVED BY
,. Environmental, Inc.
Midwest Laboratory an Allegheny Techwobgis Co.
700 6Lnf¶ehr Road - N*rhbarook, IL 6D062-23 ph. (847) 564-0700
- fax (847) 564-4517 Dr. Kjell Johansen Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 LABORATORY REPORT NO.: 8006-100-760 DATE:
06-18-07 SAMPLES.RECEIVED:
04-16-07 Well Water, analyses for gross beta, iodine-131, tritium, strontium-89, strontium-90 and gamma emitting isotopes.
Lab Code EWW-2008 EWW-2010 Date Collected 04-11-07 04-11-07 Location GW-06 SBCC GW-5 Isotope Activity / MDC (pCilL)
Activity / MDC (pCi/L)
Gross Beta 4.84 +/- 3.19
< 5.82 9.37 +/- 2.68
< 4.45 1-131
-0.090 +/- 0.22.
< 0.40
-0.23 +/- 0.20
< 0.39 Sr-89 0.033 +/- 0.49
< 0.56
-0.45 +/- 0.45
< 0.57 Sr-90 0.094 +/- 0.24
< 0.49 0.19 +/- 0.22
< 0.42 H-3 99.5 +/- 87.2
< 166.7 64.4 +/- 85.6
< 166.7 The error given is the probable counting error at the 95% confidence level. The less than value (<) is based on a 4.66 E counting error for the background sample.
Gamma*
Be-7 Mn-54 Co-58 Co-60 Fe-59 Zn-65 Zr-Nb-95 Ru-103 Cs-134 Cs-137 Ba-La-140
-11.37 +/- 18.30
-0.87 +/- 2.07 1.67 +/- 2.09 1.11 +/- 1.79
-2.22 +/- 3.35
-3.26 +/- 3.90
-0.28 +/- 2.24
-0.84 +/- 1.97
-2.17 +/- 2.20
.1.31 +/- 2.34 1.87 +/- 2.16
< 42.58
< 3.48
< 3.71
< 2.08
< 4.01
< 3.39
< 4.19
< 5.19
< 2.78
< 2.43
- 3.30 8.69 +/- 13.50 1.01 +/- 1.56 0.70 +/- 1.25 0.20 t 1.46
-4.30 +/- 3.09 1.21 +/- 3.33
-0.52 +/- 1.74
-1.40 +/- 1.56 0.95 +/- 1.29
-1.07 +/- 1.58
-0.17 +/- 1.78
< 26.49
< 2.78
< 1.95
.< 1.93
< 3.13
< 5.37
< 1.99
< 2.57
< 2.48
< 2.72
< 2.75
- For those isotopes where both an activity and an MDC value are given, the MDC value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample) and the activity is presented for Information only. For isotopes where an activity Is given, but no MDC value, the activity Is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
/ S i nce rei. y, Approved:
A A.t SA Coollirn Quality Assurance
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-765 Point Beach Nuclear Plant DATE:
05-30-07 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
04-27-07 6610 Nuclear Road Two Rivers, Wisconsin' 54241
Dear Mr. Corell:
Below are the results of the analyses for tritium in four water samples.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA GwU-VI E-001 Met Tower 04-25-07 East Creek Gw 04-25-07 West Creek C.-r-. 04-25-07 EWW-2445 EWW-2446 EWW-2447 EWW-2448
-79 +/- 79 93 +/- 87
-77 +/- 79
-156 +/- 75
<157
<157
<157
<157 EC ~-.
04-25-07 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
cc: K. Johansen Sincerely, Ellen Saar Project Coordinator APPROVED BY brbary Manager
- .Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Mr, Gary Corell LABORATORY REPORT NO.:
8006-100-770 Point Beach Nuclear Plant DATE:
-.07-03-07 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
06-05-07 6610 Nuclear Road Two Rivers, Wisconsin 54241
Dear Mr. Corell:
Below are the results of the analyses for tritium in six water samples.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA E-001 Met Tower 05-31-07 ESW-3364 98 +/- 80
<143 East Creek &
2" 05-31-07 ESW-3365 102 88
<169 West Creek C'tv 05-31-07 ESW-3366 72 +/- 87
<169 EC 05-31-07 EWW-3367 185 +/- 92 North Side Bog 05-31-07 ESW-3368 223 + 94 Energy Center Bog 05-31-07 ESW-3369 398 + 101 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
cc: K. Johansen Sincerely,
,APPROVED BY M.S.
- =- Environmental, Inc.
Midwest Laboratory an. Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-773 Point Beach Nuclear Plant DATE:.
08-06-07 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
06-29-07 6610 Nuclear Road Two Rivers,,Wisconsin 54241
Dear Mr. Corell:
Below are the results of the analyses for-tritium in four water samples.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity,.
MDA E-001 Met Tower 06-27-07 ESW-3977
-1 +/- 75
<143 East Creek 6W'02' 06-27-07 ESW-3978 73 +/- 79
<143 West Creek 6o*0 06-27-07 ESW-3979 129 +/- 82
<143 EC quJ.-
L 06-27-07 EWW-3980 43 +/- 77
<143 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
cc: K. Johansen Sincerely, Saar oordinator APPROVED BY B-roniatGrob, M.S.
Laboratory Manager
- Environmental, Inc.
Midwest Laboratory an Alfth"~ Te~i10*oes Co.
700 Lanowthr Road Northbmok. IL 60062-2310 ph. (847) 564-700 fax (547) 564-517, Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-778 Point Beach Nuclear Plant DATE:
08-31-07 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
07-30-07 6610 Nuclear Road Two Rivers, Wisconsin 54241
Dear Mr. Corell:
-*l"are----heresuIts of Wt-ariay-
-fo rI tri'um-ii-f our-,wate-r s a m p les.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA E-001 Met Tower 07-25-07 ESW-4779 126 + 107
<195 East Creek 6W 07-25-07 ESW-4780 103 +/- 107
<195 West Creek 07-25-07 ESW-4781 30 +/- 104
.<195 EC W'104 07-25-07 EWW-4782
-9 +/- 80
<153 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for-the background sample ) and the activity is presented for information only. For Isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
cc: K.,Johansen Sincerely, APPROVED BY REC'D P 2 8 2007
Environmental, Inc.
Midwest Laboratory an Aghey Technologles Co.
700 LancdweIr Road
- Northlnook. IL 60062-23 ph. (847) 56-0700 f fax (847) 564-4517 Dr. Kjell Johansen Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 LABORATORY REPORT NO.: 8006-100-779 DATE:
08-24-07 SAMPLES RECEIVED:
07-16-07 Well Water, analyses for gross beta, iodine-1 31, tritium, strontium-89, strontium-90 and gamma emitting isotopes.
Lab Code.
Date Collected Location EWW-4297 07-12-07 GW-06 SBCC EWW-4300 07-12-07 GW-5 Isotope Activity / MDC (pCi/L)
Activity/ MDC (pCi/L)
Gross Beta 0.21 +/- 0.75
< 1.12 3.15 +/- 0.79
< 1.03 1-131 0.18 +/- 0.24
< 0.36 0.13 +/- 0.25
< 0.36 Sr-89
- 0.50 +/- 0.71
< 0.81
-0.05 +/- 0.57
< 0.60 Sr-90
-0.17 +/- 0.32
< 0.74 0.10 +/- 0.27
< 0.56 H-3 56 +/- 79.
< 146
.21 + 78
< 146 The error given is the probable counting error at the 95% confidence level. The less than value (<) is based on a 4.66 s counting error for the background sample.
Gamma Be-7 Mn-54 Co-58 Co-60 Fe-59 Zn-65 Zr-Nb-95 Ru-103 Cs-134 Cs-137 Sa-La-140
-22.22 +/- 28.69 0.28 +/- 3.89
-1.30 +/- 3.95 0.14 +/- 4.53
-2.76 +/- 6.37
-3.23 +/- 6.66
-3.85 +/- 3.47
-1.69 +/- 3.59 1.29 +/- 2.96 0.09 +/- 3.27 2.49 +/- 3.84
< 31.62
< 4.53
< 5.78
< 5.86
< 10.66
< 3.34
< 5.37
< 6.28
< 5.34
< 4.88
< 5.61
-0.73 +/- 22.83
-0.68 +/- 3.15 2.80 +/- 2.90 1.25 +/- 3.64 2.21 +/- 6.27
-5.03 +/- 7.51 0.53 +/- 3.67 2.02 +/- 2.97
-3.15 +/- 3.82 0.97 +/- 3.71 1.42 +/- 3.88
< 41.98
< 2.12
< 4.08
< 4.16
< 8.85
< 4.01
< 6.66
< 5.90
< 5.03
< 3.89
< 8.25
'For those isotopes where both an activity and an MDC value are given, the MDC value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample) and the activity is presented for information only. For isotopes where an activity is given, but no MDC value, the activity is considered the reportable value and the error given is the probable counting error at the.95% confidence level.
Sincerely, Approved:
,t
~ ~'ACoorlir" Quality Assurance
Environmental, Inc.
- Midwest Laboratory AW f
M heny Te-hnologies Co, 700 Landwehr R.ad ° 5ortbrook, PL 60062-2310 ph. (047) 564-0700
- fu (S47) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-783CR Point Beach Nuclear Plant DATE:.
03-31-08 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
08-31-07 6610 Nuclear Road Two Rivers, Wiscons)n 54241
Dear Mr. Corell:
Below are the results of the analyses for tritium in four water samples.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA E-001 (GW-01) 08-29-07 ESW-5867 88 +/-186
<166 East Creek (GW-02) 08-29-07 ESW-5868 103 _ 87
<166 West Creek (GW-03) 08-29-07 ESW-5869 164 t 90
<166 Duplicate of 5869 08-29-07 ESW-5870 126 +/- 88
<166 EC (GW-04) 08-29-07 EWW-5871 124 +/- 88
<166 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for-the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the actKiity is considered the reportable value and the error given is the probable counting error at the 95% confidence level, cc: K. Johansen Ellen Saar Project Coordinator APPROVED BY
\\~Por~or~na-iaer
Environmental, Inc.
Midwest Laboratory 1___'
gn Arl*g*'ny TeChnologin Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-785 DATE:
10/16/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/28/2007 6610 Nuclear Road PURCHASE ORDER NO,:
Two -Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD GW-04 EXWW-6544 09/26/07 36 +/- 101
< 189 S-1 (Beach Drain)
EXWW-6773 10/04/07 112 +/- 107
< 195 S-3 (Beach Drain)
EXWW-6774 10/04/07 46 +/- 104
< 195 OCT 2k 2007
- ACCOUNTS PAYABLE - PBNP
, c.,',c.'ce #
The error given is the probable counting error at the 95% confidence level.
Less than (<)value§ are based on a 4.66 sigma counting error for the background sample.
/
1i SA Coorlim Quality Assurance abgratry Manager 1\\1 I
E Environm-e~ntal, Inc.
MIdWest Laboratory an Aliegheft Tafth~bgeS CO.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-782 DATE:
09/2412007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/1712007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD S-3 EXW-5914 09/05/07 299 _ 96
< 165 GW-1 I EXWW-6038 08127/07 248 +/- 102
< 185 GW-12 EXWW-6039 08/29/07 93 +/- 96
< 185 GW-13 EXWW-6040 08/29/07 70 +/- 95
< 185 GW-13 (duplicate)
EXWW-6041 08/29/07 136 +/- 98
< 185 GW-14 EXWW-6042 08/11/07 189 +/- 100
< 185 GW-15 EXWW-6043 09/04/07 224 +/- 101
< 185 GW-16 EXWW-6044 09/04/07 15 +/-92
<185 2Z-361B EXWW-6177 03/10/07 4207, 213
< 189 2Z-361B (Duplicate)
EXWW-6178 03/10/07 4205 +/- 213
< 189 2Z-361A EXWW-6179 03/10/07
-20 +/- 93
< 189 I Z-361A EXWW-6180 03/10/07 1019 +/- 133
< 189 1Z-361B EXWW-6181 05/07/07 168 +/- 101
< 188 2Z-361B EXWW-6182 06/26/07 2678 +/- 177
< 186 1Z-361A EXWW-6183.
06/26/07 1381 +/- 143
< 186 2Z-361A EXWW-6184 07/27/07 47 +/- 94
< 185 1Z-361 B EXWW-6185 07/27/07 183 +/- 100
< 185 Facade, Subsoil Sump EXWW-6192 09/01/07 529 +/- 105
< 165 The error given is the probable counting error at the 95% confidence level.
Less than (<) val es are based on a 4.66 sigma counting error for the background sample.
SA Cooriim Quality Assurance
Environmental, Inc.
Midwest Laboratory an AIregtn TemnaoboeS Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-804 DATE:
01/18/2008 Point Beach Nuclear Plant SAMPLES RECEIVED:
10/12/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD GW-05 (Warehouse 6)
EWW-6865 10/09/07 65 +/- 81
< 148 GW.06 (Site Boundary EWW-6866 10/09/07 39 +/- 80
< 148 Control Center)
The error given is the probable counting error at the 95% confidence level.
Less than (<) values are based on a 4.66 sigma counting error for the background sample.
/7
<V 1)
~ /lJ~V SA Coorlim Quality Assurance O yAuac, "Brojya Grob a boýr
~y Manager
ii Environmental, Inc.
" Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700., fax (847) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-802 Point Beach Nuclear Plant DATE:
01-02-08 Wisconsin Electric Power Co.
SAMPLES RECEIVED:
12-03-07 6610 Nuclear Road Two Rivers, Wisconsin 54241
Dear Mr. Corell:
Below are the results of the analyses for tritium in four water samples.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA E-001
&, -1 l NDa East Creek G-,
2 NDa West Creek 6 NDa EC 6LU -OL 11-29-07 EWW-8128
-70 79
<157 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
a"ND, = No data; ice buildup.
cc: K. Johansen APPROVED BY iager
.. Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 Dr. Kjell Johansen FPL Energy LABORATORY REPORT NO.:
8006-100-796 Point Beach Nuclear Plant DATE:
01-07-2008 6610 Nuclear Road SAMPLES RECEIVED:
12-19-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in six ground water samples collected December 13, 2007.
Sample Lab Concentration / LLD (pCi/L)
Description Code H-3 GW-11 (MW-01)
EXWW-8460 116 +/- 96/< 173 GW-12 (MW-02)
EXWW-8461
-19 +/- 90/< 173 GW-13 (MW-06)
EXWW-8462 85 +/- 95 / <173 GW-14 (MW-05)
EXWW-8463 75 +/- 94 / < 173 GW-15 (MW-04)
EXWW-8464 329 +/- 104/ < 173 GW-16 (MW-03)
EXWW-8465 186 +/- 99 /< 173 The error given is the'probable counting error at the 95% confidence 4.66 sigma counting error for the background sample.
E-mail: KjellJohansen@fpl.com level. The less than (<) value, is based, on APPROVED BY
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700 f ax (847) 564-4517 Mr. Gary Corell LABORATORY REPORT NO.:
8006-100-810 Point Beach Nuclear Plant DATE:
01-31-08 6610 Nuclear Road SAMPLES RECEIVED:
12-28-07 Two Rivers, Wisconsin 54241
Dear Mr. Corell:
Below is the result of the analysis for tritium in one water sample.
Concentration H-3 (pCi/L)
Location Date Collected Lab Code Activity MDA E-001 ND a East Creek ND2 West Creek GW-3 NDa EC (S'0 12-26-07 EWW-8622 107 +/- 97
<176 For those isotopes where both an activity and an MDA value are given, the MDA value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample ) and the activity is presented for information only. For isotopes where an activity value is given, but no MDA value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
a.ND" = No data; no flow.
cc: K. Johansen Ellen Saar APPROVED BY
Environmental, Inc.
Midwest Laboratory n Aflghy"tehnologie Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-782 DATE:
09/24/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/17/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD S-3 EXW-5914 09/05/07 299 96
< 165 GW-1 1 EXWW-6038 08/27/07 248 1 102
< 185 GW-12 EXWW-6039 08/29/07 93 +/- 96
< 185 GW-13 EXWW-6040 08/29/07 70 +/- 95
<185 GW-13 (duplicate)
EXWW-6041 08/29/07 136 +/- 98
< 185 GW-14 EXWW-6042 08/11/07 189 +/- 100
< 185 GW-15 EXWW-6043 09/04/07 224 +/- 101
< 185 GW-16 EXWW-6044 09104/07 15 +/- 92
< 185 2Z-361 B EXWW-6177 03/10/07 4207 +/- 213
< 189 2Z-361B (Duplicate)
EXWW-6178 03/10/07 4205 +/-213
< 189 2Z-361A EXWW-6179 03/10/07
-20
+/- 93
< 189 1Z-361A EXWW-6180 03/10/07 1019 +/- 133
< 189 1 Z-361 B EXWW-6181 05/07/07 168 +/- 101
< 188 2Z-361B EXWW-6182 06/26/07 2678 +/- 177
< 186 1Z-361A EXWW-6183 06/26/07 1381 +/- 143
< 186 2Z-361A EXWW-6184 07/27/07 47 +/- 94
< 185 1Z-361B EXWW-6185 07/27/07 183 +/- 100
< 185 Fagade, Subsoil Sump EXWW-6192 09/01/07 529 +/- 105
< 165 The error given is the probable counting error at the 95% confidence level.
Less than (<) valies are based on a 4.66 sigma counting error for the background sample.
SA Coorlim Quality Assurance
Environmental,*Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (047) 564-0700 - fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-798 Point Beach Nuclear Plant DATE:
12-26-2007 6610 Nuclear Road SAMPLES RECEIVED:
12-10-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in two water samples.
Sample Description Faqade Well U-1(Z-361A)
U-i (Z-361B)
Collection Date 09-24-07 09-24-07 Lab Code EXW-8267 EXW-8268 Isotope Concentration LLD (pCi/L)
H-3 1,525+/-144/<190 223 +/- 107/<190 The error given is the probable counting error at 95% confidence level and counting error for the background sample.
LLD values are based on 4.66.sigma APPROVED BY
Environmental, Inc.
Midwest Laboratory an AAleghiny Technologies Co.
700 Landwert Road - Northbrook, L 60062-2310 ph. 1847) 564-0700. lax (847) 564-4517 Dr. Kielt A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-799 Point Beach Nuclear Plant DATE:
01-07-2008 6610 Nuclear Road SAMPLES RECEIVED:
12-17-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in two water samples.
Sample Description Ground Water 2Z-361A 2Z-361B 2Z-361B Collection Date 12-11-07 12-11-07 12-11-07 Lab Code EXW-8377 EXW-8378 EXW-8379a Isotope Concentration / LLD (pCi/L)
H-3 77+/-94/<173 296 +/-103/ < 173 407 +/-107/ < 1.73 Denotes a duplicate.
The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
cere Bro iaS.
Labo ato M ager APPROVED BY I
Tony Coorlim, Quality Assurance
2 Environmental, Inc.
Midwest Laboratory an tluieny Tcnowlooes Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-776 DATE:
09/0712007 Point Beach Nuclear Plant SAMPLES RECEIVED:
08/14/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD Fagade Subsoil Sump Composite EXW-5147 07/03/07 708 +/- 127
< 189 S-1, Beach Drain EXW-5296 08109107 246 t 91
< 152 S-3, Beach Drain EXVW-5297 08/09(07 358 +/- 96
< 152 The error given is the probable counting error at the 95% confidence level.
Less than (<) values are based on a 4.66 sigma counting error for the background sample.
SA Coorlim Quality Assurance
-41 E
i qpýýb borl o Manager QL I
- Environmental, Inc.
Midwest Laboratory an Ailger~y Ttchnolc~gies Cm.
Dr, Kjell Johansen LABORATORY REPORT NO.:
8006-100-780 DATE:
09/11/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
08/20/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD Faqade Subsoil Sump EXW-5581 08/10/07 519 +/- 120
< 188 Fagade Subsoil Sump EXW-5615 06/08/07 491 +/- 120
< 190 The error given is the probable counting error at the 95% confidence level.
Less than (<) values are based on a 4.66 sigma counting error for the background sample.
SA Coorlim Quality Assurance
Environmental, Inc.
Midwest Laboratory.
an AA-nghvcy Th hnclogio Cý Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-782 DATE:
09124/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
09/17/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD S-3 EXW-5914 09/05/07 299 - 96
< 165 GW-1 1 EXWW-6038 08/27/07 248 +/- 102
< 185 GW-12 EXWW-6039 08/29107 93 +/- 96
< 185 GW-13 EXWW-6040 08/29/07 70 +/- 95
< 185 GW-13 (duplicate)
EXWW-6041 08/29/07 136 +/- 98
< 185 GW-14 EXWW-6042 08/11/07 189 -t 100
< i85 GW-15 EXWW-6043 09/04/07 224 +/- 101
<185 GW-16 EXWW-6044 09/04/07 15 +/- 92
< 185 2Z-361B EXWW-6177 03/10/07 4207 +/-213
< 189 2Z-361B (Duplicate)
EXWW-6178 03/10/07 4205 +/- 213
< 189 2Z-361A EXWW-6179 03/10/07
-20+/- 93
< 189 1Z-361A EXWW-6180 03/10/07
.1019 +/- 133
< 189 1Z-361B EXWW-6181 05/07/07 168 +/- 101
< 188 2Z-361B EXWW-6182 06/26/07 2678 +/- 177
< 186 IZ-361A EXWW-6183 06/26/07 1381 +/- 143
< 186 2Z-361A EXWW-6184 07/27/07 47 +/- 94
< 185 1 Z-361B EXWW-6185 07/27/07 183 +/- 100
< 185 Fa.ade, Subsoil Sump EXWW-6192 09/01/07 529 + 105
< 165 The error given is the probable counting error at the 95% confidence level.
Less than (<) val es are based on a 4.66 sigma counting error for the background sample.
SA Coodim Quality Assurance
K Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road - No-hVbroot, IL 60062-2310 ph (847) 564-0700
- fax (847) 564-4517 Dr. Kjelt A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-790 Point Beach Nuclear Plant DATE:
11-06-2007 6610 Nuclear Road SAMPLES RECEIVED:
10-18-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritium in one water sample.
Sample Description Fagade Subsoil Sump Composite Collection Date 10-1 1-07 Lab Code EXW-7297 Isotope Concentration / LLD (pCi/L)
H-3 288 109
< 189 The error given is the probable counting error at 95% confidence counting error for the background sample.
g level and LLD values are based on 4.66 sigma Sincerely, Bronia Gr'ob.'k S.
Laboratory Manager If I
APPROVED BY Tony Coorlim, Quality Assurance
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road - Northbrook, It. 60062-2310 ph. (847) 564-0700. fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-794 Point Beach Nuclear Plant DATE:
12-10-2007 6610 Nuclear Road SAMPLES RECEIVED:'
11-21-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below are the results of the analyses for tritiunri in one water sample.
Sample Description Facade Subsoil Sump Composite Collection Date 11-07-07 Lab Code EXW-7943 Isotope Concentration I LLD (pCiIL)
H-3 363 108
< 183 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting~error for the background sample.
'by
~
i-APPROVED BY Tony Coorlim, Quality Assurance
I Environmental, Inc.
Midwest Laboratory anAllegheny Tedhngogoes Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 Dr. Kjell A. Johansen Sr. Chemist-Environmental LABORATORY REPORT NO.:
8006-100-800 Point, Beach Nuclear Plant DATE:
01-07-2008 6610 Nuclear Road SAMPLES RECEIVED:
12-17-2007 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:
Below is the result of the analysis for tritium in one water sample.
Sample Description Fagade Subsoil Surmp Composite
- Collection Date 12-07-07 Lab Code EXW-8386 Isotope Concentration I LLD (pCi/L)
H-3 489+/- 110/< 173 The error given is the probable counting error at 95% confidence level and LLD values are based on 4.66 sigma counting error for the background sample.
Sincerely, APPROVED BY Quality Assurance
Environmental, Inc.
Midwest Laboratory a
l lJIqghwy Te.hologleS Co.
Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100-768 DATE:
06/19/2007 Point Beach Nuclear Plant SAMPLES RECEIVED:
06/11/2007 6610 Nuclear Road PURCHASE ORDER NO.:
Two Rivers, Wisconsin 54241 Sample ID Lab Code Collection Date H-3 (pCi/L)
LLD SSD-U1, SW Facade EXW-3476 05/24/07 317 +/- 98
< 169 SSD-U2, NW Facade EXW-3477 05/24/07 351 +/- 99
< 169 Duplicate,- EXW-3477 EXW-3478 05/24/07 405 +/- 101
<169 SSD-NSB-2 EXW-3479 05/24/07 221.+/- 94
< 169 SSD-LIN EXW-3480 05/25/07 213 +/- 93
< 169 SSD-F5-1 EXW-3481 05125/07 309 +/- 97
< 169 SSD-A12.1 EXW-3482 05/25/07 809 +/- 116
< 169 SSD-E-9.5 (Door 19)
EXW-3483 05125/07 411 +/- 102
< 169 SSD-EF-01 EXW-3484 '
05/25/07 1501 +/- 140
< 181 SSD-F13.1 EXW-3485 05/25/07 451 +/- 111
< 181 SSD-E13.1 EXW-3486 05/25/07 558 +/- 114
< 181 SSD-F6 EXW-3487 05/25/07 242 +/- 104
< 181 SSD-F7 EXW-3488 05/25/07 382 +/- 109
< 181 SSD-F9.9 EXW-3489 05/25/07 363 +/- 108
< 181 SSD-F8 EXW-3490 05/25/07 432 +/- 110.
< 181 SSD-B6.1 EXW-3491 05/25/07 317 +/- 98
<-169 MH-01 EXW-3492 05/24/07 157 +/- 101
< 181, MH-03 EXW-3493 05/24/07 145 +/- 100
<181 MH-04 EXW-3494 05/24/07 52 +/- 86
< 169 MH-05 EXW-3495 05/24/07 150 +/- 101
< 181 MH-02 EXW-3496 05/25/07 148 +/- 101
< 181 MH-09 EXW-3497 05/24/07 127 +/- 100
< 181 MH-10 EXW-3498 05/24/07 279 +/- 105
< 181 Duplicate, EXW-3498 EXW-3499 05124107 304 +/- 106
< 181 MH-14 EXW-3500 05/24/07 121 +/- 100
< 181 MH-19 EXW-3501 05/24/07 165 +/- 91
< 169 The error given is the probable counting error at the 95% confidence level.
Less than (<) v lues based on a 4.66 sigmacounting error for the background sample.
S A Coorlirn Grob Manager Quality Assurance
Environmental, Inc.
Midwest Laboratory I"
an Allegheny Technologie Co.
700 Landwej., Road - Nodhbrook, IL 60D62-2310 ph. (847) S64-0700
- fax (847) 5644517 Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100 -777 Point Beach Nuclear Plant DATE:
08-13-07 6610 Nuclear Road SAMPLES RECEIVED:
06-11-07 Two Rivers, Wisconsin 54241 Well Water, analyses for iron-55, strontium-89, strontium-90 and gamma emitting isotopes.
Lab Code EXW-3484 Date Collected 05-25-07 Location,.
SSD-EF-01 Isotope Activity/ MDC (pCi/L)
-156 +/- 459
< 768' Sr-89
-0.15 :l: 0.66 c 0.68 Sr-90 0.22 +/- 0.28
< 0.55 The error given is the probable counting. error at the 95% confidence level. The less than value (<) is based on a 4.66 sigma counting error for the background sample.
Gamma Be-7 Mn-54 Co-58 Co-60 Fe-59 Zn-65 Zr-Nb-95 Ru-103 Cs-134 Cs-137 Ba-La-140
-12.51 - 12.83 0.89 +/- 1.68 1.12 + 1.53 1.68 +/- 1.67 3.12 +/- 3.84
-0.14 +/- 3.29 0.69 +/- 1.29
-1.52 +/- 1.62
-0.69 +/- 1.40 2.02 +/- 1.78 2.59 + 1.80
- 26.69
< 2.68
- 3.44
- 2.81
< 4.61
- 3.32
- 3.28
- 4.12
- 2.59
- 3.36
- 5.64
- For those isotopes where both an activity and an MDC value are given, the MDC value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample) and the activity is presented for information only. For isotopes where an activity is given, but no MDC value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
[incerely, Approved:
I2
.'/I rob an
- e uSA Csurance L=
~or kato ej Quality Assurance
Environmental, Inc.
Midwest Laboratory an Ail=ghe*fy TeChnOlogqit Co.
700 L*ndWehr Road : Northbrook, IL 60062-2310 ph. (8471 564-0700
- fax (817) 564-4517 Dr. Kjell Johansen LABORATORY REPORT NO.:
8006-100 -778 Point Beach Nuclear Plant DATE:
08-13-07 6610 Nuclear Road SAMPLES RECEIVED:
06-11-07 Two Rivers, Wisconsin 54241 Ground Water, analyses for gamma emitting isotopes on solid portions.
Lab Code EXW-3491 Date Collected 05-25-07 Location SSD-B6.1 Isotope Activity / MDC (pCi/gdry)
Gamma Be-7 0.177 +/- 0.308
<" 0.878 K-40 5.436 +/- 1.102 Mn-54 0.011 +/- 0.034
< 0.047 Co-58 0.014 +/- 0.030
< 0.068 Co-60 0.259 +/- 0.052 Fe-59
-0.074 +/- 0.066
< 0.121 Zn-65
-0.036 +/- 0.064
< 0.112 Zr-Nb-95
-0.007 +/- 0.034
< 0.077 Ru-103
-0.012 +/- 0.030
< 0.070 Cs-134 0.0-16 +/- 0.037
< 0.066 Cs-137 1.751 +/- 0.146 Ba-La-140
-0.003 +/- 0.032
< 0.242 Bi-212 1.250 +/- 0.573 Bi-214 0.287 +/- 0.147 Pb-212 0.686 +/- 0.104 Pb-214 0.435 +/- 0.154 Ra-226 0.966 +/- 0.657
< 1.219 Ac-228 1.162 +/- 0.301 TFor those isotopes where both an activity and an MDC value are given, the MDC value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample) and the activity is presented for information *only. For isotopes where an activity is given, but no MDC value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.
Approved.
SA Coorlim Quality Assurance Grol\\
bo~aIty M aýIager\\
K Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road ' Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 Dr. Kjell Johansen FPL Energy,
LABORATORY REPORT NO.:
8006-100-821 Point Beach Nuclear Plant DATE:
05-02-2008 6610 Nuclear Road SAMPLES RECEIVED:
03-18-2008 Two Rivei-s, Wisconsin 54241 PURCHASE ORDER NO.:'
Below are the results of the analyses for tritium in two ground water 'amples.
Sample Lab Concentration / LLD (pCi/L)
Collection Description Code H-3 Date GW-09 (1Z-361A)
EXWW-1111 1,356 +/-+134 / < 175 12-13-07 GW-09 (1Z-361B)
EXWW-1112 194 93 / < 175 -
12-13-07 The error given is the probable counting error at the 95%
4.66 sigma counting error for the background sample.
E-mail: Kjell Johansen@fpl.com confidence level. The less than (<) value, is based on Si APPROVED BY 11
APPENDIX 3 University of Waterloo (Ontario)
Environmental Isotope Laboratory Precipitation Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 2007
Client: Johansen Nuclear Management Company ISO# 2007427 Location: T-1 1 for 3H Environmental Isotope Lab 2007-07-20 1 of 1 Sample Lab#
3H Result IRepeat E-02 6/6107 Rainwater 156599 X 11.6 +/-8 15.7+/-8 Tritium is reported in Tritium Units.
1TU = 3.221 Picocuries/L per IAEA, 2000 Report 1TU = 0.11919 Becquerels/L per IAEA, 2000 Report To Contact EIL:
mepatton@uwaterloo.ca or phbne:
5198884732 Robert J. Drimmie Laboratory Manager rdrimmie@uwaterloo.ca 519 888 4567 ext 32580
Client: Johansen Point Beach Nuclear Plant ISO# 2007575 Location: T - 1 Environmental Isotope Lab August 22, 2007 1 of 1
- Sample Lab#.
3H Result Repeat 1 E-0 2 (SBCC Rain Water) 08/09/07 16 0 7 3 6 1X
<6.0 +/- 8.0 500ml bottle Tritium is reported in Tritium Units.
1TU = 3.221 Picocuries/L per IAEA, 2000 Report.
1TU = 0.11919 Becquerels/L per IAEA, 2000 Report.
To Contact EIL:
mepatton@uwaterloo.ca
.or phone:
519 888 4732 Robert J. Drimmie Laboratory Manager rdrirnmie@uwaterloo.ca 519 888 4567 ext 32580
-i-I----.-
Client: Johansen Point Beach Nuclear Plant ISO# 2007632 Location: T 9-1 for 3H Environmental Isotope Lab 10/12/2007 1 of 1
- 1Sample 1Lab#
3H Result I 1a Repeat +/- lo 1 E-02 (SBCC Rain Water) 9-5-07 0805 162124 X 9.0 8.0 9.5 8.0 Tritium is reported in Tritium Units.
1TU = 3.221 Picocuries/L per IAEA, 2000 Report.
1TU = 0.11919 Becquerels/L per IAEA, 2000 Report.
To Contact E)L:
mepatton@uwaterloo.ca or phone:
519 888 4732 Robert J. Drimmie Laboratory Manager rdrimmie@uwaterloo.ca 519 888 4567 ext 32580
Client: Johansen FPL Energy Point Beach Nuclear Plant ISO# 2007735 Location: T - 2 Environmental Isotope Lab 07/11/2007 1 of 1 Sample Lab#
3H Result j+/- 1orRepeal 1+ lo 1 E-02 (SBCC Rain Water) 10/03/07 164532 X 17.4 8.0 Tritium is reported in Tritium Units.
1TU = 3.221 Picocuries/L per IAEA, 2000 Report.
1TU = 0.11919 Becquerels/L per IAEA, 2000 Report.
To Contact EIL:
mepattonf@uw/aterIoo.ca or phone:
519 888 4732 Robert J. Drimmie Laboratory Manager rdrimmie@uwaterloo.ca 519 888 4567 ext 32580
Client: Johansen FPL Energy Point Beach Nuclear Plant
.ISO# 2007751 Location: T - 14 1 for 3H.
Environmental Isotope Lab 07/11/2007 1 of 1
- Sample Lab#
3H Resultj +/- la Repeat +/- la 1 E-02 (SBCC Rain Water) 0850 10/18/07 164965 X 13.9 8.0 Tritium is reported in Tritium Units.
1TU - 3.221 Picocuries/L per IAEA, 2000 Report.
1TU 0.11919 Becquerels/L per IAEA, 2000 Report.
rnepatoii(.1,uWait Ito.Co or phone:
519 88 4732 Robert J. Drimrne Lacratzr'
",.Mam*::
rdrimmie@uwaterloo.ca
,19 888 4567 ext 32580