NRC 2016-0020, Transmittal of 2015 Annual Monitoring Report
| ML16118A349 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/28/2016 |
| From: | Woyak B Point Beach |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2016-0020 | |
| Download: ML16118A349 (164) | |
Text
{{#Wiki_filter:NEXTera ENERGY ~ POINT BEACH April28, 2016 NRC 2016-0020 10 CFR 72.44 TS 5.6.2 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 2015 Annual Monitoring Report In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31 , 2015. The Annual Monitoring Report contains information relating to the effluent impact upon the public, as well as information relating to plant releases, solid waste shipments, results from the radiological environmental monitoring program, the groundwater protection program, and miscellaneous monitoring activities which occurred in 2015. 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. The contracted laboratory's final Radiological Environmental Monitoring Program results (Appendix 1) is included. This letter contains no new regulatory commitments and no revisions to existing regulatory commitments. Very truly yours, NextEra Energy Point Beach, LLC Enclosures cc: Administrator, Region Ill, 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 Office of Nuclear Material Safety and Safeguards, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road , Two Rivers, WI 54241
ENCLOSURE 1 ANNUAL MONITORING REPORT 2015 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2), 72-005 (ISFSI) RENEWED LICENSES DPR-24 and DPR-27 January 1, 2015 through December 31, 2015
TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 3 2.0 Radioactive Liquid Releases 4 3.0 Radioactive Airborne Releases 10 4.0 Radioactive Solid Waste Shipments 16 5.0 Nonradioactive Chemical Releases 18 6.0 Circulating Water System Operation 19 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 20 Part C: Radiological Environmental Monitoring 8.0 Introduction 21 9.0 Program Description 22 10.0 Results 34 11.0 Discussion 39 12.0 REMP Conclusion 54 Part D: Groundwater Monitoring 13.0 Program Description 55 14.0 Results and Discussion 58 15.0 Groundwater Summary 63 Appendix 1: Environmental, Inc. Midwest Laboratory, Final Report for Point Beach Nuclear Plant ii
LIST OF TABLES Table 2-1 Comparison of 2015 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 4 Table 2-2 Summary of Circulating Water Discharge 6 Table 2-3 Isotopic Composition of Circulating Water Discharges 7 Table 2-4 Subsoil System Drains - Tritium Summary 8 Table 3-1 Comparison of 2015 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 13 Table 3-2 Radioactive Airborne Effluent Release Summary 13 Table 3-3 Isotopic Composition of Airborne Releases 14 Table 3-4 Comparison of Airborne Effluent Doses 15 Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2015 16 Table 4-2 2015 PBNP Radioactive Waste Shipments 16 Table 4-3 2015 Estimated Solid Waste Major Radionuclide Composition 17 Table 6-1 Circulating Water System Operation for 2015 19 Table 9-1 PBNP REMP Sample Analysis and Frequency 25 Table 9-2 PBNP REMP Sampling Locations 26 Table 9-3 ISFSI Sampling Sites 30 Table 9-4 Minimum Acceptable Sample Size 30 Table 9-5 Deviations from Scheduled Sampling and Frequency During 2015 31 Table 9-6 Sample Collection for the State of Wisconsin 31 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2015 36/37 Table 10-2 Feed Crops Grown on Point Beach Land 38 Table 10-3 Average ISFSI Fence TLD Results for 2015 38 Table 11-1 Average Indicator TLD Results from 1993-2015 39 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 40 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 41 Table 11-4 Average Gross Beta Measurements in Air 44 Table 14-1 Intermittent Streams and Bogs 58 Table 14-2 2015 Beach Drain Tritium 59 Table 14-3 2015 East Yard Area Manhole Tritium (pCi/L) 60 Table 14-4 2015 Façade Well Water Tritium (pCi/L) 61 Table 14-5 2015 Unit 2 Façade SSD Sump H-3 (pCi/L) 61 Table 14-6 2015 Quarterly Monitoring Well Tritium (pCi/L) 62 Table 14-7 2015 Potable Well Water Tritium Concentration (pCi/L) 63 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 27 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29 Figure 11-1 ISFSI Area TLD Results (1995 - 2015) 41 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 42 Figure 11-3 Sr-90 Concentration in Milk (1997 - 2015) 43 Figure 11-4 Annual Average Air Gross (1993 - 2015) 44 Figure 11-5 2015 Airborne Gross Beta 44 Figure 11-6 E-01 Results 1971 - 2015 51 Figure 11-7 Comparison of E-03 and E-20 Results 1971 - 2015 52 Figure 11-8 Comparison of E-01, E-02, E-03, and E-04 Results 1992 - 2015 52 iii
Figure 11-9 E-03, E-31, and Background Site E-20 Results 1992 - 2015 53 Figure 13-1 Groundwater Monitoring Locations 57 iv
SUMMARY
The Annual Monitoring Report for the period from January 1, 2015, through December 31, 2015, 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, non-radioactive chemical releases, and circulating water system operation. During 2015, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways: Liquid Atmospheric Tritium (Ci) 866 80.1 1 Particulate (Ci) 0.0516 0.0000689 Noble Gas (Ci) (-) 0.826 C-142 0.0197 11.75 (-)Noble gases in the liquids are added to the atmospheric release totals. 1 Atmospheric particulate includes radioiodine (I-131 - I-133). 2 Liquid is measured, atmospheric is calculated. 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) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I. LIQUID RELEASES Dose Category Calculated Dose Appendix I Dose Whole body dose 0.00684 mrem 6 mrem Organ dose 0.00684 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose Particulate organ dose 0.0315 mrem 30 mrem Noble gas beta air dose 0.0000996 mrad 40 mrad Noble gas gamma ray air dose 0.000274 mrad 20 mrad Noble gas dose to the skin 0.000349 mrem 30 mrem Noble gas dose to the whole body 0.00234 mrem 10 mrem 1
The results show that during 2015, the doses from PBNP effluents were a small percentage (0.12%) of the Appendix I design objectives. Therefore, operation of the PBNP radwaste treatment system continues to be ALARA. 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. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of the remaining ten sectors over land containing identifies any changes in the closest garden, occupied dwelling, and dairy in each sector. The 2014 LUC results confirmed the assumption that, for the purpose of calculating effluent doses, the maximally exposed person lives at the south boundary remains conservative. There is no change in that assumption for 2015. The 2015 Radiological Environmental Monitoring Program (REMP) collected 771 individual samples for radiological analyses. Quarterly composites of weekly air particulate filters generated an additional 24 samples and quarterly composites of monthly lake water samples resulted in a further 16 samples. Finally, 10 crop samples grown on the site were analyzed. This yields a total of 821 samples. The ambient radiation measurements in the vicinity of PBNP and the ISFSI was conducted using 146 sets of thermoluminescent dosimeters (TLDs). Air monitoring from six different sites did not reveal any effect from Point Beach effluents. 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. No new dry storage units added to the ISFSI in 2015. The total number remains at 39 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 23 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 2015 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment. One-hundred-fifty-two (152) samples were analyzed for H-3 as part of the groundwater protection program (GWPP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, and surface water on site. Also included in this number were a sump associated with the subsurface drainage system (SSD) located under the plant foundation, and four groundwater containment integrity monitoring wells located in the facades. The results show no substantial change in H-3 from previous years. Low levels of tritium continue under the plant foundation. No drinking water wells (depth >100 feet) have any detectable H-3. Tritium continues to be confined to the upper soil layer where the flow is toward the lake. Groundwater samples from wells in the vicinity of the remediated, former earthen retention pond continue to show low levels of H-3 whereas none was detectable in the wells monitoring the potential offsite tritium movement. Gamma scans of samples originating within the power block found no plant related gamma emitters. The results of GWPP monitoring indicate no significant change from previous years. 2
Part A EFFLUENT MONITORING
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 as low as reasonably achievable (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 licensees 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. 10 CFR 72.210 grants a general license for an Independent Spent Fuel Storage Installation (ISFSI) to all nuclear power reactor sites operating under 10 CFR 50. The annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable. However, any 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. 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. 3
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 /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 2015 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) 0.00684 0.114 % 20 (any organ) 0.00684 0.0342 % 2.2 2015 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 semi-annual and annual totals (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, the Unit 1 and 2 facade sumps and the subsurface drainage system sump. 2.3 2015 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. 4
The 2015 processed waste volume (Table 2-2) decreased about 20% from 2014 (8.76E+05 to 6.94E+05 gallons). Additionally, there was a concomitant decrease in the total isotopic curie distribution (gamma emitters plus hard-to-detects other that strontium) from 6.42E-02 Ci to 5.16E-02 Ci. In contrast, Sn-113/117m increased (from 3.11E-03 to 4.67E-03 Ci) whereas Sb-122/124/125 decreased (from 3.48E-03 Ci to 6.55E-04 Ci). Decreases also occurred in Co-58/60, Cr-51, Mn-54, Fe-55/59, and Zn-65 whereas Ni-63 increased. C-14 also had a small increase from 1.15E-02 to 1.97E-02 Ci in 2015. As in 2013 and 2014, no Sr-89 or Sr-90 was detected in liquids during 2015. H-3 increased from 796 to 866 Ci in 2015. Tritium continues to be the major radionuclide released via liquid discharges. 2.4 Beach Drain System Releases Tritium Summary Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of these outfalls carry yard and roof drain runoff to the beach. A seventh outfall drains a small portion of the grassy area on top of the bluff overlooking the lake. The quarterly results from the monthly beach drain samples are presented in Table 2-4. The total monthly flow is calculated assuming that the flow rate at the time of sampling persists for the whole month. In 2015, no tritium was observed at the effluent LLDs. No H-3 found in the beach drains is included in the effluent totals unless it can be shown to be the result of a spill or similar event. Because the source of beach drain H-3 has been determined to be recapture, including beach drain H-3 in the effluent totals would be double counting (NRC RIS 2008-03, Return/re-use of previously discharged radioactive effluents). The principle source of water for the beach drains is the yard drain system. Yard drain water sources are rain and snow melt. During the winter natural melting is the principle source. (In the past, runoff has been enhanced by the use of snow melting machines where the melt water is emptied into the yard drains. [See Section 14.2 for further discussion.] ) Additionally, various roof drains connect to the yard drain system. In addition to precipitation, the roof drains also carry condensate from various building AC units. A secondary source may be groundwater in leakage. This is evidenced by flow during periods of no precipitation. Because there are no external storage tanks or piping that carries radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne H-3 discharges via the yard drain system. Because of these various recapture sources, the beach drains also are sampled as part of the groundwater monitoring program. These results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report. 5
Table 2-2 Summary of Circulating Water Discharge January 1, 2015 through December 31, 2015 Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci) Gamma Scan(+HTDs)1 6.21E-04 7.02E-04 1.77E-03 2.53E-04 3.82E-03 5.72E-03 1.29E-02 1.40E-03 1.03E-03 4.81E-03 9.23E-03 8.18E-03 1.41E-02 5.16E-02 Gross Alpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium 0.00E+00 4.76E+00 9.71E+01 1.43E+01 3.45E+01 1.19E+02 2.70E+02 7.69E+01 7.76E+01 1.51E+02 5.59E+01 3.82E+01 1.97E+02 8.66E+02 Strontium (89/90/92) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Vol Released (gal) Processed Waste 0.00E+00 8.04E+03 4.05E+04 2.08E+04 3.12E+04 3.51E+04 1.36E+05 3.09E+04 4.02E+04 1.34E+05 1.28E+05 1.08E+05 1.17E+05 6.94E+05 Waste Water Effluent2 3.12E+06 2.57E+06 2.44E+06 2.56E+06 2.48E+06 2.47E+06 1.56E+07 2.77E+06 2.74E+06 3.06E+06 2.74E+06 2.91E+06 3.45E+06 3.33E+07 U1 SG Blowdown 2.76E+06 2.41E+06 2.68E+06 2.69E+06 3.16E+06 2.59E+06 1.63E+07 2.67E+06 2.57E+06 2.80E+06 2.68E+06 2.64E+06 2.96E+06 3.26E+07 U2 SG Blowdown 3.87E+06 1.63E+06 1.84E+06 1.75E+06 6.95E+05 1.75E+06 1.15E+07 1.77E+06 2.24E+06 2.45E+06 5.72E+05 4.31E+06 2.96E+06 2.58E+07 Total Gallons 9.75E+06 6.62E+06 7.00E+06 7.02E+06 6.37E+06 6.85E+06 4.36E+07 7.23E+06 7.59E+06 8.45E+06 6.12E+06 9.97E+06 9.49E+06 9.25E+07 Total cc 3.69E+10 2.51E+10 2.65E+10 2.66E+10 2.41E+10 2.59E+10 1.65E+11 2.74E+10 2.87E+10 3.20E+10 2.31E+10 3.77E+10 3.59E+10 3.50E+11 Dilution vol(cc)3 8.18E+13 7.39E+13 8.18E+13 1.18E+14 1.26E+14 1.22E+14 6.03E+14 1.26E+14 1.26E+14 1.22E+14 7.60E+13 1.18E+14 1.22E+14 1.29E+15 Avg diluted discharge conc (Ci/cc) Gamma Scan (+HTDs)1 7.59E-12 9.50E-12 2.17E-11 2.14E-12 3.04E-11 4.70E-11 1.11E-11 8.20E-12 3.95E-11 1.21E-10 6.96E-11 1.15E-10 Gross Alpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium 0.00E+00 6.44E-08 1.19E-06 2.15E-07 2.74E-07 9.79E-07 6.12E-07 6.17E-07 1.24E-06 7.35E-07 3.25E-07 1.61E-06 Strontium (89/90/92) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Max Batch Discharge Conc (Ci/cc) Tritium 0.00E+00 9.09E-06 3.23E-05 9.30E-06 2.03E-05 3.86E-05 3.61E-05 3.25E-05 3.92E-05 2.34E-05 1.55E-05 4.06E-05 Gamma Scan 7.59E-12 1.46E-11 1.22E-09 4.68E-11 2.93E-09 4.55E-10 5.08E-11 6.87E-11 1.77E-09 5.43E-09 2.76E-09 1.53E-09 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately. 2 The waste water effluent system replaced the Retention Pond which was taken out of service in September 2002. 3 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, 2015 through December 31, 2015 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 0.00E+00 4.76E+00 9.71E+01 1.43E+01 3.45E+01 1.19E+02 2.70E+02 7.69E+01 7.76E+01 1.51E+02 5.59E+01 3.82E+01 1.97E+02 8.66E+02 C-14 0.00E+00 0.00E+00 1.04E-04 0.00E+00 3.78E-04 4.65E-03 5.13E-03 1.00E-04 3.04E-04 3.86E-03 1.60E-04 3.46E-04 9.78E-03 1.97E-02 F-18 6.21E-04 6.95E-04 3.97E-04 1.54E-04 5.97E-04 2.22E-04 2.69E-03 1.20E-03 5.72E-04 5.32E-04 1.75E-04 4.73E-04 1.08E-03 6.71E-03 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.37E-03 1.45E-03 0.00E+00 3.82E-03 Mn-54 0.00E+00 0.00E+00 9.92E-06 0.00E+00 5.26E-06 3.16E-06 1.83E-05 0.00E+00 1.84E-06 0.00E+00 8.79E-05 6.34E-05 2.47E-06 1.74E-04 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-04 0.00E+00 1.18E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-04 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.55E-05 0.00E+00 0.00E+00 1.55E-05 Co-57 0.00E+00 0.00E+00 3.61E-06 0.00E+00 1.47E-05 4.20E-06 2.25E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-05 Co-58 0.00E+00 3.90E-06 6.03E-04 5.94E-06 1.83E-03 4.32E-04 2.87E-03 2.07E-05 1.98E-05 1.13E-05 2.28E-03 2.06E-03 1.80E-03 9.06E-03 Co-60 0.00E+00 3.71E-06 4.15E-04 4.53E-06 2.94E-04 2.26E-04 9.43E-04 5.03E-05 9.35E-05 3.00E-04 1.44E-03 8.87E-04 3.38E-04 4.05E-03 Ni-63 0.00E+00 0.00E+00 8.28E-05 2.13E-05 4.02E-04 1.17E-04 6.23E-04 1.75E-05 2.13E-05 0.00E+00 6.78E-05 6.11E-05 8.44E-05 8.75E-04 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.48E-05 0.00E+00 0.00E+00 1.48E-05 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.74E-05 0.00E+00 2.74E-05 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 0.00E+00 0.00E+00 2.13E-05 0.00E+00 0.00E+00 0.00E+00 2.13E-05 0.00E+00 0.00E+00 0.00E+00 5.23E-04 4.03E-04 2.67E-05 9.74E-04 Nb-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.66E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-07 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.27E-04 2.25E-04 4.87E-06 5.57E-04 Tc-99 0.00E+00 0.00E+00 1.04E-05 1.26E-05 6.73E-06 0.00E+00 2.98E-05 4.56E-06 1.49E-05 4.11E-05 0.00E+00 0.00E+00 6.22E-06 9.66E-05 Ag-110m 0.00E+00 0.00E+00 0.00E+00 5.44E-05 5.40E-05 2.11E-06 1.11E-04 3.15E-06 0.00E+00 0.00E+00 2.20E-05 2.25E-06 0.00E+00 1.38E-04 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-117m 0.00E+00 0.00E+00 1.27E-04 0.00E+00 3.18E-05 3.24E-05 1.91E-04 7.55E-06 3.79E-06 2.07E-06 1.66E-03 2.07E-03 7.33E-04 4.67E-03 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.02E-05 5.84E-06 2.61E-05 0.00E+00 0.00E+00 0.00E+00 4.52E-05 1.11E-04 1.99E-04 3.80E-04 Sb-125 3.80E-05 0.00E+00 0.00E+00 0.00E+00 6.79E-05 1.94E-05 1.25E-04 0.00E+00 0.00E+00 6.13E-05 3.09E-05 1.03E-06 5.68E-05 2.75E-04 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.59E-07 6.11E-06 1.79E-06 0.00E+00 8.87E-06 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries. "-" = no analysis 7
Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2015, through December 31, 2015 S-1 S-3 S-7 S-8 S-9 S-10 S-11 1st Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2nd Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 1.41E+06 2.49E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.35E+04 3rd Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 1.34E+05 4.46E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4th Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 4.40E+05 1.32E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.6 Land Application of Sewage Sludge and Wastewater In 1988, pursuant to 10 CFR 20.302(a), Point Beach received NRC approval for the disposal of sewage sludge, which may contain trace amounts of radionuclides, by land application on acreage within the site. Land application of sewage sludge is regulated by the Wisconsin Department of Natural Resources. Point Beach has not land applied sewage sludge for over a decade. Therefore, Point Beach has not renewed its WI DNR permit to dispose of sewage sludge in this manner. There were no sludge disposals by land application during 2015. All disposals were done at the Manitowoc Sewage Treatment Plant. 2.7 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors, but the amounts produced are less than C-14 produced by weapons testing or that occur naturally. Based on information from the NRC obtained at industry sponsored workshops, NextEra Point Beach began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 [RG 1.21], Rev 2 in June of 2009. Point Beach continues to analyze batch liquid waste discharges for C-14 and reporting the results in the Annual Monitoring Report. The NRC requested that all nuclear plants report C-14 emissions beginning with the 2010 monitoring reports. Pursuant to NRC guidance in RG 1.21(Rev 2), evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions. 8
However, as stated above, Point Beach began C-14 analyses and reporting prior to the issuance of RG 1.21 (Rev 2). RG 1.21 states that a radionuclide is a principal effluent component if it contributes greater than 1% of the Appendix I design objective dose compared to the other radionuclides in the effluent type, or, if it is greater than 1% of the activity of all radionuclides in the effluent type. In this case, C-14 is compared to other (non-tritium or noble gases) radionuclides discharged in liquids. For 2015, the monthly and total C-14 (1.97E-02 Ci) in liquid discharges are documented in Table 2-3. The amount of C-14 released makes up about 38% of the non-tritium radionuclides released in liquids. The liquid C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual (Table 2-1). Under the parameters and pathways used for the dose calculations, there is no C-14 dose contribution to the infant age group. For the remaining age groups, the C-14 contributes roughly 85% of the bone dose and 1.5 - 2.7% of the dose to the whole body and to other organs specified in RG 1.109. 9
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 maximum exposed individual (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, 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. C-14 is not included in the Appendix I calculations because it is not an Appendix I radionuclide. The C-14 dose calculation has been required since 2010 (see Sections 3.4 through 3.6, below, for a more detailed description) and is treated separately. The comparison between airborne effluent doses with and without C-14 is shown in Table 3-4. The highest Appendix I dose is the child age group for the liver, thyroid, kidney, lung, and GI-LLI at 3.15E-02 mrem. Had C-14 been included, the child-bone dose would have been the highest at 2.42E-01 mrem. 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 2015 is summarized in Table 3-2. The particulate total is slightly lower in 2015 than in 2014 (6.34E-05 Ci vs. 6.60E-05 Ci). H-3 increased slightly from 75.5 Ci to 80.1 Ci. Noble gases decreased from 1.44E+00 to 8.26E-01Ci. 3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2015, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections. As in 2014, in 2015 the outage impact of the isotopic mixture is demonstrated in the comparison of the October particulate releases. During October nine different particulates were identified in the airborne effluent whereas in the non-outage months, at most three were found. Most are released via the open hatch on the 66-foot elevation of containment. The convective flow through the open hatch during purge is unfiltered. Although the flow is into the façade, there are two circumferential gaps around the façade. It is assumed that the release into 10
façade is transferred to the outside and therefore is treated as a release to the environment. 3.4 Carbon-14 C-14 is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors as neutrons interact with the dissolved oxygen and nitrogen in the primary coolant. However, these amounts produced by nuclear reactors are much less that those produced by weapons testing or that occur naturally. The NRC has requested that nuclear plants report C-14 emissions. C-14 is a hard-to-detect radionuclide. It is not a gamma emitter and must be chemically separated from the effluent stream before it can be measured. Because nuclear plants currently are not equipped to perform this type of sampling, RG 1.21 allows for calculating C-14 discharges based on fission rates. The Electric Power Research Institute (EPRI) developed the methodology for calculating C-14 generation and releases for the nuclear industry. The results were published as Technical Report 1021106 (December 2010), Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." In addition to neutron flux, the percent oxygen and nitrogen in the VCTs is used in the C-14 calculation as both gases contribute to the generation of C-14. Pursuant to NRC guidance (Regulatory Guide 1.21, Rev 2, p. 16, June 2009), most of the C-14 emissions from nuclear plant occur in the gaseous phase. The Point Beach C-14 generation for 2015 was calculated using the EPRI guidance and the current core parameters resulting from the power uprate. The calculated amounts were 5.89 Ci for Unit 1 and 5.85 Ci for Unit 2 yielding a total of 11.75 Ci which is 0.11 Ci lower than 2014. It is noted that the nitrogen in the VCTs also was lower 2015 than in 2014. The 2015 calculated total 11.75 Ci is roughly 600 times higher than the 1.97E-02 Ci of C-14 determined by analyses of composites from liquid waste batch discharges, steam generator blowdown, and other waste streams. 3.5 C-14 Airborne Effluent Dose Calculation The dose from the airborne C-14 is dependent on its chemical form. The C-14 released to the atmosphere consists of both organic and inorganic species. Both the inorganic and organic C-14 contributes to the inhalation dose. Only the inorganic 14CO2 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH4, are not photosynthetically active. For PWRs such as PBNP most of the gaseous C-14 occurs as methane, 14CH4, not as carbon dioxide, 14CO2. The amount of 14CO2 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR sites similar to the PBNP design. The Ginna nuclear generating station is of similar design to PBNP. It is a Westinghouse 2-loop PWR of the same vintage as PBNP and approximately the same power (prior to the PBNP power uprate). 11
Measurements at Ginna for 18 months in 1980 - 1981 (Kunz, "Measurement of 14 C Production and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-14 was discharged as 14CO2. Therefore, 10% of the 11.75 Ci of the calculated C-14 for PBNP will be used in the ingestion dose calculations. C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 1.109. The inhalation dose was calculated using all of the C-14 calculated to be released. All the C-14 is used because whether the C-14 is in the form of 14CO2 or one of the organic forms, such as CH4, both would be inhaled and contribute to a lung dose. For the other existing pathways, milk, meat, and produce, the dose depends upon the amount incorporated into biomass consumed by cattle and people: forage for cattle and produce for humans. Incorporation only occurs via photosynthesis. Photosynthesis only incorporates 14CO2 and hence the use only of the 10% fraction of the total C-14 release for these pathways. The airborne effluent C-14 dose calculations were made as described above. They were made for the MEI as explained in Section 2.1. This approach utilizes all the pathways that are applicable to a hypothetical person residing at the site boundary. Because C-14 is present as a gas, the pathways are milk, meat, and produce (vegetables, fruit, and grain) and the Regulatory Guide 1.109, Table E-5 usage factors applied to the calculation. As such, the resulting dose will be conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-14 doses are calculated. Furthermore, because leafy vegetables are included in the produce pathway, they are not used as a separate pathway because that would result in double accounting for leafy vegetable dose contribution. Carbon-14 is not an Appendix I radionuclide. Therefore, airborne C-14 is not summed with the other airborne radioactive effluents for comparison of airborne effluent dose to the Appendix I dose objectives. However, the C-14 doses are presented and compared to the other radionuclide doses in Table 3-4. 3.6 C-14 Measurements No C-14 measurements were made of PBNP airborne effluents. In 2010, C-14 was measured in crops grown on fields in the owner controlled area located in the highest /Q sector at the site's south boundary. One field is leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans are grown by another farmer. These two crops were sampled in this sector and as well as in a background location about 17 miles SW of the plant. Based on the measurement error, there was no statistical difference between the results obtained on site in the highest /Q sector as compared to the background site some 17 miles away (2013 AMR, Table 10-3). These results demonstrated that the dose from C-14 in Point Beach airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants (1 mrem: NCRP Report 93, Ionizing Radiation Exposure of the Population of the United States, 1987, p.12). . 12
Table 3-1 Comparison of 2015 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 0.0315 mrem 0.105 Noble gas 40 mrad (beta air) 0.0000996 mrad 0.000249 Noble gas 20 mrad (gamma air) 0.000247 mrad 0.00124 Noble gas 30 mrem (skin) 0.000349 mrem 0.00116 Noble gas 10 mrem (whole body) 0.000234 mrem 0.00234 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2015, through December 31, 2015 Total Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) 0.00E+00 0.00E+00 7.65E-04 0.00E+00 4.01E-05 9.48E-04 1.75E-03 6.64E-04 1.54E-03 1.02E-02 3.81E-03 2.79E-03 1.25E-02 3.33E-02 Total Noble Gas (Ci)1 7.82E-02 1.15E-01 7.39E-02 5.76E-02 5.44E-02 6.34E-02 4.43E-01 6.32E-02 7.55E-02 7.59E-02 4.55E-02 4.58E-02 7.69E-02 8.26E-01 Total Radioiodines (Ci)2 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.61E-09 Total Particulate (Ci)3 7.10E-06 5.06E-07 2.92E-05 0.00E+00 0.00E+00 0.00E+00 3.68E-05 0.00E+00 0.00E+00 3.27E-06 2.46E-05 3.87E-06 3.79E-07 6.89E-05 Alpha (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium(Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 All other beta + gamma (Ci) 7.10E-06 5.06E-07 2.92E-05 0.00E+00 0.00E+00 0.00E+00 3.68E-05 0.00E+00 0.00E+00 3.27E-06 2.46E-05 3.87E-06 3.79E-07 6.89E-05 Total Tritium (Ci) 6.52E+00 6.92E+00 9.10E+00 6.96E+00 5.22E+00 6.37E+00 4.11E+01 4.77E+00 3.81E+00 3.64E+00 1.43E+01 5.58E+00 6.90E+00 8.01E+01 Max NG H'rly Rel.(Ci/sec) 1.85E-07 7.48E-08 7.07E-08 6.90E-08 7.63E-08 7.44E-08 7.57E-08 6.89E-08 7.71E-08 5.62E-08 4.82E-08 6.10E-08 1 Total noble gas (airborne + liquid releases) does not include F-18 which is not a noble gas. F-18 monthly and annual totals are presented in Table 3-3.. 2 Airborne radioiodines only include I-131 and I-133. Although for dose calculations iodines are grouped with particulates, for this reporting table they are separated from the particulate group. 3 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or C-14. C-14 was calculated for the year and no monthly values are available. 13
TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2015 through December 31, 2015 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 6.52E+00 6.92E+00 9.10E+00 6.96E+00 5.22E+00 6.37E+00 4.11E+01 4.77E+00 3.81E+00 3.64E+00 1.43E+01 5.58E+00 6.90E+00 8.01E+01 Ar-41 4.71E-02 4.34E-02 5.03E-02 4.65E-02 4.11E-02 4.81E-02 2.76E-01 4.77E-02 5.82E-02 5.52E-02 2.27E-02 3.75E-02 5.06E-02 5.48E-01 Kr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m 0.00E+00 4.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.49E-05 4.48E-04 Xe-133 3.10E-02 6.96E-02 2.35E-02 1.09E-02 1.32E-02 1.51E-02 1.63E-01 1.55E-02 1.70E-02 2.03E-02 2.25E-02 8.24E-03 2.60E-02 2.73E-01 Xe-133m 2.35E-05 9.46E-04 5.14E-05 0.00E+00 0.00E+00 0.00E+00 1.02E-03 0.00E+00 1.77E-05 9.67E-05 2.60E-04 0.00E+00 1.23E-04 1.52E-03 Xe-135 1.10E-04 1.13E-03 0.00E+00 2.21E-04 1.75E-04 1.71E-04 1.80E-03 0.00E+00 2.46E-04 3.21E-04 7.89E-05 2.95E-05 1.85E-04 2.66E-03 Xe-135m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 6.96E-06 0.00E+00 2.68E-05 0.00E+00 0.00E+00 0.00E+00 3.38E-05 0.00E+00 0.00E+00 3.27E-06 1.25E-06 3.86E-06 3.65E-07 4.25E-05 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.06E-06 0.00E+00 0.00E+00 1.06E-06 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 1.41E-07 5.04E-07 2.42E-06 0.00E+00 0.00E+00 0.00E+00 3.07E-06 0.00E+00 0.00E+00 0.00E+00 7.61E-07 3.53E-10 0.00E+00 3.83E-06 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-06 0.00E+00 0.00E+00 1.03E-06 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.36E-07 0.00E+00 0.00E+00 3.36E-07 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.60E-07 0.00E+00 0.00E+00 1.60E-07 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.61E-09 Sb-124 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 0.00E+00 1.49E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E-09 0.00E+00 0.00E+00 0.00E+00 1.49E-05 8.12E-09 1.01E-08 1.49E-05 Ni-63 0.00E+00 4.97E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.97E-10 0.00E+00 0.00E+00 0.00E+00 5.03E-06 2.74E-09 3.41E-09 5.04E-06 Tc-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-117m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Note: The Noble Gases listed above include the liquid contribution 14
Table 3-4 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2015 Appendix I (Airborne Particulate + Tritium) Dose (mrem) Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 1.93E-04 1.88E-02 1.88E-02 1.87E-02 1.87E-02 1.87E-02 1.88E-02 4.09E-05 Teen 2.58E-04 2.16E-02 2.16E-02 2.15E-02 2.16E-02 2.15E-02 2.16E-02 4.09E-05 Child 4.11E-04 3.15E-02 3.15E-02 3.15E-02 3.15E-02 3.15E-02 3.15E-02 4.09E-05 Infant 1.11E-04 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 4.09E-05 2015 Carbon-14 Dose (mrem) Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.66E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 0.00E+00 Teen 1.04E-01 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 0.00E+00 Child 2.41E-01 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 0.00E+00 Infant 1.23E-01 2.61E-02 2.61E-02 2.61E-02 2.61E-02 2.61E-02 2.61E-02 0.00E+00 2015 Total Airborne Non-Noble Gas Dose (Particulate + H-3 + C-14 (mrem) Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.68E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 4.09E-05 Teen 1.05E-01 4.24E-02 4.24E-02 4.23E-02 4.23E-02 4.23E-02 4.23E-02 4.09E-05 Child 2.42E-01 7.96E-02 7.97E-02 7.96E-02 7.96E-02 7.96E-02 7.96E-02 4.09E-05 Infant 1.23E-01 4.00E-02 4.00E-02 3.99E-02 4.00E-02 3.99E-02 4.00E-02 4.09E-05 Ann.Limit 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01
% Limit 8.06E-01 2.65E-01 2.65E-01 2.65E-01 2.65E-01 2.65E-01 1.36E-04 The percent of limit is calculated using the highest total dose, the Child Age Group.
15
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 2015. No Types C or D waste 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 in 2015 A. Spent resins, filter sludge, evaporator bottoms, etc. 2.4 m3 65.100 Ci 84.0 ft3 B. Dry compressible waste, contaminated equipment, etc 205.8 m3 0.212 Ci 7266.0 ft3 C. Irradiated components, control rods, etc. 0.00 m3 N/A Ci ft3 3 D. Other 0.0 m N/A Ci 3 Steam generators: Unit 1 removed 1984; Unit 2 removed 1996 0 ft 4.2 Solid Waste Disposition There were four solid waste shipments from PBNP during 2015. The dates and destinations are shown in Table 4-2. Table 4-2 2015 PBNP Radioactive Waste Shipments Date Destination 01/14/15 Oak Ridge, TN 06/09/15 Andrews, TX 06/17/15 Clive, Utah 10/21/15 Oak Ridge, TN 4.3 Major Nuclide Composition (by Type of Waste) The major radionuclide content of the 2015 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 4-3. Only those radionuclides with detectable activity are listed. 16
Table 4-3 2015 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B Percent Activity Percent Activity Nuclide Abundance (mCi) Nuclide Abundance (mCi) TOTAL 100 6.51E+04 TOTAL 100 2.11E+02 Ni-63 3.442E+01 2.24E+04 Co-60 3.861E+01 8.16E+01 Co-58 2.320E+01 1.15E+04 Fe-55 3.216E+01 6.79E+01 Co-60 1.598E+01 1.04E+04 Co-58 6.508E+00 1.37E+01 Be-7 8.467E+00 5.51E+04 Cr-51 4.743E+00 1.00E+01 Fe-55 6.807E+00 4.43E+03 Ni-63 3.626E+00 7.66E+00 Sb-125 3.688E+00 2.40E+03 Sb-125 2.619E+00 5.53E+00 Mn-54 2.797E+00 1.82E+03 Nb-95 2.073E+00 4.38E+00 Cs-137 2.136E+00 1.39E+03 Ru-106 1.247E+00 2.64E+00 Ni-59 4.287E-01 2.79E+02 Zr-95 1.132E+00 2.39E+00 Sb-124 3.596E-01 2.34E+02 Tc-99 1.131E+00 2.39E+00 Co-57 3.550E-01 2.31E+02 Sn-113 1.011E+00 2.14E+00 Ag-110m 3.304E-01 2.15E+02 Mn-54 1.006E+00 2.12E+00 Nb-95 2.366E-01 1.54E+02 Sb-124 7.820E-01 1.65E+00 C-14 2.136E-01 1.39E+02 Ni-59 7.370E-01 1.56E+00 Sn-113 2.013E-01 1.31E+02 Zn-65 4.180E-01 8.83E+02 H-3 1.613E-01 1.05E+02 Fe-59 3.450E-01 7.28E-01 Ce-144 8.744E-02 5.69E+01 H-3 3.280E-01 6.93E-01 Zr-95 7.115E-02 4.63E+01 Sn-117m 3.180E-01 6.71E-01 Sr-90 3.089E-02 2.01E+01 Pu-241 2.580E-01 5.45E-01 Sr-89 1.480E-02 9.63E+00 Ag-110m 2.140E-01 4.52E-01 Tc-99 4.180E-03 2.72E+00 Co-57 1.640E-01 3.46E-01 Pu-241 2.259E-03 1.05E+03 Ce-144 1.450E-01 3.06E-01 Am-241 1.388E-03 9.03E-01 Cs-137 1.150E-01 2.42E-01 Pu-238 5.025E-04 3.27E-01 Nb-94 8.600E-02 1.83E-01 Cm-243 3.580E-04 2.33E-01 Pu-238 8.500E-02 1.79E-01 Pu-239 3.150E-04 2.05E-01 Pu-239 6.300E-02 1.34E-01 Cm-242 7.207E-05 4.69E-02 Sr-90 4.100E-02 8.64E-02 Sr-89 1.300E-02 2.65E-02 Am-241 1.000E-02 2.21E-02 C-14 6.000E-03 1.17E-02 Cm-243 3.000E-03 7.20E-03 Pu-242 1.000E-03 2.13E-03 Cm-242 4.000E-04 8.98E-04 17
5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2015, to June 30, 2015, included 1.70E+04 gallons of neutralized wastewater. The wastewater contained 5.24E-01 lbs. of suspended solids and 1.05E+02 lbs. of dissolved solids. Scheduled chemical waste releases to the circulating water system from July 1, 2015, to December 31, 2015, included 1.08E+05 gallons of neutralized wastewater. The wastewater contained 1.57E+00 lbs. of suspended solids and 6.71E+02 lbs. 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, 2015, to June 30, 2015, included 2.09E+07 gallons of clarified effluent. The wastewater contained 2.26E+03 lbs. of suspended solids. Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2015, to December 31, 2015, included 1.75E+07 gallons of clarified effluent. The wastewater contained 3.26E+03 lbs. of suspended solids. Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2015, to June 30, 2015, included 4.27E+05 lbs. of sodium bisulfite solution (1.62E+05 lbs. sodium bisulfite), 4.48E+05 lbs. of Sodium Hypochlorite Solution (5.60E+04 lbs. sodium hypochlorite), and 4.15E+03 lbs. Acti-Brom 1338 (1.87E+03 lbs. sodium bromide). Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2015, to December 31, 2015, included 8.29E+05 lbs. of sodium bisulfite solution (3.15E+05 lbs. sodium bisulfite), 8.13E+05 lbs. Sodium Hypochlorite Solution (1.02E+05 lbs. sodium hypochlorite), 8.25E+03 lbs. Acti-Brom 1338 (3.71E+03 lbs. sodium bromide). 18
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 2015 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 358.2 358.2 358.2 527.3 542.5 542.5 Water Discharge [million gal/day]* 2 358.2 358.2 358.2 532.8 548.3 548.3 Average Cooling Water 1 37.3 42.2 40.2 44.5 47.5 53.8 Intake Temperature [F] 2 37.9 43.0 40.8 44.6 48.0 54.2 Average Cooling Water 1 69.6 69.6 72.2 64.6 66.1 72.6 Discharge Temperature [F] 2 69.0 69.3 70.8 62.8 65.1 71.2 Average Ambient Lake Temperature [F] 34.2 33.7 37.4 41.0 43.9 49.7 Table 6-1(continued) Circulating Water System Operation for 2015 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling* 1 542.5 542.5 542.5 563.1 504.8 520.0 Water Discharge [million gal/day]** 2 548.3 548.3 548.3 104.4 547.2 540.2 Average Cooling Water 1 54.2 56.5 55.7 55.3 44.5 41.0 Intake Temperature [F] 2 54.9 57.1 56.1 53.3 44.9 41.3 Average Cooling Water 1 72.8 75.6 74.9 75.2 63.7 59.9 Discharge Temperature [F] 2 71.7 73.7 72.2 56.3 61.4 58.8 Average Ambient Lake Temperature [F] 49.2 51.7 52.0 53.0 41.7 38.5
- For days with cooling water discharge flow.
**U1 outage circ water shut down 10/3/15 - 10/30/15 19
Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs Neither the ODCM, the RECM, nor the Environmental Manual (EM) were revised in 2015. 7.2 Interlaboratory Comparison Program ATI 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 2015. 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 attached final report for 2015, January - December 2015 from ATI Environmental Inc. 7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2015. 20
Part C RADIOLOGICAL ENVIRONMENTAL MONITORING
8.0 INTRODUCTION
The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To accomplish this, the REMP collects and analyzes air, water, milk, soil, vegetation (grasses, weeds, and crops), and fish samples for radionuclides and uses thermoluminescent dosimeters (TLDs) to determine the ambient radiation background. The analyses of the various environmental media provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure. 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. A subset of the PBNP REMP samples, consisting of air, soil and vegetation also fulfills 10 CFR 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. 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. 21
9.0 PROGRAM DESCRIPTION 9.1 Results Reporting 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 lower limit of detection (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. As mentioned above, radioactive decay is a statistical process which has an inherent uncertainty in the analytical result. No two measurements will yield exactly the same result. However, the results are considered equal if the results fall within a certain range based upon the statistical parameters involved in the process. The REMP analytical results are reported at the 95% confidence limit in which the true result may be two standard deviations above or below the reported result. This means that there is only a 5% chance of concluding that the identified radioactive atom is not there when it really is present in the sample. A false positive is an analytical result which statistically shows that the radionuclide is present in the sample when it really is not there. Typically, if the 95% 22
confidence interval for a positive does not include zero, the radionuclide is considered to be present. For example, the result is reported as 100 +/- 90. One hundred minus 90 yields a positive result and therefore may be considered to be present. However, this may be a false positive. If the radionuclide was not in the plant effluent, this result would fall into that category which 5% of the time it is falsely concluded that the radionuclide is present when in actuality it is not. This usually happens at low concentrations at or near the LLD where fluctuations in the background during the counting process skew the results to produce a positive result. 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 collects certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located. 23
9.5 Program Modifications In 2013, the placement of TLDs was reviewed with respect to the potential of trees and structures for interfering with the measurement of ambient radiation from natural background and of direct radiation from the plant and from airborne effluents. Two locations were found to have potential interferences. Two replacement TLD sites (E-16B and E-26B) were added in the 4th quarter of 2013. The new sites are in close proximity to E-16 and E-26 and were used concurrently with the old sites to provide data for comparisons between the old and new locations prior to deleting the old locations. These old sites were discontinued beginning in the second quarter of 2015. Based on the proximity of the new locations to the old locations, there was no need to revise the Environmental Manual maps. 24
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, -16B, -17,
-18, 20, -22, -23, -24,
-25, -26, -26B, -27, -28
-29, -30, 31, -32, -38,
-39,-41, -42,-43, -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-13 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, I-131 Gamma Isotopic Analysis Lake Water E-01, -05, -06, -33 Gross Beta, Sr-89/90, H-3 Monthly / Quarterly composite of monthly collections I-131 Monthly Gamma Isotopic Analysis Monthly Milk E-11, -40, -21 Sr-89, 90 Monthly I-131 Gamma Isotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)
-08, -20 I-131 Weekly (charcoal)
Gamma Isotopic Analysis Quarterly (on composite particulate filters) Soil E-01, -02, -03, -04, Gross Beta 2x/yr
-06, -08, -09, -20, Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, Gross Beta 2x/yr Gamma Isotopic Analysis ISFSI Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly 25
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 Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-11 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-15 Southwest Corner of Site E-16, 16B 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-18 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, -26B 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 nd rd E-28 TLD site on western most pole between the 2 and 3 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-41 NW corner of Woodside and Nuclear Rds (Kewaunee County) E-42 NW corner of Church and Division, East of Mishicot E-43 West side of Tannery Rd south of Elmwood (7th pole south of Elmwood) E-TC Transportation Control; Reserved for TLDs 26
Figure 9-1 PBNP REMP Sampling Sites 27
Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28
Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29
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 Soil 500-1000 grams Shoreline Sediment 500-1000 grams 30
Table 9-5 Deviations from Scheduled Sampling and Frequency During 2015 Sample Location Collection Reason for not conducting REMP Plans for Preventing Recurrence Type Date as required LW E-01, E-05, E-06, E-33 2/15/2015 Icy conditions at the shore prevented Nautral occurrence getting close enough to the lake to get a water sample. AP/I E-01 7/1/2015 No power to sampler Unknown cause Algae E-5, E-12 6/10/2015 No algae found growing in area Natural occurrence E-5 8/27/2015 E-5, E-12 10/7/2015 Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 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-11 Monthly E-21 Well Water E-10 Twice per year 31
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 2015. 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, I-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 the Annual Monitoring Report, are the naturally occurring radionuclides Ra-226, Bi-214, Pb-212, Tl-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 measurements are made on the solids remaining after evaporation of the unfiltered sample to dryness. Gamma isotopic analyses are performed using 1-liter liquid samples. Strontium is determined by chemical separation and beta counting. 9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours 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 cartridges for radioiodine are counted as soon as possible so the I-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for I-131 by 32
counting them all at the same time to achieve a lower LLD. If a positive result is obtained, each cartridge 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. No special vegetation samples were obtained for C-14 analyses in 2015. 9.7.6 Environmental Radiation Exposure The 2015 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 was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. An evaluation of the response difference between the two types of TLD in 2001 demonstrated that the TLD cards produced a 14% higher response than the LiF chips (2011 AMR, Table 9-7, p. 36). The reported field exposure is the arithmetic average of the measured exposure values at each location minus the exposure transportation control TLD (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. 33
9.7.7 ISFSI Ambient Radiation Exposure The ISFSI fence TLDs are part of the 10CFR72.44 monitoring and are not considered part of the REMP. However, 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. These results are used as part of the 40CFR190 compliance demonstration. 10.0 RESULTS 10.1 Summary of 2015 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2015, through December 31, 2015, 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, averages and high values, in Table 10-1 which contain 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 +/- its 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 tech spec required 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 listing of all the individual results obtained from the contracted analytical laboratory and the laboratorys radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in the Appendix. In Table 10-1 no results are reported as less than LLD (<LLD). All results are reported to Point Beach by the contracted radioanalytical laboratory "as measured" whether positive or negative (see Section 9-1). Based on these results, a radionuclide is considered detected if it meets the criterion that the measured value minus its 2 counting error is greater than zero (x-2 >0). An "ND" entry in Table 10-1 means that for this radionuclide the criterion was not satisfied for any of the measurements. If one analysis fulfilled the criterion, then all of the reported results, both positive and negative, were used in calculating the average shown in Table 10-1. 34
The method of determining averages based on "as measured" results follows the recommendations 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 520/1 012 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." In addition to the required radionuclides for each medium analyzed, Table 10-1 also has an additional radionuclide listed known to originate with nuclear power plants. This radionuclide is either Co-60, Ru-103, or any other radionuclide which has the lowest LLD based on the analytical parameters needed to meet the LLDs required for radionuclides specified for the medium being analyzed. The radionuclide is identified by parentheses. During the analyses for those radionuclides specifically required to be identified, naturally occurring radionuclides such as Ra-226, Be-7 and K-40 are detected in many samples. Their concentrations are presented in Table 10-1 for a comparison to those radionuclides for which specific analyses are required by the regulations. There are no regulatory required LLDs for naturally occurring radionuclides. Finally, Point Beach reports the results for soil analyses. There is no regulatory requirement for soil analyses in standard RETS (NUREG-0472 and NUREG-1301). Point Beach includes soil analyses in the REMP to be able to compare current results to the historical record. Additional sampling was initiated in 2015. Approximately 60% of the 1260 acres (FSAR 2.1) comprising the NextERA Point Beach site is licensed to farmers who use the land to grow various crops. These crops consist of corn, hay, alfalfa, and soy beans and appear to be for cattle feed. Ten samples were obtained from the nine separate plots and gamma scanned for radionuclides representative of Point Beach effluents and for naturally occurring radionuclides. Results are reported in Table 10-2. Table 10-3 contains the ISFSI fence TLD results. 35
Table 10-1 Summary of Radiological Environmental Monitoring Results for 2015 Average +/- 1 Std. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 126 1 mrem 1.18 +/- 0.20 1.66 +/- 0.06 mR/7days Control (E-20) 4 1 mrem 1.20 +/- 0.15 1.30 +/- 0.15 mR/7days Air Gross Beta 259 0.01 0.025 +/- 0.010 0.057 +/- 0.005 pCi/m3 Control (E-20) Gross beta 52 0.01 0.024 +/- 0.009 0.057 +/- 0.005 pCi/m3 I-131 259 0.030 (0.07) ND - pCi/m3 Control (E-20) I-131 52 0.030 (0.07) ND - pCi/m3 Cs-134 20 0.01(0.05) ND - pCi/m3 Control (E-20) Cs-134 4 0.01(0.05) ND - pCi/m3 Cs-137 20 0.01(0.06) 0.0000 +/- 0.0003 0.0007 +/- 0.0006 pCi/m3 Control (E-20) Cs-137 4 0.01(0.06) 0.0000 +/- 0.0003 0.0004 +/- 0.0003 pCi/m3 Other emitters (Co-60) 20 0.1 0.0000 +/- 0.0004 0.0006 +/- 0.0005 pCi/m3 Control (E-20) Other (Co-60) 4 0.1 ND ND pCi/m3 Natural Be-7 20 - 0.064 +/- 0.012 0.084 +/- 0.017 pCi/m3 Control (E-20) Natural Be-7 4 - 0.065 +/- 0.005 0.071 +/- 0.013 pCi/m3 Milk Sr-89 36 5 ND - pCi/L Sr-90 36 1 0.5 +/- 0.3 1.3 +/- 0.4 pCi/L I-131 36 0.5 ND - pCi/L Cs-134 36 5 (15) 0.0 +/- 0.8 2.1 +/- 1.7 pCi/L Cs-137 36 5 (18) 0.6 +/- 0.9 2.3 +/- 2.1 pCi/L Ba-La-140 36 5 (15) -0.8 +/- 1.9 2.7 +/- 1.2 pCi/L Other gamma emitters(Co-60) 36 15 0.4 +/- 1.1 3.0 +/- 1.9 pCi/L Natural K-40 36 - 1409 +/- 60 1496 +/- 106 pCi/L Well Water Gross beta 4 4 1.6 +/- 1.3 2.9 +/- 1.7 pCi/L H-3 4 200 (3000) 15.1 +/- 78.1 103.9 +/- 99.7 pCi/L Sr-89 4 5(10) ND - pCi/L Sr-90 4 1 (2) 0.2 +/- 0.5 0.9 +/- 0.3 pCi/L I-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 10(15) ND - pCi/L Co-60 4 10(15) ND - pCi/L Zn-65 4 30 ND - pCi/L Zr-Nb-95 4 15 ND - pCi/L Cs-134 4 10(15) ND - pCi/L Cs-137 4 10(18) ND - pCi/L Ba-La-140 4 15 0.8 +/- 1.9 3.1 +/- 1.7 pCi/L Other gamma emitters(Ru-103) 4 30 ND - pCi/L Algae Gross beta 1 0.25 3.04 +/- 0.13 3.04 +/- 0.13 pCi/g Co-58 1 0.25 ND - pCi/g Co-60 1 0.25 ND - pCi/g Cs-134 1 0.25 ND - pCi/g Cs-137 1 0.25 0.012 +/- 0.007 0.012 +/- 0.007 pCi/g Natural Be-7 1 - 0.85 +/- 0.09 0.85 +/- 0.09 pCi/g Natural K-40 1 - 2.26 +/- 0.16 2.26 +/- 0.16 pCi/g 36
Table 10-1 (continued) Summary of Radiological Environmental Monitoring Results for 2015 Average +/- 1 Std. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 44 4 1.6 +/- 1.0 4.4 +/- 1.1 pCi/L I-131 44 0.5 (2) ND - pCi/L Mn-54 44 10 (15) 0.1 +/- 0.7 1.3 +/- 1.1 pCi/L Fe-59 44 30 -0.6 +/- 2.0 4.4 +/- 4.2 pCi/L Co-58 44 10(15) 0.0 +/- 1.0 2.6 +/- 2.0 pCi/L Co-60 44 10(15) ND - pCi/L Zn-65 44 30 -0.5 +/- 2.5 3.8 +/- 2.7 pCi/L Zr-Nb-95 44 15 -0.1 +/- 1.1 2.4 +/- 2.0 pCi/L Cs-134 44 10 (15) -0.1 +/- 1.1 3.1 +/- 2.0 pCi/L Cs-137 44 10 (18) 0.2 +/- 0.6 2.3 +/- 2.1 pCi/L Ba-La-140 44 15 -0.8 +/- 2.2 2.9 +/- 1.5 pCi/L Other gamma (Ru-103) 44 30 -0.2 +/- 0.9 1.9 +/- 1.8 pCi/L Sr-89 16 5(10) ND - pCi/L Sr-90 16 1 (2) 0.28 +/- 0.15 0.71 +/- 0.38 pCi/L H-3 16 200 (3000) 97 +/- 116 452 +/- 94 pCi/L Fish Gross beta 14 0.5 2.81 +/- 0.56 3.62 +/- 0.08 pCi/g Mn-54 14 0.13 0.002 +/- 0.007 0.013 +/- 0.009 pCi/g Fe-59 14 0.26 0.006 +/- 0.027 0.056 +/- 0.036 pCi/g Co-58 14 0.13 -0.004 +/- 0.010 0.010 +/- 0.008 pCi/g Co-60 14 0.13 0.004 +/- 0.009 0.030 +/- 0.021 pCi/g Zn-65 14 0.26 ND - pCi/g Cs-134 14 0.13 ND - pCi/g Cs-137 14 0.15 0.029 +/- 0.012 0.054 +/- 0.020 pCi/g Other gamma (Ru-103) 14 0.5 0.000 +/- 0.011 0.020 +/- 0.009 pCi/g Natural K-40 14 - 2.42 +/- 0.57 3.25 +/- 0.42 pCi/g Gross beta 10 2 8.28 +/- 1.30 11.20 +/- 0.92 pCi/g Cs-134 10 0.18 ND - pCi/g Cs-137 10 0.15 0.019 +/- 0.008 0.029 +/- 0.016 pCi/g Natural Be-7 10 - ND - pCi/g Shoreline Natural K-40 10 - 5.75 +/- 1.53 8.69 +/- 0.50 pCi/g Sediment Natural Ra-226 10 - 0.38 +/- 0.07 0.54 +/- 0.17 pCi/g Soil Gross beta 16 2 22.62 +/- 6.24 31.19 +/- 1.22 pCi/g Cs-134 16 0.15 ND pCi/g Cs-137 16 0.15 0.154 +/- 0.077 0.315 +/- 0.036 pCi/g Natural Be-7 16 - 0.053 +/- 0.090 0.190 +/- 0.070 pCi/g Natural K-40 16 - 14.52 +/- 4.04 18.99 +/- 0.89 pCi/g Natural Ra-226 16 - 0.86 +/- 0.36 1.37 +/- 0.32 pCi/g Vegetation Gross beta 24 0.25 6.81 +/- 1.94 13.74 +/- 0.33 pCi/g I-131 24 0.06 0.000 +/- 0.008 0.016 +/- 0.010 pCi/g Cs-134 24 0.06 ND - pCi/g Cs-137 24 0.08 0.004 +/- 0.012 0.052 +/- 0.016 pCi/g Other gamma emitters (Co-60) 24 0.25 -0.005 +/- 0.005 0.011 +/- 0.008 pCi/g Natural Be-7 24 - 1.59 +/- 0.80 2.97 +/- 0.25 pCi/g Natural K-40 24 - 5.42 +/- 1.16 7.55 +/- 0.53 pCi/g (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity. (b) ND indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero or <MDA. 37
Table 10-2 Feed Crops Grown on Point Beach Land Average Max Number pCi/g 2 pCi/g 2 Gross Beta 10 4.94 +/- 3.76 8.12 +/- 0.27 Be-7 10 1.66 +/- 4.08 6.21 +/- 0.42 K-40 10 4.05 +/- 4.22 6.45 +/- 0.39 Mn-54 10 ND - Fe-59 10 ND - Co-58 10 ND - Co-60 10 0.000 +/- 0.009 0.006 +/- 0.005 Zn-65 10 ND - Zr-Nb-95 10 ND - Cs-134 10 ND - Cs-137 10 0.003 +/- 0.007 0.009 +/- 0.006 Ba-La-140 10 ND - ND = Not detected Table 10-3 Average ISFSI Fence TLD Results for 2015 Fence Location Average +/- Standard Deviation Units North 2.31 +/- 0.25 mR/7 days East 3.24 +/- 0.19 mR/7 days South 1.17 +/- 0.05 mR/7 days West 4.36 +/- 0.16 mR/7 days 38
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 indicator TLD is 1.18 +/- 0.20 mR/7-days compared to 1.20 +/- 0.15 mR/7-days at the background location. These two values are not significantly different from each other. Neither are the indicator TLD values significantly different from those observed from 2001 through 2014 for the same type of TLD (tabulated below in Table 11-1). Prior to third quarter of 2001 TLD LiF chips were used versus the current TLD cards, see Section 9.7.6 for additional information. The response difference between the two types of TLDs is evident in Table 11-1. Prior to 2001 all of the annual averages are <1 mrem/7-days. Beginning in 2001, all are >1 mrem/7-days. Table 11-1 Average Indicator TLD Results from 1993 - 2015 Year Average mR/7-days +/- St. Dev* 1993 0.82 +/- 0.15 1994 0.90 +/- 0.12 1995 0.87 +/- 0.13 1996 0.85 +/- 0.12 1997 0.87 +/- 0.11 1998 0.79 +/- 0.13 1999 0.79 +/- 0.21 2000 0.91 +/- 0.15 2001 1.06 +/- 0.19 2002 1.17 +/- 0.21 2003 1.10 +/- 0.20 2004 1.10 +/- 0.22 2005 1.04 +/- 0.21 2006 1.14 +/- 0.21 2007 1.08 +/- 0.20 2008 1.05 +/- 0.17 2009 1.08 +/- 0.17 2010 1.11 +/- 0.15 2011 1.14 +/- 0.25 2012 1.17 +/- 0.17 2013 1.14 +/- 0.20 2014 1.07 +/- 0.19 2015 1.18 +/- 0.20
*St. Dev = Standard Deviation No fuel was added to the ISFSI during 2015. However, four empty dry fuel storage units were stored at the ISFSI for use in 2016. The west fence TLDs continue to record higher exposures followed by the east, north, and south fence locations (Table 11-2). This sequence has been observed for the last five years.
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There is no significant change in the exposure on the TLD monitoring locations around the ISFSI (Table 11-3). The results at E-03 and E-31 (W of the ISFSI) and E-32 (SW of the ISFSI) are similar to previous years (1.36, 1.24, and 1.40, respectively) and continue to be higher than E-30 (1.07) on the east side and closest to the ISFSI. E-03, about equidistant between the ISFSI and the site boundary location, E-31, continues to be higher than the site boundary location. (See Figs. 9-1 and 9-2 for locations). Table 11-2 Average ISFSI Fence TLD Results (mR/7 days) TLD FENCE LOCATION YEAR 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 2008 2.64 2.37 1.36 5.36 2009 2.36 2.35 1.20 4.63 2010 2.64 3.02 1.41 5.05 2011 2.44 2.62 1.31 4.75 2012 2.59 3.27 1.40 4.92 2013 2.57 3.66 1.15 4.28 2014 2.45 3.35 1.14 4.24 2015 2.31 3.24 1.17 4.36 Although the mR/7-day results for the three TLD locations nearest the site boundary (E-03 1.36 +/- 0.31; E-31, 1.24 +/- 0.30; E-32, 1.40 +/- 0.38) are higher than at the background site E-20 (1.20 +/- 0.29), they are comparable at the 95% confidence level, indicating a small, but not significant, increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI. Further data supporting this conclusion is the comparison of the TLD results at selected locations around the ISFSI before and after the storage of spent fuel at the ISFSI (Figure 11-1). As stated in Section 9.7.6, the TLD values increased by about 14% in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of the 2001 to calcium sulfate impregnated TLD cards. After that initial change, the measured radiation exposure, as measured by the TLD cards, has remained fairly constant with a slight increase with the addition of stored fuel at the ISFSI. Each year the variations in the TLD results appear to move in 40
concert with each other and with the background site, E-20, which is 17 miles south west of the ISFSI. Comparing the ISFSI TLD results to results from surrounding REMP indicator and background TLDs reveals minimal impact of the ISFSI on the surrounding Figure 11-1 ISFSI AREA TLD RESULTS 1995 - 2015 ISFSI AREA TLD RESULTS 2 E-03 mR/7 days 1.5 E-28 1 E-29 0.5 E-30 0 E-31 1990 1995 2000 2005 2010 2015 2020 E-32 YEAR E-20 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 1.05 1.18 0.97 1.05 2008 1.33 0.75 0.81 1.00 1.12 1.03 1.00 2009 1.39 0.82 0.85 1.01 1.17 1.05 1.09 2010 1.41 0.84 0.89 1.07 1.21 1.24 1.10 2011 1.46 0.85 0.90 1.06 1.25 1.32 1.12 2012 1.54 0.87 0.91 1.10 1.21 1.39 1.14 2013 1.23 0.87 0.77 1.00 1.40 1.38 1.22 2014 1.23 0.77 0.79 0.97 1.25 1.25 1.15 2015 1.36 0.86 0.78 1.07 1.24 1.40 1.20
*Pre-Operational data are the averages of the years 1992 through 3rd 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.
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radiation levels (Figure 11-2). As previously discussed, the small increase is more related to the switch from the LiF chips to the calcium sulfate impregnated Teflon TLD cards as evidenced by the synchronicity with E-20, the background site. LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards in the third quarter of 2001 resulting in a higher measured background values. Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 11.2 Milk Naturally occurring potassium-40 (1409 +/- 60 pCi/l) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 2000 times higher than the only potential plant related radionuclide, Sr-90 (0.6 +/- 0.3 pCi/l), detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. There were several (3 of 36) positive Ba-La-140 results. However, PBNP did not discharge any Ba-La-140 during the years 2013 - 2015. Given the short half-life of Ba-La-140 (12.8 days), it is unlikely that these results represent a carry- over from previous years. Because the highest Ba-La-140 concentration is very near the detection limit, the positive values are considered to be false positives attributable to the statistical nature of radioactive decay. Some low positive Cs-134 (2 of 36) and Cs-137 (6 of 36) results were obtained. No airborne Cs-134 or Cs-137 was discharged from PBNP in 2015. The Cs-134 results are considered to be false positives which occur due to the random fluctuations in background in low activity samples. The Cs-137 values also are near the detection limit and therefore may be false positive. Another possibility is residual Cs-137 recycling through the environment from the 1960s atmospheric weapons tests and events such as Chernobyl and Fukushima. Several (3 of 36) positive Co-60 values were obtained. The only airborne Co-60 release occurred in October via the Unit 2 containment hatch. Two of the small positive results occurred prior to October. The small positive Co-60 result is from a sample obtained within the time frame of one Co-60 release. However, it is upwind of the site. Based on the sample locations and on the low Co-60 concentration values, all of the Co-60 results are considered to be false positives. No I-131 was discharged and no positive I-131 results were obtained. 42
Although the average Sr-90 concentrations have not changed much over the last nineteen (19) years, 1.2 +/- 0.5 pCi/L in 1997 to 0.5 +/- 0.3 pCi/L in 2015, a graph of the annual averages displays a logarithmic decrease over time (Figure 11-3). The annual averages are from the monthly Sr-90 measurements from three different dairies (Fig. 9-1). The only dairy that has been in the monitoring program over the entire 1997 - 2015 timespan under consideration is located at site E-21. It is located south of the plant. The other two, E-40 and E-11, are replacements for dairies which had dropped out of the program at various times during this time interval. The replacements were chosen to maintain, to the extent possible, the former sampling sites west and north of Point Beach. Over the years1997 to 2015, the Sr-90 in milk decreases with a half-life of 15.0 years. Because the radiological half-life is 28.6 years, the shorter removal half-life indicates that environmental factors as well as radioactive decay are working to decrease the concentration of Sr-90 in milk. The calculated physical removal half-life is 31.7 years. Figure 11-3 Sr-90 Concentration in Milk (1997 - 2015) The major Sr-90 input to the environment was from fallout from atmospheric weapons testing during the early 1960s with minor inputs during the 50s, 70s and later contributions from the Chernobyl accident in the late 1980s and from Fukushima in 2011. The Sr-90 in milk persists due to its 28.6 year half-life and to cycling in the biosphere. With little or no atmospheric input to the environment, the mode of entry into cattle feed must be root uptake by forage crops and transfer into the milk. Therefore, the shorter observed half-life is indicative of Sr-90 removal from the soil by processes other than radioactive decay. Over the time period of this graph (1997 - 2015), PBNP discharged airborne Sr-90 only in 3 years: 1998, 2.4E-08 Ci; 2004, 3.2E-08 Ci; and 2011, 1.6 E-08 Ci. These low discharges do not appear to impact the decreasing concentrations as they continue to decrease over time. It is concluded that the milk data for 2015 show no radiological effects of the plant operation. 43
11.3 Air The average annual gross beta concentrations (plus/minus the two-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.025 +/- 0.019 pCi/m3 and 0.024 +/- 0.019 pCi/m3, respectively, and are similar to levels observed from 1993 through 2014 (Figure 11-4). The 2015 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-5). This is a repeat of the patterns seen in 2006 - 2014. As in 2014, there is a slight peak in late summer followed by some lower values in October and early November. The cause for this variation is not known. However, the control and indicators are moving in concert. Therefore, a plant effect can be ruled out. Similarly, there is a decreasing trend in January before returning to the January highs in February. Again, the indicator and background sites move in concert ruling out a plant effect. Figure 11-4 Annual Average Air Gross (1993 - 2015) Figure 11-5 2015 Airborne Gross Beta 44
No I-131 was detected during 2015. In 2005, the new method of evaluating airborne I-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 is detected, each sample cartridge is counted individually. With no detectable I-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 0.005 to 0.0.016 pCi/m3. 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, in the range of 0.001 to 0.003 pCi/m3. At each sampling location, the particulate filters are composited quarterly and analyzed for Cs-134, Cs-137 and any other (Co-60) detectable gamma emitters. As summarized in Table 10-1, low, positive results (5 of 24) for gamma emitters attributable to Point Beach were detected. By contrast, naturally occurring Beryllium-7 was found in all of the quarterly composites at concentrations an order of magnitude higher. Be-7 (T1/2 = 53.3 days) is produced in the atmosphere by the interaction of cosmic rays with oxygen and nitrogen nuclei. Its half-life is long enough to allow for it to be detected in the quarterly composited filters. Based on location and results at or below the MDC, the Co-60 and Cs-137 results are concluded to be false positives. In summary, the 2015 air gamma data from quarterly composites do not demonstrate an environmental impact from the operation of PBNP. 11.4 Lake Water For the 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. Lake Michigan water samples are collected north (E-33 and E-05) and south (E-01 and E-06) of PBNP (see Figure 9-1). There were sixteen, slightly positive indications of gamma emitters during 2015, nine north of the plant and seven to the south. Although the major current is from north to south, these locations may be upstream or downstream of the plant discharge depending upon wind stress which can reverse currents. A comparison of when the positive results were obtained to when discharges occurred suggests that the small, positive results are false positives. For example, positive results were obtained for Ru-102, Cs-134, and Ba-La-140 which were not in the 2015 effluents. Similarly, positive results were obtained for Mn-54 and Cs-137 in months when these radionuclides were not discharged. Also, Zr-95 and Nb-95 were identified in months they were not discharged but not in the months they were in the PBNP effluents. Finally, the measured concentrations are in the range of 2 - 4 pCi/l which convert to 2 - 4E-09 Ci/cc or 10 - 100 times greater than the typical discharge concentrations of E-14 to E-11 Ci/cc. Based on the further dilution which occurs in the lake after discharge, it is highly unlikely that observed positive 45
results are real. Therefore, based on these comparisons, it is concluded that the sixteen positive results are false positives and not indications of PBNP effluents in Lake Michigan during 2015. A false positive is concluding an isotope is present when it isnt. False positives occur most often at the detection limit when the random fluctuations of the background result in lower than normal background activity. The result is a higher net count and hence falsely concluding an isotope is present when it isnt because the value is statistically above zero. In conclusion, based on the results of the gamma scans of Lake Michigan water, there is no measureable impact on the lake from PBNP discharges. Aliquots of the monthly samples are composited quarterly and analyzed for Sr-89/90 and for tritium. Small amounts of Sr-90 were detected. As in 2012 - 2014, Point Beach did not discharge any Sr-90 in 2015. There were five lake water composites in which the Sr-90 concentrations were slightly positive. They occurred north and south of the plant. Sr-90 has a 28.6 year half-life and, like Cs-137, is a remnant of atmospheric weapons testing in the 50s and 60s. Therefore, positive Sr-90 concentrations are indicative of fallout being recycled in Lake Michigan. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. It also was produced by atmospheric weapons testing. However, due to its mobility, any H-3 now found in Lake Michigan at the concentrations typically found in monitoring programs cannot be from that time period. It is the result of power plant discharges. Point Beach discharges on the order of 700 - 800 Ci per year. Eight of the sixteen quarterly composites had positive H-3 indications. Three were south and five were north of the PBNP discharge. The highest, 452 +/- 94 pCi/l, was from a fourth quarter composite sample about 1.6 miles north (E-05) of Point Beach with a lower value of 237 +/- 84 pCi/l from a location (E-33) about 4.5 miles north of PBNP near the shut-down Kewaunee plant. Based on this result, the individual month samples from the two locations were analyzed for H-3. The highest concentrations occurred in the December 10th samples, 1336 +/- 139 pCi/l closest to PBNP and a lower value of 464 +/- 111 pCi/l near the Kewaunee plant. (Both results are lower than the EPA drinking water standard of 20,000 pCi/l) There were no positive H-3 results for the October or November samples north of PBNP. As a further check the December 10th samples from the two locations 0.6 (E-01) and 6 miles (E-06) south of PBNP also were analyzed for H-3 and no positive results were obtained. Because Kewaunee had not discharged any H-3 in the month preceding the December 10th samples and PBNP had seven discharges containing H-3 in the six days prior to the December 10th sample, it is concluded that the observed H-3 results were due to PBNP effluents. The occurrence and analyses were documented in the PBNP CAP. 11.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Samples are obtained at Two Creeks Park and at the PBNP discharge (locations 5 and 12 in Figure 9-1). In order to 46
allow the algae time to grow, typically no samples are collected until June and then again August and October. This is done to ensure that there is enough new growth to provide a sample. In 2015 only one algae sample was obtained and that was on August 27th near the PBNP discharge. On the other occasions the algae either was not present or located in spot which was visible but not accessible. Positive results were obtained for the naturally occurring radionuclides Be-7 and K-40. No Co-58, Co-60, or Cs-134 was detected. Cs-137 was detected at 0.012 +/- 0.007 pCi/g. This is roughly half the highest concentration (0.023 +/- 0.009 pCi/g) found at the same location in in 2014. Co-58 and Co-60 which were discharged in the seven months preceding the August sample were not detected. As previously discussed, fallout Cs-137 recycles in Lake Michigan and is attached to particles. The positive results are attributable to the recycling of bomb fallout from weapons testing in the '50s, 60's and other nuclear events such as Chernobyl and Fukushima. There also may be a small contribution, but unknown, amount from past nuclear plant discharges. Because PBNP did not discharge any Cs-137 in 2015 prior the August sample, it is concluded that the positive result is indicative the recycling of fallout and other previously discharged Cs-137 in Lake Michigan. 11.6 Fish Fourteen fish were analyzed in 2015. All 14 fish had detectable amounts of Cs-137 with results ranging from 0.012 +/- 0.010 to 0.054 +/- 0.020 pCi/g. The Cs-137 is attributable to the recycling of this radionuclide in Lake Michigan. The majority of Cs-137 entered Lake Michigan as fallout from atmospheric weapons testing in the
'50s and '60s with lesser amounts from events at Chernobyl and Fukushima.
Fish analyses also yielded small amounts of Mn-54 (0.013 +/- 0.009), Fe-59 (0.056 +/- 0.036), Co-58 (0.010+/- 0.008), Co-60 (0.030 +/- 0.021), and Ru-103 (0.020 +/- 0.009) pCi/g. These results could be false positives. For example, Fe-59 was found is a fish from 3/15/15. However, no prior Fe-59 discharge occurred in 2015 and in 2014, Fe-59 was released only in April and May. Based on the May Fe-59 discharge concentration of 1.58E-11Ci/cc or 0.0000158 pCi/cc (Permit 14-00049L) and assuming no decay or further dilution in the lake, an iron bioaccumulation factor of 100 for freshwater fish (RG 1.109, Rev.1, Table A-1) yields a fish concentration of 0.00158 pCi/g in March of 2015. If radioactive decay were considered, a decay of about 7 half-lives or roughly 300 days would have to be factored in making the fish concentration even lower by a factor of about 1/128th of the original. This is below the highest measured Fe-59 concentration of 0.056 pCi/g. Therefore, it is concluded that the low measured Fe-59 concentrations in fish are false positives. The same evaluation holds for Co-58 and Co-60. Co-58 and Co-60 in December release permit 14-000111L had concentrations of 6.73E-11Ci/cc (6.7E-05 pCi/cc) and 5.75E-12 Ci/cc (5.75E-06 pCi/cc), respectively. Appling a bioconcentration factor of 50 yields fish concentrations of 3.37E-04 and 2.88 E-04 pCi/g, respectively, before decay and further dilution in Lake Michigan. The first positive Co-60 in a fish (0.013 pCi/g) was from a sample from 1/18/2015. This is much higher than predicted by RG 1.109. Also, no Co-58 was found in the same fish and it was discharged in a higher concentration than Co-60. Therefore, PBNP discharges cant be the cause of the identified Co-58 and Co-60. The conclusion is that the low 47
cobalt concentrations are false positives. Similarly, it is concluded that the positive result for Ru-103 is a false positive because no Ru-103 was released in either 2014 (2014 AMR Table 2-3) or 2015 (Table 2-3). The highest radionuclide concentration in fish is naturally occurring K-40 with an average concentration of 2.42E+00 pCi/g. Based on these results, it is concluded that there is no impact of PBNP discharges on Lake Michigan fish. 11.7 Well Water Three plant related radionuclides were detected in main plant well water (E-10) during 2015, Ba-La-140 and Sr-90. The April 15th Ba-La-140 result is considered to be a false positive because of its short half-life and the fact that none has been discharged in 2014 or in 2015 prior to the sampling date. Also the Sr-90 is considered to be a false positive because its concentration of 0.9 +/- 0.3 pCi/l is much higher than the gross beta result of 0.2 +/- 0.9 pCi/l. Had the Sr-90 result been real, the gross beta should have been comparable given the greater efficiency of counting the Sr-90 daughter product, Y-90, which would have been present in the gross beta measurement. Therefore, it is concluded that there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP. 11.8 Soil Cs-137 is present in the soils throughout North America and the world resulting from the atmospheric nuclear weapons testing in the 1950s, 1960s, and 1970s and from the 1986 Chernobyl accident, and more recently, from the Fukushima event. Soil is an integrating sample media, in that it is a better indicator of long term buildup of Cs-137 as opposed to current deposition for local sources. In addition to erosion and radioactive decay, human activities can modify the soil Cs-137 concentrations. Evidence for the latter are the typically higher Cs-137 concentrations found at E-06, 0.315 +/- 0.036 pCi/g in May and 0.28 +/- 0.033 in October as compared to other locations. At E-06, trees growing and incorporating Cs-137 during the time of atmospheric fallout are now being burned in camp fires thereby releasing the incorporated Cs-137 to the surrounding area. In 2015, as in 2014, Cs-137 was found in all soils analyzed with the highest values in May and in October both being at E-06, Point Beach State Park. There is no indication of a plant effect based on the comparison of indicator and background results. By comparison to naturally occurring radionuclides, the Cs-137 concentrations continue to be present in soil samples at well below levels of naturally occurring K-40 (5.38 +/- 0.37 to 18.99 +/- 0.89 pCi/g). In addition to K-40, other naturally occurring radionuclides such as Be-7 and Ra-226 were found in the soil. There is no evidence of Point Beach effluent in the soil samples. 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-137. Eight of the ten samples have Cs-137 concentrations statistically different from zero. The shoreline sediment Cs-137 48
concentrations continue to be about one-tenth of that found in soils. This is expected because Cs-137 in the geological media is bound to fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-137. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about several hundred times higher than the Cs-137 that is attached to particle surfaces. Therefore, it is not surprising that Cs-137 is present at concentrations 1% or less of the naturally occurring concentrations of K-40. The absence of any PBNP effluent nuclides, such as Co-58/60, other than Cs-137 indicates that the most likely source of the observed Cs-137 is the cycling of radionuclide in the Lake Michigan environment and not current PBNP discharges. As with soil, the naturally occurring radionuclides such as K-40, and Ra-226 are found in the shoreline sediment samples. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation. 11.10 Vegetation The REMP collects two general types of vegetation within the site. The first consists of general vegetation, non-cultivated plants which would be consumed by grazing cattle. The second consists of crops grown on site acreage licensed to farmers, about half the sites 1400 acres, for growing feed crops for cattle. Ten samples of cultivated crops (corn, hay, alfalfa, and soybeans) grown on this acreage were obtained for analyses. The naturally occurring radionuclides Be-7 and K-40 were found in all of the general vegetation samples. 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. (Spallation is a process whereby a cosmic ray breaks up the target atom's nucleus producing a radionuclide of lower mass.) Be-7 concentrations ranged from 0.18 +/- 0.08 to 2.97 +/- 0.25 pCi/g. The average concentrations increased from May (0.94 +/- 1.10 pCi/g) than in July (1.28 +/- 0.42) and October (2.54 +/- 0.78). This is consistent with the known temporal variability in Be-7 concentrations in air near the earth's surface and the gradual build-up of fallout on the vegetation over time. In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. By not being dependent upon seasonal atmospheric variations and plant surface to capture deposition, the K-40 concentrations from root uptake are more uniform with averages of 4.97, 5.60, and 5.71 in May, July, and October, respectively. Cs-137 can be present in vegetation via both pathways. Fresh Cs-137 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. This fallout Cs-137 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-137 in Wood Ash, Results of a Nationwide Survey," 5th Ann. Nat. Biofuels Conf., 10/21/1992). 49
In 2015 only four of the twenty-four vegetation samples had a positive indication for Cs-137 and only E-06 (0.052 +/- 0.016) was significantly above background. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-137. This occurrence is attributed to the above described mechanism. The only airborne Cs-137 discharged by PBNP occurred in October 2015. Therefore, it is unlikely that the four positive Cs-137 values resulted from PBNP releases. The only other radionuclides having positive indication were Co-60 and I-131. Although Co-58 airborne releases occurred prior to the July vegetation sample, no Co-60 was released. If the Co-60 were from PBNP effluent, Co-58 also should have been detected. No airborne I-131 releases occurred during 2015. Therefore, the I-131 cant be from PBNP. Based on these considerations, the Co-60 and I-131 results, it is concluded that these results are false positives. Based on the 2015 general vegetation sampling results, it is concluded that there is little or no effect from PBNP effluents. Similar results and conclusions are reached from the analytical results for the crops grown on site acreage. Naturally occurring Be-7 and K-40 are found in all crops. As in general vegetation, K-40 is incorporated from the soil whereas Be-7 is from atmospheric deposition. Only two crop samples had slightly positive results, one for Co-60 and the other for Cs-137. Although Co-58 airborne releases occurred prior to the September crop sample, no Co-60 was released. Therefore, the Co-60 is concluded to be a false positive. Similarly, in 2015 no airborne Cs-137 occurred in PBNP effluent prior to the September sample. The Cs-137 could be an indication of fallout from weapons testing, Chernobyl, and Fukushiima. However, because in both cases the results were below the minimum detectable concentration, the results are determined to be false positives. Therefore, based on the analytical results from crops grown on site, there is little or no evidence of PBNP effluents 11.12 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 2015. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. The nearest dairy lies in the SSE sector and it is one of the Point Beach REMP milk sampling sites. This dairy leases land in the S and SSE sectors at the PBNP site boundary for growing feed corn. Also, the highest /Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. Therefore, dose calculations to the maximum exposed hypothetical individual, assumed to reside at the site boundary in the S sector, continues to be conservative for the purpose of calculating doses via the grass-cow-milk and the other ingestion pathways. 50
11.13 Long Term TLD Trending To put the 2015 REMP TLD results in perspective, it is instructive to look at long term trends. The following examines the TLD results from 1971 to 2015. The ANSI standard (ANSI/HPS N13.37-2014 Environmental Dosimetry) states that the data from early vintage dosimetry systems (c. 1970 - 1990) should not be considered comparable to current dosimetry systems in establishing a baseline for environmental TLD results. These problems are evident from the review of our early data as discussed below. The pre-operational data, 1968 - 1970, are not included. The pre-operational ambient radiation monitoring sites were E-01 (the met tower area) through E-04 (the north boundary). They were monitored using TLDs and ionization chambers. E-04 was used as a background location until E-08 (see Figure 9-1) was added for the operational REMP in 1971. Prior to 1975, a control TLD stored in a lead pig was used for a comparison to those placed in the field. In the pre-operational data, the control TLD could be equal to or higher than the field results and both the field and control TLD results appear erratic compared to the ion-chamber results. Also, the reported TLD results do not have transportation exposures from New Mexico to Wisconsin subtracted. Therefore, only the TLD results beginning in 1971, with the transportation caveat, are used in this analysis of long-term trends. The trend at E-01(Figure 11-6) shows slowly decreasing tread from 1971 to 1979. This is may be an artifact. The cause is not known. As previously mentioned, no transportation controls were used until the 4th quarter of 1975 so no transport dose corrections were made prior to that quarter. There is a small increase in 1980 when the current contracted REMP lab began. A slowly decreasing exposure rate occurs from 1980 - 1992 except for the 1984 - 1988 time segments. The erratic results from 1984 - 1988 was traced to a faulty connection in the TLD reader. Figure 11-6 E-01 Results 1971 - 2015 The TLD package from 1980 to 2001 consisted of three LiF chips sealed in a black plastic bag. The magnitude of the error bars indicates the degree of variability of the 1984 - 1988 results from the three chips due to a fault in the TLD reader. The results appear much the same for the E-03 and E-20 results (Figure 11-7). Note that E-20 did not begin until 1976. Again, there is an increase in both the E-20 (the 51
background site) and E-03 (the location nearest the ISFSI) which coincides with the switch from the LiF chips to the Teflon TLD cards. Given that the first twelve casks were loaded December 1995 to September 2000 in which there were no increases in the TLD results, the increase in 2001 indicates that this change is the result of the different response of the new TLDs and not of any effluents or shine from the plant. Figure 11-7 Comparison of E-03 and E-20 Results 1971 - 2015 Narrowing the time window for the TLD comparisons from 1992 to the present allows a comparison among the for original four TLD locations since the introduction of the ISFSI (Figure 11-8) without the interference by the faulty TLD reader in the mid-1980s. Sites E-01 and E-02 are about 1 mile south of the ISFSI. E-03 is 1200 feet west and E-04 is 4300 feet north. Figure 11-8 Comparison of E-01, E-02, E-03 and E-04 Results 1992 - 2015 The comparison shows a definite difference between E-01 and the other three locations. E-01, although approximately the same distance from the ISFSI as E-02 52
and further away than either E-03 or E-04, is lower than the other three sites. Therefore, distance is not the determining factor in the difference among the measured exposures. There are two factors which could cause the observed difference. The first difference is that E-02, E-3, and E-04 are surrounded by plowed fields whereas the area around E-01 is uncultivated. Second, E-01 is within 100 feet of the lake. Therefore, about 50% of the area contributing natural radiation to the location is a combination of beach sand and lake water. As seen from the REMP soil and beach analyses, beach sand has lower averages Ra-226 content than the soil, 0.38 +/- 0.07 pCi/g for beach sand vs. 0.86 +/- 0.36 pCi/g for soil. The impact of the ISFSI on the ambient radiation levels at its nearest site boundary, the west boundary is shown in Figure 11-9. The ISFSI impact on ambient exposure levels was addressed briefly in Section 11.1 (see Figure 11-2). Figure 11-9 E-03, E-31, and Background Site E-20 Results 1992 to 2015 Figure 11-2 shows that beginning with the use of the Teflon TLD cards in the fourth quarter of 2000, the measured exposure levels at E-03 are 2 - 5 mR/7-days lower than the exposures at the west fence of the ISFSI. Figure 11-9 shows that although their individual 95% confidence levels overlap indicating no statistical difference, the quarterly exposures at E-03 (about 1200 feet from the ISFSI) are consistently higher than the exposure at E-31 (at the site boundary about 1400 feet west of E-03). Therefore, the lower values at E-31 compared to E-03 appear to be a real difference 53
as the distance from the ISFSI increases at the west boundary. Because land usage and location are similar at E-03 and E-31, the cause of the previously identified response differences between E-03 and E-01 are not applicable. Therefore, the lower results at the site boundary location E-31show that the exposures from the ISFSI are dropping off and approaching the lower readings found at the background site E-20. 12.0 REMP CONCLUSION Based on the analytical results from the 811 environmental samples and from 130 sets of TLDs that comprised the PBNP REMP for 2015, PBNP effluents had no discernable effect on the surrounding environs. The calculated effluent doses are below the 10 CFR 50, Appendix I dose objectives demonstrate that PBNP continues to have good controls on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a. Additionally, when the TLD results are factored in to the overall exposure, the resulting doses are lower than the ISFSI (10 CFR 72.104) and EPA (40 CFR 190) limits of 25 mrem whole body, 75 mrem thyroid, and 25 mrem any other organ. From the long-term analysis of TLD results, there is no evidence of elevated ambient radiation levels from the operation of Point Beach except for the slightly higher exposures measured at the site boundary (E-31) compared to the background reference site (E-20). 54
Part D GROUNDWATER MONITORING 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium as part of the Groundwater Protection Program (GWPP). During 2015 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, façade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 façade. In the late 1970s, 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 this observation, modifications were made to the pool, and the tritium concentrations decreased below the effluent LLDs. 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. In addition to H-3, groundwater beach drain samples also are gamma scanned for the same suite of radionuclides as lake water using the lake water LLDs. Three intermittent stream locations 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. A fourth stream location closer to the plant was added in 2008. 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 meteorological tower. The intermittent stream samples track H-3 in the surface groundwater. The groundwater monitoring program also includes two bogs / 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, four 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. In 2012, a new building (Warehouse 7) was constructed for radwaste. The well for this building was added to the GWPP. 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 - 600 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 55
electrical conduits are susceptible to ground water in-leakage. Therefore, a number of these were sampled. The SSD system was designed to lessen hydrostatic pressure on the foundation by controlling the flow of water under the plant and around the perimeter of the foundation walls. The SSD system flows to a sump in the Unit 2 facade. The sump was sampled ten times during 2015. Due to flooding concerns, man-holes and clean-outs for the SSD now are sealed in 2014. Therefore, only the SSD sump now is used for sampling. In the 1990s, two wells were sunk in each units façade to monitor the groundwater levels and look for evidence of concrete integrity as part of the ISI IWE Containment Inspection Program. These wells are stand pipes which are sampled periodically for chemical analyses. Façade well sampling has been part of the GWPP since 2007. These wells are sampled quarterly. The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1. 56
Figure 13-1 Groundwater Monitoring Locations 57
14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface 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 and less than the MDC. The highest averages are for the East Creek and STP which are in the flow path to Lake Michigan. The West Creek is west of the former retention pond, an upstream location with respect to the groundwater flow. The H-3 concentration at GW-08, close to the former retention pond, is about one-tenth of the H-3 concentrations it had prior to the remediation of the retention pond. Table 14-1 Intermittent Streams and Bogs H-3 Concentration (pCi/l) Month GW-01(E-01) GW-02 GW-03 GW-17 BOGS MDC Creek Confluence E. Creek W. Creek STP GW-07 GW-08 Jan NS +/- NS +/- NS +/- NS +/- Feb NS +/- NS +/- NS +/- NS +/- Mar 167 +/- 80 270 +/- 85 93 +/- 76 196 +/- 81 147 Apr 136 +/- 80 222 +/- 84 107 +/- 79 220 +/- 84 147 May 106 +/- 80 ND +/- 129 +/- 81 131 +/- 81 135 +/- 84 275 +/- 91 150 Jun 123 +/- 78 184 +/- 81 ND +/- 174 +/- 80 143 Jul 124 +/- 81 83 +/- 79 141 +/- 82 221 +/- 86 143 Aug 77 +/- 76 173 +/- 81 117 +/- 78 138 +/- 79 145 Sep 143 +/- 81 189 +/- 83 113 +/- 79 220 +/- 85 147 Oct ND +/- ND +/- ND +/- 112 +/- 76 141 Nov ND +/- 163 +/- 80 ND +/- 97 +/- 77 144 Dec ND +/- 122 +/- 78 ND +/- NS +/- 144 Average 125 +/- 29 176 +/- 54 117 +/- 17 168 +/- 49 A blank indicates no sample was available. Streams are sampled monthly; bogs, annually. NS = no sample due to dry or frozen. Streams are sampled monthly; bogs, annually. Values are presented as the measured value and the 95% confidence level counting error. ND = measured value is less than the minimum detectable concentration. The LLD = 200 pCi/l. The analyses of these surface water samples show low concentrations of H-3. Although small positive H-3 concentrations occur in samples from the confluence of the two creeks (GW-01) and from the West Creek (GW-03), all, but one, of these concentrations are below their associated MDCs. In contrast, there are more positive results from GW-02 (south end of the East Creek) and GW-17 (located at the north end of the East Creek). GW-17 is directly east of the former retention pond area in the groundwater flow path to Lake Michigan. The East Creek concentrations are generally lower than the 300 - 350 pCi/l found before the retention pond was remediated in 2002. It should be noted that the East Creek, in addition to being path of the west to east groundwater flow from the old retention pond, also is fed by yard runoff from the west side of the yard which may account for the higher values. The bog (GW-08) SE of the former retention pond is higher than the bog at GW-07 north of the former retention pond. These results are in conformance with the west to east groundwater flow described in the Site Conceptual Model and the FSAR. 58
The GW-08 bog result is down from the 3000 pCi/l seen before the pond was remediated. 14.2 Beach Drains The 2015 results for the beach drains are presented in Table 14-2. [The drain data from left to right in the table are in the order of the drains from north to south.] S-1 collects yard drainage from the north part of the site yard; S-3, from the south. Drains S-8 and S-9 carry water from the lake side yard drains whereas drains S-7 and S-10 are from the turbine building roof. S-11 is not connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant. Table 14-2 2015 Beach Drain Tritium Average H-3 Concentration (pCi/l) Month S-1 S-7 S-8 S-9 S-10 S-3 S-11 MDC Jan NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- Feb NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- Mar 355 +/- 95 NF +/- NF +/- NF +/- NF +/- 316 +/- 93 210 +/- 88 148 Apr 134 +/- 86 NF +/- NF +/- NF +/- NF +/- 430 +/- 99 214 +/- 90 150 May 200 +/- 87 NF +/- NF +/- NF +/- NF +/- 302 +/- 92 NF +/- 147 Jun 212 +/- 87 NF +/- NF +/- NF +/- NF +/- 190 +/- 86 NF +/- 155 Jul 160 +/- 100 NF +/- NF +/- NF +/- NF +/- 262 +/- 104 NF +/- 154 Aug 122 +/- 85 NF +/- NF +/- NF +/- NF +/- 644 +/- 107 NF +/- 150 Sep 205 +/- 84 NF +/- NF +/- NF +/- NF +/- 249 +/- 87 NF +/- 148 Oct 244 +/- 86 NF +/- NF +/- NF +/- NF +/- 165 +/- 82 NF +/- 149 Nov 342 +/- 92 NF +/- NF +/- NF +/- NF +/- 219 +/- 86 NF +/- 151 Dec 292 +/- 87 NF +/- NF +/- NF +/- NF +/- 152 +/- 80 NF +/- 145 Avg = 227 +/- 81 293 +/- 148 212 +/- 3 ND = not detected and MDC NF = no sample due to no flow The high H-3 concentrations (355 and 644 pCi/l) occur in March of 2015 at S-1 and August at S-3. As in previous years, measureable H-3 results occur mostly in drains S-1 and S-3. As shown in previous reports, these high values are attributable to precipitation scavenging by rain and snow followed by melting. Gamma scans were performed on the beach drain samples at the LLD used for lake water. A few indications of small, positive concentration values below the calculated MDC were found for Zr-Nb-95(1), Cs-137(2), Fe-59 (1), Zn-65(1), Ba-La-140(4) as well as for naturally occurring Be-7(1). A liquid release source can be ruled out because no Ba-La-140 was released in 2015. Had there been a liquid source radionuclides such as Co-58 and Co-60 would have been seen as well. Similarly, no airborne Ba/La-140 was released either. Given that the measured concentrations are below their analytical MDC values, that they occur sporadically, and that some of these isotopes were not found in PBNP effluent, these small, positive values are considered to be false positives. Therefore, it is concluded that H-3 is the only PBNP radionuclide found in the beach drains. 59
14.3 Electrical Vaults and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The manholes east side of the plant, between the Turbine building and Lake Michigan have low H-3 concentrations (Table 14-3). These manholes, Z-066A and Z-067A through Z-066D AND Z-067D, run in parallel in the NE section of the yard beginning just north of the Unit 2 truck bay and run from the Unit 2 truck bay north to the EDG building. Z-068 is located just west of the EDG building and north of Z-66/67D. Each of the two A, B, C, and D vaults is side by side. Based on being side-by-side, it is expected that the each pair of manholes 66A/67A, etc. would have similar H-3 concentrations. This is appears to hold except for the 66B/67B vaults where the April H-3 results were not different from zero in the 66B sample. Unequal groundwater inleakage is the most probable cause. Table 14-3 2015 East Yard Area Manhole Tritium (pCi/l) MH 4/23/2015 9/28/2015 Z-066A 77 +/- 76 163 +/- 83 Z-067A 139 +/- 79 209 +/- 85 Z-066B ND ND Z-067B 248 +/- 84 ND Z-066C ND +/- 153 +/- 82 Z-067C 98 +/- 77 125 +/- 81 Z-066D 153 +/- 80 212 +/- 85 Z-067D 199 +/- 82 136 +/- 81 Z-068 250 +/- 85 220 +/- 86 MDC 152 149 ND = not detected 14.4 Façade Wells and Subsurface Drainage System There are two methods of sampling the groundwater under the plant foundation. The first is a set of four shallow wells, two in each façade. The other is a subsurface drainage system (SSD). The façade wells were installed to monitor for groundwater conditions which may be detrimental to the integrity of the concrete and rebar of each units foundation. The SSD was designed to relieve hydrostatic pressure on each units foundation as well as the Auxiliary and Turbine buildings. The façade wells are not located symmetrically in the two units. The Unit 1 façade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361B) corners of the façade. However, in Unit 2, there is one well in the NW corner (2Z-361A) and the other rotated approximately 180° in the SW corner (2Z-361B). In each the well cap is level with the floor. The 2015 façade well results are shown in Table 14-4. The Unit 1 wells continue to have higher H-3 concentrations than the U2 wells with 1Z-361A, in the SE corner of the Unit 1 façade, having the highest H-3 concentrations. The highest results are in line with the 2013 and 2014 highs of 324 and 375 pCi/l, respectively. By contrast, the 2007 and 2008 high concentrations were 1169 - 1331 pCi/l. Based on these 60
façade well results, the conclusion is that H-3 is unevenly distributed in the soil beneath the plant continues to be true. Table 14-4 2015 Facade Well Water Tritium (pCi/l) UNIT 1 UNIT 2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B MDC February 307 +/- 91 147 +/- 83 NS +/- ND +/- 81 151 April 287 +/- 107 ND +/- ND +/- ND +/- 84 183 August 253 +/- 87 ND +/- ND +/- 101 +/- 80 150 October 346 +/- 88 ND +/- ND +/- 120 +/- 77 141 To relieve hydrostatic pressure on the foundation, Point Beach has an external and an internal subsurface drainage system (SSD) to drain groundwater away from the foundation. The internal SSD consist of perforated piping which drains groundwater by gravity to a sump located in the Unit 2 façade. The part of the SSD under the Turbine Building is at a higher elevation than the part under the facades. The SSD sump results are presented in Table 14-5. The 2015 average concentration of 599 +/- 131 pCi/l is not statistically different than the 725 +/- 235, 643 +/- 201 and 513 +/- 269 pCi/l seen in 2014, 2013 and 2012, respectively. The external SSD system runs along the external foundation walls for the Unit 1 and Unit 2 facades, the Auxiliary Building, the North Service Building, and the Turbine Hall. It is not connected to the internal SSD system. During 2014, work to mitigate the possibility of external flooding events uncovered the N and S external SSD outfalls. Both the north and south halves of the external SSD system drain toward the beach. No samples from the external SSD were obtained in 2015 because there was not flow. Table 14-5 2015 Unit 2 Facade SSD Sump H-3 (pCi/l) Date pCi/l 2 MDC 20-Jan 682 +/- 135 196 15-Feb 721 +/- 107 148 26-Mar 475 +/- 102 152 30-Apr 648 +/- 106 147 2-Jun 741 +/- 109 155 30-Jun 591 +/- 105 149 31-Aug 577 +/- 104 147 30-Sep 306 +/- 91 144 30-Oct 683 +/- 103 143 7-Dec 568 +/- 98 146 31-Dec 496 +/- 112 152 Average 590 +/- 128 In addition to H-3, the façade wells and internal SSD samples were gamma scanned. As in lake water samples, small positive values below their calculated, minimum detectable concentrations were found. 61
The isotopes in the SSD and façade wells were Fe-59, Co-58/60, Zr-Nb-95, Cs-137, and Ba-La-140. In the SSD, Mn-54, Fe-59, Co-60, Cs-137, and Ba-La-140 had small, positive values. There are no known inputs to the soil beneath the plant. Therefore, because the values were less than or equal to the MDC, it is concluded that these results are false positives. 14.5 Potable Water and Monitoring Wells Outside of the protected area, ten wells, in addition to the main plant well (Section 11.7), are used for monitoring H-3 in groundwater: the four potable water wells, GW-04 (Energy Information Center or EIC), GW-05 (Warehouse 6), GW-18 (Warehouse 7), GW-06 (Site Boundary Control Center), and six H-3 groundwater monitoring wells, GW-11 through GW-16 (Figure 13-1). The potable water wells monitor the deep, drinking water aquifer whereas the monitoring wells penetrate less than 30 feet to monitor the top soil layer. The potable water aquifer is separated from the shallow, surface water aquifer by a thick, impermeable clay layer. The potable water wells had no detectable H-3 (Table 14-6). Table 14-6 2015 Potable Well Water Tritium Concentration (pCi/l) EIC Warehouse SBCC GW-05, EIC WELL MDC 6 Well Well WH 7 06, 18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan ND 192 ND ND ND 165 Feb ND 142 Mar ND 147 Apr ND 147 ND ND ND 158 May ND 150 Jun ND 143 Jul ND 143 ND ND ND 154 Aug ND 145 Sep ND 147 Oct ND 141 ND ND ND 149 Nov ND 144 Dec ND 144 ND= not detected The monitoring well results are similar to that obtained in 2014. The two monitoring wells showing consistent, detectable H-3 (GW-15, GW-16) are in the flow path from the retention pond area to the lake (Table 14-7). The highest H-3 concentration occurs at GW-15, the well closest to the former unlined retention pond. However, considering the statistical uncertainty of the measurements, the results from GW-15 and GW-16 are the same. These two samples and those from the nearby surface water sample locations (GW-03, the east creek; GW-08, the bog to the SE of the former pond; and GW-17, the surface water on the SE corner of the STP) demonstrate that the area around and in the groundwater flow from the former retention pond remain impacted by the H-3 that diffused from the pond into the soil while it was in use. 62
Table 14-7 2015 Quarterly Monitoring Well Tritium (pCi/l) MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Q GW-11 GW-12 GW-13 GW-14 GW-15 GW-16 MDC 1 ND +/- NS +/- ND +/- ND +/- *131 +/- *105 147 +/- 106 196 2 ND +/- ND +/- ND +/- ND +/- ND +/- 186 +/- 81 159 3 130 +/- 82 ND +/- 159 +/- 83 139 +/- 82 284 +/- 89 199 +/- 85 143 4 108 +/- 76 NS +/- 134 +/- 77 91 +/- 75 187 +/- 80 179 +/- 80 141 ND= not statistically different from zero. NS = no sample available
*Duplicate samples taken. The other results was ND.
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. Results from precipitation analyses (2011 AMR) show that airborne H-3 concentrations are higher close to the plant as compared to results at the site boundaries. The observed tritium concentrations in the yard manholes can be explained by the higher H-3 in precipitation close to the plant. In addition to tritium captured by precipitation, the beach drains also receive the H-3 captured in the AC condensate because the condensate drainage is connected to the yard drain system. Tritium continues in the soil below the plant foundation as evidenced by results from the subsurface drainage system and from the façade wells. Except for the monitoring wells downstream from the former retention pond, the monitoring well tritium concentrations are not different from zero. These results conform to the known west-to-east groundwater flow at the site. Therefore, the impact of the flow of tritiated groundwater from the vicinity of the former retention pond toward the lake on beach drain S-3 tritium results as can not be discounted. The impact of this flow would be greater on beach drain S-3 than on S-1 because the eastward flow in the area of S-3 would be less impacted by plant structures than the drainage system feeding beach drain S-1. In conclusion, the groundwater H-3 concentrations observed at Point Beach are below the EPA drinking water standards prior to emptying into Lake Michigan where they will undergo further dilution. All analyses to date indicate that the drinking water contains no tritium. None of the H-3 in the upper soil layer is migrating off-site toward the surrounding population. This is based on the known west-to-east groundwater flow toward Lake Michigan and the negative results from the four wells (GW-11 through GW-14, Figure 13-1). Additionally, because no H-3 is detected in either of the four on-site drinking water wells close to the power block or from the drinking water well at the site boundary, none of the H-3 observed in the upper soil layer has penetrated into the drinking water aquifer to endanger either on-site or off-site personnel. 63
APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2015
(
~+L ATI EnvironmentaiSl Inco
'+~M.I Midwest laborat<<>>ry 700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517 FINAL REPORT TO NextEra 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 Reporting Period: January-December, 2015 Reviewed and Approved by --~--+---+~=h~~:;._,.~~~~ Date Distribution: K. Johansen, 1 hardcopy, 1 e-mail
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POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section Page List of Tables .... .. ... ... ... ............ .. ....... ........ ...................... .. ........ iii
1.0 INTRODUCTION
.. ...... ..... .. ...... .... .... ....... ... ...... .. .... .. ....... .......... iv 2.0 LISTING OF MISSED SAMPLES ......... .. .... .. ........... .... .... .. .... .. . v 3 DATA TABLES ............. ...... .. .... .. .. .. .. .... ....... .. ..... .. .... ............... vi Appendices A Interlaboratory Comparison Program Results .... .. ............ .. ...... A-1 B Data Reporting Conventions ....... .. .... .. .......... .. ... ........ .. ............ . B-1 C Sampling Program and Locations .. ..... .. .............. .. ................... C-1 D Graphs of Data Trends .. .. ...... .. ...... .... ..... .. .. .. ..... ........ .. ............ . D-1 E Supplemental Analyses .. .. .... ... .... ....... ... ............ .. ....... .. ..... .. .... . E-1 F Special Analyses .. ....... ... ... .. .... .. .... .. ...... ...... .... .. ......... F-1 ii
POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and lodine-131 Location E-01, Meteorological Tower .. ............ .. .. ... .............. ..... ...... 1-1 Location E-02, Site Boundary Control Center .. ... .. .. ........ ... ... .. ... .. . ... 1-2 Location E-03, West Boundary ....... ........... .. ... .. .. .... .. .. .. ... ... .. ... ... .. . 1-3 Location E-04, North Boundary ..... .. ... ... .. .... . ... .. .. .. ..... ..... ... ...... .. .... 1-4 Location E-08, G. J. Francar Residence.. ........ ................... ........... . 1-5 Location E-20, Silver Lake College ......... ..... .. .. .............. .. ... ... ......... 1-6 Airborne Particulates, Gamma Isotopic Analyses .. ..... ........ ... ......... .. .. ....... . 2-1 Milk......... .......... .. ...... ... .. .. ... ..... ... ... ...... .. .... .. ......... ..... .............. ........ ...... 3-1 Well Water .... .. ... .. .... .... .. ... . .. ... .. .... .. .. .. ... .. ... ... .. ......... .... .. .. ..... . .... .. .. .. .. .. . 4-1 Lake Water .. .. .. ...... .. ... ... .. ....... .. .. .. .. .. .... ... .. ... ...... ..... .. ........ ..... ... ... .. .. ... .. . 5-1 Lake Water, Analyses on Quarterly Composites ..... ................................... .. .. ... 6-1 Fish ....... ... ......... ..... ..... .......................... .. ..................... .... ....... .... .. ... .... ............ .. 7-1
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Shoreline Sediments ......... ............................................ ............. ...... .......... ... ..... 8-1 Soil ...... ....... ............................. ... ... ................ ............. ............................. .. ..... .. .. 9-1 Vegetation ......................... :.. ..................................... ..... ....... ............................. 10-1 Aquatic Vegetation ............................ ............ .... ..... .......... .................................. 11-1 Gamma Radiation, as Measured by TLDs .... ................................................... . 12-1 Groundwater Monitoring Program ................ ......... .... ...... .... ... ...... .. ................ .... 13-1
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POINT BEACH NUCLEAR PLANT
1.0 INTRODUCTION
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The following constitutes the final 2015 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, Tl-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. All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples. iv
POINT BEACH NUCLEAR PLANT ( 2.0 LISTING OF MISSED SAMPLES
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Expected Collection Sample Type Location Date Reason LW E-01 02-15-15 No sample due to icy conditions. LW E-05 02-15-15 No sample due to icy conditions. LW E-06 02-15-15 No sample due to icy conditions. LW E-33 02-15-15 No sample due to icy conditions. Algae E-05 06-10-15 No algae found Algae E-12 06-10-15 No algae found AP/AI E-01 07-01-15 Loss of power due to storms. Algae E-05 08-27-15 No algae found ( Algae E-05 10-07-15 No algae found Algae E-12 10-07-15 No algae found v
POINT BEACH NUCLEAR PLANT 3.0 Data Tables ./ vi
POINT BEACH NUCLEAR PLANT
/ Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
Location: E-01, Meteorological Tower 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 343 0.032 +/- 0.004 < 0.007 07-08-15 295 0.018 +/- 0.003 < 0.011 01 15 304 0.028 +/- 0.004 < 0.013 07-15-15 300 0.018 +/- 0.003 < 0.006 01-21-15 295 0.029 +/- 0.004 < 0.010 07-22-15 301 0.016 +/- 0.003 < 0.008 01-28-15 297 0.020 +/- 0.003 < 0.007 07-29-15 301 0.027 +/- 0.004 < 0.009 02-04-15 299 0.025 +/- 0.003 < 0.005 08-05-15 300 0.017 +/- 0.003 < 0.008 02-11-15 307 0.035 +/- 0.004 < 0.010 08-12-15 301 0.019 +/- 0.003 < 0.010 02r18-15 301 0.025 +/- 0.003 < 0.006 08-19-15 292 0.043 +/- 0.005 < 0.011 02-25-15 305 0.051 +/- 0.004 < 0.009 08-26-15 307 0.018 +/- 0.003 < 0.009 09-02-15 300 0.035 +/- 0:004 < 0.009 03-04-15 309 0.032 +/- 0.004 < 0.013 03-11-15 298 0.029 +/- 0.004 < 0.009 09-09-15 293 0.039 +/- 0.004 < 0.011 03-18-15 301 0.019 +/- 0.003 < 0.012 09-16-15 304 0.027 +/- 0.004 < 0.006 03-25-15 306 0.022 +/- 0.004 < 0.010 09-23-15 300 0.027 +/- 0.004 < 0.011 04-01-15 304 0.018 +/- 0.003 < 0.011 09-30-15 297 0.030 +/- 0.004 < 0.008 / 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.009 < 0.009 Mean+/- s.d. 0.026 +/- 0.009 < 0.009 04-08-15 311 0.024 +/- 0.003 < 0.006 10-07-15 302 0.015 +/- 0.003 < 0.006 04-15-15 298 0.020 +/- 0.003 < 0.014 10-14-15 302 0.023 +/- 0.004 < 0.008 04-22-15 296 0.013 +/- 0.003 < 0.009 10-21-15 296 0.027 +/- 0.004 < 0.007 04-29-15 306 0.014 +/- 0.003 < 0.010 10-28-15 305 0.024 +/- 0.004 < 0.005 05-06-15 300 0.015 +/- 0.003 < 0.012 11-04-15 308 0.020 +/- 0.003 < 0.008 05-13-15 300 0.012 +/- 0.003 < 0.010 11-11 -15 315 0.029 +/- 0.004 < 0.010 05-20-15 301 0.017 +/- 0.003 < 0.014 11-18-15 304 0.039 +/- 0.004 < 0.010 05-27-15 301 0.020 +/- 0.003 < 0.010 11-24-15 274 0.022 +/- 0.004 < 0.015 06-03-15 302 0.013 +/- 0.003 < 0.010 12-02-15 336 0.031 +/- 0.004 < 0.006 06-10-15 302 0.017 +/- 0.003 < 0.012 12-09-15 310 0.053 +/- 0.005 < 0.009 06-17-15 310 0.012 +/- 0.003 < 0.009 12-16-15 298 0.028 +/- 0.004 < 0.007 06-24-15 . 293 0.014 +/- 0.003 < 0.009 12-22-15 269 0.029 +/- 0.004 < 0.012/ 8 07-01 -15 ND 12-30-15 352 0.027 :!; 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.016 +/- 0.004 < 0.010 Mean+/- s.d. 0.028 +/- 0.009 < 0.009 Cumulative Average 0.025 +/- 0.009 < 0.009 a "NO" = No data; see Table 2.0, Listing of Missed Samples. 1-1
POINT BEACH NUCLEAR PLANT ( Table 1: Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 . Location: E-02, Site Boundary Control Center
' 3 Units: pCi/m Collection: Continuous, weekly exchange.
Date Vol. Date Vol. Collected (ma) Gross Beta 1-131 Collected (ma) Gross Beta 1-131 Required LLD 0.010 .Q,_@Q Required LLD 0.010 0.030 01 15 350 0.031 +/- 0.003 < 0.007 07-08-15 303 0.021 +/- 0.004 < 0.011 01-14-15 303 0.026 +/- 0.004 < 0.013 07-15-15 300 0.015 +/- 0.003 < 0.006 01-21 -15 287 0.032 +/- 0.004 < 0.011 07-22-15 299 0.019 +/- 0.003 < 0.008 01 15 306 0.022 +/- 0.003 < 0.007 07-29-15 303 0.030 +/- 0.004 < 0.009 02-04-15 310 0.024 +/- 0.003 < 0.005 08-05-15 298 0.019 +/- 0.003 < 0.008 02-11-15 307 0.032 +/- 0.004 < 0.010 08-12-15 305 0.019 +/- 0.003 < 0.010 02-18-15 310 0.028 +/- 0.004 < 0.006 08-19-15 304 0.038 +/- 0.004 < 0.010 02-25-15 323 0.054 +/- 0.004 < 0.008 08-26-15 295 0.015 +/- 0.003 < 0.010 09-02-15 295 0.039 +/- 0.004 < 0.009 03-04-15 307 0.031 +/- 0.004 < 0.013 03-11-15 303 0.020 +/- 0.004 < 0.009 09-09-15 303 0.040 +/- 0.004 < 0.010 03-18-15 303 0.020 +/- 0.004 < 0.012 09-16-15 310 0.026 +/- 0.004 < 0.006 03-25-15 305 0.019 +/- 0.004 < 0.010 09-23-15 296 0.028 +/- 0.004 < 0.011 04-01-15 306 0.018 +/- 0.003 < 0.011 09-30-15 298 0.036 +/- 0.004 < 0.008
/ 1st Quarter 3rd Quarter ' Mean+/- s.d. 0.027 +/- 0,009 < 0.009 Mean+/- s.d. 0.027 +/- 0.009 < 0.009 04-08..:15 305 0.021 +/- 0.003 < 0.006 10-07-15 297 0.016 +/- 0.003 < 0.006 04-15-15 305 0.018 +/- 0.003 < 0.014 10-14-15 296 0.029 +/- 0.004 < 0.008 04-22-15 290 0.012 +/- 0.003 < 0.009 10-21 -15 302 0.027 +/- 0.004 < 0.007 04-29-15 305 0.012 +/- 0.003 < 0.010 10-28-15 302 0.022 +/- 0.004 < 0.006 05-06-15 302 0.017 +/- 0.003 < 0.012 11 15 308 0.029 +/- 0.004 < 0.008 05-13-15 302 0.010 +/- 0.003 < 0.010 11-11-1 5 307 0.026 ::!: 0.004 < 0.010 05-20-15 297 0.013 +/- 0.003 < 0.015 11-18-15 297 0.041 +/- 0.004 < 0.010 05-27-15 297 0.022 +/- 0.003 < 0.010 11-24-15 264 0.022 +/- 0.004 < 0.016 06-03-15 300 0.014 +/- 0.003 < 0.010 12-02-15 343 0.034 +/- 0.004 < 0.006 06-10-15 300 0.021 +/- 0.003 < 0.012 12-09-15 306 0.053 +/- 0.005 < 0.009 06-17-15 304 0.009 +/- 0.003 < 0.009 12-16-15 299 0.030 +/- 0.004 < 0.007 06-24-15 294 0.014 +/- 0.003 < 0.009 12-22-15 260 ~.029 +/- 0.004 < 0.013 07-01-15 301 0.018 +/- 0.003 < 0.012 12-30-15 353 0.027 +/- 0.003 < 0.009 .
2nd Quarter 4th Quarter Mean+/- s.d. 0.016 +/-0.004 < 0.011 Mean+/- s.d. 0.029 +/- 0.009 . < 0.009 Cumulative Average 0.025 +/- 0.010 < 0.009 / 1-2
POINT BEACH NUCLEAR PLANT i
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Table 1. Airborne particulates and charcoal can isters, analyses for gross beta and iodine-131. Location: E-03, West Boundary 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reguired LLD 0.010 0.030 Reguired LLD 0.010 0.030 01-07-15 339 0.033 +/- 0.004 < 0.007 07-08-15 300 0.022 +/- 0.004 < 0.011 01-14-15 293 0.028 +/- 0.004 < 0.013 07-15-15 299 0.020 +/- 0.003 < 0.006 01-21-15 297 0.035 +/- 0.004 < 0.010 07-22-15 296 0.016 +/- 0.003 < 0.008 01-28-15 298 0.022 +/- 0.003 < 0.007 07~29 - 15 305 0.029 +/- 0.004 < 0.009 02-04-15 302 0.022 +/- 0.003 < 0.005 08-05-15 296 0.017:!; 0.003 < 0.008 02-11-15 310 0.034 +/- 0.004 < 0.009 08-12-15 302 0.016 +/- 0.003 < 0.010 02-18-15 300 0.031 +/- 0.004 < 0.006 08-19-15 213 0.051 +/- 0.006 < 0.015 02-25-15 305 0.052 +/- 0.004 < 0.009 08-26-15 306 0.015 +/- 0.003 < 0.009 09-02-15 289 0.034 +/- 0.004 < 0.009 03-04-15 306 0.030 +/- 0.004 < 0.013 03-11-15 299 0.026 +/- 0.004 < 0.009 09-09-15 300 0.051 +/- 0.005 < 0.011 03-18-15 299 0.020 +/- 0.004 < 0.012 09-16-15 302 0.027 +/- 0.004 < 0.006 03-25-15 299 0.024 +/- 0.004 < 0.010 09-23-15 304 0.031 +/- 0.004 < 0.011 04-01-15 307 0.016 +/- 0.003 < 0.011 09-30-15 295 0.036 +/- 0.004 < 0.008
/ 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.009 < 0.009 Mean+/- s.d. 0.028 +/- 0.012 < 0.009 04-08-15 308 0.022 +/- 0.003 < 0.006 10-07-15 305 0.015 +/- 0.003 < 0.006 04-15-15 297 0.017 +/- 0.003 < 0.014 10-14-15 297 0.023 +/- 0.004 < 0.008 04-22-15 286 0.010 +/- 0.003 < 0.009 10-21-15 302 0.025 +/- 0.004 < 0.007 04-29-15 304 0.013 +/- 0.003 < 0.010 10-28-15 302 0.023 +/- 0.004 < 0.006 05-06-15 303 0.014 +/- 0.003 < 0.01Z 11-04-15 302 0.030 +/- 0.004 < 0.008 05-13-15 303 0.010 +/- 0.003 < 0.010 11-11-15 310 0.030 +/- 0.004 < 0.010 05-20-15 301 0.014 +/- 0.003 < 0.014 11-18-15 298 0.036 +/- 0.004 < 0.010 05-27-15 301 0.017 +/- 0.003 < 0.010 11-24-15 263 0.020 +/- 0.004 < 0.016 06-03-15 304 0.013 +/- 0.003 < 0.010 12-02-15 336 0,031 +/- 0.004 < 0.006 06-10-15 304 0.019 +/- 0.003 < 0.012 12-09-15 302 0.057 +/- 0.005 < 0.009 06-17-15 294 0.013 +/- 0.003 < 0.009 12-16-15 300 0.028 +/- 0.004 < 0.007 06-24-15 294 0.012 +/- 0.003 < 0.009 12-22-15 264 /0.027 +/- 0.004 < 0.013 07-01-15 289 0.018 +/- 0.003 < 0.013 12-30-15 352 0.028 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.003 < 0.011 Mean+/- s.d. 0.029 +/- 0.010 < 0.009 Cumulative Averaf.le 0.025 +/- 0.011 < 0.010 a Low volume due to shut down for calibration. / ' * ~.
1-3
POINT BEACH NUCLEAR PLANT I Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
. Location: E-04, North Boundary 3
Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 QJ@ 01-07-15 345 0.033 +/- 0.004 < 0.007 07-08-15 305 0.019 +/- 0.003 < 0.011 01-14-15 305 0.040 +/- 0.004 < 0.013 07-15-15 301 0.018 +/- 0.003 < 0.006 01-21-15 300 0.028 +/- 0.004 < 0.010 07-22-15 295 0.018:!; 0.003 < 0.008 01-28-15 310 0.021 +/- 0.003 < 0.007 07-29-15 304 0.030 +/- 0.004 < 0.009 02-04-15 316 0.020 +/- 0.003 < 0.005 08-05-15 310 0.017 +/- 0.003 < 0.007 02-11-15 291 0.034 +/- 0.004 < 0.010 08-12-15 305 0.016 +/- 0.003 < 0.010 02-18-15 314 0.032 +/- 0.004 < 0.006 08-19-15 297 0.041 +/- 0.004 < 0.011 02-25-15 330 0.052 +/- 0.004 < 0.008 08-26-15 303 0.017 +/- 0.003 < 0.009 09-02-15 290 0.035 +/- 0.004 < 0.009 03-04-15 310 0.026 +/- 0.004 < 0.013 03-11-15 300 0.020 +/- 0.004 < 0.009 09-09-15 300 0.032 +/- 0.004 < 0.011 03-18-15 295 0.021 +/- 0.004 < 0.013 09-16-15 305 0.031 +/- 0.004 < 0.006 03-25-15 301 0.024 +/- 0.004 < 0.010 09-23-15 303 0.027 +/- 0.004 < 0.011 04-01-15 309 0.016 +/- 0.003 < 0.011 09-30-15 296 0.030 +/- 0.004 < 0.008 r 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.010 < 0.009 Mean+/- s.d. 0.025 +/- 0.088 < 0.009 04-08-15 308 0.022 +/- 0.003 < 0.006 10-07-15 309 0.012 +/- 0.003 < 0.006 04-15-15 302 0.018 +/- 0.003 < 0.014 10-14-15 300 0.024 +/- 0.004 < 0.008 04-22-15 293 0.011 +/- 0.003 < 0.009 10-21 -15 302 0.028 +/- 0.004 < 0.007 04-29-15 305 0.010 +/- 0.003 < 0.010 10-28-15 305 0.025 +/- 0.004 < 0.005 05-06-15 305 .-*- 0.016 +/- 0.003 < 0.012 11-04-15 302 0.025 +/- 0.004 < 0.008 05-13-15 305 0.011 :!;: 0.003 < 0.010 11-11-15 315 0.034 +/- 0.004 < 0.010 05-20-15 301 0.016 +/- 0.003 < 0.014 11-18-15 300 0.041 +/- 0.004 < 0.010 05-27-15 301 0.018 +/- 0.003 < 0.010 11-24-15 270 0.020 +/- 0.004 < 0.015 06-03-15 305 0.014 +/- 0.003 < 0.010 12-02-15 340 0.031 +/- 0.004 < 0.006 06-10-15 305 0.022 +/- 0,003 < 0.012 12-09-15 305 0.053 +/- 0.005 < 0.009 06-17-15 306 0.010 +/- 0.003 < 0.009 12-16-15 299 0.027 +/- 0.004 < 0.007 06-24-15 296 0.012 +/- 0.003 < 0.008 12-22-15 263 j0.028 +/- 0.004 < 0.013 07-01-15 307 0.017 +/- 0.003 < 0.012 12-30-15 358 0.025 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.004 < 0.010 Mean:!; s.d. 0.029 ::!: 0.010 < 0.009 Cumulative Average 0.024 +/- 0.010 < 0.009 1-4
POINT BEACH NUCLEAR PLANT
,.r Table 1. Airborne particulates and charcoal canisters, analy$es for gross beta and iodine-131.
Location: E-08, G.J. Francar Residence 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 340 0.034 +/- 0.004 < 0.007 07-08-15 298 0.020 +/- 0.003 < 0.011 01-14-15 306 0.030 +/- 0.004 < 0.013 07-15-15 302 0.017 +/- 0.003 < 0.006 01-21-15 298 0.032 +/- 0.004 < 0.010 07-22-15 304 0.021 +/- 0,003 < 0.008 01-28-15 306 0.021 +/- 0.003 < 0.007 07-29-15 311 0.028 +/- 0.004 < 0.009 02-04-15 313 0.023 +/- 0.003 < 0.005 08.05-15 307 0.018 +/- 0.003 < 0.008 02-11-15 295 0.033 +/- 0.004 < 0.010 08-12-15 269 0.024 +/- 0.004 < 0.011 02-18-15 299 0.027 :\: 0.004 < 0.006 08-19-15 285 0.037 ;!: 0.004 < 0.011 02-25-15 310 0.046 +/- 0.004 < 0.009 08-26-15 306 . 0 .014 +/- 0.003 < 0.009 09-02-15 289 0.039 +/- 0.004 < 0.009 03-04-15 306 0.029 +/- 0.004 < 0.013 03-11-15 300 0.026 +/- 0.004 < 0.009 09-09-15 303 0.039 +/- 0.004 < 0.010 03-18-15 303 0.020 +/- 0.004 < 0.012 09-16-15 307 0.027 +/- 0.004 < 0.006 03-25-15 304 0.026 +/- 0.004 < 0.010 09-23-15 298 0.034 +/- 0.004 < 0.011 04-01-15 304 0.016 +/- 0.003 < 0.011 09-30-15 299 0.033 +/- 0.004 < 0.008
/
1st Quarter 3rd Quarter
' Mean+/- s.d. 0.028 +/- 0.008 < 0.009 Mean+/- s.d. 0,027 ':!; 0,009 < 0.009 04-08-15 307 0.021 +/- 0.003 < 0.006 10-07-15 296 0.017 +/- 0.003 < 0.006 04-15-15 296 0.018 +/- 0.003 < 0.014 10-14-15 291 0.024 +/- 0.004 < 0.008 04-22-15 288 0.014 +/- 0.003 < 0.009 10-21-15 301 0.026 +/- 0.004 < 0.007 04-29-15 302 0.013 +/- 0.003 < 0.010 10-28-15 302 0.023 +/- 0.004 < 0.006 05-06-15 306 0.016 +/- 0.003 < 0.012 11-04-15 305 0.023 +/- 0.003 < 0.008 05-13-15 306 0.012 +/- 0.003 < 0.010 11-11-15 314 0.034 +/- 0.004 < 0.010 '
05-20-15 297 0.014 +/- 0.003 < 0.015 11-18-15 306 0.036 +/- 0.004 < 0.010 05-27-15 297 0.019 +/- 0.003 < 0.010 11-24-15 270 0.023 ;!: 0.004 < 0.015 06-03-15 303 0.015 +/- 0.003 < 0.010 12-02-15 344 0.030 +/- 0.004 < 0.006 06-10-15 303 0.018 +/- 0.003 < 0.012 12-09-15 307 0.053 +/- 0.005 < 0.009 06-17-15 312 0.010 +/- 0,003 < 0.009 12-16-15 293 0.029 +/- 0.004 < 0.007 06-24-15 296 0.012 +/- 0.003 < 0.008 12-22-15 271 !n.028 +/- 0.004 < 0.012 07-01-15 312 0.017 +/- 0.003 < 0.012 12-30-15 351 0.026 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.003 < 0.011 Mean+/- s.d. 0.029 l; 0.'009 < 0.009 Cumulative Average 0.025 +/- 0.009 < 0.009 Indicator Locations Annual Mean +/- s.d. 0.025 +/- 0.010 < 0.009
/
it ~* 1-5
POINT BEACH NUCLEAR PLANT
./ Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
Location : E-20, Silver Lake 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 347 0.035 +/- 0.004 < 0.007 07-08-15 299 0.020 +/- 0.003 < 0.011 01-14-15 345 0.027 +/- 0_003 < 0.011 07-15-15 299 0.018 +/- 0.003 < 0.006 01-21-15 299 0.031 +/- 0.004 < 0.010 07-22-15 300 0.020 +/- 0.003 < 0.008 01-28-15 300 0.020 +/- 0.003 < 0.007 07-29-15 301 0.030 +/- 0.004 < 0.009 02-04-15 306 0.024 +/- 0.003 < 0.005 08-05-15 311 0.018 +/- 0.003 < 0.007 02-11-15 296 0.038 +/- 0.004 < 0.010 08-12-15 301 0.020 +/- 0.003 < 0.010 02-18-15 306 0.029 +/- 0.004 < 0.006 08-19-15 283 0.044 +/- 0.005 < 0.011 02-25-15 319 0.035 +/- 0.004 < 0.008 08-26-15 306 0.015 +/- 0.003 < 0.009 09-02-15 289 0.033 +/- 0.004 < 0.009 03-04-15 310 0.030 +/- 0.004 < 0.013 03-11-15 295 0.022 +/- 0.004 < 0.009 09-09-15 311 0.034 +/- 0.004 < 0.010 03-18-15 298 0.023 +/- 0.004 < 0.012 09-16-15 307 0.025 +/- 0.004 < 0.006 03-25-15 300 0.021 +/- 0.004 < 0.010 09-23-15 302 0.023 :1; 0.003 < 0.011 04-01-15 309 0.014 +/- 0.003 < 0.011 09-30-15 298 o.o33 +/- o*: oo4 < 0.008
~* ../ ..;.
1st Quarter 3rd Quarter .' Mean+/- s.d. 0.027 +/- 0.007 < 0.009 Mean+/- s.d. 0.026 +/- 0.009 '< 0.009 04-08-15 307 0.022 +/- 0.003 < 0.006 10-07-15 309 *o.o13 +/- o.oo3 < 0.006 04-15-15 296 0.021 +/- 0.003 < 0.014 10-14-15 293 0.024 +/- 0.004 < 0.008
- 04:?2-15 285 0.011 +/- 0.003 < 0.009 10-21-15 299 0.027 +/- 0.004 < 0.007 ,
'\..
04~29-15 304 0.014 +/- 0.003 < 0.010 10-28-15 306 0.025 +/- 0.004 < 0.005 05-06-15 301 0.012 +/- 0.003 < 0.012 11-04-15 305 0.023 +/- 0.003 < 0.008 05-13-15 301 0.010 +/- 0.003 < 0.010 11-11-15 311 0.030 +/- 0.004 < 0.010 05-20-15 303 0.012 +/- 0.003 < 0.014 11-18-15 301 0.041 +/- 0.004 < 0.010 05-27-15 303 0.017 +/- 0.003 < 0.010 11-24-15 265 0.025 +/- 0.004 < 0.016 06-03-15 304 0.013 +/- 0.003 < 0.010 12-02-15 346 0.031 +/- 0.004 < 0.006 06-10-15 304 0.017 +/- 0.003 < 0.012 12-09-15 301 0.057 +/- 0.005 < 0.009 06-17-15 313 0.010 +/- 0.003 < 0.009 12-16-15 299 0.031 +/- 0.004 < 0.007 06-24-15 296 0.014 +/- 0.003 < 0.008 12-22-15 264 /0.030 +/- 0.004 < 0.013 07-01-15 309 0.016 :!: 0.003 < 0.012 12-30-15 349 0.027 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. O.Of5 +/- 0.004 < 0.010 Mean+/- s.d. 0.029 +/- 0.010 < 0.009 Cumulative Average 0.024 +/- 0.009 < 0.009 Control Annual Mean +/- s.d. 0.024 +/- 0.009 < 0.009 I' 1-6
POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pCi/m 3 (Other) (Other) Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co-60) Volume Req . LLD MDC 0.01 MDC 0.01 MDC ( 0.10) MDC m3 1st Quarter E-01 EAP- 1903 0.074 +/- 0.015 0.0000 +/- 0.0004 < 0.0005 0.0002 +/- 0.0004 < 0.0006 -0 .0002 +/- 0.0007 < 0.0007 3970 E-02 - 1904 vd.084 +/- 0.017 -0.0003 +/- 0.0004 < 0.0008 0.0002 +/- 0.0005 < 0.0008 -0.0001 +/- 0.0006 < 0.0007 4020 E-03 - 1905 0.058 +/- 0.015 0.0000 +/- 0.0004 < 0.0007 0.0001 +/- 0.0006 < 0.0010 0.0003 +/- 0.0005 < 0.0007 3953 E-04 - 1906 0.061 +/- 0.020 -0.0004 +/- 0.0005 < 0.0009 -0.0001 +/- 0.0005 < 0.0007 -0.0001 +/- 0.0007 < 0.0008 4025 E-08 - 1907 0.061 +/- 0.017 0.0003 +/- 0.0004 < 0.0008 0.0003 +/- 0.0005 < 0.0009 -0 .0001 +/- 0.0005 < 0.0007 3983 E-20 - 1908 0.063 +/- 0.014 0.0004 + 0.0004 < 0.0007 0.0000 + 0.0005 < 0.0008 -0 0001 + 0.0006 < 0.0007 4030 2nd Quarter E-01 EAP- 3960 0.069 +/- 0.018 0.0000 +/- 0.0004 < 0.0009 -0.0004 +/- 0.0006 < 0.0008 0.0001 +/- 0.0006 < 0.0004 3620 E-02 - 3961 0.065 +/- 0.014 -0.0003 +/- 0.0005 < 0.0009 -0 .0004 +/- 0.0006 < 0.0007 0.0004 +/- 0.0005 < 0.0008 3901 E-03 - 3962 0.066 +/- 0.012 -0.0001 +/- 0.0004 < 0.0008 >C(ooo7 +/- o.ooo6 < 0.0010 -0.0002 +/- 0.0005 < 0.0005 3888 E-04 - 3963 0.064 +/- 0.014 0.0001 +/- 0.0005 < 0.0007 -0.0002 +/- 0.0006 < 0.0006 -0.0008 +/- 0.0006 < 0.0004 3937 E-08 - 3964 0.062 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0004 < 0.0005 -0.0003 +/- 0.0004 < 0.0004 3925 E-20 - 3965 0.066 +/- 0.013 0.0000 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0005 < 0.0006 0.0000 +/- 0.0006 < 0.0005 3927 3rd Quarter E-01 EAP- 5991 0.076 +/- 0.015 -0.0003 +/- 0.0006 < 0.0009 0.0002 +/- 0.0006 < 0.0007 vb.0006 +/- 0.0005 < 0.0005 3892 E-02 - 5992 0.068 +/- 0.016 -0.0002 +/- 0.0005 < 0.0010 0.0000 +/- 0.0006 < 0.0010 0.0001 +/- 0.0006 < 0.0007 3910 E-03 - 5993 0.083 +/- 0.015 -0.0002 +/- 0.0005 < 0.0009 -0.0002 +/- 0.0005 < 0.0007 0.0006 +/- 0.0006 < 0.0006 3805 E-04 - 5994 0.071 +/- 0.016 0.0000 +/- 0.0006 < 0.0010 0.0000 +/- 0.0007 < 0.0010 0.0002 +/- 0.0006 < 0.0006 3914 E-08 - 5995 0.080 +/- 0.015 -0.0003 +/- 0.0005 < 0.0011 0.0001 +/- 0.0006 < 0.0010 -0.0009 +/- 0.0006 < 0.0005 3878 E-20 - 5996 o.o71 +/- o.o13V - 0.0001 +/- 0.0003 < 0.0006 Vb .0004 +/- 0.0003' < 0.0006 -0.0003 +/- 0.0003 < 0.0003 3906 4th Quarter E-01 EAP- 7361 0.050 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 0.0000 +/- 0.0004 < 0.0006 0.0000 +/- 0.0004 < 0.0004 3969 E-02 - 7362 0.056 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0004 < 0.0006 0.0001 +/- 0.0003 < 0.0003 3934 E-03 - 7363 0.050 +/- 0.014 -0 .0001 +/- 0.0005 < 0.0010 p6.0007 +/- 0.0006 < 0.0011 -0.0001 +/- 0.0005 < 0.0006 3931 E-04 - 7364 0.047 +/- 0.009 0.0002 +/- 0.0003 < 0.0007 0.0000 +/- 0.0004 < 0.0005 ..e.0004 +/- 0.0003 < 0.0003 3969 E-08 - 7365 0.041 +/- 0.010 v'- -0.0001 +/- 0.0003 < 0.0006 -0 .0003 +/- 0.0003 < 0.0004 -0.0003 +/- 0.0004 < 0.0003 3950 E-20 - 7366 0.059 + 0.015 - -0.0002 + 0.0004 < 0.0007 -0.0003 + 0.0005 < 0.0005 -0.0003 + 0.0006 < 0.0003 3948/ Annual Mean+/-s.d. 0.064 +/- 0.011 *0.0001 +/- 0.0002 < 0.0008 0.0000 +/- 0.0003 < 0.0007 0.0000 +/- 0.0004 < 0.0005 2-1
POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dail}' Farm MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 113 EMI- 540 EMI- 966 Sr-89 0.9 +/- 0.9 / < 0.7 0.2 +/- 0.7 < 0.6 0.2 +/- 0.7 < 0.7 5.0
,.,. 0.8 +/- 0.3 /
Sr-90 1.3 +/- 0.4 < 0.6 0.9 +/- 0.3 < 0.4 < 0.5 1.0 1-131 0.05 +/- 0.15 < 0.26 -0.02 +/- 0.10 < 0.19 -0.11 +/- 0.12 < 0.23 0.5 K-40 1294 +/- 103 1438 +/- 51 1394 +/- 97 Cs-134 2.1 +/- 1.7 < 3.8 -0.2 +/- 0.7 < 1.5 -1.1 +/- 1.5 < 3.0 5.0 Cs-137 2.2 +/- 2.1 < 3.9 0.6 +/- 0.8 < 1.7 -0.2 +/- 2.0 < 2.9 5.0 Ba-La-140 -2.7 +/- 1.6 < 4.7 0.5 +/- 0.7 < 3.1 1.3 +/- 1.8 < 4.2 5.0 Other (Co-60) 2.5 +/- 2.2 < 3.2 0.7 +/- 0.9 < 1.5 0.1 +/- 1.8 < 2.4 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD Lab Code EMI- 1465 EMI- 2376 EMI- 2905 Sr-89 0.0 +/- 0.8 < 0.8 -0.3 +/- 0.9 / < 0.8 0.3 +/- 0.8 < 0.7 5.0 Sr-90 0.8 +/- 0.3 / < 0.5 1.0 +/- 0.4 < 0.7 0.7 +/- 0.3 / < 0.5 1.0 1-131 0.19 +/- 0.24 - < 0.46 -0.06 +/- 0.15 < 0.28 -0.02 +/- 0.18 < 0.32 0.5 K-40 1472 +/- 75 1418 +/- 77 1389 +/- 95 Cs-134 0.3 +/- 1.3 < 2.4 0.2 +/- 1.4 < 2.4 -1.1 +/- 1.6 < 2.8 5.0 Cs-137 0.7 +/- 1.4 < 3.0 -0.4 +/- 1.5 < 1.9 0.4 +/- 2.0 < 3.6 5.0 Ba-La-140 -1 .1 +/- 1.3 < 2.2 2.7 +/- 1.2 < 4.5 1.3 +/- 1.7 < 2.6 5.0 Other (Co-60) -1.1 +/- 1.5 < 2.4 1.0 +/- 1.4 < 2.2 0.5 +/- 1.8 < 2.5 15.0 3-1
P01NT BEACH NUCLEAR PLANT I Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dai!Y Farm MDC MDC MDC Required Collection Date o7-08-1o 08-12-15 09-09-15 LLD Lab Code EMI- 3501 EMI- 4449 EMI- 4914 Sr-89 0.1 +/- 0.6 < 0.7 0.3 +/- 0.8 < 0.7 0.3 +/- 0.8 < 0.7 5.0 Sr-90 0.5 +/- 0.3 < 0.5 0.8 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.6 1.0 1-131 0.04+/-0.16 < 0.28 0.04 +/- 0.21 < 0.44 -0.03 +/- 0.11 < 0.20 0.5 K-40 1496 +/- 106 1388 +/- 41 1388 +/- 126 Cs-134 -0.6 :1; 1.6 < 2.9 -0.9 +/- 0.7 <1.4 0.5 +/- 1.8 < 3.8 5.0 Cs-137 2.3 +/- 2.1 < 3.1 0.2 +/- 0.8 < 1.7 2.2 +/- 2.3 < 4.4 5.0 Ba-La-140 -0.3 +/- 1.6 < 1.2 -2.9 +/- 0.6 < 2.8 2.6 +/- 2.1 < 3.8 5.0 Other (Co-60) 3.0 +/- 1.9 < 2.8
- 0.1 +/- 0.8 < 1.0 0.3 +/- 2.4 < 3.3 15.0 Required Collection Date 10-14-15 11-11-15 12-09-15 LLD Lab Code EMI- 5781 EMI- 6482 EMI- 6910
/
{ Sr-89 0.1 +/-0.8 < 0.7 0.5 +/- 0.6 < 0.7 -0.2 +/- 0.8/ < 0.8 5.0
'* Sr-90 1.0 +/- 0.3 < 0.5 0.6 +/- 0.3 < 0.4 0.8 +/- 0.4 < 0.6 1.0 1-131 0.16 +/- 0.19 < 0.32 0.05 +/- 0.11 < 0.20 -0.15 +/- 0.19 < 0.30 0.5 K-40 1250 +/- 109 1376 +/- 42 1366 +/- 105 Cs-134 -0.6 +/- 1.9 < 3.5 0.1 +/- 0.7 < 1.3 0.5 +/- 1.8 < 3.4 5.0 Cs-137 -0.2 +/- -2.2 < 3.8 -0.1 +/- 0.8 < 1.6 0.1 +/- 2.0 < 2.4 5.0 Ba-La-140 0.5 +/- 1.5 < 3.4 -2.5 +/- 0.7 < 2.0 0.3 +/- 1.6 < 3.2 5.0 Other (Co-60) 2.5 +/- 1.8 < 1.8 0.2 +/- 0.9 < 1.5 ' -0.4 +/- 2.0 < 2.2 15.0 I
3-2
POINT BEACH NUCLEAR PLANT
/
Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E721 Strutz Dai!Y Farm MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 114 EMI- 541 EMI* 967 Sr-89 0.5 +/- 0.7 < 0.8 0.0 +/- 0.6 < 0.7 0.6 :1: 0.8 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.6 0.2:!; 0.3 < 0.5 0.4 +/- 0.3 < 0.6 1.0 1-131 0.14 +/- 0.15 < 0.25 0.12 +/- 0.20 < 0.40 -0.13 +/- 0.11 < 0.22 0.5 K-40 1458 +/- 101 1426 +/- 76 1479 +/- 92 Cs-134 0.7 +/- 1.6 < 2.9 r2.0 +/- 1.2 < 2.5 0.1 :!: 1.6 < 2.7 5.0 Cs-137 2.0:!; 1.9 < 3.2 0.5 +/- 1.5 < 2.1 0.5 +/- 1.8 < 3.2 5.0 Ba-La-140 2.5 +/- 1.3 < 2.2 . -2.3 +/- 1.4 < 3.8 0.1 +/- 1.6 < 1.8 5.0 Other (Co-60) -0.1 +/- 1.9 < 2.6 -0.2 +/- 1.5 < 2.6 1.9 +/- 2.0 < 2.3 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD Lab Code EMI- 1466 EMI- 2377 EMI- 2906
/ '* Sr-89 0.6 :;1: 0.7 < 0.8 0.4 +/- 0.7 < 0.8 0.2 +/- 0.7 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.1 +/- 0.3 < 0.6 0.2 +/- 0.3 < 0.6 1.0 1-131 0.16 +/- 0.16 < 0.28 0.03 +/- 0.15 < 0.27 0.10 +/- 0.18 < 0.31 0.5 K-40 1360:!: 76 1463 +/- 102 1454;!: 98 Cs-134 1.4 :t 1.3 < 2.5 0.0 +/- 1.6 < 2.8 0.8;!: 1.6 < 3.3 5.0 Cs-137 1.6 +/- 1.5 < 3.0 1.0 +/- 2.1 < 3.0 1.0:!: 2.0 < 2.9 5.0 Ba-La-140 -4.1 +/- 1.3 < 2.1 -3.6 +/- 1.7 < 2.9 -4.3 +/- 1.5 < 2.6 5.0 Other (Co-60) 0.9 +/- 1.6 < .2.5 -0.7 +/- 2.0 < 1.8 -0.5 +/- 2.0 < 2.6 15.0 3-3
POINT BEACH NUCLEAR PLANT
/ Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)
E-21 Strutz Dai!Y Farm MDC MDC MDC Required Collection Date 07-08-15 08-12-15 09-09-15 LLD Lab Code EMI- 3502 EMI- 4450 EMI- 4915 Sr-89 0.3 +/- 0.7 < 0.7 0.6 +/- 0.8 < 0.9 0.3 +/- 0.7 < 0.8 5.0 Sr-90 0.5:!: 0.3 < 0.5 0.4 +/- 0.3 < 0.6 0.2 ;t 0.3 < 0.5 1.0 1-131 0.15 +/- 0.19 < 0.33 0.17 +/- 0.23 < 0.46 0.03+/-0.10 < 0.18 0.5 K-40 1403 +/- 97 1481 +/- 43 1298 +/- 107 Cs-134 0.1 +/- 1.9 < 3.5 -0.2 +/- 0.7 <1.4 0.1 +/- 1:7 < 3.4 5.0 Cs-137 1.9 +/- 1.8 < 3.5 -0.1 +/- 0.8 < 1.2 0.5 +/- 2.4 < 3.5 5.0 Ba-La-140 -0.2 +/- 1.6 < 2.4 -3.4 +/- 0.7 < 4.2 -1.9 +/- 1.8 < 1.7 5.0 Other (Co-60) -1 .6 +/- 2.0 < 2.2 -0.2 +/- 0.9 < 1.8 0.4 +/- 2.4 < 3.3 15.0 Required Collection Date 10-14-15 11-11-15 12-09-15 LLD
/ Lab Code EMI- 5762 EMI- 6483 EMI- 6911 ., -0.3 +/- 0.7 < 0.8 0.2 +/- 0.5 < 0.7 Sr-89 -0.1 :1: 0.6 / < 0.8 5.0 Sr-90 0.4 +/- 0.3 < 0.6 0.1 +/- 0.2 < 0.4 0.2 +/- 0.3 < 0.5 1.0 1-131 0.19 +/- 0.20 < 0.35 -0.01 +/- 0.19 < 0.42 0.18 ;1: 0.18 < 0.31 0.5 K-40 1323 +/- 112 1468 +/- 41 1459 +/- 104 Cs-134 -0.7 +/- 1.9 <* 3.6 -1 .1 +/- 0.7 < 1.2 0.4 +/- 1.8 < 3.7 5.0 Cs-137 -0.2 +/- 2.2 < 3.8 0.0;!: 0.8 < 1.0 0.6 +/- 1.8 < 3.4 5.0 Ba-La-140 -1.2 +/- 1.5 < 3.1 -0.1 +/- 0.7 < 2.9 -1 .0 +/- 1.5 / < 5.2 5.0 Olher (Co-60) -0.4 +/- 2.1 < 3.1 -0.4 +/- 0.8 < 1.2 2.1 :!: 2.1 < 1.9 15.0
( 3-4
POINT BEACH NUCLEAR PLANT
/ Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)
E-40 Barta MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 115 EMI- 542 EMI- 968 sr-89 -0.7:!; 0.6 < 0.6 -0.2 +/- 0.6 < 0.6 0.2 +/- 0.7 < 0.7 5.0 Sr-90 0.7 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.4 0.5 +/- 0.3 < 0.5 1.0 1-131 -0.01 +/- 0.20 < 0.41 0.05 +/- 0..10 < 0.17 0.02 +/- 0.12 < 0.21 0.5 K-40 1329 +/- 77 1471 +/- 76 1421 +/- 81 Cs-134 0.7 +/- 1.3 < 2.2 0.4 +/- 1.3 < 2.6 1.1 +/- 1.5 < 2.4 5.0 Cs-137 -1 .3 +/- 1.4 < 1.7 1.3:!; 1.5 < 2.7 1.6 +/- 1.6 < 2.7 5.0 Ba-La-140 -0.2 +/- 1.1 < 3.6 -1.7 +/- 1.2 < 5.3 -3.1 +/- 1.2 < 0.9 5.0 Other (Co-60) 1.7 +/- 1.7 < 2.9 1.2 +/- 1.5 < 2.5 0.6 +/- 1.8 < 2.5 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD
/ Lab Code EMI- 1467 EMI- 2378 EMI- 2907 ., -0.2;!: 0.9 < 0.9 -0.8 +/- 0.7 < 0.7 Sr-89 -0.4:!: 0.7 / < 0.7 5.0 Sr-90 0.6 +/- 0.4 < 0.6 0.9;!: 0.3 < 0.5 0.5 :1: 0.3 < 0.5 1.0 1-131 0.15;!; 0.25 < 0.48 -0.06 +/- 0.17 < 0.31 0.14 :I; 0.22 < 0.38 0.5 K-40 1419 +/- 93 1424 +/- 84 1447 +/- 68 Cs-134 0.1 +/- 1.7 < 3.0 -0.6 +/- 1.4 < 2.9 -1 .0 +/- 1.2 < 2.3 5.0 Cs-137 0.8;!; 1.8 < 3.2 1.8 +/- 1.6 < 2.9 0.1 +/- 1.3 < 2.3 5.0 Ba-La-140 0.5 +/- 1.6 < 4.1 0.6;!: 1.2 < 2.4 0.2 :1: 1.0 < 2.8 5.0 Other (Co-60) -1.1 ;!; 1.9 < 3.0 -0.2;!; 1.7 < 2.9 0.1 +/- 1.3 < 2.3 15.0
( 3-5
POINT BEACH NUCLEAR PLANT ~ Table 3. Radioactivity in milk samples Collection : Monthly Sample Description and Concentration (pCi/L) E-40 Barta MDC MDC MD C Required Collection Date 07-08-15 08-12-15 09-09-15 LLD Lab Code EMI- 3503 EMI- 4451 EMI- 4916 Sr-89 -0.1 +/- 0.6 < 0.6 -0.8 +/- 0.8 < 0.8 0.3 +/- 0.9 < 0.9 5.0 Sr-90 0.4 +/- 0.3 < 0.4 0.6 +/- 0.4 < 0.6 0.4 +/- 0.4 < 0.7 1.0 1-131 0.07 +/- 0.13 < 0.19 0.08 +/- 0.13 < 0.22 -0.13 +/- 0.21 < 0.39 0.5 K-40 1360 +/- 104 1445 +/- 39 1383 +/- 112 Cs-134 0.2 +/- 1.8 < 3.7 -0.4 +/- 0.7 < 1.2 0.5 +/- 1.8 < 3.8 5.0 Cs-137 -1 .0 +/- 2.1 < 2.9 0.6 +/- 0.8 < 1.5 -0.1 +/- 2.6 < 3.8 5.0 Ba-La-140 -0.1 +/- 1.7 < 2.1 -0.9 +/- 0.6 < 2.1 -1 .9 +/- 2.1 < 2.3 5.0 Other (Co-60) -1.1 +/- 2.2 < 1.8 -0.5 +/- 0.8 < 0.8 0.8 +/- 2.4 < 3.1 15.0 Required Collection Date 10-14-15 11 15 12-09-15 LLD Lab Code EM I- 5783 EMI- 6484 EMI- 6912 Sr-89 -0.1 +/- 0.6 < 0.1 0.0 +/- 0.6 < 0.9 -0.2 +/- 0.6 < 0.6 5.0 Sr-90 0.6 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.4 1.0 1-131 0.07+/-0.13 < 0.23 0.14 +/- 0.18 < 0.31 -0.07 +/- 0.16 < 0.30 0.5 K-40 1431 +/- 99 1384 +/- 82 1486 +/- 96 Cs-134 -1.4 +/- 1.8 < 3.4 0.6 +/- 1.3 < 2.5 -0.4 +/- 1.6 < 3.1 5.0 Cs-137 -0.6 +/- 1.9 < 3.0 1.2 +/- 1.4 < 2.2 0.7 +/- 1.9 < 3.5 5.0 Ba-La-140 -1 .8 +/- 1.6 < 3.0 -0.6 +/- 1.2 < 4.6 1.9 +/- 1.4 < 2.1 5.0 Other (Co-60) 1.0 +/- 1.9 < 2.4 0.3 +/- 1.5 < 1.7 0.2 +/- 1.8 < 2.9 15.0 Sr-89 An nual Mean + s.d. 0.1 +/- 0.4 Sr-90 Annual Mean + s.d. 0.6 +/- 0.3 1-131 Annual Mean+ s.d. 0.05 +/- 0. 10 K-40 Annual Mean+ s.d. 1409 +/- 60 Cs-134 Annual Mean+ s.d. 0.0 +/- 0.8 Cs-137 Annual Mean + s.d. 0.6 +/- 0.9 Ba-La Annual Mean + s.d. -0.8 +/- 1.9 Co-60 Annual Mean+ s.d. 0.4 +/- 1.1 3-6
POINT BEACH NUCLEAR PLANT
/ Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly
' Units: pCi/L 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean +/-s.d Collection Date 01-15-15 04-15-15 07-09-15 10-07-15 Lab Code EWW- 140 EWW- 1664 EWW- 3618 EWW- 5625 Gross Beta 2.9 +/- 1.7 0.2 +/- 0.9 2.4 +/- 1.9 0.7 +/- 1.0 4.0 1.6 +/- 1.3 H-3 103.9 +/- 99.7 57.5 :t 78.4 -52.0 +/- 91.1 -49.2 +/- 70.8 500 15.1 +/- 78.1 Sr-89 0.0 +/- 0.6 -1.5 +/- 0.7 0.2 +/- 0.3 0.2 :1:0.3 5.0 -0.3 +/- 0.8 Sr-90 0.0 +/- 0.2 0.9 +/- 0.3 -0.1 +/- 0.2 -0.1 +/- 0.2 1.0 0.2 +/- 0.5 1-131 0.07 +/- 0.13 -0.03 +/- 0.13 0.22 +/- 0.24 0.08 :t 0.13 0.5 0.09 +/- 0.10 Mn-54 -0.4 +/- 1.3 -0.3 +/- 1.5 1.2 +/- 2.1 -0.7 +/- 1.7 10 0.0 +/- 0.9 Fe-59 0.1 +/- 2.4 -2.9 +/- 2.9 1.4 +/- 3.8 -0.7 +/- 3.5 30 -0.5 +/- 1.8 Co-58 -1.3 +/- 1.3 0.3 +/- 1.5 -1.0+/-2.1 1.0 +/- 1.5 10 -0.2 +/- 1.1 Co-60 -0.7 +/- 1.4 -0.4 +/- 1.6 1.6 +/- 2.0 0.4 +/- 1.5 10 0.2 +/- 1.0 Zn-65 0.2 +/- 2.6 0.3 +/- 3.2 -7.5 +/- 4.5 -4.0 +/- 3.4 30 -2.8 +/- 3.7 Zr-Nb-95 -0.6 +/- 1.6 -2.6 +/- 1.7 -3.3 +/- 2.3 -0.8 +/- 1.8 15 -1.8 +/- 1.3 Cs-134 0.5 +/- 1.4 1.0 +/- 1.4 -1.0 +/- 1.9 0.2 +/- 1.7 10 0.2 +/- 0.8 Cs-137 -0.2 +/- 1.6 1.8 +/- 1.8 0.5 +/- 2.5 0.2 +/- Hl 10 0.6 +/- 0.9 Ba-La-140 1.2 +/- 1.6 -1.4 +/- 2.0 0.2 +/- 3.2 3.1 +/- 1.7 15 0.8 +/- 1.9
/
Other (R!J-103) 1.2 +/- 1.4 -0.8 +/- 1.4 -1.2 +/- 2.4 0.1 +/- 2.0 30 -0.2 +/- 1.1 MDC Data Collection Date 01-15-15 04-15-15 07-09-15 10-07-15 Lab Code EWW- 140 EWW- 1664 EWW- 3618 EWW- 5625 Gross Beta < 2.8 < 1.7 < 3.6 < 2.0 4.0 < 2.5 H-3 < 187.6 <151.9 < 153.9 < 148.7 500 < 160.5 Sr-89 < 0.8 < 0.6 < 0.5 < 0.4 5.0 < 0.6 Sr-90 < 0.5 < 0.5 < 0.4 < 0.5 1.0 < 0.5 1-131 < 0.22 < 0.23 < 0.45 < 0.22 0.5 <0.28 Mn-54 < 2.6 < 2.8 < 3.4 < 3.1 10 < 2.9 Fe-59 < 4.4 < 4.2 < 6.2 < 6.4 30 < 5.3 Co-58 < 1.7 < 2.6 < 2.5 < 2.0 10 < 2.2 Co-60 < 1.2 < 2.2 < 2.7 < 2.6 10 < 2.2 Zn-65 < 4.3 < 5.5 < 5.2 < 3.2 30 <4.6 Zr-Nb-95 < 3.6 < 2.5 < 5.1 < 3.7 15 < .3.7 Cs-134 < 2.7 < 2.7 < 4.2 < 3.6 10 < 3.3 Cs-137 < 2.3 < 3.1 < 4.2 < 3.5 10 < 3.3 Ba-La-140 < 6.1 < 3.5 < 4.2 < 4.2 15 <4.5 O~her (Ru-1 03) < 3.7 < 3.3 < 4.7 < 3.8 30 < 3.9 .,I 4-1
POINT BEACH Table 5. L,ake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-01 (Meteorological Tower) r-* Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 136 NSa ELW- 988 ELW- 1660 Date Collected 01-15-15 02-15-15 03-11-15 04-16-15 Req.LLD Gross beta 2.2 +/- 0.8 < 1.3 3.5 +/- 1.1 < 1.8 2.4 +/- 0.7 < 0.9 4.0 1-131 0.05 +/- 0.13 < 0,23 -0.04 +/- 0.22 < 0.49 -0.07 +/- 0.12 < 0.22 0.5 Be-7 4.2 +/- 15.8 < 32.8 7.9 +/- 13.3 < 32.6 -4.4 +/- 14.8 < 20.6 Mn-54 0.1 +/- 1.4 < 2.5 0.4 +/- 1.2 < 2.5 -0.5 +/- 1.5 < 2.2 10 Fe-59 0.9 +/- 3.0 < 5.0 0.1 +/- 2.7 < 2.7 -4.2 +/- 3.3 < 2.7 30 Co-58 0.1 +/- 1.4 < 1.9 0.3 +/- 1.3 < 2.4 0.2 +/- 1.4 < 2.5 10 Co-60 0.8 +/- 1.6 < 2.3 1.0 +/- 1.3 < 1.7 -1 .2 +/- 1.7 < 1.7 10 Zn-65 -2.3 +/- 3.2 < 3.3 -1.6 +/- 2.7 < 3.9 -1.9 +/- 4.3 < 6.9 30 Zr-Nb-95 -0.5 +/- 1.4 < 3.2 -0.2 ;!: 1.4 < 3.5 1.8 +/- 1.6 < 3.0 15 Cs-134 0.4 +/- 1.6 < 3.1 0.1 +/- 1.2 < 2.5 .0.6 +/- 1.6 < 3.1 10 Cs-137 -1.9 ;t 1.8 < 1.6 0.1 +/- 1.6 < 2.6 0.4 +/- 1.9 < 3.6 10 Ba-La-140 -2.5 +/- 2.1 < 6.3 -4.3 +/- 1.5 < 5.7 0.4 +/- 2.0 < 4.3 15 Other (Ru-1 03) -1.7 +/- 1.8 < 3.0 -0.3 +/- 1.5 < 3.8 -0.9 +/- 1.7 < 2.6 30 Lab Code ELW- 2422 ELW- 2935 ELW- 3614 E;:LW- 4480 Date Collected 05-14-15 06-11 -15 07-09-15 08-13-15 Req. LLD Gross beta 1.1 +/- 0.5 .:: 0.8 1.0 +/- 0.5 < 0.9 1.2 +/- 0.9 < 1.6 1.1 +/- 0.5 < 0.9 4.0 1-131 -0.07 +/- 0.13 < 0.24 0.15 +/- 0.19 < 0.35 -0.05 +/- 0.16 < 0.29 0.03 +/- 0.15 < 0.26 0.5 Be-7 -1.7+/-5.9 < 13.1 -5.7 +/- 20.1 < 33.7 -9.5 +/- 12.2 < 29.5 -11 .0 +/- 19.0 < 30.5 Mn-54 -0.1 +/- 0.6 < 0.9 1.3 +/- 2.0 < 4.0 -1.0 +/- 1.6 < 1.6 -0.9 +/- 2.0 < 3.0 10 Fe-59 -0.4 +/- 1.2 < 2.8 -2.6 +/- 4.1 < 5.0 -2.2 +/- 3.3 < 4.2 -3.5 +/- 3.7 < 3.3 30 Co-58 -0.7 +/- 0.6 < 0.8 -0.4 +/- 2.0 < 3.1 1.0 +/- 1.7 < 2.9 -1.0 +/- 1.9 < 2.5 10 Co-60 -0.5 +/- 0.6 < 1.2 -2.1 +/-1.9 < 1.7 0.6 +/- 1.7 < 1.5 2.1 +/- 2.2 < 3.8 10 I Zn-65 0.1 +/- 1.2 < 2.0 -0.2 +/- 4.3 < 6.8 0.1 ;!: 3.1 < 4.8 -1,6 +/- 4.8 < 4.0 30
' Zr-Nb-95 0.0 +/- 0.6 <1.4 2.4 +/- 2.0 < 3.3 2.9 +/- 1.6 < 3.9 -0.7 +/- 1.9 < 3.3 15 Cs-134 -0.2 +/- 0.7 <1.4 0.9 +/- 2.0 < 4.2 -1 .2 +/- 1.6 < 2.7 0.7 +/- 2 .1 < 4.3 10 Cs-137 0.2 +/- 0.7 < 1.3 -0.5 +/- 2.4 < 3.5 0.1 +/- 1.8 < 2.7 0.5 +/- 2.0 < 3.5 10 Ba-La-140 0.0 +/- 0.7 < 3.3 0.9 +/- 3.1 < 4.5 0.9 +/- 1.8 < 5.7 0.8 +/- 2.1 < 3.6 15 Other (Ru-1 03) -0.2 +/- 0.7 <1.4 1.1 +/- 2.1 < 4.3 0.4 +/- 1.5 < 3.4 -0.4 +/- 2.1 < 4.4 30 Lab Code ELW- 5108 ELW- 5784 ELW- 6353 E~W- 6938 Date Collected 09-16-15 10-14-15 11-05-15 12-10-15 Req.LLD Gross beta 0.5 +/- 0.5 < 0.9 1.3 +/- 0.6 < 0.9 1.6 +/- 1.0 < 1.8 1.8 +/- 0.6 < 0.9 4.0 1-131 0.02 +/- 0.14 < 0.25 0.03 +/-0.17 < 0.30 0.02 +/- 0.13 < 0.23 0.03 +/- 0.15 < 0.27 0.5 Be-7 -4.5 +/- 18.8 < 44.6 4.1 +/- 17.9 < 37.5 2.4 +/- 4.8 < 15.1 2.9 +/- 10.8 < 23.6 Mn-54 -0.2 +/- 2.5 < 4.6 -0.6 +/- 1.4 < 2.0 0.2 +/- 0.6 < 0.9 -0.3 +/- 1.4 < 2.7 10 Fe-59 4.4 +/- 4.2 < 5.6 -3.4 +/- 3.3 < 4 .8 -0.7 +/- 1.0 < 2.7 1.1 +/- 2.3 < 5.0 30 Co-58 -3.5 +/- 2.2 < 2.6 0.5 +/- 1.7 < 3.3 0.3 +/- 0.5 < 1.1 0.8 +/- 1.2 < 2.3 10 Co-60 1.0 +/- 2.7 < 4.4 -0.9 +/- 2.0 < 1.5 -0.4 +/- 0.6 < 1.0 -1.6 +/- 1.6 / < 1.5 10 Zn-65 1.1 +/- 5.0 < 3.8 0.5 +/- 3.6 < 2.7 -1.3 +/- 1.1 < 1.7 3.4 +/- 2.9 < 3.1 30 Zr-Nb-95 -0.1 +/- 2.6 < 6.6 -2.3 +/- 1.6 < 2.1 0.5 +/- 0.6 < 1.7 -0.5 +/- 1.3 < 2.1 15 Cs-134 -3.2 +/- 2.6 < 4.4 -1.1 +/- 1,7 < 3.3 -0.1 ;!: 0.6 < 1.1 0.5 +/- 1.3 < 2.3 10 1.2 +/- 2.9 < 4.1 0.2+/-1.7 < 2.6 0.5 +/- 0.7 < 1.3 0.1 +/- 1.6 < 2.7 10 Cs-137 Ba-La.140 1.8 +/- 2.4 < 14.4 0.4+/-1.7 < 7.8 -1 .3 :t 0.6 < 1.7 1.6 +/- 1.4
/ < 2.8 15 Other (Ru-103) -0.1 +/- 2.2 < 5.1 0.6 +/- 1.8 < 4.0 -0.4 +/- 0.6 < 1.3 0.3 +/- 1.2 < 2.5 30
""NS'; =No sample; see Table*2.0, Listing of Missed Samples.
(
\ ,
5-1
POINT BEACH Table 5. Lake water, analyses for gross bela, iodine-131 and gamma emitting isotopes. Location: E-05 (Two Creeks Park) Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 137 NS" ELW- 989 ELW- 1661 Dale Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req. LLD Gross beta 2.5 +/- 0.8 < 1.2 3.4 +/- 1.0 < 1.6 1.7 +/- 0.6 < 0.9 4.0 1-131 0.07 +/- 0.13 < 0.22 0.03 +/- 0.14 < 0.26 0.07 +/- 0.22 < 0.45 0.5 Be-7 7.0 +/- 11.3 < 22.8 13.1 +/- 15.5 < 35.8 -9.8 +/- 17.3 < 32.8 Mn-54 -1 .0 +/- 1.2 < 1.6 -0.1 +/- 1.6 < 2.2 0.1 +/- 1.6 < 2.6 10 Fe-59 -2.3 +/- 2.7 < 2.8 -2.7 +/- 3.4 < 3.3 -1 .6 +/- 3.2 < 4.3 30 Co-58 0.9 +/- 1.2 < 2.3 0.8 +/- 1.5 < 3.3 -0.9 +/- 1.5 < 1.9 10 Co-60 0.7 +/- 1.5 < 1.9 0.7 +/- 1.1 < 0.8 -0.1 +/- 1.2 < 2.1 10 Zn-65 -0.7 +/- 2.3 < 2.1 -1 .1 +/-3.3 < 4.2 -1 .5 +/- 4.4 < 5.1 30 Zr-Nb-95 -1.9 +/- 1.4 < 1.9 -0.3 +/- 1.7 < 4.4 0.1 +/- 1.9 < 4.7 15 Cs-134 -0.7 +/- 1.3 < 2.4 1.1 +/- 1.7 < 3.5 1.0 +/- 1.6 < 2.8 10 Cs-137 0.5 +/- 1.4 < 2.6 0.0 +/- 1.9 < 2.1 -0.2 +/- 2.0 < 2.3 10 Ba-La-140 1.3 +/- 1.4 < 2.8 1.9 +/- 2.0 < 6.2 0.8 +/- 1.6 < 3.0 15 Other (Ru-103) 1.2 +/- 1.3 < 3.4 1.0 +/- 1.8 < 3.5 1.9 +/- 1.8 < 3.8 30 Lab Code ELW- 2423 ELW- 2936 ELW- 3615 ELW- 4481 Date Collected 05-14-15 06-11-15 07-09-15 08 15 Req. LLD Gross beta 1.0 +/- 0.5 < 0.8 0.8 +/- 0.5 < 0.8 1.1 +/- 0.9 < 1.7 0.8 +/- 0.5 < 0.8 4.0 1-131 -0.02 +/- 0.12 < 0.22 0.00 +/- 0.20 < 0.43 0.00 +/- Q.15 < 0,27 0.03 +/- 0.14 < 0.25 0.5 Be-7 -4.2 +/- 6.0 < 11.8 -7.3 +/- 23.6 < 38.5 -13.5 +/- 14.7 < 18.2 4 .8 +/- 10.6 < 18.6 Mn-54 0.7 +/- 0.6 < 1.3 -1 .1 +/- 2.2 < 2.7 0.5 +/- 1.5 < 1.9 0.2 +/- 1.4 < 2.1 10 Fe-59 -0.1 +/- 1.3 < 3.2 -1 .1 +/- 4.9 <; 5.7 2.1 +/- 3.0 < 3.9 0.4 +/- 2.4 < 5.2 30 Co-58 -0.5 +/- 0.6 < 1.0 0.5 +/- 2.1 < 3.9 0.4 +/- 1.4 < 2.3 0.7 +/- 1.4 < 2.4 10
/ Co-60 -0.3 +/- 0.7 < 1.2 -1 .6 +/- 2.4 < 2.8 -0.4 +/- 1.6 < 1.4 -0.4 +/- 1.6 < 2.3 10 Zn-65 -0.4 +/- 1.3 < 2.0 -11. 1 +/- 6.1 < 6.8 -4.8 +/- 3.7 < 2.7 -0.5 +/- 2.7 < 5.9 30 Zr-Nb-95 -0.4 +/- 0.6 < 2.0 -2.8 +/- 2.8 < 3.3 -1.4 +/- 1.6 < 2.5 -1.0 +/- 1.5 < 2.9 15 Cs-134 -0.4 +/- 0.6 < 1.3 -3.1 +/- 2..4 < 4.5 -1.1 +/- 1.6 < 3.3 -0.9 +/- 1.5 < 2.8 10 Cs-137 0.5 +/- 0.7 < 1.6 1.0 +/- 2..1 < 4.0 0.9 +/- 1.9 < 3.3 -0.5 +/- 1.5 < 1.9 10 Ba-La-140 -6.6 +/- 0.8 < 2.2 -3.2 +/- 2.7 < 2.2 -0.7 +/- 2.0 < 9.5 -3.4 +/- 1.6 < 4.6 15 Other (Ru-103) -1.3 +/- 0.7 < 1.0 -1.3 +/- 2.3 < 3.0 -0,9 +/- 1.9 < 3.9 -0.3 +/- 1.4 < 3.2 30 Lab Code ELW- 5109 ELW- 5785 ELW- 6354 ELW- 6939 Date Collected 09-16-15 10-14-15 11-05-15 12-10-15 Req.LLO Gross bela 0.6 +/- 0.5 < 0.8 1.2 +/- 0.5 < 0.8 2.2 +/- 0.9 *< 1.6 1.3+/-0.5/ < 0.8 4.0 1-131 -0.03 +/- 0.15 < 0.27 0.11 +/- 0.22 < 0.41 -0.01 +/- 0.22 < 0.45 -0.02 +/- 0.15 < 0.27 0.5 Be-7 7.6 +/- 18.0 < 45.9 10.1 +/- 16.3 < 43.1 -8.2 +/- 14.8 < 26.6 17.8 +/- 11 .7 < 29.8 Mn-54 -0.1+/-1 .8 < 2.8 0.5 +/- 1.5 < 2.9 0.7 +/- 1.4 < 2.4 -0.1 +/- 1.3 < 1.5. 10 Fe-59 -0.7 +/- 3.5 < 6.6 0.4 +/- 2.8 < 4.3 0.5 +/- 3.0 < 5.2 1.7 +/- 2.5 < 3.8 30 Co-58 0.0 +/- 1.6 < 3.0 -0.2 +/- 1.4 < 2.3 -0.6 +/- 1.6 < 2.2 0.2 +/- 1.6 < 1.7 10 Co-60 1.0 +/- 1.8 < 2.3 -0.6 +/- 1.8 < 1.8 -0.1 +/- 1.7 < 1.9 1.0 +/- 1.4/ < 2.6 10 Zn-65 -5.2 +/- 4.3 < 3.6 2.0 +/- 2..6 < 4.1 -2.6 +/- 3.1 < 3.0 2.2 +/- 2.7 < 4.7 30 Zr-Nb-95 -1.3 +/-1.6 < 3.8 0.4 +/- 1.6 < 4.6 -0.1 +/- 1.4 < 3.4 0.3 +/- 1.4 < 3.0 15 Cs-134 1.9 +/- 1.7 < 3.5 -1 .0 +/-*1.7 < 3.3 -0.3 +/- 1.4 < 2.7 0.8 +/- 1.4 < 2.6 10 Cs-137 -1.3 +/- 2.0 < 3,1 -0.1 +/- 2.0 < 3.0 0.4 +/- 1.7 < 2.8 0.7 +/- 1,5 < 1.9 10 Ba-La-140 1.3 +/- 2.3 < 13.0 -3.6 +/- 1.8 < 11.0 1.4 +/- 1.3 < 7.6 1.0 +/- 1.5 I < 2.9 15 Other (Ru-103) 0.3 +/- 1.9 < 4.7 0.7 +/- 1.7 < 4.6 0.5 +/- 1.7 < 3.8 0.0 +/- 1.3 < 2.5 30
* "NS." =No sample; see Table 2.0, listing of Missed Samples.
I i
!i-?
POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-06 (Coast Guard Station)
/ Collection: Monthly composites Units: pCi/L
[\ MDC MDC MDC MDC 8 Lab Code ELW- 138 NS ELW- 990 ELW- 1662 Date Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req . LLD Gross beta 4 .0 +/- 0.9 < 1.3 4.4 +/- 1.1 < 1.8 2.0 +/- 0.6 < 0.9 4.0 1-131 0.02 +/- 0.20 < 0.39 0.06 +/- 0.24 < 0.49 0.15 +/- 0.25 < 0.50 0.5 Be-7 -1 .7 +/- 10.8 < 24.6 9.8 +/- 9.3 < 19.1 1.8 +/- 15.0 < 27.2 Mn-54 0.7 +/- 1.1 < 2.1 0.9 +/- 1.2 < 2.6 0.6 +/- 1.5 < 2.9 10 Fe-59 1.7 +/- 2.1 < 3.4 -1.9 +/- 2.1 < 3.5 -0.3 +/- 2.9 < 4.3 30 Co-58 1.2 +/- 1.2 < 2.4 -0.5 +/- 1.1 < 1.7 1.1 +/- 1.3 < 3.0 10 Co-60 0.7 t 1.5 < 2.3 -0.8 +/- 1.1 < 1.1 1.2 +/- 1.6 < 2.5 10 Zn-65 -0.8 +/- 2.4 < 2.4 -1.3 +/- 2 .5 < 4.3 1.0 :t: 2.9 < 3.7 30 Zr-Nb-95 0.5 +/- 1.4 < 2.9 0.1 +/- 1.2 < 2.9 -0.4 +/- 1.3 < 2.5 15 Cs-134 0.1 +/- 1.3 < 2.5 -0.3 +/- 1.2 < 2.2 0.4 +/- 1.4 < 2.7 10 Cs-137 0.8 +/- 1.5 < 2.5 -0.2 +/- 1.5 < 2.6 0.3 +/- 1.6 < 2.9 10 Ba-La-140 -3.7 +/- 1.2 < 1.7 0.8 +/- 1.4 < 4.3 -3.3 +/- 1.7 < 3.6 15 Other (Ru-103) 0.3 +/- 1.1 < 2.9 0.3 +/- 1.0 < 2.5 0.1 +/- 1.6 < 2.2 30 Lab Code ELW- 2424 ELW- 2937 ELW- 3616 ELW- 4482 Date Collected 05-14-15 06-11-15 07-09-15 08-13-15 Req. LLD Gross beta 0.4 +/- 0.5 < 0.9 1.3 +/- 0.6 < 0.9 1.1 +/- 0.9 < 1.7 0.8 +/- 0.5 < 0.9 4.0 1-131 -0.07 +/- 0.11 . < 0.21 0.01 +/- 0.13 < 0.23 0.14 +/- 0.17 < 0.30 -0.03 +/- 0.15 < 0.26 0.5 Be-7 0.3 +/- 4.9 < 14.7 12.0 +/- 18.5 < 37.2 -0.2 +/- 17.0 < 34.3 -10.0 +/- 14.6 < 37.5 Mn-54 0.0 +/- 0.6 < 1.2 0.5 +/- 1.4 < 2.3 -0.1 +/- 1.8 < 1.9 1.5 +/- 1.7 < 2.8 10 Fe-59 0.9 +/- 1.1 < 2.9 1.6 +/- 3.3 < 3.3 0.2 +/- 4.2 < 8.1 0.5 +/- 2.9 < 4.9 30 Co-58 0.4 +/- 0.6 < 1.5 0.2 +/- 2.1 < 4.5 -2.3 +/- 1.9 < 2.0 1.7 +/- 1.7 < 3.2 10
/ ' Co-60 0.1 +/- 0.6 < 0.6 1.4 ;!: 1.8 < 2.4 0.9 +/- 2.3 < 3.4 -1.1 +/- 1.8 <1.4 10 Zn-65 0.4 +/- 1.1 < 2.6 1.3 +/- 4.2 < 6.5 -0.2 +/- 4.3 < 1.8 0.2 +/- 2.9 < 2.9 30
' Zr-Nb-95 -0.4 +/- 0.6 < 1.8 -1.2 +/- 1.7 < 2.5 1.9 +/- 2.1 < 4.9 0.1 +/- 1.7 < 3.3 15 Cs-134 -0. 1 +/- 0.6 < 1.2 0.8 +/- 1.6 < 3.4 3.1 ;!: 2.0 < 3.8 -0.9 +/- 1.9 < 3.8 10 Cs-137 0.3 +/- 0.7 < 1.4 0,6 t 2.1 < 4.0 1.5 +/- 1.9 < 3.6 -0.1 +/- 1.9 < 2.9 10 Ba-La-140 -2.3 +/- 0.6 < 4.6 0.7 +/- 2.1 < 2.2 -3.6 +/- 2.2 < 6.9 -2.0 +/- 1.7 < 4.0 15 Other (Ru-1 03) 0.2 +/- 0.6 < 1.5 -2.0 +/- 2.1 < 3.1 -1.0 :!: 2.2 < 3.8 -1 .0 +/- 1.6 < 2.9 30 Lab Code ELW- 5110 ELW- 5786 ELW- 6355 ELW- 6940 Date Collected 09-16-15 10-14-15 11 15 12-10-15 Req. l-LD Gross beta 1.1 +/- 0.5 < 0.9 0.7 +/- 0.5 < 0.9 2.4 +/- 1.0 < 1.8 1.7 +/- 0.6 < 0.9 4.0 1-131 0.12 +/- 0.14 < 0.24 -0.03 +/- 0.23 < 0.41 0.17 +/- 0.26 < 0.49 -0.02 :1: 0.16 < 0.29 0.5
/
Be-7 1.7 +/- 9.3 < 26.6 -14.1 +/- 16.7 < 30.4 -3.3 +/- 5.9 < 11 .2 7.6 +/- 10.8 < 20.8 Mn-54 1.3 +/- 1.1 < 2.5 -1.8 +/- 1.7 < 2.8 0.5 +/- 0.6 < 1.3 0.5:!: 1.3 < 2.3 10 Fe-59 -1.3+/-2.1 < 5.1 -0.6 +/- 3.0 < 6.2 1.1 +/- 1.1 < 3.0 -3.4 +/- 2.8 < 5.2 30 Co-58 0.4 +/- 1.1 < 3.1 -0.8 +/- 1.8 < 3.6 0.4 +/- 0.6 <1.4 -0.8 +/- 1.2 < 1.5 10 Co-60 0.2 +/- 1.2 < 1.f;l -0.7 ;!; 1.5 < 1.6 0.1 +/- 0.7 < 1.0 -0.1 +/- 1.4 / < 2.0 10 Zn-65 -2.0 +/- 2.6 < 1.9 2.9 +/- 3.7 < 4.4 0.7 +/- 1.2 < 1.8 3.8 +/- 2.7 < 3.4 30 Zr-Nb-95 -0.7 +/- 1.1 < 3.9 1.6 +/- 1.7 < 5.4 0.1 +/- 0.6 < 1.6 0.3 +/- 1.5 < 2.6 15 Cs-134 -0.2 +/- 1.1 < 2.1 1.3 +/- 1.7 < 3.2 -0.4 +/- 0.6 < 1.3 0.4 +/- 1.3 < 2.3 10 Cs-137 -0.8 +/- 1.3 < 1.8 0.4 +/- 2.2 < 2.5 0.0 +/- 0.7 < 1.2 0.3 +/- 1.5 < 2.6 10 Ba-La-140 -2.3 +/- 1.3 < 10.3 1.1 +/- 1.9 < 6.8 -1 .0 +/- 0.7 < 5.0 0.8 +/- 1.9 < 2.6 15 Other (Ru-103) 0.0 +/- 1.1 < 3.7 -1.6 +/- 1.9 < 2.8 -0.2 +/- 0.7 < 1.9 -0.8 +/- 1.2 < 2.2 30
* "NS" = No sample; see Table 2.0, Listing of Missed Samples.
( 5-3
POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. location: E-33 (Kewaunee)
/ Collection: Monthly composites Units: pCi/1,.
\
MDC MDC MDC MDC Lab Code ELW- 139 NS" ElW- 991 ELW- 1663 Date Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req. LLD Gross beta 3.2 +/- 0.8 < 1.1 2.4 +/- 1.0 < 1.8 1.0 +/- 0.5 < 0.8 4.0 1-131 -0.01 +/- 0.16 < 0.29 0.02 +/- 0.13 < 0.23 -0.15 +/- 0.21 < 0.48 0.5 Be-7 -3.0 +/- 8.0 < 13.3 -3.2 +/- 8.9 < 20.4 -8.6 +/- 14.3 < 29.1 Mn-54 -0.8 :t 1.0 < 1.5 0.5 +/- 1.0 < 2.1 -0.5 +/- 1.4 < 2.0 10 Fe-59 2.4 +/- 1.7 < 3.8 -0.8 +/- 1.8 < 2.3 -1.5 +/- 3.0 < 4.2 30 Co-58 -0.5 +/- 1.0 < 1.8 0.6 +/- 1.0 < 2.3 0.1 +/- 1.5 < 2.0 10 Co-60 -0.1 +/- 0.9 < 1.1 -0.5 +/- 1.1 < 1.1 -1.3 +/- 1.8 < 1.6 10 Zn-65 -0.(3 +/- 1.5 < 2.3 0.1 +/- 2.1 < 1.8 2.7 +/- 3.2 <2.4 30 Zr-Nb-95 -0.1 +/- 1.1 < 2.5 0.5 +/- 1.2 < 3.3 -2.6 +/- 1.7 < 2.3 15 Cs-134 0.0 +/- 1.0 < 1.9 1.2 +/- 1.1 < 2.0 -1 .2 ;!: 1.4 < 3.0 10 Cs-137 -0.6 +/- 1.2 < 1.8 0.2 +/- 1.3 < 2.4 0.6 +/- 1.8 < 3.3 10 Ba-La-140 -0.9 +/- 1.1 < 3.8 1.5 +/- 1.1 < 2.8 2.9 :t 1.5 < 2.5 15 Other (Ru-1 03) 0.2 +/- 0.9 <( 2.2 -0.9 +/- 1.1 < 2.4 -0.6 +/- 1.8 < 2.1* 30 Lab Code ELW- 2425 ELW- 2938 ELW- 3617 ELW- 4483 Date ~ollected 05-14-15 06-11-15 07-()9-15 08-13-15 Req. LLD Gross beta 2.1 +/- 1.0 < 1.8 1.0 +/- 0.5 < 0.8 1.6 +/- 0.9 < 1.6 0.9 +/- 0.5 < 0.8 4.0 1-131 -0.03 +/- 0.12 < 0.23 -0.04 +/- 0.11 < 0.21 -0.01 +/- 0.20 < 0.37 0.01 +/- 0.16 < 0.29 0.5 Be-7 -4.0 +/- 4.9 < 11.0 2.8 +/- 10.7 < 24.9 4.3 +/- 13.9 < 36.1 9.2 +/- 11 .1 < 30.0 Mn-54 0.1 +/-. 0.6 < 1.2 0.6 +/- 1.0 < 1.7 0.0 +/- 1.5 < 2.6 0.4 +/- 1.5 < 2.9 10 Fe-59 -1 .1 +/- 1.0 < 2.8 0.3 +/- 2.1 < 2.5 -0.7 +/- 2.5 < 4.0 -0.3 +/- 2.7 < 5.3 30 Co-58 -0.2 +/- 0.5 < 1.3 -0.3 +/- 0.9 < 1.3 0.3 +/- 1,5 < 3.5 -1.0 +/- 1.2 < 1.7 10 Co-60 0.3 +/- 0.6 < 1.2 -0.3 +/- 1.1 < 2.0 -0.2 +/- 1.5 < 1.8 -0.2 +/- 1.6 < 1.8 10 I' Zn-65 0.7 +/- 1.1 < 2.5 -1.1+/-2..4 < 3.5 -0.2 +/- 2.6 < 2.9 -0.2 +/- 2.4 < 3.1 30
\. Zr-Nb-95 -0.2 +/- 0.6 < 1.7 0.6 +/- 1.1 < 2.4 -2.4 +/- 1.6 < 2.7 2.2 +/- 1.3 < 3.7 15 Cs-134 -0.1 +/- 0.6 < 1.1 -0.2 +/- 1.1 < 2.2 -0.8 +/- 1.7 < 2.9 0.8 +/- 1.6 < 3.0 10 Cs-137 0.6 +/- 0.7 < 1.2 -0.4 +/- 1.3 < 1..5 0.4 +/- 1.9 < 2 .8 0.2 +/- 1.7 < 2.5 10 Ba-La-140 -2.3 +/- 0.7 < 2.4 -3.2 +/- 1.3 < 1.8 -1 .0 +/- 1.7 < 6.5 -1.4 +/- 1.7 < 7.6 15 Other (Ru-103) -0.9 +/- 0.5 < 1.9 -1.3 +/- 1.3 < 2.1 -0.4 +/- 1.5 < 3.0 0.2 +/- 1.3 < 3.2 30 Lab Code ELW-5111 ~LW- 5767 J;:LW- 6356 ELW- 6941 Date *collected 09-16-15 10-14-15 11-05-15 12-10-15 Req. LLD Gross beta 0.6:!; 0.5 < 0.8 . 0.9 +/- 0.5 < 0.8 1.8 +/- 0.9 < 1.7 2.3 :!; 0.6 < 0.8 4.0 1-131 0.13 +/- 0.16 < 0.27 0.00 +/- 0.19 < 0.35 0.25 :j: 0.26 < 0.49 0.13 +/- 0.17 < 0.29 0.5 Be-7 7.8 +/- 8.4 < 19.7 16.4 +/- 14.4 < 38.0 2.5 +/- 4.4 < 13.5 -5.6 +/- 19.1 < 29.6 Mn-54 0.3 +/- 0.8 < 1.7 0.1 +/- 1.4 < 2.3 -0.2 +/- 0.6 < 1.0 0.1 +/- 2.0 < 3.7 10 Fe-59 1.0 +/- 1.6 < 3.5 -5.6 +/- 2.5 < 3.3 -0.7:!; 1.0 < 2.8 -3.4 +/- 4.2 / < 5.9 30 Co-58 -0.3 +/- 0.8 < 1.8 -0.7 +/- 1.7 < 2.9 0.4 +/- 0.5 < 1.2 2.6 +/- 2.0 < 3.4 10 Co-60 -0.2 +/- 0.9 < 1.5 0.2 +/- 1.6 < 1.6 0.1 t 0.6 < 1.0 -1.3 :t 1.7 < 1.4 10 Zn-65 -1 .1 +/- 1.8 < 2.6 2.1 +/- 3.2 < 6.1 -1 .0 +/- 1.1 . < 1.5 -1 .9 +/- 5.0 < 5.7 30 Zr-Nb-95 1.3 +/- 0.8 < 2.5 -1 .9 +/- 1.6 < 2.4 -0.1 +/- 0.5 < 1.8 0.3 +/- 2.0 < 2.9 15 Cs-134 -0.6 +/- 0.9 < 1.6 -0.4 +/- 1.4 < 2.9 0.2 +/- 0.5 < 1.0 o.3 +/- 2.11 < 3.8 10 Cs-137 -0.1 +/- 0.9 < 1.1 1.5 +/- 1.8 < 2.1 0.3 +/- 0.6 < 1.1 2.3 +/- 2.1 < 4.0 10 Ba-La-140 -4.3 +/- 1.0 < 4.2 0.8 +/- 2.2 < 13.4 0.7 +/- 0.7 < 3.8 -5.3 +/- 2.1 < 1.8 15 Other (Ru-103) -0.7 :t 0.9 < 2.3 1.6 +/- 1.6 < 4.1 0.5 +/- 0.5 < 1.6 -0.4 +/- 2.3 < 3.6 30
* "NS" = No sample; see Table 2.0, Listing of Missed Samples.
Annual All loaations Mean +/-S.d. Mean +/-S.d. Mean +/-S.d. Gross Beta 1.6 +/- 1.0 1-131 0.03 +/- 0.06 Co-58 o.o +/- 1.0 Cs-134 -0.1 +/- 1.1 Be-7 0.3 +/- 8.0 Co-60 -0.1 :!;0.9 Cs-137 0,2 +/- 0.6 ( Mn-54 0.1 +/- 0.7 Zn-65 -0.5 +/- 2.5 Ba-La-140 -0.8 +/- 2.2
'* Fe-59 -0.6 +/- 2.0 Zr-Nb-95 -0.1+/-1.3 Ru-103 -0.2 +/- 0.9 fi-4
POINT BEACH NUCLEAR PLANT Table 6. Lake water, analyses for tritium, strontium-89 and strontium~90. Collection: Quarterly composites of weekly grab samples Units: pCi/L Location E-01 (Meteorolo9ical Tower) Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4th Qtr. MDC Lab Code ELW- 1087 ELW- 3139 ELW- 5202 ELW- 7017 Req.LLOs H-3 -38 +/- 71 < 148 55 +/-74 < 144 128 +/- 78 < 142 85 +/-76 < 145 500 Sr-89 -0.13 +/- 0.66 < 0.76 0.17 +/-0.88 < 1.01 0.17 +/- 0.63 < 0.76 0.34 +/-0.62 < 0.73 5.0 Sr-90 0.35 +/-0.28 < 0.53 0.28 +/-0.37 < 0.73 0.19 +/- 0.30 < 0.59 0.22 +/-0.26 < 0.51 1.0 Location E-05 (Two Creeks Park) Period 1st Q!r. 2nd Qtr. 3nd Qtr. 4th Qtr. l.,ab Code ELW- 1088 ELW- 3140 ELW- 5203 ELW- 7018 a Req.LLDs H-3 15 +/-74 < 148 29 +/-73 < 144 96 +/- 76 < 142 452 :1;94@145 500 Sr-89 -0.05 +/-0.63 < 0.79 0.29 +/-0.62 < 0.78 0.48 +/- 0.58 < 0.73 0.53 +/-0.63 < 0.72 5.0 Sr-90 0.24 +/-0.26 < 0.51 0.12 +/-0.25 < 0.52 0.16 +/- 0.26 < 0.51 0.14 +/-0.26 < 0.52 1.0 Location E-06 (Coast Guard Station) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 1089 ELW- 3141 ELW- 5204 ELW- 7019 Req. LLDs H-3 4 +/-74 < 148 86 +/-76 < 144 61 +/- 74 < 142 61 +/-75 < 145 500
$r-89 -0.08 +/-0.57 < 0.69 -0.80 +/-0.86 < 0.91 -0.04 +/- 0.50 < 0.61 -0.43 +/-0.69 < 0.78 5.0 /
Sr-90 0.23 +/-0.24 < 0.46 0.71 +/-0.38 < 0.64 0.23 ;i: 0.24 < 0.45 0.47 +/- 0.31 < 0.55 1.0 Location E-33 {Kewaunee) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 1090 !;LW- 3142 ELW- 5205 ELW- 7020 Req. LLDs H-3 158 +/- 82 < 148 8 +/-72 < 144 113+/-77 < 142 237 +/- 84 ~< 145 500 Sr-89 0,39 +/-0.57 < 0.69 -0.21 +/-0.57 < 0.68 -0.15 +/- 0.54 < 0.62 -0.24 +/- 0.61 < 0.76 5.0 Sr-90 0.14 +/- 0.23 < 0.44 0.26 :1;0.25 < 0.48 0.41 +/- 0.26 < 0.44 0.26 +/-0.27 <0.51 1.0
~iz kLR0 :t..fS-1~
~~
Tritium Annual Mean +/- s.d. 97 +/- 116 Sr*89 Annual Mean +/- s.d. 0.02 +/-0.36 Sr-90 Annual Mean +/- s.d. 0.28 :!:0.15 a Tritium recounted with a result of 584;!:99 pCi/L.
/
(. 6-1
POINT BEACH NUCLEAR PLANT
/---
Table 7. Fish, analyses for gross bela and gamma emitting isotopes. ( Location: E-13 Collection: 2x I year Units: pCi/g wet Sample Description and Concentration Req. MDC MDC MDC LLD Collection Dale 01-05-15 01-06-15 01-18-15 Lab Code EF- 146 EF- 148 EF- 1334 Type Lake Trout While Fish Smallmouth Bass Ratio (wet/drY wt.) 4.71 4.87 5.19 Gross Bela 3.31 +/- 0.09 < 0.031 3.41 +/- 0.10 < 0.038 3.26 +/- 0.03 < 0.010 0.5 K-40 2.49 +/- 0.34 3.25 +/- 0.42 3.03 +/- 0.40 Mn-54 0.005 +/- 0.007 < 0.015 0.001 +/- 0.010 < 0.013 0.002 +/- 0.010 < 0.023 0.13 Fe-59 -0.010 +/- 0.018 < 0.054 -0.044 +/- 0.021 < 0.028 -0.004 +/- 0.018 < 0.133 0.26 Co-58 0.008 +/- 0.007 < 0.020 -0.003 +/- 0.009 < 0.014 -0.018 +/- 0.009 < 0.028 0.13 Co-60 0.001 +/- 0.010 < 0.015 -0.004 +/- 0.010 < 0.011 0.013 +/- 0.010 < 0.018 0.13 Zn-65 -0.009 +/- 0.020 < 0.024 0.006 +/- 0.024 < 0.026 0.010 +/- 0.017 < 0.037 0.26 Cs-134 0.003 +/- 0.009 < 0.018 -0.005 +/- 0.009 < 0.015 0.000 +/- 0.009 < 0.017 0.13 Cs-137 0.014 +/- 0.011 < 0.020 0.012 +/- 0.010 < 0.012 0.025 +/- 0.013 < 0.021 0.15 Other (Ru-103) 0.020 +/- 0.009 < 0.042 0.010 +/- 0.008 < 0.016 -0.014 +/- 0.007 < 0.049 0.5 Collection Dale 03-15-15 03-15-15 03-30-15 Lab Code EF- 1335 EF- 1336 EF- 1337 Type Lake Herring Burbol Chinook Ratio (wet/drY wl.) 5.19 5.77 5.17 Gross Bela 3.16 +/- 0.03 < 0.010 1.75 +/- 0.02 < 0.009 2.30 +/- 0.02 < 0.007 0.5 ( K-40 2.32 +/- 0.34 0.94 +/- 0.49 2.11 +/- 0.30
\
Mn-54 -0.001 +/- *0.009 < 0.015 -0.014 +/- 0.021 < 0.025 -0.007 +/- 0.008 < 0.011 0.13 Fe-59 -0.003 +/- 0.015 < 0.037 0.056 +/- 0.036 < 0.108 -0.029 +/- 0.018 < 0.034 0.26 Co-58 -0.015 +/- 0.009 < 0.015 -0.021 +/- 0.020 < 0.039 0.001 +/- 0.007 < 0.016 0.13 Co-60 0.003 +/- 0.011 < 0.012 0.030 +/- 0.021 < 0.021 0.002 +/- 0.009 < 0.013 0.13 Zn-65 -0.006 +/- 0.018 < 0.024 0.008 +/- 0.041 < 0.082 -0.008 +/- 0.018 < 0.030 0.26 Cs-134 -0.002 +/- 0.008 < 0.015 0.000 +/- 0.021 < 0.044 0.000 +/- 0.008 < 0.016 0.13 Cs-137 0.044 +/- 0.023 < 0.022 0.038 +/- 0.027 < 0.049 0.023 +/- 0.010 < 0.018 0.15 Other (Ru-103) 0.000 +/- 0.007 < 0.030 -0.010 +/- 0.0 18 < 0.073 -0.010 +/- 0.008 < 0.016 0.5
/
rt \ 7-1
POINT BEACH NUCLEAR PlANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes. Location: E-13 Collection: 2x /year Units: pCi/g wet Sample Description and Concentration (pCilg wet) Req. MDC MDC MDC LLD Collection Date 04-30-15 05-18-15 06-12-15 Lab Code EF- 2214 EF- 2637 EF- 3732 Type Lake Trout Lake Trout Lake Trout Ratio (wet/dry wt.) 3.42 3.78 3.82 Gross Beta 2.78 +/- 0.06 < 0.020 2.43 +/- 0.06 < 0.020 3.62 +/- 0.08 < 0.029 0.5 K40 2.59 +/- 0.41 2.46 +/- 0.41 2.33 +/- 0.40 Mn-54 -0.004 +/- 0.009 < 0.013 0.013 +/- 0.009 < 0.014 0.003 +/- 0.008 < 0.016 0.13 Fe-59 0.025 +/- 0.021 < 0.042 0.008 :l: 0.018 < 0.039 0.036 +/- 0.019 < 0.055 0.26 Co-58 0.000 +/- 0.009 < 0.016 0.000 +/- 0.009 < 0.007 0.008 +/- 0.008 < 0.019 0.13 Co*60 0.008 +/- 0.006 < 0.013 0.002 +/- 0.010 < 0.014 0.003 +/- 0.010 < 0.016 0.13 Zn-65 -0.011 +/- 0.024 < 0.013 -0.013 +/- 0.020 < 0.009 -0.017 +/- 0.022 < 0.022 0.26 Cs-134 -0.004 +/- 0.009 < 0.013 0.000 +/- 0.009 < 0.016 -0.010 +/- 0.010 < 0.018 0.13 Cs-137 0.021 +/- 0.010 < 0.015 0.037 +/- 0.021 < 0.018 0.022 +/- 0.011 < 0.018 0.15 Other (Ru-103) 0.004 +/- 0.009 < 0.021 0.005 +/- 0.008 < 0.009 -0.011 +/- 0.009 < 0.027 0.5 Collection Date 06-19-15 08-18-15 09-02-15
/ EF- 3733 EF- 4660 Lab Code EF- 5230 Type Burbot Lake Trout c;:oho Ratio (wet/dry wt.) 5.99. 5.08 5.15 Gross Beta 2.06 +/- 0.06 < 0.028 2.32 +/- 0.05 < 0.029 2.72 +/- 0.06 < 0.018 K-40 2.00;!; 0.36 2.22:!: 0.35 2.58 +/- 0.39 Mn-54 0.011 +/- 0.009 < 0.015 0.006 :t: 0.009 < 0.018 0.004 +/- 0.009 < 0.020 Fe-59 -0.010 +/- 0.020 < 0.049 0.029 +/- 0.016 < 0.051 0.032 :!: 0.015 < 0.048 Co-58 -0.014 +/- 0.008 < 0.013 0.010 +/- 0.008 < 0.013 0.002 +/- 0.008 < O.Q18 Co-60 0.002 +/- 0.010 < 0.012 0.004 +/- 0.010 < 0.014 0.000 +/- 0.010 < 0.015 Zn-65 -0.023 +/- 0.022 < 0.019 0.006 +/- 0.015 < 0.019 0.006 +/- 0.017 < 0.029 Cs-134 -0.006 +/- 0.009 < 0.019 0.006 +/- 0.008 < 0.015 0.003 +/- 0.008 < 0.014 Cs-137 0.054 :!: 0.020 < 0.018 0.041 +/- 0.020 < 0.021 0.026 +/- 0.011 < 0.019 Other (Ru-103) -0.009 +/- 0.009 < 0.031 0.\)01 +/- 0.007 < 0.034 0.018 +/- 0.007 < 0.036 /
f 7-2
POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.
/
I Location: E-13
\
Collection: 2x/ year Units: pCi/g wet Sample Description and Concentration (pCi/g wet) Req . MDC MDC MDC LLD Collection Date 11-27-15 11-27-15 Lab Code EF- 6744 EF- 6745 Type Chinook Salmon Lake Trout Ratio (wet/dry wt.) 4.07 4.15 Gross Beta 3.24 +/- 0.06 < 0.020 2.95 +/- 0.07 < 0.025 0.5 K-40 3.22 +/- 0.42 2.34 +/- 0.38 Mn-54 0.004 +/- 0.008 < 0.012 0.000 +/- 0.008 < 0.015 0.13 Fe-59 -0.003 +/- 0.018 < 0.026 0.002 +/- 0.016 < 0.035 0.26 Co-58 -0.011 +/- 0.008 < 0.009 0.002 +/- 0.008 < 0.014 0.13 Co-60 -0.002 +/- 0.009 < 0.008 -0.005 +/- 0.008 < 0.008 0.13 Zn-65 -0.011 +/- 0.021 < 0.013 -0.004 +/- 0.019 < 0.026 0.26 Cs-134 0.001 +/- 0.008 < 0.016 0.004 +/- 0.007 < 0.013 0.13 Cs-137 0.021 +/- 0.011 < 0.017 0.021 +/- 0.011 < 0.017 0.15 Other (Ru-103) -0.003 +/- 0.008 < 0.020 -0.003 +/- 0.008 < 0.018 0.5 r Annual tl Mean +/- s.d. Gross Beta 2.81 +/- 0.56 K-40 2.42 +/- 0.57 Mn-54 0.002 +/- 0.007 Fe-59 0.006 +/- 0.027 Co-58 -0.004 +/- 0.010 Co-60 0.004 +/- 0.009 Zn-65 -0.005 +/- 0.010 Cs-134 -0.001 +/- 0.004 Cs-137 0.029 +/- 0.012 Other (Ru-1 03) 0.000 +/- 0.011 7-3
POINT BEACH NUCLEAR PLANT
/ Table 8. Radioactivity in shoreline sediment samples Collection: Semiannual Sample Description and Concentration (pCi/g dry)
MDC MDC MDC Collection Date 4/16/2015 4/16/2015 4/16/2015 Lab Code ESS- 1668 ESS- 1669 ESS- 1670 LLD Location E-01 E-05 E-06 Gross Beta 6.93 +/- 0.88 < 1.13 7.14 +/- 0.84 < 1.06 8.60 +/- 0.95 < 1.19 2.0 Be-7 0.028 +/- 0.050 < 0.09 -0.034 +/- 0.037 < 0.08 -0.063 +/- 0.061 < 0.14 K-40 5.73 +/- 0.40 3.20 +/- 0.26 5.13 +/- 0.39 Cs-134 0.000 +/- 0.007 < 0.012 -0.002 +/- 0.004 < 0.007 0.001 +/- 0.007 < 0.013 0.15 Cs-137 0.008 +/- 0.009 < 0.017 0.006 +/- 0.006 < 0.009 0.025 +/- 0.013 < 0.013 0.15 Tl-208 0.045 +/- 0.022 0.032 +/- 0.012 0.090 +/- 0.020 Pb-212 0.20 +/- 0.057 0.079 +/- 0.016 0.32 +/- 0.069 Bi-214 0.12 +/- 0.027 0.094 +/- 0.017 0.23 +/- 0.034 Ra-226 0.38 +/- 0.15 < 0.28 0.31 +/- 0.11 < 0.19 0.54 +/- 0.17 < 0.30 Ac-228 0.20 +/- 0.063 0.11 +/- 0.030 0.27 +/- 0.077 Collection Date 4/16/2015 4/16/2015 Lab Code ESS- 1671 ESS- 1672 Location E-12 E-33 Gross Beta 9.14 +/- 0.88 < 1.05 7.72 +/- 0.83 < 1.04 2.0
/' Be-7 0.011 +/- 0.053 < 0.11 -0.036 +/- 0.051 < 0.10 f:, K-40 5.75 +/- 0.38 5.81 +/- 0.40 Cs-134 -0.007 +/- 0.007 < 0.009 0.000 +/- 0.006 < 0.009 0.15 Cs-137 0.014 +/- 0.008 < 0.015 0.017 +/- 0.008 < 0.014 0.15 Tl-208 0.042 +/- 0.022 0.038 +/- 0.018 Pb-212 0.12 +/- 0.018 0.16 +/- 0.054 Bi-214 0.13 +/- 0.026 0.11 +/- 0.025 Ra-226 0.42 +/- 0.14 < 0.25 0.31 +/- 0.16 Ac-228 0.15 +/- 0.047 0.14 +/- 0.049 /
I \., 8-1
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections) Sample Descriptior] and Concentration (pCi/g dry) IV! DC MDC MDC Collection Dale 10/14/2015 10/14/2015 10/14/2015 Req. Lab Code ESS- 5818 ESS- 5820 ESS- 5821 LLD Location E-01 E-05 E-06 Gross Bela 8.10 +/- 0.87 < 1.07 9.15 +/- 0.9,? < 1.11 11.20 +/- 0.92 < 1.06 2.0 Be-7 0.037 +/- 0.067 < 0.17 -0.001 +/- 0.061 < 0.14 -0.001 +/- 0.066 < 0.18 K-40 5.22 +/- 0.40 7.78 +/- 0.42 8.69 +/- 0.50 Cs-134 -O.OO(;l +/- 0.008 <: 0.017 -0.003 +/- 0.006 < 0.013 0.005 +/- 0.007 < 0.011 0.15 Cs-137 0.029 ;!: 0.016 < 0.016 0.014 +/- 0.008 <: 0.015 0.020 +/- 0.010 < 0.017 0.15 Tl-208 0.059 +/- 0.018 0.065 +/- 0.018 0.050 +/- 0.016 Pb-212 0.19 +/- 0.027 0.15 +/- 0.020 0.14 +/- 0.024 Bi-214 0.15 +/- 0.041 0.23 +/- 0.029 0.13 +/- 0.027 Ra-226 0.47 +/- 0.24 0.35 +/-0.14 < 0.29 0.37 +/- 0.18 < 0.35 Ac-228 0.20 +/- 0.059 0.18 +/- 0.069 0.17 +/- 0.080 Collection Date 10/14/2015 10/14/2015 Lab Code ESS- 5822 ESS- 5823 Annual Location E-12 E-33 Mean +/-s.d.
!' Gross Beta 7.31 +/- 0.84 < 1.04 7.50 +/- 0.94 < 1.22 2 .0 8.28 +/- 1.30 i' \,
Be-7 -0.012 +/- 0.056 < 0.14 0.058 +/- 0.064 < 0.21 -0.001 +/- 0.037 K-40 4.69 +/- 0.34 5.56 :!: 0.41 5.75 +/- 1.53 Cs-134 -0.002 +/- 0.006 < 0.011 -0.008 ;!: 0.007 < 0.012 0.15 0.00 +/- 0.00 Cs-137 0.026 +/- 0.011 < 0.012 0,028 +/- 0.013 < 0.015 0.15 0.019 +/- 0.008 Tl-2()8 0.050 +/- 0.014 0.049 ;!: 0.020 0.05 +/- 0.02 Pb-212 0.14 +/- 0.021 0.13 +/- 0.021 0.16 +/-0.06 Bi-214 0.13 +/- 0.024 0.086 +/- 0.025 0.14 +/- 0.05 Ra-226 o.36 +/- o.;w 0.33 ::!: 0.17 < 0.33 0.38 +/- 0.07 Ac-228 0.14 +/- 0.061 0.14 +/- 0.051 0.17 +/- 0.05
/
I \, 8-2
POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCi/g dry) MDC MDC MDC Collection Date 5/29/2015 5/29/2015 6/1/2015 Req . Lab Code ESO- 2728 ESO- 2729 ESO- 2730 LLD Location E-01 E-02 E-03 Gross Beta 8.08 +/- 0.92 < 1.15 31.19 +/- 1.22 < 1.04 26.25 +/- 1.15 < 1.03 2.0 Be-7 0.098 +/- 0.057 < 0.12 0.14 +/- 0.10 < 0.21 0.026 +/- 0.088 < 0.18 K-40 5.38 +/- 0.37 18.99 +/- 0.89 18.03 +/- 0.81 Cs-134 -0.004 +/- 0.006 < 0.008 -0.004 +/- 0.011 < 0.018 -0.004 +/- 0.008 < 0.013 0.15 Cs-137 0.031 +/- 0.015 < 0.013 0.12 +/- 0.044 < 0.032 0.15 +/- 0.030 < 0.022 0.15 Tl-208 0.054 +/- 0.015 0.20 +/- 0.035 0.20 +/- 0.034 Pb-212 0.16 +/- 0.028 0.51 +/- 0.046 0.57 +/- 0.096 Bi-214 0.13 +/- 0.027 0.36 +/- 0.053 0.33 +/- 0.042 Ra-226 0.42 +/-0.14 < 0.27 1.02 +/- 0.32 1.18 +/- 0.27 Ac-228 0.26 +/- 0.057 0.62 +/- 0.11 0.68 +/- 0.11 Collection Date 6/1/2015 5/29/2015 6/1/2015 Lab Code ESO- 2731 ESO- 2732 ESO- 2734 Location E-04 E-06 E-08 Gross Beta 15.40 +/- 1.07 < 1.20 19.14 +/- 1.10 < 1.14 22.32 +/- 1.15 < 1.15 2.0 Be-7 0.094 +/- 0.068 < 0.13 0.191 +/- 0.073 < 0.15 0.15 +/- 0.082 < 0.20 K-40 . 8.39 +/- 0.56 11 .85 +/- 0.66 13.44 +/- 0.74 Cs-134 0.005 +/- 0.008 < 0.015 -0.002 +/- 0.008 < 0.013 -0.001 +/- 0.010 < 0.016 0.15 Cs-137 0.088 +/- 0.024 < 0.018 0.315 +/- 0.036 < 0.024 0.23 +/- 0.034 < 0.023 0.15 Tl-208 0.11 +/- 0.022 0.082 +/- 0.027 0.092 +/- 0.031 Pb-212 0.33 +/- 0.077 0.19 +/- 0.038 0.21 +/- 0.030 Bi-214 0.17 +/- 0.039 0.15 +/- 0.035 0.17 +/-0.037 Ra-226 0.41 +/- 0.22 0.38 +/- 0.22 0.53 +/- 0.24 Ac-228 0.38 +/- 0.087 0.28 +/- 0.067 0.35 +/- 0.091 Collection Date 6/1/2015 5/29/2015 Lab Code ESO- 2735 ESO- 2736 Location E-09 E-20 Gross Beta 26.28 +/- 1.15 < 1.03 23.45 +/- 1.18 < 1.17 2.0 Be-7 0.077 +/- 0.093 < 0.21 -0.20 +/- 0.09 < 0.15 K-40 17.00 +/- 0.82 14.20 +/- 0.77 Cs-134 0.009 +/- 0.010 < 0.016 -0.006 +/- 0.010 < 0.014 0.15 Cs-137 0.11 +/- 0.035 < 0.026 0.089 +/- 0.022 < 0.018 0.15 Tl-208 0.14 +/- 0.031 0.12 +/- 0.025 Pb-212 0.51 +/- 0.10 0.49 +/- 0.10 Bi-214 0.40 +/- 0.054 0.24 +/- 0.044 Ra-226 0.92 +/- 0.29 0.67 +/- 0.26 Ac-228 0.51 +/- 0.10 0.46 +/- 0.093 9-1
POINT BEACH NUCLEAR PLANT
,. Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCi/g dry)
MDC MDC MDC Collection Date 10/28/2015 10/28/2015 10/28/2015 Req. Lab Code ESO- 6252 ESO- 6253 ESO- 6254 LLD Location E-01 E-02 E-03 Gross Beta 24.11 +/- 1.58 < 1.69 26.54 +/- 1.59 < 1.56 28.29 +/- 1.60 < 1.50 2.0 Be-7 0.024 +/- 0.090 < 0.18 0.020 +/- 0.094 < 0.19 0.083 +/- 0.085 < 0.21 K-40 16.38 +/- 0.72 16.15 +/- 0.73 15.01 +/- 0.69 Cs-134 0.003 +/- 0.010 < 0.020 -0.006 +/- 0.011 < 0.018 0.002 +/- 0.009 < 0.018 0.15 Cs-137 0.17 +/-0.035 < 0.030 0.095 +/- 0.034 < 0.031 0.12 +/- 0.026 < 0.024 0.15 Tl-208 0.16 +/- 0.025 0.16 +/- 0.028 0.17 +/-0.030 Pb-212 0.51 +/- 0.038 0.52 +/- 0.040 0.46 +/- 0.036 Bi-214 0.34 +/- 0.045 0.31 +/- 0.046 0.26 +/- 0.039 Ra-226 1.12 +/- 0.30 0.83 +/- 0.32 1.37 +/- 0.32 Ac-228 0.61 +/- 0.12 0.40 +/- 0.075 0.48 +/- 0.082 Collection Date 10/28/2015 10/28/2015 10/28/2015 Lab Code ESO- 6255 ESO- 6256 ESO- 6257 Location E-04 E-06 E-08 Gross Beta 28.38 +/- 1.62 < 1.55 13.87 +/- 1.37 < 1.73 18.75 +/- 1.13 < 1.21 2.0 Be-7 0.085 +/- 0.090 < 0.25 -0.026 +/- 0.080 < 0.14 0.058 +/- 0.075 < 0.24 K-40 17.17 +/- 0.73 8.55 +/- 0.52 15.61 +/- 0.71 Cs-134 -0.009 +/- 0.010 < 0.013 0.000 +/- 0.008 < 0.014 -0.012 +/- 0.009 < 0.011 0.15 Cs-137 0.12 +/- 0.024 < 0.023 0.28 +/- 0.033 < 0.024 0.24 +/- 0.030 < 0.023 0.15 Tl-208 0.15 +/- 0.027 0.070 +/- 0.020 0.11 +/- 0.026 Pb-212 0.46 +/- 0.036 0.24 +/- 0.028 0.29 +/- 0.029 Bi-214 0.36 +/- 0.041 0.14 +/-0.031 0.30 +/- 0.054 Ra-226 1.14 +/- 0.29 0.30 +/- 0.21 < 0.42 1.23 +/- 0.25 Ac-228 0.45 +/- 0.095 0.25 +/- 0.091 0.40 +/- 0.10 Collection Date 10/28/2015 10/28/2015 Lab Code ESO- 6258 ESO- 6259 Annual Location E-09 E-20 Mean +/- s.d. Gross Beta 28.28 +/- 1.21 < 1.10 21.61 +/- 1.11 < 1.09 22.62 +/- 6.24 2.0 Be-7 0.008 +/- 0.092 < 0.18 0.016 +/- 0.10 < 0.25 0.053 +/- 0.09 K-40 18.83 +/- 0.77 17.29 +/- 0.85 14.52 +/- 4.04 Cs-134 0.007 +/- 0.009 < 0.018 -0.012 +/- 0.012 < 0.019 0.018 +/- 0.08 0.15 Cs-137 0.15 +/- 0.028 < 0.026 0.17 +/-0.031 < 0.031 0.154 +/- 0.077 0.15 Tl-208 0.16 +/-0.030 0.16 +/-0.031 0.13 +/- 0.04 Pb-212 0.47 +/- 0.035 0.53 +/- 0.043 0.40 +/- 0.14 Bi-214 0.36 +/- 0.044 0.40 +/- 0.062 0.28 +/- 0.10 Ra-226 0.85 +/- 0.28 1.30 +/- 0.36 0.86 +/- 0.36 Ac-228 0.60 +/- 0.075 0.60 +/- 0.10 0.46 +/- 0.14 9-2
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection : Tri-annual
/
i
\.
Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 E-02 E-03 Collection Date 5/29/2015 5/29/2015 6/1/2015 Lab Code EG- 2709 EG- 2710 EG- 2711 Req . LLD Ratio (wet/dry) 3.08 3.82 5.35 Gross 8eta 7.62 +/-0.15 < 0.050 5.80 +/- 0.18 < 0.087 7.42 +/- 0.13 < 0.035 0.25 Be-7 1.37 +/-0.16 1.64 +/- 0.21 0.51 +/- 0.09 +/- 0.09 K-40 5.01 +/- 0.37 5.78 +/- 0.40 5.01 +/- 0.31 1-131 0.006 +/- 0.006 < 0.019 0.007 +/- 0.006 < 0.023 0.002 +/- 0.005 < 0.009 0.060 Cs-134 0.002 +/- 0.006 < 0.011 0.001 :1: 0.006 < 0.012 -0.001 +/- 0.004 < 0.008 0.060 Cs-137 0.008 +/- 0.007 < 0.012 -0.001 +/- 0.007 < 0.013 -0.002 +/- 0.005 .< 0.011 0.080 Other (Co-60) 0.002 +/- 0.007 < 0.013 0.002 +/- 0.007 < 0.008 -0.003 +/- 0.006 < 0.009 0.060 Location E-04 E-06 E-08 Collection Date 6/1/2015 5/29/2015 611/2015 Lab Code EG- 2713 EG- 2714 EG- 2715 Req. LLD Ratio (wet/dry) 6.09 5.28 4.71 Gross Beta 3.98 +/- 0.08 < 0.026 5.04 +/- 0.10 < 0.034 6.71 +/- 0.13 < 0.041 0.25 Be-7 0.65 +/- 0.10 1.11 +/- 0.16 1.57 +/- 0.18 +/- 0.175 K-40 2.82 +/- 0.24 4.36 +/- 0.33 5.89 +/- 0.41 1-131 -0.002 +/- 0.005 < 0.015 -0.012 +/- 0.007 < 0.018 -0.007 +/- 0.006 < 0.014 0.060
/
Cs-134 0.000 +/- 0.005 < 0.008 -0.003 +/- 0.007 < 0.011 0.004 +/- 0.006 < 0.012 0.060 !,, Cs-137 0.002 +/- 0.005 < 0.010 0.052 +/- 0.016 < 0.015 -0.001 +/- 0.007 < 0.014 0.080
'* Other (Co-60) 0.001 +/- 0.004 < 0.006 -0.002 +/- 0.008 < 0.011 0.003 +/- 0.008 < 0.014 0.060 Location E-09 E-20 Collection Date 6/1/2015 5/29/2015 Lab Code EG* 2716 EG- 2717 Req . LLD Ratio (wet/dry) 3.90 5.27 Gross Beta 6.77 +/- 0.14 < 0.042 6.42 +/-0.13 < 0.044 0.25 Be-7 0.52 +/- 0.13 0.18 +/- 0.08 +/- 0.08 K-40 5.52 +/- 0.34 5.39:!; 0.30 1-131 -0.003 +/- 0.004 < 0.011 0.001 +/- 0.005 < 0.016 0.060 Cs-134 Q.OOO +/- 0.005 < 0.009 0.001 +/- 0.005 < 0.009 0.060 Cs-137 0.005 +/- 0.006 < 0.012 -0.002 +/- 0.005 < 0.007 0.080 Other (Co-60) -0.001 +/- 0.006 < 0.007 -0.001 +/- 0.005 < 0.005 0.060 10-1
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection : Tri-annual
/
\
Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 . E-02 E-03 Collection Date 07-22-15 07-22-15 07-22-15 Lab Code EG- 4014 EG- 4015 EG- 4016 Req. LLD Ratio (weUdry) 3.32 4.01 4.21 Gross Beta 5.43 +/- 0.12 < 0.048 6.47 +/- 0.13 < 0.043 8.02 +/- 0.16 < 0.055 0.25 Be-7 1.26 +/- 0.22 1.15+/-0.23 1.08+/-0.16 K-40 3.77 +/- 0.42 5.70 +/- 0.46 6.62 +/- 0.44 1-131 0.016 +/- 0.010 < 0.037 0.004 +/- 0.009 < 0.033 -0.003 +/- 0.007 < 0.025 0.060 Cs-134 -0.008 +/- 0.009 < 0.017 -0.003 +/- 0.008 < 0.017 0.000 +/- 0.007 < 0.013 0.060 Cs-137 0.001 +/- 0.009 < 0.011 0.005 +/- 0.009 < 0.011 0.007 +/- 0.008 < 0.013 0.080 Other (Co-60) 0.001 +/- 0.010 < 0.01 1 0.011 +/- 0.008 < 0.011 -0.003 +/- 0.007 < 0.008 0.060 Location E-04 E-06 E-08 Collection Date 07-22-15 07-22-15 07-22-15 Lab Code EG- 4017 EG- 4018 EG- 4019 Req . LLD Ratio (weUdry) 3.82 2.67 3.28 Gross Beta 7.45 +/- 0.17 < 0.057 . 5.60 +/- 0.12 < 0.041 4.71 +/- 0.12 < 0.054 0.25 Be-7 1.69 +/- 0.20 1.13 +/- 0.15 1.13 +/- 0.19 K-40 6.56 +/- 0.49 4.45 +/- 0.34 4.42 +/- 0.38 1-131 0.001 +/- 0.007 < 0.026 0.015 +/- 0.006 < 0.025 -0.004 +/- 0.008 < 0.029 0.060 Cs-134 0.001 +/- 0.008 < 0.014 -0.004 +/- 0.006 < 0.012 -0.003 :1; 0.007 < 0.015 0.060
/
Cs-137 0.004 +/- 0.009 < 0.015 0.001 +/- 0.008 < O.Q13 -0.002 +/- 0.007 < 0.013 0.080
+/- 0.007 ' Other (Co-60) -0.005 +/- 0.008 < 0.007 0.003 < 0.010 0.001 +/- 0.008 < 0.007 0.060 Location E-09 1=-20 Collection Date 07-22-15 07-22-15 Lab Code EG- 4020 EG- 4021 Req. LLD Ratio (weUdry) 3.67 3.38 Gross Beta 8.01 +/- 0.17 < 0.056 13.74 +/- 0.33 < 0.13 0.25 Be-7 1.39 +/- 0.20 1.43 +/- 0.24 K-40 7.32 +/- 0.51 5.93 +/- 0.48 1-131 ' 0.003 +/- 0.008 < 0.034 0.005 +/- 0.010 < 0.045 0.060 Cs-134 -0.002 +/- 0.007 < 0.014 -0.002 +/- 0.008 < 0.015 0.060 Cs-137 -0.002 +/- 0.008 < 0.016 -0.005 +/- 0.010 < 0.013 0.080 Other (Co-60) 0.009 +/- 0.008 < 0.008 -0.006 +/- 0.013 < 0.012 0.060
( \ 10-2
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual
'* Sample Description and Concentration (pCi/g wet)
MDC MDC MDC . Location E-01 E-02 E-03 Collection Date 10-01-15 10-01-15 10-01-15 Lab Code EG- 5421 EG- 5422 -EG- 5423 Req. LLD Ratio (wet/dry) 2.95 2.79 4.88 Gross Beta 5.11+/-0.19 < 0.079 7.62 +/- 0.26 < 0.11 7.38 +/- 0.22 < 0.072 0.25 Be-7 2.95 +/- 0.31 2.38 +/- 0.28 2.17 +/- 0.27 K-40 4.78 +/- 0.50 5.53 +/- 0.48 6.72 +/- 0.48 1-131 -0.006 +/- 0.013 < 0.031 -0.013 +/- 0.009 < 0.018 -0.007 +/- 0.010 < 0.033 0.060 Cs-134 -0.002 +/- 0.009 < 0.019 0.006 +/- 0.009 < 0.018 0.002 +/- 0.008 < 0.016 0.060 Cs-137 -0.005 +/- 0.012 < 0.018 -0.004 +/- 0.010 < 0.014 0.001 +/- 0.009 < 0.015 0.080 Other (Co-60) -0.003 +/- 0.011 < 0.012 -0.001 +/- 0.011 < 0.011 -0.001 +/- 0.010 < 0.015 0.060 Location E-04 E-06 E-08 Collection Date 10-01-15 10-01-15 10-01-15 Lab Code EG- 5424 EG- 5425 EG- 5426 Req. LLD Ratio (wet/dry) 3.74 3.18 3.78 Gross Beta 8.56 +/- 0.27 < 0.095 4.71 +/- 0.17 < 0.071 7,83 +/- 0.24 < 0.088 0.25 Be-7 2.71 +/- 0.30 2.19 +/- 0.26 2.97:!; 0.25 K-40 6.46 +/- 0.51 3.79 +/- 0.38 4.81 +/- 0.44 1-131 0.001 +/- 0.009 < 0.022 ~0.011 +/- 0.009 < 0.026 0.001 +/- 0.009 < 0.043 0.060 Cs-134 -0.004 +/- 0.008 < 0.016 -0.003 +/- 0.009 < 0.015 -0.002 +/- 0.008 < 0.016 0.060 Cs-137 0.004 +/- 0.010 < 0.017 0.016 +/- 0.011 < 0.018 0.012 +/- 0.010 < 0.016 0.080
/'
Other (Co-60) -0.008 +/- 0.009 < 0.011 0.007 +/- 0.009 < 0.009 -0.005 +/- 0.009 < 0.011 0.060 Location E-09 E-20 Collection Date 10-01-15 10-01-15 Lab Code EG- 5427 EG- 5428 Req . LLD Ratio (wet/dry) 4.50 4.08 Gross Beta 5.77 +/- 0.19 < 0.071 7.20;!: 0.24 < 0.10 0.25 Be-7 2.03 +/- 0.28 2.92 +/- 0.31 K-40 6.01 +/- 0.45 7.55 +/- 0.53 1-131 0.001 +/- 0.009 < 0.024 0.016 +/- 0.010 < 0.051 0.060 Cs-134 0.000 +/- 0.008 < 0.015 -0.006 +/- 0.009 < 0.017 0.060 Cs-137 0.005 +/- 0.009 < 0.019 -0.002 +/- 0.011 < 0.018 0.080 Other (Co-60) 0.000 +/- 0.009 < 0.007 -0.005 +/- 0.010 < 0.012 0.060 Beta Annual Mean +/- s.c;f. 6.81 :t 1.94 13e-7 Annual Mean +/- s.d. 1.59 +/- 0.80 K-40 Annual Mean +/- s.d. 5.42 +/- 1.16 1-131 Annual Mean+/- s.d. 0.000 +/-.0.008 I Cs-134 Annual Me~n +/- s.d. -0.001 +/- 0.003 ! Cs-137 Annual Mean+/- s.d. 0.004 +/- 0.012 Co-60 Annual Mean +/- s.d. -0.005 ;!: 0.005 10-3
POINT BEACH NUCLEAR PLANT Table 11. Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.
\
Collection: Triannual Units: pCi/g wet Sample Description and Concentration Collection Date MDC 08-27-15 MDC Req. Lab Code NSa ESL- 4698 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 6.86 Gross Beta 3.04 +/- 0.13 < 0.11 0.25 Be-7 0.85 +/- 0.09 K-40 2.26 +/- 0.16 Co-58 -0.001 +/- 0.003 < 0.007 0.25 Co-60 0.004 +/- 0.004 < 0.007 0.25 Cs-134 -0.001 +/- 0.004 < 0.007 0.25 Cs-137 0.012 +/- 0.007 < 0.008 0.25 .r'* * \ Annual Mean+/- s.d. Gr. Beta 3.04 Be-7 0.85 K-40 2.26 Co-58 -0.001 Co-60 0.004 Cs-134 -0.001 Cs-137 0.012 a "NS" =No sample. See Table 2.0, Listing of Missed Samples. 11-1
POINT BEACH NUCLEAR PLANT
/ ' Table 12. Ambient Gamma Radiation a Po LLD/7days: < 1mRITLD 1st. Quarter, 2015 Date Annealed: 12-11-14 Days in the field 89 Date Placed: 01-02-15 Days from Annealing Date Removed : 04-01-15 to Readout: 124 Date Read: 04-14-15 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 89 17.7 +/- 0.8 12.5+/-1.0 12.8 +/- 1.0 0.99 +/- 0.08 E-2 89 21.7 :j:0.3 16.5 +/- 0.5 16.9 +/- 0.5 1.30 +/- 0.04 E-3 89 20.9 +/- 1.9 15.8 +/- 2.0 16.1 +/-2.0 1.24 +/- 0.15 E-4 89 20.6+/-1.7 15.4 +/- 1.8 15.7 +/- 1.8 1.21 +/- 0.14 E-5 89 19.8+/-1.3 14.7 +/- 1.4 15.0 +/- 1.4 1.16 +/- 0.11 E-6 89 17.4+/-1 .2 12.3 +/- 1.3 12.5 +/- 1.3 0.97 +/- 0.10 E-7 89 18.1 +/- 1.3 13.0 +/- 1.4 13.3 +/- 1.4 1.02 +/- 0.11 E-8 89 18.6+/-1.5 13.4 +/- 1.5 13.7 +/- 1.6 1.06+/-0.12 E-9 89 22.1 +/- 0.5 16.9 +/- 0.7 17.3 +/- 0.7 1.33 +/- 0.05 E-12 89 16.3+/-1 .1 11 .2 +/- 1.2 11.4 +/- 1.2 0.88 +/- 0.09 E-14 89 19.9+/-1.1 14.7 +/- 1.2 15.1 +/- 1.2 1.16 +/- 0.09 E-15 89 18.2 +/- 0.3 13.1 +/- 0.5 13.4 +/- 0.5 1.03 +/- 0.04 E-16 89 20.5 +/- 0.4 15.3 +/- 0.6 15.7 +/- 0.6 1.20 +/- 0.05 E-168 89 20.8 +/- 0.6 15.6 +/- 0.7 16.0 +/- 0.7 1.23 +/- 0.08 E-17 89 20.4+/-1.0 15.3 +/- 1.1 15.6 +/- 1.1 1.20 +/- 0.09 E-18 89 21.9+/-1.7 16.8 +/- 1.7 17.1 +/- 1.8 1.32 +/-0.13 /' 89 21.4 +/- 1.2 16.3 +/- 1.2 16.6 +/- 1.3 1.28 +/- 0.10 E-22 E-23 89 20.0 +/- 0.9 14.8 +/- 1.0 15.1 +/- 1.0 1.17 +/- 0.08 E-24 89 19.3 +/- 0.8 14.2 +/- 0.9 14.5 +/- 0.9 1.12 +/- 0.07 E-25 89 18.1 +/-0.5 12.9 +/- 0.7 13.2 +/- 0.7 1.02 +/- 0.05 E-26 89 17.5+/-1.1 12.3 +/- 1.2 12.6 +/- 1.2 0.97 +/- 0.09 E-268 89 18.3 +/- 0.3 13.2 +/- 0.5 13.5 +/- 0.5 1.04 +/- 0.04 E-27 89 20.6 +/- 0.7 15.5 +/- 0.8 15.8 +/- 0.8 1.22 +/- 0.06 E-28 89 14.8 +/- 0.4 9.6 +/- 0.5 9.9 +/- 0.5 0.76 +/- 0.04 E-29 89 15.5+/-1.3 10.4 +/- 1.4 10.6 +/- 1.4 0.82 +/- 0.11 E-30 89 17.9 +/- 1.0 12.8 +/- 1.0 13.1 +/- 1.1 1.01 +/- 0.08 E-31 89 21.5 +/- 0.4 16.4 +/- 0.6 16.7 +/- 0.6 1.29 +/- 0.04 E-32 89 20.6 +/- 1.0 15.5+/-1 .1 15.8 +/- 1.1 1.22 +/- 0.09 E-38 89 18.2+/-1 .0 13.0+/-1.1 13.3 +/- 1.1 1.02 +/- 0.09 E-39 89 20.5 +/- 1.2 15.3 +/- 1.3 15.7 +/-1.3 1.21 +/- 0.10 E-41 89 17.6 +/- 0.6 12.4 +/- 0.7 12.7 +/- 0.7 0.98 +/- 0.05 E-42 89 21 .7 +/- 1.2 16.5 +/- 1.2 16.9+/-1 .3 1.30+/-0.10 E-43 89 18.0+/-1 .3 12.9+/-1.3 13.1 +/- 1.4 1.01 +/-0.10 Control E-20 89 21.2 +/- 1.4 16.0 +/- 1.4 16.4 +/- 1.4 1.26 +/- 0.11 Mean+/-s.d. 19.3 +/- 1.9 14.2+/-1.9 14.5 +/- 1.9 1.12 +/-0.15 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-11-14 01-07-15 4.6 +/- 0.4 5.0 +/-0.3 03-24-15 04-14-15 2.4 +/- 0.2 2.5 +/- 0.2
- The CaS04 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the
/ average of the four readings. 12-1
POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mRITLD
\
2nd Quarter, 2015 Date Annealed: 03-24-15 Days in the field 90 Date Placed: 04-01-15 Days from Annealing Date Removed: 06-30-15 to Readout: 105 Dale Read: 07-07-15 Days in mR!Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 90 12.6 +/- 0.8 9.1 +/- 1.0 9.2 +/- 1.0 0.71 +/- 0.08 E-2 90 17.4 +/- 1.2 13.9+/-1.3 14.1+/-1.4 1.08 +/- 0.10 E-3 90 19.0 +/- 1.2 15.6+/-1 .3 15.7 +/- 1.3 1.21 +/-0.10 E-4 90 15.9 +/- 0.7 12.5 +/- 0.9 12.6 +/- 0.9 0.97 +/- 0.07 E-5 90 17.2 +/- 0.4 13.7 +/- 0.7 13.9 +/- 0.7 1.07 +/- 0.06 E-6 90 13.7 +/- 0.4 10.2 +/- 0.7 10.3 +/- 0.7 0.80 +/- 0.05 E-7 90 15.0 +/- 0.2 11 .5 +/- 0.6 11.6 +/-0.6 0.90 +/- 0.05 E-8 90 15.0 +/- 0.9 11.6+/-1.0 11.7 +/- 1.1 0.90 +/- 0.08 E-9 90 16.9 +/-0.7 13.4 +/- 0.9 13.6 +/- 0.9 1.05 +/- 0.07 E-12 90 14.9 +/- 0.2 11.4+/-0.6 11 .6 +/- 0.6 0.89 +/- 0.05 E-14 90 17.2 +/- 1.3 13.7+/-1.5 13.9 +/- 1.5 1.07 +/- 0.11 E-15 90 20.0 +/- 1.7 16.6 +/- 1.8 16.8 +/-1.8 1.29 +/-0.14 E-168 90 16.8 +/- 0.4 13.4 +/- 0.7 13.5 +/- 0.7 1.04 +/- 0.06 E-17 90 18.4 +/- 0.1 15.0 +/- 0.6 15.1 +/- 0.6 1.17 +/-0.05 E-18 90 21 .6 +/- 0.5 18.1 +/- 0.8 18.3 +/- 0.8 1.41 +/- 0.06 E-22 90 18.4 +/- 0.7 14.9 +/- 0.9 15.1+/-0.9 1.16 +/-0.07 E-23 90 20.3 +/- 0.5 16.9 +/- 0.8 17.1 +/- 0.8 1.31 +/- 0.06
/
E-24 90 15.9 +/- 0.3 12.5 +/- 0.6 12.6 +/- 0.6 0.97 +/- 0.05 E-25 90 19.3 +/- 0.5 15.9 +/- 0.8 16.1 +/- 0.8 1.23 +/- 0.06 E-268 90 14.9 +/- 0.6 11.5 +/- 0.8 11.6 +/- 0.8 0.89 +/- 0.06 E-27 90 19.3 +/- 0.6 15.8 +/- 0.8 16.0 +/- 0.8 1.23 +/- 0.06 E-28 90 13.3 +/- 0.2 9.9 +/- 0.6 10.0 +/- 0.6 0.77 +/- 0.05 E-29 90 11.4 +/- 0.4 8.0 +/- 0.7 8.1 +/- 0.7 0.62 +/- 0.06 E-30 90 15.3 +/- 0.6 11.9 +/- 0.8 12.0 +/- 0.8 0.92 +/- 0.06 E-31 90 16.6+/-1 .2 13.1 +/- 1.4 13.3 +/- 1.4 1.02 +/- 0.11 E-32 90 20.3 +/- 0.2 16.8 +/- 0.6 17.0 +/- 0.6 1.31 +/- 0.05 E-38 90 17.1 +/- 0.2 13.7 +/- 0.6 13.8 +/- 0.6 1.06 +/- 0.05 E-39 90 17.5 +/- 0.5 14.1 +/- 0.8 14.2 +/- 0.8 1.09 +/- 0.06 E-41 90 15.7 +/- 0.3 12.2 +/- 0.6 12.4 +/- 0.6 0.95 +/- 0.05 E-42 90 18.7 +/- 0.6 15.2 +/- 0.8 15.4 +/- 0.8 1.18 +/- 0.06 E-43 90 17.7 +/- 0.5 14.3 +/- 0.8 14.4 +/- 0.8 1.11 +/- 0.06 Control E-20 92 16.4 +/- 1.4 12.9+/-1 .5 12.8+/-1 .5 0.98 +/- 0.12 Mean+/-s.d. 16.9 +/- 2.4 13.4 +/- 2.4 13.6 +/- 2.4 1.04 +/-0.18 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 03-24-15 04-14-15 2.4 +/- 0.2 2.5 +/- 0.2 06-08-15 07-07-15 4.3 +/- 0.3 4.6 +/- 0.4
- The CaS0 4:Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.
I ~ 12-2
POINT BEACH NUCLEAR PLANT
/ Table 12. Ambient Gamma Radiation a I
\ LLD/7days: < 1mRITLD 3rd Quarter, 2015 Date Annealed: 06-08-15 Days in the field 86 Date Placed: 06-30-15 Days from Annealing Date Removed: 09-24-15 to Readout: 115 Date Read: 10-01-15 Days in mR!Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 86 20.3 +/- 0.3 16.9 :!: 0.6 17.9 +/- 0.7 1.38 +/- 0.05 E-2 86 20.3 ;1;0.6 16.9 :!: o.8 17.8 +/- 0.9 1.37 +/- 0.07 E-3 86 21.7 +/- 0.9 18.3 +/- 1.1 19.3 :1:1.1 1.49 +/- 0.09 E*4 86 18.1 +/- 1.1 14.7 +/- 1.2 15.5:;!: 1.3 1.19 :!: 0.10 E-5 86 19.0+/-1 .1 15.5 ;1: 1.2. 16.4 +/- 1.3 1.26 :t 0.10 E-6 86 16.2 ;1: 0.8 12.8 +/- 0.9 13.5:!:1.0 1.04 :1:0.08 E-7 86 16.1 :1:0.6 12.7 :!; 0.8 13.4 +/- 0.8 1.03 +/- 0.06 E-8 86 17.7 +/- 1.3 14.2 :1: 1.4 15.1 +/- 1.4 1.16 +/- 0.11 E-9 86 21.0 +/- 0.6 17.6:!; 0.8 18.6 :1: 0.9 1.43 :1:0.07 E-12 86 14.5 +/- 0.7 11 .1 :t 0.9 11.7 +/- 0.9 0.90 +/- 0.07 E-14 86 18.1 +/-0.5 14.7 :1:0.8 15.6 +/- 0.1;3 1.20 +/- 0.06 E-15 86 18.7 +/- 0.6 15.2 +/- 0.8 16.1 :1: 0.9 1.24:!; 0.07 E-16 86 19.4+/-1.1 16.0 +/- 1.2 16.9 +/- 1.3 1.30 +/-0.10 E-168 86 20.5 +/- 0.5 17.0 +/- 0.8 18.0 :1:0.8 1.39 +/- 0.06 E-17 86 19.0 :1:0.9 15.6 +/- 1.1 16.5 +/- 1.1 1.27:!: 0.09 E-18 86 21 .2 +/- 1.1 17.8 :1: 1.2 18.8 +/- 1.3 1.45 +/- 0.10
/
1.1 E-22 86 20.0 +/- 1.2 16.6 +/- 1.3 17.5 :1: 1.4 1.35 +/- 0.11
\ E-23 86 20.0 +/- 0.8 16.6 +/- 0.9 17.6+/-1.0 1.35 +/- 0.08 E-24 86 17.9 +/- 0.6 14.5 +/- 0.8 15.3 +/- 0.8 1.18 +/- 0.06 E-25 86 18.2 +/- 0.5 14.7 :1:0.7 15.6 +/- 0.8 1.20:!: 0.06 E-26 86 18.7 +/- 1.3 15.3 +/- 1.4 16.2+/-1.5 1.25 :1: 0.11 E-268 86 17.1+/-0.7 13.7:!: 0.9 14.5 :1:0.9 1.12 +/- 0.07 E-27 86 20.3 +/-0.5 16.9 ;1: 0.7 17.8 :1:0.8 1.37 +/- 0.06 E:-28 86 14.3 +/- 0.8 10.8:!;1 .0 11.5 +/- 1.0 0.88 +/- 0.08 E-29 86 13.6 +/- 0.8 10.2:!:1.0 10.8+/-1.0 0.83 +/-0.08 E-30 86 16..3:1:1 .1 12.9 ;1: 1.3 13.7 +/- 1.3 1.05 :!;0.10 E-31 86 20.1 +/-0.7 16.7:!: 0.9 17.7+/-0.9 1.36 +/- 0.07 E-32 86 20.7 +/-0.7 17.3 +/- 0.9 18.3+/-1 .0 1.41 +/-0.07 E-38 86 17.2 +/- 0.9 13.7 :t 1.0 14.5 +/- 1.1 1.12 :1; 0.08 E-39 86 20.3 +/- 1.4 16.9+/-1 .5 17.9 :l: 1.6 1.37 :!;0.12 E-41 86 18.2 +/- 0.5 . 14.8 :1:0.8 16.7 :!; 0.8 1.21 +/- 0.06 E-42 86 22.3:!: 0.8 18.8 +/- 0.9 19.9 :1;1.0 1.53 ;1: 0.08 E-43 86 20.5 +/- 1.7 17.1 +/- 1.8 18.1 +/- 1.9 1.39 +/- 0.15
.QQ.n.trQ!
E-20 86 18.8 :!; 1.6 15.3+/-1 .7 16.2+/-1.8 1.25 +/-0.14 Mean+/-s.d. 18.7 +/-2.1 15.3 +/-2.1 16.2:!: 2.3 1.24 +/- 0.18 In-Transit Exposure Date Annealed Date Read ITC-1 !IQ:1 06-08-15 07-07-15 4.3 :t 0,3 4.6 :1; 0.4 09-11.15 10-01-15 2.3 +/- 0.1 2.5 +/- 0.2
- The CaS04: Dy dosimeter cards provide fovr separate readout areas. Values listed represent the mean and standard devi<;~tion of !he
(
- average of the four readings.
12-3
POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Raqiation " ( LLD/7days: < 1mRITLD 4th Quarter, 2015 Pate Annealed: 09-16-14 Days in the field 90 Date Placed: 10-04-14 Days from Annealing Date Removed: 01-02-15 to Readout: 113 Date Reacl: 01-07-15 Pays in mRJStnd Qtr t.ocation Field TotalmR NetmR (91 days) Net mR per 7 days Indicator E-1 90 16.8+/-1.4 13.0 +/- 1.5 13.1 +/-1.5 1.01 +/- 0.12 E-2 90 20.8 +/-0.9 17.0 +/- 1.0 17.2 +/- 1.0 1.32 +/- 0.08 E-3 90 23.1 +/- 1.5 19.3 +/- 1.6 19.6+/-1.6 1.50 +/- 0.12/ E-4 90 19.4 +/-0.4 15.6 +/- 0.6 15.7 +/- 0.6 1.21 +/- 0.05 E-5 90 21.0 +/- 0.4 17.2 +/- 0.6 17.4 +/- 0.1~ 1.34 +/- 0.05 E-6 90 17.6 +/- 0.5 13.8 :!; 0.7 14.0 +/- 0.7 1.08 +/- 0,05 E-7 90 18.3 +/- 0.2 14.5 +/- 0.5 14.7 +/- 0.5 1.13 +/- 0.04/ E-8 90 18.8 +/- 0.7 15.0 +/- 0.8 15.2 +/- 0.9 1.17+/-0.07 E-9 90 19.4 +/- 0.6 15.6 +/- 0.7 15.7 +/- 0.7 1.21 +/- 0.06 E-12 90 17.4+/-1.2 13.6 +/- 1.3 13.8+/-1.3 1.06+/-0.10 E-14 90 21.3 +/- 1.8 17.5+/-1.9 17.7 +/- 1.9 1.36 +/- 0.15 E-15 90 23.0 +/- 1.0 19.2 +/- 1.1 19.4 +/- 1.1 1.50 +/- 0.09
*~ .
1;:-166 90 20.2 +/-0.2 16.4 +/- 0.5 16.6 +/- 0.5 1.27 +/- 0.04 E-17 90 22.6:;!: 0.7 18.8 +/- 0 . ~ 19.0 +/- 0.8 1.46 +/- 0.06 E-18 90 23.2 :l; 0.9 19.4+/-1.0 19.6:!;: 1.0 1.51:!; 0.08/ E-22 90 23. 1 +/-0.9 19.3+/-1.1 19.5:!; 1.1 1.50:!; 0.08
/ E-23 90 25.2 :!:0.6 21.4 +/-0.8 21.6 +/- 0,8 1.66 +/- 0.06 . / \ E-24 90 20.4 +/-0.5 16.6 +/- 0.7 16.8 :t 0.7 1.29 +/- 0.06 .\
E-25 90 21 .1+/-0.6 17.3:!; 0.9 17.5 +/-0.9 1.35 +/- 0,07/ E:-268 90 19.2 +/- 0.2 15.4;!: 0.5 15.6 +/- 0.5 1.20 +/- 0.04 E-27 90 23.6 +/- 0,8 19.8 ;!: 0.9 20.0 :1:0.9 1.54 +/- 0.07 E-28 90 16.8 ;j: 0.3. 13.0 +/- 0.6 13.2 t. 0.5 1.01 +/- 0.-04 E*29 90 14.6 +/- 0.6 10.8 ;t 0.13 10.9:!; 0.6 0.84 :1; 0.06
!':-30 90 20.2 +/- 0.8 16.4 ;!; 0.9 16.6 +/- 0.9 1.28 ;l; 0.07 E-31 90 20.6 :;t 1.2 16.8 +/- 1.3 17.0:!:1.3 1.30 +/- 0.10 E-32 90 25.1 :j: 0.5 21.3 +/-0.7 21.6 :j: 0.7 1.()6;!:: 0.05 /
E-36 90 20.1 +/- 0.4 16.3 +/- 0.6 16.5:!: 0.7 1.27 +/- 0.05 E-39 90 20.5:!: 0.8 16.7 +/- 0.9 16.9 ;t 0.9 1.30 +/- 0.07 E-41 90 19.4 +/- 0.5 15.6 +/- 0.7 15.8 +/- 0.7 1.21 :;!; 0.05 E;-42 90 22.0 +/-0.7 18.2 +/- 0.9 18.4 +/- 0.9 1.42 +/- 0.07
~-43 90 21.5 +/- 0.7 17.7 +/- 0.8 17.9 +/- 0,9 1.38 +/- 0.07 Control E-20 90 20.5 +/- 1.9 16.7 :\:2.0 16.9 +/- 2.0 1.30 +/- 0.15 Mean+/-s.d. 20.1 +/- 1.5 16.7 :!: 2.4 19.7 +/- 1.5 1.30 +/- 0.19 In-Transit Exposure Date Annealed Date Read n:c~1 ITC-2 Or.:l-11-15 10-01-15 2.3 +/- 0.1 2.5 +/- 0.2 12-08-15 01-09-16 5.2 +/- 0.3 5.,4 +/- 0.3
- Thl;l CaS04 : Dy dosimeter cards provide fow ~>ep<;~rate reado\Jt areas. Values listed represent the mean and standard deviation of the average of the four readings.
Annual Indicator Mean;ts.d. 18.9 +/- 2.p 14,~:!: 2.9 15.3 +/- 2.6 1.2 +/- 0.2 I Annual Control Mean;!;s.d. 19.2:!: 2.2 15.3 t 1.7 15.6 +/- 1.9 1.2 +/-0.1 .:, Annual Indicator/Control Mean;J:s.d. 18.9 +/- 2.6 14.9 +/-2.5 15.3 2.6 1.2 +/- 0.2 1~-4
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections) I Units= Ci/L I Intermittent Streams S!lm~le ID GW-01 GW-02 Collection Collection Date Lab Code Tritium MDC Date Lab Coqe Tritium MDC 01-22-15 NS" 01-22-15 Ns* 02-25-15 Ns* 02-25-1 5 NS" 03-25-15 EWW-1247 167 ;!: 80 < 147 03-25-15 EWW- 1248 270 +/- 8(i < 147 04-29-15 EWW-2019 136 +/- 80 < 147 04-29-16 EWW-2020 222 +/- 84 < 147 05-20-15 EWW-2643 106 ;!: 80 < 150 05-29-15 EWW-2644 3 +/- 75 < 160 06-24-15 EWW-3233 123 +/- 78 < 143 06-24-15 EWW-3234 184 +/- 81 < 143 07-23-15 EWW-4150 124 +/- 81 < 143 07-23-15 EWW- 4151 83 +/- 79 < 143 08 15 EWW-4699 77 +/- 70 < 145 08-27-15 EWW-4700 173 +/- 81 < 145 09-30-15 EWW-5373 143 +/- 81 < 147 09-30-15 EWW-5374 189 +/- 83 < 147 10-28-15 EWW- 6222 39 ;!: 72 < 141 10-28-15 EWW- 6223 69 +/- 74 < 141 11-25-15 EWW-6682 53+/- 74 < 144 11 15 EWW-6683 163;!: 80 < 144 12-30-15 EWW- 7226 70;!: 75 < 144 12-30-15 EWW- 7227 122 ;!: 78 / < 144 Mean +/-s.d. 104 +/-42 Mean +/- s.d. 148 +/- 79 Sam~leiD GW-03 GW-17 Collection Collection Date Lab Code Trili!Jm MDC Date Lab Code Tritium MDC Q1 15 NS" 01-22-15 NS" 02-25-15 NS* 02-25-15 Ns* 03-25-15 EWW-1249 93 +/- 76 < 147 03-25-15 EWW- 1251 196 +/- 81 < 147 04-29-15 EWW-2021 107 +/- 79 < 147 04-29-15 EWW-2023 220 :!; 84 < 147 05-20-15 t;WW- 2645 129 +/- 81 " 150 05-20-15 EWW-2647 131 +/- 81 < 150 06-24-15 EWW-3235 -4 +/- 71 < 143 06-24-15 EWW-3237 174 +/- 80 " 143 07-23-15 EWW- 4152 141 +/- 82 < 143 07-23-15 EWW-4154 221 +/- 86 < 143
/ 08-27-15 EWW-4701 117 +/- 78 < 145 08 15 EWW-4703 138 +/- 79 < 145
', 09-30-15 EWW- 5375 113 +/- 79 < 147 09-30-15 EWW-5377 220 +/- 8(5 < 147
' 10-28-15 EWW-6224 45 +/- 73 < 141 10-28-15 EWW-6226 112 +/- 76 < 141 11-25-15 EWW- 6684 -27 +/- 70 < 144 11 15 EWW- 6686 97 +/- 77 < 144 12-30-15 EWW-7228 45 +/- 74 < 144 12-30-15 NSb Mean+/- s.d. 76 +/-58 . Mean +/-s.d. 168 :!; 49 Wells Samele 10 GW-04 (EIC Well)
Collection Date Lab Code Tritium MDC 01-22-15 EWW-327 -78 +/- 90 < 192 01-22-15 EWW-676 -39 +/- 72 < 142 03-25-15 EWW-1250 19 +/- 72 < 147 04-29-11> EWW- 2022 13 +/- 74 < 147 05-20-15 EWW-2646 -3 +/- 74 < 150 06 15 EWW-3236 2 +/- 71 < 143 07-23-15 EWW-4153 48;!: 77 < 143 08-27-15 EWW-4702 -24 ;!: 70 < 145 09-30-15 EWW-5376 - 101 +/- 67 < 147 10-28-15 EWW-6~25 14 +/- 71 < 141 11-25-15 EWW-6685 -25 +/- 70 < 144 12-30-15 EWW-7229 51 +/- 74 < 144 Mean :!; s.d. ;1(j +/- 46
- Water tfozen.
b No sample. ( I 13-1
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)
/ Units= Ci/L
\ Beach Drains Sam le ID S-1 S-3 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 EWW-1355 355 +/- 95 < 148 04-02-15 EWW-1356 316 +/- 93 < 148 04-2~-15 EWW-1778 134 +/- 86 < 150 04-22-15 EWW-1779 430 +/- 99 < 150 05-06-15 EWW-2222 200 :!: 87 < 147 05-06-15 EWW-22.23 302 +/- 92 < 147 06-02-15 EWW-2748 212 +/- 87 < 155 06-02-15 EWW-2749 190 +/- 86 < 155 07-09-15 EWW-3622 160 +/- 100 < 154 07-09-15 EWW-3623 262 +/- 104 < 154 08-05-15 EWW-4340 122 +/- 85 < 150 08-05-15 EWW-4341 644 +/- 107 < 150 09-10-15 EWW-4990 205 +/- 84 < 148 09-10-15 EWW-4991 249 +/- 87 < 148 10-07-15 EWW-5629 244 +/- 86 < 149 10-07-15 EWW-5631 165 :!: 82 < 149 11-05-15 EWW-6408 342 +/- 92/ < 151 11-05-15 EWW-6409 219 +/- 86 < 151 12-10-15 EWW-6935 292 +/- 87 " 145 12-10-15 EWW-6936 152 +/- 80 / < 145 Mean +/-s.d. 227 +/- 81 Mean +/-s.d. 293 +/- 148 Sam ie ID S-7 S-8 Collection Collection Date Lab Code Tritium MDC Date L.ab Codt;J Tritium MDC 01 15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 NF" 04-02-15 NF" 04-22-15 NF" 04-22-15 NF" 05-06-15 NF" 05-06-15 NF"
,/ 06-02-15 NF" 06-02-15 NF" 07-09-15 NF" 07-09-15 NF" 08-05-15 NF" 08-05-15 NF" 09-10-15 NF" 09-10-15 NF" 10-07-15 NF" 10-07-15 NF" 11-05-15 NF" 11-05-15 NF 0 12-10-15 NF" 12-10-15 NF" Mean +/-s.d. Mean;!: s.d.
Sam[;!le ID S-9 8-10 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 NF" 04-02-15 NF" 04-22-15 NF" 04-22-15 NF" 05-06-15 NF" 05-06-15 NF" 06-02-15 NF" 06-02-15 NF" 07-09-15 NF" 07-09-15 NF" 08-05-15 NF" 08-05-15 NF" 09-10-15 NF" 09-10-15 NF" 10-07-15 NF" 10-07-15 NF" 11-0!i-15 NF" 11-05-15 NF" 12-10-15 NF" 12-10-15 NF" Mean +/-s.d. Mean +/-s.d.
* "NF" =No flow.
/ 13-2
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections) Units= Ci/L Beach Drains (cont.) Sam le ID S-11 Collection Date Lab Code Tritium MDC 01-10-15 NFa 02-10-15 NFa 04-02-15 EWW-1357 210 +/- 88 < 148 04-22-15 EWW-1780 214 +/- 90 < 150 05-06-15 NFa 06-02-15 NFa 07-09-15 NFa 08-05-15 NFa 09-10-15 NFa 10-07-15 NFa 11 15 NFa 12-10-15 NFa Mean+/- s.d. 212 +/- 3 Sample ID U2 Fa~ade Subsurface Drain Sump Collection Collection Date Lab Code Date Lab Code Tritium MDC Tritium MDC 01-20-15 EW- 508 682 +/- 135 < 196 02-15-15 EW- 993 721 +/- 107 < 148 03-26-15 EW- 1501 475 +/- 102 < 152 04-30-15 EW- 2227 648 +/- 106 < 147 06-02-15 EW- 2747 741 +/- 109 < 155 06-30-15 EW- 4025 591 +/- 105 < 149 08-31-15 EW- 4951 577 +/- 104 < 147 09-30-15 EW- 6410 306 +/- 91 < 144 10-31-15 EW- 6411 683 +/- 103 < 143 12-07-15 EW- 6978 568 +/- 98 < 146 12-31-15 EW- 7465 496 +/- 112 < 152 Mean+/- s.d. 590 +/- 128 a "NF" = No flow. 13-3
POINT BEACH NUCLEAR PLANT Beach Drains r\ Units: =pCi/L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 01-10-15 01-10-15 01-10-15 01-10-15 3 Lab Code NFa MDC NF MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-9 S-1*0 S-11 S-1 Collection Date 01-10-15 01-10-15 01-10-15 02-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54
/
Fe-59 Co-58
\.
Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-3 S-7 S-8 S-9 Collection Date 02-10-15 02-10-15 02-10-15 01-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow. ( 13-4
POINT BEACH NUCLEAR PLANT
\ Beach Drains (cont.)
Units: = pCi\L Gamma isotopic analysis Location S-10 S-11 S-1 S-3 Collection Date 02-10-15 02-10-15 04-02-15 04-02-15 Lab Code NF" MDC NF" MDC EW- 1355 MDC EW- 1356 MDC Be-7 5.9 +/- 6.3 < 17.4 2.7 +/- 5.9 < 14.7 Mn-54 -0.6 +/- 0.6 < 0.8 0.3 +/- 0 .6 < 1.1 Fe-59 1.4 +/- 1.2 < 3.1 -0.1 +/- 1.2 < 3.1 Co-58 0.2 +/- 0.6 <1.4 0.5 +/- 0.5 < 1.2 Co-60 0.1 +/- 0.6 < 1.1 -0.3 +/- 0.6 < 1.1 Zn-65 0.7 +/- 1.5 < 2 .8 -0.4 +/- 1.3 < 2 .5 Zr-N~-95 -0 .8 +/- 0.7 < 1.5 0.8 +/- 0.6 < 1.7 Cs-134 0.3 +/- 0.7 < 1.3 0.3 +/- 0.6 < 1.2 Cs-137 1.0 +/- 0.8 <1.4 0.0 +/- 0.7 < 1.2 Ba-La-140 -2.1 +/- 0.7 < 2.3 -0.9 +/- 0.7 < 3.2 Location S-7 S-8 S-9 S-10 Collection Date 04-02-15 04-02-15 04-02-15 04-02-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 ( Fe-59
' Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-1 I'"
S-3 S-7 Collection Date 04-02-15 04-22-15 04-22-15 04-22-15 Lab Code EW- 1357 EW- 1778 EW- 1779 NF" Be-7 1.6 +/- 4.7 < 14.4 2.2 +/- 4.7 < 14.3 -4.3 +/- 10.3 < 27.8 Mn-54 0.6 +/- 0.6 < 1.1 -0.2 +/- 0.6 < 0.8 -1.4 +/- 1.3 < 2.3 Fe-59 -0.5 +/- 1.1 < 1.7 -0.3 +/- 1.0 < 2.6 -0.2 +/- 2.1 < 2.9 Co-58 0.1 +/- 0.6 < 1.4 0.3 +/- 0.6 < 1.1 -0.7 +/- 1.1 < 1.5 Co-60 -0.3 +/- 0.6 < 1.2 0.2 +/- 0.6 < 0.9 0.1 +/- 1.2 < 1.7 Zn-65 0.2 +/- 1.1 < 2.1 0.0 +/- 1.1 < 2.2 0.2 +/- 2.0 < 2.8 Zr-Nb-95 -0.3 +/- 0.6 < 1.6 -0.4 +/- 0.6 < 1.7 -1.1 +/- 1.4 < 2.2 Cs-134 0.4 +/- 0.6 < 1.1 -0.5 +/- 0.6 < 1.1 -1.7 +/- 1.'2 < 2.2 Cs-137 0.5 +/- 0.7 < 1.3 0.1 +/- 0.7 < 1.1 1.5 +/- 1.4 < 2.6 Ba-La-140 -0.5 +/- 0.7 < 3.5 0.1 +/- 0.6 < 5.7 -3.0 +/- 1.4 < 3:2 a "NF" = No flow.
/
I 13-5
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-8 S-9 S-10 S-11 MDC Collection Date 04-22-15 04-22-15 04-22-15 04-22-15 Lab Code NF" MDC NF" MDC NF" MDC EW- 1780 MDC Be-7 -0.2 +/- 13.5 < 28.1 Mn-54 0.5 +/- 1.3 < 2.7 Fe-59 2.2 +/- 2.8 < 5.9 Co-58 -0.5 +/- 1.3 < 2.1 Co-60 0.4 +/- 1.1 < 1.9 Zn-65 -0.5 +/- 3.0 < 3.3 Zr-Nb-95 0.5 +/- 1.4 < 3 .3 Cs-134 -1.0+/-1 .3 < 2.6 Cs-137 0.2 +/- 1.4 < 1.9 Ba-La-140 .- 1.9 +/- 1.5 < 5.5 Location S-1 S-3 S-7 S-8 Collection Date 05-06-15 05-06-15 05-06-15 05-06-15 Lab Code EW- 2222 EW- 2223 NF" NF" MDC Be-7 -0.1 +/- 6.3 < 15.2 5.8 +/- 4 .9 < 16.1 Mn-54 0.3 +/- 0.6 < 1.2 0.3 +/- 0.6 <1.4 Fe-59 0.4 +/- 1.2 < 3.7 -1.6+/-1.0 < 1.9 Co-58 -1 .0 +/- 0.6 < 1.0 0.0 +/- 0.6 <1.4
/
Co-60 0.6 +/- 0.6 < 1.3 0.5 +/- 0.6 < 1.2
*, Zn-65 -0.2 +/- 1.3 < 2.0 0.3 +/- 1.2 < 2.5 Zr-Nb-95 - 0.7 +/- 0.7 < 1.3 -0.2 +/- 0.6 < 1.3 Cs-134 -0.1 +/-0.7 < 1.3 0.3 +/- 0.6 < 1.1 Cs-137 0.4 +/- 0.7 <1.4 0.5 +/- 0.7 < 1.1 Ba-La-140 -1.9+/-0.7 < 5.0 -3.4 +/- 0.7 < 4.6 Location S-9 S-10 S-11 S-1 Collection Date 05-06-15 05-06-15 05-06-15 06-02-15 Lab Code NF" MDC NF" MDC NF" MDC . EW- 2748 Be-7 -7.7 +/- 9.9 <19.4 Mn-54 0.7 +/- 1.2 < 2.4 Fe-59 -0.7 +/- 2.3 < 3.6 Co-58 -0.8 +/- 1.1 < 1.3 Co-60 -0.9 +/- 1.5 < 1.9 Zn-65 -2.5 +/- 2.8 < 4.3 Zr-Nb-95 -1.1 +/- 1.4 < 2.3 Cs-134 0.8 +/- 1.1 < 2.3 .
Cs-137 0.4 +/- 1.4 < 1.9 Ba-La-140 -0.9 +/- 1.4 < 3.5 a "NF" =No flow. .( 13-6
POINT BEACH NUCLEAR PLANT
/
Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 06-02-15 06-02-15 06-02-15 06-02-15 Lab Code EW- 2749 MDC NF" MDC NF" MDC NF" MDC Be-7 4.8 +/- 11.3 < 30.0 Mn-54 -0.3 +/- 1.2 < 1.9 Fe-59 1.4 +/- 2.0 < 3.1 Co-58 0.9 +/- 1.3 < 2.2 Co-60 -0.3 +/- 1.5 < 1.6 Zn-65 -1.5+/-2.8 < 3.2 Zr-Nb-95 0.8 +/- 1.5 < 4.4 Cs-134 0.2 +/- 1.3 < 2.3 Cs-137 -0.5 +/- 1.4 < 2.1 Ba-La-140 -0.8 +/- 1.4 < 2.5 Location S-10 S-11 S-1 S-3 Collection Date 06-02-15 06-02-15 07-09-15 07-09-15 Lab Code NF" NF" EW- 3622 EW- 3623 Be-7 -8.7 +/- 12.5 < 32.1 9.1 +/- 20.0 < 47.7 Mn-54 -1.3 +/- 1.4 < 1.8 1.2 +/- 2.2 < 3.7 Fe-59 -1 .5 +/- 2.8 < 3.8 0.6 +/- 4.0 < 4.9 ( Co-58 0.1 +/- 1.3 < 1.5 1.0 +/- 1.7 < 2.4 Co-60 1.3 +/- 1.4 < 2.0 0.8 +/- 2.0 < 2.3 Zn-65 0.6 +/- 3.2 < 5.6 -3.1 +/- 4.9 < 7.2 Zr-Nb-95 -0.3 +/- 1.5 < 2.7 -0.9 +/- 2.3 < 5.7 Cs-134 -0.5 +/- 1.3 < 2.7 0.7 +/- 2.0 < 3.9 Cs-137 -1.3+/-1.7 < 2.2 -0.7 +/- 2.2 < 3.4 Ba-La-140 -2.9 +/- 1.8 < 2.7 -4.5 +/- 2.8 < 6.5 Location S-7 S-8 S-9 S-10 Collection Date 07-09-15 07-09-15 07-09-15 07-09-15 Lab Code NF" NF" NF" NF" Be-7 < 47.7 Mn-54 < 3.7 Fe-59 < 4.9 Co-58 < 2.4 Co-60 < 2.3 Zn-65 < 7.2 Zr-Nb-95 < 5.7 Cs-134 < 3.9 Cs-137 < 3.4 Ba-La-140 < 6.5 a "NF" = No flow. / 13-7
POINT BEACH NUCLEAR PLANT
/
Beach Drains (cont.)
\
Units: = pCi\L Gamma isotopic analysis Location S-11 S-1 S-3 S-7 Collection Date 07-09-15 08-05-15 08-05-15 08-05-15 Lab Code NF" MDC EW- 4340 MDC EW- 4341 MDC NF" MDC Be-7 -0.1 +/- 11.4 < 30.6 0.3 +/- 12.1 < 29.3 Mn-54 1.2 +/- 1.6 < 2.6 -0.2 +/- 1.6 < 3.1 Fe-59 0.9 +/- 2.7 < 5.2 -1.7 +/- 2.6 < 4.0 Co-58 -1.0+/-1.5 < 2.8 -1.1 +/- 1.3 <1.4 Co-60 -0.2 +/- 1.4 < 1.3 0.4 +/- 1.4 < 1.1 Zn-65 0.7 +/- 2.7 < 2.5 -0.6 +/- 2.8 < 2.4 Zr-Nb-95 0.7 +/- 1.6 < 3.0 0.7 +/- 1.5 < 3.5 Cs-134 0.1 +/- 1.4 < 2.4 -0.9 +/- 1.5 < 2.5 Cs-137 2.0 +/- 1.7 < 2.8 1.3 +/- 1.6 < 2.9 Ba-La-140 2.3 +/- 1.1 < 3,1 1.6 +/- 1.8 < 5.6 Location S-8 S-9 S-10 S-11 Collection Date 08-05-15 08-05-15 08-05-15 08-05-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 I' Co-58
'\. Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S.3 S-7 S-8 Collection Date 09-10-15 09-10-15 09-10-15 09-10-15 Lab Code EW- 4990 EW- 4991 NF" NF" Be-7 25.4 +/- 16.0 < 36.2 3.0 +/- 11.6 < 26.7 Mn-54 0.1 ;t 1.5 < 2.9 0.6 :J; 1.3 < 2.4 Fe-59 - 7.3 :J; 3.9 < 4.9 1.4 +/- 2.1 < 2.9 Co-58 0.2 +/- 1.4 < 3.3 -0.8 +/- 1.3 < 2.3 Co-60 -0.2 +/- 1.7 < 1.0 0.5 +/- 1.2 < 1.7 Zn-65 2.2 +/- 3.2 < 2.0 1.0 +/- 2.7 < 3.8 Zr-Nb-95 0.4 +/- 1.4 < 3 .5 1.1 +/- 1.3 < 3.5 Cs-134 0.3 +/- 1.8 < 3.3 0.7 +/- 1.2 < 2.5 Cs-137 0.5 :j: 1.7 < 3.6 0.8 +/- 1.5 < 2.5 Ba-La-140 7.7 +/- 1.7 < 8.6 1.1 +/- 1.5 < 6.7 a "NF" = -No flow.
( 13-8
POINT BEACH NUCLEAR PLANT I' Beach Drains (cont.)
\
Units: = pCi\L Gamma isotopic analysis I Location S-9 S-10 ' S-11 S-1 Collection Date 09-10-15 09-10-15 09-10-15 10-07-15 Lab Code NF" MDC NFa MDC NF" MDC EW- 5629 MDC Be-7 -4.4 +/- 21.7 < 29.4
. Mn-54 1.1 +/- 2 .5 < 3.6 Fe-59 2.5 +/- 5.5 < 4.9 Co-58 -2 .5 +/- 2.7 < 3.2 Co-60 1.3 +/- 2.6 < 4.6 Zn-65 2.8 +/- 6.3 < 5 .1 Zr-Nb-95 2.7 +/- 2.9 < 5.7 Cs-134 -0.6 +/- 2.7 < 4.8 Cs-137 0.9 +/- 2.8 < 4.2 Ba-La-140 4.9 +/- 3.1 < 7.6 Location S-3 S-7 S-8 S-9 Collection Date 10-07-15 10-07-15 10-07-15 10-07-15 Lab Code EW- 5631 NF3 NF" NF" Be-7 -33.1 +/- 26.9 < 36.9 Mn-54 0.0 +/- 2.9 < 4.6 Fe-59 -3.6 +/- 5.3 < 4.9 / Co-58 -2 .1 +/- 2.8 < 4.0 \ Co-60 1.0 +/- 2.6 < 3.8 Zn-65 -30.1 +/- 9.8 < 11 .9 Zr-Nb-95 -13.5 +/- 3.9 < 9.8 Cs-134 -1 .8 +/- 2.7 < 4.6 Cs-137 0.3 +/- 3.2 < 5.7 Ba-La-140 -0.7 +/- 4.5 < 13.4 Location S-10 S-11 S-1 S-3 Collection Date 10-07-15 10-07-15 11 15 11 15 Lab Code NF" NF" EW- 6408 EW- 6409 Be-7 6.6 +/- 21.4 < 38.8 8.3 +/- 9.1 < 30.1 Mn-54 1.1 +/- 2.7 < 4.2 0.6 +/- 1.2 < 1.8 Fe-59 -8.9 +/- 5.1 < 5 .8 0.4 +/- 2.0 < 5.8 Co-58 -2.1 +/- 2.6 < 3 .0 0.3 +/- 1.1 < 2.4 Co-60 3.5 +/- 2.8 < 5.3 0.7 +/- 1.2 < 2.4 Zn-65 -4.5 +/- 5.2 < 6.8 -2.3 +/- 2.6 < 2.7 Zr-Nb-95 1.9 +/- 2.9 < 5.6 0.6 +/- 1.1 < 1.9 Cs-134 -1 .9 +/-2.6 < 5.0 -0.5 +/- 1.1 < 2.1 Cs-137 0.6 +/- 3.0 < 5 .3 -1.3 +/- 1.3 < 1.1 Ba-La-140 -0.3 +/- 3.2 < 8.0 -4.3 +/- 1.4 < 6.8 a "NF" = No flow.
( 13-9
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-7 S-8 S~9 S-10 Collection Date 11-05-15 11-05-15 11-05-15 11-05-15 Lab Code NF" MDC NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-1 S-3 S-7 Collection Date 11-05-15 12-10-15 12-10-15 12-10-15 Lab Code NF" EW- 6935 MDC EW- 6936 MOC NF" MOC Be-7 -1.0 +/- 15.9 < 34.5 9.0 +/- 13.1 / < 17.2 Mn-54 0.7 +/- 1.6/ < 2.5 0.1 :t 1.3 < 1.2 Fe-59 1.5 +/- 3.2 < 4.2 -0.4 +/- 3.1 < 4.7
/
Co-58 0.2 +/- 1.6 < 2.3 0.6 +/- 1.3 < 1.9 '- Co-60 -1.0 +/- 1.6/ < 1.3 -0.1 +/- 1.7 < 2.2 Zn-65 3.9 +/- 3.8 < 6.4 2.0 +/- 3.1 / < 2.7 Zr-Nb-95 n1 ,8 +/-. 1,7 < 2.6 0.1 +/- 1.4 < 2.6 Cs-134 0.5 +/- 1.5 < 2.9 0.2 +/- 1.5 < 2.9 Cs-137 n1,2 :I; 2.1 < 2.9 0.5 ;I; 1.6 < 2.5 Ba-La-140 0.3 +/- 1.4 < 3.7 0.4 ::!; 1.7 < 6.2 Location S-8 S-9 S-10 S-11 Collection Date 12-10-15 12-10-15 12-10-15 12-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow. 13-10
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Annual All locations Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. Be-7 1.0 +/- 9.6 Co-58 -0.3 +/- 0.9 Zr/Nb-95 -0.4 +/- 2.8 Ba/La-140 -0.2 +/- 2.6 Mn-54 0.2 +/- 0.7 Co-60 0.3 +/- 0.9 Cs-134 -0.2 +/- -0.8 Fe-59 -0.5 +/- 2.6 Zn-65 -1.2 +/- 6.1 Cs-137 0.3 +/- 0.8 13-11
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) Units= Ci/L Quarter!~ Wells Sample ID GW-05 (WH 6 Well) GW-06 {SBCC Well) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-15-15 EWW-142 36 +/- 102 < 165 01-15-15 EWW-143 39 +/- 102 < 165 04-15-15 EWW-1665 -47 +/- 76 < 158 04-15-15 EWW-1666 -76 +/- 74 < 158 07-09-15 EWW- 3619 -44 +/- 91 < 154 07-09-15 EWW- 3620 -48 +/- 91 < 154 10-07-15 EWW- 5626 19 +/- 75 < 149 10-07-15 EWW- 5627 -8 +/- 73 < 149 Mean+/- s.d. -9 +/-43 Mean+/- s.d. -23 +/-50 Samele ID GW-11 {MW-1) GW-12 (MW-2) Collection Collection Date Lab Code Tritium MOC Date Lab Code Tritium MDC 8 01-21-15 EWW- 513 -10 +/- 96 < 196 01-21-15 NS 04-24-15 EWW- 2036 -72 +/- 80 < 159 04-24-15 EWW- 2038 -168 +/- 75 < 159 07-09-15 EWW- 4155 130 +/- 82 < 143 07-09-15 EWW- 4156 54+/- 78 < 143 10-19-15 EWW- 6214 108 +/- 76 < 141 10-19-15 EWW- 6215 12 +/- 71 < 141 Mean+/- s.d. 39 :1:96 Mean+/- s.d. Sample ID GW-13 {MW-6) GW-14A (MW-05A) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-21-15 EWW- 514 -83 +/- 91 < 196 01-21-15 EWW- 515 29 :1; 99 < 196 04-24-15 EWW- 2039 -145 +/- 76 < 159 04-24-15 EWW- 2040 -101 +/- 78 < 159 07-09-15 EWW- 4157 159 +/- 83 < 143 07-09-15 EWW- 4158 139 +/- 82 < 143
' 10-19-15 EWW- 6216 134 :1; 77 < 141 10-19-15 EWW- 6217 91 +/- 75 < 141 Mean+/- s.d. 16 +/- 153 Mean+/- s.d. 39 +/- 104 Sample ID GW-15A (MW-4) GW-158 (MW-4)
Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-21-15 EWW-516 96 +/- 103 < 196 01-21-15 EWW- 517 131 +/- 105 < 196 04-24-15 EWW- 2041 -18 :;1: 83 < 159 04-24-15 EWW- 2042 -32 +/- 82 < 159 07-09-15 EWW-4160 284 +/- 89 < 143 07-09-15 EWW- 4161 278 +/- 89 < 143 10-19-15 EWW- 6219 187 +/- 80 <. 141 10-19-15 EWW- 6220 181 :l;: 80 < 141 Mean+/- s.d. 137 +/- 129 Mean:!: s.d. 139 +/- 130 Sample ID GW-16 (MW-3) Collection Date Lab Code Tritium MDC 01-21-15 EWW- 518 147 +/- 106 < 196 04-24-15 EWW- 2043 186 +/- 81 < 152 07-09-15 EWW- 4162 199 +/- 85 < 143 10-19-15 EWW- 6221 179 :t: 80 < 141 Mean+/- s.d. 178 +/-22 a Water frozen. ~ 13-12
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) f Units= Ci/L Quarterly Wells (cont.) Sample ID GW-18 (WH 7 Well) Collection Date Lab Code Tritium MDC 01-15-15 EWW- 144 62 +/- 104 < 165 04-16-15 EWW-1667 23 +/- 80 < 158 07-09-15 EWW- 3621 -23 +/- 92 < 154 10-07-15 EWW- 5628 19 +/- 75 < 149 Mean +/-s.d. 21 +/-35 Facade Wells Sample ID GW-09 1Z-3.61A GW-09 1Z-361 B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 02-27-15 EWW- 867 307 +/- 91 < 151 02-27-15 EWW- 868 147 +/- 83 < 151 04-12-15 EWW- 2515 287 +/- 107 < 183 04-12-15 EWW- 2516 91 +/- 100 < 183 08-08-15 EWW-4709 253 +/- 87 < 150 08-08-15 EWW- 4710 50+/- 77 < 150 10-15-15 EWW- 6210 346 +/- 88 < 141 10-15-15 EWW- 6211 51 +/- 73 < 141
/
Mean+/- s.d. 298 +/-39 Mean+/- s.d. 85 +/-46 Sample ID GW-10 2Z-361A GW-1 0 2Z-361 8 Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 02-27-15 NSa 02-27-15 EWW- 869 68 +/- 79 < 151 04-12-15 EWW- 2517 35 +/- 98 < 183 04-12-15 EWW- 2518 64 +/- 99 < 183 08-08-15 EWW- 4711 54+/- 77 < 150 08-08-15 EWW- 4712 101 +/- 80 < 150 10-15-15 EWW- 6212 61 +/- 74 < 141 10-15-15 EWW- 6213 120 +/- 77 < 141 Mean+/-s.d. 50+/- 14 Mean+/- s.d. 88 +/-27 (Annual Collections) Units= Ci/L Bogs Sample ID GW-07 (North Bo£1) GW-08 EIC Bo£1 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 05-06-15 EWW- 2224 135 +/- 84 < 147 05-06-15 EWW-2225 275 +/- 91 < 147 a Water frozen. I" 13-13
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program
/ Units = pCi/L Manholes Sample ID MH Z-065A MH Z-0658 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d.
Sample ID MH Z-065C MH Z-065D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCI/L) Date (pCi/L) 8 04-23-15 NS 04-23-15 NS 8 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean +/- .s.d. Sample ID MH Z-066A MH Z-0668 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCI/L) Date (pCi/L) 04-23-15 EW- 2044 77 +/- 76 < 152 04-23-15 EW- 2045 58+/- 75 < 152
/
09-28-15 EW- 5400 163 :1: 83 < 149 09-28-15 EW- 5401 24 +/- 75 < 149 Mean +/-s.d. 120 +/- 61 Mean+/- s.d. 41 +/-24 Sample ID MH Z-066C MH Z-066D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCIIL) Date (pCi/L) 04-23-15 EW- 2046 38 +/- 73 < 152 05-01-14 EW- 2047 153 +/- 80 < 152 09-28-15 EW- 5402 153 +/- 82 < 149 09-28-15 EW- 5403 212 +/- 85 < 149 Mean+/- s.d. 95 +/-81 Mean+/- s.d. 182 +/- 41 samele ID MH Z-067A MH Z-0678 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2048 139 +/- 79 < 152 04-23-15 EW- 2049 248 +/- 84 < 152 09-28-15 EW- 5404 209 +/- 85 < 149 09-28-15 EW- 5405 34 +/- 76 < 149 Mean +/-s.d. 174 +/-50 Mean+/- s.d. 141 +/- 151 a "NS" = No sample; not sent. ( 13-14
POINT BEACH NUCLEAR PLANT Manholes (cont.) (
'\ *Sample ID MH Z-067C MH Z-067D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2050 98 +/- 77 < 152 04-23-15 EW- 2051 199 +/- 82 < 152 09-28-15 EW- 5406 125 +/- 81 < 149 09-28-15 EW- 5407 136 +/- 81 < 149 Mean+/- s.d. 111 +/- 19 Mean+/- s.d. 167 +/- 44 Sample ID MH Z-068 MH-1 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2052 250 +/- 85 < 152 04-23-15 NS 8 09-28-15 EW- 5408 220 +/- 86 < 149 09-28-15 NS 8 Mean+/- s.d. 235 +/- 21 Mean+/- s.d.
Sample ID MH-4 MH-6 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d.
.( \
Sample ID MH-7 MH-8 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d. Sample ID MH-16 MH-2 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 09-28-15 NS 8 09-28-15 NS 8 Mean+/- s.d. Mean+/- s.d. Sample 10 MH-5A MH-9 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS
/
il Mean+/- s.d. Mean+/- s.d. a "NS" = No sample; not sent. 13-15
~*!!.._ ATJ E~vironmentaiJ" Inc.
~~.1"'\1 M1dwest Laboratory 700 Landwehr Rr>ad
- Ncxfhbrrx>k, /L 6008:Z-2310 phone (847) 564-0700
- fs)( (847) 564-4!317 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmentar 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 lntercomparlson results, in-house spikes, blanks, duplicates and mixed ana~yte 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, 2015 through December, 2015 I ( I! l f
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 possible problems. 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. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NlST 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-51ists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. 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 the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES 8 One standard deviation Analysis Level for sinple determination Gamma Emitters 5 to 100 pCi!liter or kg 5.0 pCi/liter
> 100 pCilliter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCilliter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi!liter
> 30 pCifliter or kg 10% of known value C: 0.1 glliter or kg 5% of known value Gross alpha s 20 pCilliter 5.0 pCi/liter
> 20 pCilliter 25% of known value Gross beta -::; 100 pCi/liter 5.0 pCilliter I
> 100 pCilliter 5% of known value i*
Tritium -::; 4,000 pCi/liter +/- 1a = 169.85 x (known) 0 *0933
> 4,000 pCi/liter 10% of known value Radium-226,-228 C: 0.1 pCilliter 15% of known value Plutonium e: 0.1 pCilfiler, gram, or sample 10% of known value lodine-131, s 55 pCilliter 6 pCilliter lodine-129b > 55 pCi/Hter 10% of known value Uranium-238, :;; 35 pCilliter 6 pCilliter Nickel-63b > 35 pCi!liter 15% of known value Technetium-99b lron-55b 50 to 100 pCI/Iiter 10 pCilliter
> 100 pCilliter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
( b Laboratory limit. \._ A2
/
! TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a
- Concentration {pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71 .20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41 .90 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61 .80 - 83.30 Pass ERW- 1448 4/6/2015 Cs-137 191 .9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85 .05 :1:4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 ~ 238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22 .10 - 54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21 .30 - 40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 - 28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56-6.01 Pass ERW- 1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770-3,620 Pass ERW-5528 t0/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.10 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.51 62.30 50.69 - 68.50 Pass f
'*.... ERW-5531 10/5/2015 Cs-137 163.1 +/- 4.8 157.0 141.0 - 175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71 .10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 1.13.0 - 149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/-0.08 51 .60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/-0.04 36.60 24 .10 - 44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21 .90 - 31 .00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46-5.85 Fail ERW-5540e 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 - 5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/5/2015 H-3 21 ,260 +/- 351 21,300 18,700-23,400 Pass
- Resulls 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.
- Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. ~
d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
- The result of reanalysis (Compare to original result. footnoted "e" above).
(_ A1 -1 I Il
I' TABLE A-2.1. Thermofuminescent Dosimetry, (TLD, CaSOi Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental. Inc. 2015-1 6/24/2015 30 em . 98.81 103,67 +/- 6.05 69.20 - 128.50 Pass 2015-1 6/24/2015 30 em. 98.81 111.32 +/- 15.97 69.20 - 128.50 Pass 2015-1 6/24/2015 60em . 24.10 27.23 +/- 1.33 17.30- 32.10 Pass 2015-1 6/24/2015 60 em. 24.70 26.98 +/-4.98 17.30- 32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30 - 8.00 Pass 201-5-1 6/24/2015 120 em. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120 em. 6. 18 6.43 +/- 2.00 4 .30-8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150 em. 3.95 4.12 +/- 1.36 2.80 - 5.10 Pass 2015-1 6/24/2015 150 em . 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180 em . 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180 em . 2.74 3.05 +/- 1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14+/-0.18 1.90-3.60 Pass I J i A2-1 j
I, ' TABLE A-2.2 Thermofuminescent Dosjmetry, (TLD, CaS0 4 : Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental. Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/- 2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 12/1512015 Spike3 138.0 121.9+/-1 .9 -0.12 Pass 2015-2 12/1512015 Spike4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12115/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2 +/- 1.2 -0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/-4.0 -0.01 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/- 5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/1512015 Spike 12 138.0 119.0+/-3.4 -0.14 Pass r 2015-2 12/15/2015 Spike 13 138.0 123.0 +/- 2.7 -0.1 1 Pass
.\ \ 2015-2 12/15/2015 Spi-ke14 138.0 125.4 :!;2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/- 3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/- 2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass
- TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N 13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose - conventlally true value) .,. conventially true value) where the convenlially true value is the delivered dose.
~ Acceptance Is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
e Tables A2. 1 and A2.2 assume 1 roentgen" 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). ( \ ... A2*2
! TABLE A-3. In-House "Spiked" Samples Concentration <eCi!L)"
Lab Code b Date Analysis Laboratory results Known Control 2s, n=1c Activity Limits d Acceetance W-020315 2/3/2015 Ra-226 16.19 +/- 0.42 16.70 13.36-20.04 Pass W-021215 2/12/2015 Gr. Alpha 18.38 +/- 0.39 20.10 16.08-24.12 Pass W-021215 2/12/2015 Gr. Beta 27.98 +/- 0.32 30.90 24.72-37.08 Pass SPW-687 2/27/2015 Ni-63 239.6 +/- 3.5 202.4 161.9-242.9 Pass SPAP-689 3/2/2015 Gr. Beta 42.37 +/- 3.50 43.61 34.89 - 52.33 Pass SPAP-691 3/2/2015 Cs-134 1.77 +/- 0.61 1.90 1.52-2.28 Pass SPAP-691 3/2/2015 Cs-137 83.02 +/- 2.60 97.20 77.76-116.64 Pass SPW-693 3/2/2015 Cs-134 44.30 +/- 2.53 53.40 42.72 - 64.08 Pass SPW-693 3/2/2015 Cs-137 74.82 +/- 3.50 73.80 59.04 - 88.56 Pass SPW-693 3/2/2015 Sr-89 87.45 +/- 3.62 87.48 69.98 - 104.98 Pass SPW-693 3/25/2015 Sr-90 37.22 +/- 1.55 38.10 3D.48 - 45.72 Pass SPMI-697 3/2/2015 Cs-134 96.67 +/- 7.74 107.00 85.60 - 128.40 Pass SPMI-697 3/2/2015 Cs-137 78.51 +/- 7.02 73.84 59.07 - 88.61 Pass SPMI-697 3/2/2015 Sr-89 72.98 +/-4.86 87.48 69.98- 104.98 Pass SPMI-697 3/2/2015 Sr-90 39.17+/-1 .51 38.10 30.48 - 45.72 Pass SPW-699 3/2/2015 H-3 59,592 +/- 703 58,445 46,756- 70,134 Pass W-031115 3/11/2015 Ra-226 13.73 +/- 0.35 16.70 13.36-20.04 Pass W-030215 3/2/2015 Ra-228 32.79 +/- 2.31 31 .44 25.15. 37.73 Pass SPF*1040 3/16/2015 Cs-134 787.5 +/- 9.2 840.0 672.0 -1,008.0 Pass SPF-1040 3/16/2015 Cs-137 2,599 +/- 24 2,360 1,888
- 2,832 Pass
/' SPW-1036 3/25/2015 Fe-55 1,792 +/- 63 1961 1,569 ~ 2,353 Pass i:\_
SPW-1374 4/6/2015 U-238 46.03 +/- 2.25 41.70 25.02 - 58.38 Pass W-040815 4/8/2015 Gr. Alpha 20.18 +/- 0.42 20.10 16.08 - 24.12 Pass W-040815 4/8/2015 Gr. Beta 29.70 +/- 0.33 30.90 24.72 - 37.08 Pass SPW-1038 4/13/2015 C-14 3,497 +/- 9 4,734 2,840 - 6,628 Pass W-2165 4/20/2015 H-3 5550 +/- 226 5,780 3,468 - 8,092 Pass W-2165 4/20/2015 Sr-89 90.70 +/- 8.20 108.70 65.22- 152.18 Pass W-2165 4/20/2015 Sr-90 76.80 +/- 2.00 75.90 45.54 - 106.26 Pass W-2165 4/20/2015 Cs-134 62.40 +/- 6.40 57.30 34.38 - 80.22. Pass W-2165 4/2012015 Cs-137 91.30 +/- 7.70 84.00 50.40 - 117.60 Pass W-2392 4/13/2015 H-3 5032 +/- 214 5780 3468-8092 Pass W-2392 4/13/2015 Ni-63 222.4 +/- 3.8 202.0 121.2 -282.8 Pass W-2392 4/13/2015 Cs-134 53.26 +/- 5.01 57.30 34.38 - 80.22 Pass W-2392 4/13/2015 Cs-137 91.90 +/- 7.76 84.20 50.52- 117.88 Pass W-042415 4/24/2015 Ra-22.6 12.52 +/-0.39 16.70 10.02 . 23.38 Pass W-05071-5 517/2015 Gr. Alpha 19.05 +/- 0.41 20.10 12.06-28.14 Pass W-05071-5 5/7/2015 Gr. Beta 27.30 +/- 0.32 30.90 18.54-43.26 Pass W-061215 6/12/2015 Gr. Alpha 20.72 +/- 0.44 20.10 12.06-28.14 Pass W-061215 6/12/2015 Gr. Bela 28.51 +/- 0.33 30.90 1'8.54 - 43.26 Pass U-2982 6/9/2015 Gr. Beta 500.1 +/- 5.1 604.0 362.4 - 845.6 Pass U-3200 6/9/2015 H-3 2229 +/-424 2346 1408-3284 Pass W-70915 7/9/2015 Gr. Alpha 18.76 +/- 0.40 20.10 12.1 - 28.1 Pass W-70915 7/9/2015 Gr. Beta 29.71 +/- 0.33 30.90 18.5 - 43.3 Pass SPAP-3859 7/21/2015 Gr. Bela 41.59 +/- 0.12 43.61 26.17 - 61.05 Pass SPAP-3861 7/21/2015 Cs-134 1.69 +/- 0.60 1.69 1.0-2.4 Pass { A3-1
/'~
1\ TABLE A-3. In-House "Spiked" Samples Concentration (pCf/L)" Lab Code b Date Analysis Laboratory results Known Control 2s, n;1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 - 135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/-5.12 47.02 28.21 - 65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Nr-63 451 .3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/-8.3 539.1 323.5- 754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 - 44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5 +/- 115.9 740.0 444.0- 1036.0 Pass SPP-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1,404- 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06 - 28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 - 43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 - 23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass c\ _ W-091415 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2016 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02- 23.38 Pass W-100615 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 - 28.14 Pass W-10061:5 10/6/2016 Gr. Beta 29.35 :;!:0.33 30.90 18.54-43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280- 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52- 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86-44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738- 15,723 Pass W-6086,6081 11/18/2015 Cs-134 92.98 +/-7.29 96.25 57.75 34.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76-116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54-43.26 Pass I W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 - 3,247 Pass r W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass l
+/- 0.33 l
W-120815 12/8/2015 Gr. Beta 29.50 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02-23.38 Pass 1
- Liquid sample results are reported In pCIILiter, air filters( pCI/m3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation}, CH (charcoal canister), F (fish), U (urine). 1 [
' Results are based on single detenninatlons. 1 d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.
I NOTE: For fish, Jello is used for the spike mabix. For vegetation, cabbage is used for the spike matrix. i
~
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~
A3-2 f t f [
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TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)" Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 a) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/-0.02 1 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/-0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/-0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/-0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1 .57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/- 3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/-368.1 1000 I~ SPW-1037 Water 3/16/2015 C-14 8.94 2.16+/-5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1 .00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 517/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/-- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 1.56 +/- 1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 ~1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 i SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 rI SPW-3870 SPW-3870 Water Water 7/21/2015 7/21/2015 Sr-89 Sr-90 2.28 0.84
-0.42 +/- 1.80 0.25 +/-0.42 5
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\. f A4-1 i I,.
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if
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TABLE A-4. In-House "Blank" Samples Concentration <eCi/L)a Lab Code Sample Date Analysisb Laboratory results ( 4.66cr) Acceptance Type LLD ActivitXc Criteria (4.66 a-) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51 .3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/- 8.06 100 W-{)81015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015
- Ra-226 0,03 0.03 +/- 0.02 2 W-{)90615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/-0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/-0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/-0.52 4 C',_
W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/-0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-12081-5 Water 12/8/2015 Gr. Beta 0.76 0.17 +/- 0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2
- Liquid sample results are reported in pCi/Liter, air filters( pCitm\ charcoal (pCi/charcoal canister), and solid samples (pCllkg}.
b 1-131 (G); iodlne-131 as analyzed by gamma spectroscopy. c Activity reported Is a net activity result. A4-2
\ TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72 +/-0.12 5.78 +/-0.12 5.75 :1; 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/-0.135 0.919 +/-0.102 0.917+/-0.15 Pass CF-62,63 1/7/2015 K-40 3.97 +/-0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 V712015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/1212015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90+/-1 .16 Pass SG-83,84 1112/2015 Tl-208 0.57 +/-0.07 0.56 +/-0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73 +/- 0.10 1.58 +/- 0.09 1.65 +/-0.13 Pass SG-83,84 1/1212015 Pb-214 13.33 +/- 0.33 13.88 +/-0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47:!: 0.24 Pass SG-83,84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 111212015 Ac-228 13.33 +/-0.59 12.86 :!: 0.43 13.09 +/- 0.36 Pass AP-011215N8 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-60010,60011 1/28/2015 Ra-226 1.25+/-0.14 1.40 +/- 0.15 1.33 +/-0.10 Pass OW-60010,60011 1/2812015 Ra-228 2 .00 +/- 0.66 1.39 +/- 0.60 1.70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-2t4 6.45 +/-0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/-0.24 4.20 +/-0.58 4.32 +/- 0.31 Pass AP-020415NB 214/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115NB 2111/2015 Gr. Bela 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass
/ DW-60023,60024 212612015 Ra-226 1.52 +/-,0.15 1.51 +/-0.15 1.52 +/- 0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/-0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 212612015 K-40 11 .96 +/- 0.98 11.49 +/- 0.82 11.7.2 +/- 0.64 Pass S-799,800 2126/2015 Tl-208 0.36 +/-0.04 0.31 +/- 0.04 0.34 +/-0.03 Pass S-799,800 2/2612015 Pb-212 0.92 +/-0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 212612015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2126/2015 Ac-228 1.35 +/- 0.22 1.23 +/- 0. "t7 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3 +/- 6.3 t17.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 212/2015 Gr. Beta 82.27 +/-2.79 84.33 +/-2.74 83.30 +/- 1.96 Pass DW-60031 ,60032 314/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/-7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/-0.34 6.88 +/-0.32 6.89 +/-0.23 Pass DW-60036,60037 314/2015 Ra-228 4.43 +/-0.73 4.41 +/- 0.72 4.42 +/- 0.51 Pass DW-60048,60049 314/2015 Ra-226 0.84 +/-0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169,1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/912015 Gr. Bela 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 411312015 H-3 1,628 +/- 139 1,695 +/- 141 1,662 +/- 99 Pass SG-1847,1848 4/20/2015 K-40 3.24+/-1.18 1.99 +/- 0.76 2.62 +/- 0.70 Pass SG-1847,1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847,1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/2312015 H-3 6,584 +/-244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/2712015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/-64.3 Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)" Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/-3.63 43 .61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/-2.02 51.40 +/- 1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 ;!; 0.62 13.67 +/- 0.40 Pass SG-1868,1869 4/28/2015 Ra-228 20.10 +/-0.92 22.10 +/- 1.29 21 .10 +/- 0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087 ,60088 5/14/2015 Ra-226 1.58 +/-0.17 1.52 +/-0.17 1.55 +/- 0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/-0.61 47.80 +/-0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/-7.9 254.6 +/- 7.6 261 .2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10 +/-0.92 40.80 +/-0.83 40.95 +/- 0.62 Pass DW-60095 ,60096 5/26/2015 Gr. Alpha 1.34 +/-0.69 0.91 +/-0.62 1.13+/-0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/-0.14 1.08 +/-0.12 0.97 +/- 0.09 Pass
/
S-2627,2628 5/29/2015 Cs-137 0.07 +/-0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/-0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11 .15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/-214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/-658 20,987 +/- 600 21 ,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-301 07,30108 6/8/2015 Gr. Alpha 1.34 +/-0.82 1.47 +/- 0.85 1.41 +/- 0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/- 0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841 .9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Bela 0.023 +/- 0.004 O.D18 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78 +/-0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass j VE-3300,3301 6/24/2015 K-40 29.12 +/-0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass ! AP-062915 WW-3632,3633 6/29/2015 6/30/2015 Gr. Beta H-3 0.023 :l: 0.005 5,169 +/- 225 0.023 +/- 0.005 5,058 +/- 223 0.023 +/- 0.003 5,114+/-158 Pass Pass II I! it
"~
f* ( f \ ~ t N AS-2 [
)'
f f f r
\ TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"
Averaged Lab Code Dale Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-03 2,332 +/- 233 2,108 +/- 211 2,220 +/- 157 Pass WW-fl377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/-83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1{2015 Be-7 2.02 +/-0.32 1.98 +/- 0.25 2.00 +/-0.20 Pass G-5461,2 10/1/2015 K-40 8.77 +/-0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/- 0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/-0.04 0.52 +/-0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/-0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17+/-0.73 2.10 +/-0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/-0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/-0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/-0.03 0.25 +/-0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/20t5 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31 .36 +/- 2.08 29.80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/-0.29 4.13 +/- 0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/-0.06 0.24 +/-0.06 0.22 +/- 0.04 Pass _/ SS-5818, 5819 10/14/2015 Cs-137 0.03 +/-0.02 0.02 :1:0.01 0.03 :1:0.01 Pass i., SS-5818, 5819 10/14/2015 Gr. Beta 8.10 :1:0.87 8.08 +/-0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass 88-5818,5819 10/14/2015 Ra-226 0.47 +/-0.24 0.45 +/- 0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 1-0115/2015 Ra-228 0.79 +/- 0.48 1.16+/-0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/-0.15 1.14 +/-0.15 1.11 +/-0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/-0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-t37 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/-0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06+/-0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0 -5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/- 0.43 *2.16 +/- 0.37 2.14 +/- 0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28 +/- 1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 1-70 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/-0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bl-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/-0.03 0.19 +/- O.D3 0.1'8 +/- 0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21 .6+/- 1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/-0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/201 5 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass l i J 1 I I I I j (
- , I A5-4 1
f f
TABLE A-5. In-House "Duplicate" Samples Concentration (pCill)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Pass Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 Pass S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 :1; 0.03 0.17 +/- 0.02 Pass S0-6841, 6842 11/24/2015 K-40 13.62 +/-0.76 13.67 +/-0.69 13.64 :1; 0.51 Pass WW-f>978, 6979 11130/2015 H-3 569.0 +/-97.7 480.3 +/-93.9 524.7 +/- 67.8 Pass SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81 .2 164.0 +/- 57.0 Pass SW-7017, 7018 12/1012015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0+/-68.1 Pass LW-7020, 7021 12/10/2015 H-3 236.9 +/-84.2 285.6 +/- 86.5 261.2 +/-60.3 Pass AP-7351, 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 Pass
- AP-7414, 7415 12/3012015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Pass Note: Duplicate analyses an~ performed on every twentieth sample received in-house. Results are not listed tor those analyses with activities that measure below the LLD.
- Results are ~ported In units of pCVL, except for air filters (pCI/Filter or pCVm3), food products, vegetation, soil, sediment (pClfg).
\
I j ( I I 1 A5-5 f
~
I i
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration
- Known Control Lab Code b Date Analysis Laboratory result Activity Limits " Acceptance MAS0-975 2/1/2015 Nl-63 341 +/- 18 448 314 - 582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 2/1/2015 Tc-99 614 +/- 12 867 607-1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475-881 Pass 0
MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA Pass 0 MAS0-975 2/1/2015 Co-57 0.5 :t 1.0 0.0 NA Pass MAS0-975 2/1/2015 Co-60 741 +/-8 817 572 - 1,062 Pass MAS0-975 2/1/2015 Mn-54 '},153 +/-9 1,198 839 - 1,557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 -1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21 .1 :1:0.3 23.5 16.5 -30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4-24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 :f: 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569:!: 13 563 394 - 732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.68 4.82-8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NAC Pass
/
MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass
\. MAW-969 2/1/2015 Zn-65 16.5 :f: 0.9 18.3 12.8 ~23. 8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23-4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/-0.03 0.01 NA " Pass MAW-969 2/1/2015 Pu-239/240 0.81:1:0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104-0.192 Pass MAW-969 2/1 /2015 U-238 0.84 +/- 0.09 0.97 0.68 -1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/201 5 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72:1:0.06 2.79 1.40-4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/-0.12 1.49 1.04 -1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA" Pass MAAP-978 r 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fall MAAP-978 211/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83+/-0.10 0.83 0.58 - 1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.06-0.11 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069-0.129 Pass
(' I
\, ,
A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control lab Codeb Date Anal¥sls Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33,3 - 61 .8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74- 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59:1:0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95:1:0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.1 3 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01- :1:0.04 0.00 NA c Pass MAVE-972 2/1-/2015 Co-60 3.89:1:0.20 5.55 3.89 -7.22 Pass 0 MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NA Pass 0 MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0,110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 - 0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass
/
MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61 .8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 - 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/20t5 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - U3 Pass MAVE-972 2/1/2015 Cs-134 6.98 :1:0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -1 1.93 Pass MAVE-972 2/1/20t5 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89-7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NA " Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477 -887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298-553 Fail MAS0-4903 9 8/1/2015 Sr-90 352 +/- 10 425 298-553 Pass MAS0-4903 h 811/2015 Tc-99 411 +/- 11 631 442 -820 Fail I MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 - 1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 ~ 1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1,180 826 -1 ,534 Pass MAS0-4903 8/1/2015 Co-60 2+/-2 1.3 NA" Pass MAS0-4903 8/1/2015 Mn-54 1,331 :1: 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463
- 861 Pass
{ A6-2
TABLE A-6 . Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 -30.0 Pass 0 MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1- 0.0 NA Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 -27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0 -22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151 .0-281.0 Pass 1 MAW-5007 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 -17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0-11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7-18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 -9.35 Pass MAW-5007 8/1/2015 Sr-90 4 .80 +/- 0.50 4.80 3.36 -6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13-0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 -5.28 Pass MAW-5007 8/1/2015 1-129 1.42 :!:0.13 1.49 1.04 -1.94 Pass
/
MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79-5.17 Pass ( MAAP-4911 8/1/2015 Sr-90 0.94 t 0.16 1.05 0.74-1.37 Pass
\
MAAP-4907 8/1/2015 Gr. Alpha 0.30 t 0.04 0.90 0.27 -1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78-2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/-0.16 5.80 4.06 -7.54 Pass 0 MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA Pass MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63-8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/-0.15 4.56 3.19-5.93 Pass MAVE-4901 8/1/20t5 Mn-54 8.25 +/-0.25 7.68 5.38-9.98 Pass MAVE-4901 81t/2015 Zn-65 5.78 +/- 0.29 5.46 3.82-7.10 Pass
- Results are reported in units of Bq/kg (soil), Bq!L (water) or Bqftotal sample (filters, vegetation).
blaboratory co<les as follows: MAW (water), MMP {air filter), MASO (soil), MAVE (vegetation). c MAPEP results are presented as the known values and expected laboratory precision {1 sigma, 1 detennination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a false positive". MAPEP does not provide control limits. d Lab result was 27.84. Data entry error resulted in a non-acceptable result.
- Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
1 Lab result was 1.58. Data entry error resulted in a non-acceptable result. 0 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable. h The complex sample matrix is interfering with yield calculations causing a failed low resull An investigation is in process to determine a more reliable yield determination. 1 The known activity was below the routine laboratory detection limits for the available aliquot fraction. / A6-3
\ TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 8
- Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/-2.2 49.8 30.7. 67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61 .2-98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/-34.7 909.0 578.0 -1 '130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312 +/- 12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/-48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3116/2015 Mn-54 <2.7 <50 0.0-50.0 Pass ERAP-1091 3/16/2015 Pu-238 51 .0 +/-3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 - 52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 - 145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21 .3-51 .7 Pass ERAP-1091 3/16/2015 U-238 31 .0 +/- 1.1 34.0 22.0 - 47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/-0.7 62.2 20.8 - 96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/-0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 1571 .8 +/-209.6 1,500 878 - 1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/- 455.7 1,780 414 -2,620 Pass
/ 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass
'\ ERS0-1098 ERS0-1098 3/16/2015 Co-60 1779.8 +/- 41 .0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180 -7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/- 41 .9 1,490 1,140 - 1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810 - 14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1 ,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806-1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/-93 4,530 2,640 - 6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 - 1 ,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185 +/- 140 1,210 791 -1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724 +/- 125 1,940 740-3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/-948 3,890 1,230
- 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/-226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/-232 3,890 2,410 - 4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680
- 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11 .5 119.0 42.2 -184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/-4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 - 14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/-266 4,340 2,650 - 5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 - 2,120 Pass A7-1
TABLEA-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 3 . Concentration {pCI/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Resultd Limits Acceptance ERVE-1100
- 3116/2015 Co-BO 1,030 +/- 29 1,540 1,060 - 2,150 Fail ERVE-1100 t 3/16/2015 Co-BO 1,684 +/-48 1,540 1,060-2,150 Pass ERVE-1100
- 3/16/2015 Cs-134 1,615 +/-27 2,650 1'700 - 3,440 Fail ERVE-1100 1 3/16/2015 Cs-134 2,554 +/-49 2,650 1'700 - 3,440 Pass ERVE-1100 e 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 -2,520 Fail ERVE-1100 1 3/16/2015 Cs-137 2,078 +/- 68 1,810 1,310 - 2,520 Pass ERVE-1100 " 3/16/2015 K-40 22,037 +/-463 30,900 22,300
- 43,400 Fail ERVE-1100 t 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass ERVE-1100
- 3/16/2015 Mn-54 <13.8 <300 0.0 -300.0 Pass 1
ERVE*1100 3/16/2015 Mn-54 <24.4 <300 0.0-300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/-232 3,680 2,190 - 5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/-240 4, 180 2.570 - 5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/-326 6,590 3,760 -8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 - 4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 - 3,980 Pass ERVE-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 - 1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31 .0 -61.7 Pass (
- ERW-1103 ERW-1103 3/16/2015 3/16/2015 Co-60 Cs-134 1,217 +/- 17 1,121 +/- 18 1,250 1,260 i ,090 - 1,460 925 -1,450 Pass Pass
\, ERW-1103 3/16/2015 Cs-137 1,332 +/-31 1,360 1'150 -1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 - 232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/-4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7-75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/-136 1,180 984 - 1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149 +/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860 .0 +/-37.0 912.0 594.0 -1,210.0 Pass
- 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).
b laboratory codes as follows: ERW {water}, ERAP (air filter}, ERSO (soil), ERVE {vegetation). Results are reported In units of pCiiL, except for air filters (pCUFilter), vegetation and soil (pCI/kg). c Unless otherwise Indicated, the laboratory result Is given as the mean :t standard deviation for three detenninatlons. d Results are presented as the known values, expected laboratory precision (1 sigma. 1 detenninatlon) and control limits as provided by ERA. A known value of "zero* indicates an analysis was Included in the testing series as a false positive". Control limits are not provided.
"Technician error weighing sample caused submitted gamma results to be understated and outside the control Jimits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).
9 The results of reanalysis were outside the control limits (low). h sample ERW-3742 was ordered from E~ to determine why ERW-11 03 results for Pu-239 were outside the acceptable range. The results for ERW-3742 were acceptable. No reason for the unacceptable results for ERW-3742 was determined. A7-2
APPENDIX 8 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 = 2cr 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 4.66a uncertainty for a background sample. 3.0. Duplicate anaivses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x, :1: s1 and ~ +/- s2 Reported result: x :1: s; where x = (1/2) (x1 + x2), and s = (1/2) ~ + s; s; 3.2. Individual results: < L1 , < L2 Reported result:< L, where L =lower of L1 and L2 3.3. individual results: x :1: s, < L Reported result: x*:t 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 exal!!ple, 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, x *** xn are defined 2 as follows: X =n1 LX s---~ -\j~ 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 LLO 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 following those to be retained Is equal to or 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
,(
APPENDIXC (
- . Sampling Program and Locations C-1
POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)" (and Frequency)b (and Frequency)b Airborne Filters 6 E-1-4, 8, 20 Weekly GB, GS, on QC 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 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 I 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 I \ *, as available Fish E-13 2x /year GB, GS (in edible portions) as available
- 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 2011 -2015 0.050 C'? 0.030 ~--___,;f!L--.J.--,~-J-l.-1----\-.---+.--l+-\----4>c...J..J.---Ji?..-l-
.§
~ 0.020 -I----\----,'L-----G--+------,IA--i-.\,!----'\--.,..¥--\-+-----l,-_,6---.:.___,...
0.010 -----~------------- 0.000 +H+H-+1-t++++-t++++-H+I-++-I+H+H+H-++-I+H-++++++++-~f-HIIH-1-HIIH-1+-IIIH-1++-ilI ij 2011 2012 2013 2014 2015 2016 Year Location E-2, monthly averages 2011-2015 0.050 0.040 0.030 C'? E
.(3
- 0. 0.020 0.010 0.000 2011 2012 2013 2014 2015 2016 Year l
D-2
POINT BEACH Air Particulates- Gross Beta Location E-3, monthly averages 2011-2015 0.050 0.040 C"? E 0.030 0c. 0.020 Af ~ 0.010 0.000 --HI 2011 2012 2013 2014 2015 2016 Year Location E-4, monthly averages 2011-2015 0.050 0.010 +-- - - - -- - - - - - - - - - - - - - - 0.000 ++-++++++t++++-H+IHI1+1HI1+1HI1+1HI1+1-HI1+1+-II1+1+-II1-tl-1-111-+1+111-+1+1HI1+1HI,+1HI1+1+-II1+1+-II1+1 I
+-Ill 2011 2012 2013 2014 2015 2016 Year
/ l D-3
POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2011-2015 0.050 0.040 (") 0.030 E ~~ 0 0.020 0. 0.010 0.000 2011 2012 2013 2014 2015 2016 Year Location E-20, monthly averages 2011 -2015
/
I
'* 0.050 0.040 +-------"'l>-l~>-----------
(") 0.030 ~~-~+-----+--"f-----++fr-----~1---~ E
~ 0.020 +---\-;-J-=------':...+-1'---~'f---.-~~~---*~-...;--r:-~
0.010 + - -- -- - - -- - - - - -- -- - -
- 0. 000 +H-+++H-HI-t-H++++H-++++-t+t+t-1-t-H++++H++++-t+H-HI-+H-++t+++-H+-1 2011 2012 2013 2014 201 5 2016 Year
( D-4
POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses .( \. E-1
POINT BEACH NUCLEAR PLANT
/ Supplemental Analyses a
\
Units: = pCi\L Gamma isotopic analysis Location U2FSSDS U2FSSDS U2FSSDS Collection Date 01 15 02-15-15 03-26-15 Lab Code EWW- 508 MDC EW- 993 MDC EW- 1501 MDC Be-7 2.4 +/- 9.8 < 29.7 1.2 +/- 11 .3 < 26.7 -8.3 +/- 8.8 < 15.3 Mn-54 0.3 :t 1.2 < 2.3 1.4 +/- 1.4 < 3.0 -0.3 +/- 1.2 < 2.6 Fe-59 3.5 +/- 2.1 < 5.7 -0.8 +/- 2.9 < 3.7 1.2 +/- 2.0 < 4.4 Co-58 0.3 +/- 1.2 < 3.3 0.8 +/- 1.3 < 1.9 -0.4 +/- 1.1 < 2.4 Co-60 0.4 +/- 1.2 < 1.9 0.5 +/- 1.5 < 2.2 -0.8 +/- 1.3 < 2.1 Zn-65 -0.7 +/- 2.2 < 4.7 0.7 +/- 2.9 < 4.4 1.0 +/- 2.3 < 4.7 Zr-Nb-95 -1.8 +/- 1.3 < 2.7 -0.5 +/- 1.4 < 4.0 -1.0+/-1.2 < 2.4 Cs-134 0.5 +/- 1.2 < 2.2 0.1 +/- 1.4 < 2.4 1.1 +/- 1.1 < 2.1 Cs-137 1.4 +/- 1.4 < 2.6 0.6 +/- 1.5 < 2.5 1.1 +/- 1.4 < 2 .7 Ba-La-140 -2.8 +/- 1.5 < 7.7 1.3 +/- 1.5 < 8.0 0.3 +/- 1.3 < 4 .6 Location U2FSSDS MH Z-067C U2FSSDS Suspended solids Collection Date 04-30-15 04-23-15 06-02-15 Lab Code EW- 2227 EW- 2050 EW- 2747 Be-7 -18.3 +/- 13.8 < 29.7 ~0.001 +/- 0.016 < 0.033 -5.7 +/- 13.7 < 29.2 Mn-54 0.4 +/- 1.7 < 3.4 0.000 +/- 0.002 < 0.004 1.8 +/- 1.5 < 3.2 Fe-59 -0.7 +/- 3.1 < 7.4 0.004 +/- 0.004 < 0.014 1.7 +/- 2.9 < 5 .0 l*,
\
Co-58 -0.8 +/- 1.6 < 2.2 0.001 +/- 0.002 < 0.005 0.4 +/- 1.5 < 2.1 Co-60 1.7 +/- 1.6 < 2.9 -0.002 +/- 0.002 < 0.003 3.1 +/- 1.7 < 3.1 Zn-65 1.5 +/- 3.4 < 2.2 -0.002 +/- 0.005 < 0.007 1.6 +/- 3.4 < 4.9 Zr-Nb-95 0.4 +/- 1.5 < 2.6 -0.007 +/- 0.002 < 0.010 -1 .8 +/- 1.8 < 3.0 Cs-134 1.2 +/- 1.6 < 3.1 -0.001 +/- 0.002 < 0 .004 0.0 +/- 1.6 < 2.7 Cs-137 -0.1 +/- 1.7 < 2.9 0.001 +/- 0.002 < 0.004 1.3 +/- 1.8 < 3.4 Ba-La-140 -1.6 +/- 1.8 < 3.4 -0.005 +/- 0.002 < 0.036 -1.4. +/- 2.0 < 3.4 Location U2FSSDS U2FSSDS U2FSSDS Collection Date 06-30-15 08-31-15 09-30-15 Lab Code EW" 4025 EW- 4951 EWW- 6410 Be-7 -1 .6 +/- 13.1 < 21 .9 5.4 +/- 10.8 < 27.7 8.0 +/- 10.2 < 41 .1 Mn-54 2.1 +/- 1.6 < 3.3 -0.9 +/- 1.4 < 3.1 1.2 +/- 1.3 < 2.8 Fe-59 - 1.5 +/- 3.1 < 7.8 -2.3 +/- 2.5 < 5.2 2.4 +/- 2.4 < 8.2 Co..S8 0.2 +/- 1.5 < 2.8 -1.0 +/- 1.3 < 2.1 -0.1 +/- 1.3 < 3.5 Co-60 0.0 +/- 1.6 < 1.8 -2.0 +/- 1.5 < 2.3 0.2 +/- 1.3 < 1.9 Zn-65 0.4 +/- 3.4 < 4.6 0.4 +/- 2.6 < 4.4 0.3 +/- 2.7 < 4.7 Zr-Nb-95 -0.8+/-1 .7 < 3.6 -0.3 +/- 1.5 < 3.2 -2.4 +/- 1.3 < 3.5 Cs-134 0.5 +/- 1.6 < 3.1 -0.3 +/- 1.4 < 2 .5 -0.7 +/- 1.3 < 2.5 Cs-137 -0.8 +/- 1.7 < 2.5 0.4 +/- 1.5 < 2.6 2.3 +/- 1.5 < 3.0 a Ba-La-140
- 4.9 +/- 1.8 < 6.7 -2.9 +/- 1.6 < 5 .5 - 3.5 +/- 1.5 < 19.7
- LLD not reached due to age of sample; received 11-06-15.
~~ E-2
POINT BEACH NUCLEAR PLANT ( Supplemental Analyses Units: =pCi\L
- Gamma isotopic analysis Location E-F1A E-F18 E-F2 Corn Corn Hay Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5135 MDC EVE- 5136 MDC J;VE- 5137 MDC Gross Beta 2.66:!: 0.06 < 0.025 2.82 +/- 0.07 < 0.024 5.11 +/- 0.15 < 0.073 Be-7 0.18+/-0.10 0.12 +/- 0.05 4.41 +/- 0.25 K-40 2.60 +/- 0.22 1.28 +/- 0.15 2.88 +/- 0.26 Mn-54 0.004 +/- 0.004 < 0.005 0.000 +/- 0.003 < 0.006 0.006 +/- 0 .007 < 0.015 Fe-59 0.001 +/- 0.009 < 0.011 -0.001 +/- 0.006 < 0.010 0.009 +/- 0.015 < 0.028 Co-58 0.001 +/- 0.004 < 0.006 0.000 +/- 0.002 < 0.004 -0.001 +/- 0.007 < 0.017 Co-60 0.006 +/- 0.005 < 0.009 0.001 +/- 0.003 < 0.002 -0.009 +/- 0.007 < 0.009 Zn-65 0.008 +/- 0.012 < 0.021 0.001 +/- 0.007 < 0.009 0.002 +/- 0.017 < 0.022 Zr-Nb-95 -0.004 +/- 0.004 < 0.009 -0.004 +/- 0.003 < 0.003 -0.005 +/- 0.008 < 0.016 Cs-134 0.003 +/- 0.004 < 0.009 0.001 +/- 0.003 < 0.006 0.001 +/- 0.008 < 0.016 Cs-137 0.002 +/- 0.005 < 0.010 0.003 +/- 0.003 < 0.006 0.005 ;f: 0.008 < 0.018 Ba-La-140 0.001 +/- 0.004 < 0.010 -0.005 +/- 0.003 < 0.005 0.000 +/- 0.006 < 0 .026 Location E-F3 E-F4 E-F5 Hay Corn Alfalfa Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5138 EVE- 5139 EVE- 5140
/ ~
Gross Beta 8.12 +/- 0.27 < 0.14 3.59 +/- 0.09 < 0.032 6.70 +/- 0.15 < 0.049
\
Be-7 ' 6.21 +/- 0.42 0.31 +/- 0.11 0.70 +/- 0.15 K-40 6.21 +/- 0.51 2.47 +/- 0.22 6.86 +/- 0.40 Mn-54 -0.001 +/- 0.011 < 0.019 0.003 +/- 0.004 < 0.007 0.005 +/- 0.006 < 0.013 Fe-59 0.012 +/- 0.023 < 0.047 -0.002 +/- 0.010 -:= 0.013 0.001 +/- 0.013 < 0.025 Co-58 0.004 +/- 0.011 < 0.024 0.002 +/- 0.004 < 0.005 -0.002 +/- 0.006 < 0.011 Co-60 -0.005 +/- 0.012 < 0.014 0.000 +/- 0.005 < 0.004 0.002 +/- 0.008 < 0.012 Zn-65 -0.020 +/- 0.030 < 0.028 0.004 +/- 0.010 < 0.016 0.009 +/- 0.016 < 0.032 Zr-Nb-95 0,004 +/- 0.011 < 0.025 0.001 +/- 0.004 < 0.008 0.000 +/- 0.007 < 0.014 Cs-134 -0.007 +/- 0.012 < 0.024 0.002 +/- 0.004 < 0.009 0.003 +/- 0.006 < 0.010 Cs-137 0.000 +/- 0.013 < 0.022 0.000 +/- 0.004 < 0.007 0.006 +/- 0.007 < 0.012 Ba-La-140 0.001 +/- 0.011 < 0.026 -0.002 +/- 0.004 < 0.009 -0.004 +/- 0.005 < 0.009 Location E-F6 E-F7 E-FB Alfalfa Alfalfa Soybeans Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5141 EVE- 5142 EVE- 5143 Gross Beta 6.16 +/- 0.14 < 0.054 6.40 +/- 0.13 < 0.043 4.68 +/- 0.12 < 0.048 Be-7 1.30 +/- 0.18 0.35 +/- 0.13 1.42 +/- 0.20 K-40 5.98 +/- 0.45 6.45 +/- 0.39 3.74 +/- 0.32 Mn-54 0.004 +/- 0.007 < 0.012 0.003 +/- 0.005 < 0.010 0.004 +/- 0.006 < 0.011 Fe-59 0.002 +/- 0.017 < 0.024 0.000 +/- 0.013 < 0.018 0.003 +/- 0.012 < 0.013 Co-58 0.001 +/- 0.007 < 0.012 0.004 +/- 0.006 < 0.011 0.002 +/- 0.006 < 0.009 Co-60 -0.004 +/- 0.008 < 0.011 0.003 +/- 0.006 < 0.010 -0.001 +/- 0.007 < 0.007 Zn-65 0.004 +/- 0.020 < 0.022 -0.003 +/- 0.017 < 0.023 -0.008 +/- 0.014 < 0.011 Zr-Nb-95 0.004 +/- 0.007 < 0.013 -0.001 +/- 0.006 < 0.010 -0.004 +/- 0.005 < 0.009
/ Cs-134 -0.001 +/- 0.007 < 0.015 0.004 +/- 0.005 < 0.011 -0.002 +/- 0.005 < 0.010 j
Cs-137 -0.001 +/- 0.008 . < 0.014 0.009 +/- 0.006 < 0.010 0.005 +/- 0.005 < 0.008
' Ba-La-140 -0.003 +/- 0.007 < 0.023 0.002 +/- 0.005 < 0.010 -0.014 +/- 0.006 < 0.017 E-3
POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location E-F9 Corn U2FSSDS U2FSSDS Collection Date 09-17-15 10-31-15 12-07-15 Lab Code EVE- 5144 MDC EW- 6411 MDC EW- 6978 MDC Gross Beta 3.11 +/- 0.08 < 0.033 Be-7 1.58 +/-0.16 -3.9 +/- 22 .2 < 30.5 -0 .7 +/- 10.3 < 21.8 a K-40 1.98 +/- 0.21 Mn-54 0.005 +/- 0.005 < 0.009 -0.1+/-2.4 < 2.4 -0.6 +/- 1.3 < 2.0 Fe-59 0.012 +/- 0.010 < 0.022 -1 .5 +/- 4.9 < 11.4 0.7 +/- 2.5 < 4.6 Co-58 -0.005 +/- 0.005 < 0.004 -0.2 +/- 2.3 < 5.1 -1.4 +/- 1.2 < 2 .1 Co-60 0.004 +/- 0.005 < 0.007 0.6 +/- 2.6 < 2.3 1.2 +/- 1.2 < 2 .2 Zn-65 0.002 +/- 0.010 < 0.015 -1.3 +/- 5.7 < 9.6 0.0 +/- 2.4 < 4 .0 Zr-Nb-95 -0.003 +/- 0.005 < 0.008 -2.6 +/- 2.6 < 4.4 -0.5 +/- 1.3 < 2.9 Cs-134 -0 .001 +/- 0.005 < 0.009 -0 .3 +/- 2.6 < 5.1 0.2 +/- 1.3 < 2.5 Cs-137 -0.002 +/- 0.005 < 0.006 0.9 +/- 2.9 < 5.7 0.2 +/- 1.5 < 2.5 Ba-La"-140 0.000 +/- 0.005 < 0.008 0.4 +/- 2.8 < 7.5 0.2 +/- 1.6 < 2.6 Location U2FSSD MDC Collection Date 12-31-15 Lab Code EWW- 7465 Be-7 -8.5 +/- 10.1 < 54.1 Mn-54 0.9 +/- 1.3 < 3.1 Fe-59 1.0 +/- 2.3 < 14.0 Co-58 1.0 +/- 1.2 < 5.2 Co-60 0.5 +/- 1.4 < 2.8 Zn-65 -0.4 +/- 2.5 < 6.6 Zr-Nb-95 -4.7 +/- 1.3 < 6.2 Cs-134 0.5 +/- 1.3 < 2.6 Cs-137 -0.8 +/- 1.5 < 2.0 Ba-La-140 -36 .2 +/- 1.5 < 117.7 a Analysis not required . b LLD not reached due to age of sample; sample received and counted 03-11-16. E-4
POINT BEACH NUCLEAR PLANT { Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 02-27-15 02-27-15 02-27-15 02-27-15 Lab Code EWW- 867 MDC EWW- 868 MDC ND" MDC EWW- 869 MDC Be-7 0.4 +/- 17.3 < 28.9 -3.9 +/- 15.2 *< 31 .0 -2.1 +/- 12.5 < 24.6 Mn-54 0.0 +/- 1.8 < 3.0 0.7 +/- 1.6 < 3.0 0.1 +/- 1.6 < 3.4 Fe-59 -2.0 +/- 3.7 < 5.7 2 .2 +/- 3.0 < 5.6 -1 .8 +/- 3.0 < 3.1 Co-58 1.5 +/- 1.8 < 3.2 2.4 +/- 2.3 < 6.8 0.1 +/- 1.7 < 3.2 Co-60 0.3 +/- 1.9 < 3.5 0.7 +/- 1.7 < 2.7 2 .2 +/- 1.7 < 3 .2 Zn-65 1.7 +/- 4 .0 < 6.2 1.1 :I; 3.4 < 6.2 1.3 +/- 3 .3 < 6 .7 Zr-Nb-95 -0.7+/-1 .9 < 3.9 -1.3+/-1.7 < 3.0 0.1 +/- 1.8 < 4.3 Cs-134 -0.2 +/- 1.9 < 3.8 -1.4+/-1 .7 < 3.5 -0.2 +/- 1.6 < 2 .9 Cs-137 2.5 +/- 2.0 < 3.7 1.3 +/- 1.8 < 4,2 1.8 +/- 1.8 < 3.6 Ba-La-140 * -1.4 +/- 2.2 < 5.1 0.6 +/- 1.6 < 3.0 -0.1 +/- 2 .1 < 5.7 Location GW-091Z-361A GW-09 1Z-361 B GW-10 2Z-361A GW-10 2Z-361B Collection Date 04-12-15 04-12-15 04-12-15 04-12-15 Lab Code EWW- 2515 EWW- 2516 EWW- 2517 EWW- 2518 Be-7 18.4 +/- 14.6 < 42.6 7.9 :I; 14.9 < 45.4 26.0 +/- 15.3 < 4:_7 .5 23.3 +/- 14.4 < 42.2 Mn-54 1.4 :I; 1.8 < 4.1 1.1 +/- 1.8 < 2.6 0.7 +/- 1.9 < 3.8 1.9 +/- 1.7 < 3.7 Fe-59 -1.1 :I; 3.5 < 11.5 1.8 +/- 3.8 < 13.0 -4.7 +/- 3.8 < 11 .9 1.9 +/- 3.5 < 14.2 Co-58 1.3 :I; 1.6 < 3.7 -1.5 :I; 1.6 < 3.0 -0.1 +/- 1.7 < 4 .2 2.1 +/- 1.9 < 5.2 ( Co-60 0.3 :I; 2 .0 < 2.9 -0.7 +/- 2.1 < 4.1 -0.2 :I; 2.0 < 3.7 1.1 :I; 1.9 < 3.4 i'*,1 Zn-65 -0.9 :I; 3.6 < 4.6 1.2 +/- 3.8 < 7.1 2.4 +/- 4 .1 < 8.0 -0.5 +/- 3.9 < 4.0
\
Zr-Nb-95 -0.7 :I; 1.7 < 5.6 4.5 +/- 1.6 < 6.7 -1.0 :I; 1.9 < 4.6 -3.5 :I; 1.8 < 5.2 Cs-134 0.2 :I; 1.8 < 3.5 0.8 +/- 1.7 < 3.4 -1.4 +/- 1.8 < 3.5 -2.1 +/- 1.9 < 3.4 Cs-137 0.9 :I; 1.9 < 3.7 1.7+/-1.9 < 3.7 -0.1 +/- 1.8 < 2 .9 -1 .0 +/- 1.9 < 4.0 b b Ba-La-140 7.6 :I; 2.0 < 14.3 -6.8 +/- 2.4 < 26.8 -2.3 +/- 2 .0 < 19.6 18.5 +/- 2 .2 < 37.2 Location GW-09 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 08-08-15 08-08-15 08-08-15 08-08-15 Lab Code EWW- 4709 EWW- 4710 EWW- 4711 EWW- 4712 Be-7 -2.5 +/- 17.1 < 38.4 5.4 +/- 15.3 < 38.1 -4.9 :I; 16.7 < 34.5 1.1 +/- 15.4 < 23.3 Mn-54 1.0 +/- 1.7 < 3.3 -0.1 +/- 1.6 < 3.6 -0.4 +/- 1.7 < 3.3 1.5 +/- 1.6 < 3.5 Fe-59 0.4 +/- 3.4 < 10.2 1.1 +/- 2.9 < 8.2 -3.7 +/- 3.5 < 6.0 -0.5 +/- 2.8 < 7.7 Co-58 -0.7+/-1.7 < 4 .0 1.1 +/- 1.6 < 4.4 -0.8 +/- 1.7 < 4.0 -0.4+/-1 .6 < 3.5 Co-60 0.6 +/- 1.9 < 2.9 0.2 +/-1 .8 < 3.3 1.4 +/- 1.8 < 1.8 -0.5+/-1.8 < 3.3 Zn-65 -4.9 +/- 4.0 < 5.8 -3.5 +/- 3.1 < 5.0 -5.2 +/- 4.3 < 6.4 0.2 +/- 3.1 < 6.4 Zr-Nb-95 -2.5+/-1.8 < 5.0 -2.7 +/- 1.7 < 4.4 -1 .1 +/- 1.9 < 5.9 -1.2 +/- 1.8 < 4.9 Cs-134 -0.2 +/- 1.8 < 3.7 -1.3 +/- 1.7 < 3.1 -0.8 +/- 1.8 < 3.7 -0.4 +/- 1.7 < 3.5 Cs-137 1.1+/-2.0 < 4.0 0.3 +/- 2.0 < 3.5 -0.6 +/- 2 .1 < 3.2 1.6 +/- 1.9 < 4.0 Ba-La-140 -0.4+/-1.9 -< 10.8 -0.9 +/- 2.0 < 11.3 -2.6 :t 1.8 < 13.5 -1.2 +/- 2.1 < 16.0
* *"ND" =No data; water frozen.
"LLD not reached due to age of sample and smaller sample volume (received 05-21-15/500 mL).
E-5
POINT BEACH NUCLEAR PlANT ( Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 10-15-15 10-15-15 10-15-15 10-15-15 Lab Code EWW- 6210 MDC EWW- 6211 MDC EWW- 6212 MDC EWW- 6213 MDC Se-7 9.9 +/- 12.0 < 34.3 -10.4 +/- 10.0 < 29.4 5.6 +/- 11 .8 < 28.8 -1 .3 +/- 11 .3 < 22.5 Mn-54 -0.2 +/- 1.2 < 1.9 -0.2 +/- 1.2 < 2.8 0.9 +/- 1.2 < 2.3 -0.1 +/- 1.1 < 2.2 Fe-59 2.5 +/- 2.3 < 5.7 0.6 +/- 2.3 < 4.5 0.2 +/- 2.4 < 4.0 -0.7 +/- 2.3 < 4.4 Co-58 0.1 +/- 1.3 < 2.4 -0.7 +/- 1.2 < 2.0 0.2 :i; 1.2 < 1.9 1.7 +/- 1.2 < 3.2 Co-60 0.9 :j; 1.5 < 2.5 0.4 +/- 1.2 < 2.1 0.4 +/- 1.3 < 2.4 -0.5 +/- 1.3 < 2.1 Zn-65 -1.0 +/- 2.7 < 4.5 -1 .8 .:!= 2.4 < 4.6 -2.7 +/- 2.7 < 3.8 -0.7 +/- 2.3 < 3.9 Zr-Nb-95 -1 .1 +/- 1.3 < 2.4 0.9 +/- 1.3 < 3.4 0.7 +/- 1.3 < 3.6 0.0 +/- 1.3 < 3.2 Cs-134 -0.4 +/- 1.3 < 2.6 0.1 +/- 1.3 < 2.4 -0.5 +/- 1.2 < 2.5 -1.4 +/- 1.2 < 2.5 Cs-137 -1.4 +/- 1.4 < 1.8 0.8 +/- 1.4 < 2.5 -0.2 +/- 1.3 < 2.3 0.1 +/- 1.4 < 1.7 Ba-La-140 -0.7 +/- 1.6 < 7.0 -0.9 +/- 1.3 < 7.2 -1.4 +/- 1.3 < 5.2 -0.9 +/- 1.4 < 3.5 l', E-6
POINT BEACH NUCLEAR PLANT
/ 'i \
APPENDIX F Special Analyses [ iJ F-1
f,.
- A-v='R IEnvironrnent:aJ, Inc.
1""'\B D Midwest: ll..aboratory 700 LontJwchr ROIHI* Northbrook, IL 6(){)f;2* 23f0 phone {847) SS4-D700
- TB>< {347) 564--4517 Corrected Report Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1145C Radiation Protection Mgr. DATE: 07-29-15 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-02-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the corrected results of the readout of supplemental TLDs deployed during the first quarter, 2015. Period: 1st Quarter, 2015 Date Annealed: 12/11/14 Date Placed: 01/02/15 Date Removed: 04/01/15 Date Read: 04/14/15 Days in the Field: 89 Days from Annealing to Readout: 124 In-transit exposure: 5.20 +/- 0.32 a
,/
1 Net mRa Net mRa Location Total mR Net mRa Std Qtr per 7 days SGSF-North 19.5 +/- 0.8 14.3 +/- 0.9 14.6 +/- 0.9 1.13+/-0.07 SGSF-East 16.8 +/- 0.8 11.6 +/- 0.8 11.8 +/- 0.8 0.91 +/- 0.06 SGSF-South 18.1 +/- 1.0 12.9+/-1.1 13.2 +/- 1.1 1.02 +/- 0.09 SGSF-West 17.4 +/- 0.5 12.2 +/- 0.6 12.5 +/- 0.6 0.96 +/- 0.04 ISFSI-North 37.6 +/- 0.9 32.4 +/- 1.0 33.1 +/- 1.0 2.55 +/- 0.08 ISFSI-East 45.8 +/- 0.5 40.6 +/- 0.6 41.6 +/- 0.6 3.20 +/- 0.05 ISFSI-South 20.0 +/- 0.7 14.8 +/- 0.8 15.1 +/- 0.8 1.16 +/- 0.06 ISFSI-West 60.9 +/- 3.3 55.7 +/- 3.4 56.9 +/- 3.4 4.38 +/- 0.26 Control 24.3 +/- 0.7 19.1 +/- 0.8 19.6 +/- 0.8 1.50 +/- 0.06 a original report dated 5/7/15 had an incorrect value for the in-transit exposure. The incorrect value caused the each of the original net mR values to be overstated by approximately 1.3 mR per standard quarter.
~~~~
Quality Assurance . { APPROVED \_ cc: K. Johansen
/ J\""FD Environmental. Inc.
'F"\. 0 Y Midwest Laboratory
*{ 700 Landwehr Roed
- Northbrook, /L 60062-2310 phone (847} 564-D700
- IS>< (1147) 664--4517 Mr. Richard Welty LAB ORA TORY REPORT NO.: 8006-100-1150 Radiation Protection Mgr. DATE: 07-29-15 Point Beach Nuclear Plant SAMPLES RECEIVED: .07-03-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2015. Period: 2nd Quarter, 2015 Date Annealed: 03/24/15
- Date Placed: 04/01/15 Date Removed: 07/01/15 Date Read: 07/06/15 Days in the Field: 91 Days from Annealing to Readout: 104 In-transit exposure: 1.78 +/- 0.07 NetmR NetmR
\- Location Total mR NetmR Std Qtr per 7 days SGSF-North 14.7 +/- 0.4 12.9 +/- 0.4 12.9 +/- 0.4 0.99 +/- 0.03 SGSF-East 13.1 +/- 0.2 11.3 +/- 0.2 11.3 +/-0.2 0.87 +/- 0.01 SGSF-South 14.2 +/- 0.5 12.4 +/- 0.5 12.4 +/- 0.5 0.96 +/- 0.04 SGSF-West 14.3 +/- 0.8 12.5 +/- 0.8 12.5 +/- 0.8 0.96 +/- 0.06 ISFSI-North 28.2 +/- 1.4 26.4 +/- 1.4 26.4 +/- 1.4 2.03+/-0.11 ISFSI-East 44.1 +/- 1.5 42.3 +/- 1.5 42.3 +/- 1.5 3.25 +/- 0.12 ISFSI-South 16.6 +/- 1.3 14.8 +/- 1.3 14.8 +/- 1.3 1.14+/-0.10 ISFSI-West 59.3 +/- 2.4 57.5 +/- 2.4 57.5 +/- 2.4 4.42 +/- 0.19 Control 15.9 +/- 0.7 14.1 +/-0.7 14.1 +/-0.7 1.09 +/- 0.05 2:!::~
Quality Assurance APPROVED ( cc: K. Johansen
A-rl Environmental. Inc .
/ .,..,... . I M idwest Lab orat:ory 700 Lenrtwehr Roed
- Norlhbror>k, IL 60062-2310 phone (8 47) M<l-0700
- ft<< (847} M4-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1164C Radiation Protection Mgr. DATE: 12-04-15 Point Beach Nuclear Plant SAMPLES RECEIVED: 09-28-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Corrected Report Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2015. 8 Period: 3rd Quarter, 2015 a Date Annealed: 06/08/15 Date Placed: 07/01/15 Date Removed: 09/24/15 Date Read: 10/01/15 Days in the Field: 85 Days from Annealing to Readout: 115 In-transit exposure: 4.09 +/- 0.18
/ NetmR NetmR (i Location Total mR NetmR Std Qtr per 7 days SGSF-North 17.2 +/- 0.9 13.1 +/-0.9 14.0 +/- 0.9 1.08 +/- 0.07 SGSF-East 15.0 +/- 0.7 10.9 +/- 0.7 11.7+/-0.7 0.90 +/- 0.06 SGSF-Soi.lth 16.2 +/- 0.3 12.1 +/- 0.4 13.0+/-0.4 1.00 +/- 0.03 SGSF-West 15.6 +/- 0.5 11.5 +/- 0.6 12.3 +/- 0.6 0.95 +/- 0.05 ISFSI-North 34.2 +/- 0.7 30.1 +/- 0.7 32.2 +/- 0.8 2.48 +/- 0.06 ISFSI-East 40.7 +/- 0.9 36.6 +/- 0.9 39.2 +/- 0.9 3.02 +/- 0.07 ISFSI-South 17.9 +/- 0.6 13.8 +/- 0.6 14.8 +/- 0.7 1.14+/-0.05 ISFSI-West 54.3 +/- 2.8 50.2 +/- 2.8 53.7 +/- 3.0 4.13 +/- 0.23 Control 21.9 +/- 0.8 17.8 +/- 0.8 19.1 +/- 0.8 1.47 +/- 0.06 a The original report had a typographical error referencing the wrong period as footnoted above.
All other reported values were correct as originally reported. u~~~ ~u:~i~ Assurance APPROVED ( cc: K. Johansen
A . , Environmental, Inc.
- 1""\1 I Midwest Laboratory
/ 700 Lvndwehr Road
- Norlhbroolc, /L 60062,-2310 pho,., (1147) U4-l1700
- fox (847) 68~17 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1169 Radiation Protection Mgr. DATE: 02-01-16 Point Beach Nuclear Plant SAMPLES RECEIVED: 01-07-16 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2015. Period: 4th Quarter, 2015 Date Annealed: 09/11/15 Date Placed: 09/24/15 Date Removed: 01/06/16 Date Read: 01/09/16 Days in the Field: 104 Days from Annealing to Readout: 120 In-transit exposure: 2.21 +/- 0.20 / NetmR NetmR Location Total mR NetmR Std Qtr per 7 days SGSF-North 17.5 +/- 0.4 15.3 +/- 0.4 13.4 +/- 0.4 1.03 +/- 0.03 SGSF-East 16.1 +/-0.4 13.9 +/- 0.5 12.2 +/- 0.4 0.94 +/- 0.03 SGSF-South 17.7 +/- 0.7 15.4 +/- 0.7 13.5 +/- Q.6 1.04 +/- 0.05 SGSF-West 18.2 +/- 1.0 16.0 +/- 1.0 14.0 +/- 0.9 1.08 +/- 0.07 ISFSI-North 34.6 +/- 2.4 32.4 +/- 2.4 28.3 +/- 2.1 2.18 +/- 0.16 ISFSI-East 53.7 +/- 1.2 51.5 +/- 1.2 45.1 +/- 1.1 3.47 +/- 0.08 ISFSI-South 20.6 +/- 0.9 18.4 +/- 0.9 16.1 +/-0.8 1.24 +/- 0.06 ISFSI-West 69.0 +/- 0.9 66.8 +/- 0.9 58.4 +/- 0.8 4.50 +/- 0.06 Control 19.3 +/- 0.5 17.1 +/-0.6 14.9 +/- 0.5 1.15+/-0.04 (!::~~~ Quality Assurance APPROVED cc:K.Johansen
~+.L ATf Environmental, Inc. ,-~I""\ I Midwest Laboratory 700 Landwehr Ro*d
- NOI1hbro0k, IL 60062-2310 phone (847} 564-D700
- fax (847} 564-4517 Dr. Kjell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-1 00-1170 Point Beach Nwclear Plant DATE: 02-08-2016 6610 Nuclear Road SAMPLES RECEIVED:
Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.: Below are the results of the analyses for tritium in monthly lake water samples. Sample Collection Lab Concentration I MDC (pCi/L) Location Date Code H-3 E-05 10-14-15 ELW-5785 -47 +/- 90 I< 152 E-05 11-05-15 ELW-6354 -10 +/- 92/ < 152 E-05 12-10-15 ELW-6939 1,336 +/- 139/ < 151 E-33 10-14-15 ELW-5787 -25 +/- 91/ < 152 E-33 11-05-15 ELW-6356 68 +/- 95/ < 152 E-33 12-10-15 ELW-6941 464+/- 111/< 151 E-01 12-10-15 ELW-6938 76 +/- 89/ < 141 E-06 12-10-15 ELW-6940 79 +/- 89/ < 141 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. E-mail: kjell.iohansen@NextERAEnergy.com
~ :zj?/10 APPROVED BY:_-/--P~-:--=-'~-'----:-::----
NEXTera ENERGY ~ POINT BEACH April28, 2016 NRC 2016-0020 10 CFR 72.44 TS 5.6.2 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 2015 Annual Monitoring Report In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31 , 2015. The Annual Monitoring Report contains information relating to the effluent impact upon the public, as well as information relating to plant releases, solid waste shipments, results from the radiological environmental monitoring program, the groundwater protection program, and miscellaneous monitoring activities which occurred in 2015. 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. The contracted laboratory's final Radiological Environmental Monitoring Program results (Appendix 1) is included. This letter contains no new regulatory commitments and no revisions to existing regulatory commitments. Very truly yours, NextEra Energy Point Beach, LLC Enclosures cc: Administrator, Region Ill, 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 Office of Nuclear Material Safety and Safeguards, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road , Two Rivers, WI 54241
ENCLOSURE 1 ANNUAL MONITORING REPORT 2015 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2), 72-005 (ISFSI) RENEWED LICENSES DPR-24 and DPR-27 January 1, 2015 through December 31, 2015
TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 3 2.0 Radioactive Liquid Releases 4 3.0 Radioactive Airborne Releases 10 4.0 Radioactive Solid Waste Shipments 16 5.0 Nonradioactive Chemical Releases 18 6.0 Circulating Water System Operation 19 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 20 Part C: Radiological Environmental Monitoring 8.0 Introduction 21 9.0 Program Description 22 10.0 Results 34 11.0 Discussion 39 12.0 REMP Conclusion 54 Part D: Groundwater Monitoring 13.0 Program Description 55 14.0 Results and Discussion 58 15.0 Groundwater Summary 63 Appendix 1: Environmental, Inc. Midwest Laboratory, Final Report for Point Beach Nuclear Plant ii
LIST OF TABLES Table 2-1 Comparison of 2015 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 4 Table 2-2 Summary of Circulating Water Discharge 6 Table 2-3 Isotopic Composition of Circulating Water Discharges 7 Table 2-4 Subsoil System Drains - Tritium Summary 8 Table 3-1 Comparison of 2015 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 13 Table 3-2 Radioactive Airborne Effluent Release Summary 13 Table 3-3 Isotopic Composition of Airborne Releases 14 Table 3-4 Comparison of Airborne Effluent Doses 15 Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2015 16 Table 4-2 2015 PBNP Radioactive Waste Shipments 16 Table 4-3 2015 Estimated Solid Waste Major Radionuclide Composition 17 Table 6-1 Circulating Water System Operation for 2015 19 Table 9-1 PBNP REMP Sample Analysis and Frequency 25 Table 9-2 PBNP REMP Sampling Locations 26 Table 9-3 ISFSI Sampling Sites 30 Table 9-4 Minimum Acceptable Sample Size 30 Table 9-5 Deviations from Scheduled Sampling and Frequency During 2015 31 Table 9-6 Sample Collection for the State of Wisconsin 31 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2015 36/37 Table 10-2 Feed Crops Grown on Point Beach Land 38 Table 10-3 Average ISFSI Fence TLD Results for 2015 38 Table 11-1 Average Indicator TLD Results from 1993-2015 39 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 40 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 41 Table 11-4 Average Gross Beta Measurements in Air 44 Table 14-1 Intermittent Streams and Bogs 58 Table 14-2 2015 Beach Drain Tritium 59 Table 14-3 2015 East Yard Area Manhole Tritium (pCi/L) 60 Table 14-4 2015 Façade Well Water Tritium (pCi/L) 61 Table 14-5 2015 Unit 2 Façade SSD Sump H-3 (pCi/L) 61 Table 14-6 2015 Quarterly Monitoring Well Tritium (pCi/L) 62 Table 14-7 2015 Potable Well Water Tritium Concentration (pCi/L) 63 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 27 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29 Figure 11-1 ISFSI Area TLD Results (1995 - 2015) 41 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 42 Figure 11-3 Sr-90 Concentration in Milk (1997 - 2015) 43 Figure 11-4 Annual Average Air Gross (1993 - 2015) 44 Figure 11-5 2015 Airborne Gross Beta 44 Figure 11-6 E-01 Results 1971 - 2015 51 Figure 11-7 Comparison of E-03 and E-20 Results 1971 - 2015 52 Figure 11-8 Comparison of E-01, E-02, E-03, and E-04 Results 1992 - 2015 52 iii
Figure 11-9 E-03, E-31, and Background Site E-20 Results 1992 - 2015 53 Figure 13-1 Groundwater Monitoring Locations 57 iv
SUMMARY
The Annual Monitoring Report for the period from January 1, 2015, through December 31, 2015, 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, non-radioactive chemical releases, and circulating water system operation. During 2015, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways: Liquid Atmospheric Tritium (Ci) 866 80.1 1 Particulate (Ci) 0.0516 0.0000689 Noble Gas (Ci) (-) 0.826 C-142 0.0197 11.75 (-)Noble gases in the liquids are added to the atmospheric release totals. 1 Atmospheric particulate includes radioiodine (I-131 - I-133). 2 Liquid is measured, atmospheric is calculated. 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) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I. LIQUID RELEASES Dose Category Calculated Dose Appendix I Dose Whole body dose 0.00684 mrem 6 mrem Organ dose 0.00684 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose Particulate organ dose 0.0315 mrem 30 mrem Noble gas beta air dose 0.0000996 mrad 40 mrad Noble gas gamma ray air dose 0.000274 mrad 20 mrad Noble gas dose to the skin 0.000349 mrem 30 mrem Noble gas dose to the whole body 0.00234 mrem 10 mrem 1
The results show that during 2015, the doses from PBNP effluents were a small percentage (0.12%) of the Appendix I design objectives. Therefore, operation of the PBNP radwaste treatment system continues to be ALARA. 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. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of the remaining ten sectors over land containing identifies any changes in the closest garden, occupied dwelling, and dairy in each sector. The 2014 LUC results confirmed the assumption that, for the purpose of calculating effluent doses, the maximally exposed person lives at the south boundary remains conservative. There is no change in that assumption for 2015. The 2015 Radiological Environmental Monitoring Program (REMP) collected 771 individual samples for radiological analyses. Quarterly composites of weekly air particulate filters generated an additional 24 samples and quarterly composites of monthly lake water samples resulted in a further 16 samples. Finally, 10 crop samples grown on the site were analyzed. This yields a total of 821 samples. The ambient radiation measurements in the vicinity of PBNP and the ISFSI was conducted using 146 sets of thermoluminescent dosimeters (TLDs). Air monitoring from six different sites did not reveal any effect from Point Beach effluents. 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. No new dry storage units added to the ISFSI in 2015. The total number remains at 39 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 23 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 2015 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment. One-hundred-fifty-two (152) samples were analyzed for H-3 as part of the groundwater protection program (GWPP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, and surface water on site. Also included in this number were a sump associated with the subsurface drainage system (SSD) located under the plant foundation, and four groundwater containment integrity monitoring wells located in the facades. The results show no substantial change in H-3 from previous years. Low levels of tritium continue under the plant foundation. No drinking water wells (depth >100 feet) have any detectable H-3. Tritium continues to be confined to the upper soil layer where the flow is toward the lake. Groundwater samples from wells in the vicinity of the remediated, former earthen retention pond continue to show low levels of H-3 whereas none was detectable in the wells monitoring the potential offsite tritium movement. Gamma scans of samples originating within the power block found no plant related gamma emitters. The results of GWPP monitoring indicate no significant change from previous years. 2
Part A EFFLUENT MONITORING
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 as low as reasonably achievable (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 licensees 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. 10 CFR 72.210 grants a general license for an Independent Spent Fuel Storage Installation (ISFSI) to all nuclear power reactor sites operating under 10 CFR 50. The annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable. However, any 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. 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. 3
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 /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 2015 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) 0.00684 0.114 % 20 (any organ) 0.00684 0.0342 % 2.2 2015 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 semi-annual and annual totals (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, the Unit 1 and 2 facade sumps and the subsurface drainage system sump. 2.3 2015 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. 4
The 2015 processed waste volume (Table 2-2) decreased about 20% from 2014 (8.76E+05 to 6.94E+05 gallons). Additionally, there was a concomitant decrease in the total isotopic curie distribution (gamma emitters plus hard-to-detects other that strontium) from 6.42E-02 Ci to 5.16E-02 Ci. In contrast, Sn-113/117m increased (from 3.11E-03 to 4.67E-03 Ci) whereas Sb-122/124/125 decreased (from 3.48E-03 Ci to 6.55E-04 Ci). Decreases also occurred in Co-58/60, Cr-51, Mn-54, Fe-55/59, and Zn-65 whereas Ni-63 increased. C-14 also had a small increase from 1.15E-02 to 1.97E-02 Ci in 2015. As in 2013 and 2014, no Sr-89 or Sr-90 was detected in liquids during 2015. H-3 increased from 796 to 866 Ci in 2015. Tritium continues to be the major radionuclide released via liquid discharges. 2.4 Beach Drain System Releases Tritium Summary Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of these outfalls carry yard and roof drain runoff to the beach. A seventh outfall drains a small portion of the grassy area on top of the bluff overlooking the lake. The quarterly results from the monthly beach drain samples are presented in Table 2-4. The total monthly flow is calculated assuming that the flow rate at the time of sampling persists for the whole month. In 2015, no tritium was observed at the effluent LLDs. No H-3 found in the beach drains is included in the effluent totals unless it can be shown to be the result of a spill or similar event. Because the source of beach drain H-3 has been determined to be recapture, including beach drain H-3 in the effluent totals would be double counting (NRC RIS 2008-03, Return/re-use of previously discharged radioactive effluents). The principle source of water for the beach drains is the yard drain system. Yard drain water sources are rain and snow melt. During the winter natural melting is the principle source. (In the past, runoff has been enhanced by the use of snow melting machines where the melt water is emptied into the yard drains. [See Section 14.2 for further discussion.] ) Additionally, various roof drains connect to the yard drain system. In addition to precipitation, the roof drains also carry condensate from various building AC units. A secondary source may be groundwater in leakage. This is evidenced by flow during periods of no precipitation. Because there are no external storage tanks or piping that carries radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne H-3 discharges via the yard drain system. Because of these various recapture sources, the beach drains also are sampled as part of the groundwater monitoring program. These results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report. 5
Table 2-2 Summary of Circulating Water Discharge January 1, 2015 through December 31, 2015 Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci) Gamma Scan(+HTDs)1 6.21E-04 7.02E-04 1.77E-03 2.53E-04 3.82E-03 5.72E-03 1.29E-02 1.40E-03 1.03E-03 4.81E-03 9.23E-03 8.18E-03 1.41E-02 5.16E-02 Gross Alpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium 0.00E+00 4.76E+00 9.71E+01 1.43E+01 3.45E+01 1.19E+02 2.70E+02 7.69E+01 7.76E+01 1.51E+02 5.59E+01 3.82E+01 1.97E+02 8.66E+02 Strontium (89/90/92) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Vol Released (gal) Processed Waste 0.00E+00 8.04E+03 4.05E+04 2.08E+04 3.12E+04 3.51E+04 1.36E+05 3.09E+04 4.02E+04 1.34E+05 1.28E+05 1.08E+05 1.17E+05 6.94E+05 Waste Water Effluent2 3.12E+06 2.57E+06 2.44E+06 2.56E+06 2.48E+06 2.47E+06 1.56E+07 2.77E+06 2.74E+06 3.06E+06 2.74E+06 2.91E+06 3.45E+06 3.33E+07 U1 SG Blowdown 2.76E+06 2.41E+06 2.68E+06 2.69E+06 3.16E+06 2.59E+06 1.63E+07 2.67E+06 2.57E+06 2.80E+06 2.68E+06 2.64E+06 2.96E+06 3.26E+07 U2 SG Blowdown 3.87E+06 1.63E+06 1.84E+06 1.75E+06 6.95E+05 1.75E+06 1.15E+07 1.77E+06 2.24E+06 2.45E+06 5.72E+05 4.31E+06 2.96E+06 2.58E+07 Total Gallons 9.75E+06 6.62E+06 7.00E+06 7.02E+06 6.37E+06 6.85E+06 4.36E+07 7.23E+06 7.59E+06 8.45E+06 6.12E+06 9.97E+06 9.49E+06 9.25E+07 Total cc 3.69E+10 2.51E+10 2.65E+10 2.66E+10 2.41E+10 2.59E+10 1.65E+11 2.74E+10 2.87E+10 3.20E+10 2.31E+10 3.77E+10 3.59E+10 3.50E+11 Dilution vol(cc)3 8.18E+13 7.39E+13 8.18E+13 1.18E+14 1.26E+14 1.22E+14 6.03E+14 1.26E+14 1.26E+14 1.22E+14 7.60E+13 1.18E+14 1.22E+14 1.29E+15 Avg diluted discharge conc (Ci/cc) Gamma Scan (+HTDs)1 7.59E-12 9.50E-12 2.17E-11 2.14E-12 3.04E-11 4.70E-11 1.11E-11 8.20E-12 3.95E-11 1.21E-10 6.96E-11 1.15E-10 Gross Alpha 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium 0.00E+00 6.44E-08 1.19E-06 2.15E-07 2.74E-07 9.79E-07 6.12E-07 6.17E-07 1.24E-06 7.35E-07 3.25E-07 1.61E-06 Strontium (89/90/92) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Max Batch Discharge Conc (Ci/cc) Tritium 0.00E+00 9.09E-06 3.23E-05 9.30E-06 2.03E-05 3.86E-05 3.61E-05 3.25E-05 3.92E-05 2.34E-05 1.55E-05 4.06E-05 Gamma Scan 7.59E-12 1.46E-11 1.22E-09 4.68E-11 2.93E-09 4.55E-10 5.08E-11 6.87E-11 1.77E-09 5.43E-09 2.76E-09 1.53E-09 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately. 2 The waste water effluent system replaced the Retention Pond which was taken out of service in September 2002. 3 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, 2015 through December 31, 2015 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 0.00E+00 4.76E+00 9.71E+01 1.43E+01 3.45E+01 1.19E+02 2.70E+02 7.69E+01 7.76E+01 1.51E+02 5.59E+01 3.82E+01 1.97E+02 8.66E+02 C-14 0.00E+00 0.00E+00 1.04E-04 0.00E+00 3.78E-04 4.65E-03 5.13E-03 1.00E-04 3.04E-04 3.86E-03 1.60E-04 3.46E-04 9.78E-03 1.97E-02 F-18 6.21E-04 6.95E-04 3.97E-04 1.54E-04 5.97E-04 2.22E-04 2.69E-03 1.20E-03 5.72E-04 5.32E-04 1.75E-04 4.73E-04 1.08E-03 6.71E-03 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.37E-03 1.45E-03 0.00E+00 3.82E-03 Mn-54 0.00E+00 0.00E+00 9.92E-06 0.00E+00 5.26E-06 3.16E-06 1.83E-05 0.00E+00 1.84E-06 0.00E+00 8.79E-05 6.34E-05 2.47E-06 1.74E-04 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-04 0.00E+00 1.18E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E-04 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.55E-05 0.00E+00 0.00E+00 1.55E-05 Co-57 0.00E+00 0.00E+00 3.61E-06 0.00E+00 1.47E-05 4.20E-06 2.25E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-05 Co-58 0.00E+00 3.90E-06 6.03E-04 5.94E-06 1.83E-03 4.32E-04 2.87E-03 2.07E-05 1.98E-05 1.13E-05 2.28E-03 2.06E-03 1.80E-03 9.06E-03 Co-60 0.00E+00 3.71E-06 4.15E-04 4.53E-06 2.94E-04 2.26E-04 9.43E-04 5.03E-05 9.35E-05 3.00E-04 1.44E-03 8.87E-04 3.38E-04 4.05E-03 Ni-63 0.00E+00 0.00E+00 8.28E-05 2.13E-05 4.02E-04 1.17E-04 6.23E-04 1.75E-05 2.13E-05 0.00E+00 6.78E-05 6.11E-05 8.44E-05 8.75E-04 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.48E-05 0.00E+00 0.00E+00 1.48E-05 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.74E-05 0.00E+00 2.74E-05 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 0.00E+00 0.00E+00 2.13E-05 0.00E+00 0.00E+00 0.00E+00 2.13E-05 0.00E+00 0.00E+00 0.00E+00 5.23E-04 4.03E-04 2.67E-05 9.74E-04 Nb-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.66E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-07 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.27E-04 2.25E-04 4.87E-06 5.57E-04 Tc-99 0.00E+00 0.00E+00 1.04E-05 1.26E-05 6.73E-06 0.00E+00 2.98E-05 4.56E-06 1.49E-05 4.11E-05 0.00E+00 0.00E+00 6.22E-06 9.66E-05 Ag-110m 0.00E+00 0.00E+00 0.00E+00 5.44E-05 5.40E-05 2.11E-06 1.11E-04 3.15E-06 0.00E+00 0.00E+00 2.20E-05 2.25E-06 0.00E+00 1.38E-04 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-117m 0.00E+00 0.00E+00 1.27E-04 0.00E+00 3.18E-05 3.24E-05 1.91E-04 7.55E-06 3.79E-06 2.07E-06 1.66E-03 2.07E-03 7.33E-04 4.67E-03 Sb-122 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.02E-05 5.84E-06 2.61E-05 0.00E+00 0.00E+00 0.00E+00 4.52E-05 1.11E-04 1.99E-04 3.80E-04 Sb-125 3.80E-05 0.00E+00 0.00E+00 0.00E+00 6.79E-05 1.94E-05 1.25E-04 0.00E+00 0.00E+00 6.13E-05 3.09E-05 1.03E-06 5.68E-05 2.75E-04 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.59E-07 6.11E-06 1.79E-06 0.00E+00 8.87E-06 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries. "-" = no analysis 7
Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2015, through December 31, 2015 S-1 S-3 S-7 S-8 S-9 S-10 S-11 1st Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2nd Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 1.41E+06 2.49E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.35E+04 3rd Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 1.34E+05 4.46E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4th Qtr H-3 (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Flow (gal) 4.40E+05 1.32E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.6 Land Application of Sewage Sludge and Wastewater In 1988, pursuant to 10 CFR 20.302(a), Point Beach received NRC approval for the disposal of sewage sludge, which may contain trace amounts of radionuclides, by land application on acreage within the site. Land application of sewage sludge is regulated by the Wisconsin Department of Natural Resources. Point Beach has not land applied sewage sludge for over a decade. Therefore, Point Beach has not renewed its WI DNR permit to dispose of sewage sludge in this manner. There were no sludge disposals by land application during 2015. All disposals were done at the Manitowoc Sewage Treatment Plant. 2.7 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors, but the amounts produced are less than C-14 produced by weapons testing or that occur naturally. Based on information from the NRC obtained at industry sponsored workshops, NextEra Point Beach began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 [RG 1.21], Rev 2 in June of 2009. Point Beach continues to analyze batch liquid waste discharges for C-14 and reporting the results in the Annual Monitoring Report. The NRC requested that all nuclear plants report C-14 emissions beginning with the 2010 monitoring reports. Pursuant to NRC guidance in RG 1.21(Rev 2), evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions. 8
However, as stated above, Point Beach began C-14 analyses and reporting prior to the issuance of RG 1.21 (Rev 2). RG 1.21 states that a radionuclide is a principal effluent component if it contributes greater than 1% of the Appendix I design objective dose compared to the other radionuclides in the effluent type, or, if it is greater than 1% of the activity of all radionuclides in the effluent type. In this case, C-14 is compared to other (non-tritium or noble gases) radionuclides discharged in liquids. For 2015, the monthly and total C-14 (1.97E-02 Ci) in liquid discharges are documented in Table 2-3. The amount of C-14 released makes up about 38% of the non-tritium radionuclides released in liquids. The liquid C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual (Table 2-1). Under the parameters and pathways used for the dose calculations, there is no C-14 dose contribution to the infant age group. For the remaining age groups, the C-14 contributes roughly 85% of the bone dose and 1.5 - 2.7% of the dose to the whole body and to other organs specified in RG 1.109. 9
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 maximum exposed individual (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, 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. C-14 is not included in the Appendix I calculations because it is not an Appendix I radionuclide. The C-14 dose calculation has been required since 2010 (see Sections 3.4 through 3.6, below, for a more detailed description) and is treated separately. The comparison between airborne effluent doses with and without C-14 is shown in Table 3-4. The highest Appendix I dose is the child age group for the liver, thyroid, kidney, lung, and GI-LLI at 3.15E-02 mrem. Had C-14 been included, the child-bone dose would have been the highest at 2.42E-01 mrem. 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 2015 is summarized in Table 3-2. The particulate total is slightly lower in 2015 than in 2014 (6.34E-05 Ci vs. 6.60E-05 Ci). H-3 increased slightly from 75.5 Ci to 80.1 Ci. Noble gases decreased from 1.44E+00 to 8.26E-01Ci. 3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2015, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections. As in 2014, in 2015 the outage impact of the isotopic mixture is demonstrated in the comparison of the October particulate releases. During October nine different particulates were identified in the airborne effluent whereas in the non-outage months, at most three were found. Most are released via the open hatch on the 66-foot elevation of containment. The convective flow through the open hatch during purge is unfiltered. Although the flow is into the façade, there are two circumferential gaps around the façade. It is assumed that the release into 10
façade is transferred to the outside and therefore is treated as a release to the environment. 3.4 Carbon-14 C-14 is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors as neutrons interact with the dissolved oxygen and nitrogen in the primary coolant. However, these amounts produced by nuclear reactors are much less that those produced by weapons testing or that occur naturally. The NRC has requested that nuclear plants report C-14 emissions. C-14 is a hard-to-detect radionuclide. It is not a gamma emitter and must be chemically separated from the effluent stream before it can be measured. Because nuclear plants currently are not equipped to perform this type of sampling, RG 1.21 allows for calculating C-14 discharges based on fission rates. The Electric Power Research Institute (EPRI) developed the methodology for calculating C-14 generation and releases for the nuclear industry. The results were published as Technical Report 1021106 (December 2010), Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." In addition to neutron flux, the percent oxygen and nitrogen in the VCTs is used in the C-14 calculation as both gases contribute to the generation of C-14. Pursuant to NRC guidance (Regulatory Guide 1.21, Rev 2, p. 16, June 2009), most of the C-14 emissions from nuclear plant occur in the gaseous phase. The Point Beach C-14 generation for 2015 was calculated using the EPRI guidance and the current core parameters resulting from the power uprate. The calculated amounts were 5.89 Ci for Unit 1 and 5.85 Ci for Unit 2 yielding a total of 11.75 Ci which is 0.11 Ci lower than 2014. It is noted that the nitrogen in the VCTs also was lower 2015 than in 2014. The 2015 calculated total 11.75 Ci is roughly 600 times higher than the 1.97E-02 Ci of C-14 determined by analyses of composites from liquid waste batch discharges, steam generator blowdown, and other waste streams. 3.5 C-14 Airborne Effluent Dose Calculation The dose from the airborne C-14 is dependent on its chemical form. The C-14 released to the atmosphere consists of both organic and inorganic species. Both the inorganic and organic C-14 contributes to the inhalation dose. Only the inorganic 14CO2 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH4, are not photosynthetically active. For PWRs such as PBNP most of the gaseous C-14 occurs as methane, 14CH4, not as carbon dioxide, 14CO2. The amount of 14CO2 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR sites similar to the PBNP design. The Ginna nuclear generating station is of similar design to PBNP. It is a Westinghouse 2-loop PWR of the same vintage as PBNP and approximately the same power (prior to the PBNP power uprate). 11
Measurements at Ginna for 18 months in 1980 - 1981 (Kunz, "Measurement of 14 C Production and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-14 was discharged as 14CO2. Therefore, 10% of the 11.75 Ci of the calculated C-14 for PBNP will be used in the ingestion dose calculations. C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 1.109. The inhalation dose was calculated using all of the C-14 calculated to be released. All the C-14 is used because whether the C-14 is in the form of 14CO2 or one of the organic forms, such as CH4, both would be inhaled and contribute to a lung dose. For the other existing pathways, milk, meat, and produce, the dose depends upon the amount incorporated into biomass consumed by cattle and people: forage for cattle and produce for humans. Incorporation only occurs via photosynthesis. Photosynthesis only incorporates 14CO2 and hence the use only of the 10% fraction of the total C-14 release for these pathways. The airborne effluent C-14 dose calculations were made as described above. They were made for the MEI as explained in Section 2.1. This approach utilizes all the pathways that are applicable to a hypothetical person residing at the site boundary. Because C-14 is present as a gas, the pathways are milk, meat, and produce (vegetables, fruit, and grain) and the Regulatory Guide 1.109, Table E-5 usage factors applied to the calculation. As such, the resulting dose will be conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-14 doses are calculated. Furthermore, because leafy vegetables are included in the produce pathway, they are not used as a separate pathway because that would result in double accounting for leafy vegetable dose contribution. Carbon-14 is not an Appendix I radionuclide. Therefore, airborne C-14 is not summed with the other airborne radioactive effluents for comparison of airborne effluent dose to the Appendix I dose objectives. However, the C-14 doses are presented and compared to the other radionuclide doses in Table 3-4. 3.6 C-14 Measurements No C-14 measurements were made of PBNP airborne effluents. In 2010, C-14 was measured in crops grown on fields in the owner controlled area located in the highest /Q sector at the site's south boundary. One field is leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans are grown by another farmer. These two crops were sampled in this sector and as well as in a background location about 17 miles SW of the plant. Based on the measurement error, there was no statistical difference between the results obtained on site in the highest /Q sector as compared to the background site some 17 miles away (2013 AMR, Table 10-3). These results demonstrated that the dose from C-14 in Point Beach airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants (1 mrem: NCRP Report 93, Ionizing Radiation Exposure of the Population of the United States, 1987, p.12). . 12
Table 3-1 Comparison of 2015 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 0.0315 mrem 0.105 Noble gas 40 mrad (beta air) 0.0000996 mrad 0.000249 Noble gas 20 mrad (gamma air) 0.000247 mrad 0.00124 Noble gas 30 mrem (skin) 0.000349 mrem 0.00116 Noble gas 10 mrem (whole body) 0.000234 mrem 0.00234 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2015, through December 31, 2015 Total Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) 0.00E+00 0.00E+00 7.65E-04 0.00E+00 4.01E-05 9.48E-04 1.75E-03 6.64E-04 1.54E-03 1.02E-02 3.81E-03 2.79E-03 1.25E-02 3.33E-02 Total Noble Gas (Ci)1 7.82E-02 1.15E-01 7.39E-02 5.76E-02 5.44E-02 6.34E-02 4.43E-01 6.32E-02 7.55E-02 7.59E-02 4.55E-02 4.58E-02 7.69E-02 8.26E-01 Total Radioiodines (Ci)2 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.61E-09 Total Particulate (Ci)3 7.10E-06 5.06E-07 2.92E-05 0.00E+00 0.00E+00 0.00E+00 3.68E-05 0.00E+00 0.00E+00 3.27E-06 2.46E-05 3.87E-06 3.79E-07 6.89E-05 Alpha (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium(Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 All other beta + gamma (Ci) 7.10E-06 5.06E-07 2.92E-05 0.00E+00 0.00E+00 0.00E+00 3.68E-05 0.00E+00 0.00E+00 3.27E-06 2.46E-05 3.87E-06 3.79E-07 6.89E-05 Total Tritium (Ci) 6.52E+00 6.92E+00 9.10E+00 6.96E+00 5.22E+00 6.37E+00 4.11E+01 4.77E+00 3.81E+00 3.64E+00 1.43E+01 5.58E+00 6.90E+00 8.01E+01 Max NG H'rly Rel.(Ci/sec) 1.85E-07 7.48E-08 7.07E-08 6.90E-08 7.63E-08 7.44E-08 7.57E-08 6.89E-08 7.71E-08 5.62E-08 4.82E-08 6.10E-08 1 Total noble gas (airborne + liquid releases) does not include F-18 which is not a noble gas. F-18 monthly and annual totals are presented in Table 3-3.. 2 Airborne radioiodines only include I-131 and I-133. Although for dose calculations iodines are grouped with particulates, for this reporting table they are separated from the particulate group. 3 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or C-14. C-14 was calculated for the year and no monthly values are available. 13
TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2015 through December 31, 2015 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 6.52E+00 6.92E+00 9.10E+00 6.96E+00 5.22E+00 6.37E+00 4.11E+01 4.77E+00 3.81E+00 3.64E+00 1.43E+01 5.58E+00 6.90E+00 8.01E+01 Ar-41 4.71E-02 4.34E-02 5.03E-02 4.65E-02 4.11E-02 4.81E-02 2.76E-01 4.77E-02 5.82E-02 5.52E-02 2.27E-02 3.75E-02 5.06E-02 5.48E-01 Kr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m 0.00E+00 4.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.49E-05 4.48E-04 Xe-133 3.10E-02 6.96E-02 2.35E-02 1.09E-02 1.32E-02 1.51E-02 1.63E-01 1.55E-02 1.70E-02 2.03E-02 2.25E-02 8.24E-03 2.60E-02 2.73E-01 Xe-133m 2.35E-05 9.46E-04 5.14E-05 0.00E+00 0.00E+00 0.00E+00 1.02E-03 0.00E+00 1.77E-05 9.67E-05 2.60E-04 0.00E+00 1.23E-04 1.52E-03 Xe-135 1.10E-04 1.13E-03 0.00E+00 2.21E-04 1.75E-04 1.71E-04 1.80E-03 0.00E+00 2.46E-04 3.21E-04 7.89E-05 2.95E-05 1.85E-04 2.66E-03 Xe-135m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 6.96E-06 0.00E+00 2.68E-05 0.00E+00 0.00E+00 0.00E+00 3.38E-05 0.00E+00 0.00E+00 3.27E-06 1.25E-06 3.86E-06 3.65E-07 4.25E-05 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.06E-06 0.00E+00 0.00E+00 1.06E-06 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 1.41E-07 5.04E-07 2.42E-06 0.00E+00 0.00E+00 0.00E+00 3.07E-06 0.00E+00 0.00E+00 0.00E+00 7.61E-07 3.53E-10 0.00E+00 3.83E-06 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-06 0.00E+00 0.00E+00 1.03E-06 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.36E-07 0.00E+00 0.00E+00 3.36E-07 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.60E-07 0.00E+00 0.00E+00 1.60E-07 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 2.61E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.61E-09 Sb-124 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 0.00E+00 1.49E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E-09 0.00E+00 0.00E+00 0.00E+00 1.49E-05 8.12E-09 1.01E-08 1.49E-05 Ni-63 0.00E+00 4.97E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.97E-10 0.00E+00 0.00E+00 0.00E+00 5.03E-06 2.74E-09 3.41E-09 5.04E-06 Tc-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-117m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Note: The Noble Gases listed above include the liquid contribution 14
Table 3-4 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2015 Appendix I (Airborne Particulate + Tritium) Dose (mrem) Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 1.93E-04 1.88E-02 1.88E-02 1.87E-02 1.87E-02 1.87E-02 1.88E-02 4.09E-05 Teen 2.58E-04 2.16E-02 2.16E-02 2.15E-02 2.16E-02 2.15E-02 2.16E-02 4.09E-05 Child 4.11E-04 3.15E-02 3.15E-02 3.15E-02 3.15E-02 3.15E-02 3.15E-02 4.09E-05 Infant 1.11E-04 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 1.39E-02 4.09E-05 2015 Carbon-14 Dose (mrem) Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.66E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 0.00E+00 Teen 1.04E-01 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 0.00E+00 Child 2.41E-01 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 0.00E+00 Infant 1.23E-01 2.61E-02 2.61E-02 2.61E-02 2.61E-02 2.61E-02 2.61E-02 0.00E+00 2015 Total Airborne Non-Noble Gas Dose (Particulate + H-3 + C-14 (mrem) Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.68E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 4.09E-05 Teen 1.05E-01 4.24E-02 4.24E-02 4.23E-02 4.23E-02 4.23E-02 4.23E-02 4.09E-05 Child 2.42E-01 7.96E-02 7.97E-02 7.96E-02 7.96E-02 7.96E-02 7.96E-02 4.09E-05 Infant 1.23E-01 4.00E-02 4.00E-02 3.99E-02 4.00E-02 3.99E-02 4.00E-02 4.09E-05 Ann.Limit 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01
% Limit 8.06E-01 2.65E-01 2.65E-01 2.65E-01 2.65E-01 2.65E-01 1.36E-04 The percent of limit is calculated using the highest total dose, the Child Age Group.
15
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 2015. No Types C or D waste 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 in 2015 A. Spent resins, filter sludge, evaporator bottoms, etc. 2.4 m3 65.100 Ci 84.0 ft3 B. Dry compressible waste, contaminated equipment, etc 205.8 m3 0.212 Ci 7266.0 ft3 C. Irradiated components, control rods, etc. 0.00 m3 N/A Ci ft3 3 D. Other 0.0 m N/A Ci 3 Steam generators: Unit 1 removed 1984; Unit 2 removed 1996 0 ft 4.2 Solid Waste Disposition There were four solid waste shipments from PBNP during 2015. The dates and destinations are shown in Table 4-2. Table 4-2 2015 PBNP Radioactive Waste Shipments Date Destination 01/14/15 Oak Ridge, TN 06/09/15 Andrews, TX 06/17/15 Clive, Utah 10/21/15 Oak Ridge, TN 4.3 Major Nuclide Composition (by Type of Waste) The major radionuclide content of the 2015 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 4-3. Only those radionuclides with detectable activity are listed. 16
Table 4-3 2015 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B Percent Activity Percent Activity Nuclide Abundance (mCi) Nuclide Abundance (mCi) TOTAL 100 6.51E+04 TOTAL 100 2.11E+02 Ni-63 3.442E+01 2.24E+04 Co-60 3.861E+01 8.16E+01 Co-58 2.320E+01 1.15E+04 Fe-55 3.216E+01 6.79E+01 Co-60 1.598E+01 1.04E+04 Co-58 6.508E+00 1.37E+01 Be-7 8.467E+00 5.51E+04 Cr-51 4.743E+00 1.00E+01 Fe-55 6.807E+00 4.43E+03 Ni-63 3.626E+00 7.66E+00 Sb-125 3.688E+00 2.40E+03 Sb-125 2.619E+00 5.53E+00 Mn-54 2.797E+00 1.82E+03 Nb-95 2.073E+00 4.38E+00 Cs-137 2.136E+00 1.39E+03 Ru-106 1.247E+00 2.64E+00 Ni-59 4.287E-01 2.79E+02 Zr-95 1.132E+00 2.39E+00 Sb-124 3.596E-01 2.34E+02 Tc-99 1.131E+00 2.39E+00 Co-57 3.550E-01 2.31E+02 Sn-113 1.011E+00 2.14E+00 Ag-110m 3.304E-01 2.15E+02 Mn-54 1.006E+00 2.12E+00 Nb-95 2.366E-01 1.54E+02 Sb-124 7.820E-01 1.65E+00 C-14 2.136E-01 1.39E+02 Ni-59 7.370E-01 1.56E+00 Sn-113 2.013E-01 1.31E+02 Zn-65 4.180E-01 8.83E+02 H-3 1.613E-01 1.05E+02 Fe-59 3.450E-01 7.28E-01 Ce-144 8.744E-02 5.69E+01 H-3 3.280E-01 6.93E-01 Zr-95 7.115E-02 4.63E+01 Sn-117m 3.180E-01 6.71E-01 Sr-90 3.089E-02 2.01E+01 Pu-241 2.580E-01 5.45E-01 Sr-89 1.480E-02 9.63E+00 Ag-110m 2.140E-01 4.52E-01 Tc-99 4.180E-03 2.72E+00 Co-57 1.640E-01 3.46E-01 Pu-241 2.259E-03 1.05E+03 Ce-144 1.450E-01 3.06E-01 Am-241 1.388E-03 9.03E-01 Cs-137 1.150E-01 2.42E-01 Pu-238 5.025E-04 3.27E-01 Nb-94 8.600E-02 1.83E-01 Cm-243 3.580E-04 2.33E-01 Pu-238 8.500E-02 1.79E-01 Pu-239 3.150E-04 2.05E-01 Pu-239 6.300E-02 1.34E-01 Cm-242 7.207E-05 4.69E-02 Sr-90 4.100E-02 8.64E-02 Sr-89 1.300E-02 2.65E-02 Am-241 1.000E-02 2.21E-02 C-14 6.000E-03 1.17E-02 Cm-243 3.000E-03 7.20E-03 Pu-242 1.000E-03 2.13E-03 Cm-242 4.000E-04 8.98E-04 17
5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2015, to June 30, 2015, included 1.70E+04 gallons of neutralized wastewater. The wastewater contained 5.24E-01 lbs. of suspended solids and 1.05E+02 lbs. of dissolved solids. Scheduled chemical waste releases to the circulating water system from July 1, 2015, to December 31, 2015, included 1.08E+05 gallons of neutralized wastewater. The wastewater contained 1.57E+00 lbs. of suspended solids and 6.71E+02 lbs. 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, 2015, to June 30, 2015, included 2.09E+07 gallons of clarified effluent. The wastewater contained 2.26E+03 lbs. of suspended solids. Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2015, to December 31, 2015, included 1.75E+07 gallons of clarified effluent. The wastewater contained 3.26E+03 lbs. of suspended solids. Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2015, to June 30, 2015, included 4.27E+05 lbs. of sodium bisulfite solution (1.62E+05 lbs. sodium bisulfite), 4.48E+05 lbs. of Sodium Hypochlorite Solution (5.60E+04 lbs. sodium hypochlorite), and 4.15E+03 lbs. Acti-Brom 1338 (1.87E+03 lbs. sodium bromide). Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2015, to December 31, 2015, included 8.29E+05 lbs. of sodium bisulfite solution (3.15E+05 lbs. sodium bisulfite), 8.13E+05 lbs. Sodium Hypochlorite Solution (1.02E+05 lbs. sodium hypochlorite), 8.25E+03 lbs. Acti-Brom 1338 (3.71E+03 lbs. sodium bromide). 18
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 2015 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 358.2 358.2 358.2 527.3 542.5 542.5 Water Discharge [million gal/day]* 2 358.2 358.2 358.2 532.8 548.3 548.3 Average Cooling Water 1 37.3 42.2 40.2 44.5 47.5 53.8 Intake Temperature [F] 2 37.9 43.0 40.8 44.6 48.0 54.2 Average Cooling Water 1 69.6 69.6 72.2 64.6 66.1 72.6 Discharge Temperature [F] 2 69.0 69.3 70.8 62.8 65.1 71.2 Average Ambient Lake Temperature [F] 34.2 33.7 37.4 41.0 43.9 49.7 Table 6-1(continued) Circulating Water System Operation for 2015 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling* 1 542.5 542.5 542.5 563.1 504.8 520.0 Water Discharge [million gal/day]** 2 548.3 548.3 548.3 104.4 547.2 540.2 Average Cooling Water 1 54.2 56.5 55.7 55.3 44.5 41.0 Intake Temperature [F] 2 54.9 57.1 56.1 53.3 44.9 41.3 Average Cooling Water 1 72.8 75.6 74.9 75.2 63.7 59.9 Discharge Temperature [F] 2 71.7 73.7 72.2 56.3 61.4 58.8 Average Ambient Lake Temperature [F] 49.2 51.7 52.0 53.0 41.7 38.5
- For days with cooling water discharge flow.
**U1 outage circ water shut down 10/3/15 - 10/30/15 19
Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs Neither the ODCM, the RECM, nor the Environmental Manual (EM) were revised in 2015. 7.2 Interlaboratory Comparison Program ATI 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 2015. 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 attached final report for 2015, January - December 2015 from ATI Environmental Inc. 7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2015. 20
Part C RADIOLOGICAL ENVIRONMENTAL MONITORING
8.0 INTRODUCTION
The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To accomplish this, the REMP collects and analyzes air, water, milk, soil, vegetation (grasses, weeds, and crops), and fish samples for radionuclides and uses thermoluminescent dosimeters (TLDs) to determine the ambient radiation background. The analyses of the various environmental media provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure. 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. A subset of the PBNP REMP samples, consisting of air, soil and vegetation also fulfills 10 CFR 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. 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. 21
9.0 PROGRAM DESCRIPTION 9.1 Results Reporting 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 lower limit of detection (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. As mentioned above, radioactive decay is a statistical process which has an inherent uncertainty in the analytical result. No two measurements will yield exactly the same result. However, the results are considered equal if the results fall within a certain range based upon the statistical parameters involved in the process. The REMP analytical results are reported at the 95% confidence limit in which the true result may be two standard deviations above or below the reported result. This means that there is only a 5% chance of concluding that the identified radioactive atom is not there when it really is present in the sample. A false positive is an analytical result which statistically shows that the radionuclide is present in the sample when it really is not there. Typically, if the 95% 22
confidence interval for a positive does not include zero, the radionuclide is considered to be present. For example, the result is reported as 100 +/- 90. One hundred minus 90 yields a positive result and therefore may be considered to be present. However, this may be a false positive. If the radionuclide was not in the plant effluent, this result would fall into that category which 5% of the time it is falsely concluded that the radionuclide is present when in actuality it is not. This usually happens at low concentrations at or near the LLD where fluctuations in the background during the counting process skew the results to produce a positive result. 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 collects certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located. 23
9.5 Program Modifications In 2013, the placement of TLDs was reviewed with respect to the potential of trees and structures for interfering with the measurement of ambient radiation from natural background and of direct radiation from the plant and from airborne effluents. Two locations were found to have potential interferences. Two replacement TLD sites (E-16B and E-26B) were added in the 4th quarter of 2013. The new sites are in close proximity to E-16 and E-26 and were used concurrently with the old sites to provide data for comparisons between the old and new locations prior to deleting the old locations. These old sites were discontinued beginning in the second quarter of 2015. Based on the proximity of the new locations to the old locations, there was no need to revise the Environmental Manual maps. 24
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, -16B, -17,
-18, 20, -22, -23, -24,
-25, -26, -26B, -27, -28
-29, -30, 31, -32, -38,
-39,-41, -42,-43, -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-13 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, I-131 Gamma Isotopic Analysis Lake Water E-01, -05, -06, -33 Gross Beta, Sr-89/90, H-3 Monthly / Quarterly composite of monthly collections I-131 Monthly Gamma Isotopic Analysis Monthly Milk E-11, -40, -21 Sr-89, 90 Monthly I-131 Gamma Isotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)
-08, -20 I-131 Weekly (charcoal)
Gamma Isotopic Analysis Quarterly (on composite particulate filters) Soil E-01, -02, -03, -04, Gross Beta 2x/yr
-06, -08, -09, -20, Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, Gross Beta 2x/yr Gamma Isotopic Analysis ISFSI Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly 25
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 Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-11 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-15 Southwest Corner of Site E-16, 16B 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-18 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, -26B 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 nd rd E-28 TLD site on western most pole between the 2 and 3 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-41 NW corner of Woodside and Nuclear Rds (Kewaunee County) E-42 NW corner of Church and Division, East of Mishicot E-43 West side of Tannery Rd south of Elmwood (7th pole south of Elmwood) E-TC Transportation Control; Reserved for TLDs 26
Figure 9-1 PBNP REMP Sampling Sites 27
Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28
Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29
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 Soil 500-1000 grams Shoreline Sediment 500-1000 grams 30
Table 9-5 Deviations from Scheduled Sampling and Frequency During 2015 Sample Location Collection Reason for not conducting REMP Plans for Preventing Recurrence Type Date as required LW E-01, E-05, E-06, E-33 2/15/2015 Icy conditions at the shore prevented Nautral occurrence getting close enough to the lake to get a water sample. AP/I E-01 7/1/2015 No power to sampler Unknown cause Algae E-5, E-12 6/10/2015 No algae found growing in area Natural occurrence E-5 8/27/2015 E-5, E-12 10/7/2015 Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 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-11 Monthly E-21 Well Water E-10 Twice per year 31
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 2015. 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, I-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 the Annual Monitoring Report, are the naturally occurring radionuclides Ra-226, Bi-214, Pb-212, Tl-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 measurements are made on the solids remaining after evaporation of the unfiltered sample to dryness. Gamma isotopic analyses are performed using 1-liter liquid samples. Strontium is determined by chemical separation and beta counting. 9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours 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 cartridges for radioiodine are counted as soon as possible so the I-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for I-131 by 32
counting them all at the same time to achieve a lower LLD. If a positive result is obtained, each cartridge 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. No special vegetation samples were obtained for C-14 analyses in 2015. 9.7.6 Environmental Radiation Exposure The 2015 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 was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. An evaluation of the response difference between the two types of TLD in 2001 demonstrated that the TLD cards produced a 14% higher response than the LiF chips (2011 AMR, Table 9-7, p. 36). The reported field exposure is the arithmetic average of the measured exposure values at each location minus the exposure transportation control TLD (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. 33
9.7.7 ISFSI Ambient Radiation Exposure The ISFSI fence TLDs are part of the 10CFR72.44 monitoring and are not considered part of the REMP. However, 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. These results are used as part of the 40CFR190 compliance demonstration. 10.0 RESULTS 10.1 Summary of 2015 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2015, through December 31, 2015, 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, averages and high values, in Table 10-1 which contain 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 +/- its 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 tech spec required 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 listing of all the individual results obtained from the contracted analytical laboratory and the laboratorys radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in the Appendix. In Table 10-1 no results are reported as less than LLD (<LLD). All results are reported to Point Beach by the contracted radioanalytical laboratory "as measured" whether positive or negative (see Section 9-1). Based on these results, a radionuclide is considered detected if it meets the criterion that the measured value minus its 2 counting error is greater than zero (x-2 >0). An "ND" entry in Table 10-1 means that for this radionuclide the criterion was not satisfied for any of the measurements. If one analysis fulfilled the criterion, then all of the reported results, both positive and negative, were used in calculating the average shown in Table 10-1. 34
The method of determining averages based on "as measured" results follows the recommendations 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 520/1 012 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." In addition to the required radionuclides for each medium analyzed, Table 10-1 also has an additional radionuclide listed known to originate with nuclear power plants. This radionuclide is either Co-60, Ru-103, or any other radionuclide which has the lowest LLD based on the analytical parameters needed to meet the LLDs required for radionuclides specified for the medium being analyzed. The radionuclide is identified by parentheses. During the analyses for those radionuclides specifically required to be identified, naturally occurring radionuclides such as Ra-226, Be-7 and K-40 are detected in many samples. Their concentrations are presented in Table 10-1 for a comparison to those radionuclides for which specific analyses are required by the regulations. There are no regulatory required LLDs for naturally occurring radionuclides. Finally, Point Beach reports the results for soil analyses. There is no regulatory requirement for soil analyses in standard RETS (NUREG-0472 and NUREG-1301). Point Beach includes soil analyses in the REMP to be able to compare current results to the historical record. Additional sampling was initiated in 2015. Approximately 60% of the 1260 acres (FSAR 2.1) comprising the NextERA Point Beach site is licensed to farmers who use the land to grow various crops. These crops consist of corn, hay, alfalfa, and soy beans and appear to be for cattle feed. Ten samples were obtained from the nine separate plots and gamma scanned for radionuclides representative of Point Beach effluents and for naturally occurring radionuclides. Results are reported in Table 10-2. Table 10-3 contains the ISFSI fence TLD results. 35
Table 10-1 Summary of Radiological Environmental Monitoring Results for 2015 Average +/- 1 Std. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 126 1 mrem 1.18 +/- 0.20 1.66 +/- 0.06 mR/7days Control (E-20) 4 1 mrem 1.20 +/- 0.15 1.30 +/- 0.15 mR/7days Air Gross Beta 259 0.01 0.025 +/- 0.010 0.057 +/- 0.005 pCi/m3 Control (E-20) Gross beta 52 0.01 0.024 +/- 0.009 0.057 +/- 0.005 pCi/m3 I-131 259 0.030 (0.07) ND - pCi/m3 Control (E-20) I-131 52 0.030 (0.07) ND - pCi/m3 Cs-134 20 0.01(0.05) ND - pCi/m3 Control (E-20) Cs-134 4 0.01(0.05) ND - pCi/m3 Cs-137 20 0.01(0.06) 0.0000 +/- 0.0003 0.0007 +/- 0.0006 pCi/m3 Control (E-20) Cs-137 4 0.01(0.06) 0.0000 +/- 0.0003 0.0004 +/- 0.0003 pCi/m3 Other emitters (Co-60) 20 0.1 0.0000 +/- 0.0004 0.0006 +/- 0.0005 pCi/m3 Control (E-20) Other (Co-60) 4 0.1 ND ND pCi/m3 Natural Be-7 20 - 0.064 +/- 0.012 0.084 +/- 0.017 pCi/m3 Control (E-20) Natural Be-7 4 - 0.065 +/- 0.005 0.071 +/- 0.013 pCi/m3 Milk Sr-89 36 5 ND - pCi/L Sr-90 36 1 0.5 +/- 0.3 1.3 +/- 0.4 pCi/L I-131 36 0.5 ND - pCi/L Cs-134 36 5 (15) 0.0 +/- 0.8 2.1 +/- 1.7 pCi/L Cs-137 36 5 (18) 0.6 +/- 0.9 2.3 +/- 2.1 pCi/L Ba-La-140 36 5 (15) -0.8 +/- 1.9 2.7 +/- 1.2 pCi/L Other gamma emitters(Co-60) 36 15 0.4 +/- 1.1 3.0 +/- 1.9 pCi/L Natural K-40 36 - 1409 +/- 60 1496 +/- 106 pCi/L Well Water Gross beta 4 4 1.6 +/- 1.3 2.9 +/- 1.7 pCi/L H-3 4 200 (3000) 15.1 +/- 78.1 103.9 +/- 99.7 pCi/L Sr-89 4 5(10) ND - pCi/L Sr-90 4 1 (2) 0.2 +/- 0.5 0.9 +/- 0.3 pCi/L I-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 10(15) ND - pCi/L Co-60 4 10(15) ND - pCi/L Zn-65 4 30 ND - pCi/L Zr-Nb-95 4 15 ND - pCi/L Cs-134 4 10(15) ND - pCi/L Cs-137 4 10(18) ND - pCi/L Ba-La-140 4 15 0.8 +/- 1.9 3.1 +/- 1.7 pCi/L Other gamma emitters(Ru-103) 4 30 ND - pCi/L Algae Gross beta 1 0.25 3.04 +/- 0.13 3.04 +/- 0.13 pCi/g Co-58 1 0.25 ND - pCi/g Co-60 1 0.25 ND - pCi/g Cs-134 1 0.25 ND - pCi/g Cs-137 1 0.25 0.012 +/- 0.007 0.012 +/- 0.007 pCi/g Natural Be-7 1 - 0.85 +/- 0.09 0.85 +/- 0.09 pCi/g Natural K-40 1 - 2.26 +/- 0.16 2.26 +/- 0.16 pCi/g 36
Table 10-1 (continued) Summary of Radiological Environmental Monitoring Results for 2015 Average +/- 1 Std. Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 44 4 1.6 +/- 1.0 4.4 +/- 1.1 pCi/L I-131 44 0.5 (2) ND - pCi/L Mn-54 44 10 (15) 0.1 +/- 0.7 1.3 +/- 1.1 pCi/L Fe-59 44 30 -0.6 +/- 2.0 4.4 +/- 4.2 pCi/L Co-58 44 10(15) 0.0 +/- 1.0 2.6 +/- 2.0 pCi/L Co-60 44 10(15) ND - pCi/L Zn-65 44 30 -0.5 +/- 2.5 3.8 +/- 2.7 pCi/L Zr-Nb-95 44 15 -0.1 +/- 1.1 2.4 +/- 2.0 pCi/L Cs-134 44 10 (15) -0.1 +/- 1.1 3.1 +/- 2.0 pCi/L Cs-137 44 10 (18) 0.2 +/- 0.6 2.3 +/- 2.1 pCi/L Ba-La-140 44 15 -0.8 +/- 2.2 2.9 +/- 1.5 pCi/L Other gamma (Ru-103) 44 30 -0.2 +/- 0.9 1.9 +/- 1.8 pCi/L Sr-89 16 5(10) ND - pCi/L Sr-90 16 1 (2) 0.28 +/- 0.15 0.71 +/- 0.38 pCi/L H-3 16 200 (3000) 97 +/- 116 452 +/- 94 pCi/L Fish Gross beta 14 0.5 2.81 +/- 0.56 3.62 +/- 0.08 pCi/g Mn-54 14 0.13 0.002 +/- 0.007 0.013 +/- 0.009 pCi/g Fe-59 14 0.26 0.006 +/- 0.027 0.056 +/- 0.036 pCi/g Co-58 14 0.13 -0.004 +/- 0.010 0.010 +/- 0.008 pCi/g Co-60 14 0.13 0.004 +/- 0.009 0.030 +/- 0.021 pCi/g Zn-65 14 0.26 ND - pCi/g Cs-134 14 0.13 ND - pCi/g Cs-137 14 0.15 0.029 +/- 0.012 0.054 +/- 0.020 pCi/g Other gamma (Ru-103) 14 0.5 0.000 +/- 0.011 0.020 +/- 0.009 pCi/g Natural K-40 14 - 2.42 +/- 0.57 3.25 +/- 0.42 pCi/g Gross beta 10 2 8.28 +/- 1.30 11.20 +/- 0.92 pCi/g Cs-134 10 0.18 ND - pCi/g Cs-137 10 0.15 0.019 +/- 0.008 0.029 +/- 0.016 pCi/g Natural Be-7 10 - ND - pCi/g Shoreline Natural K-40 10 - 5.75 +/- 1.53 8.69 +/- 0.50 pCi/g Sediment Natural Ra-226 10 - 0.38 +/- 0.07 0.54 +/- 0.17 pCi/g Soil Gross beta 16 2 22.62 +/- 6.24 31.19 +/- 1.22 pCi/g Cs-134 16 0.15 ND pCi/g Cs-137 16 0.15 0.154 +/- 0.077 0.315 +/- 0.036 pCi/g Natural Be-7 16 - 0.053 +/- 0.090 0.190 +/- 0.070 pCi/g Natural K-40 16 - 14.52 +/- 4.04 18.99 +/- 0.89 pCi/g Natural Ra-226 16 - 0.86 +/- 0.36 1.37 +/- 0.32 pCi/g Vegetation Gross beta 24 0.25 6.81 +/- 1.94 13.74 +/- 0.33 pCi/g I-131 24 0.06 0.000 +/- 0.008 0.016 +/- 0.010 pCi/g Cs-134 24 0.06 ND - pCi/g Cs-137 24 0.08 0.004 +/- 0.012 0.052 +/- 0.016 pCi/g Other gamma emitters (Co-60) 24 0.25 -0.005 +/- 0.005 0.011 +/- 0.008 pCi/g Natural Be-7 24 - 1.59 +/- 0.80 2.97 +/- 0.25 pCi/g Natural K-40 24 - 5.42 +/- 1.16 7.55 +/- 0.53 pCi/g (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity. (b) ND indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero or <MDA. 37
Table 10-2 Feed Crops Grown on Point Beach Land Average Max Number pCi/g 2 pCi/g 2 Gross Beta 10 4.94 +/- 3.76 8.12 +/- 0.27 Be-7 10 1.66 +/- 4.08 6.21 +/- 0.42 K-40 10 4.05 +/- 4.22 6.45 +/- 0.39 Mn-54 10 ND - Fe-59 10 ND - Co-58 10 ND - Co-60 10 0.000 +/- 0.009 0.006 +/- 0.005 Zn-65 10 ND - Zr-Nb-95 10 ND - Cs-134 10 ND - Cs-137 10 0.003 +/- 0.007 0.009 +/- 0.006 Ba-La-140 10 ND - ND = Not detected Table 10-3 Average ISFSI Fence TLD Results for 2015 Fence Location Average +/- Standard Deviation Units North 2.31 +/- 0.25 mR/7 days East 3.24 +/- 0.19 mR/7 days South 1.17 +/- 0.05 mR/7 days West 4.36 +/- 0.16 mR/7 days 38
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 indicator TLD is 1.18 +/- 0.20 mR/7-days compared to 1.20 +/- 0.15 mR/7-days at the background location. These two values are not significantly different from each other. Neither are the indicator TLD values significantly different from those observed from 2001 through 2014 for the same type of TLD (tabulated below in Table 11-1). Prior to third quarter of 2001 TLD LiF chips were used versus the current TLD cards, see Section 9.7.6 for additional information. The response difference between the two types of TLDs is evident in Table 11-1. Prior to 2001 all of the annual averages are <1 mrem/7-days. Beginning in 2001, all are >1 mrem/7-days. Table 11-1 Average Indicator TLD Results from 1993 - 2015 Year Average mR/7-days +/- St. Dev* 1993 0.82 +/- 0.15 1994 0.90 +/- 0.12 1995 0.87 +/- 0.13 1996 0.85 +/- 0.12 1997 0.87 +/- 0.11 1998 0.79 +/- 0.13 1999 0.79 +/- 0.21 2000 0.91 +/- 0.15 2001 1.06 +/- 0.19 2002 1.17 +/- 0.21 2003 1.10 +/- 0.20 2004 1.10 +/- 0.22 2005 1.04 +/- 0.21 2006 1.14 +/- 0.21 2007 1.08 +/- 0.20 2008 1.05 +/- 0.17 2009 1.08 +/- 0.17 2010 1.11 +/- 0.15 2011 1.14 +/- 0.25 2012 1.17 +/- 0.17 2013 1.14 +/- 0.20 2014 1.07 +/- 0.19 2015 1.18 +/- 0.20
*St. Dev = Standard Deviation No fuel was added to the ISFSI during 2015. However, four empty dry fuel storage units were stored at the ISFSI for use in 2016. The west fence TLDs continue to record higher exposures followed by the east, north, and south fence locations (Table 11-2). This sequence has been observed for the last five years.
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There is no significant change in the exposure on the TLD monitoring locations around the ISFSI (Table 11-3). The results at E-03 and E-31 (W of the ISFSI) and E-32 (SW of the ISFSI) are similar to previous years (1.36, 1.24, and 1.40, respectively) and continue to be higher than E-30 (1.07) on the east side and closest to the ISFSI. E-03, about equidistant between the ISFSI and the site boundary location, E-31, continues to be higher than the site boundary location. (See Figs. 9-1 and 9-2 for locations). Table 11-2 Average ISFSI Fence TLD Results (mR/7 days) TLD FENCE LOCATION YEAR 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 2008 2.64 2.37 1.36 5.36 2009 2.36 2.35 1.20 4.63 2010 2.64 3.02 1.41 5.05 2011 2.44 2.62 1.31 4.75 2012 2.59 3.27 1.40 4.92 2013 2.57 3.66 1.15 4.28 2014 2.45 3.35 1.14 4.24 2015 2.31 3.24 1.17 4.36 Although the mR/7-day results for the three TLD locations nearest the site boundary (E-03 1.36 +/- 0.31; E-31, 1.24 +/- 0.30; E-32, 1.40 +/- 0.38) are higher than at the background site E-20 (1.20 +/- 0.29), they are comparable at the 95% confidence level, indicating a small, but not significant, increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI. Further data supporting this conclusion is the comparison of the TLD results at selected locations around the ISFSI before and after the storage of spent fuel at the ISFSI (Figure 11-1). As stated in Section 9.7.6, the TLD values increased by about 14% in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of the 2001 to calcium sulfate impregnated TLD cards. After that initial change, the measured radiation exposure, as measured by the TLD cards, has remained fairly constant with a slight increase with the addition of stored fuel at the ISFSI. Each year the variations in the TLD results appear to move in 40
concert with each other and with the background site, E-20, which is 17 miles south west of the ISFSI. Comparing the ISFSI TLD results to results from surrounding REMP indicator and background TLDs reveals minimal impact of the ISFSI on the surrounding Figure 11-1 ISFSI AREA TLD RESULTS 1995 - 2015 ISFSI AREA TLD RESULTS 2 E-03 mR/7 days 1.5 E-28 1 E-29 0.5 E-30 0 E-31 1990 1995 2000 2005 2010 2015 2020 E-32 YEAR E-20 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 1.05 1.18 0.97 1.05 2008 1.33 0.75 0.81 1.00 1.12 1.03 1.00 2009 1.39 0.82 0.85 1.01 1.17 1.05 1.09 2010 1.41 0.84 0.89 1.07 1.21 1.24 1.10 2011 1.46 0.85 0.90 1.06 1.25 1.32 1.12 2012 1.54 0.87 0.91 1.10 1.21 1.39 1.14 2013 1.23 0.87 0.77 1.00 1.40 1.38 1.22 2014 1.23 0.77 0.79 0.97 1.25 1.25 1.15 2015 1.36 0.86 0.78 1.07 1.24 1.40 1.20
*Pre-Operational data are the averages of the years 1992 through 3rd 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.
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radiation levels (Figure 11-2). As previously discussed, the small increase is more related to the switch from the LiF chips to the calcium sulfate impregnated Teflon TLD cards as evidenced by the synchronicity with E-20, the background site. LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards in the third quarter of 2001 resulting in a higher measured background values. Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 11.2 Milk Naturally occurring potassium-40 (1409 +/- 60 pCi/l) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 2000 times higher than the only potential plant related radionuclide, Sr-90 (0.6 +/- 0.3 pCi/l), detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. There were several (3 of 36) positive Ba-La-140 results. However, PBNP did not discharge any Ba-La-140 during the years 2013 - 2015. Given the short half-life of Ba-La-140 (12.8 days), it is unlikely that these results represent a carry- over from previous years. Because the highest Ba-La-140 concentration is very near the detection limit, the positive values are considered to be false positives attributable to the statistical nature of radioactive decay. Some low positive Cs-134 (2 of 36) and Cs-137 (6 of 36) results were obtained. No airborne Cs-134 or Cs-137 was discharged from PBNP in 2015. The Cs-134 results are considered to be false positives which occur due to the random fluctuations in background in low activity samples. The Cs-137 values also are near the detection limit and therefore may be false positive. Another possibility is residual Cs-137 recycling through the environment from the 1960s atmospheric weapons tests and events such as Chernobyl and Fukushima. Several (3 of 36) positive Co-60 values were obtained. The only airborne Co-60 release occurred in October via the Unit 2 containment hatch. Two of the small positive results occurred prior to October. The small positive Co-60 result is from a sample obtained within the time frame of one Co-60 release. However, it is upwind of the site. Based on the sample locations and on the low Co-60 concentration values, all of the Co-60 results are considered to be false positives. No I-131 was discharged and no positive I-131 results were obtained. 42
Although the average Sr-90 concentrations have not changed much over the last nineteen (19) years, 1.2 +/- 0.5 pCi/L in 1997 to 0.5 +/- 0.3 pCi/L in 2015, a graph of the annual averages displays a logarithmic decrease over time (Figure 11-3). The annual averages are from the monthly Sr-90 measurements from three different dairies (Fig. 9-1). The only dairy that has been in the monitoring program over the entire 1997 - 2015 timespan under consideration is located at site E-21. It is located south of the plant. The other two, E-40 and E-11, are replacements for dairies which had dropped out of the program at various times during this time interval. The replacements were chosen to maintain, to the extent possible, the former sampling sites west and north of Point Beach. Over the years1997 to 2015, the Sr-90 in milk decreases with a half-life of 15.0 years. Because the radiological half-life is 28.6 years, the shorter removal half-life indicates that environmental factors as well as radioactive decay are working to decrease the concentration of Sr-90 in milk. The calculated physical removal half-life is 31.7 years. Figure 11-3 Sr-90 Concentration in Milk (1997 - 2015) The major Sr-90 input to the environment was from fallout from atmospheric weapons testing during the early 1960s with minor inputs during the 50s, 70s and later contributions from the Chernobyl accident in the late 1980s and from Fukushima in 2011. The Sr-90 in milk persists due to its 28.6 year half-life and to cycling in the biosphere. With little or no atmospheric input to the environment, the mode of entry into cattle feed must be root uptake by forage crops and transfer into the milk. Therefore, the shorter observed half-life is indicative of Sr-90 removal from the soil by processes other than radioactive decay. Over the time period of this graph (1997 - 2015), PBNP discharged airborne Sr-90 only in 3 years: 1998, 2.4E-08 Ci; 2004, 3.2E-08 Ci; and 2011, 1.6 E-08 Ci. These low discharges do not appear to impact the decreasing concentrations as they continue to decrease over time. It is concluded that the milk data for 2015 show no radiological effects of the plant operation. 43
11.3 Air The average annual gross beta concentrations (plus/minus the two-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.025 +/- 0.019 pCi/m3 and 0.024 +/- 0.019 pCi/m3, respectively, and are similar to levels observed from 1993 through 2014 (Figure 11-4). The 2015 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-5). This is a repeat of the patterns seen in 2006 - 2014. As in 2014, there is a slight peak in late summer followed by some lower values in October and early November. The cause for this variation is not known. However, the control and indicators are moving in concert. Therefore, a plant effect can be ruled out. Similarly, there is a decreasing trend in January before returning to the January highs in February. Again, the indicator and background sites move in concert ruling out a plant effect. Figure 11-4 Annual Average Air Gross (1993 - 2015) Figure 11-5 2015 Airborne Gross Beta 44
No I-131 was detected during 2015. In 2005, the new method of evaluating airborne I-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 is detected, each sample cartridge is counted individually. With no detectable I-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 0.005 to 0.0.016 pCi/m3. 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, in the range of 0.001 to 0.003 pCi/m3. At each sampling location, the particulate filters are composited quarterly and analyzed for Cs-134, Cs-137 and any other (Co-60) detectable gamma emitters. As summarized in Table 10-1, low, positive results (5 of 24) for gamma emitters attributable to Point Beach were detected. By contrast, naturally occurring Beryllium-7 was found in all of the quarterly composites at concentrations an order of magnitude higher. Be-7 (T1/2 = 53.3 days) is produced in the atmosphere by the interaction of cosmic rays with oxygen and nitrogen nuclei. Its half-life is long enough to allow for it to be detected in the quarterly composited filters. Based on location and results at or below the MDC, the Co-60 and Cs-137 results are concluded to be false positives. In summary, the 2015 air gamma data from quarterly composites do not demonstrate an environmental impact from the operation of PBNP. 11.4 Lake Water For the 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. Lake Michigan water samples are collected north (E-33 and E-05) and south (E-01 and E-06) of PBNP (see Figure 9-1). There were sixteen, slightly positive indications of gamma emitters during 2015, nine north of the plant and seven to the south. Although the major current is from north to south, these locations may be upstream or downstream of the plant discharge depending upon wind stress which can reverse currents. A comparison of when the positive results were obtained to when discharges occurred suggests that the small, positive results are false positives. For example, positive results were obtained for Ru-102, Cs-134, and Ba-La-140 which were not in the 2015 effluents. Similarly, positive results were obtained for Mn-54 and Cs-137 in months when these radionuclides were not discharged. Also, Zr-95 and Nb-95 were identified in months they were not discharged but not in the months they were in the PBNP effluents. Finally, the measured concentrations are in the range of 2 - 4 pCi/l which convert to 2 - 4E-09 Ci/cc or 10 - 100 times greater than the typical discharge concentrations of E-14 to E-11 Ci/cc. Based on the further dilution which occurs in the lake after discharge, it is highly unlikely that observed positive 45
results are real. Therefore, based on these comparisons, it is concluded that the sixteen positive results are false positives and not indications of PBNP effluents in Lake Michigan during 2015. A false positive is concluding an isotope is present when it isnt. False positives occur most often at the detection limit when the random fluctuations of the background result in lower than normal background activity. The result is a higher net count and hence falsely concluding an isotope is present when it isnt because the value is statistically above zero. In conclusion, based on the results of the gamma scans of Lake Michigan water, there is no measureable impact on the lake from PBNP discharges. Aliquots of the monthly samples are composited quarterly and analyzed for Sr-89/90 and for tritium. Small amounts of Sr-90 were detected. As in 2012 - 2014, Point Beach did not discharge any Sr-90 in 2015. There were five lake water composites in which the Sr-90 concentrations were slightly positive. They occurred north and south of the plant. Sr-90 has a 28.6 year half-life and, like Cs-137, is a remnant of atmospheric weapons testing in the 50s and 60s. Therefore, positive Sr-90 concentrations are indicative of fallout being recycled in Lake Michigan. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. It also was produced by atmospheric weapons testing. However, due to its mobility, any H-3 now found in Lake Michigan at the concentrations typically found in monitoring programs cannot be from that time period. It is the result of power plant discharges. Point Beach discharges on the order of 700 - 800 Ci per year. Eight of the sixteen quarterly composites had positive H-3 indications. Three were south and five were north of the PBNP discharge. The highest, 452 +/- 94 pCi/l, was from a fourth quarter composite sample about 1.6 miles north (E-05) of Point Beach with a lower value of 237 +/- 84 pCi/l from a location (E-33) about 4.5 miles north of PBNP near the shut-down Kewaunee plant. Based on this result, the individual month samples from the two locations were analyzed for H-3. The highest concentrations occurred in the December 10th samples, 1336 +/- 139 pCi/l closest to PBNP and a lower value of 464 +/- 111 pCi/l near the Kewaunee plant. (Both results are lower than the EPA drinking water standard of 20,000 pCi/l) There were no positive H-3 results for the October or November samples north of PBNP. As a further check the December 10th samples from the two locations 0.6 (E-01) and 6 miles (E-06) south of PBNP also were analyzed for H-3 and no positive results were obtained. Because Kewaunee had not discharged any H-3 in the month preceding the December 10th samples and PBNP had seven discharges containing H-3 in the six days prior to the December 10th sample, it is concluded that the observed H-3 results were due to PBNP effluents. The occurrence and analyses were documented in the PBNP CAP. 11.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Samples are obtained at Two Creeks Park and at the PBNP discharge (locations 5 and 12 in Figure 9-1). In order to 46
allow the algae time to grow, typically no samples are collected until June and then again August and October. This is done to ensure that there is enough new growth to provide a sample. In 2015 only one algae sample was obtained and that was on August 27th near the PBNP discharge. On the other occasions the algae either was not present or located in spot which was visible but not accessible. Positive results were obtained for the naturally occurring radionuclides Be-7 and K-40. No Co-58, Co-60, or Cs-134 was detected. Cs-137 was detected at 0.012 +/- 0.007 pCi/g. This is roughly half the highest concentration (0.023 +/- 0.009 pCi/g) found at the same location in in 2014. Co-58 and Co-60 which were discharged in the seven months preceding the August sample were not detected. As previously discussed, fallout Cs-137 recycles in Lake Michigan and is attached to particles. The positive results are attributable to the recycling of bomb fallout from weapons testing in the '50s, 60's and other nuclear events such as Chernobyl and Fukushima. There also may be a small contribution, but unknown, amount from past nuclear plant discharges. Because PBNP did not discharge any Cs-137 in 2015 prior the August sample, it is concluded that the positive result is indicative the recycling of fallout and other previously discharged Cs-137 in Lake Michigan. 11.6 Fish Fourteen fish were analyzed in 2015. All 14 fish had detectable amounts of Cs-137 with results ranging from 0.012 +/- 0.010 to 0.054 +/- 0.020 pCi/g. The Cs-137 is attributable to the recycling of this radionuclide in Lake Michigan. The majority of Cs-137 entered Lake Michigan as fallout from atmospheric weapons testing in the
'50s and '60s with lesser amounts from events at Chernobyl and Fukushima.
Fish analyses also yielded small amounts of Mn-54 (0.013 +/- 0.009), Fe-59 (0.056 +/- 0.036), Co-58 (0.010+/- 0.008), Co-60 (0.030 +/- 0.021), and Ru-103 (0.020 +/- 0.009) pCi/g. These results could be false positives. For example, Fe-59 was found is a fish from 3/15/15. However, no prior Fe-59 discharge occurred in 2015 and in 2014, Fe-59 was released only in April and May. Based on the May Fe-59 discharge concentration of 1.58E-11Ci/cc or 0.0000158 pCi/cc (Permit 14-00049L) and assuming no decay or further dilution in the lake, an iron bioaccumulation factor of 100 for freshwater fish (RG 1.109, Rev.1, Table A-1) yields a fish concentration of 0.00158 pCi/g in March of 2015. If radioactive decay were considered, a decay of about 7 half-lives or roughly 300 days would have to be factored in making the fish concentration even lower by a factor of about 1/128th of the original. This is below the highest measured Fe-59 concentration of 0.056 pCi/g. Therefore, it is concluded that the low measured Fe-59 concentrations in fish are false positives. The same evaluation holds for Co-58 and Co-60. Co-58 and Co-60 in December release permit 14-000111L had concentrations of 6.73E-11Ci/cc (6.7E-05 pCi/cc) and 5.75E-12 Ci/cc (5.75E-06 pCi/cc), respectively. Appling a bioconcentration factor of 50 yields fish concentrations of 3.37E-04 and 2.88 E-04 pCi/g, respectively, before decay and further dilution in Lake Michigan. The first positive Co-60 in a fish (0.013 pCi/g) was from a sample from 1/18/2015. This is much higher than predicted by RG 1.109. Also, no Co-58 was found in the same fish and it was discharged in a higher concentration than Co-60. Therefore, PBNP discharges cant be the cause of the identified Co-58 and Co-60. The conclusion is that the low 47
cobalt concentrations are false positives. Similarly, it is concluded that the positive result for Ru-103 is a false positive because no Ru-103 was released in either 2014 (2014 AMR Table 2-3) or 2015 (Table 2-3). The highest radionuclide concentration in fish is naturally occurring K-40 with an average concentration of 2.42E+00 pCi/g. Based on these results, it is concluded that there is no impact of PBNP discharges on Lake Michigan fish. 11.7 Well Water Three plant related radionuclides were detected in main plant well water (E-10) during 2015, Ba-La-140 and Sr-90. The April 15th Ba-La-140 result is considered to be a false positive because of its short half-life and the fact that none has been discharged in 2014 or in 2015 prior to the sampling date. Also the Sr-90 is considered to be a false positive because its concentration of 0.9 +/- 0.3 pCi/l is much higher than the gross beta result of 0.2 +/- 0.9 pCi/l. Had the Sr-90 result been real, the gross beta should have been comparable given the greater efficiency of counting the Sr-90 daughter product, Y-90, which would have been present in the gross beta measurement. Therefore, it is concluded that there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP. 11.8 Soil Cs-137 is present in the soils throughout North America and the world resulting from the atmospheric nuclear weapons testing in the 1950s, 1960s, and 1970s and from the 1986 Chernobyl accident, and more recently, from the Fukushima event. Soil is an integrating sample media, in that it is a better indicator of long term buildup of Cs-137 as opposed to current deposition for local sources. In addition to erosion and radioactive decay, human activities can modify the soil Cs-137 concentrations. Evidence for the latter are the typically higher Cs-137 concentrations found at E-06, 0.315 +/- 0.036 pCi/g in May and 0.28 +/- 0.033 in October as compared to other locations. At E-06, trees growing and incorporating Cs-137 during the time of atmospheric fallout are now being burned in camp fires thereby releasing the incorporated Cs-137 to the surrounding area. In 2015, as in 2014, Cs-137 was found in all soils analyzed with the highest values in May and in October both being at E-06, Point Beach State Park. There is no indication of a plant effect based on the comparison of indicator and background results. By comparison to naturally occurring radionuclides, the Cs-137 concentrations continue to be present in soil samples at well below levels of naturally occurring K-40 (5.38 +/- 0.37 to 18.99 +/- 0.89 pCi/g). In addition to K-40, other naturally occurring radionuclides such as Be-7 and Ra-226 were found in the soil. There is no evidence of Point Beach effluent in the soil samples. 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-137. Eight of the ten samples have Cs-137 concentrations statistically different from zero. The shoreline sediment Cs-137 48
concentrations continue to be about one-tenth of that found in soils. This is expected because Cs-137 in the geological media is bound to fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-137. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about several hundred times higher than the Cs-137 that is attached to particle surfaces. Therefore, it is not surprising that Cs-137 is present at concentrations 1% or less of the naturally occurring concentrations of K-40. The absence of any PBNP effluent nuclides, such as Co-58/60, other than Cs-137 indicates that the most likely source of the observed Cs-137 is the cycling of radionuclide in the Lake Michigan environment and not current PBNP discharges. As with soil, the naturally occurring radionuclides such as K-40, and Ra-226 are found in the shoreline sediment samples. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation. 11.10 Vegetation The REMP collects two general types of vegetation within the site. The first consists of general vegetation, non-cultivated plants which would be consumed by grazing cattle. The second consists of crops grown on site acreage licensed to farmers, about half the sites 1400 acres, for growing feed crops for cattle. Ten samples of cultivated crops (corn, hay, alfalfa, and soybeans) grown on this acreage were obtained for analyses. The naturally occurring radionuclides Be-7 and K-40 were found in all of the general vegetation samples. 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. (Spallation is a process whereby a cosmic ray breaks up the target atom's nucleus producing a radionuclide of lower mass.) Be-7 concentrations ranged from 0.18 +/- 0.08 to 2.97 +/- 0.25 pCi/g. The average concentrations increased from May (0.94 +/- 1.10 pCi/g) than in July (1.28 +/- 0.42) and October (2.54 +/- 0.78). This is consistent with the known temporal variability in Be-7 concentrations in air near the earth's surface and the gradual build-up of fallout on the vegetation over time. In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. By not being dependent upon seasonal atmospheric variations and plant surface to capture deposition, the K-40 concentrations from root uptake are more uniform with averages of 4.97, 5.60, and 5.71 in May, July, and October, respectively. Cs-137 can be present in vegetation via both pathways. Fresh Cs-137 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. This fallout Cs-137 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-137 in Wood Ash, Results of a Nationwide Survey," 5th Ann. Nat. Biofuels Conf., 10/21/1992). 49
In 2015 only four of the twenty-four vegetation samples had a positive indication for Cs-137 and only E-06 (0.052 +/- 0.016) was significantly above background. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-137. This occurrence is attributed to the above described mechanism. The only airborne Cs-137 discharged by PBNP occurred in October 2015. Therefore, it is unlikely that the four positive Cs-137 values resulted from PBNP releases. The only other radionuclides having positive indication were Co-60 and I-131. Although Co-58 airborne releases occurred prior to the July vegetation sample, no Co-60 was released. If the Co-60 were from PBNP effluent, Co-58 also should have been detected. No airborne I-131 releases occurred during 2015. Therefore, the I-131 cant be from PBNP. Based on these considerations, the Co-60 and I-131 results, it is concluded that these results are false positives. Based on the 2015 general vegetation sampling results, it is concluded that there is little or no effect from PBNP effluents. Similar results and conclusions are reached from the analytical results for the crops grown on site acreage. Naturally occurring Be-7 and K-40 are found in all crops. As in general vegetation, K-40 is incorporated from the soil whereas Be-7 is from atmospheric deposition. Only two crop samples had slightly positive results, one for Co-60 and the other for Cs-137. Although Co-58 airborne releases occurred prior to the September crop sample, no Co-60 was released. Therefore, the Co-60 is concluded to be a false positive. Similarly, in 2015 no airborne Cs-137 occurred in PBNP effluent prior to the September sample. The Cs-137 could be an indication of fallout from weapons testing, Chernobyl, and Fukushiima. However, because in both cases the results were below the minimum detectable concentration, the results are determined to be false positives. Therefore, based on the analytical results from crops grown on site, there is little or no evidence of PBNP effluents 11.12 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 2015. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. The nearest dairy lies in the SSE sector and it is one of the Point Beach REMP milk sampling sites. This dairy leases land in the S and SSE sectors at the PBNP site boundary for growing feed corn. Also, the highest /Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. Therefore, dose calculations to the maximum exposed hypothetical individual, assumed to reside at the site boundary in the S sector, continues to be conservative for the purpose of calculating doses via the grass-cow-milk and the other ingestion pathways. 50
11.13 Long Term TLD Trending To put the 2015 REMP TLD results in perspective, it is instructive to look at long term trends. The following examines the TLD results from 1971 to 2015. The ANSI standard (ANSI/HPS N13.37-2014 Environmental Dosimetry) states that the data from early vintage dosimetry systems (c. 1970 - 1990) should not be considered comparable to current dosimetry systems in establishing a baseline for environmental TLD results. These problems are evident from the review of our early data as discussed below. The pre-operational data, 1968 - 1970, are not included. The pre-operational ambient radiation monitoring sites were E-01 (the met tower area) through E-04 (the north boundary). They were monitored using TLDs and ionization chambers. E-04 was used as a background location until E-08 (see Figure 9-1) was added for the operational REMP in 1971. Prior to 1975, a control TLD stored in a lead pig was used for a comparison to those placed in the field. In the pre-operational data, the control TLD could be equal to or higher than the field results and both the field and control TLD results appear erratic compared to the ion-chamber results. Also, the reported TLD results do not have transportation exposures from New Mexico to Wisconsin subtracted. Therefore, only the TLD results beginning in 1971, with the transportation caveat, are used in this analysis of long-term trends. The trend at E-01(Figure 11-6) shows slowly decreasing tread from 1971 to 1979. This is may be an artifact. The cause is not known. As previously mentioned, no transportation controls were used until the 4th quarter of 1975 so no transport dose corrections were made prior to that quarter. There is a small increase in 1980 when the current contracted REMP lab began. A slowly decreasing exposure rate occurs from 1980 - 1992 except for the 1984 - 1988 time segments. The erratic results from 1984 - 1988 was traced to a faulty connection in the TLD reader. Figure 11-6 E-01 Results 1971 - 2015 The TLD package from 1980 to 2001 consisted of three LiF chips sealed in a black plastic bag. The magnitude of the error bars indicates the degree of variability of the 1984 - 1988 results from the three chips due to a fault in the TLD reader. The results appear much the same for the E-03 and E-20 results (Figure 11-7). Note that E-20 did not begin until 1976. Again, there is an increase in both the E-20 (the 51
background site) and E-03 (the location nearest the ISFSI) which coincides with the switch from the LiF chips to the Teflon TLD cards. Given that the first twelve casks were loaded December 1995 to September 2000 in which there were no increases in the TLD results, the increase in 2001 indicates that this change is the result of the different response of the new TLDs and not of any effluents or shine from the plant. Figure 11-7 Comparison of E-03 and E-20 Results 1971 - 2015 Narrowing the time window for the TLD comparisons from 1992 to the present allows a comparison among the for original four TLD locations since the introduction of the ISFSI (Figure 11-8) without the interference by the faulty TLD reader in the mid-1980s. Sites E-01 and E-02 are about 1 mile south of the ISFSI. E-03 is 1200 feet west and E-04 is 4300 feet north. Figure 11-8 Comparison of E-01, E-02, E-03 and E-04 Results 1992 - 2015 The comparison shows a definite difference between E-01 and the other three locations. E-01, although approximately the same distance from the ISFSI as E-02 52
and further away than either E-03 or E-04, is lower than the other three sites. Therefore, distance is not the determining factor in the difference among the measured exposures. There are two factors which could cause the observed difference. The first difference is that E-02, E-3, and E-04 are surrounded by plowed fields whereas the area around E-01 is uncultivated. Second, E-01 is within 100 feet of the lake. Therefore, about 50% of the area contributing natural radiation to the location is a combination of beach sand and lake water. As seen from the REMP soil and beach analyses, beach sand has lower averages Ra-226 content than the soil, 0.38 +/- 0.07 pCi/g for beach sand vs. 0.86 +/- 0.36 pCi/g for soil. The impact of the ISFSI on the ambient radiation levels at its nearest site boundary, the west boundary is shown in Figure 11-9. The ISFSI impact on ambient exposure levels was addressed briefly in Section 11.1 (see Figure 11-2). Figure 11-9 E-03, E-31, and Background Site E-20 Results 1992 to 2015 Figure 11-2 shows that beginning with the use of the Teflon TLD cards in the fourth quarter of 2000, the measured exposure levels at E-03 are 2 - 5 mR/7-days lower than the exposures at the west fence of the ISFSI. Figure 11-9 shows that although their individual 95% confidence levels overlap indicating no statistical difference, the quarterly exposures at E-03 (about 1200 feet from the ISFSI) are consistently higher than the exposure at E-31 (at the site boundary about 1400 feet west of E-03). Therefore, the lower values at E-31 compared to E-03 appear to be a real difference 53
as the distance from the ISFSI increases at the west boundary. Because land usage and location are similar at E-03 and E-31, the cause of the previously identified response differences between E-03 and E-01 are not applicable. Therefore, the lower results at the site boundary location E-31show that the exposures from the ISFSI are dropping off and approaching the lower readings found at the background site E-20. 12.0 REMP CONCLUSION Based on the analytical results from the 811 environmental samples and from 130 sets of TLDs that comprised the PBNP REMP for 2015, PBNP effluents had no discernable effect on the surrounding environs. The calculated effluent doses are below the 10 CFR 50, Appendix I dose objectives demonstrate that PBNP continues to have good controls on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a. Additionally, when the TLD results are factored in to the overall exposure, the resulting doses are lower than the ISFSI (10 CFR 72.104) and EPA (40 CFR 190) limits of 25 mrem whole body, 75 mrem thyroid, and 25 mrem any other organ. From the long-term analysis of TLD results, there is no evidence of elevated ambient radiation levels from the operation of Point Beach except for the slightly higher exposures measured at the site boundary (E-31) compared to the background reference site (E-20). 54
Part D GROUNDWATER MONITORING 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium as part of the Groundwater Protection Program (GWPP). During 2015 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, façade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 façade. In the late 1970s, 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 this observation, modifications were made to the pool, and the tritium concentrations decreased below the effluent LLDs. 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. In addition to H-3, groundwater beach drain samples also are gamma scanned for the same suite of radionuclides as lake water using the lake water LLDs. Three intermittent stream locations 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. A fourth stream location closer to the plant was added in 2008. 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 meteorological tower. The intermittent stream samples track H-3 in the surface groundwater. The groundwater monitoring program also includes two bogs / 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, four 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. In 2012, a new building (Warehouse 7) was constructed for radwaste. The well for this building was added to the GWPP. 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 - 600 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 55
electrical conduits are susceptible to ground water in-leakage. Therefore, a number of these were sampled. The SSD system was designed to lessen hydrostatic pressure on the foundation by controlling the flow of water under the plant and around the perimeter of the foundation walls. The SSD system flows to a sump in the Unit 2 facade. The sump was sampled ten times during 2015. Due to flooding concerns, man-holes and clean-outs for the SSD now are sealed in 2014. Therefore, only the SSD sump now is used for sampling. In the 1990s, two wells were sunk in each units façade to monitor the groundwater levels and look for evidence of concrete integrity as part of the ISI IWE Containment Inspection Program. These wells are stand pipes which are sampled periodically for chemical analyses. Façade well sampling has been part of the GWPP since 2007. These wells are sampled quarterly. The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1. 56
Figure 13-1 Groundwater Monitoring Locations 57
14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface 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 and less than the MDC. The highest averages are for the East Creek and STP which are in the flow path to Lake Michigan. The West Creek is west of the former retention pond, an upstream location with respect to the groundwater flow. The H-3 concentration at GW-08, close to the former retention pond, is about one-tenth of the H-3 concentrations it had prior to the remediation of the retention pond. Table 14-1 Intermittent Streams and Bogs H-3 Concentration (pCi/l) Month GW-01(E-01) GW-02 GW-03 GW-17 BOGS MDC Creek Confluence E. Creek W. Creek STP GW-07 GW-08 Jan NS +/- NS +/- NS +/- NS +/- Feb NS +/- NS +/- NS +/- NS +/- Mar 167 +/- 80 270 +/- 85 93 +/- 76 196 +/- 81 147 Apr 136 +/- 80 222 +/- 84 107 +/- 79 220 +/- 84 147 May 106 +/- 80 ND +/- 129 +/- 81 131 +/- 81 135 +/- 84 275 +/- 91 150 Jun 123 +/- 78 184 +/- 81 ND +/- 174 +/- 80 143 Jul 124 +/- 81 83 +/- 79 141 +/- 82 221 +/- 86 143 Aug 77 +/- 76 173 +/- 81 117 +/- 78 138 +/- 79 145 Sep 143 +/- 81 189 +/- 83 113 +/- 79 220 +/- 85 147 Oct ND +/- ND +/- ND +/- 112 +/- 76 141 Nov ND +/- 163 +/- 80 ND +/- 97 +/- 77 144 Dec ND +/- 122 +/- 78 ND +/- NS +/- 144 Average 125 +/- 29 176 +/- 54 117 +/- 17 168 +/- 49 A blank indicates no sample was available. Streams are sampled monthly; bogs, annually. NS = no sample due to dry or frozen. Streams are sampled monthly; bogs, annually. Values are presented as the measured value and the 95% confidence level counting error. ND = measured value is less than the minimum detectable concentration. The LLD = 200 pCi/l. The analyses of these surface water samples show low concentrations of H-3. Although small positive H-3 concentrations occur in samples from the confluence of the two creeks (GW-01) and from the West Creek (GW-03), all, but one, of these concentrations are below their associated MDCs. In contrast, there are more positive results from GW-02 (south end of the East Creek) and GW-17 (located at the north end of the East Creek). GW-17 is directly east of the former retention pond area in the groundwater flow path to Lake Michigan. The East Creek concentrations are generally lower than the 300 - 350 pCi/l found before the retention pond was remediated in 2002. It should be noted that the East Creek, in addition to being path of the west to east groundwater flow from the old retention pond, also is fed by yard runoff from the west side of the yard which may account for the higher values. The bog (GW-08) SE of the former retention pond is higher than the bog at GW-07 north of the former retention pond. These results are in conformance with the west to east groundwater flow described in the Site Conceptual Model and the FSAR. 58
The GW-08 bog result is down from the 3000 pCi/l seen before the pond was remediated. 14.2 Beach Drains The 2015 results for the beach drains are presented in Table 14-2. [The drain data from left to right in the table are in the order of the drains from north to south.] S-1 collects yard drainage from the north part of the site yard; S-3, from the south. Drains S-8 and S-9 carry water from the lake side yard drains whereas drains S-7 and S-10 are from the turbine building roof. S-11 is not connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant. Table 14-2 2015 Beach Drain Tritium Average H-3 Concentration (pCi/l) Month S-1 S-7 S-8 S-9 S-10 S-3 S-11 MDC Jan NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- Feb NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- Mar 355 +/- 95 NF +/- NF +/- NF +/- NF +/- 316 +/- 93 210 +/- 88 148 Apr 134 +/- 86 NF +/- NF +/- NF +/- NF +/- 430 +/- 99 214 +/- 90 150 May 200 +/- 87 NF +/- NF +/- NF +/- NF +/- 302 +/- 92 NF +/- 147 Jun 212 +/- 87 NF +/- NF +/- NF +/- NF +/- 190 +/- 86 NF +/- 155 Jul 160 +/- 100 NF +/- NF +/- NF +/- NF +/- 262 +/- 104 NF +/- 154 Aug 122 +/- 85 NF +/- NF +/- NF +/- NF +/- 644 +/- 107 NF +/- 150 Sep 205 +/- 84 NF +/- NF +/- NF +/- NF +/- 249 +/- 87 NF +/- 148 Oct 244 +/- 86 NF +/- NF +/- NF +/- NF +/- 165 +/- 82 NF +/- 149 Nov 342 +/- 92 NF +/- NF +/- NF +/- NF +/- 219 +/- 86 NF +/- 151 Dec 292 +/- 87 NF +/- NF +/- NF +/- NF +/- 152 +/- 80 NF +/- 145 Avg = 227 +/- 81 293 +/- 148 212 +/- 3 ND = not detected and MDC NF = no sample due to no flow The high H-3 concentrations (355 and 644 pCi/l) occur in March of 2015 at S-1 and August at S-3. As in previous years, measureable H-3 results occur mostly in drains S-1 and S-3. As shown in previous reports, these high values are attributable to precipitation scavenging by rain and snow followed by melting. Gamma scans were performed on the beach drain samples at the LLD used for lake water. A few indications of small, positive concentration values below the calculated MDC were found for Zr-Nb-95(1), Cs-137(2), Fe-59 (1), Zn-65(1), Ba-La-140(4) as well as for naturally occurring Be-7(1). A liquid release source can be ruled out because no Ba-La-140 was released in 2015. Had there been a liquid source radionuclides such as Co-58 and Co-60 would have been seen as well. Similarly, no airborne Ba/La-140 was released either. Given that the measured concentrations are below their analytical MDC values, that they occur sporadically, and that some of these isotopes were not found in PBNP effluent, these small, positive values are considered to be false positives. Therefore, it is concluded that H-3 is the only PBNP radionuclide found in the beach drains. 59
14.3 Electrical Vaults and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The manholes east side of the plant, between the Turbine building and Lake Michigan have low H-3 concentrations (Table 14-3). These manholes, Z-066A and Z-067A through Z-066D AND Z-067D, run in parallel in the NE section of the yard beginning just north of the Unit 2 truck bay and run from the Unit 2 truck bay north to the EDG building. Z-068 is located just west of the EDG building and north of Z-66/67D. Each of the two A, B, C, and D vaults is side by side. Based on being side-by-side, it is expected that the each pair of manholes 66A/67A, etc. would have similar H-3 concentrations. This is appears to hold except for the 66B/67B vaults where the April H-3 results were not different from zero in the 66B sample. Unequal groundwater inleakage is the most probable cause. Table 14-3 2015 East Yard Area Manhole Tritium (pCi/l) MH 4/23/2015 9/28/2015 Z-066A 77 +/- 76 163 +/- 83 Z-067A 139 +/- 79 209 +/- 85 Z-066B ND ND Z-067B 248 +/- 84 ND Z-066C ND +/- 153 +/- 82 Z-067C 98 +/- 77 125 +/- 81 Z-066D 153 +/- 80 212 +/- 85 Z-067D 199 +/- 82 136 +/- 81 Z-068 250 +/- 85 220 +/- 86 MDC 152 149 ND = not detected 14.4 Façade Wells and Subsurface Drainage System There are two methods of sampling the groundwater under the plant foundation. The first is a set of four shallow wells, two in each façade. The other is a subsurface drainage system (SSD). The façade wells were installed to monitor for groundwater conditions which may be detrimental to the integrity of the concrete and rebar of each units foundation. The SSD was designed to relieve hydrostatic pressure on each units foundation as well as the Auxiliary and Turbine buildings. The façade wells are not located symmetrically in the two units. The Unit 1 façade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361B) corners of the façade. However, in Unit 2, there is one well in the NW corner (2Z-361A) and the other rotated approximately 180° in the SW corner (2Z-361B). In each the well cap is level with the floor. The 2015 façade well results are shown in Table 14-4. The Unit 1 wells continue to have higher H-3 concentrations than the U2 wells with 1Z-361A, in the SE corner of the Unit 1 façade, having the highest H-3 concentrations. The highest results are in line with the 2013 and 2014 highs of 324 and 375 pCi/l, respectively. By contrast, the 2007 and 2008 high concentrations were 1169 - 1331 pCi/l. Based on these 60
façade well results, the conclusion is that H-3 is unevenly distributed in the soil beneath the plant continues to be true. Table 14-4 2015 Facade Well Water Tritium (pCi/l) UNIT 1 UNIT 2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B MDC February 307 +/- 91 147 +/- 83 NS +/- ND +/- 81 151 April 287 +/- 107 ND +/- ND +/- ND +/- 84 183 August 253 +/- 87 ND +/- ND +/- 101 +/- 80 150 October 346 +/- 88 ND +/- ND +/- 120 +/- 77 141 To relieve hydrostatic pressure on the foundation, Point Beach has an external and an internal subsurface drainage system (SSD) to drain groundwater away from the foundation. The internal SSD consist of perforated piping which drains groundwater by gravity to a sump located in the Unit 2 façade. The part of the SSD under the Turbine Building is at a higher elevation than the part under the facades. The SSD sump results are presented in Table 14-5. The 2015 average concentration of 599 +/- 131 pCi/l is not statistically different than the 725 +/- 235, 643 +/- 201 and 513 +/- 269 pCi/l seen in 2014, 2013 and 2012, respectively. The external SSD system runs along the external foundation walls for the Unit 1 and Unit 2 facades, the Auxiliary Building, the North Service Building, and the Turbine Hall. It is not connected to the internal SSD system. During 2014, work to mitigate the possibility of external flooding events uncovered the N and S external SSD outfalls. Both the north and south halves of the external SSD system drain toward the beach. No samples from the external SSD were obtained in 2015 because there was not flow. Table 14-5 2015 Unit 2 Facade SSD Sump H-3 (pCi/l) Date pCi/l 2 MDC 20-Jan 682 +/- 135 196 15-Feb 721 +/- 107 148 26-Mar 475 +/- 102 152 30-Apr 648 +/- 106 147 2-Jun 741 +/- 109 155 30-Jun 591 +/- 105 149 31-Aug 577 +/- 104 147 30-Sep 306 +/- 91 144 30-Oct 683 +/- 103 143 7-Dec 568 +/- 98 146 31-Dec 496 +/- 112 152 Average 590 +/- 128 In addition to H-3, the façade wells and internal SSD samples were gamma scanned. As in lake water samples, small positive values below their calculated, minimum detectable concentrations were found. 61
The isotopes in the SSD and façade wells were Fe-59, Co-58/60, Zr-Nb-95, Cs-137, and Ba-La-140. In the SSD, Mn-54, Fe-59, Co-60, Cs-137, and Ba-La-140 had small, positive values. There are no known inputs to the soil beneath the plant. Therefore, because the values were less than or equal to the MDC, it is concluded that these results are false positives. 14.5 Potable Water and Monitoring Wells Outside of the protected area, ten wells, in addition to the main plant well (Section 11.7), are used for monitoring H-3 in groundwater: the four potable water wells, GW-04 (Energy Information Center or EIC), GW-05 (Warehouse 6), GW-18 (Warehouse 7), GW-06 (Site Boundary Control Center), and six H-3 groundwater monitoring wells, GW-11 through GW-16 (Figure 13-1). The potable water wells monitor the deep, drinking water aquifer whereas the monitoring wells penetrate less than 30 feet to monitor the top soil layer. The potable water aquifer is separated from the shallow, surface water aquifer by a thick, impermeable clay layer. The potable water wells had no detectable H-3 (Table 14-6). Table 14-6 2015 Potable Well Water Tritium Concentration (pCi/l) EIC Warehouse SBCC GW-05, EIC WELL MDC 6 Well Well WH 7 06, 18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan ND 192 ND ND ND 165 Feb ND 142 Mar ND 147 Apr ND 147 ND ND ND 158 May ND 150 Jun ND 143 Jul ND 143 ND ND ND 154 Aug ND 145 Sep ND 147 Oct ND 141 ND ND ND 149 Nov ND 144 Dec ND 144 ND= not detected The monitoring well results are similar to that obtained in 2014. The two monitoring wells showing consistent, detectable H-3 (GW-15, GW-16) are in the flow path from the retention pond area to the lake (Table 14-7). The highest H-3 concentration occurs at GW-15, the well closest to the former unlined retention pond. However, considering the statistical uncertainty of the measurements, the results from GW-15 and GW-16 are the same. These two samples and those from the nearby surface water sample locations (GW-03, the east creek; GW-08, the bog to the SE of the former pond; and GW-17, the surface water on the SE corner of the STP) demonstrate that the area around and in the groundwater flow from the former retention pond remain impacted by the H-3 that diffused from the pond into the soil while it was in use. 62
Table 14-7 2015 Quarterly Monitoring Well Tritium (pCi/l) MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Q GW-11 GW-12 GW-13 GW-14 GW-15 GW-16 MDC 1 ND +/- NS +/- ND +/- ND +/- *131 +/- *105 147 +/- 106 196 2 ND +/- ND +/- ND +/- ND +/- ND +/- 186 +/- 81 159 3 130 +/- 82 ND +/- 159 +/- 83 139 +/- 82 284 +/- 89 199 +/- 85 143 4 108 +/- 76 NS +/- 134 +/- 77 91 +/- 75 187 +/- 80 179 +/- 80 141 ND= not statistically different from zero. NS = no sample available
*Duplicate samples taken. The other results was ND.
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. Results from precipitation analyses (2011 AMR) show that airborne H-3 concentrations are higher close to the plant as compared to results at the site boundaries. The observed tritium concentrations in the yard manholes can be explained by the higher H-3 in precipitation close to the plant. In addition to tritium captured by precipitation, the beach drains also receive the H-3 captured in the AC condensate because the condensate drainage is connected to the yard drain system. Tritium continues in the soil below the plant foundation as evidenced by results from the subsurface drainage system and from the façade wells. Except for the monitoring wells downstream from the former retention pond, the monitoring well tritium concentrations are not different from zero. These results conform to the known west-to-east groundwater flow at the site. Therefore, the impact of the flow of tritiated groundwater from the vicinity of the former retention pond toward the lake on beach drain S-3 tritium results as can not be discounted. The impact of this flow would be greater on beach drain S-3 than on S-1 because the eastward flow in the area of S-3 would be less impacted by plant structures than the drainage system feeding beach drain S-1. In conclusion, the groundwater H-3 concentrations observed at Point Beach are below the EPA drinking water standards prior to emptying into Lake Michigan where they will undergo further dilution. All analyses to date indicate that the drinking water contains no tritium. None of the H-3 in the upper soil layer is migrating off-site toward the surrounding population. This is based on the known west-to-east groundwater flow toward Lake Michigan and the negative results from the four wells (GW-11 through GW-14, Figure 13-1). Additionally, because no H-3 is detected in either of the four on-site drinking water wells close to the power block or from the drinking water well at the site boundary, none of the H-3 observed in the upper soil layer has penetrated into the drinking water aquifer to endanger either on-site or off-site personnel. 63
APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2015
(
~+L ATI EnvironmentaiSl Inco
'+~M.I Midwest laborat<<>>ry 700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-4517 FINAL REPORT TO NextEra 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 Reporting Period: January-December, 2015 Reviewed and Approved by --~--+---+~=h~~:;._,.~~~~ Date Distribution: K. Johansen, 1 hardcopy, 1 e-mail
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POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section Page List of Tables .... .. ... ... ... ............ .. ....... ........ ...................... .. ........ iii
1.0 INTRODUCTION
.. ...... ..... .. ...... .... .... ....... ... ...... .. .... .. ....... .......... iv 2.0 LISTING OF MISSED SAMPLES ......... .. .... .. ........... .... .... .. .... .. . v 3 DATA TABLES ............. ...... .. .... .. .. .. .. .... ....... .. ..... .. .... ............... vi Appendices A Interlaboratory Comparison Program Results .... .. ............ .. ...... A-1 B Data Reporting Conventions ....... .. .... .. .......... .. ... ........ .. ............ . B-1 C Sampling Program and Locations .. ..... .. .............. .. ................... C-1 D Graphs of Data Trends .. .. ...... .. ...... .... ..... .. .. .. ..... ........ .. ............ . D-1 E Supplemental Analyses .. .. .... ... .... ....... ... ............ .. ....... .. ..... .. .... . E-1 F Special Analyses .. ....... ... ... .. .... .. .... .. ...... ...... .... .. ......... F-1 ii
POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and lodine-131 Location E-01, Meteorological Tower .. ............ .. .. ... .............. ..... ...... 1-1 Location E-02, Site Boundary Control Center .. ... .. .. ........ ... ... .. ... .. . ... 1-2 Location E-03, West Boundary ....... ........... .. ... .. .. .... .. .. .. ... ... .. ... ... .. . 1-3 Location E-04, North Boundary ..... .. ... ... .. .... . ... .. .. .. ..... ..... ... ...... .. .... 1-4 Location E-08, G. J. Francar Residence.. ........ ................... ........... . 1-5 Location E-20, Silver Lake College ......... ..... .. .. .............. .. ... ... ......... 1-6 Airborne Particulates, Gamma Isotopic Analyses .. ..... ........ ... ......... .. .. ....... . 2-1 Milk......... .......... .. ...... ... .. .. ... ..... ... ... ...... .. .... .. ......... ..... .............. ........ ...... 3-1 Well Water .... .. ... .. .... .... .. ... . .. ... .. .... .. .. .. ... .. ... ... .. ......... .... .. .. ..... . .... .. .. .. .. .. . 4-1 Lake Water .. .. .. ...... .. ... ... .. ....... .. .. .. .. .. .... ... .. ... ...... ..... .. ........ ..... ... ... .. .. ... .. . 5-1 Lake Water, Analyses on Quarterly Composites ..... ................................... .. .. ... 6-1 Fish ....... ... ......... ..... ..... .......................... .. ..................... .... ....... .... .. ... .... ............ .. 7-1
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Shoreline Sediments ......... ............................................ ............. ...... .......... ... ..... 8-1 Soil ...... ....... ............................. ... ... ................ ............. ............................. .. ..... .. .. 9-1 Vegetation ......................... :.. ..................................... ..... ....... ............................. 10-1 Aquatic Vegetation ............................ ............ .... ..... .......... .................................. 11-1 Gamma Radiation, as Measured by TLDs .... ................................................... . 12-1 Groundwater Monitoring Program ................ ......... .... ...... .... ... ...... .. ................ .... 13-1
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POINT BEACH NUCLEAR PLANT
1.0 INTRODUCTION
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The following constitutes the final 2015 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, Tl-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. All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples. iv
POINT BEACH NUCLEAR PLANT ( 2.0 LISTING OF MISSED SAMPLES
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Expected Collection Sample Type Location Date Reason LW E-01 02-15-15 No sample due to icy conditions. LW E-05 02-15-15 No sample due to icy conditions. LW E-06 02-15-15 No sample due to icy conditions. LW E-33 02-15-15 No sample due to icy conditions. Algae E-05 06-10-15 No algae found Algae E-12 06-10-15 No algae found AP/AI E-01 07-01-15 Loss of power due to storms. Algae E-05 08-27-15 No algae found ( Algae E-05 10-07-15 No algae found Algae E-12 10-07-15 No algae found v
POINT BEACH NUCLEAR PLANT 3.0 Data Tables ./ vi
POINT BEACH NUCLEAR PLANT
/ Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
Location: E-01, Meteorological Tower 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 343 0.032 +/- 0.004 < 0.007 07-08-15 295 0.018 +/- 0.003 < 0.011 01 15 304 0.028 +/- 0.004 < 0.013 07-15-15 300 0.018 +/- 0.003 < 0.006 01-21-15 295 0.029 +/- 0.004 < 0.010 07-22-15 301 0.016 +/- 0.003 < 0.008 01-28-15 297 0.020 +/- 0.003 < 0.007 07-29-15 301 0.027 +/- 0.004 < 0.009 02-04-15 299 0.025 +/- 0.003 < 0.005 08-05-15 300 0.017 +/- 0.003 < 0.008 02-11-15 307 0.035 +/- 0.004 < 0.010 08-12-15 301 0.019 +/- 0.003 < 0.010 02r18-15 301 0.025 +/- 0.003 < 0.006 08-19-15 292 0.043 +/- 0.005 < 0.011 02-25-15 305 0.051 +/- 0.004 < 0.009 08-26-15 307 0.018 +/- 0.003 < 0.009 09-02-15 300 0.035 +/- 0:004 < 0.009 03-04-15 309 0.032 +/- 0.004 < 0.013 03-11-15 298 0.029 +/- 0.004 < 0.009 09-09-15 293 0.039 +/- 0.004 < 0.011 03-18-15 301 0.019 +/- 0.003 < 0.012 09-16-15 304 0.027 +/- 0.004 < 0.006 03-25-15 306 0.022 +/- 0.004 < 0.010 09-23-15 300 0.027 +/- 0.004 < 0.011 04-01-15 304 0.018 +/- 0.003 < 0.011 09-30-15 297 0.030 +/- 0.004 < 0.008 / 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.009 < 0.009 Mean+/- s.d. 0.026 +/- 0.009 < 0.009 04-08-15 311 0.024 +/- 0.003 < 0.006 10-07-15 302 0.015 +/- 0.003 < 0.006 04-15-15 298 0.020 +/- 0.003 < 0.014 10-14-15 302 0.023 +/- 0.004 < 0.008 04-22-15 296 0.013 +/- 0.003 < 0.009 10-21-15 296 0.027 +/- 0.004 < 0.007 04-29-15 306 0.014 +/- 0.003 < 0.010 10-28-15 305 0.024 +/- 0.004 < 0.005 05-06-15 300 0.015 +/- 0.003 < 0.012 11-04-15 308 0.020 +/- 0.003 < 0.008 05-13-15 300 0.012 +/- 0.003 < 0.010 11-11 -15 315 0.029 +/- 0.004 < 0.010 05-20-15 301 0.017 +/- 0.003 < 0.014 11-18-15 304 0.039 +/- 0.004 < 0.010 05-27-15 301 0.020 +/- 0.003 < 0.010 11-24-15 274 0.022 +/- 0.004 < 0.015 06-03-15 302 0.013 +/- 0.003 < 0.010 12-02-15 336 0.031 +/- 0.004 < 0.006 06-10-15 302 0.017 +/- 0.003 < 0.012 12-09-15 310 0.053 +/- 0.005 < 0.009 06-17-15 310 0.012 +/- 0.003 < 0.009 12-16-15 298 0.028 +/- 0.004 < 0.007 06-24-15 . 293 0.014 +/- 0.003 < 0.009 12-22-15 269 0.029 +/- 0.004 < 0.012/ 8 07-01 -15 ND 12-30-15 352 0.027 :!; 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.016 +/- 0.004 < 0.010 Mean+/- s.d. 0.028 +/- 0.009 < 0.009 Cumulative Average 0.025 +/- 0.009 < 0.009 a "NO" = No data; see Table 2.0, Listing of Missed Samples. 1-1
POINT BEACH NUCLEAR PLANT ( Table 1: Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 . Location: E-02, Site Boundary Control Center
' 3 Units: pCi/m Collection: Continuous, weekly exchange.
Date Vol. Date Vol. Collected (ma) Gross Beta 1-131 Collected (ma) Gross Beta 1-131 Required LLD 0.010 .Q,_@Q Required LLD 0.010 0.030 01 15 350 0.031 +/- 0.003 < 0.007 07-08-15 303 0.021 +/- 0.004 < 0.011 01-14-15 303 0.026 +/- 0.004 < 0.013 07-15-15 300 0.015 +/- 0.003 < 0.006 01-21 -15 287 0.032 +/- 0.004 < 0.011 07-22-15 299 0.019 +/- 0.003 < 0.008 01 15 306 0.022 +/- 0.003 < 0.007 07-29-15 303 0.030 +/- 0.004 < 0.009 02-04-15 310 0.024 +/- 0.003 < 0.005 08-05-15 298 0.019 +/- 0.003 < 0.008 02-11-15 307 0.032 +/- 0.004 < 0.010 08-12-15 305 0.019 +/- 0.003 < 0.010 02-18-15 310 0.028 +/- 0.004 < 0.006 08-19-15 304 0.038 +/- 0.004 < 0.010 02-25-15 323 0.054 +/- 0.004 < 0.008 08-26-15 295 0.015 +/- 0.003 < 0.010 09-02-15 295 0.039 +/- 0.004 < 0.009 03-04-15 307 0.031 +/- 0.004 < 0.013 03-11-15 303 0.020 +/- 0.004 < 0.009 09-09-15 303 0.040 +/- 0.004 < 0.010 03-18-15 303 0.020 +/- 0.004 < 0.012 09-16-15 310 0.026 +/- 0.004 < 0.006 03-25-15 305 0.019 +/- 0.004 < 0.010 09-23-15 296 0.028 +/- 0.004 < 0.011 04-01-15 306 0.018 +/- 0.003 < 0.011 09-30-15 298 0.036 +/- 0.004 < 0.008
/ 1st Quarter 3rd Quarter ' Mean+/- s.d. 0.027 +/- 0,009 < 0.009 Mean+/- s.d. 0.027 +/- 0.009 < 0.009 04-08..:15 305 0.021 +/- 0.003 < 0.006 10-07-15 297 0.016 +/- 0.003 < 0.006 04-15-15 305 0.018 +/- 0.003 < 0.014 10-14-15 296 0.029 +/- 0.004 < 0.008 04-22-15 290 0.012 +/- 0.003 < 0.009 10-21 -15 302 0.027 +/- 0.004 < 0.007 04-29-15 305 0.012 +/- 0.003 < 0.010 10-28-15 302 0.022 +/- 0.004 < 0.006 05-06-15 302 0.017 +/- 0.003 < 0.012 11 15 308 0.029 +/- 0.004 < 0.008 05-13-15 302 0.010 +/- 0.003 < 0.010 11-11-1 5 307 0.026 ::!: 0.004 < 0.010 05-20-15 297 0.013 +/- 0.003 < 0.015 11-18-15 297 0.041 +/- 0.004 < 0.010 05-27-15 297 0.022 +/- 0.003 < 0.010 11-24-15 264 0.022 +/- 0.004 < 0.016 06-03-15 300 0.014 +/- 0.003 < 0.010 12-02-15 343 0.034 +/- 0.004 < 0.006 06-10-15 300 0.021 +/- 0.003 < 0.012 12-09-15 306 0.053 +/- 0.005 < 0.009 06-17-15 304 0.009 +/- 0.003 < 0.009 12-16-15 299 0.030 +/- 0.004 < 0.007 06-24-15 294 0.014 +/- 0.003 < 0.009 12-22-15 260 ~.029 +/- 0.004 < 0.013 07-01-15 301 0.018 +/- 0.003 < 0.012 12-30-15 353 0.027 +/- 0.003 < 0.009 .
2nd Quarter 4th Quarter Mean+/- s.d. 0.016 +/-0.004 < 0.011 Mean+/- s.d. 0.029 +/- 0.009 . < 0.009 Cumulative Average 0.025 +/- 0.010 < 0.009 / 1-2
POINT BEACH NUCLEAR PLANT i
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Table 1. Airborne particulates and charcoal can isters, analyses for gross beta and iodine-131. Location: E-03, West Boundary 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reguired LLD 0.010 0.030 Reguired LLD 0.010 0.030 01-07-15 339 0.033 +/- 0.004 < 0.007 07-08-15 300 0.022 +/- 0.004 < 0.011 01-14-15 293 0.028 +/- 0.004 < 0.013 07-15-15 299 0.020 +/- 0.003 < 0.006 01-21-15 297 0.035 +/- 0.004 < 0.010 07-22-15 296 0.016 +/- 0.003 < 0.008 01-28-15 298 0.022 +/- 0.003 < 0.007 07~29 - 15 305 0.029 +/- 0.004 < 0.009 02-04-15 302 0.022 +/- 0.003 < 0.005 08-05-15 296 0.017:!; 0.003 < 0.008 02-11-15 310 0.034 +/- 0.004 < 0.009 08-12-15 302 0.016 +/- 0.003 < 0.010 02-18-15 300 0.031 +/- 0.004 < 0.006 08-19-15 213 0.051 +/- 0.006 < 0.015 02-25-15 305 0.052 +/- 0.004 < 0.009 08-26-15 306 0.015 +/- 0.003 < 0.009 09-02-15 289 0.034 +/- 0.004 < 0.009 03-04-15 306 0.030 +/- 0.004 < 0.013 03-11-15 299 0.026 +/- 0.004 < 0.009 09-09-15 300 0.051 +/- 0.005 < 0.011 03-18-15 299 0.020 +/- 0.004 < 0.012 09-16-15 302 0.027 +/- 0.004 < 0.006 03-25-15 299 0.024 +/- 0.004 < 0.010 09-23-15 304 0.031 +/- 0.004 < 0.011 04-01-15 307 0.016 +/- 0.003 < 0.011 09-30-15 295 0.036 +/- 0.004 < 0.008
/ 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.009 < 0.009 Mean+/- s.d. 0.028 +/- 0.012 < 0.009 04-08-15 308 0.022 +/- 0.003 < 0.006 10-07-15 305 0.015 +/- 0.003 < 0.006 04-15-15 297 0.017 +/- 0.003 < 0.014 10-14-15 297 0.023 +/- 0.004 < 0.008 04-22-15 286 0.010 +/- 0.003 < 0.009 10-21-15 302 0.025 +/- 0.004 < 0.007 04-29-15 304 0.013 +/- 0.003 < 0.010 10-28-15 302 0.023 +/- 0.004 < 0.006 05-06-15 303 0.014 +/- 0.003 < 0.01Z 11-04-15 302 0.030 +/- 0.004 < 0.008 05-13-15 303 0.010 +/- 0.003 < 0.010 11-11-15 310 0.030 +/- 0.004 < 0.010 05-20-15 301 0.014 +/- 0.003 < 0.014 11-18-15 298 0.036 +/- 0.004 < 0.010 05-27-15 301 0.017 +/- 0.003 < 0.010 11-24-15 263 0.020 +/- 0.004 < 0.016 06-03-15 304 0.013 +/- 0.003 < 0.010 12-02-15 336 0,031 +/- 0.004 < 0.006 06-10-15 304 0.019 +/- 0.003 < 0.012 12-09-15 302 0.057 +/- 0.005 < 0.009 06-17-15 294 0.013 +/- 0.003 < 0.009 12-16-15 300 0.028 +/- 0.004 < 0.007 06-24-15 294 0.012 +/- 0.003 < 0.009 12-22-15 264 /0.027 +/- 0.004 < 0.013 07-01-15 289 0.018 +/- 0.003 < 0.013 12-30-15 352 0.028 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.003 < 0.011 Mean+/- s.d. 0.029 +/- 0.010 < 0.009 Cumulative Averaf.le 0.025 +/- 0.011 < 0.010 a Low volume due to shut down for calibration. / ' * ~.
1-3
POINT BEACH NUCLEAR PLANT I Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
. Location: E-04, North Boundary 3
Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 QJ@ 01-07-15 345 0.033 +/- 0.004 < 0.007 07-08-15 305 0.019 +/- 0.003 < 0.011 01-14-15 305 0.040 +/- 0.004 < 0.013 07-15-15 301 0.018 +/- 0.003 < 0.006 01-21-15 300 0.028 +/- 0.004 < 0.010 07-22-15 295 0.018:!; 0.003 < 0.008 01-28-15 310 0.021 +/- 0.003 < 0.007 07-29-15 304 0.030 +/- 0.004 < 0.009 02-04-15 316 0.020 +/- 0.003 < 0.005 08-05-15 310 0.017 +/- 0.003 < 0.007 02-11-15 291 0.034 +/- 0.004 < 0.010 08-12-15 305 0.016 +/- 0.003 < 0.010 02-18-15 314 0.032 +/- 0.004 < 0.006 08-19-15 297 0.041 +/- 0.004 < 0.011 02-25-15 330 0.052 +/- 0.004 < 0.008 08-26-15 303 0.017 +/- 0.003 < 0.009 09-02-15 290 0.035 +/- 0.004 < 0.009 03-04-15 310 0.026 +/- 0.004 < 0.013 03-11-15 300 0.020 +/- 0.004 < 0.009 09-09-15 300 0.032 +/- 0.004 < 0.011 03-18-15 295 0.021 +/- 0.004 < 0.013 09-16-15 305 0.031 +/- 0.004 < 0.006 03-25-15 301 0.024 +/- 0.004 < 0.010 09-23-15 303 0.027 +/- 0.004 < 0.011 04-01-15 309 0.016 +/- 0.003 < 0.011 09-30-15 296 0.030 +/- 0.004 < 0.008 r 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.010 < 0.009 Mean+/- s.d. 0.025 +/- 0.088 < 0.009 04-08-15 308 0.022 +/- 0.003 < 0.006 10-07-15 309 0.012 +/- 0.003 < 0.006 04-15-15 302 0.018 +/- 0.003 < 0.014 10-14-15 300 0.024 +/- 0.004 < 0.008 04-22-15 293 0.011 +/- 0.003 < 0.009 10-21 -15 302 0.028 +/- 0.004 < 0.007 04-29-15 305 0.010 +/- 0.003 < 0.010 10-28-15 305 0.025 +/- 0.004 < 0.005 05-06-15 305 .-*- 0.016 +/- 0.003 < 0.012 11-04-15 302 0.025 +/- 0.004 < 0.008 05-13-15 305 0.011 :!;: 0.003 < 0.010 11-11-15 315 0.034 +/- 0.004 < 0.010 05-20-15 301 0.016 +/- 0.003 < 0.014 11-18-15 300 0.041 +/- 0.004 < 0.010 05-27-15 301 0.018 +/- 0.003 < 0.010 11-24-15 270 0.020 +/- 0.004 < 0.015 06-03-15 305 0.014 +/- 0.003 < 0.010 12-02-15 340 0.031 +/- 0.004 < 0.006 06-10-15 305 0.022 +/- 0,003 < 0.012 12-09-15 305 0.053 +/- 0.005 < 0.009 06-17-15 306 0.010 +/- 0.003 < 0.009 12-16-15 299 0.027 +/- 0.004 < 0.007 06-24-15 296 0.012 +/- 0.003 < 0.008 12-22-15 263 j0.028 +/- 0.004 < 0.013 07-01-15 307 0.017 +/- 0.003 < 0.012 12-30-15 358 0.025 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.004 < 0.010 Mean:!; s.d. 0.029 ::!: 0.010 < 0.009 Cumulative Average 0.024 +/- 0.010 < 0.009 1-4
POINT BEACH NUCLEAR PLANT
,.r Table 1. Airborne particulates and charcoal canisters, analy$es for gross beta and iodine-131.
Location: E-08, G.J. Francar Residence 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 340 0.034 +/- 0.004 < 0.007 07-08-15 298 0.020 +/- 0.003 < 0.011 01-14-15 306 0.030 +/- 0.004 < 0.013 07-15-15 302 0.017 +/- 0.003 < 0.006 01-21-15 298 0.032 +/- 0.004 < 0.010 07-22-15 304 0.021 +/- 0,003 < 0.008 01-28-15 306 0.021 +/- 0.003 < 0.007 07-29-15 311 0.028 +/- 0.004 < 0.009 02-04-15 313 0.023 +/- 0.003 < 0.005 08.05-15 307 0.018 +/- 0.003 < 0.008 02-11-15 295 0.033 +/- 0.004 < 0.010 08-12-15 269 0.024 +/- 0.004 < 0.011 02-18-15 299 0.027 :\: 0.004 < 0.006 08-19-15 285 0.037 ;!: 0.004 < 0.011 02-25-15 310 0.046 +/- 0.004 < 0.009 08-26-15 306 . 0 .014 +/- 0.003 < 0.009 09-02-15 289 0.039 +/- 0.004 < 0.009 03-04-15 306 0.029 +/- 0.004 < 0.013 03-11-15 300 0.026 +/- 0.004 < 0.009 09-09-15 303 0.039 +/- 0.004 < 0.010 03-18-15 303 0.020 +/- 0.004 < 0.012 09-16-15 307 0.027 +/- 0.004 < 0.006 03-25-15 304 0.026 +/- 0.004 < 0.010 09-23-15 298 0.034 +/- 0.004 < 0.011 04-01-15 304 0.016 +/- 0.003 < 0.011 09-30-15 299 0.033 +/- 0.004 < 0.008
/
1st Quarter 3rd Quarter
' Mean+/- s.d. 0.028 +/- 0.008 < 0.009 Mean+/- s.d. 0,027 ':!; 0,009 < 0.009 04-08-15 307 0.021 +/- 0.003 < 0.006 10-07-15 296 0.017 +/- 0.003 < 0.006 04-15-15 296 0.018 +/- 0.003 < 0.014 10-14-15 291 0.024 +/- 0.004 < 0.008 04-22-15 288 0.014 +/- 0.003 < 0.009 10-21-15 301 0.026 +/- 0.004 < 0.007 04-29-15 302 0.013 +/- 0.003 < 0.010 10-28-15 302 0.023 +/- 0.004 < 0.006 05-06-15 306 0.016 +/- 0.003 < 0.012 11-04-15 305 0.023 +/- 0.003 < 0.008 05-13-15 306 0.012 +/- 0.003 < 0.010 11-11-15 314 0.034 +/- 0.004 < 0.010 '
05-20-15 297 0.014 +/- 0.003 < 0.015 11-18-15 306 0.036 +/- 0.004 < 0.010 05-27-15 297 0.019 +/- 0.003 < 0.010 11-24-15 270 0.023 ;!: 0.004 < 0.015 06-03-15 303 0.015 +/- 0.003 < 0.010 12-02-15 344 0.030 +/- 0.004 < 0.006 06-10-15 303 0.018 +/- 0.003 < 0.012 12-09-15 307 0.053 +/- 0.005 < 0.009 06-17-15 312 0.010 +/- 0,003 < 0.009 12-16-15 293 0.029 +/- 0.004 < 0.007 06-24-15 296 0.012 +/- 0.003 < 0.008 12-22-15 271 !n.028 +/- 0.004 < 0.012 07-01-15 312 0.017 +/- 0.003 < 0.012 12-30-15 351 0.026 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. 0.015 +/- 0.003 < 0.011 Mean+/- s.d. 0.029 l; 0.'009 < 0.009 Cumulative Average 0.025 +/- 0.009 < 0.009 Indicator Locations Annual Mean +/- s.d. 0.025 +/- 0.010 < 0.009
/
it ~* 1-5
POINT BEACH NUCLEAR PLANT
./ Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .
Location : E-20, Silver Lake 3 Units: pCi/m Collection: Continuous, weekly exchange. Date Vol. Date Vol. Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-15 347 0.035 +/- 0.004 < 0.007 07-08-15 299 0.020 +/- 0.003 < 0.011 01-14-15 345 0.027 +/- 0_003 < 0.011 07-15-15 299 0.018 +/- 0.003 < 0.006 01-21-15 299 0.031 +/- 0.004 < 0.010 07-22-15 300 0.020 +/- 0.003 < 0.008 01-28-15 300 0.020 +/- 0.003 < 0.007 07-29-15 301 0.030 +/- 0.004 < 0.009 02-04-15 306 0.024 +/- 0.003 < 0.005 08-05-15 311 0.018 +/- 0.003 < 0.007 02-11-15 296 0.038 +/- 0.004 < 0.010 08-12-15 301 0.020 +/- 0.003 < 0.010 02-18-15 306 0.029 +/- 0.004 < 0.006 08-19-15 283 0.044 +/- 0.005 < 0.011 02-25-15 319 0.035 +/- 0.004 < 0.008 08-26-15 306 0.015 +/- 0.003 < 0.009 09-02-15 289 0.033 +/- 0.004 < 0.009 03-04-15 310 0.030 +/- 0.004 < 0.013 03-11-15 295 0.022 +/- 0.004 < 0.009 09-09-15 311 0.034 +/- 0.004 < 0.010 03-18-15 298 0.023 +/- 0.004 < 0.012 09-16-15 307 0.025 +/- 0.004 < 0.006 03-25-15 300 0.021 +/- 0.004 < 0.010 09-23-15 302 0.023 :1; 0.003 < 0.011 04-01-15 309 0.014 +/- 0.003 < 0.011 09-30-15 298 o.o33 +/- o*: oo4 < 0.008
~* ../ ..;.
1st Quarter 3rd Quarter .' Mean+/- s.d. 0.027 +/- 0.007 < 0.009 Mean+/- s.d. 0.026 +/- 0.009 '< 0.009 04-08-15 307 0.022 +/- 0.003 < 0.006 10-07-15 309 *o.o13 +/- o.oo3 < 0.006 04-15-15 296 0.021 +/- 0.003 < 0.014 10-14-15 293 0.024 +/- 0.004 < 0.008
- 04:?2-15 285 0.011 +/- 0.003 < 0.009 10-21-15 299 0.027 +/- 0.004 < 0.007 ,
'\..
04~29-15 304 0.014 +/- 0.003 < 0.010 10-28-15 306 0.025 +/- 0.004 < 0.005 05-06-15 301 0.012 +/- 0.003 < 0.012 11-04-15 305 0.023 +/- 0.003 < 0.008 05-13-15 301 0.010 +/- 0.003 < 0.010 11-11-15 311 0.030 +/- 0.004 < 0.010 05-20-15 303 0.012 +/- 0.003 < 0.014 11-18-15 301 0.041 +/- 0.004 < 0.010 05-27-15 303 0.017 +/- 0.003 < 0.010 11-24-15 265 0.025 +/- 0.004 < 0.016 06-03-15 304 0.013 +/- 0.003 < 0.010 12-02-15 346 0.031 +/- 0.004 < 0.006 06-10-15 304 0.017 +/- 0.003 < 0.012 12-09-15 301 0.057 +/- 0.005 < 0.009 06-17-15 313 0.010 +/- 0.003 < 0.009 12-16-15 299 0.031 +/- 0.004 < 0.007 06-24-15 296 0.014 +/- 0.003 < 0.008 12-22-15 264 /0.030 +/- 0.004 < 0.013 07-01-15 309 0.016 :!: 0.003 < 0.012 12-30-15 349 0.027 +/- 0.003 < 0.009 2nd Quarter 4th Quarter Mean+/- s.d. O.Of5 +/- 0.004 < 0.010 Mean+/- s.d. 0.029 +/- 0.010 < 0.009 Cumulative Average 0.024 +/- 0.009 < 0.009 Control Annual Mean +/- s.d. 0.024 +/- 0.009 < 0.009 I' 1-6
POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pCi/m 3 (Other) (Other) Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co-60) Volume Req . LLD MDC 0.01 MDC 0.01 MDC ( 0.10) MDC m3 1st Quarter E-01 EAP- 1903 0.074 +/- 0.015 0.0000 +/- 0.0004 < 0.0005 0.0002 +/- 0.0004 < 0.0006 -0 .0002 +/- 0.0007 < 0.0007 3970 E-02 - 1904 vd.084 +/- 0.017 -0.0003 +/- 0.0004 < 0.0008 0.0002 +/- 0.0005 < 0.0008 -0.0001 +/- 0.0006 < 0.0007 4020 E-03 - 1905 0.058 +/- 0.015 0.0000 +/- 0.0004 < 0.0007 0.0001 +/- 0.0006 < 0.0010 0.0003 +/- 0.0005 < 0.0007 3953 E-04 - 1906 0.061 +/- 0.020 -0.0004 +/- 0.0005 < 0.0009 -0.0001 +/- 0.0005 < 0.0007 -0.0001 +/- 0.0007 < 0.0008 4025 E-08 - 1907 0.061 +/- 0.017 0.0003 +/- 0.0004 < 0.0008 0.0003 +/- 0.0005 < 0.0009 -0 .0001 +/- 0.0005 < 0.0007 3983 E-20 - 1908 0.063 +/- 0.014 0.0004 + 0.0004 < 0.0007 0.0000 + 0.0005 < 0.0008 -0 0001 + 0.0006 < 0.0007 4030 2nd Quarter E-01 EAP- 3960 0.069 +/- 0.018 0.0000 +/- 0.0004 < 0.0009 -0.0004 +/- 0.0006 < 0.0008 0.0001 +/- 0.0006 < 0.0004 3620 E-02 - 3961 0.065 +/- 0.014 -0.0003 +/- 0.0005 < 0.0009 -0 .0004 +/- 0.0006 < 0.0007 0.0004 +/- 0.0005 < 0.0008 3901 E-03 - 3962 0.066 +/- 0.012 -0.0001 +/- 0.0004 < 0.0008 >C(ooo7 +/- o.ooo6 < 0.0010 -0.0002 +/- 0.0005 < 0.0005 3888 E-04 - 3963 0.064 +/- 0.014 0.0001 +/- 0.0005 < 0.0007 -0.0002 +/- 0.0006 < 0.0006 -0.0008 +/- 0.0006 < 0.0004 3937 E-08 - 3964 0.062 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0004 < 0.0005 -0.0003 +/- 0.0004 < 0.0004 3925 E-20 - 3965 0.066 +/- 0.013 0.0000 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0005 < 0.0006 0.0000 +/- 0.0006 < 0.0005 3927 3rd Quarter E-01 EAP- 5991 0.076 +/- 0.015 -0.0003 +/- 0.0006 < 0.0009 0.0002 +/- 0.0006 < 0.0007 vb.0006 +/- 0.0005 < 0.0005 3892 E-02 - 5992 0.068 +/- 0.016 -0.0002 +/- 0.0005 < 0.0010 0.0000 +/- 0.0006 < 0.0010 0.0001 +/- 0.0006 < 0.0007 3910 E-03 - 5993 0.083 +/- 0.015 -0.0002 +/- 0.0005 < 0.0009 -0.0002 +/- 0.0005 < 0.0007 0.0006 +/- 0.0006 < 0.0006 3805 E-04 - 5994 0.071 +/- 0.016 0.0000 +/- 0.0006 < 0.0010 0.0000 +/- 0.0007 < 0.0010 0.0002 +/- 0.0006 < 0.0006 3914 E-08 - 5995 0.080 +/- 0.015 -0.0003 +/- 0.0005 < 0.0011 0.0001 +/- 0.0006 < 0.0010 -0.0009 +/- 0.0006 < 0.0005 3878 E-20 - 5996 o.o71 +/- o.o13V - 0.0001 +/- 0.0003 < 0.0006 Vb .0004 +/- 0.0003' < 0.0006 -0.0003 +/- 0.0003 < 0.0003 3906 4th Quarter E-01 EAP- 7361 0.050 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 0.0000 +/- 0.0004 < 0.0006 0.0000 +/- 0.0004 < 0.0004 3969 E-02 - 7362 0.056 +/- 0.011 -0.0002 +/- 0.0004 < 0.0008 -0.0001 +/- 0.0004 < 0.0006 0.0001 +/- 0.0003 < 0.0003 3934 E-03 - 7363 0.050 +/- 0.014 -0 .0001 +/- 0.0005 < 0.0010 p6.0007 +/- 0.0006 < 0.0011 -0.0001 +/- 0.0005 < 0.0006 3931 E-04 - 7364 0.047 +/- 0.009 0.0002 +/- 0.0003 < 0.0007 0.0000 +/- 0.0004 < 0.0005 ..e.0004 +/- 0.0003 < 0.0003 3969 E-08 - 7365 0.041 +/- 0.010 v'- -0.0001 +/- 0.0003 < 0.0006 -0 .0003 +/- 0.0003 < 0.0004 -0.0003 +/- 0.0004 < 0.0003 3950 E-20 - 7366 0.059 + 0.015 - -0.0002 + 0.0004 < 0.0007 -0.0003 + 0.0005 < 0.0005 -0.0003 + 0.0006 < 0.0003 3948/ Annual Mean+/-s.d. 0.064 +/- 0.011 *0.0001 +/- 0.0002 < 0.0008 0.0000 +/- 0.0003 < 0.0007 0.0000 +/- 0.0004 < 0.0005 2-1
POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dail}' Farm MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 113 EMI- 540 EMI- 966 Sr-89 0.9 +/- 0.9 / < 0.7 0.2 +/- 0.7 < 0.6 0.2 +/- 0.7 < 0.7 5.0
,.,. 0.8 +/- 0.3 /
Sr-90 1.3 +/- 0.4 < 0.6 0.9 +/- 0.3 < 0.4 < 0.5 1.0 1-131 0.05 +/- 0.15 < 0.26 -0.02 +/- 0.10 < 0.19 -0.11 +/- 0.12 < 0.23 0.5 K-40 1294 +/- 103 1438 +/- 51 1394 +/- 97 Cs-134 2.1 +/- 1.7 < 3.8 -0.2 +/- 0.7 < 1.5 -1.1 +/- 1.5 < 3.0 5.0 Cs-137 2.2 +/- 2.1 < 3.9 0.6 +/- 0.8 < 1.7 -0.2 +/- 2.0 < 2.9 5.0 Ba-La-140 -2.7 +/- 1.6 < 4.7 0.5 +/- 0.7 < 3.1 1.3 +/- 1.8 < 4.2 5.0 Other (Co-60) 2.5 +/- 2.2 < 3.2 0.7 +/- 0.9 < 1.5 0.1 +/- 1.8 < 2.4 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD Lab Code EMI- 1465 EMI- 2376 EMI- 2905 Sr-89 0.0 +/- 0.8 < 0.8 -0.3 +/- 0.9 / < 0.8 0.3 +/- 0.8 < 0.7 5.0 Sr-90 0.8 +/- 0.3 / < 0.5 1.0 +/- 0.4 < 0.7 0.7 +/- 0.3 / < 0.5 1.0 1-131 0.19 +/- 0.24 - < 0.46 -0.06 +/- 0.15 < 0.28 -0.02 +/- 0.18 < 0.32 0.5 K-40 1472 +/- 75 1418 +/- 77 1389 +/- 95 Cs-134 0.3 +/- 1.3 < 2.4 0.2 +/- 1.4 < 2.4 -1.1 +/- 1.6 < 2.8 5.0 Cs-137 0.7 +/- 1.4 < 3.0 -0.4 +/- 1.5 < 1.9 0.4 +/- 2.0 < 3.6 5.0 Ba-La-140 -1 .1 +/- 1.3 < 2.2 2.7 +/- 1.2 < 4.5 1.3 +/- 1.7 < 2.6 5.0 Other (Co-60) -1.1 +/- 1.5 < 2.4 1.0 +/- 1.4 < 2.2 0.5 +/- 1.8 < 2.5 15.0 3-1
P01NT BEACH NUCLEAR PLANT I Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E-11 Lambert Dai!Y Farm MDC MDC MDC Required Collection Date o7-08-1o 08-12-15 09-09-15 LLD Lab Code EMI- 3501 EMI- 4449 EMI- 4914 Sr-89 0.1 +/- 0.6 < 0.7 0.3 +/- 0.8 < 0.7 0.3 +/- 0.8 < 0.7 5.0 Sr-90 0.5 +/- 0.3 < 0.5 0.8 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.6 1.0 1-131 0.04+/-0.16 < 0.28 0.04 +/- 0.21 < 0.44 -0.03 +/- 0.11 < 0.20 0.5 K-40 1496 +/- 106 1388 +/- 41 1388 +/- 126 Cs-134 -0.6 :1; 1.6 < 2.9 -0.9 +/- 0.7 <1.4 0.5 +/- 1.8 < 3.8 5.0 Cs-137 2.3 +/- 2.1 < 3.1 0.2 +/- 0.8 < 1.7 2.2 +/- 2.3 < 4.4 5.0 Ba-La-140 -0.3 +/- 1.6 < 1.2 -2.9 +/- 0.6 < 2.8 2.6 +/- 2.1 < 3.8 5.0 Other (Co-60) 3.0 +/- 1.9 < 2.8
- 0.1 +/- 0.8 < 1.0 0.3 +/- 2.4 < 3.3 15.0 Required Collection Date 10-14-15 11-11-15 12-09-15 LLD Lab Code EMI- 5781 EMI- 6482 EMI- 6910
/
{ Sr-89 0.1 +/-0.8 < 0.7 0.5 +/- 0.6 < 0.7 -0.2 +/- 0.8/ < 0.8 5.0
'* Sr-90 1.0 +/- 0.3 < 0.5 0.6 +/- 0.3 < 0.4 0.8 +/- 0.4 < 0.6 1.0 1-131 0.16 +/- 0.19 < 0.32 0.05 +/- 0.11 < 0.20 -0.15 +/- 0.19 < 0.30 0.5 K-40 1250 +/- 109 1376 +/- 42 1366 +/- 105 Cs-134 -0.6 +/- 1.9 < 3.5 0.1 +/- 0.7 < 1.3 0.5 +/- 1.8 < 3.4 5.0 Cs-137 -0.2 +/- -2.2 < 3.8 -0.1 +/- 0.8 < 1.6 0.1 +/- 2.0 < 2.4 5.0 Ba-La-140 0.5 +/- 1.5 < 3.4 -2.5 +/- 0.7 < 2.0 0.3 +/- 1.6 < 3.2 5.0 Other (Co-60) 2.5 +/- 1.8 < 1.8 0.2 +/- 0.9 < 1.5 ' -0.4 +/- 2.0 < 2.2 15.0 I
3-2
POINT BEACH NUCLEAR PLANT
/
Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L) E721 Strutz Dai!Y Farm MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 114 EMI- 541 EMI* 967 Sr-89 0.5 +/- 0.7 < 0.8 0.0 +/- 0.6 < 0.7 0.6 :1: 0.8 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.6 0.2:!; 0.3 < 0.5 0.4 +/- 0.3 < 0.6 1.0 1-131 0.14 +/- 0.15 < 0.25 0.12 +/- 0.20 < 0.40 -0.13 +/- 0.11 < 0.22 0.5 K-40 1458 +/- 101 1426 +/- 76 1479 +/- 92 Cs-134 0.7 +/- 1.6 < 2.9 r2.0 +/- 1.2 < 2.5 0.1 :!: 1.6 < 2.7 5.0 Cs-137 2.0:!; 1.9 < 3.2 0.5 +/- 1.5 < 2.1 0.5 +/- 1.8 < 3.2 5.0 Ba-La-140 2.5 +/- 1.3 < 2.2 . -2.3 +/- 1.4 < 3.8 0.1 +/- 1.6 < 1.8 5.0 Other (Co-60) -0.1 +/- 1.9 < 2.6 -0.2 +/- 1.5 < 2.6 1.9 +/- 2.0 < 2.3 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD Lab Code EMI- 1466 EMI- 2377 EMI- 2906
/ '* Sr-89 0.6 :;1: 0.7 < 0.8 0.4 +/- 0.7 < 0.8 0.2 +/- 0.7 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.1 +/- 0.3 < 0.6 0.2 +/- 0.3 < 0.6 1.0 1-131 0.16 +/- 0.16 < 0.28 0.03 +/- 0.15 < 0.27 0.10 +/- 0.18 < 0.31 0.5 K-40 1360:!: 76 1463 +/- 102 1454;!: 98 Cs-134 1.4 :t 1.3 < 2.5 0.0 +/- 1.6 < 2.8 0.8;!: 1.6 < 3.3 5.0 Cs-137 1.6 +/- 1.5 < 3.0 1.0 +/- 2.1 < 3.0 1.0:!: 2.0 < 2.9 5.0 Ba-La-140 -4.1 +/- 1.3 < 2.1 -3.6 +/- 1.7 < 2.9 -4.3 +/- 1.5 < 2.6 5.0 Other (Co-60) 0.9 +/- 1.6 < .2.5 -0.7 +/- 2.0 < 1.8 -0.5 +/- 2.0 < 2.6 15.0 3-3
POINT BEACH NUCLEAR PLANT
/ Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)
E-21 Strutz Dai!Y Farm MDC MDC MDC Required Collection Date 07-08-15 08-12-15 09-09-15 LLD Lab Code EMI- 3502 EMI- 4450 EMI- 4915 Sr-89 0.3 +/- 0.7 < 0.7 0.6 +/- 0.8 < 0.9 0.3 +/- 0.7 < 0.8 5.0 Sr-90 0.5:!: 0.3 < 0.5 0.4 +/- 0.3 < 0.6 0.2 ;t 0.3 < 0.5 1.0 1-131 0.15 +/- 0.19 < 0.33 0.17 +/- 0.23 < 0.46 0.03+/-0.10 < 0.18 0.5 K-40 1403 +/- 97 1481 +/- 43 1298 +/- 107 Cs-134 0.1 +/- 1.9 < 3.5 -0.2 +/- 0.7 <1.4 0.1 +/- 1:7 < 3.4 5.0 Cs-137 1.9 +/- 1.8 < 3.5 -0.1 +/- 0.8 < 1.2 0.5 +/- 2.4 < 3.5 5.0 Ba-La-140 -0.2 +/- 1.6 < 2.4 -3.4 +/- 0.7 < 4.2 -1.9 +/- 1.8 < 1.7 5.0 Other (Co-60) -1 .6 +/- 2.0 < 2.2 -0.2 +/- 0.9 < 1.8 0.4 +/- 2.4 < 3.3 15.0 Required Collection Date 10-14-15 11-11-15 12-09-15 LLD
/ Lab Code EMI- 5762 EMI- 6483 EMI- 6911 ., -0.3 +/- 0.7 < 0.8 0.2 +/- 0.5 < 0.7 Sr-89 -0.1 :1: 0.6 / < 0.8 5.0 Sr-90 0.4 +/- 0.3 < 0.6 0.1 +/- 0.2 < 0.4 0.2 +/- 0.3 < 0.5 1.0 1-131 0.19 +/- 0.20 < 0.35 -0.01 +/- 0.19 < 0.42 0.18 ;1: 0.18 < 0.31 0.5 K-40 1323 +/- 112 1468 +/- 41 1459 +/- 104 Cs-134 -0.7 +/- 1.9 <* 3.6 -1 .1 +/- 0.7 < 1.2 0.4 +/- 1.8 < 3.7 5.0 Cs-137 -0.2 +/- 2.2 < 3.8 0.0;!: 0.8 < 1.0 0.6 +/- 1.8 < 3.4 5.0 Ba-La-140 -1.2 +/- 1.5 < 3.1 -0.1 +/- 0.7 < 2.9 -1 .0 +/- 1.5 / < 5.2 5.0 Olher (Co-60) -0.4 +/- 2.1 < 3.1 -0.4 +/- 0.8 < 1.2 2.1 :!: 2.1 < 1.9 15.0
( 3-4
POINT BEACH NUCLEAR PLANT
/ Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)
E-40 Barta MDC MDC MDC Required Collection Date 01-14-15 02-11-15 03-11-15 LLD Lab Code EMI- 115 EMI- 542 EMI- 968 sr-89 -0.7:!; 0.6 < 0.6 -0.2 +/- 0.6 < 0.6 0.2 +/- 0.7 < 0.7 5.0 Sr-90 0.7 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.4 0.5 +/- 0.3 < 0.5 1.0 1-131 -0.01 +/- 0.20 < 0.41 0.05 +/- 0..10 < 0.17 0.02 +/- 0.12 < 0.21 0.5 K-40 1329 +/- 77 1471 +/- 76 1421 +/- 81 Cs-134 0.7 +/- 1.3 < 2.2 0.4 +/- 1.3 < 2.6 1.1 +/- 1.5 < 2.4 5.0 Cs-137 -1 .3 +/- 1.4 < 1.7 1.3:!; 1.5 < 2.7 1.6 +/- 1.6 < 2.7 5.0 Ba-La-140 -0.2 +/- 1.1 < 3.6 -1.7 +/- 1.2 < 5.3 -3.1 +/- 1.2 < 0.9 5.0 Other (Co-60) 1.7 +/- 1.7 < 2.9 1.2 +/- 1.5 < 2.5 0.6 +/- 1.8 < 2.5 15.0 Required Collection Date 04-08-15 05-13-15 06-10-15 LLD
/ Lab Code EMI- 1467 EMI- 2378 EMI- 2907 ., -0.2;!: 0.9 < 0.9 -0.8 +/- 0.7 < 0.7 Sr-89 -0.4:!: 0.7 / < 0.7 5.0 Sr-90 0.6 +/- 0.4 < 0.6 0.9;!: 0.3 < 0.5 0.5 :1: 0.3 < 0.5 1.0 1-131 0.15;!; 0.25 < 0.48 -0.06 +/- 0.17 < 0.31 0.14 :I; 0.22 < 0.38 0.5 K-40 1419 +/- 93 1424 +/- 84 1447 +/- 68 Cs-134 0.1 +/- 1.7 < 3.0 -0.6 +/- 1.4 < 2.9 -1 .0 +/- 1.2 < 2.3 5.0 Cs-137 0.8;!; 1.8 < 3.2 1.8 +/- 1.6 < 2.9 0.1 +/- 1.3 < 2.3 5.0 Ba-La-140 0.5 +/- 1.6 < 4.1 0.6;!: 1.2 < 2.4 0.2 :1: 1.0 < 2.8 5.0 Other (Co-60) -1.1 ;!; 1.9 < 3.0 -0.2;!; 1.7 < 2.9 0.1 +/- 1.3 < 2.3 15.0
( 3-5
POINT BEACH NUCLEAR PLANT ~ Table 3. Radioactivity in milk samples Collection : Monthly Sample Description and Concentration (pCi/L) E-40 Barta MDC MDC MD C Required Collection Date 07-08-15 08-12-15 09-09-15 LLD Lab Code EMI- 3503 EMI- 4451 EMI- 4916 Sr-89 -0.1 +/- 0.6 < 0.6 -0.8 +/- 0.8 < 0.8 0.3 +/- 0.9 < 0.9 5.0 Sr-90 0.4 +/- 0.3 < 0.4 0.6 +/- 0.4 < 0.6 0.4 +/- 0.4 < 0.7 1.0 1-131 0.07 +/- 0.13 < 0.19 0.08 +/- 0.13 < 0.22 -0.13 +/- 0.21 < 0.39 0.5 K-40 1360 +/- 104 1445 +/- 39 1383 +/- 112 Cs-134 0.2 +/- 1.8 < 3.7 -0.4 +/- 0.7 < 1.2 0.5 +/- 1.8 < 3.8 5.0 Cs-137 -1 .0 +/- 2.1 < 2.9 0.6 +/- 0.8 < 1.5 -0.1 +/- 2.6 < 3.8 5.0 Ba-La-140 -0.1 +/- 1.7 < 2.1 -0.9 +/- 0.6 < 2.1 -1 .9 +/- 2.1 < 2.3 5.0 Other (Co-60) -1.1 +/- 2.2 < 1.8 -0.5 +/- 0.8 < 0.8 0.8 +/- 2.4 < 3.1 15.0 Required Collection Date 10-14-15 11 15 12-09-15 LLD Lab Code EM I- 5783 EMI- 6484 EMI- 6912 Sr-89 -0.1 +/- 0.6 < 0.1 0.0 +/- 0.6 < 0.9 -0.2 +/- 0.6 < 0.6 5.0 Sr-90 0.6 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.4 1.0 1-131 0.07+/-0.13 < 0.23 0.14 +/- 0.18 < 0.31 -0.07 +/- 0.16 < 0.30 0.5 K-40 1431 +/- 99 1384 +/- 82 1486 +/- 96 Cs-134 -1.4 +/- 1.8 < 3.4 0.6 +/- 1.3 < 2.5 -0.4 +/- 1.6 < 3.1 5.0 Cs-137 -0.6 +/- 1.9 < 3.0 1.2 +/- 1.4 < 2.2 0.7 +/- 1.9 < 3.5 5.0 Ba-La-140 -1 .8 +/- 1.6 < 3.0 -0.6 +/- 1.2 < 4.6 1.9 +/- 1.4 < 2.1 5.0 Other (Co-60) 1.0 +/- 1.9 < 2.4 0.3 +/- 1.5 < 1.7 0.2 +/- 1.8 < 2.9 15.0 Sr-89 An nual Mean + s.d. 0.1 +/- 0.4 Sr-90 Annual Mean + s.d. 0.6 +/- 0.3 1-131 Annual Mean+ s.d. 0.05 +/- 0. 10 K-40 Annual Mean+ s.d. 1409 +/- 60 Cs-134 Annual Mean+ s.d. 0.0 +/- 0.8 Cs-137 Annual Mean + s.d. 0.6 +/- 0.9 Ba-La Annual Mean + s.d. -0.8 +/- 1.9 Co-60 Annual Mean+ s.d. 0.4 +/- 1.1 3-6
POINT BEACH NUCLEAR PLANT
/ Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly
' Units: pCi/L 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean +/-s.d Collection Date 01-15-15 04-15-15 07-09-15 10-07-15 Lab Code EWW- 140 EWW- 1664 EWW- 3618 EWW- 5625 Gross Beta 2.9 +/- 1.7 0.2 +/- 0.9 2.4 +/- 1.9 0.7 +/- 1.0 4.0 1.6 +/- 1.3 H-3 103.9 +/- 99.7 57.5 :t 78.4 -52.0 +/- 91.1 -49.2 +/- 70.8 500 15.1 +/- 78.1 Sr-89 0.0 +/- 0.6 -1.5 +/- 0.7 0.2 +/- 0.3 0.2 :1:0.3 5.0 -0.3 +/- 0.8 Sr-90 0.0 +/- 0.2 0.9 +/- 0.3 -0.1 +/- 0.2 -0.1 +/- 0.2 1.0 0.2 +/- 0.5 1-131 0.07 +/- 0.13 -0.03 +/- 0.13 0.22 +/- 0.24 0.08 :t 0.13 0.5 0.09 +/- 0.10 Mn-54 -0.4 +/- 1.3 -0.3 +/- 1.5 1.2 +/- 2.1 -0.7 +/- 1.7 10 0.0 +/- 0.9 Fe-59 0.1 +/- 2.4 -2.9 +/- 2.9 1.4 +/- 3.8 -0.7 +/- 3.5 30 -0.5 +/- 1.8 Co-58 -1.3 +/- 1.3 0.3 +/- 1.5 -1.0+/-2.1 1.0 +/- 1.5 10 -0.2 +/- 1.1 Co-60 -0.7 +/- 1.4 -0.4 +/- 1.6 1.6 +/- 2.0 0.4 +/- 1.5 10 0.2 +/- 1.0 Zn-65 0.2 +/- 2.6 0.3 +/- 3.2 -7.5 +/- 4.5 -4.0 +/- 3.4 30 -2.8 +/- 3.7 Zr-Nb-95 -0.6 +/- 1.6 -2.6 +/- 1.7 -3.3 +/- 2.3 -0.8 +/- 1.8 15 -1.8 +/- 1.3 Cs-134 0.5 +/- 1.4 1.0 +/- 1.4 -1.0 +/- 1.9 0.2 +/- 1.7 10 0.2 +/- 0.8 Cs-137 -0.2 +/- 1.6 1.8 +/- 1.8 0.5 +/- 2.5 0.2 +/- Hl 10 0.6 +/- 0.9 Ba-La-140 1.2 +/- 1.6 -1.4 +/- 2.0 0.2 +/- 3.2 3.1 +/- 1.7 15 0.8 +/- 1.9
/
Other (R!J-103) 1.2 +/- 1.4 -0.8 +/- 1.4 -1.2 +/- 2.4 0.1 +/- 2.0 30 -0.2 +/- 1.1 MDC Data Collection Date 01-15-15 04-15-15 07-09-15 10-07-15 Lab Code EWW- 140 EWW- 1664 EWW- 3618 EWW- 5625 Gross Beta < 2.8 < 1.7 < 3.6 < 2.0 4.0 < 2.5 H-3 < 187.6 <151.9 < 153.9 < 148.7 500 < 160.5 Sr-89 < 0.8 < 0.6 < 0.5 < 0.4 5.0 < 0.6 Sr-90 < 0.5 < 0.5 < 0.4 < 0.5 1.0 < 0.5 1-131 < 0.22 < 0.23 < 0.45 < 0.22 0.5 <0.28 Mn-54 < 2.6 < 2.8 < 3.4 < 3.1 10 < 2.9 Fe-59 < 4.4 < 4.2 < 6.2 < 6.4 30 < 5.3 Co-58 < 1.7 < 2.6 < 2.5 < 2.0 10 < 2.2 Co-60 < 1.2 < 2.2 < 2.7 < 2.6 10 < 2.2 Zn-65 < 4.3 < 5.5 < 5.2 < 3.2 30 <4.6 Zr-Nb-95 < 3.6 < 2.5 < 5.1 < 3.7 15 < .3.7 Cs-134 < 2.7 < 2.7 < 4.2 < 3.6 10 < 3.3 Cs-137 < 2.3 < 3.1 < 4.2 < 3.5 10 < 3.3 Ba-La-140 < 6.1 < 3.5 < 4.2 < 4.2 15 <4.5 O~her (Ru-1 03) < 3.7 < 3.3 < 4.7 < 3.8 30 < 3.9 .,I 4-1
POINT BEACH Table 5. L,ake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-01 (Meteorological Tower) r-* Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 136 NSa ELW- 988 ELW- 1660 Date Collected 01-15-15 02-15-15 03-11-15 04-16-15 Req.LLD Gross beta 2.2 +/- 0.8 < 1.3 3.5 +/- 1.1 < 1.8 2.4 +/- 0.7 < 0.9 4.0 1-131 0.05 +/- 0.13 < 0,23 -0.04 +/- 0.22 < 0.49 -0.07 +/- 0.12 < 0.22 0.5 Be-7 4.2 +/- 15.8 < 32.8 7.9 +/- 13.3 < 32.6 -4.4 +/- 14.8 < 20.6 Mn-54 0.1 +/- 1.4 < 2.5 0.4 +/- 1.2 < 2.5 -0.5 +/- 1.5 < 2.2 10 Fe-59 0.9 +/- 3.0 < 5.0 0.1 +/- 2.7 < 2.7 -4.2 +/- 3.3 < 2.7 30 Co-58 0.1 +/- 1.4 < 1.9 0.3 +/- 1.3 < 2.4 0.2 +/- 1.4 < 2.5 10 Co-60 0.8 +/- 1.6 < 2.3 1.0 +/- 1.3 < 1.7 -1 .2 +/- 1.7 < 1.7 10 Zn-65 -2.3 +/- 3.2 < 3.3 -1.6 +/- 2.7 < 3.9 -1.9 +/- 4.3 < 6.9 30 Zr-Nb-95 -0.5 +/- 1.4 < 3.2 -0.2 ;!: 1.4 < 3.5 1.8 +/- 1.6 < 3.0 15 Cs-134 0.4 +/- 1.6 < 3.1 0.1 +/- 1.2 < 2.5 .0.6 +/- 1.6 < 3.1 10 Cs-137 -1.9 ;t 1.8 < 1.6 0.1 +/- 1.6 < 2.6 0.4 +/- 1.9 < 3.6 10 Ba-La-140 -2.5 +/- 2.1 < 6.3 -4.3 +/- 1.5 < 5.7 0.4 +/- 2.0 < 4.3 15 Other (Ru-1 03) -1.7 +/- 1.8 < 3.0 -0.3 +/- 1.5 < 3.8 -0.9 +/- 1.7 < 2.6 30 Lab Code ELW- 2422 ELW- 2935 ELW- 3614 E;:LW- 4480 Date Collected 05-14-15 06-11 -15 07-09-15 08-13-15 Req. LLD Gross beta 1.1 +/- 0.5 .:: 0.8 1.0 +/- 0.5 < 0.9 1.2 +/- 0.9 < 1.6 1.1 +/- 0.5 < 0.9 4.0 1-131 -0.07 +/- 0.13 < 0.24 0.15 +/- 0.19 < 0.35 -0.05 +/- 0.16 < 0.29 0.03 +/- 0.15 < 0.26 0.5 Be-7 -1.7+/-5.9 < 13.1 -5.7 +/- 20.1 < 33.7 -9.5 +/- 12.2 < 29.5 -11 .0 +/- 19.0 < 30.5 Mn-54 -0.1 +/- 0.6 < 0.9 1.3 +/- 2.0 < 4.0 -1.0 +/- 1.6 < 1.6 -0.9 +/- 2.0 < 3.0 10 Fe-59 -0.4 +/- 1.2 < 2.8 -2.6 +/- 4.1 < 5.0 -2.2 +/- 3.3 < 4.2 -3.5 +/- 3.7 < 3.3 30 Co-58 -0.7 +/- 0.6 < 0.8 -0.4 +/- 2.0 < 3.1 1.0 +/- 1.7 < 2.9 -1.0 +/- 1.9 < 2.5 10 Co-60 -0.5 +/- 0.6 < 1.2 -2.1 +/-1.9 < 1.7 0.6 +/- 1.7 < 1.5 2.1 +/- 2.2 < 3.8 10 I Zn-65 0.1 +/- 1.2 < 2.0 -0.2 +/- 4.3 < 6.8 0.1 ;!: 3.1 < 4.8 -1,6 +/- 4.8 < 4.0 30
' Zr-Nb-95 0.0 +/- 0.6 <1.4 2.4 +/- 2.0 < 3.3 2.9 +/- 1.6 < 3.9 -0.7 +/- 1.9 < 3.3 15 Cs-134 -0.2 +/- 0.7 <1.4 0.9 +/- 2.0 < 4.2 -1 .2 +/- 1.6 < 2.7 0.7 +/- 2 .1 < 4.3 10 Cs-137 0.2 +/- 0.7 < 1.3 -0.5 +/- 2.4 < 3.5 0.1 +/- 1.8 < 2.7 0.5 +/- 2.0 < 3.5 10 Ba-La-140 0.0 +/- 0.7 < 3.3 0.9 +/- 3.1 < 4.5 0.9 +/- 1.8 < 5.7 0.8 +/- 2.1 < 3.6 15 Other (Ru-1 03) -0.2 +/- 0.7 <1.4 1.1 +/- 2.1 < 4.3 0.4 +/- 1.5 < 3.4 -0.4 +/- 2.1 < 4.4 30 Lab Code ELW- 5108 ELW- 5784 ELW- 6353 E~W- 6938 Date Collected 09-16-15 10-14-15 11-05-15 12-10-15 Req.LLD Gross beta 0.5 +/- 0.5 < 0.9 1.3 +/- 0.6 < 0.9 1.6 +/- 1.0 < 1.8 1.8 +/- 0.6 < 0.9 4.0 1-131 0.02 +/- 0.14 < 0.25 0.03 +/-0.17 < 0.30 0.02 +/- 0.13 < 0.23 0.03 +/- 0.15 < 0.27 0.5 Be-7 -4.5 +/- 18.8 < 44.6 4.1 +/- 17.9 < 37.5 2.4 +/- 4.8 < 15.1 2.9 +/- 10.8 < 23.6 Mn-54 -0.2 +/- 2.5 < 4.6 -0.6 +/- 1.4 < 2.0 0.2 +/- 0.6 < 0.9 -0.3 +/- 1.4 < 2.7 10 Fe-59 4.4 +/- 4.2 < 5.6 -3.4 +/- 3.3 < 4 .8 -0.7 +/- 1.0 < 2.7 1.1 +/- 2.3 < 5.0 30 Co-58 -3.5 +/- 2.2 < 2.6 0.5 +/- 1.7 < 3.3 0.3 +/- 0.5 < 1.1 0.8 +/- 1.2 < 2.3 10 Co-60 1.0 +/- 2.7 < 4.4 -0.9 +/- 2.0 < 1.5 -0.4 +/- 0.6 < 1.0 -1.6 +/- 1.6 / < 1.5 10 Zn-65 1.1 +/- 5.0 < 3.8 0.5 +/- 3.6 < 2.7 -1.3 +/- 1.1 < 1.7 3.4 +/- 2.9 < 3.1 30 Zr-Nb-95 -0.1 +/- 2.6 < 6.6 -2.3 +/- 1.6 < 2.1 0.5 +/- 0.6 < 1.7 -0.5 +/- 1.3 < 2.1 15 Cs-134 -3.2 +/- 2.6 < 4.4 -1.1 +/- 1,7 < 3.3 -0.1 ;!: 0.6 < 1.1 0.5 +/- 1.3 < 2.3 10 1.2 +/- 2.9 < 4.1 0.2+/-1.7 < 2.6 0.5 +/- 0.7 < 1.3 0.1 +/- 1.6 < 2.7 10 Cs-137 Ba-La.140 1.8 +/- 2.4 < 14.4 0.4+/-1.7 < 7.8 -1 .3 :t 0.6 < 1.7 1.6 +/- 1.4
/ < 2.8 15 Other (Ru-103) -0.1 +/- 2.2 < 5.1 0.6 +/- 1.8 < 4.0 -0.4 +/- 0.6 < 1.3 0.3 +/- 1.2 < 2.5 30
""NS'; =No sample; see Table*2.0, Listing of Missed Samples.
(
\ ,
5-1
POINT BEACH Table 5. Lake water, analyses for gross bela, iodine-131 and gamma emitting isotopes. Location: E-05 (Two Creeks Park) Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 137 NS" ELW- 989 ELW- 1661 Dale Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req. LLD Gross beta 2.5 +/- 0.8 < 1.2 3.4 +/- 1.0 < 1.6 1.7 +/- 0.6 < 0.9 4.0 1-131 0.07 +/- 0.13 < 0.22 0.03 +/- 0.14 < 0.26 0.07 +/- 0.22 < 0.45 0.5 Be-7 7.0 +/- 11.3 < 22.8 13.1 +/- 15.5 < 35.8 -9.8 +/- 17.3 < 32.8 Mn-54 -1 .0 +/- 1.2 < 1.6 -0.1 +/- 1.6 < 2.2 0.1 +/- 1.6 < 2.6 10 Fe-59 -2.3 +/- 2.7 < 2.8 -2.7 +/- 3.4 < 3.3 -1 .6 +/- 3.2 < 4.3 30 Co-58 0.9 +/- 1.2 < 2.3 0.8 +/- 1.5 < 3.3 -0.9 +/- 1.5 < 1.9 10 Co-60 0.7 +/- 1.5 < 1.9 0.7 +/- 1.1 < 0.8 -0.1 +/- 1.2 < 2.1 10 Zn-65 -0.7 +/- 2.3 < 2.1 -1 .1 +/-3.3 < 4.2 -1 .5 +/- 4.4 < 5.1 30 Zr-Nb-95 -1.9 +/- 1.4 < 1.9 -0.3 +/- 1.7 < 4.4 0.1 +/- 1.9 < 4.7 15 Cs-134 -0.7 +/- 1.3 < 2.4 1.1 +/- 1.7 < 3.5 1.0 +/- 1.6 < 2.8 10 Cs-137 0.5 +/- 1.4 < 2.6 0.0 +/- 1.9 < 2.1 -0.2 +/- 2.0 < 2.3 10 Ba-La-140 1.3 +/- 1.4 < 2.8 1.9 +/- 2.0 < 6.2 0.8 +/- 1.6 < 3.0 15 Other (Ru-103) 1.2 +/- 1.3 < 3.4 1.0 +/- 1.8 < 3.5 1.9 +/- 1.8 < 3.8 30 Lab Code ELW- 2423 ELW- 2936 ELW- 3615 ELW- 4481 Date Collected 05-14-15 06-11-15 07-09-15 08 15 Req. LLD Gross beta 1.0 +/- 0.5 < 0.8 0.8 +/- 0.5 < 0.8 1.1 +/- 0.9 < 1.7 0.8 +/- 0.5 < 0.8 4.0 1-131 -0.02 +/- 0.12 < 0.22 0.00 +/- 0.20 < 0.43 0.00 +/- Q.15 < 0,27 0.03 +/- 0.14 < 0.25 0.5 Be-7 -4.2 +/- 6.0 < 11.8 -7.3 +/- 23.6 < 38.5 -13.5 +/- 14.7 < 18.2 4 .8 +/- 10.6 < 18.6 Mn-54 0.7 +/- 0.6 < 1.3 -1 .1 +/- 2.2 < 2.7 0.5 +/- 1.5 < 1.9 0.2 +/- 1.4 < 2.1 10 Fe-59 -0.1 +/- 1.3 < 3.2 -1 .1 +/- 4.9 <; 5.7 2.1 +/- 3.0 < 3.9 0.4 +/- 2.4 < 5.2 30 Co-58 -0.5 +/- 0.6 < 1.0 0.5 +/- 2.1 < 3.9 0.4 +/- 1.4 < 2.3 0.7 +/- 1.4 < 2.4 10
/ Co-60 -0.3 +/- 0.7 < 1.2 -1 .6 +/- 2.4 < 2.8 -0.4 +/- 1.6 < 1.4 -0.4 +/- 1.6 < 2.3 10 Zn-65 -0.4 +/- 1.3 < 2.0 -11. 1 +/- 6.1 < 6.8 -4.8 +/- 3.7 < 2.7 -0.5 +/- 2.7 < 5.9 30 Zr-Nb-95 -0.4 +/- 0.6 < 2.0 -2.8 +/- 2.8 < 3.3 -1.4 +/- 1.6 < 2.5 -1.0 +/- 1.5 < 2.9 15 Cs-134 -0.4 +/- 0.6 < 1.3 -3.1 +/- 2..4 < 4.5 -1.1 +/- 1.6 < 3.3 -0.9 +/- 1.5 < 2.8 10 Cs-137 0.5 +/- 0.7 < 1.6 1.0 +/- 2..1 < 4.0 0.9 +/- 1.9 < 3.3 -0.5 +/- 1.5 < 1.9 10 Ba-La-140 -6.6 +/- 0.8 < 2.2 -3.2 +/- 2.7 < 2.2 -0.7 +/- 2.0 < 9.5 -3.4 +/- 1.6 < 4.6 15 Other (Ru-103) -1.3 +/- 0.7 < 1.0 -1.3 +/- 2.3 < 3.0 -0,9 +/- 1.9 < 3.9 -0.3 +/- 1.4 < 3.2 30 Lab Code ELW- 5109 ELW- 5785 ELW- 6354 ELW- 6939 Date Collected 09-16-15 10-14-15 11-05-15 12-10-15 Req.LLO Gross bela 0.6 +/- 0.5 < 0.8 1.2 +/- 0.5 < 0.8 2.2 +/- 0.9 *< 1.6 1.3+/-0.5/ < 0.8 4.0 1-131 -0.03 +/- 0.15 < 0.27 0.11 +/- 0.22 < 0.41 -0.01 +/- 0.22 < 0.45 -0.02 +/- 0.15 < 0.27 0.5 Be-7 7.6 +/- 18.0 < 45.9 10.1 +/- 16.3 < 43.1 -8.2 +/- 14.8 < 26.6 17.8 +/- 11 .7 < 29.8 Mn-54 -0.1+/-1 .8 < 2.8 0.5 +/- 1.5 < 2.9 0.7 +/- 1.4 < 2.4 -0.1 +/- 1.3 < 1.5. 10 Fe-59 -0.7 +/- 3.5 < 6.6 0.4 +/- 2.8 < 4.3 0.5 +/- 3.0 < 5.2 1.7 +/- 2.5 < 3.8 30 Co-58 0.0 +/- 1.6 < 3.0 -0.2 +/- 1.4 < 2.3 -0.6 +/- 1.6 < 2.2 0.2 +/- 1.6 < 1.7 10 Co-60 1.0 +/- 1.8 < 2.3 -0.6 +/- 1.8 < 1.8 -0.1 +/- 1.7 < 1.9 1.0 +/- 1.4/ < 2.6 10 Zn-65 -5.2 +/- 4.3 < 3.6 2.0 +/- 2..6 < 4.1 -2.6 +/- 3.1 < 3.0 2.2 +/- 2.7 < 4.7 30 Zr-Nb-95 -1.3 +/-1.6 < 3.8 0.4 +/- 1.6 < 4.6 -0.1 +/- 1.4 < 3.4 0.3 +/- 1.4 < 3.0 15 Cs-134 1.9 +/- 1.7 < 3.5 -1 .0 +/-*1.7 < 3.3 -0.3 +/- 1.4 < 2.7 0.8 +/- 1.4 < 2.6 10 Cs-137 -1.3 +/- 2.0 < 3,1 -0.1 +/- 2.0 < 3.0 0.4 +/- 1.7 < 2.8 0.7 +/- 1,5 < 1.9 10 Ba-La-140 1.3 +/- 2.3 < 13.0 -3.6 +/- 1.8 < 11.0 1.4 +/- 1.3 < 7.6 1.0 +/- 1.5 I < 2.9 15 Other (Ru-103) 0.3 +/- 1.9 < 4.7 0.7 +/- 1.7 < 4.6 0.5 +/- 1.7 < 3.8 0.0 +/- 1.3 < 2.5 30
* "NS." =No sample; see Table 2.0, listing of Missed Samples.
I i
!i-?
POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. Location: E-06 (Coast Guard Station)
/ Collection: Monthly composites Units: pCi/L
[\ MDC MDC MDC MDC 8 Lab Code ELW- 138 NS ELW- 990 ELW- 1662 Date Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req . LLD Gross beta 4 .0 +/- 0.9 < 1.3 4.4 +/- 1.1 < 1.8 2.0 +/- 0.6 < 0.9 4.0 1-131 0.02 +/- 0.20 < 0.39 0.06 +/- 0.24 < 0.49 0.15 +/- 0.25 < 0.50 0.5 Be-7 -1 .7 +/- 10.8 < 24.6 9.8 +/- 9.3 < 19.1 1.8 +/- 15.0 < 27.2 Mn-54 0.7 +/- 1.1 < 2.1 0.9 +/- 1.2 < 2.6 0.6 +/- 1.5 < 2.9 10 Fe-59 1.7 +/- 2.1 < 3.4 -1.9 +/- 2.1 < 3.5 -0.3 +/- 2.9 < 4.3 30 Co-58 1.2 +/- 1.2 < 2.4 -0.5 +/- 1.1 < 1.7 1.1 +/- 1.3 < 3.0 10 Co-60 0.7 t 1.5 < 2.3 -0.8 +/- 1.1 < 1.1 1.2 +/- 1.6 < 2.5 10 Zn-65 -0.8 +/- 2.4 < 2.4 -1.3 +/- 2 .5 < 4.3 1.0 :t: 2.9 < 3.7 30 Zr-Nb-95 0.5 +/- 1.4 < 2.9 0.1 +/- 1.2 < 2.9 -0.4 +/- 1.3 < 2.5 15 Cs-134 0.1 +/- 1.3 < 2.5 -0.3 +/- 1.2 < 2.2 0.4 +/- 1.4 < 2.7 10 Cs-137 0.8 +/- 1.5 < 2.5 -0.2 +/- 1.5 < 2.6 0.3 +/- 1.6 < 2.9 10 Ba-La-140 -3.7 +/- 1.2 < 1.7 0.8 +/- 1.4 < 4.3 -3.3 +/- 1.7 < 3.6 15 Other (Ru-103) 0.3 +/- 1.1 < 2.9 0.3 +/- 1.0 < 2.5 0.1 +/- 1.6 < 2.2 30 Lab Code ELW- 2424 ELW- 2937 ELW- 3616 ELW- 4482 Date Collected 05-14-15 06-11-15 07-09-15 08-13-15 Req. LLD Gross beta 0.4 +/- 0.5 < 0.9 1.3 +/- 0.6 < 0.9 1.1 +/- 0.9 < 1.7 0.8 +/- 0.5 < 0.9 4.0 1-131 -0.07 +/- 0.11 . < 0.21 0.01 +/- 0.13 < 0.23 0.14 +/- 0.17 < 0.30 -0.03 +/- 0.15 < 0.26 0.5 Be-7 0.3 +/- 4.9 < 14.7 12.0 +/- 18.5 < 37.2 -0.2 +/- 17.0 < 34.3 -10.0 +/- 14.6 < 37.5 Mn-54 0.0 +/- 0.6 < 1.2 0.5 +/- 1.4 < 2.3 -0.1 +/- 1.8 < 1.9 1.5 +/- 1.7 < 2.8 10 Fe-59 0.9 +/- 1.1 < 2.9 1.6 +/- 3.3 < 3.3 0.2 +/- 4.2 < 8.1 0.5 +/- 2.9 < 4.9 30 Co-58 0.4 +/- 0.6 < 1.5 0.2 +/- 2.1 < 4.5 -2.3 +/- 1.9 < 2.0 1.7 +/- 1.7 < 3.2 10
/ ' Co-60 0.1 +/- 0.6 < 0.6 1.4 ;!: 1.8 < 2.4 0.9 +/- 2.3 < 3.4 -1.1 +/- 1.8 <1.4 10 Zn-65 0.4 +/- 1.1 < 2.6 1.3 +/- 4.2 < 6.5 -0.2 +/- 4.3 < 1.8 0.2 +/- 2.9 < 2.9 30
' Zr-Nb-95 -0.4 +/- 0.6 < 1.8 -1.2 +/- 1.7 < 2.5 1.9 +/- 2.1 < 4.9 0.1 +/- 1.7 < 3.3 15 Cs-134 -0. 1 +/- 0.6 < 1.2 0.8 +/- 1.6 < 3.4 3.1 ;!: 2.0 < 3.8 -0.9 +/- 1.9 < 3.8 10 Cs-137 0.3 +/- 0.7 < 1.4 0,6 t 2.1 < 4.0 1.5 +/- 1.9 < 3.6 -0.1 +/- 1.9 < 2.9 10 Ba-La-140 -2.3 +/- 0.6 < 4.6 0.7 +/- 2.1 < 2.2 -3.6 +/- 2.2 < 6.9 -2.0 +/- 1.7 < 4.0 15 Other (Ru-1 03) 0.2 +/- 0.6 < 1.5 -2.0 +/- 2.1 < 3.1 -1.0 :!: 2.2 < 3.8 -1 .0 +/- 1.6 < 2.9 30 Lab Code ELW- 5110 ELW- 5786 ELW- 6355 ELW- 6940 Date Collected 09-16-15 10-14-15 11 15 12-10-15 Req. l-LD Gross beta 1.1 +/- 0.5 < 0.9 0.7 +/- 0.5 < 0.9 2.4 +/- 1.0 < 1.8 1.7 +/- 0.6 < 0.9 4.0 1-131 0.12 +/- 0.14 < 0.24 -0.03 +/- 0.23 < 0.41 0.17 +/- 0.26 < 0.49 -0.02 :1: 0.16 < 0.29 0.5
/
Be-7 1.7 +/- 9.3 < 26.6 -14.1 +/- 16.7 < 30.4 -3.3 +/- 5.9 < 11 .2 7.6 +/- 10.8 < 20.8 Mn-54 1.3 +/- 1.1 < 2.5 -1.8 +/- 1.7 < 2.8 0.5 +/- 0.6 < 1.3 0.5:!: 1.3 < 2.3 10 Fe-59 -1.3+/-2.1 < 5.1 -0.6 +/- 3.0 < 6.2 1.1 +/- 1.1 < 3.0 -3.4 +/- 2.8 < 5.2 30 Co-58 0.4 +/- 1.1 < 3.1 -0.8 +/- 1.8 < 3.6 0.4 +/- 0.6 <1.4 -0.8 +/- 1.2 < 1.5 10 Co-60 0.2 +/- 1.2 < 1.f;l -0.7 ;!; 1.5 < 1.6 0.1 +/- 0.7 < 1.0 -0.1 +/- 1.4 / < 2.0 10 Zn-65 -2.0 +/- 2.6 < 1.9 2.9 +/- 3.7 < 4.4 0.7 +/- 1.2 < 1.8 3.8 +/- 2.7 < 3.4 30 Zr-Nb-95 -0.7 +/- 1.1 < 3.9 1.6 +/- 1.7 < 5.4 0.1 +/- 0.6 < 1.6 0.3 +/- 1.5 < 2.6 15 Cs-134 -0.2 +/- 1.1 < 2.1 1.3 +/- 1.7 < 3.2 -0.4 +/- 0.6 < 1.3 0.4 +/- 1.3 < 2.3 10 Cs-137 -0.8 +/- 1.3 < 1.8 0.4 +/- 2.2 < 2.5 0.0 +/- 0.7 < 1.2 0.3 +/- 1.5 < 2.6 10 Ba-La-140 -2.3 +/- 1.3 < 10.3 1.1 +/- 1.9 < 6.8 -1 .0 +/- 0.7 < 5.0 0.8 +/- 1.9 < 2.6 15 Other (Ru-103) 0.0 +/- 1.1 < 3.7 -1.6 +/- 1.9 < 2.8 -0.2 +/- 0.7 < 1.9 -0.8 +/- 1.2 < 2.2 30
* "NS" = No sample; see Table 2.0, Listing of Missed Samples.
( 5-3
POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes. location: E-33 (Kewaunee)
/ Collection: Monthly composites Units: pCi/1,.
\
MDC MDC MDC MDC Lab Code ELW- 139 NS" ElW- 991 ELW- 1663 Date Collected 01-15-15 02-15-15 03-12-15 04-16-15 Req. LLD Gross beta 3.2 +/- 0.8 < 1.1 2.4 +/- 1.0 < 1.8 1.0 +/- 0.5 < 0.8 4.0 1-131 -0.01 +/- 0.16 < 0.29 0.02 +/- 0.13 < 0.23 -0.15 +/- 0.21 < 0.48 0.5 Be-7 -3.0 +/- 8.0 < 13.3 -3.2 +/- 8.9 < 20.4 -8.6 +/- 14.3 < 29.1 Mn-54 -0.8 :t 1.0 < 1.5 0.5 +/- 1.0 < 2.1 -0.5 +/- 1.4 < 2.0 10 Fe-59 2.4 +/- 1.7 < 3.8 -0.8 +/- 1.8 < 2.3 -1.5 +/- 3.0 < 4.2 30 Co-58 -0.5 +/- 1.0 < 1.8 0.6 +/- 1.0 < 2.3 0.1 +/- 1.5 < 2.0 10 Co-60 -0.1 +/- 0.9 < 1.1 -0.5 +/- 1.1 < 1.1 -1.3 +/- 1.8 < 1.6 10 Zn-65 -0.(3 +/- 1.5 < 2.3 0.1 +/- 2.1 < 1.8 2.7 +/- 3.2 <2.4 30 Zr-Nb-95 -0.1 +/- 1.1 < 2.5 0.5 +/- 1.2 < 3.3 -2.6 +/- 1.7 < 2.3 15 Cs-134 0.0 +/- 1.0 < 1.9 1.2 +/- 1.1 < 2.0 -1 .2 ;!: 1.4 < 3.0 10 Cs-137 -0.6 +/- 1.2 < 1.8 0.2 +/- 1.3 < 2.4 0.6 +/- 1.8 < 3.3 10 Ba-La-140 -0.9 +/- 1.1 < 3.8 1.5 +/- 1.1 < 2.8 2.9 :t 1.5 < 2.5 15 Other (Ru-1 03) 0.2 +/- 0.9 <( 2.2 -0.9 +/- 1.1 < 2.4 -0.6 +/- 1.8 < 2.1* 30 Lab Code ELW- 2425 ELW- 2938 ELW- 3617 ELW- 4483 Date ~ollected 05-14-15 06-11-15 07-()9-15 08-13-15 Req. LLD Gross beta 2.1 +/- 1.0 < 1.8 1.0 +/- 0.5 < 0.8 1.6 +/- 0.9 < 1.6 0.9 +/- 0.5 < 0.8 4.0 1-131 -0.03 +/- 0.12 < 0.23 -0.04 +/- 0.11 < 0.21 -0.01 +/- 0.20 < 0.37 0.01 +/- 0.16 < 0.29 0.5 Be-7 -4.0 +/- 4.9 < 11.0 2.8 +/- 10.7 < 24.9 4.3 +/- 13.9 < 36.1 9.2 +/- 11 .1 < 30.0 Mn-54 0.1 +/-. 0.6 < 1.2 0.6 +/- 1.0 < 1.7 0.0 +/- 1.5 < 2.6 0.4 +/- 1.5 < 2.9 10 Fe-59 -1 .1 +/- 1.0 < 2.8 0.3 +/- 2.1 < 2.5 -0.7 +/- 2.5 < 4.0 -0.3 +/- 2.7 < 5.3 30 Co-58 -0.2 +/- 0.5 < 1.3 -0.3 +/- 0.9 < 1.3 0.3 +/- 1,5 < 3.5 -1.0 +/- 1.2 < 1.7 10 Co-60 0.3 +/- 0.6 < 1.2 -0.3 +/- 1.1 < 2.0 -0.2 +/- 1.5 < 1.8 -0.2 +/- 1.6 < 1.8 10 I' Zn-65 0.7 +/- 1.1 < 2.5 -1.1+/-2..4 < 3.5 -0.2 +/- 2.6 < 2.9 -0.2 +/- 2.4 < 3.1 30
\. Zr-Nb-95 -0.2 +/- 0.6 < 1.7 0.6 +/- 1.1 < 2.4 -2.4 +/- 1.6 < 2.7 2.2 +/- 1.3 < 3.7 15 Cs-134 -0.1 +/- 0.6 < 1.1 -0.2 +/- 1.1 < 2.2 -0.8 +/- 1.7 < 2.9 0.8 +/- 1.6 < 3.0 10 Cs-137 0.6 +/- 0.7 < 1.2 -0.4 +/- 1.3 < 1..5 0.4 +/- 1.9 < 2 .8 0.2 +/- 1.7 < 2.5 10 Ba-La-140 -2.3 +/- 0.7 < 2.4 -3.2 +/- 1.3 < 1.8 -1 .0 +/- 1.7 < 6.5 -1.4 +/- 1.7 < 7.6 15 Other (Ru-103) -0.9 +/- 0.5 < 1.9 -1.3 +/- 1.3 < 2.1 -0.4 +/- 1.5 < 3.0 0.2 +/- 1.3 < 3.2 30 Lab Code ELW-5111 ~LW- 5767 J;:LW- 6356 ELW- 6941 Date *collected 09-16-15 10-14-15 11-05-15 12-10-15 Req. LLD Gross beta 0.6:!; 0.5 < 0.8 . 0.9 +/- 0.5 < 0.8 1.8 +/- 0.9 < 1.7 2.3 :!; 0.6 < 0.8 4.0 1-131 0.13 +/- 0.16 < 0.27 0.00 +/- 0.19 < 0.35 0.25 :j: 0.26 < 0.49 0.13 +/- 0.17 < 0.29 0.5 Be-7 7.8 +/- 8.4 < 19.7 16.4 +/- 14.4 < 38.0 2.5 +/- 4.4 < 13.5 -5.6 +/- 19.1 < 29.6 Mn-54 0.3 +/- 0.8 < 1.7 0.1 +/- 1.4 < 2.3 -0.2 +/- 0.6 < 1.0 0.1 +/- 2.0 < 3.7 10 Fe-59 1.0 +/- 1.6 < 3.5 -5.6 +/- 2.5 < 3.3 -0.7:!; 1.0 < 2.8 -3.4 +/- 4.2 / < 5.9 30 Co-58 -0.3 +/- 0.8 < 1.8 -0.7 +/- 1.7 < 2.9 0.4 +/- 0.5 < 1.2 2.6 +/- 2.0 < 3.4 10 Co-60 -0.2 +/- 0.9 < 1.5 0.2 +/- 1.6 < 1.6 0.1 t 0.6 < 1.0 -1.3 :t 1.7 < 1.4 10 Zn-65 -1 .1 +/- 1.8 < 2.6 2.1 +/- 3.2 < 6.1 -1 .0 +/- 1.1 . < 1.5 -1 .9 +/- 5.0 < 5.7 30 Zr-Nb-95 1.3 +/- 0.8 < 2.5 -1 .9 +/- 1.6 < 2.4 -0.1 +/- 0.5 < 1.8 0.3 +/- 2.0 < 2.9 15 Cs-134 -0.6 +/- 0.9 < 1.6 -0.4 +/- 1.4 < 2.9 0.2 +/- 0.5 < 1.0 o.3 +/- 2.11 < 3.8 10 Cs-137 -0.1 +/- 0.9 < 1.1 1.5 +/- 1.8 < 2.1 0.3 +/- 0.6 < 1.1 2.3 +/- 2.1 < 4.0 10 Ba-La-140 -4.3 +/- 1.0 < 4.2 0.8 +/- 2.2 < 13.4 0.7 +/- 0.7 < 3.8 -5.3 +/- 2.1 < 1.8 15 Other (Ru-103) -0.7 :t 0.9 < 2.3 1.6 +/- 1.6 < 4.1 0.5 +/- 0.5 < 1.6 -0.4 +/- 2.3 < 3.6 30
* "NS" = No sample; see Table 2.0, Listing of Missed Samples.
Annual All loaations Mean +/-S.d. Mean +/-S.d. Mean +/-S.d. Gross Beta 1.6 +/- 1.0 1-131 0.03 +/- 0.06 Co-58 o.o +/- 1.0 Cs-134 -0.1 +/- 1.1 Be-7 0.3 +/- 8.0 Co-60 -0.1 :!;0.9 Cs-137 0,2 +/- 0.6 ( Mn-54 0.1 +/- 0.7 Zn-65 -0.5 +/- 2.5 Ba-La-140 -0.8 +/- 2.2
'* Fe-59 -0.6 +/- 2.0 Zr-Nb-95 -0.1+/-1.3 Ru-103 -0.2 +/- 0.9 fi-4
POINT BEACH NUCLEAR PLANT Table 6. Lake water, analyses for tritium, strontium-89 and strontium~90. Collection: Quarterly composites of weekly grab samples Units: pCi/L Location E-01 (Meteorolo9ical Tower) Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4th Qtr. MDC Lab Code ELW- 1087 ELW- 3139 ELW- 5202 ELW- 7017 Req.LLOs H-3 -38 +/- 71 < 148 55 +/-74 < 144 128 +/- 78 < 142 85 +/-76 < 145 500 Sr-89 -0.13 +/- 0.66 < 0.76 0.17 +/-0.88 < 1.01 0.17 +/- 0.63 < 0.76 0.34 +/-0.62 < 0.73 5.0 Sr-90 0.35 +/-0.28 < 0.53 0.28 +/-0.37 < 0.73 0.19 +/- 0.30 < 0.59 0.22 +/-0.26 < 0.51 1.0 Location E-05 (Two Creeks Park) Period 1st Q!r. 2nd Qtr. 3nd Qtr. 4th Qtr. l.,ab Code ELW- 1088 ELW- 3140 ELW- 5203 ELW- 7018 a Req.LLDs H-3 15 +/-74 < 148 29 +/-73 < 144 96 +/- 76 < 142 452 :1;94@145 500 Sr-89 -0.05 +/-0.63 < 0.79 0.29 +/-0.62 < 0.78 0.48 +/- 0.58 < 0.73 0.53 +/-0.63 < 0.72 5.0 Sr-90 0.24 +/-0.26 < 0.51 0.12 +/-0.25 < 0.52 0.16 +/- 0.26 < 0.51 0.14 +/-0.26 < 0.52 1.0 Location E-06 (Coast Guard Station) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 1089 ELW- 3141 ELW- 5204 ELW- 7019 Req. LLDs H-3 4 +/-74 < 148 86 +/-76 < 144 61 +/- 74 < 142 61 +/-75 < 145 500
$r-89 -0.08 +/-0.57 < 0.69 -0.80 +/-0.86 < 0.91 -0.04 +/- 0.50 < 0.61 -0.43 +/-0.69 < 0.78 5.0 /
Sr-90 0.23 +/-0.24 < 0.46 0.71 +/-0.38 < 0.64 0.23 ;i: 0.24 < 0.45 0.47 +/- 0.31 < 0.55 1.0 Location E-33 {Kewaunee) Period 1st Qtr. 2nd Qtr. 3nd Qtr. 4th Qtr. Lab Code ELW- 1090 !;LW- 3142 ELW- 5205 ELW- 7020 Req. LLDs H-3 158 +/- 82 < 148 8 +/-72 < 144 113+/-77 < 142 237 +/- 84 ~< 145 500 Sr-89 0,39 +/-0.57 < 0.69 -0.21 +/-0.57 < 0.68 -0.15 +/- 0.54 < 0.62 -0.24 +/- 0.61 < 0.76 5.0 Sr-90 0.14 +/- 0.23 < 0.44 0.26 :1;0.25 < 0.48 0.41 +/- 0.26 < 0.44 0.26 +/-0.27 <0.51 1.0
~iz kLR0 :t..fS-1~
~~
Tritium Annual Mean +/- s.d. 97 +/- 116 Sr*89 Annual Mean +/- s.d. 0.02 +/-0.36 Sr-90 Annual Mean +/- s.d. 0.28 :!:0.15 a Tritium recounted with a result of 584;!:99 pCi/L.
/
(. 6-1
POINT BEACH NUCLEAR PLANT
/---
Table 7. Fish, analyses for gross bela and gamma emitting isotopes. ( Location: E-13 Collection: 2x I year Units: pCi/g wet Sample Description and Concentration Req. MDC MDC MDC LLD Collection Dale 01-05-15 01-06-15 01-18-15 Lab Code EF- 146 EF- 148 EF- 1334 Type Lake Trout While Fish Smallmouth Bass Ratio (wet/drY wt.) 4.71 4.87 5.19 Gross Bela 3.31 +/- 0.09 < 0.031 3.41 +/- 0.10 < 0.038 3.26 +/- 0.03 < 0.010 0.5 K-40 2.49 +/- 0.34 3.25 +/- 0.42 3.03 +/- 0.40 Mn-54 0.005 +/- 0.007 < 0.015 0.001 +/- 0.010 < 0.013 0.002 +/- 0.010 < 0.023 0.13 Fe-59 -0.010 +/- 0.018 < 0.054 -0.044 +/- 0.021 < 0.028 -0.004 +/- 0.018 < 0.133 0.26 Co-58 0.008 +/- 0.007 < 0.020 -0.003 +/- 0.009 < 0.014 -0.018 +/- 0.009 < 0.028 0.13 Co-60 0.001 +/- 0.010 < 0.015 -0.004 +/- 0.010 < 0.011 0.013 +/- 0.010 < 0.018 0.13 Zn-65 -0.009 +/- 0.020 < 0.024 0.006 +/- 0.024 < 0.026 0.010 +/- 0.017 < 0.037 0.26 Cs-134 0.003 +/- 0.009 < 0.018 -0.005 +/- 0.009 < 0.015 0.000 +/- 0.009 < 0.017 0.13 Cs-137 0.014 +/- 0.011 < 0.020 0.012 +/- 0.010 < 0.012 0.025 +/- 0.013 < 0.021 0.15 Other (Ru-103) 0.020 +/- 0.009 < 0.042 0.010 +/- 0.008 < 0.016 -0.014 +/- 0.007 < 0.049 0.5 Collection Dale 03-15-15 03-15-15 03-30-15 Lab Code EF- 1335 EF- 1336 EF- 1337 Type Lake Herring Burbol Chinook Ratio (wet/drY wl.) 5.19 5.77 5.17 Gross Bela 3.16 +/- 0.03 < 0.010 1.75 +/- 0.02 < 0.009 2.30 +/- 0.02 < 0.007 0.5 ( K-40 2.32 +/- 0.34 0.94 +/- 0.49 2.11 +/- 0.30
\
Mn-54 -0.001 +/- *0.009 < 0.015 -0.014 +/- 0.021 < 0.025 -0.007 +/- 0.008 < 0.011 0.13 Fe-59 -0.003 +/- 0.015 < 0.037 0.056 +/- 0.036 < 0.108 -0.029 +/- 0.018 < 0.034 0.26 Co-58 -0.015 +/- 0.009 < 0.015 -0.021 +/- 0.020 < 0.039 0.001 +/- 0.007 < 0.016 0.13 Co-60 0.003 +/- 0.011 < 0.012 0.030 +/- 0.021 < 0.021 0.002 +/- 0.009 < 0.013 0.13 Zn-65 -0.006 +/- 0.018 < 0.024 0.008 +/- 0.041 < 0.082 -0.008 +/- 0.018 < 0.030 0.26 Cs-134 -0.002 +/- 0.008 < 0.015 0.000 +/- 0.021 < 0.044 0.000 +/- 0.008 < 0.016 0.13 Cs-137 0.044 +/- 0.023 < 0.022 0.038 +/- 0.027 < 0.049 0.023 +/- 0.010 < 0.018 0.15 Other (Ru-103) 0.000 +/- 0.007 < 0.030 -0.010 +/- 0.0 18 < 0.073 -0.010 +/- 0.008 < 0.016 0.5
/
rt \ 7-1
POINT BEACH NUCLEAR PlANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes. Location: E-13 Collection: 2x /year Units: pCi/g wet Sample Description and Concentration (pCilg wet) Req. MDC MDC MDC LLD Collection Date 04-30-15 05-18-15 06-12-15 Lab Code EF- 2214 EF- 2637 EF- 3732 Type Lake Trout Lake Trout Lake Trout Ratio (wet/dry wt.) 3.42 3.78 3.82 Gross Beta 2.78 +/- 0.06 < 0.020 2.43 +/- 0.06 < 0.020 3.62 +/- 0.08 < 0.029 0.5 K40 2.59 +/- 0.41 2.46 +/- 0.41 2.33 +/- 0.40 Mn-54 -0.004 +/- 0.009 < 0.013 0.013 +/- 0.009 < 0.014 0.003 +/- 0.008 < 0.016 0.13 Fe-59 0.025 +/- 0.021 < 0.042 0.008 :l: 0.018 < 0.039 0.036 +/- 0.019 < 0.055 0.26 Co-58 0.000 +/- 0.009 < 0.016 0.000 +/- 0.009 < 0.007 0.008 +/- 0.008 < 0.019 0.13 Co*60 0.008 +/- 0.006 < 0.013 0.002 +/- 0.010 < 0.014 0.003 +/- 0.010 < 0.016 0.13 Zn-65 -0.011 +/- 0.024 < 0.013 -0.013 +/- 0.020 < 0.009 -0.017 +/- 0.022 < 0.022 0.26 Cs-134 -0.004 +/- 0.009 < 0.013 0.000 +/- 0.009 < 0.016 -0.010 +/- 0.010 < 0.018 0.13 Cs-137 0.021 +/- 0.010 < 0.015 0.037 +/- 0.021 < 0.018 0.022 +/- 0.011 < 0.018 0.15 Other (Ru-103) 0.004 +/- 0.009 < 0.021 0.005 +/- 0.008 < 0.009 -0.011 +/- 0.009 < 0.027 0.5 Collection Date 06-19-15 08-18-15 09-02-15
/ EF- 3733 EF- 4660 Lab Code EF- 5230 Type Burbot Lake Trout c;:oho Ratio (wet/dry wt.) 5.99. 5.08 5.15 Gross Beta 2.06 +/- 0.06 < 0.028 2.32 +/- 0.05 < 0.029 2.72 +/- 0.06 < 0.018 K-40 2.00;!; 0.36 2.22:!: 0.35 2.58 +/- 0.39 Mn-54 0.011 +/- 0.009 < 0.015 0.006 :t: 0.009 < 0.018 0.004 +/- 0.009 < 0.020 Fe-59 -0.010 +/- 0.020 < 0.049 0.029 +/- 0.016 < 0.051 0.032 :!: 0.015 < 0.048 Co-58 -0.014 +/- 0.008 < 0.013 0.010 +/- 0.008 < 0.013 0.002 +/- 0.008 < O.Q18 Co-60 0.002 +/- 0.010 < 0.012 0.004 +/- 0.010 < 0.014 0.000 +/- 0.010 < 0.015 Zn-65 -0.023 +/- 0.022 < 0.019 0.006 +/- 0.015 < 0.019 0.006 +/- 0.017 < 0.029 Cs-134 -0.006 +/- 0.009 < 0.019 0.006 +/- 0.008 < 0.015 0.003 +/- 0.008 < 0.014 Cs-137 0.054 :!: 0.020 < 0.018 0.041 +/- 0.020 < 0.021 0.026 +/- 0.011 < 0.019 Other (Ru-103) -0.009 +/- 0.009 < 0.031 0.\)01 +/- 0.007 < 0.034 0.018 +/- 0.007 < 0.036 /
f 7-2
POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.
/
I Location: E-13
\
Collection: 2x/ year Units: pCi/g wet Sample Description and Concentration (pCi/g wet) Req . MDC MDC MDC LLD Collection Date 11-27-15 11-27-15 Lab Code EF- 6744 EF- 6745 Type Chinook Salmon Lake Trout Ratio (wet/dry wt.) 4.07 4.15 Gross Beta 3.24 +/- 0.06 < 0.020 2.95 +/- 0.07 < 0.025 0.5 K-40 3.22 +/- 0.42 2.34 +/- 0.38 Mn-54 0.004 +/- 0.008 < 0.012 0.000 +/- 0.008 < 0.015 0.13 Fe-59 -0.003 +/- 0.018 < 0.026 0.002 +/- 0.016 < 0.035 0.26 Co-58 -0.011 +/- 0.008 < 0.009 0.002 +/- 0.008 < 0.014 0.13 Co-60 -0.002 +/- 0.009 < 0.008 -0.005 +/- 0.008 < 0.008 0.13 Zn-65 -0.011 +/- 0.021 < 0.013 -0.004 +/- 0.019 < 0.026 0.26 Cs-134 0.001 +/- 0.008 < 0.016 0.004 +/- 0.007 < 0.013 0.13 Cs-137 0.021 +/- 0.011 < 0.017 0.021 +/- 0.011 < 0.017 0.15 Other (Ru-103) -0.003 +/- 0.008 < 0.020 -0.003 +/- 0.008 < 0.018 0.5 r Annual tl Mean +/- s.d. Gross Beta 2.81 +/- 0.56 K-40 2.42 +/- 0.57 Mn-54 0.002 +/- 0.007 Fe-59 0.006 +/- 0.027 Co-58 -0.004 +/- 0.010 Co-60 0.004 +/- 0.009 Zn-65 -0.005 +/- 0.010 Cs-134 -0.001 +/- 0.004 Cs-137 0.029 +/- 0.012 Other (Ru-1 03) 0.000 +/- 0.011 7-3
POINT BEACH NUCLEAR PLANT
/ Table 8. Radioactivity in shoreline sediment samples Collection: Semiannual Sample Description and Concentration (pCi/g dry)
MDC MDC MDC Collection Date 4/16/2015 4/16/2015 4/16/2015 Lab Code ESS- 1668 ESS- 1669 ESS- 1670 LLD Location E-01 E-05 E-06 Gross Beta 6.93 +/- 0.88 < 1.13 7.14 +/- 0.84 < 1.06 8.60 +/- 0.95 < 1.19 2.0 Be-7 0.028 +/- 0.050 < 0.09 -0.034 +/- 0.037 < 0.08 -0.063 +/- 0.061 < 0.14 K-40 5.73 +/- 0.40 3.20 +/- 0.26 5.13 +/- 0.39 Cs-134 0.000 +/- 0.007 < 0.012 -0.002 +/- 0.004 < 0.007 0.001 +/- 0.007 < 0.013 0.15 Cs-137 0.008 +/- 0.009 < 0.017 0.006 +/- 0.006 < 0.009 0.025 +/- 0.013 < 0.013 0.15 Tl-208 0.045 +/- 0.022 0.032 +/- 0.012 0.090 +/- 0.020 Pb-212 0.20 +/- 0.057 0.079 +/- 0.016 0.32 +/- 0.069 Bi-214 0.12 +/- 0.027 0.094 +/- 0.017 0.23 +/- 0.034 Ra-226 0.38 +/- 0.15 < 0.28 0.31 +/- 0.11 < 0.19 0.54 +/- 0.17 < 0.30 Ac-228 0.20 +/- 0.063 0.11 +/- 0.030 0.27 +/- 0.077 Collection Date 4/16/2015 4/16/2015 Lab Code ESS- 1671 ESS- 1672 Location E-12 E-33 Gross Beta 9.14 +/- 0.88 < 1.05 7.72 +/- 0.83 < 1.04 2.0
/' Be-7 0.011 +/- 0.053 < 0.11 -0.036 +/- 0.051 < 0.10 f:, K-40 5.75 +/- 0.38 5.81 +/- 0.40 Cs-134 -0.007 +/- 0.007 < 0.009 0.000 +/- 0.006 < 0.009 0.15 Cs-137 0.014 +/- 0.008 < 0.015 0.017 +/- 0.008 < 0.014 0.15 Tl-208 0.042 +/- 0.022 0.038 +/- 0.018 Pb-212 0.12 +/- 0.018 0.16 +/- 0.054 Bi-214 0.13 +/- 0.026 0.11 +/- 0.025 Ra-226 0.42 +/- 0.14 < 0.25 0.31 +/- 0.16 Ac-228 0.15 +/- 0.047 0.14 +/- 0.049 /
I \., 8-1
POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections) Sample Descriptior] and Concentration (pCi/g dry) IV! DC MDC MDC Collection Dale 10/14/2015 10/14/2015 10/14/2015 Req. Lab Code ESS- 5818 ESS- 5820 ESS- 5821 LLD Location E-01 E-05 E-06 Gross Bela 8.10 +/- 0.87 < 1.07 9.15 +/- 0.9,? < 1.11 11.20 +/- 0.92 < 1.06 2.0 Be-7 0.037 +/- 0.067 < 0.17 -0.001 +/- 0.061 < 0.14 -0.001 +/- 0.066 < 0.18 K-40 5.22 +/- 0.40 7.78 +/- 0.42 8.69 +/- 0.50 Cs-134 -O.OO(;l +/- 0.008 <: 0.017 -0.003 +/- 0.006 < 0.013 0.005 +/- 0.007 < 0.011 0.15 Cs-137 0.029 ;!: 0.016 < 0.016 0.014 +/- 0.008 <: 0.015 0.020 +/- 0.010 < 0.017 0.15 Tl-208 0.059 +/- 0.018 0.065 +/- 0.018 0.050 +/- 0.016 Pb-212 0.19 +/- 0.027 0.15 +/- 0.020 0.14 +/- 0.024 Bi-214 0.15 +/- 0.041 0.23 +/- 0.029 0.13 +/- 0.027 Ra-226 0.47 +/- 0.24 0.35 +/-0.14 < 0.29 0.37 +/- 0.18 < 0.35 Ac-228 0.20 +/- 0.059 0.18 +/- 0.069 0.17 +/- 0.080 Collection Date 10/14/2015 10/14/2015 Lab Code ESS- 5822 ESS- 5823 Annual Location E-12 E-33 Mean +/-s.d.
!' Gross Beta 7.31 +/- 0.84 < 1.04 7.50 +/- 0.94 < 1.22 2 .0 8.28 +/- 1.30 i' \,
Be-7 -0.012 +/- 0.056 < 0.14 0.058 +/- 0.064 < 0.21 -0.001 +/- 0.037 K-40 4.69 +/- 0.34 5.56 :!: 0.41 5.75 +/- 1.53 Cs-134 -0.002 +/- 0.006 < 0.011 -0.008 ;!: 0.007 < 0.012 0.15 0.00 +/- 0.00 Cs-137 0.026 +/- 0.011 < 0.012 0,028 +/- 0.013 < 0.015 0.15 0.019 +/- 0.008 Tl-2()8 0.050 +/- 0.014 0.049 ;!: 0.020 0.05 +/- 0.02 Pb-212 0.14 +/- 0.021 0.13 +/- 0.021 0.16 +/-0.06 Bi-214 0.13 +/- 0.024 0.086 +/- 0.025 0.14 +/- 0.05 Ra-226 o.36 +/- o.;w 0.33 ::!: 0.17 < 0.33 0.38 +/- 0.07 Ac-228 0.14 +/- 0.061 0.14 +/- 0.051 0.17 +/- 0.05
/
I \, 8-2
POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCi/g dry) MDC MDC MDC Collection Date 5/29/2015 5/29/2015 6/1/2015 Req . Lab Code ESO- 2728 ESO- 2729 ESO- 2730 LLD Location E-01 E-02 E-03 Gross Beta 8.08 +/- 0.92 < 1.15 31.19 +/- 1.22 < 1.04 26.25 +/- 1.15 < 1.03 2.0 Be-7 0.098 +/- 0.057 < 0.12 0.14 +/- 0.10 < 0.21 0.026 +/- 0.088 < 0.18 K-40 5.38 +/- 0.37 18.99 +/- 0.89 18.03 +/- 0.81 Cs-134 -0.004 +/- 0.006 < 0.008 -0.004 +/- 0.011 < 0.018 -0.004 +/- 0.008 < 0.013 0.15 Cs-137 0.031 +/- 0.015 < 0.013 0.12 +/- 0.044 < 0.032 0.15 +/- 0.030 < 0.022 0.15 Tl-208 0.054 +/- 0.015 0.20 +/- 0.035 0.20 +/- 0.034 Pb-212 0.16 +/- 0.028 0.51 +/- 0.046 0.57 +/- 0.096 Bi-214 0.13 +/- 0.027 0.36 +/- 0.053 0.33 +/- 0.042 Ra-226 0.42 +/-0.14 < 0.27 1.02 +/- 0.32 1.18 +/- 0.27 Ac-228 0.26 +/- 0.057 0.62 +/- 0.11 0.68 +/- 0.11 Collection Date 6/1/2015 5/29/2015 6/1/2015 Lab Code ESO- 2731 ESO- 2732 ESO- 2734 Location E-04 E-06 E-08 Gross Beta 15.40 +/- 1.07 < 1.20 19.14 +/- 1.10 < 1.14 22.32 +/- 1.15 < 1.15 2.0 Be-7 0.094 +/- 0.068 < 0.13 0.191 +/- 0.073 < 0.15 0.15 +/- 0.082 < 0.20 K-40 . 8.39 +/- 0.56 11 .85 +/- 0.66 13.44 +/- 0.74 Cs-134 0.005 +/- 0.008 < 0.015 -0.002 +/- 0.008 < 0.013 -0.001 +/- 0.010 < 0.016 0.15 Cs-137 0.088 +/- 0.024 < 0.018 0.315 +/- 0.036 < 0.024 0.23 +/- 0.034 < 0.023 0.15 Tl-208 0.11 +/- 0.022 0.082 +/- 0.027 0.092 +/- 0.031 Pb-212 0.33 +/- 0.077 0.19 +/- 0.038 0.21 +/- 0.030 Bi-214 0.17 +/- 0.039 0.15 +/- 0.035 0.17 +/-0.037 Ra-226 0.41 +/- 0.22 0.38 +/- 0.22 0.53 +/- 0.24 Ac-228 0.38 +/- 0.087 0.28 +/- 0.067 0.35 +/- 0.091 Collection Date 6/1/2015 5/29/2015 Lab Code ESO- 2735 ESO- 2736 Location E-09 E-20 Gross Beta 26.28 +/- 1.15 < 1.03 23.45 +/- 1.18 < 1.17 2.0 Be-7 0.077 +/- 0.093 < 0.21 -0.20 +/- 0.09 < 0.15 K-40 17.00 +/- 0.82 14.20 +/- 0.77 Cs-134 0.009 +/- 0.010 < 0.016 -0.006 +/- 0.010 < 0.014 0.15 Cs-137 0.11 +/- 0.035 < 0.026 0.089 +/- 0.022 < 0.018 0.15 Tl-208 0.14 +/- 0.031 0.12 +/- 0.025 Pb-212 0.51 +/- 0.10 0.49 +/- 0.10 Bi-214 0.40 +/- 0.054 0.24 +/- 0.044 Ra-226 0.92 +/- 0.29 0.67 +/- 0.26 Ac-228 0.51 +/- 0.10 0.46 +/- 0.093 9-1
POINT BEACH NUCLEAR PLANT
,. Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCi/g dry)
MDC MDC MDC Collection Date 10/28/2015 10/28/2015 10/28/2015 Req. Lab Code ESO- 6252 ESO- 6253 ESO- 6254 LLD Location E-01 E-02 E-03 Gross Beta 24.11 +/- 1.58 < 1.69 26.54 +/- 1.59 < 1.56 28.29 +/- 1.60 < 1.50 2.0 Be-7 0.024 +/- 0.090 < 0.18 0.020 +/- 0.094 < 0.19 0.083 +/- 0.085 < 0.21 K-40 16.38 +/- 0.72 16.15 +/- 0.73 15.01 +/- 0.69 Cs-134 0.003 +/- 0.010 < 0.020 -0.006 +/- 0.011 < 0.018 0.002 +/- 0.009 < 0.018 0.15 Cs-137 0.17 +/-0.035 < 0.030 0.095 +/- 0.034 < 0.031 0.12 +/- 0.026 < 0.024 0.15 Tl-208 0.16 +/- 0.025 0.16 +/- 0.028 0.17 +/-0.030 Pb-212 0.51 +/- 0.038 0.52 +/- 0.040 0.46 +/- 0.036 Bi-214 0.34 +/- 0.045 0.31 +/- 0.046 0.26 +/- 0.039 Ra-226 1.12 +/- 0.30 0.83 +/- 0.32 1.37 +/- 0.32 Ac-228 0.61 +/- 0.12 0.40 +/- 0.075 0.48 +/- 0.082 Collection Date 10/28/2015 10/28/2015 10/28/2015 Lab Code ESO- 6255 ESO- 6256 ESO- 6257 Location E-04 E-06 E-08 Gross Beta 28.38 +/- 1.62 < 1.55 13.87 +/- 1.37 < 1.73 18.75 +/- 1.13 < 1.21 2.0 Be-7 0.085 +/- 0.090 < 0.25 -0.026 +/- 0.080 < 0.14 0.058 +/- 0.075 < 0.24 K-40 17.17 +/- 0.73 8.55 +/- 0.52 15.61 +/- 0.71 Cs-134 -0.009 +/- 0.010 < 0.013 0.000 +/- 0.008 < 0.014 -0.012 +/- 0.009 < 0.011 0.15 Cs-137 0.12 +/- 0.024 < 0.023 0.28 +/- 0.033 < 0.024 0.24 +/- 0.030 < 0.023 0.15 Tl-208 0.15 +/- 0.027 0.070 +/- 0.020 0.11 +/- 0.026 Pb-212 0.46 +/- 0.036 0.24 +/- 0.028 0.29 +/- 0.029 Bi-214 0.36 +/- 0.041 0.14 +/-0.031 0.30 +/- 0.054 Ra-226 1.14 +/- 0.29 0.30 +/- 0.21 < 0.42 1.23 +/- 0.25 Ac-228 0.45 +/- 0.095 0.25 +/- 0.091 0.40 +/- 0.10 Collection Date 10/28/2015 10/28/2015 Lab Code ESO- 6258 ESO- 6259 Annual Location E-09 E-20 Mean +/- s.d. Gross Beta 28.28 +/- 1.21 < 1.10 21.61 +/- 1.11 < 1.09 22.62 +/- 6.24 2.0 Be-7 0.008 +/- 0.092 < 0.18 0.016 +/- 0.10 < 0.25 0.053 +/- 0.09 K-40 18.83 +/- 0.77 17.29 +/- 0.85 14.52 +/- 4.04 Cs-134 0.007 +/- 0.009 < 0.018 -0.012 +/- 0.012 < 0.019 0.018 +/- 0.08 0.15 Cs-137 0.15 +/- 0.028 < 0.026 0.17 +/-0.031 < 0.031 0.154 +/- 0.077 0.15 Tl-208 0.16 +/-0.030 0.16 +/-0.031 0.13 +/- 0.04 Pb-212 0.47 +/- 0.035 0.53 +/- 0.043 0.40 +/- 0.14 Bi-214 0.36 +/- 0.044 0.40 +/- 0.062 0.28 +/- 0.10 Ra-226 0.85 +/- 0.28 1.30 +/- 0.36 0.86 +/- 0.36 Ac-228 0.60 +/- 0.075 0.60 +/- 0.10 0.46 +/- 0.14 9-2
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection : Tri-annual
/
i
\.
Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 E-02 E-03 Collection Date 5/29/2015 5/29/2015 6/1/2015 Lab Code EG- 2709 EG- 2710 EG- 2711 Req . LLD Ratio (wet/dry) 3.08 3.82 5.35 Gross 8eta 7.62 +/-0.15 < 0.050 5.80 +/- 0.18 < 0.087 7.42 +/- 0.13 < 0.035 0.25 Be-7 1.37 +/-0.16 1.64 +/- 0.21 0.51 +/- 0.09 +/- 0.09 K-40 5.01 +/- 0.37 5.78 +/- 0.40 5.01 +/- 0.31 1-131 0.006 +/- 0.006 < 0.019 0.007 +/- 0.006 < 0.023 0.002 +/- 0.005 < 0.009 0.060 Cs-134 0.002 +/- 0.006 < 0.011 0.001 :1: 0.006 < 0.012 -0.001 +/- 0.004 < 0.008 0.060 Cs-137 0.008 +/- 0.007 < 0.012 -0.001 +/- 0.007 < 0.013 -0.002 +/- 0.005 .< 0.011 0.080 Other (Co-60) 0.002 +/- 0.007 < 0.013 0.002 +/- 0.007 < 0.008 -0.003 +/- 0.006 < 0.009 0.060 Location E-04 E-06 E-08 Collection Date 6/1/2015 5/29/2015 611/2015 Lab Code EG- 2713 EG- 2714 EG- 2715 Req. LLD Ratio (wet/dry) 6.09 5.28 4.71 Gross Beta 3.98 +/- 0.08 < 0.026 5.04 +/- 0.10 < 0.034 6.71 +/- 0.13 < 0.041 0.25 Be-7 0.65 +/- 0.10 1.11 +/- 0.16 1.57 +/- 0.18 +/- 0.175 K-40 2.82 +/- 0.24 4.36 +/- 0.33 5.89 +/- 0.41 1-131 -0.002 +/- 0.005 < 0.015 -0.012 +/- 0.007 < 0.018 -0.007 +/- 0.006 < 0.014 0.060
/
Cs-134 0.000 +/- 0.005 < 0.008 -0.003 +/- 0.007 < 0.011 0.004 +/- 0.006 < 0.012 0.060 !,, Cs-137 0.002 +/- 0.005 < 0.010 0.052 +/- 0.016 < 0.015 -0.001 +/- 0.007 < 0.014 0.080
'* Other (Co-60) 0.001 +/- 0.004 < 0.006 -0.002 +/- 0.008 < 0.011 0.003 +/- 0.008 < 0.014 0.060 Location E-09 E-20 Collection Date 6/1/2015 5/29/2015 Lab Code EG* 2716 EG- 2717 Req . LLD Ratio (wet/dry) 3.90 5.27 Gross Beta 6.77 +/- 0.14 < 0.042 6.42 +/-0.13 < 0.044 0.25 Be-7 0.52 +/- 0.13 0.18 +/- 0.08 +/- 0.08 K-40 5.52 +/- 0.34 5.39:!; 0.30 1-131 -0.003 +/- 0.004 < 0.011 0.001 +/- 0.005 < 0.016 0.060 Cs-134 Q.OOO +/- 0.005 < 0.009 0.001 +/- 0.005 < 0.009 0.060 Cs-137 0.005 +/- 0.006 < 0.012 -0.002 +/- 0.005 < 0.007 0.080 Other (Co-60) -0.001 +/- 0.006 < 0.007 -0.001 +/- 0.005 < 0.005 0.060 10-1
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection : Tri-annual
/
\
Sample Description and Concentration (pCi/g wet) MDC MDC MDC Location E-01 . E-02 E-03 Collection Date 07-22-15 07-22-15 07-22-15 Lab Code EG- 4014 EG- 4015 EG- 4016 Req. LLD Ratio (weUdry) 3.32 4.01 4.21 Gross Beta 5.43 +/- 0.12 < 0.048 6.47 +/- 0.13 < 0.043 8.02 +/- 0.16 < 0.055 0.25 Be-7 1.26 +/- 0.22 1.15+/-0.23 1.08+/-0.16 K-40 3.77 +/- 0.42 5.70 +/- 0.46 6.62 +/- 0.44 1-131 0.016 +/- 0.010 < 0.037 0.004 +/- 0.009 < 0.033 -0.003 +/- 0.007 < 0.025 0.060 Cs-134 -0.008 +/- 0.009 < 0.017 -0.003 +/- 0.008 < 0.017 0.000 +/- 0.007 < 0.013 0.060 Cs-137 0.001 +/- 0.009 < 0.011 0.005 +/- 0.009 < 0.011 0.007 +/- 0.008 < 0.013 0.080 Other (Co-60) 0.001 +/- 0.010 < 0.01 1 0.011 +/- 0.008 < 0.011 -0.003 +/- 0.007 < 0.008 0.060 Location E-04 E-06 E-08 Collection Date 07-22-15 07-22-15 07-22-15 Lab Code EG- 4017 EG- 4018 EG- 4019 Req . LLD Ratio (weUdry) 3.82 2.67 3.28 Gross Beta 7.45 +/- 0.17 < 0.057 . 5.60 +/- 0.12 < 0.041 4.71 +/- 0.12 < 0.054 0.25 Be-7 1.69 +/- 0.20 1.13 +/- 0.15 1.13 +/- 0.19 K-40 6.56 +/- 0.49 4.45 +/- 0.34 4.42 +/- 0.38 1-131 0.001 +/- 0.007 < 0.026 0.015 +/- 0.006 < 0.025 -0.004 +/- 0.008 < 0.029 0.060 Cs-134 0.001 +/- 0.008 < 0.014 -0.004 +/- 0.006 < 0.012 -0.003 :1; 0.007 < 0.015 0.060
/
Cs-137 0.004 +/- 0.009 < 0.015 0.001 +/- 0.008 < O.Q13 -0.002 +/- 0.007 < 0.013 0.080
+/- 0.007 ' Other (Co-60) -0.005 +/- 0.008 < 0.007 0.003 < 0.010 0.001 +/- 0.008 < 0.007 0.060 Location E-09 1=-20 Collection Date 07-22-15 07-22-15 Lab Code EG- 4020 EG- 4021 Req. LLD Ratio (weUdry) 3.67 3.38 Gross Beta 8.01 +/- 0.17 < 0.056 13.74 +/- 0.33 < 0.13 0.25 Be-7 1.39 +/- 0.20 1.43 +/- 0.24 K-40 7.32 +/- 0.51 5.93 +/- 0.48 1-131 ' 0.003 +/- 0.008 < 0.034 0.005 +/- 0.010 < 0.045 0.060 Cs-134 -0.002 +/- 0.007 < 0.014 -0.002 +/- 0.008 < 0.015 0.060 Cs-137 -0.002 +/- 0.008 < 0.016 -0.005 +/- 0.010 < 0.013 0.080 Other (Co-60) 0.009 +/- 0.008 < 0.008 -0.006 +/- 0.013 < 0.012 0.060
( \ 10-2
POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual
'* Sample Description and Concentration (pCi/g wet)
MDC MDC MDC . Location E-01 E-02 E-03 Collection Date 10-01-15 10-01-15 10-01-15 Lab Code EG- 5421 EG- 5422 -EG- 5423 Req. LLD Ratio (wet/dry) 2.95 2.79 4.88 Gross Beta 5.11+/-0.19 < 0.079 7.62 +/- 0.26 < 0.11 7.38 +/- 0.22 < 0.072 0.25 Be-7 2.95 +/- 0.31 2.38 +/- 0.28 2.17 +/- 0.27 K-40 4.78 +/- 0.50 5.53 +/- 0.48 6.72 +/- 0.48 1-131 -0.006 +/- 0.013 < 0.031 -0.013 +/- 0.009 < 0.018 -0.007 +/- 0.010 < 0.033 0.060 Cs-134 -0.002 +/- 0.009 < 0.019 0.006 +/- 0.009 < 0.018 0.002 +/- 0.008 < 0.016 0.060 Cs-137 -0.005 +/- 0.012 < 0.018 -0.004 +/- 0.010 < 0.014 0.001 +/- 0.009 < 0.015 0.080 Other (Co-60) -0.003 +/- 0.011 < 0.012 -0.001 +/- 0.011 < 0.011 -0.001 +/- 0.010 < 0.015 0.060 Location E-04 E-06 E-08 Collection Date 10-01-15 10-01-15 10-01-15 Lab Code EG- 5424 EG- 5425 EG- 5426 Req. LLD Ratio (wet/dry) 3.74 3.18 3.78 Gross Beta 8.56 +/- 0.27 < 0.095 4.71 +/- 0.17 < 0.071 7,83 +/- 0.24 < 0.088 0.25 Be-7 2.71 +/- 0.30 2.19 +/- 0.26 2.97:!; 0.25 K-40 6.46 +/- 0.51 3.79 +/- 0.38 4.81 +/- 0.44 1-131 0.001 +/- 0.009 < 0.022 ~0.011 +/- 0.009 < 0.026 0.001 +/- 0.009 < 0.043 0.060 Cs-134 -0.004 +/- 0.008 < 0.016 -0.003 +/- 0.009 < 0.015 -0.002 +/- 0.008 < 0.016 0.060 Cs-137 0.004 +/- 0.010 < 0.017 0.016 +/- 0.011 < 0.018 0.012 +/- 0.010 < 0.016 0.080
/'
Other (Co-60) -0.008 +/- 0.009 < 0.011 0.007 +/- 0.009 < 0.009 -0.005 +/- 0.009 < 0.011 0.060 Location E-09 E-20 Collection Date 10-01-15 10-01-15 Lab Code EG- 5427 EG- 5428 Req . LLD Ratio (wet/dry) 4.50 4.08 Gross Beta 5.77 +/- 0.19 < 0.071 7.20;!: 0.24 < 0.10 0.25 Be-7 2.03 +/- 0.28 2.92 +/- 0.31 K-40 6.01 +/- 0.45 7.55 +/- 0.53 1-131 0.001 +/- 0.009 < 0.024 0.016 +/- 0.010 < 0.051 0.060 Cs-134 0.000 +/- 0.008 < 0.015 -0.006 +/- 0.009 < 0.017 0.060 Cs-137 0.005 +/- 0.009 < 0.019 -0.002 +/- 0.011 < 0.018 0.080 Other (Co-60) 0.000 +/- 0.009 < 0.007 -0.005 +/- 0.010 < 0.012 0.060 Beta Annual Mean +/- s.c;f. 6.81 :t 1.94 13e-7 Annual Mean +/- s.d. 1.59 +/- 0.80 K-40 Annual Mean +/- s.d. 5.42 +/- 1.16 1-131 Annual Mean+/- s.d. 0.000 +/-.0.008 I Cs-134 Annual Me~n +/- s.d. -0.001 +/- 0.003 ! Cs-137 Annual Mean+/- s.d. 0.004 +/- 0.012 Co-60 Annual Mean +/- s.d. -0.005 ;!: 0.005 10-3
POINT BEACH NUCLEAR PLANT Table 11. Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.
\
Collection: Triannual Units: pCi/g wet Sample Description and Concentration Collection Date MDC 08-27-15 MDC Req. Lab Code NSa ESL- 4698 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 6.86 Gross Beta 3.04 +/- 0.13 < 0.11 0.25 Be-7 0.85 +/- 0.09 K-40 2.26 +/- 0.16 Co-58 -0.001 +/- 0.003 < 0.007 0.25 Co-60 0.004 +/- 0.004 < 0.007 0.25 Cs-134 -0.001 +/- 0.004 < 0.007 0.25 Cs-137 0.012 +/- 0.007 < 0.008 0.25 .r'* * \ Annual Mean+/- s.d. Gr. Beta 3.04 Be-7 0.85 K-40 2.26 Co-58 -0.001 Co-60 0.004 Cs-134 -0.001 Cs-137 0.012 a "NS" =No sample. See Table 2.0, Listing of Missed Samples. 11-1
POINT BEACH NUCLEAR PLANT
/ ' Table 12. Ambient Gamma Radiation a Po LLD/7days: < 1mRITLD 1st. Quarter, 2015 Date Annealed: 12-11-14 Days in the field 89 Date Placed: 01-02-15 Days from Annealing Date Removed : 04-01-15 to Readout: 124 Date Read: 04-14-15 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 89 17.7 +/- 0.8 12.5+/-1.0 12.8 +/- 1.0 0.99 +/- 0.08 E-2 89 21.7 :j:0.3 16.5 +/- 0.5 16.9 +/- 0.5 1.30 +/- 0.04 E-3 89 20.9 +/- 1.9 15.8 +/- 2.0 16.1 +/-2.0 1.24 +/- 0.15 E-4 89 20.6+/-1.7 15.4 +/- 1.8 15.7 +/- 1.8 1.21 +/- 0.14 E-5 89 19.8+/-1.3 14.7 +/- 1.4 15.0 +/- 1.4 1.16 +/- 0.11 E-6 89 17.4+/-1 .2 12.3 +/- 1.3 12.5 +/- 1.3 0.97 +/- 0.10 E-7 89 18.1 +/- 1.3 13.0 +/- 1.4 13.3 +/- 1.4 1.02 +/- 0.11 E-8 89 18.6+/-1.5 13.4 +/- 1.5 13.7 +/- 1.6 1.06+/-0.12 E-9 89 22.1 +/- 0.5 16.9 +/- 0.7 17.3 +/- 0.7 1.33 +/- 0.05 E-12 89 16.3+/-1 .1 11 .2 +/- 1.2 11.4 +/- 1.2 0.88 +/- 0.09 E-14 89 19.9+/-1.1 14.7 +/- 1.2 15.1 +/- 1.2 1.16 +/- 0.09 E-15 89 18.2 +/- 0.3 13.1 +/- 0.5 13.4 +/- 0.5 1.03 +/- 0.04 E-16 89 20.5 +/- 0.4 15.3 +/- 0.6 15.7 +/- 0.6 1.20 +/- 0.05 E-168 89 20.8 +/- 0.6 15.6 +/- 0.7 16.0 +/- 0.7 1.23 +/- 0.08 E-17 89 20.4+/-1.0 15.3 +/- 1.1 15.6 +/- 1.1 1.20 +/- 0.09 E-18 89 21.9+/-1.7 16.8 +/- 1.7 17.1 +/- 1.8 1.32 +/-0.13 /' 89 21.4 +/- 1.2 16.3 +/- 1.2 16.6 +/- 1.3 1.28 +/- 0.10 E-22 E-23 89 20.0 +/- 0.9 14.8 +/- 1.0 15.1 +/- 1.0 1.17 +/- 0.08 E-24 89 19.3 +/- 0.8 14.2 +/- 0.9 14.5 +/- 0.9 1.12 +/- 0.07 E-25 89 18.1 +/-0.5 12.9 +/- 0.7 13.2 +/- 0.7 1.02 +/- 0.05 E-26 89 17.5+/-1.1 12.3 +/- 1.2 12.6 +/- 1.2 0.97 +/- 0.09 E-268 89 18.3 +/- 0.3 13.2 +/- 0.5 13.5 +/- 0.5 1.04 +/- 0.04 E-27 89 20.6 +/- 0.7 15.5 +/- 0.8 15.8 +/- 0.8 1.22 +/- 0.06 E-28 89 14.8 +/- 0.4 9.6 +/- 0.5 9.9 +/- 0.5 0.76 +/- 0.04 E-29 89 15.5+/-1.3 10.4 +/- 1.4 10.6 +/- 1.4 0.82 +/- 0.11 E-30 89 17.9 +/- 1.0 12.8 +/- 1.0 13.1 +/- 1.1 1.01 +/- 0.08 E-31 89 21.5 +/- 0.4 16.4 +/- 0.6 16.7 +/- 0.6 1.29 +/- 0.04 E-32 89 20.6 +/- 1.0 15.5+/-1 .1 15.8 +/- 1.1 1.22 +/- 0.09 E-38 89 18.2+/-1 .0 13.0+/-1.1 13.3 +/- 1.1 1.02 +/- 0.09 E-39 89 20.5 +/- 1.2 15.3 +/- 1.3 15.7 +/-1.3 1.21 +/- 0.10 E-41 89 17.6 +/- 0.6 12.4 +/- 0.7 12.7 +/- 0.7 0.98 +/- 0.05 E-42 89 21 .7 +/- 1.2 16.5 +/- 1.2 16.9+/-1 .3 1.30+/-0.10 E-43 89 18.0+/-1 .3 12.9+/-1.3 13.1 +/- 1.4 1.01 +/-0.10 Control E-20 89 21.2 +/- 1.4 16.0 +/- 1.4 16.4 +/- 1.4 1.26 +/- 0.11 Mean+/-s.d. 19.3 +/- 1.9 14.2+/-1.9 14.5 +/- 1.9 1.12 +/-0.15 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-11-14 01-07-15 4.6 +/- 0.4 5.0 +/-0.3 03-24-15 04-14-15 2.4 +/- 0.2 2.5 +/- 0.2
- The CaS04 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the
/ average of the four readings. 12-1
POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mRITLD
\
2nd Quarter, 2015 Date Annealed: 03-24-15 Days in the field 90 Date Placed: 04-01-15 Days from Annealing Date Removed: 06-30-15 to Readout: 105 Dale Read: 07-07-15 Days in mR!Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 90 12.6 +/- 0.8 9.1 +/- 1.0 9.2 +/- 1.0 0.71 +/- 0.08 E-2 90 17.4 +/- 1.2 13.9+/-1.3 14.1+/-1.4 1.08 +/- 0.10 E-3 90 19.0 +/- 1.2 15.6+/-1 .3 15.7 +/- 1.3 1.21 +/-0.10 E-4 90 15.9 +/- 0.7 12.5 +/- 0.9 12.6 +/- 0.9 0.97 +/- 0.07 E-5 90 17.2 +/- 0.4 13.7 +/- 0.7 13.9 +/- 0.7 1.07 +/- 0.06 E-6 90 13.7 +/- 0.4 10.2 +/- 0.7 10.3 +/- 0.7 0.80 +/- 0.05 E-7 90 15.0 +/- 0.2 11 .5 +/- 0.6 11.6 +/-0.6 0.90 +/- 0.05 E-8 90 15.0 +/- 0.9 11.6+/-1.0 11.7 +/- 1.1 0.90 +/- 0.08 E-9 90 16.9 +/-0.7 13.4 +/- 0.9 13.6 +/- 0.9 1.05 +/- 0.07 E-12 90 14.9 +/- 0.2 11.4+/-0.6 11 .6 +/- 0.6 0.89 +/- 0.05 E-14 90 17.2 +/- 1.3 13.7+/-1.5 13.9 +/- 1.5 1.07 +/- 0.11 E-15 90 20.0 +/- 1.7 16.6 +/- 1.8 16.8 +/-1.8 1.29 +/-0.14 E-168 90 16.8 +/- 0.4 13.4 +/- 0.7 13.5 +/- 0.7 1.04 +/- 0.06 E-17 90 18.4 +/- 0.1 15.0 +/- 0.6 15.1 +/- 0.6 1.17 +/-0.05 E-18 90 21 .6 +/- 0.5 18.1 +/- 0.8 18.3 +/- 0.8 1.41 +/- 0.06 E-22 90 18.4 +/- 0.7 14.9 +/- 0.9 15.1+/-0.9 1.16 +/-0.07 E-23 90 20.3 +/- 0.5 16.9 +/- 0.8 17.1 +/- 0.8 1.31 +/- 0.06
/
E-24 90 15.9 +/- 0.3 12.5 +/- 0.6 12.6 +/- 0.6 0.97 +/- 0.05 E-25 90 19.3 +/- 0.5 15.9 +/- 0.8 16.1 +/- 0.8 1.23 +/- 0.06 E-268 90 14.9 +/- 0.6 11.5 +/- 0.8 11.6 +/- 0.8 0.89 +/- 0.06 E-27 90 19.3 +/- 0.6 15.8 +/- 0.8 16.0 +/- 0.8 1.23 +/- 0.06 E-28 90 13.3 +/- 0.2 9.9 +/- 0.6 10.0 +/- 0.6 0.77 +/- 0.05 E-29 90 11.4 +/- 0.4 8.0 +/- 0.7 8.1 +/- 0.7 0.62 +/- 0.06 E-30 90 15.3 +/- 0.6 11.9 +/- 0.8 12.0 +/- 0.8 0.92 +/- 0.06 E-31 90 16.6+/-1 .2 13.1 +/- 1.4 13.3 +/- 1.4 1.02 +/- 0.11 E-32 90 20.3 +/- 0.2 16.8 +/- 0.6 17.0 +/- 0.6 1.31 +/- 0.05 E-38 90 17.1 +/- 0.2 13.7 +/- 0.6 13.8 +/- 0.6 1.06 +/- 0.05 E-39 90 17.5 +/- 0.5 14.1 +/- 0.8 14.2 +/- 0.8 1.09 +/- 0.06 E-41 90 15.7 +/- 0.3 12.2 +/- 0.6 12.4 +/- 0.6 0.95 +/- 0.05 E-42 90 18.7 +/- 0.6 15.2 +/- 0.8 15.4 +/- 0.8 1.18 +/- 0.06 E-43 90 17.7 +/- 0.5 14.3 +/- 0.8 14.4 +/- 0.8 1.11 +/- 0.06 Control E-20 92 16.4 +/- 1.4 12.9+/-1 .5 12.8+/-1 .5 0.98 +/- 0.12 Mean+/-s.d. 16.9 +/- 2.4 13.4 +/- 2.4 13.6 +/- 2.4 1.04 +/-0.18 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 03-24-15 04-14-15 2.4 +/- 0.2 2.5 +/- 0.2 06-08-15 07-07-15 4.3 +/- 0.3 4.6 +/- 0.4
- The CaS0 4:Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.
I ~ 12-2
POINT BEACH NUCLEAR PLANT
/ Table 12. Ambient Gamma Radiation a I
\ LLD/7days: < 1mRITLD 3rd Quarter, 2015 Date Annealed: 06-08-15 Days in the field 86 Date Placed: 06-30-15 Days from Annealing Date Removed: 09-24-15 to Readout: 115 Date Read: 10-01-15 Days in mR!Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 86 20.3 +/- 0.3 16.9 :!: 0.6 17.9 +/- 0.7 1.38 +/- 0.05 E-2 86 20.3 ;1;0.6 16.9 :!: o.8 17.8 +/- 0.9 1.37 +/- 0.07 E-3 86 21.7 +/- 0.9 18.3 +/- 1.1 19.3 :1:1.1 1.49 +/- 0.09 E*4 86 18.1 +/- 1.1 14.7 +/- 1.2 15.5:;!: 1.3 1.19 :!: 0.10 E-5 86 19.0+/-1 .1 15.5 ;1: 1.2. 16.4 +/- 1.3 1.26 :t 0.10 E-6 86 16.2 ;1: 0.8 12.8 +/- 0.9 13.5:!:1.0 1.04 :1:0.08 E-7 86 16.1 :1:0.6 12.7 :!; 0.8 13.4 +/- 0.8 1.03 +/- 0.06 E-8 86 17.7 +/- 1.3 14.2 :1: 1.4 15.1 +/- 1.4 1.16 +/- 0.11 E-9 86 21.0 +/- 0.6 17.6:!; 0.8 18.6 :1: 0.9 1.43 :1:0.07 E-12 86 14.5 +/- 0.7 11 .1 :t 0.9 11.7 +/- 0.9 0.90 +/- 0.07 E-14 86 18.1 +/-0.5 14.7 :1:0.8 15.6 +/- 0.1;3 1.20 +/- 0.06 E-15 86 18.7 +/- 0.6 15.2 +/- 0.8 16.1 :1: 0.9 1.24:!; 0.07 E-16 86 19.4+/-1.1 16.0 +/- 1.2 16.9 +/- 1.3 1.30 +/-0.10 E-168 86 20.5 +/- 0.5 17.0 +/- 0.8 18.0 :1:0.8 1.39 +/- 0.06 E-17 86 19.0 :1:0.9 15.6 +/- 1.1 16.5 +/- 1.1 1.27:!: 0.09 E-18 86 21 .2 +/- 1.1 17.8 :1: 1.2 18.8 +/- 1.3 1.45 +/- 0.10
/
1.1 E-22 86 20.0 +/- 1.2 16.6 +/- 1.3 17.5 :1: 1.4 1.35 +/- 0.11
\ E-23 86 20.0 +/- 0.8 16.6 +/- 0.9 17.6+/-1.0 1.35 +/- 0.08 E-24 86 17.9 +/- 0.6 14.5 +/- 0.8 15.3 +/- 0.8 1.18 +/- 0.06 E-25 86 18.2 +/- 0.5 14.7 :1:0.7 15.6 +/- 0.8 1.20:!: 0.06 E-26 86 18.7 +/- 1.3 15.3 +/- 1.4 16.2+/-1.5 1.25 :1: 0.11 E-268 86 17.1+/-0.7 13.7:!: 0.9 14.5 :1:0.9 1.12 +/- 0.07 E-27 86 20.3 +/-0.5 16.9 ;1: 0.7 17.8 :1:0.8 1.37 +/- 0.06 E:-28 86 14.3 +/- 0.8 10.8:!;1 .0 11.5 +/- 1.0 0.88 +/- 0.08 E-29 86 13.6 +/- 0.8 10.2:!:1.0 10.8+/-1.0 0.83 +/-0.08 E-30 86 16..3:1:1 .1 12.9 ;1: 1.3 13.7 +/- 1.3 1.05 :!;0.10 E-31 86 20.1 +/-0.7 16.7:!: 0.9 17.7+/-0.9 1.36 +/- 0.07 E-32 86 20.7 +/-0.7 17.3 +/- 0.9 18.3+/-1 .0 1.41 +/-0.07 E-38 86 17.2 +/- 0.9 13.7 :t 1.0 14.5 +/- 1.1 1.12 :1; 0.08 E-39 86 20.3 +/- 1.4 16.9+/-1 .5 17.9 :l: 1.6 1.37 :!;0.12 E-41 86 18.2 +/- 0.5 . 14.8 :1:0.8 16.7 :!; 0.8 1.21 +/- 0.06 E-42 86 22.3:!: 0.8 18.8 +/- 0.9 19.9 :1;1.0 1.53 ;1: 0.08 E-43 86 20.5 +/- 1.7 17.1 +/- 1.8 18.1 +/- 1.9 1.39 +/- 0.15
.QQ.n.trQ!
E-20 86 18.8 :!; 1.6 15.3+/-1 .7 16.2+/-1.8 1.25 +/-0.14 Mean+/-s.d. 18.7 +/-2.1 15.3 +/-2.1 16.2:!: 2.3 1.24 +/- 0.18 In-Transit Exposure Date Annealed Date Read ITC-1 !IQ:1 06-08-15 07-07-15 4.3 :t 0,3 4.6 :1; 0.4 09-11.15 10-01-15 2.3 +/- 0.1 2.5 +/- 0.2
- The CaS04: Dy dosimeter cards provide fovr separate readout areas. Values listed represent the mean and standard devi<;~tion of !he
(
- average of the four readings.
12-3
POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Raqiation " ( LLD/7days: < 1mRITLD 4th Quarter, 2015 Pate Annealed: 09-16-14 Days in the field 90 Date Placed: 10-04-14 Days from Annealing Date Removed: 01-02-15 to Readout: 113 Date Reacl: 01-07-15 Pays in mRJStnd Qtr t.ocation Field TotalmR NetmR (91 days) Net mR per 7 days Indicator E-1 90 16.8+/-1.4 13.0 +/- 1.5 13.1 +/-1.5 1.01 +/- 0.12 E-2 90 20.8 +/-0.9 17.0 +/- 1.0 17.2 +/- 1.0 1.32 +/- 0.08 E-3 90 23.1 +/- 1.5 19.3 +/- 1.6 19.6+/-1.6 1.50 +/- 0.12/ E-4 90 19.4 +/-0.4 15.6 +/- 0.6 15.7 +/- 0.6 1.21 +/- 0.05 E-5 90 21.0 +/- 0.4 17.2 +/- 0.6 17.4 +/- 0.1~ 1.34 +/- 0.05 E-6 90 17.6 +/- 0.5 13.8 :!; 0.7 14.0 +/- 0.7 1.08 +/- 0,05 E-7 90 18.3 +/- 0.2 14.5 +/- 0.5 14.7 +/- 0.5 1.13 +/- 0.04/ E-8 90 18.8 +/- 0.7 15.0 +/- 0.8 15.2 +/- 0.9 1.17+/-0.07 E-9 90 19.4 +/- 0.6 15.6 +/- 0.7 15.7 +/- 0.7 1.21 +/- 0.06 E-12 90 17.4+/-1.2 13.6 +/- 1.3 13.8+/-1.3 1.06+/-0.10 E-14 90 21.3 +/- 1.8 17.5+/-1.9 17.7 +/- 1.9 1.36 +/- 0.15 E-15 90 23.0 +/- 1.0 19.2 +/- 1.1 19.4 +/- 1.1 1.50 +/- 0.09
*~ .
1;:-166 90 20.2 +/-0.2 16.4 +/- 0.5 16.6 +/- 0.5 1.27 +/- 0.04 E-17 90 22.6:;!: 0.7 18.8 +/- 0 . ~ 19.0 +/- 0.8 1.46 +/- 0.06 E-18 90 23.2 :l; 0.9 19.4+/-1.0 19.6:!;: 1.0 1.51:!; 0.08/ E-22 90 23. 1 +/-0.9 19.3+/-1.1 19.5:!; 1.1 1.50:!; 0.08
/ E-23 90 25.2 :!:0.6 21.4 +/-0.8 21.6 +/- 0,8 1.66 +/- 0.06 . / \ E-24 90 20.4 +/-0.5 16.6 +/- 0.7 16.8 :t 0.7 1.29 +/- 0.06 .\
E-25 90 21 .1+/-0.6 17.3:!; 0.9 17.5 +/-0.9 1.35 +/- 0,07/ E:-268 90 19.2 +/- 0.2 15.4;!: 0.5 15.6 +/- 0.5 1.20 +/- 0.04 E-27 90 23.6 +/- 0,8 19.8 ;!: 0.9 20.0 :1:0.9 1.54 +/- 0.07 E-28 90 16.8 ;j: 0.3. 13.0 +/- 0.6 13.2 t. 0.5 1.01 +/- 0.-04 E*29 90 14.6 +/- 0.6 10.8 ;t 0.13 10.9:!; 0.6 0.84 :1; 0.06
!':-30 90 20.2 +/- 0.8 16.4 ;!; 0.9 16.6 +/- 0.9 1.28 ;l; 0.07 E-31 90 20.6 :;t 1.2 16.8 +/- 1.3 17.0:!:1.3 1.30 +/- 0.10 E-32 90 25.1 :j: 0.5 21.3 +/-0.7 21.6 :j: 0.7 1.()6;!:: 0.05 /
E-36 90 20.1 +/- 0.4 16.3 +/- 0.6 16.5:!: 0.7 1.27 +/- 0.05 E-39 90 20.5:!: 0.8 16.7 +/- 0.9 16.9 ;t 0.9 1.30 +/- 0.07 E-41 90 19.4 +/- 0.5 15.6 +/- 0.7 15.8 +/- 0.7 1.21 :;!; 0.05 E;-42 90 22.0 +/-0.7 18.2 +/- 0.9 18.4 +/- 0.9 1.42 +/- 0.07
~-43 90 21.5 +/- 0.7 17.7 +/- 0.8 17.9 +/- 0,9 1.38 +/- 0.07 Control E-20 90 20.5 +/- 1.9 16.7 :\:2.0 16.9 +/- 2.0 1.30 +/- 0.15 Mean+/-s.d. 20.1 +/- 1.5 16.7 :!: 2.4 19.7 +/- 1.5 1.30 +/- 0.19 In-Transit Exposure Date Annealed Date Read n:c~1 ITC-2 Or.:l-11-15 10-01-15 2.3 +/- 0.1 2.5 +/- 0.2 12-08-15 01-09-16 5.2 +/- 0.3 5.,4 +/- 0.3
- Thl;l CaS04 : Dy dosimeter cards provide fow ~>ep<;~rate reado\Jt areas. Values listed represent the mean and standard deviation of the average of the four readings.
Annual Indicator Mean;ts.d. 18.9 +/- 2.p 14,~:!: 2.9 15.3 +/- 2.6 1.2 +/- 0.2 I Annual Control Mean;!;s.d. 19.2:!: 2.2 15.3 t 1.7 15.6 +/- 1.9 1.2 +/-0.1 .:, Annual Indicator/Control Mean;J:s.d. 18.9 +/- 2.6 14.9 +/-2.5 15.3 2.6 1.2 +/- 0.2 1~-4
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections) I Units= Ci/L I Intermittent Streams S!lm~le ID GW-01 GW-02 Collection Collection Date Lab Code Tritium MDC Date Lab Coqe Tritium MDC 01-22-15 NS" 01-22-15 Ns* 02-25-15 Ns* 02-25-1 5 NS" 03-25-15 EWW-1247 167 ;!: 80 < 147 03-25-15 EWW- 1248 270 +/- 8(i < 147 04-29-15 EWW-2019 136 +/- 80 < 147 04-29-16 EWW-2020 222 +/- 84 < 147 05-20-15 EWW-2643 106 ;!: 80 < 150 05-29-15 EWW-2644 3 +/- 75 < 160 06-24-15 EWW-3233 123 +/- 78 < 143 06-24-15 EWW-3234 184 +/- 81 < 143 07-23-15 EWW-4150 124 +/- 81 < 143 07-23-15 EWW- 4151 83 +/- 79 < 143 08 15 EWW-4699 77 +/- 70 < 145 08-27-15 EWW-4700 173 +/- 81 < 145 09-30-15 EWW-5373 143 +/- 81 < 147 09-30-15 EWW-5374 189 +/- 83 < 147 10-28-15 EWW- 6222 39 ;!: 72 < 141 10-28-15 EWW- 6223 69 +/- 74 < 141 11-25-15 EWW-6682 53+/- 74 < 144 11 15 EWW-6683 163;!: 80 < 144 12-30-15 EWW- 7226 70;!: 75 < 144 12-30-15 EWW- 7227 122 ;!: 78 / < 144 Mean +/-s.d. 104 +/-42 Mean +/- s.d. 148 +/- 79 Sam~leiD GW-03 GW-17 Collection Collection Date Lab Code Trili!Jm MDC Date Lab Code Tritium MDC Q1 15 NS" 01-22-15 NS" 02-25-15 NS* 02-25-15 Ns* 03-25-15 EWW-1249 93 +/- 76 < 147 03-25-15 EWW- 1251 196 +/- 81 < 147 04-29-15 EWW-2021 107 +/- 79 < 147 04-29-15 EWW-2023 220 :!; 84 < 147 05-20-15 t;WW- 2645 129 +/- 81 " 150 05-20-15 EWW-2647 131 +/- 81 < 150 06-24-15 EWW-3235 -4 +/- 71 < 143 06-24-15 EWW-3237 174 +/- 80 " 143 07-23-15 EWW- 4152 141 +/- 82 < 143 07-23-15 EWW-4154 221 +/- 86 < 143
/ 08-27-15 EWW-4701 117 +/- 78 < 145 08 15 EWW-4703 138 +/- 79 < 145
', 09-30-15 EWW- 5375 113 +/- 79 < 147 09-30-15 EWW-5377 220 +/- 8(5 < 147
' 10-28-15 EWW-6224 45 +/- 73 < 141 10-28-15 EWW-6226 112 +/- 76 < 141 11-25-15 EWW- 6684 -27 +/- 70 < 144 11 15 EWW- 6686 97 +/- 77 < 144 12-30-15 EWW-7228 45 +/- 74 < 144 12-30-15 NSb Mean+/- s.d. 76 +/-58 . Mean +/-s.d. 168 :!; 49 Wells Samele 10 GW-04 (EIC Well)
Collection Date Lab Code Tritium MDC 01-22-15 EWW-327 -78 +/- 90 < 192 01-22-15 EWW-676 -39 +/- 72 < 142 03-25-15 EWW-1250 19 +/- 72 < 147 04-29-11> EWW- 2022 13 +/- 74 < 147 05-20-15 EWW-2646 -3 +/- 74 < 150 06 15 EWW-3236 2 +/- 71 < 143 07-23-15 EWW-4153 48;!: 77 < 143 08-27-15 EWW-4702 -24 ;!: 70 < 145 09-30-15 EWW-5376 - 101 +/- 67 < 147 10-28-15 EWW-6~25 14 +/- 71 < 141 11-25-15 EWW-6685 -25 +/- 70 < 144 12-30-15 EWW-7229 51 +/- 74 < 144 Mean :!; s.d. ;1(j +/- 46
- Water tfozen.
b No sample. ( I 13-1
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)
/ Units= Ci/L
\ Beach Drains Sam le ID S-1 S-3 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 EWW-1355 355 +/- 95 < 148 04-02-15 EWW-1356 316 +/- 93 < 148 04-2~-15 EWW-1778 134 +/- 86 < 150 04-22-15 EWW-1779 430 +/- 99 < 150 05-06-15 EWW-2222 200 :!: 87 < 147 05-06-15 EWW-22.23 302 +/- 92 < 147 06-02-15 EWW-2748 212 +/- 87 < 155 06-02-15 EWW-2749 190 +/- 86 < 155 07-09-15 EWW-3622 160 +/- 100 < 154 07-09-15 EWW-3623 262 +/- 104 < 154 08-05-15 EWW-4340 122 +/- 85 < 150 08-05-15 EWW-4341 644 +/- 107 < 150 09-10-15 EWW-4990 205 +/- 84 < 148 09-10-15 EWW-4991 249 +/- 87 < 148 10-07-15 EWW-5629 244 +/- 86 < 149 10-07-15 EWW-5631 165 :!: 82 < 149 11-05-15 EWW-6408 342 +/- 92/ < 151 11-05-15 EWW-6409 219 +/- 86 < 151 12-10-15 EWW-6935 292 +/- 87 " 145 12-10-15 EWW-6936 152 +/- 80 / < 145 Mean +/-s.d. 227 +/- 81 Mean +/-s.d. 293 +/- 148 Sam ie ID S-7 S-8 Collection Collection Date Lab Code Tritium MDC Date L.ab Codt;J Tritium MDC 01 15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 NF" 04-02-15 NF" 04-22-15 NF" 04-22-15 NF" 05-06-15 NF" 05-06-15 NF"
,/ 06-02-15 NF" 06-02-15 NF" 07-09-15 NF" 07-09-15 NF" 08-05-15 NF" 08-05-15 NF" 09-10-15 NF" 09-10-15 NF" 10-07-15 NF" 10-07-15 NF" 11-05-15 NF" 11-05-15 NF 0 12-10-15 NF" 12-10-15 NF" Mean +/-s.d. Mean;!: s.d.
Sam[;!le ID S-9 8-10 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-15 NF" 01-10-15 NF" 02-10-15 NF" 02-10-15 NF" 04-02-15 NF" 04-02-15 NF" 04-22-15 NF" 04-22-15 NF" 05-06-15 NF" 05-06-15 NF" 06-02-15 NF" 06-02-15 NF" 07-09-15 NF" 07-09-15 NF" 08-05-15 NF" 08-05-15 NF" 09-10-15 NF" 09-10-15 NF" 10-07-15 NF" 10-07-15 NF" 11-0!i-15 NF" 11-05-15 NF" 12-10-15 NF" 12-10-15 NF" Mean +/-s.d. Mean +/-s.d.
* "NF" =No flow.
/ 13-2
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections) Units= Ci/L Beach Drains (cont.) Sam le ID S-11 Collection Date Lab Code Tritium MDC 01-10-15 NFa 02-10-15 NFa 04-02-15 EWW-1357 210 +/- 88 < 148 04-22-15 EWW-1780 214 +/- 90 < 150 05-06-15 NFa 06-02-15 NFa 07-09-15 NFa 08-05-15 NFa 09-10-15 NFa 10-07-15 NFa 11 15 NFa 12-10-15 NFa Mean+/- s.d. 212 +/- 3 Sample ID U2 Fa~ade Subsurface Drain Sump Collection Collection Date Lab Code Date Lab Code Tritium MDC Tritium MDC 01-20-15 EW- 508 682 +/- 135 < 196 02-15-15 EW- 993 721 +/- 107 < 148 03-26-15 EW- 1501 475 +/- 102 < 152 04-30-15 EW- 2227 648 +/- 106 < 147 06-02-15 EW- 2747 741 +/- 109 < 155 06-30-15 EW- 4025 591 +/- 105 < 149 08-31-15 EW- 4951 577 +/- 104 < 147 09-30-15 EW- 6410 306 +/- 91 < 144 10-31-15 EW- 6411 683 +/- 103 < 143 12-07-15 EW- 6978 568 +/- 98 < 146 12-31-15 EW- 7465 496 +/- 112 < 152 Mean+/- s.d. 590 +/- 128 a "NF" = No flow. 13-3
POINT BEACH NUCLEAR PLANT Beach Drains r\ Units: =pCi/L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 01-10-15 01-10-15 01-10-15 01-10-15 3 Lab Code NFa MDC NF MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-9 S-1*0 S-11 S-1 Collection Date 01-10-15 01-10-15 01-10-15 02-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54
/
Fe-59 Co-58
\.
Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-3 S-7 S-8 S-9 Collection Date 02-10-15 02-10-15 02-10-15 01-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow. ( 13-4
POINT BEACH NUCLEAR PLANT
\ Beach Drains (cont.)
Units: = pCi\L Gamma isotopic analysis Location S-10 S-11 S-1 S-3 Collection Date 02-10-15 02-10-15 04-02-15 04-02-15 Lab Code NF" MDC NF" MDC EW- 1355 MDC EW- 1356 MDC Be-7 5.9 +/- 6.3 < 17.4 2.7 +/- 5.9 < 14.7 Mn-54 -0.6 +/- 0.6 < 0.8 0.3 +/- 0 .6 < 1.1 Fe-59 1.4 +/- 1.2 < 3.1 -0.1 +/- 1.2 < 3.1 Co-58 0.2 +/- 0.6 <1.4 0.5 +/- 0.5 < 1.2 Co-60 0.1 +/- 0.6 < 1.1 -0.3 +/- 0.6 < 1.1 Zn-65 0.7 +/- 1.5 < 2 .8 -0.4 +/- 1.3 < 2 .5 Zr-N~-95 -0 .8 +/- 0.7 < 1.5 0.8 +/- 0.6 < 1.7 Cs-134 0.3 +/- 0.7 < 1.3 0.3 +/- 0.6 < 1.2 Cs-137 1.0 +/- 0.8 <1.4 0.0 +/- 0.7 < 1.2 Ba-La-140 -2.1 +/- 0.7 < 2.3 -0.9 +/- 0.7 < 3.2 Location S-7 S-8 S-9 S-10 Collection Date 04-02-15 04-02-15 04-02-15 04-02-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 ( Fe-59
' Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-1 I'"
S-3 S-7 Collection Date 04-02-15 04-22-15 04-22-15 04-22-15 Lab Code EW- 1357 EW- 1778 EW- 1779 NF" Be-7 1.6 +/- 4.7 < 14.4 2.2 +/- 4.7 < 14.3 -4.3 +/- 10.3 < 27.8 Mn-54 0.6 +/- 0.6 < 1.1 -0.2 +/- 0.6 < 0.8 -1.4 +/- 1.3 < 2.3 Fe-59 -0.5 +/- 1.1 < 1.7 -0.3 +/- 1.0 < 2.6 -0.2 +/- 2.1 < 2.9 Co-58 0.1 +/- 0.6 < 1.4 0.3 +/- 0.6 < 1.1 -0.7 +/- 1.1 < 1.5 Co-60 -0.3 +/- 0.6 < 1.2 0.2 +/- 0.6 < 0.9 0.1 +/- 1.2 < 1.7 Zn-65 0.2 +/- 1.1 < 2.1 0.0 +/- 1.1 < 2.2 0.2 +/- 2.0 < 2.8 Zr-Nb-95 -0.3 +/- 0.6 < 1.6 -0.4 +/- 0.6 < 1.7 -1.1 +/- 1.4 < 2.2 Cs-134 0.4 +/- 0.6 < 1.1 -0.5 +/- 0.6 < 1.1 -1.7 +/- 1.'2 < 2.2 Cs-137 0.5 +/- 0.7 < 1.3 0.1 +/- 0.7 < 1.1 1.5 +/- 1.4 < 2.6 Ba-La-140 -0.5 +/- 0.7 < 3.5 0.1 +/- 0.6 < 5.7 -3.0 +/- 1.4 < 3:2 a "NF" = No flow.
/
I 13-5
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-8 S-9 S-10 S-11 MDC Collection Date 04-22-15 04-22-15 04-22-15 04-22-15 Lab Code NF" MDC NF" MDC NF" MDC EW- 1780 MDC Be-7 -0.2 +/- 13.5 < 28.1 Mn-54 0.5 +/- 1.3 < 2.7 Fe-59 2.2 +/- 2.8 < 5.9 Co-58 -0.5 +/- 1.3 < 2.1 Co-60 0.4 +/- 1.1 < 1.9 Zn-65 -0.5 +/- 3.0 < 3.3 Zr-Nb-95 0.5 +/- 1.4 < 3 .3 Cs-134 -1.0+/-1 .3 < 2.6 Cs-137 0.2 +/- 1.4 < 1.9 Ba-La-140 .- 1.9 +/- 1.5 < 5.5 Location S-1 S-3 S-7 S-8 Collection Date 05-06-15 05-06-15 05-06-15 05-06-15 Lab Code EW- 2222 EW- 2223 NF" NF" MDC Be-7 -0.1 +/- 6.3 < 15.2 5.8 +/- 4 .9 < 16.1 Mn-54 0.3 +/- 0.6 < 1.2 0.3 +/- 0.6 <1.4 Fe-59 0.4 +/- 1.2 < 3.7 -1.6+/-1.0 < 1.9 Co-58 -1 .0 +/- 0.6 < 1.0 0.0 +/- 0.6 <1.4
/
Co-60 0.6 +/- 0.6 < 1.3 0.5 +/- 0.6 < 1.2
*, Zn-65 -0.2 +/- 1.3 < 2.0 0.3 +/- 1.2 < 2.5 Zr-Nb-95 - 0.7 +/- 0.7 < 1.3 -0.2 +/- 0.6 < 1.3 Cs-134 -0.1 +/-0.7 < 1.3 0.3 +/- 0.6 < 1.1 Cs-137 0.4 +/- 0.7 <1.4 0.5 +/- 0.7 < 1.1 Ba-La-140 -1.9+/-0.7 < 5.0 -3.4 +/- 0.7 < 4.6 Location S-9 S-10 S-11 S-1 Collection Date 05-06-15 05-06-15 05-06-15 06-02-15 Lab Code NF" MDC NF" MDC NF" MDC . EW- 2748 Be-7 -7.7 +/- 9.9 <19.4 Mn-54 0.7 +/- 1.2 < 2.4 Fe-59 -0.7 +/- 2.3 < 3.6 Co-58 -0.8 +/- 1.1 < 1.3 Co-60 -0.9 +/- 1.5 < 1.9 Zn-65 -2.5 +/- 2.8 < 4.3 Zr-Nb-95 -1.1 +/- 1.4 < 2.3 Cs-134 0.8 +/- 1.1 < 2.3 .
Cs-137 0.4 +/- 1.4 < 1.9 Ba-La-140 -0.9 +/- 1.4 < 3.5 a "NF" =No flow. .( 13-6
POINT BEACH NUCLEAR PLANT
/
Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 06-02-15 06-02-15 06-02-15 06-02-15 Lab Code EW- 2749 MDC NF" MDC NF" MDC NF" MDC Be-7 4.8 +/- 11.3 < 30.0 Mn-54 -0.3 +/- 1.2 < 1.9 Fe-59 1.4 +/- 2.0 < 3.1 Co-58 0.9 +/- 1.3 < 2.2 Co-60 -0.3 +/- 1.5 < 1.6 Zn-65 -1.5+/-2.8 < 3.2 Zr-Nb-95 0.8 +/- 1.5 < 4.4 Cs-134 0.2 +/- 1.3 < 2.3 Cs-137 -0.5 +/- 1.4 < 2.1 Ba-La-140 -0.8 +/- 1.4 < 2.5 Location S-10 S-11 S-1 S-3 Collection Date 06-02-15 06-02-15 07-09-15 07-09-15 Lab Code NF" NF" EW- 3622 EW- 3623 Be-7 -8.7 +/- 12.5 < 32.1 9.1 +/- 20.0 < 47.7 Mn-54 -1.3 +/- 1.4 < 1.8 1.2 +/- 2.2 < 3.7 Fe-59 -1 .5 +/- 2.8 < 3.8 0.6 +/- 4.0 < 4.9 ( Co-58 0.1 +/- 1.3 < 1.5 1.0 +/- 1.7 < 2.4 Co-60 1.3 +/- 1.4 < 2.0 0.8 +/- 2.0 < 2.3 Zn-65 0.6 +/- 3.2 < 5.6 -3.1 +/- 4.9 < 7.2 Zr-Nb-95 -0.3 +/- 1.5 < 2.7 -0.9 +/- 2.3 < 5.7 Cs-134 -0.5 +/- 1.3 < 2.7 0.7 +/- 2.0 < 3.9 Cs-137 -1.3+/-1.7 < 2.2 -0.7 +/- 2.2 < 3.4 Ba-La-140 -2.9 +/- 1.8 < 2.7 -4.5 +/- 2.8 < 6.5 Location S-7 S-8 S-9 S-10 Collection Date 07-09-15 07-09-15 07-09-15 07-09-15 Lab Code NF" NF" NF" NF" Be-7 < 47.7 Mn-54 < 3.7 Fe-59 < 4.9 Co-58 < 2.4 Co-60 < 2.3 Zn-65 < 7.2 Zr-Nb-95 < 5.7 Cs-134 < 3.9 Cs-137 < 3.4 Ba-La-140 < 6.5 a "NF" = No flow. / 13-7
POINT BEACH NUCLEAR PLANT
/
Beach Drains (cont.)
\
Units: = pCi\L Gamma isotopic analysis Location S-11 S-1 S-3 S-7 Collection Date 07-09-15 08-05-15 08-05-15 08-05-15 Lab Code NF" MDC EW- 4340 MDC EW- 4341 MDC NF" MDC Be-7 -0.1 +/- 11.4 < 30.6 0.3 +/- 12.1 < 29.3 Mn-54 1.2 +/- 1.6 < 2.6 -0.2 +/- 1.6 < 3.1 Fe-59 0.9 +/- 2.7 < 5.2 -1.7 +/- 2.6 < 4.0 Co-58 -1.0+/-1.5 < 2.8 -1.1 +/- 1.3 <1.4 Co-60 -0.2 +/- 1.4 < 1.3 0.4 +/- 1.4 < 1.1 Zn-65 0.7 +/- 2.7 < 2.5 -0.6 +/- 2.8 < 2.4 Zr-Nb-95 0.7 +/- 1.6 < 3.0 0.7 +/- 1.5 < 3.5 Cs-134 0.1 +/- 1.4 < 2.4 -0.9 +/- 1.5 < 2.5 Cs-137 2.0 +/- 1.7 < 2.8 1.3 +/- 1.6 < 2.9 Ba-La-140 2.3 +/- 1.1 < 3,1 1.6 +/- 1.8 < 5.6 Location S-8 S-9 S-10 S-11 Collection Date 08-05-15 08-05-15 08-05-15 08-05-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 I' Co-58
'\. Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S.3 S-7 S-8 Collection Date 09-10-15 09-10-15 09-10-15 09-10-15 Lab Code EW- 4990 EW- 4991 NF" NF" Be-7 25.4 +/- 16.0 < 36.2 3.0 +/- 11.6 < 26.7 Mn-54 0.1 ;t 1.5 < 2.9 0.6 :J; 1.3 < 2.4 Fe-59 - 7.3 :J; 3.9 < 4.9 1.4 +/- 2.1 < 2.9 Co-58 0.2 +/- 1.4 < 3.3 -0.8 +/- 1.3 < 2.3 Co-60 -0.2 +/- 1.7 < 1.0 0.5 +/- 1.2 < 1.7 Zn-65 2.2 +/- 3.2 < 2.0 1.0 +/- 2.7 < 3.8 Zr-Nb-95 0.4 +/- 1.4 < 3 .5 1.1 +/- 1.3 < 3.5 Cs-134 0.3 +/- 1.8 < 3.3 0.7 +/- 1.2 < 2.5 Cs-137 0.5 :j: 1.7 < 3.6 0.8 +/- 1.5 < 2.5 Ba-La-140 7.7 +/- 1.7 < 8.6 1.1 +/- 1.5 < 6.7 a "NF" = -No flow.
( 13-8
POINT BEACH NUCLEAR PLANT I' Beach Drains (cont.)
\
Units: = pCi\L Gamma isotopic analysis I Location S-9 S-10 ' S-11 S-1 Collection Date 09-10-15 09-10-15 09-10-15 10-07-15 Lab Code NF" MDC NFa MDC NF" MDC EW- 5629 MDC Be-7 -4.4 +/- 21.7 < 29.4
. Mn-54 1.1 +/- 2 .5 < 3.6 Fe-59 2.5 +/- 5.5 < 4.9 Co-58 -2 .5 +/- 2.7 < 3.2 Co-60 1.3 +/- 2.6 < 4.6 Zn-65 2.8 +/- 6.3 < 5 .1 Zr-Nb-95 2.7 +/- 2.9 < 5.7 Cs-134 -0.6 +/- 2.7 < 4.8 Cs-137 0.9 +/- 2.8 < 4.2 Ba-La-140 4.9 +/- 3.1 < 7.6 Location S-3 S-7 S-8 S-9 Collection Date 10-07-15 10-07-15 10-07-15 10-07-15 Lab Code EW- 5631 NF3 NF" NF" Be-7 -33.1 +/- 26.9 < 36.9 Mn-54 0.0 +/- 2.9 < 4.6 Fe-59 -3.6 +/- 5.3 < 4.9 / Co-58 -2 .1 +/- 2.8 < 4.0 \ Co-60 1.0 +/- 2.6 < 3.8 Zn-65 -30.1 +/- 9.8 < 11 .9 Zr-Nb-95 -13.5 +/- 3.9 < 9.8 Cs-134 -1 .8 +/- 2.7 < 4.6 Cs-137 0.3 +/- 3.2 < 5.7 Ba-La-140 -0.7 +/- 4.5 < 13.4 Location S-10 S-11 S-1 S-3 Collection Date 10-07-15 10-07-15 11 15 11 15 Lab Code NF" NF" EW- 6408 EW- 6409 Be-7 6.6 +/- 21.4 < 38.8 8.3 +/- 9.1 < 30.1 Mn-54 1.1 +/- 2.7 < 4.2 0.6 +/- 1.2 < 1.8 Fe-59 -8.9 +/- 5.1 < 5 .8 0.4 +/- 2.0 < 5.8 Co-58 -2.1 +/- 2.6 < 3 .0 0.3 +/- 1.1 < 2.4 Co-60 3.5 +/- 2.8 < 5.3 0.7 +/- 1.2 < 2.4 Zn-65 -4.5 +/- 5.2 < 6.8 -2.3 +/- 2.6 < 2.7 Zr-Nb-95 1.9 +/- 2.9 < 5.6 0.6 +/- 1.1 < 1.9 Cs-134 -1 .9 +/-2.6 < 5.0 -0.5 +/- 1.1 < 2.1 Cs-137 0.6 +/- 3.0 < 5 .3 -1.3 +/- 1.3 < 1.1 Ba-La-140 -0.3 +/- 3.2 < 8.0 -4.3 +/- 1.4 < 6.8 a "NF" = No flow.
( 13-9
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: =pCi\L Gamma isotopic analysis Location S-7 S-8 S~9 S-10 Collection Date 11-05-15 11-05-15 11-05-15 11-05-15 Lab Code NF" MDC NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-11 S-1 S-3 S-7 Collection Date 11-05-15 12-10-15 12-10-15 12-10-15 Lab Code NF" EW- 6935 MDC EW- 6936 MOC NF" MOC Be-7 -1.0 +/- 15.9 < 34.5 9.0 +/- 13.1 / < 17.2 Mn-54 0.7 +/- 1.6/ < 2.5 0.1 :t 1.3 < 1.2 Fe-59 1.5 +/- 3.2 < 4.2 -0.4 +/- 3.1 < 4.7
/
Co-58 0.2 +/- 1.6 < 2.3 0.6 +/- 1.3 < 1.9 '- Co-60 -1.0 +/- 1.6/ < 1.3 -0.1 +/- 1.7 < 2.2 Zn-65 3.9 +/- 3.8 < 6.4 2.0 +/- 3.1 / < 2.7 Zr-Nb-95 n1 ,8 +/-. 1,7 < 2.6 0.1 +/- 1.4 < 2.6 Cs-134 0.5 +/- 1.5 < 2.9 0.2 +/- 1.5 < 2.9 Cs-137 n1,2 :I; 2.1 < 2.9 0.5 ;I; 1.6 < 2.5 Ba-La-140 0.3 +/- 1.4 < 3.7 0.4 ::!; 1.7 < 6.2 Location S-8 S-9 S-10 S-11 Collection Date 12-10-15 12-10-15 12-10-15 12-10-15 Lab Code NF" NF" NF" NF" Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow. 13-10
POINT BEACH NUCLEAR PLANT Beach Drains (cont.) Units: = pCi\L Gamma isotopic analysis Annual All locations Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. Mean +/- s.d. Be-7 1.0 +/- 9.6 Co-58 -0.3 +/- 0.9 Zr/Nb-95 -0.4 +/- 2.8 Ba/La-140 -0.2 +/- 2.6 Mn-54 0.2 +/- 0.7 Co-60 0.3 +/- 0.9 Cs-134 -0.2 +/- -0.8 Fe-59 -0.5 +/- 2.6 Zn-65 -1.2 +/- 6.1 Cs-137 0.3 +/- 0.8 13-11
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) Units= Ci/L Quarter!~ Wells Sample ID GW-05 (WH 6 Well) GW-06 {SBCC Well) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-15-15 EWW-142 36 +/- 102 < 165 01-15-15 EWW-143 39 +/- 102 < 165 04-15-15 EWW-1665 -47 +/- 76 < 158 04-15-15 EWW-1666 -76 +/- 74 < 158 07-09-15 EWW- 3619 -44 +/- 91 < 154 07-09-15 EWW- 3620 -48 +/- 91 < 154 10-07-15 EWW- 5626 19 +/- 75 < 149 10-07-15 EWW- 5627 -8 +/- 73 < 149 Mean+/- s.d. -9 +/-43 Mean+/- s.d. -23 +/-50 Samele ID GW-11 {MW-1) GW-12 (MW-2) Collection Collection Date Lab Code Tritium MOC Date Lab Code Tritium MDC 8 01-21-15 EWW- 513 -10 +/- 96 < 196 01-21-15 NS 04-24-15 EWW- 2036 -72 +/- 80 < 159 04-24-15 EWW- 2038 -168 +/- 75 < 159 07-09-15 EWW- 4155 130 +/- 82 < 143 07-09-15 EWW- 4156 54+/- 78 < 143 10-19-15 EWW- 6214 108 +/- 76 < 141 10-19-15 EWW- 6215 12 +/- 71 < 141 Mean+/- s.d. 39 :1:96 Mean+/- s.d. Sample ID GW-13 {MW-6) GW-14A (MW-05A) Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-21-15 EWW- 514 -83 +/- 91 < 196 01-21-15 EWW- 515 29 :1; 99 < 196 04-24-15 EWW- 2039 -145 +/- 76 < 159 04-24-15 EWW- 2040 -101 +/- 78 < 159 07-09-15 EWW- 4157 159 +/- 83 < 143 07-09-15 EWW- 4158 139 +/- 82 < 143
' 10-19-15 EWW- 6216 134 :1; 77 < 141 10-19-15 EWW- 6217 91 +/- 75 < 141 Mean+/- s.d. 16 +/- 153 Mean+/- s.d. 39 +/- 104 Sample ID GW-15A (MW-4) GW-158 (MW-4)
Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-21-15 EWW-516 96 +/- 103 < 196 01-21-15 EWW- 517 131 +/- 105 < 196 04-24-15 EWW- 2041 -18 :;1: 83 < 159 04-24-15 EWW- 2042 -32 +/- 82 < 159 07-09-15 EWW-4160 284 +/- 89 < 143 07-09-15 EWW- 4161 278 +/- 89 < 143 10-19-15 EWW- 6219 187 +/- 80 <. 141 10-19-15 EWW- 6220 181 :l;: 80 < 141 Mean+/- s.d. 137 +/- 129 Mean:!: s.d. 139 +/- 130 Sample ID GW-16 (MW-3) Collection Date Lab Code Tritium MDC 01-21-15 EWW- 518 147 +/- 106 < 196 04-24-15 EWW- 2043 186 +/- 81 < 152 07-09-15 EWW- 4162 199 +/- 85 < 143 10-19-15 EWW- 6221 179 :t: 80 < 141 Mean+/- s.d. 178 +/-22 a Water frozen. ~ 13-12
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections) f Units= Ci/L Quarterly Wells (cont.) Sample ID GW-18 (WH 7 Well) Collection Date Lab Code Tritium MDC 01-15-15 EWW- 144 62 +/- 104 < 165 04-16-15 EWW-1667 23 +/- 80 < 158 07-09-15 EWW- 3621 -23 +/- 92 < 154 10-07-15 EWW- 5628 19 +/- 75 < 149 Mean +/-s.d. 21 +/-35 Facade Wells Sample ID GW-09 1Z-3.61A GW-09 1Z-361 B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 02-27-15 EWW- 867 307 +/- 91 < 151 02-27-15 EWW- 868 147 +/- 83 < 151 04-12-15 EWW- 2515 287 +/- 107 < 183 04-12-15 EWW- 2516 91 +/- 100 < 183 08-08-15 EWW-4709 253 +/- 87 < 150 08-08-15 EWW- 4710 50+/- 77 < 150 10-15-15 EWW- 6210 346 +/- 88 < 141 10-15-15 EWW- 6211 51 +/- 73 < 141
/
Mean+/- s.d. 298 +/-39 Mean+/- s.d. 85 +/-46 Sample ID GW-10 2Z-361A GW-1 0 2Z-361 8 Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 02-27-15 NSa 02-27-15 EWW- 869 68 +/- 79 < 151 04-12-15 EWW- 2517 35 +/- 98 < 183 04-12-15 EWW- 2518 64 +/- 99 < 183 08-08-15 EWW- 4711 54+/- 77 < 150 08-08-15 EWW- 4712 101 +/- 80 < 150 10-15-15 EWW- 6212 61 +/- 74 < 141 10-15-15 EWW- 6213 120 +/- 77 < 141 Mean+/-s.d. 50+/- 14 Mean+/- s.d. 88 +/-27 (Annual Collections) Units= Ci/L Bogs Sample ID GW-07 (North Bo£1) GW-08 EIC Bo£1 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 05-06-15 EWW- 2224 135 +/- 84 < 147 05-06-15 EWW-2225 275 +/- 91 < 147 a Water frozen. I" 13-13
POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program
/ Units = pCi/L Manholes Sample ID MH Z-065A MH Z-0658 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d.
Sample ID MH Z-065C MH Z-065D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCI/L) Date (pCi/L) 8 04-23-15 NS 04-23-15 NS 8 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean +/- .s.d. Sample ID MH Z-066A MH Z-0668 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCI/L) Date (pCi/L) 04-23-15 EW- 2044 77 +/- 76 < 152 04-23-15 EW- 2045 58+/- 75 < 152
/
09-28-15 EW- 5400 163 :1: 83 < 149 09-28-15 EW- 5401 24 +/- 75 < 149 Mean +/-s.d. 120 +/- 61 Mean+/- s.d. 41 +/-24 Sample ID MH Z-066C MH Z-066D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCIIL) Date (pCi/L) 04-23-15 EW- 2046 38 +/- 73 < 152 05-01-14 EW- 2047 153 +/- 80 < 152 09-28-15 EW- 5402 153 +/- 82 < 149 09-28-15 EW- 5403 212 +/- 85 < 149 Mean+/- s.d. 95 +/-81 Mean+/- s.d. 182 +/- 41 samele ID MH Z-067A MH Z-0678 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2048 139 +/- 79 < 152 04-23-15 EW- 2049 248 +/- 84 < 152 09-28-15 EW- 5404 209 +/- 85 < 149 09-28-15 EW- 5405 34 +/- 76 < 149 Mean +/-s.d. 174 +/-50 Mean+/- s.d. 141 +/- 151 a "NS" = No sample; not sent. ( 13-14
POINT BEACH NUCLEAR PLANT Manholes (cont.) (
'\ *Sample ID MH Z-067C MH Z-067D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2050 98 +/- 77 < 152 04-23-15 EW- 2051 199 +/- 82 < 152 09-28-15 EW- 5406 125 +/- 81 < 149 09-28-15 EW- 5407 136 +/- 81 < 149 Mean+/- s.d. 111 +/- 19 Mean+/- s.d. 167 +/- 44 Sample ID MH Z-068 MH-1 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-23-15 EW- 2052 250 +/- 85 < 152 04-23-15 NS 8 09-28-15 EW- 5408 220 +/- 86 < 149 09-28-15 NS 8 Mean+/- s.d. 235 +/- 21 Mean+/- s.d.
Sample ID MH-4 MH-6 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d.
.( \
Sample ID MH-7 MH-8 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS Mean+/- s.d. Mean+/- s.d. Sample ID MH-16 MH-2 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 09-28-15 NS 8 09-28-15 NS 8 Mean+/- s.d. Mean+/- s.d. Sample 10 MH-5A MH-9 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 8 8 04-23-15 NS 04-23-15 NS 8 8 09-28-15 NS 09-28-15 NS
/
il Mean+/- s.d. Mean+/- s.d. a "NS" = No sample; not sent. 13-15
~*!!.._ ATJ E~vironmentaiJ" Inc.
~~.1"'\1 M1dwest Laboratory 700 Landwehr Rr>ad
- Ncxfhbrrx>k, /L 6008:Z-2310 phone (847) 564-0700
- fs)( (847) 564-4!317 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmentar 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 lntercomparlson results, in-house spikes, blanks, duplicates and mixed ana~yte 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, 2015 through December, 2015 I ( I! l f
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 possible problems. 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. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NlST 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-51ists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. 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 the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES 8 One standard deviation Analysis Level for sinple determination Gamma Emitters 5 to 100 pCi!liter or kg 5.0 pCi/liter
> 100 pCilliter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCilliter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi!liter
> 30 pCifliter or kg 10% of known value C: 0.1 glliter or kg 5% of known value Gross alpha s 20 pCilliter 5.0 pCi/liter
> 20 pCilliter 25% of known value Gross beta -::; 100 pCi/liter 5.0 pCilliter I
> 100 pCilliter 5% of known value i*
Tritium -::; 4,000 pCi/liter +/- 1a = 169.85 x (known) 0 *0933
> 4,000 pCi/liter 10% of known value Radium-226,-228 C: 0.1 pCilliter 15% of known value Plutonium e: 0.1 pCilfiler, gram, or sample 10% of known value lodine-131, s 55 pCilliter 6 pCilliter lodine-129b > 55 pCi/Hter 10% of known value Uranium-238, :;; 35 pCilliter 6 pCilliter Nickel-63b > 35 pCi!liter 15% of known value Technetium-99b lron-55b 50 to 100 pCI/Iiter 10 pCilliter
> 100 pCilliter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
( b Laboratory limit. \._ A2
/
! TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a
- Concentration {pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71 .20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41 .90 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61 .80 - 83.30 Pass ERW- 1448 4/6/2015 Cs-137 191 .9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85 .05 :1:4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 ~ 238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22 .10 - 54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21 .30 - 40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 - 28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56-6.01 Pass ERW- 1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770-3,620 Pass ERW-5528 t0/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.10 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.51 62.30 50.69 - 68.50 Pass f
'*.... ERW-5531 10/5/2015 Cs-137 163.1 +/- 4.8 157.0 141.0 - 175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71 .10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 1.13.0 - 149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/-0.08 51 .60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/-0.04 36.60 24 .10 - 44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21 .90 - 31 .00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46-5.85 Fail ERW-5540e 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 - 5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/5/2015 H-3 21 ,260 +/- 351 21,300 18,700-23,400 Pass
- Resulls 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.
- Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. ~
d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
- The result of reanalysis (Compare to original result. footnoted "e" above).
(_ A1 -1 I Il
I' TABLE A-2.1. Thermofuminescent Dosimetry, (TLD, CaSOi Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental. Inc. 2015-1 6/24/2015 30 em . 98.81 103,67 +/- 6.05 69.20 - 128.50 Pass 2015-1 6/24/2015 30 em. 98.81 111.32 +/- 15.97 69.20 - 128.50 Pass 2015-1 6/24/2015 60em . 24.10 27.23 +/- 1.33 17.30- 32.10 Pass 2015-1 6/24/2015 60 em. 24.70 26.98 +/-4.98 17.30- 32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30 - 8.00 Pass 201-5-1 6/24/2015 120 em. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120 em. 6. 18 6.43 +/- 2.00 4 .30-8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150 em. 3.95 4.12 +/- 1.36 2.80 - 5.10 Pass 2015-1 6/24/2015 150 em . 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180 em . 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180 em . 2.74 3.05 +/- 1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14+/-0.18 1.90-3.60 Pass I J i A2-1 j
I, ' TABLE A-2.2 Thermofuminescent Dosjmetry, (TLD, CaS0 4 : Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental. Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/- 2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 12/1512015 Spike3 138.0 121.9+/-1 .9 -0.12 Pass 2015-2 12/1512015 Spike4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12115/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2 +/- 1.2 -0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/-4.0 -0.01 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/- 5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/1512015 Spike 12 138.0 119.0+/-3.4 -0.14 Pass r 2015-2 12/15/2015 Spike 13 138.0 123.0 +/- 2.7 -0.1 1 Pass
.\ \ 2015-2 12/15/2015 Spi-ke14 138.0 125.4 :!;2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/- 3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/- 2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass
- TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N 13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose - conventlally true value) .,. conventially true value) where the convenlially true value is the delivered dose.
~ Acceptance Is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
e Tables A2. 1 and A2.2 assume 1 roentgen" 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). ( \ ... A2*2
! TABLE A-3. In-House "Spiked" Samples Concentration <eCi!L)"
Lab Code b Date Analysis Laboratory results Known Control 2s, n=1c Activity Limits d Acceetance W-020315 2/3/2015 Ra-226 16.19 +/- 0.42 16.70 13.36-20.04 Pass W-021215 2/12/2015 Gr. Alpha 18.38 +/- 0.39 20.10 16.08-24.12 Pass W-021215 2/12/2015 Gr. Beta 27.98 +/- 0.32 30.90 24.72-37.08 Pass SPW-687 2/27/2015 Ni-63 239.6 +/- 3.5 202.4 161.9-242.9 Pass SPAP-689 3/2/2015 Gr. Beta 42.37 +/- 3.50 43.61 34.89 - 52.33 Pass SPAP-691 3/2/2015 Cs-134 1.77 +/- 0.61 1.90 1.52-2.28 Pass SPAP-691 3/2/2015 Cs-137 83.02 +/- 2.60 97.20 77.76-116.64 Pass SPW-693 3/2/2015 Cs-134 44.30 +/- 2.53 53.40 42.72 - 64.08 Pass SPW-693 3/2/2015 Cs-137 74.82 +/- 3.50 73.80 59.04 - 88.56 Pass SPW-693 3/2/2015 Sr-89 87.45 +/- 3.62 87.48 69.98 - 104.98 Pass SPW-693 3/25/2015 Sr-90 37.22 +/- 1.55 38.10 3D.48 - 45.72 Pass SPMI-697 3/2/2015 Cs-134 96.67 +/- 7.74 107.00 85.60 - 128.40 Pass SPMI-697 3/2/2015 Cs-137 78.51 +/- 7.02 73.84 59.07 - 88.61 Pass SPMI-697 3/2/2015 Sr-89 72.98 +/-4.86 87.48 69.98- 104.98 Pass SPMI-697 3/2/2015 Sr-90 39.17+/-1 .51 38.10 30.48 - 45.72 Pass SPW-699 3/2/2015 H-3 59,592 +/- 703 58,445 46,756- 70,134 Pass W-031115 3/11/2015 Ra-226 13.73 +/- 0.35 16.70 13.36-20.04 Pass W-030215 3/2/2015 Ra-228 32.79 +/- 2.31 31 .44 25.15. 37.73 Pass SPF*1040 3/16/2015 Cs-134 787.5 +/- 9.2 840.0 672.0 -1,008.0 Pass SPF-1040 3/16/2015 Cs-137 2,599 +/- 24 2,360 1,888
- 2,832 Pass
/' SPW-1036 3/25/2015 Fe-55 1,792 +/- 63 1961 1,569 ~ 2,353 Pass i:\_
SPW-1374 4/6/2015 U-238 46.03 +/- 2.25 41.70 25.02 - 58.38 Pass W-040815 4/8/2015 Gr. Alpha 20.18 +/- 0.42 20.10 16.08 - 24.12 Pass W-040815 4/8/2015 Gr. Beta 29.70 +/- 0.33 30.90 24.72 - 37.08 Pass SPW-1038 4/13/2015 C-14 3,497 +/- 9 4,734 2,840 - 6,628 Pass W-2165 4/20/2015 H-3 5550 +/- 226 5,780 3,468 - 8,092 Pass W-2165 4/20/2015 Sr-89 90.70 +/- 8.20 108.70 65.22- 152.18 Pass W-2165 4/20/2015 Sr-90 76.80 +/- 2.00 75.90 45.54 - 106.26 Pass W-2165 4/20/2015 Cs-134 62.40 +/- 6.40 57.30 34.38 - 80.22. Pass W-2165 4/2012015 Cs-137 91.30 +/- 7.70 84.00 50.40 - 117.60 Pass W-2392 4/13/2015 H-3 5032 +/- 214 5780 3468-8092 Pass W-2392 4/13/2015 Ni-63 222.4 +/- 3.8 202.0 121.2 -282.8 Pass W-2392 4/13/2015 Cs-134 53.26 +/- 5.01 57.30 34.38 - 80.22 Pass W-2392 4/13/2015 Cs-137 91.90 +/- 7.76 84.20 50.52- 117.88 Pass W-042415 4/24/2015 Ra-22.6 12.52 +/-0.39 16.70 10.02 . 23.38 Pass W-05071-5 517/2015 Gr. Alpha 19.05 +/- 0.41 20.10 12.06-28.14 Pass W-05071-5 5/7/2015 Gr. Beta 27.30 +/- 0.32 30.90 18.54-43.26 Pass W-061215 6/12/2015 Gr. Alpha 20.72 +/- 0.44 20.10 12.06-28.14 Pass W-061215 6/12/2015 Gr. Bela 28.51 +/- 0.33 30.90 1'8.54 - 43.26 Pass U-2982 6/9/2015 Gr. Beta 500.1 +/- 5.1 604.0 362.4 - 845.6 Pass U-3200 6/9/2015 H-3 2229 +/-424 2346 1408-3284 Pass W-70915 7/9/2015 Gr. Alpha 18.76 +/- 0.40 20.10 12.1 - 28.1 Pass W-70915 7/9/2015 Gr. Beta 29.71 +/- 0.33 30.90 18.5 - 43.3 Pass SPAP-3859 7/21/2015 Gr. Bela 41.59 +/- 0.12 43.61 26.17 - 61.05 Pass SPAP-3861 7/21/2015 Cs-134 1.69 +/- 0.60 1.69 1.0-2.4 Pass { A3-1
/'~
1\ TABLE A-3. In-House "Spiked" Samples Concentration (pCf/L)" Lab Code b Date Analysis Laboratory results Known Control 2s, n;1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 - 135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/-5.12 47.02 28.21 - 65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Nr-63 451 .3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/-8.3 539.1 323.5- 754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 - 44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5 +/- 115.9 740.0 444.0- 1036.0 Pass SPP-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1,404- 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06 - 28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 - 43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 - 23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass c\ _ W-091415 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2016 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02- 23.38 Pass W-100615 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 - 28.14 Pass W-10061:5 10/6/2016 Gr. Beta 29.35 :;!:0.33 30.90 18.54-43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280- 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52- 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86-44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738- 15,723 Pass W-6086,6081 11/18/2015 Cs-134 92.98 +/-7.29 96.25 57.75 34.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76-116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54-43.26 Pass I W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 - 3,247 Pass r W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass l
+/- 0.33 l
W-120815 12/8/2015 Gr. Beta 29.50 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02-23.38 Pass 1
- Liquid sample results are reported In pCIILiter, air filters( pCI/m3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation}, CH (charcoal canister), F (fish), U (urine). 1 [
' Results are based on single detenninatlons. 1 d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.
I NOTE: For fish, Jello is used for the spike mabix. For vegetation, cabbage is used for the spike matrix. i
~
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~
A3-2 f t f [
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TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)" Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc Criteria (4.66 a) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/-0.02 1 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/-0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/-0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/-0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1 .57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/- 3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/-368.1 1000 I~ SPW-1037 Water 3/16/2015 C-14 8.94 2.16+/-5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1 .00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 517/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/-- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 1.56 +/- 1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 ~1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 i SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 rI SPW-3870 SPW-3870 Water Water 7/21/2015 7/21/2015 Sr-89 Sr-90 2.28 0.84
-0.42 +/- 1.80 0.25 +/-0.42 5
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\. f A4-1 i I,.
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if
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TABLE A-4. In-House "Blank" Samples Concentration <eCi/L)a Lab Code Sample Date Analysisb Laboratory results ( 4.66cr) Acceptance Type LLD ActivitXc Criteria (4.66 a-) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51 .3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/- 8.06 100 W-{)81015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015
- Ra-226 0,03 0.03 +/- 0.02 2 W-{)90615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/-0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/-0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/-0.52 4 C',_
W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/-0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-12081-5 Water 12/8/2015 Gr. Beta 0.76 0.17 +/- 0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2
- Liquid sample results are reported in pCi/Liter, air filters( pCitm\ charcoal (pCi/charcoal canister), and solid samples (pCllkg}.
b 1-131 (G); iodlne-131 as analyzed by gamma spectroscopy. c Activity reported Is a net activity result. A4-2
\ TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72 +/-0.12 5.78 +/-0.12 5.75 :1; 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/-0.135 0.919 +/-0.102 0.917+/-0.15 Pass CF-62,63 1/7/2015 K-40 3.97 +/-0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 V712015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/1212015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90+/-1 .16 Pass SG-83,84 1112/2015 Tl-208 0.57 +/-0.07 0.56 +/-0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73 +/- 0.10 1.58 +/- 0.09 1.65 +/-0.13 Pass SG-83,84 1/1212015 Pb-214 13.33 +/- 0.33 13.88 +/-0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47:!: 0.24 Pass SG-83,84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 111212015 Ac-228 13.33 +/-0.59 12.86 :!: 0.43 13.09 +/- 0.36 Pass AP-011215N8 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-60010,60011 1/28/2015 Ra-226 1.25+/-0.14 1.40 +/- 0.15 1.33 +/-0.10 Pass OW-60010,60011 1/2812015 Ra-228 2 .00 +/- 0.66 1.39 +/- 0.60 1.70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-2t4 6.45 +/-0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/-0.24 4.20 +/-0.58 4.32 +/- 0.31 Pass AP-020415NB 214/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115NB 2111/2015 Gr. Bela 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass
/ DW-60023,60024 212612015 Ra-226 1.52 +/-,0.15 1.51 +/-0.15 1.52 +/- 0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/-0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 212612015 K-40 11 .96 +/- 0.98 11.49 +/- 0.82 11.7.2 +/- 0.64 Pass S-799,800 2126/2015 Tl-208 0.36 +/-0.04 0.31 +/- 0.04 0.34 +/-0.03 Pass S-799,800 2/2612015 Pb-212 0.92 +/-0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 212612015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2126/2015 Ac-228 1.35 +/- 0.22 1.23 +/- 0. "t7 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3 +/- 6.3 t17.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 212/2015 Gr. Beta 82.27 +/-2.79 84.33 +/-2.74 83.30 +/- 1.96 Pass DW-60031 ,60032 314/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/-7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/-0.34 6.88 +/-0.32 6.89 +/-0.23 Pass DW-60036,60037 314/2015 Ra-228 4.43 +/-0.73 4.41 +/- 0.72 4.42 +/- 0.51 Pass DW-60048,60049 314/2015 Ra-226 0.84 +/-0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169,1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/912015 Gr. Bela 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 411312015 H-3 1,628 +/- 139 1,695 +/- 141 1,662 +/- 99 Pass SG-1847,1848 4/20/2015 K-40 3.24+/-1.18 1.99 +/- 0.76 2.62 +/- 0.70 Pass SG-1847,1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847,1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/2312015 H-3 6,584 +/-244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/2712015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/-64.3 Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)" Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/-3.63 43 .61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/-2.02 51.40 +/- 1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 ;!; 0.62 13.67 +/- 0.40 Pass SG-1868,1869 4/28/2015 Ra-228 20.10 +/-0.92 22.10 +/- 1.29 21 .10 +/- 0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087 ,60088 5/14/2015 Ra-226 1.58 +/-0.17 1.52 +/-0.17 1.55 +/- 0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/-0.61 47.80 +/-0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/-7.9 254.6 +/- 7.6 261 .2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10 +/-0.92 40.80 +/-0.83 40.95 +/- 0.62 Pass DW-60095 ,60096 5/26/2015 Gr. Alpha 1.34 +/-0.69 0.91 +/-0.62 1.13+/-0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/-0.14 1.08 +/-0.12 0.97 +/- 0.09 Pass
/
S-2627,2628 5/29/2015 Cs-137 0.07 +/-0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/-0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11 .15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/-214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/-658 20,987 +/- 600 21 ,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-301 07,30108 6/8/2015 Gr. Alpha 1.34 +/-0.82 1.47 +/- 0.85 1.41 +/- 0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/- 0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841 .9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Bela 0.023 +/- 0.004 O.D18 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78 +/-0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass j VE-3300,3301 6/24/2015 K-40 29.12 +/-0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass ! AP-062915 WW-3632,3633 6/29/2015 6/30/2015 Gr. Beta H-3 0.023 :l: 0.005 5,169 +/- 225 0.023 +/- 0.005 5,058 +/- 223 0.023 +/- 0.003 5,114+/-158 Pass Pass II I! it
"~
f* ( f \ ~ t N AS-2 [
)'
f f f r
\ TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"
Averaged Lab Code Dale Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-03 2,332 +/- 233 2,108 +/- 211 2,220 +/- 157 Pass WW-fl377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/-83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1{2015 Be-7 2.02 +/-0.32 1.98 +/- 0.25 2.00 +/-0.20 Pass G-5461,2 10/1/2015 K-40 8.77 +/-0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/- 0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/-0.04 0.52 +/-0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/-0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17+/-0.73 2.10 +/-0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/-0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/-0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/-0.03 0.25 +/-0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/20t5 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31 .36 +/- 2.08 29.80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/-0.29 4.13 +/- 0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/-0.06 0.24 +/-0.06 0.22 +/- 0.04 Pass _/ SS-5818, 5819 10/14/2015 Cs-137 0.03 +/-0.02 0.02 :1:0.01 0.03 :1:0.01 Pass i., SS-5818, 5819 10/14/2015 Gr. Beta 8.10 :1:0.87 8.08 +/-0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass 88-5818,5819 10/14/2015 Ra-226 0.47 +/-0.24 0.45 +/- 0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 1-0115/2015 Ra-228 0.79 +/- 0.48 1.16+/-0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/-0.15 1.14 +/-0.15 1.11 +/-0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/-0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-t37 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/-0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06+/-0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0 -5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/- 0.43 *2.16 +/- 0.37 2.14 +/- 0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28 +/- 1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 1-70 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/-0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bl-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/-0.03 0.19 +/- O.D3 0.1'8 +/- 0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21 .6+/- 1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/-0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/201 5 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass l i J 1 I I I I j (
- , I A5-4 1
f f
TABLE A-5. In-House "Duplicate" Samples Concentration (pCill)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Pass Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 Pass S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 :1; 0.03 0.17 +/- 0.02 Pass S0-6841, 6842 11/24/2015 K-40 13.62 +/-0.76 13.67 +/-0.69 13.64 :1; 0.51 Pass WW-f>978, 6979 11130/2015 H-3 569.0 +/-97.7 480.3 +/-93.9 524.7 +/- 67.8 Pass SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81 .2 164.0 +/- 57.0 Pass SW-7017, 7018 12/1012015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0+/-68.1 Pass LW-7020, 7021 12/10/2015 H-3 236.9 +/-84.2 285.6 +/- 86.5 261.2 +/-60.3 Pass AP-7351, 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 Pass
- AP-7414, 7415 12/3012015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Pass Note: Duplicate analyses an~ performed on every twentieth sample received in-house. Results are not listed tor those analyses with activities that measure below the LLD.
- Results are ~ported In units of pCVL, except for air filters (pCI/Filter or pCVm3), food products, vegetation, soil, sediment (pClfg).
\
I j ( I I 1 A5-5 f
~
I i
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration
- Known Control Lab Code b Date Analysis Laboratory result Activity Limits " Acceptance MAS0-975 2/1/2015 Nl-63 341 +/- 18 448 314 - 582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 2/1/2015 Tc-99 614 +/- 12 867 607-1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475-881 Pass 0
MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA Pass 0 MAS0-975 2/1/2015 Co-57 0.5 :t 1.0 0.0 NA Pass MAS0-975 2/1/2015 Co-60 741 +/-8 817 572 - 1,062 Pass MAS0-975 2/1/2015 Mn-54 '},153 +/-9 1,198 839 - 1,557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 -1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21 .1 :1:0.3 23.5 16.5 -30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4-24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 :f: 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569:!: 13 563 394 - 732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.68 4.82-8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NAC Pass
/
MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass
\. MAW-969 2/1/2015 Zn-65 16.5 :f: 0.9 18.3 12.8 ~23. 8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23-4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/-0.03 0.01 NA " Pass MAW-969 2/1/2015 Pu-239/240 0.81:1:0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104-0.192 Pass MAW-969 2/1 /2015 U-238 0.84 +/- 0.09 0.97 0.68 -1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/201 5 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72:1:0.06 2.79 1.40-4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/-0.12 1.49 1.04 -1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA" Pass MAAP-978 r 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fall MAAP-978 211/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83+/-0.10 0.83 0.58 - 1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.06-0.11 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069-0.129 Pass
(' I
\, ,
A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control lab Codeb Date Anal¥sls Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33,3 - 61 .8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74- 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59:1:0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95:1:0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.1 3 7.32 5.12 -9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01- :1:0.04 0.00 NA c Pass MAVE-972 2/1-/2015 Co-60 3.89:1:0.20 5.55 3.89 -7.22 Pass 0 MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NA Pass 0 MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0,110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 - 0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass
/
MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61 .8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 - 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/20t5 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - U3 Pass MAVE-972 2/1/2015 Cs-134 6.98 :1:0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -1 1.93 Pass MAVE-972 2/1/20t5 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89-7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/-0.07 0.00 NA " Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477 -887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298-553 Fail MAS0-4903 9 8/1/2015 Sr-90 352 +/- 10 425 298-553 Pass MAS0-4903 h 811/2015 Tc-99 411 +/- 11 631 442 -820 Fail I MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 - 1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 ~ 1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1,180 826 -1 ,534 Pass MAS0-4903 8/1/2015 Co-60 2+/-2 1.3 NA" Pass MAS0-4903 8/1/2015 Mn-54 1,331 :1: 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463
- 861 Pass
{ A6-2
TABLE A-6 . Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 -30.0 Pass 0 MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1- 0.0 NA Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 -27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0 -22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151 .0-281.0 Pass 1 MAW-5007 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 -17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0-11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7-18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 -9.35 Pass MAW-5007 8/1/2015 Sr-90 4 .80 +/- 0.50 4.80 3.36 -6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13-0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 -5.28 Pass MAW-5007 8/1/2015 1-129 1.42 :!:0.13 1.49 1.04 -1.94 Pass
/
MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79-5.17 Pass ( MAAP-4911 8/1/2015 Sr-90 0.94 t 0.16 1.05 0.74-1.37 Pass
\
MAAP-4907 8/1/2015 Gr. Alpha 0.30 t 0.04 0.90 0.27 -1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78-2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/-0.16 5.80 4.06 -7.54 Pass 0 MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA Pass MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63-8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/-0.15 4.56 3.19-5.93 Pass MAVE-4901 8/1/20t5 Mn-54 8.25 +/-0.25 7.68 5.38-9.98 Pass MAVE-4901 81t/2015 Zn-65 5.78 +/- 0.29 5.46 3.82-7.10 Pass
- Results are reported in units of Bq/kg (soil), Bq!L (water) or Bqftotal sample (filters, vegetation).
blaboratory co<les as follows: MAW (water), MMP {air filter), MASO (soil), MAVE (vegetation). c MAPEP results are presented as the known values and expected laboratory precision {1 sigma, 1 detennination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a false positive". MAPEP does not provide control limits. d Lab result was 27.84. Data entry error resulted in a non-acceptable result.
- Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
1 Lab result was 1.58. Data entry error resulted in a non-acceptable result. 0 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable. h The complex sample matrix is interfering with yield calculations causing a failed low resull An investigation is in process to determine a more reliable yield determination. 1 The known activity was below the routine laboratory detection limits for the available aliquot fraction. / A6-3
\ TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 8
- Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/-2.2 49.8 30.7. 67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61 .2-98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/-34.7 909.0 578.0 -1 '130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312 +/- 12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/-48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3116/2015 Mn-54 <2.7 <50 0.0-50.0 Pass ERAP-1091 3/16/2015 Pu-238 51 .0 +/-3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 - 52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 - 145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21 .3-51 .7 Pass ERAP-1091 3/16/2015 U-238 31 .0 +/- 1.1 34.0 22.0 - 47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/-0.7 62.2 20.8 - 96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/-0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 1571 .8 +/-209.6 1,500 878 - 1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/- 455.7 1,780 414 -2,620 Pass
/ 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass
'\ ERS0-1098 ERS0-1098 3/16/2015 Co-60 1779.8 +/- 41 .0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180 -7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/- 41 .9 1,490 1,140 - 1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810 - 14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1 ,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806-1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/-93 4,530 2,640 - 6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 - 1 ,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185 +/- 140 1,210 791 -1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724 +/- 125 1,940 740-3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/-948 3,890 1,230
- 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/-226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/-232 3,890 2,410 - 4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680
- 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11 .5 119.0 42.2 -184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/-4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 - 14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/-266 4,340 2,650 - 5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 - 2,120 Pass A7-1
TABLEA-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 3 . Concentration {pCI/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Resultd Limits Acceptance ERVE-1100
- 3116/2015 Co-BO 1,030 +/- 29 1,540 1,060 - 2,150 Fail ERVE-1100 t 3/16/2015 Co-BO 1,684 +/-48 1,540 1,060-2,150 Pass ERVE-1100
- 3/16/2015 Cs-134 1,615 +/-27 2,650 1'700 - 3,440 Fail ERVE-1100 1 3/16/2015 Cs-134 2,554 +/-49 2,650 1'700 - 3,440 Pass ERVE-1100 e 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 -2,520 Fail ERVE-1100 1 3/16/2015 Cs-137 2,078 +/- 68 1,810 1,310 - 2,520 Pass ERVE-1100 " 3/16/2015 K-40 22,037 +/-463 30,900 22,300
- 43,400 Fail ERVE-1100 t 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass ERVE-1100
- 3/16/2015 Mn-54 <13.8 <300 0.0 -300.0 Pass 1
ERVE*1100 3/16/2015 Mn-54 <24.4 <300 0.0-300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/-232 3,680 2,190 - 5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/-240 4, 180 2.570 - 5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/-326 6,590 3,760 -8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 - 4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 - 3,980 Pass ERVE-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 - 1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31 .0 -61.7 Pass (
- ERW-1103 ERW-1103 3/16/2015 3/16/2015 Co-60 Cs-134 1,217 +/- 17 1,121 +/- 18 1,250 1,260 i ,090 - 1,460 925 -1,450 Pass Pass
\, ERW-1103 3/16/2015 Cs-137 1,332 +/-31 1,360 1'150 -1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 - 232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/-4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7-75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/-136 1,180 984 - 1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149 +/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860 .0 +/-37.0 912.0 594.0 -1,210.0 Pass
- 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).
b laboratory codes as follows: ERW {water}, ERAP (air filter}, ERSO (soil), ERVE {vegetation). Results are reported In units of pCiiL, except for air filters (pCUFilter), vegetation and soil (pCI/kg). c Unless otherwise Indicated, the laboratory result Is given as the mean :t standard deviation for three detenninatlons. d Results are presented as the known values, expected laboratory precision (1 sigma. 1 detenninatlon) and control limits as provided by ERA. A known value of "zero* indicates an analysis was Included in the testing series as a false positive". Control limits are not provided.
"Technician error weighing sample caused submitted gamma results to be understated and outside the control Jimits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).
9 The results of reanalysis were outside the control limits (low). h sample ERW-3742 was ordered from E~ to determine why ERW-11 03 results for Pu-239 were outside the acceptable range. The results for ERW-3742 were acceptable. No reason for the unacceptable results for ERW-3742 was determined. A7-2
APPENDIX 8 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 = 2cr 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 4.66a uncertainty for a background sample. 3.0. Duplicate anaivses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x, :1: s1 and ~ +/- s2 Reported result: x :1: s; where x = (1/2) (x1 + x2), and s = (1/2) ~ + s; s; 3.2. Individual results: < L1 , < L2 Reported result:< L, where L =lower of L1 and L2 3.3. individual results: x :1: s, < L Reported result: x*:t 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 exal!!ple, 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, x *** xn are defined 2 as follows: X =n1 LX s---~ -\j~ 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 LLO 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 following those to be retained Is equal to or 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
,(
APPENDIXC (
- . Sampling Program and Locations C-1
POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)" (and Frequency)b (and Frequency)b Airborne Filters 6 E-1-4, 8, 20 Weekly GB, GS, on QC 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 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 I 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 I \ *, as available Fish E-13 2x /year GB, GS (in edible portions) as available
- 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 2011 -2015 0.050 C'? 0.030 ~--___,;f!L--.J.--,~-J-l.-1----\-.---+.--l+-\----4>c...J..J.---Ji?..-l-
.§
~ 0.020 -I----\----,'L-----G--+------,IA--i-.\,!----'\--.,..¥--\-+-----l,-_,6---.:.___,...
0.010 -----~------------- 0.000 +H+H-+1-t++++-t++++-H+I-++-I+H+H+H-++-I+H-++++++++-~f-HIIH-1-HIIH-1+-IIIH-1++-ilI ij 2011 2012 2013 2014 2015 2016 Year Location E-2, monthly averages 2011-2015 0.050 0.040 0.030 C'? E
.(3
- 0. 0.020 0.010 0.000 2011 2012 2013 2014 2015 2016 Year l
D-2
POINT BEACH Air Particulates- Gross Beta Location E-3, monthly averages 2011-2015 0.050 0.040 C"? E 0.030 0c. 0.020 Af ~ 0.010 0.000 --HI 2011 2012 2013 2014 2015 2016 Year Location E-4, monthly averages 2011-2015 0.050 0.010 +-- - - - -- - - - - - - - - - - - - - - 0.000 ++-++++++t++++-H+IHI1+1HI1+1HI1+1HI1+1-HI1+1+-II1+1+-II1-tl-1-111-+1+111-+1+1HI1+1HI,+1HI1+1+-II1+1+-II1+1 I
+-Ill 2011 2012 2013 2014 2015 2016 Year
/ l D-3
POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2011-2015 0.050 0.040 (") 0.030 E ~~ 0 0.020 0. 0.010 0.000 2011 2012 2013 2014 2015 2016 Year Location E-20, monthly averages 2011 -2015
/
I
'* 0.050 0.040 +-------"'l>-l~>-----------
(") 0.030 ~~-~+-----+--"f-----++fr-----~1---~ E
~ 0.020 +---\-;-J-=------':...+-1'---~'f---.-~~~---*~-...;--r:-~
0.010 + - -- -- - - -- - - - - -- -- - -
- 0. 000 +H-+++H-HI-t-H++++H-++++-t+t+t-1-t-H++++H++++-t+H-HI-+H-++t+++-H+-1 2011 2012 2013 2014 201 5 2016 Year
( D-4
POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses .( \. E-1
POINT BEACH NUCLEAR PLANT
/ Supplemental Analyses a
\
Units: = pCi\L Gamma isotopic analysis Location U2FSSDS U2FSSDS U2FSSDS Collection Date 01 15 02-15-15 03-26-15 Lab Code EWW- 508 MDC EW- 993 MDC EW- 1501 MDC Be-7 2.4 +/- 9.8 < 29.7 1.2 +/- 11 .3 < 26.7 -8.3 +/- 8.8 < 15.3 Mn-54 0.3 :t 1.2 < 2.3 1.4 +/- 1.4 < 3.0 -0.3 +/- 1.2 < 2.6 Fe-59 3.5 +/- 2.1 < 5.7 -0.8 +/- 2.9 < 3.7 1.2 +/- 2.0 < 4.4 Co-58 0.3 +/- 1.2 < 3.3 0.8 +/- 1.3 < 1.9 -0.4 +/- 1.1 < 2.4 Co-60 0.4 +/- 1.2 < 1.9 0.5 +/- 1.5 < 2.2 -0.8 +/- 1.3 < 2.1 Zn-65 -0.7 +/- 2.2 < 4.7 0.7 +/- 2.9 < 4.4 1.0 +/- 2.3 < 4.7 Zr-Nb-95 -1.8 +/- 1.3 < 2.7 -0.5 +/- 1.4 < 4.0 -1.0+/-1.2 < 2.4 Cs-134 0.5 +/- 1.2 < 2.2 0.1 +/- 1.4 < 2.4 1.1 +/- 1.1 < 2.1 Cs-137 1.4 +/- 1.4 < 2.6 0.6 +/- 1.5 < 2.5 1.1 +/- 1.4 < 2 .7 Ba-La-140 -2.8 +/- 1.5 < 7.7 1.3 +/- 1.5 < 8.0 0.3 +/- 1.3 < 4 .6 Location U2FSSDS MH Z-067C U2FSSDS Suspended solids Collection Date 04-30-15 04-23-15 06-02-15 Lab Code EW- 2227 EW- 2050 EW- 2747 Be-7 -18.3 +/- 13.8 < 29.7 ~0.001 +/- 0.016 < 0.033 -5.7 +/- 13.7 < 29.2 Mn-54 0.4 +/- 1.7 < 3.4 0.000 +/- 0.002 < 0.004 1.8 +/- 1.5 < 3.2 Fe-59 -0.7 +/- 3.1 < 7.4 0.004 +/- 0.004 < 0.014 1.7 +/- 2.9 < 5 .0 l*,
\
Co-58 -0.8 +/- 1.6 < 2.2 0.001 +/- 0.002 < 0.005 0.4 +/- 1.5 < 2.1 Co-60 1.7 +/- 1.6 < 2.9 -0.002 +/- 0.002 < 0.003 3.1 +/- 1.7 < 3.1 Zn-65 1.5 +/- 3.4 < 2.2 -0.002 +/- 0.005 < 0.007 1.6 +/- 3.4 < 4.9 Zr-Nb-95 0.4 +/- 1.5 < 2.6 -0.007 +/- 0.002 < 0.010 -1 .8 +/- 1.8 < 3.0 Cs-134 1.2 +/- 1.6 < 3.1 -0.001 +/- 0.002 < 0 .004 0.0 +/- 1.6 < 2.7 Cs-137 -0.1 +/- 1.7 < 2.9 0.001 +/- 0.002 < 0.004 1.3 +/- 1.8 < 3.4 Ba-La-140 -1.6 +/- 1.8 < 3.4 -0.005 +/- 0.002 < 0.036 -1.4. +/- 2.0 < 3.4 Location U2FSSDS U2FSSDS U2FSSDS Collection Date 06-30-15 08-31-15 09-30-15 Lab Code EW" 4025 EW- 4951 EWW- 6410 Be-7 -1 .6 +/- 13.1 < 21 .9 5.4 +/- 10.8 < 27.7 8.0 +/- 10.2 < 41 .1 Mn-54 2.1 +/- 1.6 < 3.3 -0.9 +/- 1.4 < 3.1 1.2 +/- 1.3 < 2.8 Fe-59 - 1.5 +/- 3.1 < 7.8 -2.3 +/- 2.5 < 5.2 2.4 +/- 2.4 < 8.2 Co..S8 0.2 +/- 1.5 < 2.8 -1.0 +/- 1.3 < 2.1 -0.1 +/- 1.3 < 3.5 Co-60 0.0 +/- 1.6 < 1.8 -2.0 +/- 1.5 < 2.3 0.2 +/- 1.3 < 1.9 Zn-65 0.4 +/- 3.4 < 4.6 0.4 +/- 2.6 < 4.4 0.3 +/- 2.7 < 4.7 Zr-Nb-95 -0.8+/-1 .7 < 3.6 -0.3 +/- 1.5 < 3.2 -2.4 +/- 1.3 < 3.5 Cs-134 0.5 +/- 1.6 < 3.1 -0.3 +/- 1.4 < 2 .5 -0.7 +/- 1.3 < 2.5 Cs-137 -0.8 +/- 1.7 < 2.5 0.4 +/- 1.5 < 2.6 2.3 +/- 1.5 < 3.0 a Ba-La-140
- 4.9 +/- 1.8 < 6.7 -2.9 +/- 1.6 < 5 .5 - 3.5 +/- 1.5 < 19.7
- LLD not reached due to age of sample; received 11-06-15.
~~ E-2
POINT BEACH NUCLEAR PLANT ( Supplemental Analyses Units: =pCi\L
- Gamma isotopic analysis Location E-F1A E-F18 E-F2 Corn Corn Hay Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5135 MDC EVE- 5136 MDC J;VE- 5137 MDC Gross Beta 2.66:!: 0.06 < 0.025 2.82 +/- 0.07 < 0.024 5.11 +/- 0.15 < 0.073 Be-7 0.18+/-0.10 0.12 +/- 0.05 4.41 +/- 0.25 K-40 2.60 +/- 0.22 1.28 +/- 0.15 2.88 +/- 0.26 Mn-54 0.004 +/- 0.004 < 0.005 0.000 +/- 0.003 < 0.006 0.006 +/- 0 .007 < 0.015 Fe-59 0.001 +/- 0.009 < 0.011 -0.001 +/- 0.006 < 0.010 0.009 +/- 0.015 < 0.028 Co-58 0.001 +/- 0.004 < 0.006 0.000 +/- 0.002 < 0.004 -0.001 +/- 0.007 < 0.017 Co-60 0.006 +/- 0.005 < 0.009 0.001 +/- 0.003 < 0.002 -0.009 +/- 0.007 < 0.009 Zn-65 0.008 +/- 0.012 < 0.021 0.001 +/- 0.007 < 0.009 0.002 +/- 0.017 < 0.022 Zr-Nb-95 -0.004 +/- 0.004 < 0.009 -0.004 +/- 0.003 < 0.003 -0.005 +/- 0.008 < 0.016 Cs-134 0.003 +/- 0.004 < 0.009 0.001 +/- 0.003 < 0.006 0.001 +/- 0.008 < 0.016 Cs-137 0.002 +/- 0.005 < 0.010 0.003 +/- 0.003 < 0.006 0.005 ;f: 0.008 < 0.018 Ba-La-140 0.001 +/- 0.004 < 0.010 -0.005 +/- 0.003 < 0.005 0.000 +/- 0.006 < 0 .026 Location E-F3 E-F4 E-F5 Hay Corn Alfalfa Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5138 EVE- 5139 EVE- 5140
/ ~
Gross Beta 8.12 +/- 0.27 < 0.14 3.59 +/- 0.09 < 0.032 6.70 +/- 0.15 < 0.049
\
Be-7 ' 6.21 +/- 0.42 0.31 +/- 0.11 0.70 +/- 0.15 K-40 6.21 +/- 0.51 2.47 +/- 0.22 6.86 +/- 0.40 Mn-54 -0.001 +/- 0.011 < 0.019 0.003 +/- 0.004 < 0.007 0.005 +/- 0.006 < 0.013 Fe-59 0.012 +/- 0.023 < 0.047 -0.002 +/- 0.010 -:= 0.013 0.001 +/- 0.013 < 0.025 Co-58 0.004 +/- 0.011 < 0.024 0.002 +/- 0.004 < 0.005 -0.002 +/- 0.006 < 0.011 Co-60 -0.005 +/- 0.012 < 0.014 0.000 +/- 0.005 < 0.004 0.002 +/- 0.008 < 0.012 Zn-65 -0.020 +/- 0.030 < 0.028 0.004 +/- 0.010 < 0.016 0.009 +/- 0.016 < 0.032 Zr-Nb-95 0,004 +/- 0.011 < 0.025 0.001 +/- 0.004 < 0.008 0.000 +/- 0.007 < 0.014 Cs-134 -0.007 +/- 0.012 < 0.024 0.002 +/- 0.004 < 0.009 0.003 +/- 0.006 < 0.010 Cs-137 0.000 +/- 0.013 < 0.022 0.000 +/- 0.004 < 0.007 0.006 +/- 0.007 < 0.012 Ba-La-140 0.001 +/- 0.011 < 0.026 -0.002 +/- 0.004 < 0.009 -0.004 +/- 0.005 < 0.009 Location E-F6 E-F7 E-FB Alfalfa Alfalfa Soybeans Collection Date 09-17-15 09-17-15 09-17-15 Lab Code EVE- 5141 EVE- 5142 EVE- 5143 Gross Beta 6.16 +/- 0.14 < 0.054 6.40 +/- 0.13 < 0.043 4.68 +/- 0.12 < 0.048 Be-7 1.30 +/- 0.18 0.35 +/- 0.13 1.42 +/- 0.20 K-40 5.98 +/- 0.45 6.45 +/- 0.39 3.74 +/- 0.32 Mn-54 0.004 +/- 0.007 < 0.012 0.003 +/- 0.005 < 0.010 0.004 +/- 0.006 < 0.011 Fe-59 0.002 +/- 0.017 < 0.024 0.000 +/- 0.013 < 0.018 0.003 +/- 0.012 < 0.013 Co-58 0.001 +/- 0.007 < 0.012 0.004 +/- 0.006 < 0.011 0.002 +/- 0.006 < 0.009 Co-60 -0.004 +/- 0.008 < 0.011 0.003 +/- 0.006 < 0.010 -0.001 +/- 0.007 < 0.007 Zn-65 0.004 +/- 0.020 < 0.022 -0.003 +/- 0.017 < 0.023 -0.008 +/- 0.014 < 0.011 Zr-Nb-95 0.004 +/- 0.007 < 0.013 -0.001 +/- 0.006 < 0.010 -0.004 +/- 0.005 < 0.009
/ Cs-134 -0.001 +/- 0.007 < 0.015 0.004 +/- 0.005 < 0.011 -0.002 +/- 0.005 < 0.010 j
Cs-137 -0.001 +/- 0.008 . < 0.014 0.009 +/- 0.006 < 0.010 0.005 +/- 0.005 < 0.008
' Ba-La-140 -0.003 +/- 0.007 < 0.023 0.002 +/- 0.005 < 0.010 -0.014 +/- 0.006 < 0.017 E-3
POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location E-F9 Corn U2FSSDS U2FSSDS Collection Date 09-17-15 10-31-15 12-07-15 Lab Code EVE- 5144 MDC EW- 6411 MDC EW- 6978 MDC Gross Beta 3.11 +/- 0.08 < 0.033 Be-7 1.58 +/-0.16 -3.9 +/- 22 .2 < 30.5 -0 .7 +/- 10.3 < 21.8 a K-40 1.98 +/- 0.21 Mn-54 0.005 +/- 0.005 < 0.009 -0.1+/-2.4 < 2.4 -0.6 +/- 1.3 < 2.0 Fe-59 0.012 +/- 0.010 < 0.022 -1 .5 +/- 4.9 < 11.4 0.7 +/- 2.5 < 4.6 Co-58 -0.005 +/- 0.005 < 0.004 -0.2 +/- 2.3 < 5.1 -1.4 +/- 1.2 < 2 .1 Co-60 0.004 +/- 0.005 < 0.007 0.6 +/- 2.6 < 2.3 1.2 +/- 1.2 < 2 .2 Zn-65 0.002 +/- 0.010 < 0.015 -1.3 +/- 5.7 < 9.6 0.0 +/- 2.4 < 4 .0 Zr-Nb-95 -0.003 +/- 0.005 < 0.008 -2.6 +/- 2.6 < 4.4 -0.5 +/- 1.3 < 2.9 Cs-134 -0 .001 +/- 0.005 < 0.009 -0 .3 +/- 2.6 < 5.1 0.2 +/- 1.3 < 2.5 Cs-137 -0.002 +/- 0.005 < 0.006 0.9 +/- 2.9 < 5.7 0.2 +/- 1.5 < 2.5 Ba-La"-140 0.000 +/- 0.005 < 0.008 0.4 +/- 2.8 < 7.5 0.2 +/- 1.6 < 2.6 Location U2FSSD MDC Collection Date 12-31-15 Lab Code EWW- 7465 Be-7 -8.5 +/- 10.1 < 54.1 Mn-54 0.9 +/- 1.3 < 3.1 Fe-59 1.0 +/- 2.3 < 14.0 Co-58 1.0 +/- 1.2 < 5.2 Co-60 0.5 +/- 1.4 < 2.8 Zn-65 -0.4 +/- 2.5 < 6.6 Zr-Nb-95 -4.7 +/- 1.3 < 6.2 Cs-134 0.5 +/- 1.3 < 2.6 Cs-137 -0.8 +/- 1.5 < 2.0 Ba-La-140 -36 .2 +/- 1.5 < 117.7 a Analysis not required . b LLD not reached due to age of sample; sample received and counted 03-11-16. E-4
POINT BEACH NUCLEAR PLANT { Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 02-27-15 02-27-15 02-27-15 02-27-15 Lab Code EWW- 867 MDC EWW- 868 MDC ND" MDC EWW- 869 MDC Be-7 0.4 +/- 17.3 < 28.9 -3.9 +/- 15.2 *< 31 .0 -2.1 +/- 12.5 < 24.6 Mn-54 0.0 +/- 1.8 < 3.0 0.7 +/- 1.6 < 3.0 0.1 +/- 1.6 < 3.4 Fe-59 -2.0 +/- 3.7 < 5.7 2 .2 +/- 3.0 < 5.6 -1 .8 +/- 3.0 < 3.1 Co-58 1.5 +/- 1.8 < 3.2 2.4 +/- 2.3 < 6.8 0.1 +/- 1.7 < 3.2 Co-60 0.3 +/- 1.9 < 3.5 0.7 +/- 1.7 < 2.7 2 .2 +/- 1.7 < 3 .2 Zn-65 1.7 +/- 4 .0 < 6.2 1.1 :I; 3.4 < 6.2 1.3 +/- 3 .3 < 6 .7 Zr-Nb-95 -0.7+/-1 .9 < 3.9 -1.3+/-1.7 < 3.0 0.1 +/- 1.8 < 4.3 Cs-134 -0.2 +/- 1.9 < 3.8 -1.4+/-1 .7 < 3.5 -0.2 +/- 1.6 < 2 .9 Cs-137 2.5 +/- 2.0 < 3.7 1.3 +/- 1.8 < 4,2 1.8 +/- 1.8 < 3.6 Ba-La-140 * -1.4 +/- 2.2 < 5.1 0.6 +/- 1.6 < 3.0 -0.1 +/- 2 .1 < 5.7 Location GW-091Z-361A GW-09 1Z-361 B GW-10 2Z-361A GW-10 2Z-361B Collection Date 04-12-15 04-12-15 04-12-15 04-12-15 Lab Code EWW- 2515 EWW- 2516 EWW- 2517 EWW- 2518 Be-7 18.4 +/- 14.6 < 42.6 7.9 :I; 14.9 < 45.4 26.0 +/- 15.3 < 4:_7 .5 23.3 +/- 14.4 < 42.2 Mn-54 1.4 :I; 1.8 < 4.1 1.1 +/- 1.8 < 2.6 0.7 +/- 1.9 < 3.8 1.9 +/- 1.7 < 3.7 Fe-59 -1.1 :I; 3.5 < 11.5 1.8 +/- 3.8 < 13.0 -4.7 +/- 3.8 < 11 .9 1.9 +/- 3.5 < 14.2 Co-58 1.3 :I; 1.6 < 3.7 -1.5 :I; 1.6 < 3.0 -0.1 +/- 1.7 < 4 .2 2.1 +/- 1.9 < 5.2 ( Co-60 0.3 :I; 2 .0 < 2.9 -0.7 +/- 2.1 < 4.1 -0.2 :I; 2.0 < 3.7 1.1 :I; 1.9 < 3.4 i'*,1 Zn-65 -0.9 :I; 3.6 < 4.6 1.2 +/- 3.8 < 7.1 2.4 +/- 4 .1 < 8.0 -0.5 +/- 3.9 < 4.0
\
Zr-Nb-95 -0.7 :I; 1.7 < 5.6 4.5 +/- 1.6 < 6.7 -1.0 :I; 1.9 < 4.6 -3.5 :I; 1.8 < 5.2 Cs-134 0.2 :I; 1.8 < 3.5 0.8 +/- 1.7 < 3.4 -1.4 +/- 1.8 < 3.5 -2.1 +/- 1.9 < 3.4 Cs-137 0.9 :I; 1.9 < 3.7 1.7+/-1.9 < 3.7 -0.1 +/- 1.8 < 2 .9 -1 .0 +/- 1.9 < 4.0 b b Ba-La-140 7.6 :I; 2.0 < 14.3 -6.8 +/- 2.4 < 26.8 -2.3 +/- 2 .0 < 19.6 18.5 +/- 2 .2 < 37.2 Location GW-09 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 08-08-15 08-08-15 08-08-15 08-08-15 Lab Code EWW- 4709 EWW- 4710 EWW- 4711 EWW- 4712 Be-7 -2.5 +/- 17.1 < 38.4 5.4 +/- 15.3 < 38.1 -4.9 :I; 16.7 < 34.5 1.1 +/- 15.4 < 23.3 Mn-54 1.0 +/- 1.7 < 3.3 -0.1 +/- 1.6 < 3.6 -0.4 +/- 1.7 < 3.3 1.5 +/- 1.6 < 3.5 Fe-59 0.4 +/- 3.4 < 10.2 1.1 +/- 2.9 < 8.2 -3.7 +/- 3.5 < 6.0 -0.5 +/- 2.8 < 7.7 Co-58 -0.7+/-1.7 < 4 .0 1.1 +/- 1.6 < 4.4 -0.8 +/- 1.7 < 4.0 -0.4+/-1 .6 < 3.5 Co-60 0.6 +/- 1.9 < 2.9 0.2 +/-1 .8 < 3.3 1.4 +/- 1.8 < 1.8 -0.5+/-1.8 < 3.3 Zn-65 -4.9 +/- 4.0 < 5.8 -3.5 +/- 3.1 < 5.0 -5.2 +/- 4.3 < 6.4 0.2 +/- 3.1 < 6.4 Zr-Nb-95 -2.5+/-1.8 < 5.0 -2.7 +/- 1.7 < 4.4 -1 .1 +/- 1.9 < 5.9 -1.2 +/- 1.8 < 4.9 Cs-134 -0.2 +/- 1.8 < 3.7 -1.3 +/- 1.7 < 3.1 -0.8 +/- 1.8 < 3.7 -0.4 +/- 1.7 < 3.5 Cs-137 1.1+/-2.0 < 4.0 0.3 +/- 2.0 < 3.5 -0.6 +/- 2 .1 < 3.2 1.6 +/- 1.9 < 4.0 Ba-La-140 -0.4+/-1.9 -< 10.8 -0.9 +/- 2.0 < 11.3 -2.6 :t 1.8 < 13.5 -1.2 +/- 2.1 < 16.0
* *"ND" =No data; water frozen.
"LLD not reached due to age of sample and smaller sample volume (received 05-21-15/500 mL).
E-5
POINT BEACH NUCLEAR PlANT ( Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 10-15-15 10-15-15 10-15-15 10-15-15 Lab Code EWW- 6210 MDC EWW- 6211 MDC EWW- 6212 MDC EWW- 6213 MDC Se-7 9.9 +/- 12.0 < 34.3 -10.4 +/- 10.0 < 29.4 5.6 +/- 11 .8 < 28.8 -1 .3 +/- 11 .3 < 22.5 Mn-54 -0.2 +/- 1.2 < 1.9 -0.2 +/- 1.2 < 2.8 0.9 +/- 1.2 < 2.3 -0.1 +/- 1.1 < 2.2 Fe-59 2.5 +/- 2.3 < 5.7 0.6 +/- 2.3 < 4.5 0.2 +/- 2.4 < 4.0 -0.7 +/- 2.3 < 4.4 Co-58 0.1 +/- 1.3 < 2.4 -0.7 +/- 1.2 < 2.0 0.2 :i; 1.2 < 1.9 1.7 +/- 1.2 < 3.2 Co-60 0.9 :j; 1.5 < 2.5 0.4 +/- 1.2 < 2.1 0.4 +/- 1.3 < 2.4 -0.5 +/- 1.3 < 2.1 Zn-65 -1.0 +/- 2.7 < 4.5 -1 .8 .:!= 2.4 < 4.6 -2.7 +/- 2.7 < 3.8 -0.7 +/- 2.3 < 3.9 Zr-Nb-95 -1 .1 +/- 1.3 < 2.4 0.9 +/- 1.3 < 3.4 0.7 +/- 1.3 < 3.6 0.0 +/- 1.3 < 3.2 Cs-134 -0.4 +/- 1.3 < 2.6 0.1 +/- 1.3 < 2.4 -0.5 +/- 1.2 < 2.5 -1.4 +/- 1.2 < 2.5 Cs-137 -1.4 +/- 1.4 < 1.8 0.8 +/- 1.4 < 2.5 -0.2 +/- 1.3 < 2.3 0.1 +/- 1.4 < 1.7 Ba-La-140 -0.7 +/- 1.6 < 7.0 -0.9 +/- 1.3 < 7.2 -1.4 +/- 1.3 < 5.2 -0.9 +/- 1.4 < 3.5 l', E-6
POINT BEACH NUCLEAR PLANT
/ 'i \
APPENDIX F Special Analyses [ iJ F-1
f,.
- A-v='R IEnvironrnent:aJ, Inc.
1""'\B D Midwest: ll..aboratory 700 LontJwchr ROIHI* Northbrook, IL 6(){)f;2* 23f0 phone {847) SS4-D700
- TB>< {347) 564--4517 Corrected Report Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1145C Radiation Protection Mgr. DATE: 07-29-15 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-02-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the corrected results of the readout of supplemental TLDs deployed during the first quarter, 2015. Period: 1st Quarter, 2015 Date Annealed: 12/11/14 Date Placed: 01/02/15 Date Removed: 04/01/15 Date Read: 04/14/15 Days in the Field: 89 Days from Annealing to Readout: 124 In-transit exposure: 5.20 +/- 0.32 a
,/
1 Net mRa Net mRa Location Total mR Net mRa Std Qtr per 7 days SGSF-North 19.5 +/- 0.8 14.3 +/- 0.9 14.6 +/- 0.9 1.13+/-0.07 SGSF-East 16.8 +/- 0.8 11.6 +/- 0.8 11.8 +/- 0.8 0.91 +/- 0.06 SGSF-South 18.1 +/- 1.0 12.9+/-1.1 13.2 +/- 1.1 1.02 +/- 0.09 SGSF-West 17.4 +/- 0.5 12.2 +/- 0.6 12.5 +/- 0.6 0.96 +/- 0.04 ISFSI-North 37.6 +/- 0.9 32.4 +/- 1.0 33.1 +/- 1.0 2.55 +/- 0.08 ISFSI-East 45.8 +/- 0.5 40.6 +/- 0.6 41.6 +/- 0.6 3.20 +/- 0.05 ISFSI-South 20.0 +/- 0.7 14.8 +/- 0.8 15.1 +/- 0.8 1.16 +/- 0.06 ISFSI-West 60.9 +/- 3.3 55.7 +/- 3.4 56.9 +/- 3.4 4.38 +/- 0.26 Control 24.3 +/- 0.7 19.1 +/- 0.8 19.6 +/- 0.8 1.50 +/- 0.06 a original report dated 5/7/15 had an incorrect value for the in-transit exposure. The incorrect value caused the each of the original net mR values to be overstated by approximately 1.3 mR per standard quarter.
~~~~
Quality Assurance . { APPROVED \_ cc: K. Johansen
/ J\""FD Environmental. Inc.
'F"\. 0 Y Midwest Laboratory
*{ 700 Landwehr Roed
- Northbrook, /L 60062-2310 phone (847} 564-D700
- IS>< (1147) 664--4517 Mr. Richard Welty LAB ORA TORY REPORT NO.: 8006-100-1150 Radiation Protection Mgr. DATE: 07-29-15 Point Beach Nuclear Plant SAMPLES RECEIVED: .07-03-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2015. Period: 2nd Quarter, 2015 Date Annealed: 03/24/15
- Date Placed: 04/01/15 Date Removed: 07/01/15 Date Read: 07/06/15 Days in the Field: 91 Days from Annealing to Readout: 104 In-transit exposure: 1.78 +/- 0.07 NetmR NetmR
\- Location Total mR NetmR Std Qtr per 7 days SGSF-North 14.7 +/- 0.4 12.9 +/- 0.4 12.9 +/- 0.4 0.99 +/- 0.03 SGSF-East 13.1 +/- 0.2 11.3 +/- 0.2 11.3 +/-0.2 0.87 +/- 0.01 SGSF-South 14.2 +/- 0.5 12.4 +/- 0.5 12.4 +/- 0.5 0.96 +/- 0.04 SGSF-West 14.3 +/- 0.8 12.5 +/- 0.8 12.5 +/- 0.8 0.96 +/- 0.06 ISFSI-North 28.2 +/- 1.4 26.4 +/- 1.4 26.4 +/- 1.4 2.03+/-0.11 ISFSI-East 44.1 +/- 1.5 42.3 +/- 1.5 42.3 +/- 1.5 3.25 +/- 0.12 ISFSI-South 16.6 +/- 1.3 14.8 +/- 1.3 14.8 +/- 1.3 1.14+/-0.10 ISFSI-West 59.3 +/- 2.4 57.5 +/- 2.4 57.5 +/- 2.4 4.42 +/- 0.19 Control 15.9 +/- 0.7 14.1 +/-0.7 14.1 +/-0.7 1.09 +/- 0.05 2:!::~
Quality Assurance APPROVED ( cc: K. Johansen
A-rl Environmental. Inc .
/ .,..,... . I M idwest Lab orat:ory 700 Lenrtwehr Roed
- Norlhbror>k, IL 60062-2310 phone (8 47) M<l-0700
- ft<< (847} M4-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1164C Radiation Protection Mgr. DATE: 12-04-15 Point Beach Nuclear Plant SAMPLES RECEIVED: 09-28-15 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Corrected Report Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2015. 8 Period: 3rd Quarter, 2015 a Date Annealed: 06/08/15 Date Placed: 07/01/15 Date Removed: 09/24/15 Date Read: 10/01/15 Days in the Field: 85 Days from Annealing to Readout: 115 In-transit exposure: 4.09 +/- 0.18
/ NetmR NetmR (i Location Total mR NetmR Std Qtr per 7 days SGSF-North 17.2 +/- 0.9 13.1 +/-0.9 14.0 +/- 0.9 1.08 +/- 0.07 SGSF-East 15.0 +/- 0.7 10.9 +/- 0.7 11.7+/-0.7 0.90 +/- 0.06 SGSF-Soi.lth 16.2 +/- 0.3 12.1 +/- 0.4 13.0+/-0.4 1.00 +/- 0.03 SGSF-West 15.6 +/- 0.5 11.5 +/- 0.6 12.3 +/- 0.6 0.95 +/- 0.05 ISFSI-North 34.2 +/- 0.7 30.1 +/- 0.7 32.2 +/- 0.8 2.48 +/- 0.06 ISFSI-East 40.7 +/- 0.9 36.6 +/- 0.9 39.2 +/- 0.9 3.02 +/- 0.07 ISFSI-South 17.9 +/- 0.6 13.8 +/- 0.6 14.8 +/- 0.7 1.14+/-0.05 ISFSI-West 54.3 +/- 2.8 50.2 +/- 2.8 53.7 +/- 3.0 4.13 +/- 0.23 Control 21.9 +/- 0.8 17.8 +/- 0.8 19.1 +/- 0.8 1.47 +/- 0.06 a The original report had a typographical error referencing the wrong period as footnoted above.
All other reported values were correct as originally reported. u~~~ ~u:~i~ Assurance APPROVED ( cc: K. Johansen
A . , Environmental, Inc.
- 1""\1 I Midwest Laboratory
/ 700 Lvndwehr Road
- Norlhbroolc, /L 60062,-2310 pho,., (1147) U4-l1700
- fox (847) 68~17 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1169 Radiation Protection Mgr. DATE: 02-01-16 Point Beach Nuclear Plant SAMPLES RECEIVED: 01-07-16 NextEraEnergy PURCHASE ORDER NO.:
6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2015. Period: 4th Quarter, 2015 Date Annealed: 09/11/15 Date Placed: 09/24/15 Date Removed: 01/06/16 Date Read: 01/09/16 Days in the Field: 104 Days from Annealing to Readout: 120 In-transit exposure: 2.21 +/- 0.20 / NetmR NetmR Location Total mR NetmR Std Qtr per 7 days SGSF-North 17.5 +/- 0.4 15.3 +/- 0.4 13.4 +/- 0.4 1.03 +/- 0.03 SGSF-East 16.1 +/-0.4 13.9 +/- 0.5 12.2 +/- 0.4 0.94 +/- 0.03 SGSF-South 17.7 +/- 0.7 15.4 +/- 0.7 13.5 +/- Q.6 1.04 +/- 0.05 SGSF-West 18.2 +/- 1.0 16.0 +/- 1.0 14.0 +/- 0.9 1.08 +/- 0.07 ISFSI-North 34.6 +/- 2.4 32.4 +/- 2.4 28.3 +/- 2.1 2.18 +/- 0.16 ISFSI-East 53.7 +/- 1.2 51.5 +/- 1.2 45.1 +/- 1.1 3.47 +/- 0.08 ISFSI-South 20.6 +/- 0.9 18.4 +/- 0.9 16.1 +/-0.8 1.24 +/- 0.06 ISFSI-West 69.0 +/- 0.9 66.8 +/- 0.9 58.4 +/- 0.8 4.50 +/- 0.06 Control 19.3 +/- 0.5 17.1 +/-0.6 14.9 +/- 0.5 1.15+/-0.04 (!::~~~ Quality Assurance APPROVED cc:K.Johansen
~+.L ATf Environmental, Inc. ,-~I""\ I Midwest Laboratory 700 Landwehr Ro*d
- NOI1hbro0k, IL 60062-2310 phone (847} 564-D700
- fax (847} 564-4517 Dr. Kjell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-1 00-1170 Point Beach Nwclear Plant DATE: 02-08-2016 6610 Nuclear Road SAMPLES RECEIVED:
Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.: Below are the results of the analyses for tritium in monthly lake water samples. Sample Collection Lab Concentration I MDC (pCi/L) Location Date Code H-3 E-05 10-14-15 ELW-5785 -47 +/- 90 I< 152 E-05 11-05-15 ELW-6354 -10 +/- 92/ < 152 E-05 12-10-15 ELW-6939 1,336 +/- 139/ < 151 E-33 10-14-15 ELW-5787 -25 +/- 91/ < 152 E-33 11-05-15 ELW-6356 68 +/- 95/ < 152 E-33 12-10-15 ELW-6941 464+/- 111/< 151 E-01 12-10-15 ELW-6938 76 +/- 89/ < 141 E-06 12-10-15 ELW-6940 79 +/- 89/ < 141 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. E-mail: kjell.iohansen@NextERAEnergy.com
~ :zj?/10 APPROVED BY:_-/--P~-:--=-'~-'----:-::----}}