Text

Annual Monitoring Report
	ML101230145
Person / Time
Site:	Point Beach
Issue date:	04/30/2010
From:	Jim Costedio; Point Beach
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	NRC-2010-0062
	Download: ML101230145 (232)
	v • d • e

April 30, 2010 NRC 2010-0062 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 2009 Annual Monitoring R e ~ o r t In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units Iand 2, for the period January 1 through December 31,2009.

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, and miscellaneous monitoring activities which occurred in 2009. 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.

Enclosure 2 contains the PBNP Environmental Manual, which was revised in May 2009.

Enclosure 3 contains the PBNP Radiological Effluent Control Manual, which was revised in January 2009.

This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.

Very truly yours, NextEra Energy Point Beach, LLC/

James Costedio Licensing Manager 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 NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT I ) , 50-301 (UNIT 2),72-005 (ISFSI)

January 1,2009 through December 31,2009

TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 3 2.0 Radioactive Liquid Releases 4 3.0 Radioactive Airborne Releases 9 4.0 Radioactive Solid Waste Shipments 12 5.0 Nonradioactive Chemical Releases 15 6.0 Circulating Water System Operation 16 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 17 Part C: Radiological Environmental Monitoring 8.0 Introduction 18 9.0 Program Description 19 10.0 Results 30 11.0 Discussion 34 12.0 REMP Conclusion 42 Part D: Groundwater Monitoring 13.0 Program Description 43 14.0 Results 46 15.0 Groundwater Summary 53 Appendix 1: Environmental, Inc. Midwest Laboratory, Final Report for Point Beach Nuclear Plant Appendix 2: University of Waterloo (Ontario) Environmental Isotope Laboratory, precipitation ii

LIST OF TABLES Table 2-1 Comparison of 2009 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 (Curies) 7 Table 2-4 Subsoil System Drains - Tritium Summary 8 Table 3-1 Comparison of 2009 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 10 Table 3-2 Radioactive Airborne Effluent Release Summary 10 Table 3-3 Isotopic Composition of Airborne Releases 11 Table 4-1 Quantities and Types of Waste Shipped from PBNP 12 Table 4-2 2009 Estimated Solid Waste Major Radionuclide Composition 13 Table 4-3 2009 PBNP Radioactive Waste Shipments 14 Table 6-1 Circulating Water System Operation for 2009 16 Table 9-1 PBNP REMP Sample Analysis and Frequency 21 Table 9-2 PBNP REMP Sampling Locations 22 Table 9-3 ISFSI Sampling Sites 26 Table 9-4 Minimum Acceptable Sample Size 26 Table 9-5 Deviations from Scheduled Sampling and Frequency 27 Table 9-6 Sample Collection for the State of Wisconsin 27 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2009 32 Table 10-2 ISFSI Fence TLD Results for 2009 34 Table 11-1 Average Indicator TLD Results from 1993-2009 34 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 35 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 36 Table 11-4 Average Gross Beta Measurements in Air 37 Table 11-5 Average Gross Beta Concentrations in Soil 40 Table 14-1 Intermittent Streams and Bogs 46 Table 14-2 2009 Beach Drain Tritium 47 Table 14-3 U2 Façade Subsurface Drainage Sump H-3 49 Table 14-4 Electrical Vault and Other Manholes 49 Table 14-5 2009 Façade Well Water Tritium 50 Table 14-6 2009 Potable Well Water Tritium 51 Table 14-7 2009 Monitoring Well Water Tritium 52 Table 14-8 Precipitation H-3 52 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 23 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 24 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 25 Figure 11-1 2009 Airborne Gross Beta Concentration (pCi/m3) vs. Time 37 Figure 13-1 Groundwater Monitoring Locations 45 Figure 14-1 2009 S-1 and S-3 Beach Drain Concentrations (pCi/l) vs. Time 48 iii

SUMMARY

The Annual Monitoring Report for the period from January 1, 2009, through December 31, 2009, 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 2009, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

Liquid Atmospheric Tritium (Ci) 637 81.6 1

Particulate (Ci) 0.097 0.00050 Noble Gas (Ci) (-) 1.040

(-)Noble gases in the liquids are added to the atmospheric release totals.

1 Atmospheric particulate includes radioiodine (I-131, I-133).

For the purpose of compliance with the effluent design objectives of Appendix I to 10 CFR 50, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as low as reasonably achievable (ALARA). The maximum annual calculated doses in millirem (mrem) or millirad (mrad) 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 0.00602 mrem 6 mrem Organ dose 0.00701 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose Organ dose 0.0321 mrem 30 mrem Noble gas beta air dose 0.00016 mrad 40 mrad Noble gas gamma ray air dose 0.00041 mrad 20 mrad Noble gas dose to the skin 0.00059 mrem 30 mrem Noble gas dose to the whole body 0.00039 mrem 10 mrem The results show that during 2009, the doses from PBNP effluents were a small percentage (0.11% at the most) of the Appendix I design objectives. Therefore, operation of PBNP continues to be ALARA.

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A survey of land use with respect to the location of dairy cattle was made pursuant to Section 2.5 of the PBNP Environmental Manual. As in previous years, no dairy cattle were found to be grazing at the site boundary. Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative.

The 2009 Radiological Environmental Monitoring Program (REMP) collected 814 samples for radiological analyses and 124 sets of thermoluminescent dosimeters (TLDs) to measure ambient radiation in the vicinity of PBNP and the ISFSI. Air monitoring from six different sites showed only background radioactivity from naturally occurring radionuclides. Terrestrial monitoring consisting of soil, vegetation and milk found no influence from PBNP. Similarly, samples from the aquatic environment, consisting of lake and well water, fish and algae revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, the data show no plant effect on its environs.

There were five (5) NUHOMS dry storage units added to the ISFSI in 2009. The total number is now 30 dry storage casks. Sixteen are the ventilated, vertical storage casks (VSC-24) and fourteen (14) are the NUHOMS, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSI showed no environmental impact from its operation.

The environmental monitoring conducted during 2009 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

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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.

A General License was granted pursuant to 10 CFR 72.210, for an Independent Spent Fuel Storage Installation (ISFSI). The release of radioactive materials from the operation of the ISFSI must also comply with the limits of Part 20 and Part 50 Appendix I design objectives. Per 10 CFR 72.44(d) (3), the results of radiological effluent monitoring are to be reported annually.* The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process Holders of a Part 72 license are allowed to submit the report required by 72.44(d)(3) concurrent with the effluent report required by 10 CFR 50.36a (a)(2). (

Reference:

64 FR 33178) 3

will be assessed and quantified as part of the PBNP Radiological Effluent Control Program.

2.0 RADIOACTIVE LIQUID RELEASES The radioactive liquid release path to the environment is via the circulating water discharge. A liquid waste treatment system in conjunction with administrative controls is used to minimize the impact on the environment and maintain doses to the public ALARA from the liquid releases.

2.1 Doses From Liquid Effluent Doses from liquid effluent are calculated using the methodology of the Offsite Dose Calculation Manual (ODCM). These calculated doses use parameters such as the amount of radioactive material released, the total volume of liquid, the total volume of dilution water, and usage factors (e.g., water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. For compliance with 10 CFR 50, Appendix I design objectives, the annual dose is calculated to the hypothetical maximally exposed individual (MEI). The MEI is assumed to reside at the site boundary in the highest /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 2009 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) 0.00602 0.100 %

20 (any organ) 0.00701 0.035 %

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2.2 2009 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis and presented in Table 2-2. These releases are composed of processed waste, wastewater effluent, and blowdown from Units 1 and 2. The wastewater effluent consists of liquid from turbine hall sumps, plant well house backwashes, sewage treatment plant effluent, water treatment plant backwashes, and the Unit 1 and 2 facade sumps.

2.3 2009 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3. The noble gases released in liquids are reported with the airborne releases in Section 3. The isotopic distribution shows slight change from 2008, with tritium up from 2008 but similar to 2006.

Tritium continues to be the major radionuclide released via liquid discharges.

2.4 Beach Drain System Releases Tritium Summary Beach drains is the term used to describe the point at which the site yard drainage system empties onto the shore of the lake. Six of the drains carry yard and roof drain off to the beach. A seventh drains a small portion of the grassy area on top of the bluff overlooking the lake. Each of the drains is sampled monthly. The quarterly results of monitoring the beach drains 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. During 2009, no tritium was observed in any of the beach drains at the effluent LLDs used to detect and quantify tritium released from discreet volumes such as hold up tanks and waste distillate tanks.

Because these drains are subject to ground water inleakage, they are sampled as part of the ground water monitoring program. These beach drain results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report. One of these drains receives water from a groundwater sump under the plant. Others receive yard runoff or roof drainage. The southern most drain was added in May of 2009. This drain carries no roof or yard drainage. It was added to the beach drain sampling program to check on rain from a small, grassy area on the bluff overlooking the beach.

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Table 2-2 Summary of Circulating Water Discharge January 1, 2009 through December 31, 2009 Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci)

Gamma Scan (+Fe-55) 5.22E-04 3.58E-03 9.95E-04 4.57E-03 5.70E-03 1.68E-02 3.22E-02 1.94E-02 1.04E-03 2.25E-03 8.74E-04 2.44E-03 3.83E-02 9.65E-02 Gross Alpha 2.31E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.31E-07 2.02E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-06 Tritium 8.37E+00 1.60E+01 2.43E+01 5.49E+01 3.16E+01 1.06E+02 2.41E+02 1.60E+02 1.81E+01 7.85E+01 5.93E+01 6.18E+01 1.77E+01 6.37E+02 Strontium (89/90/92) 7.69E-05 0.00E+00 0.00E+00 4.29E-07 7.79E-06 7.02E-06 9.21E-05 4.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.76E-06 9.82E-05 Total Vol Released (gal)

Processed Waste 8.04E+03 3.16E+04 1.69E+04 2.22E+04 1.47E+05 7.42E+04 3.00E+05 8.07E+04 3.94E+04 9.05E+04 8.87E+04 1.36E+05 9.65E+04 8.32E+05 Waste Water Effluent* 3.44E+06 3.83E+06 4.08E+06 3.10E+06 2.74E+06 2.63E+06 1.98E+07 2.06E+06 2.26E+06 2.41E+06 3.79E+06 3.40E+06 3.16E+07 6.53E+07 U1 SG Blowdown 3.81E+06 2.73E+06 2.61E+06 2.59E+06 2.64E+06 2.53E+06 1.69E+07 2.59E+06 2.68E+06 2.88E+06 2.47E+06 2.58E+06 2.54E+06 3.27E+07 U2 SG Blowdown 2.52E+06 2.39E+06 2.57E+06 2.53E+06 2.54E+06 2.33E+06 1.49E+07 2.59E+06 2.59E+06 2.55E+06 1.09E+06 0.00E+00 4.17E+06 2.79E+07 Total Gallons 9.78E+06 8.99E+06 9.28E+06 8.25E+06 8.07E+06 7.56E+06 5.19E+07 7.32E+06 7.56E+06 7.93E+06 7.44E+06 6.12E+06 3.84E+07 1.27E+08 Total cc 3.70E+10 3.40E+10 3.51E+10 3.12E+10 3.05E+10 2.86E+10 1.97E+11 2.77E+10 2.86E+10 3.00E+10 2.82E+10 2.31E+10 1.45E+11 4.80E+11 Dilution vol(cc)** 6.62E+13 5.98E+13 6.62E+13 9.09E+13 1.08E+14 1.11E+14 5.02E+14 1.14E+14 1.15E+14 1.11E+14 8.48E+13 5.63E+13 8.31E+13 1.07E+15 Avg diluted discharge conc (Ci/cc)

Gamma Scan (+Fe-55) 7.89E-12 5.99E-11 1.50E-11 5.03E-11 5.28E-11 1.51E-10 1.70E-10 9.04E-12 2.03E-11 1.03E-11 4.33E-11 4.61E-10 Gross Alpha 3.49E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.76E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium 1.26E-07 2.68E-07 3.67E-07 6.04E-07 2.93E-07 9.53E-07 1.40E-06 1.58E-07 7.06E-07 7.00E-07 1.10E-06 2.13E-07 Strontium (89/90/92) 1.16E-12 0.00E+00 0.00E+00 4.72E-15 7.21E-14 6.32E-14 3.74E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.12E-14 Max Batch Discharge Conc (Ci/cc)

Tritium 1.69E-05 2.12E-05 2.37E-05 2.18E-05 1.39E-05 2.10E-05 4.09E-05 1.80E-05 1.76E-05 2.49E-05 4.87E-05 1.40E-05 Gamma Scan 5.88E-10 2.74E-09 8.36E-10 1.05E-09 1.54E-09 5.15E-09 6.63E-09 2.50E-10 4.27E-10 2.59E-10 1.67E-09 2.86E-08

The waste water effluent system replaced the Retention Pond which was taken out of service in September 2002.

- Circulating water discharge from both units.

Note: Dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries 6

Table 2-3 Isotopic Composition of Circulating Water Discharges (Ci)

January, 2009 through December 31, 2009 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 8.37E+00 1.60E+01 2.43E+01 5.49E+01 3.16E+01 1.06E+02 2.41E+02 1.60E+02 1.81E+01 7.85E+01 5.93E+01 6.18E+01 1.77E+01 6.37E+02 F-18 1.19E-04 2.06E-04 3.04E-04 4.14E-04 1.56E-04 3.14E-04 1.51E-03 3.43E-04 3.57E-04 4.88E-05 4.72E-04 1.72E-04 9.04E-04 3.81E-03 Cr-51 0.00E+00 6.56E-05 0.00E+00 0.00E+00 4.24E-06 1.56E-04 2.26E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.86E-05 8.35E-03 8.63E-03 Mn-54 9.37E-06 1.78E-05 1.11E-05 2.78E-05 6.16E-06 7.32E-05 1.45E-04 1.25E-04 3.57E-06 2.75E-06 7.69E-06 0.00E+00 6.26E-04 9.10E-04 Fe-55 0.00E+00 2.27E-04 0.00E+00 1.94E-04 2.78E-03 5.05E-04 3.71E-03 9.16E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.62E-03 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 0.00E+00 0.00E+00 1.49E-04 1.49E-04 Co-57 0.00E+00 2.50E-06 2.64E-06 5.66E-06 1.39E-06 6.49E-06 1.87E-05 4.08E-05 0.00E+00 3.71E-06 0.00E+00 9.42E-07 2.72E-05 9.13E-05 Co-58 2.34E-04 5.97E-04 5.83E-04 7.12E-04 5.14E-04 8.42E-04 3.48E-03 3.35E-03 4.26E-05 1.42E-04 4.59E-05 4.45E-04 6.05E-03 1.36E-02 Co-60 4.08E-05 1.81E-04 8.50E-05 5.60E-04 4.30E-04 7.13E-04 2.01E-03 2.66E-03 2.41E-04 1.84E-04 1.48E-04 2.43E-04 1.62E-02 2.17E-02 Zn-65 0.00E+00 0.00E+00 0.00E+00 1.51E-05 0.00E+00 0.00E+00 1.51E-05 4.06E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.31E-04 3.50E-04 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 9.33E-05 0.00E+00 0.00E+00 9.33E-05 Sr-89 7.69E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.69E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.69E-05 Sr-90 0.00E+00 0.00E+00 0.00E+00 4.29E-07 7.79E-06 7.02E-06 1.52E-05 4.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.95E-05 Sr-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 1.76E-06 1.76E-06 Nb-95 0.00E+00 2.89E-05 0.00E+00 5.00E-05 0.00E+00 0.00E+00 7.89E-05 6.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E-03 1.57E-03 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 1.63E-06 0.00E+00 4.73E-06 0.00E+00 6.36E-06 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 0.00E+00 0.00E+00 8.17E-04 8.17E-04 Ag-110m 5.81E-06 8.85E-05 9.48E-06 3.15E-04 7.19E-05 1.51E-04 6.42E-04 7.68E-05 1.05E-05 3.05E-06 5.82E-05 1.19E-05 2.60E-04 1.06E-03 Sn-113 0.00E+00 1.75E-05 0.00E+00 3.66E-05 0.00E+00 0.00E+00 5.41E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.80E-04 4.34E-04 Sn-117m 1.68E-06 1.75E-04 0.00E+00 8.92E-05 2.27E-06 9.25E-06 2.77E-04 2.15E-05 1.09E-05 3.99E-05 2.83E-05 1.46E-03 1.84E-03 3.68E-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 5.66E-07 0.00E+00 0.00E+00 5.66E-07 Sb-124 0.00E+00 7.84E-05 0.00E+00 0.00E+00 4.80E-05 2.22E-04 3.48E-04 1.95E-05 0.00E+00 0.00E+00 0.00E+00 1.47E-05 3.76E-04 7.59E-04 Sb-125 0.00E+00 1.30E-03 0.00E+00 1.20E-03 8.44E-04 4.30E-03 7.64E-03 7.23E-04 4.27E-05 3.95E-05 1.23E-05 2.07E-05 4.18E-04 8.90E-03 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.67E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.67E-06 Cs-137 0.00E+00 1.50E-04 0.00E+00 1.63E-04 2.63E-05 7.95E-04 1.13E-03 1.23E-03 3.55E-05 3.30E-05 7.61E-06 3.84E-06 1.63E-06 2.45E-03 Ru-103 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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-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 Na-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.58E-06 5.58E-06 Ni-63 3.35E-05 3.23E-04 4.74E-05 6.82E-04 7.79E-04 1.49E-03 3.35E-03 5.19E-03 1.16E-04 5.48E-04 1.28E-04 1.65E-04 4.38E-04 9.94E-03 Tc-99 1.10E-06 1.20E-04 2.56E-06 3.28E-05 3.00E-05 2.08E-04 3.94E-04 8.55E-05 2.24E-06 4.11E-06 8.39E-06 9.29E-06 1.42E-04 6.46E-04 C-14 - - - 7.66E-05 0.00E+00 7.02E-03 7.10E-03 4.58E-03 1.79E-04 1.20E-03 2.11E-04 1.50E-03 0.00E+00 1.48E-02 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, 2009, through December 31, 2009 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) 1.12E+04 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) 7.62E+05 2.40E+05 0.00E+00 2.16E+04 2.07E+03 6.91E+01 1.44E+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) 9.04E+04 4.82E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+02 1.33E+04 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) 7.11E+05 2.04E+05 0.00E+00 0.00E+00 1.41E+05 0.00E+00 1.57E+04 2.6 Land Application of Sewage Sludge The Wisconsin Department of Natural Resources has approved the disposal of PBNP sewage by land application on various NextEra Energy Point Beach, LLC (NextEra) properties surrounding the plant. This sewage sludge, which may contain trace amounts of radionuclides, is to be applied in accordance with methodologies approved by the NRC on January 13, 1988, pursuant to 10 CFR 20.302(a). The approved methodology requires analyses prior to every disposal. Based upon an investigation of the source of the radionuclides, a combination of engineering modifications and administrative controls has eliminated plant generated radiological inputs to the sewage. This was verified by sludge analyses using the environmental lower level of detection (LLD) criteria. No byproduct radionuclides were found in the sludge after the controls and modifications were completed. Sludge is routinely monitored and no radionuclides attributable to PBNP have been found.

There was no disposal of sewage by land application during 2009. All disposals were done at the Manitowoc Sewage Treatment Plant.

8

3.0 RADIOACTIVE AIRBORNE RELEASES The release paths to the environment contributing to radioactive airborne release totals during this reporting period were the auxiliary building vent stack, the drumming area vent stack, the letdown gas stripper, the Unit 1 containment purge stack, and the Unit 2 containment purge stack. A gaseous radioactive effluent treatment system in conjunction with administrative controls is used to minimize the impact on the environment from the airborne releases and maintain doses to the public ALARA.

3.1 Doses from Airborne Effluent Doses from airborne effluent are calculated for the 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.

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 2009 are summarized in Table 3-2. Noble gases are similar to 2008 totals but airborne tritium is seventeen curies higher.

3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2009, from which the airborne doses were calculated, are presented in Table 3-3. When both the equipment hatch and the Elevation 66 hatch are open during an outage, there is a measurable, convective flow out the upper hatch. Because this air is not filtered, whatever is measured in containment air (particulates, tritium, noble gases, radioiodine) is assumed to be carried out the hatch, through the façade, and into the environment thereby contributing to the effluent and the calculated dose.

9

Table 3-1 Comparison of 2009 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 0.0321 mrem 0.107 Noble gas 40 mrad (beta air) 0.00016 mrad 0.0004 Noble gas 20 mrad (gamma air) 0.00041 mrad 0.0020 Noble gas 30 mrem/skin 0.00059 mrem 0.0020 Noble gas 10 mrem (whole body) 0.00039 mrem 0.0039 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2009, through December 31, 2009 Total Jan Feb Mar Apr May Jun J-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.70E-06 3.70E-06 3.88E-04 5.00E-04 9.23E-04 6.47E-04 7.01E-03 1.89E-03 1.14E-02 Total Noble Gas (Ci)1 7.29E-02 5.51E-02 1.05E-01 5.66E-02 1.72E-01 1.11E-01 5.73E-01 1.25E-01 6.53E-02 5.89E-02 5.00E-02 2.74E-02 1.44E-01 1.04E+00 Total Radioiodines (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.17E-07 3.17E-07 0.00E+00 0.00E+00 0.00E+00 2.21E-07 0.00E+00 0.00E+00 5.38E-07 Total Particulate (Ci)2 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.60E-06 9.47E-07 3.55E-06 0.00E+00 0.00E+00 0.00E+00 6.84E-07 5.69E-06 0.00E+00 9.92E-06 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) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.60E-06 9.47E-07 3.55E-06 0.00E+00 0.00E+00 0.00E+00 6.84E-07 5.69E-06 0.00E+00 9.92E-06 Total Tritium (Ci) 6.38E+00 8.67E+00 1.10E+01 8.71E+00 5.08E+00 4.74E+00 4.46E+01 3.76E+00 2.44E+00 4.53E+00 1.19E+01 7.94E+00 6.47E+00 8.16E+01 Max NG H'rly Rel.(Ci/sec) 5.01E-07 1.33E-07 5.39E-07 3.02E-07 7.27E-07 4.22E-08 9.19E-07 4.74E-08 4.96E-08 6.30E-07 6.58E-07 6.20E-07 1

Total noble gas (airborne + liquid releases).

2 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or F-18. F-18 and other airborne particulates with half-lives <8 days do not to be considered for dose calculations. Airborne radioiodines only include I-131 and I-133.

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TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2009, through December 31, 2009 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 6.38E+00 8.67E+00 1.10E+01 8.71E+00 5.08E+00 4.74E+00 4.46E+01 3.76E+00 2.44E+00 4.53E+00 1.19E+01 7.94E+00 6.47E+00 8.16E+01 Ar-41 5.81E-02 5.18E-02 7.60E-02 5.30E-02 1.15E-01 8.52E-02 4.39E-01 8.11E-02 5.43E-02 5.15E-02 3.67E-02 1.46E-02 8.96E-02 7.67E-01 Kr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.66E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.66E-03 Kr-85m 4.89E-04 1.22E-04 9.93E-04 8.85E-05 1.98E-03 7.76E-04 4.45E-03 1.11E-03 4.67E-05 0.00E+00 3.06E-04 1.41E-04 1.55E-03 7.60E-03 Kr-87 1.29E-03 2.26E-04 2.58E-03 2.14E-04 5.06E-03 2.04E-03 1.14E-02 2.56E-03 1.08E-04 0.00E+00 7.37E-04 3.17E-04 3.49E-03 1.86E-02 Kr-88 1.28E-03 2.19E-04 2.53E-03 2.09E-04 4.74E-03 1.86E-03 1.08E-02 2.61E-03 1.18E-04 0.00E+00 7.22E-04 3.21E-04 3.43E-03 1.80E-02 Xe-131m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.73E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.31E-04 8.04E-04 Xe-133 2.61E-04 3.67E-04 7.00E-04 1.12E-03 3.32E-03 3.28E-03 9.05E-03 5.06E-03 9.65E-03 7.39E-03 3.69E-03 7.59E-03 1.19E-02 5.43E-02 Xe-133m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.47E-04 5.47E-04 1.79E-04 3.57E-05 0.00E+00 5.21E-05 6.76E-05 5.89E-05 9.40E-04 Xe-135 2.45E-03 4.16E-04 4.88E-03 5.06E-04 9.65E-03 3.82E-03 2.17E-02 7.76E-03 2.73E-04 1.27E-05 2.02E-03 1.72E-03 9.31E-03 4.28E-02 Xe-135m 2.20E-03 4.94E-04 4.54E-03 3.41E-04 8.11E-03 3.30E-03 1.90E-02 3.84E-03 2.16E-04 0.00E+00 1.88E-03 9.51E-04 7.68E-03 3.36E-02 Xe-138 6.81E-03 1.47E-03 1.32E-02 1.05E-03 2.44E-02 1.03E-02 5.72E-02 1.17E-02 5.52E-04 0.00E+00 3.92E-03 1.62E-03 1.67E-02 9.17E-02 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 0.00E+00 1.62E-06 0.00E+00 1.62E-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 3.29E-08 0.00E+00 3.29E-08 Nd-147 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.08E-08 0.00E+00 2.08E-08 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.47E-07 4.10E-07 0.00E+00 5.57E-07 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 3.12E-07 1.16E-06 0.00E+00 1.47E-06 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 0.00E+00 9.89E-07 0.00E+00 9.89E-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 0.00E+00 1.05E-06 0.00E+00 1.05E-06 Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 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 3.38E-07 0.00E+00 3.38E-07 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 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 5.93E-08 0.00E+00 0.00E+00 5.93E-08 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.17E-07 3.17E-07 0.00E+00 0.00E+00 0.00E+00 1.61E-07 0.00E+00 0.00E+00 4.78E-07 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 2.25E-08 0.00E+00 0.00E+00 2.25E-08 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 9.02E-08 0.00E+00 9.02E-08 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.60E-06 9.47E-07 3.55E-06 0.00E+00 0.00E+00 0.00E+00 2.02E-07 8.47E-10 0.00E+00 3.75E-06 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.62E-09 0.00E+00 1.62E-09 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 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 Note: The Noble Gases listed above include the liquid contribution 11

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 2009. No Types C or D were shipped.

No irradiated fuel was shipped offsite. The volume, activity and type of waste are listed in Table 4-1.

Table 4-1 Quantities and Types of Waste Shipped from PBNP Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc. 9.100 m3 183.670 Ci 3

320.00 ft 3

B. Dry compr essible waste, contaminated equipment, etc 552.7 m 0.479 Ci 3

19520.0 ft 3

C. Irradiated components, control rods, etc. N/A m N/A Ci 3

ft 3

D. Other N/A m N/A Ci 3

ft 4.2 Major Nuclide Composition (by Type of Waste)

The major radionuclide content of the 2009 solid waste was determined by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-2. Only those radionuclides with detectable activity are listed.

12

Table 4-2 2009 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B TYPE C TY PE D Percent Percent Percent Percent Nuclide Abundance Nuclide Abundance Nuclide Abundance Nuclide Abundance Ni-63 47.250% Co-60 26.828%

Co-60 11.994% Fe-55 27.065%

Sr-90 11.509% Nb-95 18.174%

Am-241 10.493% Ni-63 9.713%

Co-58 5.013% Ag-110m 6.741%

Fe-55 3.219% Co-58 2.481%

Sb-125 2.785% Sb-125 2.352%

Cs-137 2.121% Cs-137 2.244%

Zr-95 1.745% Zr-95 1.847%

Mn-54 1.501% Mn-54 1.036%

Ce-144 0.505% Tc-99 0.755%

Ni-59 0.474% H-3 0.225%

Tc-99 0.435% Zn-65 0.132%

Pu-241 0.330% In-113m 0.113%

Co-57 0.214% Sr-90 0.067%

Cm-243 0.151% Ce-144 0.050%

Ag-110m 0.121% Sr-89 0.038%

C-14 0.095% Pu-241 0.038%

Cm-244 0.018% Ag-108m 0.034%

Zn-65 0.010% Co-57 0.027%

Cm-242 0.008% Am-241 0.022%

H-3 0.005% Pu-239 0.008%

Fe-55 0.002% Pu-238 0.006%

Pu-239 0.001% Cm-243 0.004%

Pu-238 0.000% Cm-242 0.000%

Nb-95 0.000%

Pu-240 0.000%

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4.3 Solid Waste Disposition There were thirteen solid waste shipments from PBNP during 2009. The dates and destinations are shown in Table 4-3.

Table 4-3 2009 PBNP Radioactive Waste Shipments Date Destination 01/05/09 Oak Ridge, TN 02/06/09 Oak Ridge, TN 02/17/09 Erwin, TN 04/23/09 Oak Ridge, TN 05/13/09 Oak Ridge, TN 06/03/09 Oak Ridge, TN 08/13/09 Oak Ridge, TN 09/30/09 Oak Ridge, TN 10/07/09 Erwin, TN 10/23/09 Oak Ridge, TN 11/02/09 Oak Ridge, TN 11/18/09 Oak Ridge, TN 12/11/09 Oak Ridge, TN 14

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2009, to June 30, 2009, included 4.67E+05 gallons of neutralized wastewater. The wastewater contained 1.65E+01 pounds of suspended solids and 3.03E+03 pounds of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1, 2009, to December 31, 2009, included 6.31E+05 gallons of neutralized wastewater. The wastewater contained 5.8E-01 pounds of suspended solids and 1.03E+02 pounds of dissolved solids.

Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks.

5.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for January 1, 2009, to June 30, 2009, included 1.98E+07 gallons of clarified wastewater. The wastewater contained 6.52E+03 pounds of suspended solids.

Miscellaneous chemical waste releases from the Wastewater Effluent (based on effluent analyses) to the circulating water for July 1, 2009, to December 31, 2009, included 4.55E+07 gallons of clarified wastewater. The wastewater contained 9.90E+03 pounds of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2009, to June 30, 2009, included 2.81E+05 pounds of sodium bisulfite and 1.19E+05 pounds of sodium hypochlorite (January-April). There was also 1.34E+05 pounds of Stabrex ST70 released into the circulating water via wastewater effluent. Stabrex ST70 is a liquid bromine biocide.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2009, to December 31, 2009, included 5.60E+05 pounds of sodium bisulfite and 6.95E+05 pounds of Stabrex ST70.

Stabrex ST70 is a liquid bromine biocide.

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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 2009 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 282.2 282.2 282.5 400.6 441.5 489.6 Water Discharge [million gal/day]** 2 282.2 282.2 282.5 400.6 478.5 489.6 Average Cooling Water 1 38.0 36.7 37.0 42.0 47.9 53.5 Intake Temperature [°F] 2 39.5 38.3 38.0 42.4 48.6 54.3 Average Cooling Water 1 69.6 68.5 68.7 66.1 66.6 72.4 Discharge Temperature [°F] 2 78.6 77.3 76.5 72.4 73.3 79.0 Average Ambient Lake Temperature [°F] 33.1 32.8 34.7 39.8 44.9 49.0

- For days with cooling water discharge flow.

Table 6-1(continued)

Circulating Water System Operation for 2009 UNIT JUL AUG SEP OCT* NOV* DEC Average Volume Cooling 1 487.1 489.6 489.6 491.1 495.2 353.5 Water Discharge [million gal/day]** 2 487.4 489.6 489.6 445.6 234.6 354.7 Average Cooling Water 1 55.7 54.7 66.1 53.2 46.4 39.0 Intake Temperature [°F] 2 56.6 55.6 66.9 56.7 46.7 39.4 Average Cooling Water 1 75.1 73.6 85.4 72.2 62.7 65.8 Discharge Temperature [°F] 2 81.5 80.2 92.6 79.1 51.2 69.2 Average Ambient Lake Temperature [°F] 52.0 49.7 61.3 49.6 42.5 35.4

Unit 2 outage 10/17/09 -12/3/09

- For days with cooling water discharge flow.

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Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The ODCM was not revised in 2009. However, the Environmental Manual and the Radiological Effluent Control Manual were revised. Both manuals are part of the ODCM. Copies of the revised manuals are being submitted with this 2009 Annual Monitoring Report 7.2 Interlaboratory Comparison Program Environmental, Inc, Midwest Laboratory, the analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples, participated in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) as well as in the interlaboratory comparison studies administered by Environmental Resources Associates (ERA) during 2009. 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.

7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2009.

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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, and fish samples for radionuclides and uses 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, thermoluminescent dosimeters (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.

18

For the measurement of ambient environmental radiation levels that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs situated around PBNP and the ISFSI.

9.0 PROGRAM DESCRIPTION 9.1 Results 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.

Just because a result is statistically greater than zero, it does not necessarily indicate that the radionuclide is present in an environmental sample. False positives may be obtained by fluctuations in background during the counting process. This phenomenon is most prevalent for concentrations at or near the LLD. Therefore, other information such as PBNP emissions records and 19

radionuclide half-life must be used to evaluate whether the result is real or a statistical artifact.

In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A key interpretive aid in assessment of these effects is the design of the PBNP REMP, which is based upon the indicator-control concept.

Most types of samples are collected at both indicator locations and at control locations. A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuation in radiation levels arising from other sources.

9.2 Sampling Parameters Samples are collected and analyzed at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1, 9-2 and 9-3. (The latter two figures show sampling locations not shown in preceding figures due to space limitations. The location of the former retention pond, retired and remediated to NRC unrestricted access criteria, is indicated in Figure 9-3). The list of PBNP REMP sampling sites used to determine environmental impact around the ISFSI is found in Table 9-3. The minimum acceptable sample size is found in Table 9-4. In addition, Table 9-1 indicates the collection and analysis frequency of the ISFSI fence TLDs.

9.3 Deviations from Required Collection Frequency Deviations from the collection frequency given in Table 9-1 are allowed because of hazardous conditions, automatic sampler malfunction, seasonal unavailability, and other legitimate reasons (Section 2.2.6 of the Environmental Manual).

Table 9-5 lists the deviations from the scheduled sampling frequency that occurred during the reporting period.

9.4 Assistance to the State of Wisconsin The Radiation Protection Unit of the Wisconsin Department of Health and Family Services maintains a radiological environmental monitoring program to confirm the results from the PBNP REMP. As a courtesy to the State of Wisconsin, PBNP personnel also collect certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located.

9.5 Program Modifications Three new TLD monitoring sites were added to the REMP during 2009. One dairy farm went out of business and was replaced by a new dairy farm in the area.

20

Table 9-1 PBNP REMP Sample Analysis and Frequency Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05 TLD Quarterly Exposure -06, -07, -08, -09, -12

-14, -15, -16, -17, -18,

-20, -22, -23, -24, -25,

-26, -27, -28, -29, -30,

-31, -32, -38, -39,-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 (on total solids)

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 (on total solids)

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 21

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 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-26 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 TLD site on western most pole between the 2nd and 3rd parking lots.

E-29 Area of North Meteorological Tower.

E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads.

E-31 On utility pole North side of Tapawingo Road closest to the gate at the West property line.

E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers.

Lake Michigan shoreline accessed from the SE corner of KNPP parking lot. Sample South of E-33 creek.

E-38 Tree located at the West end of the area previously containing the Retention Pond.

E-39 Tree located at the East end of the area previously containing the Retention Pond.

E-40 Local Dairy Farm, W side of Hwy 42, about 1.8 miles north of the Nuclear Rd intersection E-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 22

F I W 6 2-lb SITE MAP POINT BEACH NUCLEAR PLANT TRAINING BLDG.

TLD @ TLD 8 AIR A A OTHER CiX FILE tOT46 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP

Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP

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 26

Table 9-5 Deviations from Scheduled Sampling and Frequency Sample Location Collection Reason for not conducting REMP Plans for Preventing Recurrence Type Date as required AP/AI E-03 4/29/2009 Power loss None as reason for loss not determined.

E-20 7/22/09 & Power cut off during construction Power had to be cut to area for electrical safety reasons E-20 7/29/09 activities during construction in the area.

E-06 12/09/09 Power loss due to snowstorm Loss beyond plant's control Lake E-01, E-05, E-06 1/13/2009 Lake Frozen Loss beyond plant's control Water E-01 2/12/09 Lost in transit Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 Weekly, Composited Monthly Air Filters E-07 Weekly E-08 Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-11 Monthly E-19 Well Water E-10 Twice per year 27

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 2009.

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 and gamma isotopic analytical results for water are obtained by measurements on the solids remaining after evaporation of the unfiltered sample to dryness. Hence, the results are indicated as on total solids in Table 10-1.

9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-134 and Cs-137. Charcoal canisters for radioiodine are counted as soon as possible so the I-131 will undergo only minimal decay prior to analyses. The weekly charcoal canisters are screened for I-131 by 28

counting them all at the same time to achieve a lower LLD. If a positive result is obtained, each canister is counted individually.

In order to ensure that the air sampling pumps are operating satisfactorily, a gross leak check is performed weekly. The pumps are changed out annually for calibration and maintenance beyond what can be accomplished in the field.

9.7.5 Vegetation Vegetation samples consist predominantly of green, growing plant material (grasses and weeds most likely to be eaten by cattle if they were present at the sampling site). Care is taken not to include dirt associated with roots by cutting the vegetation off above the soil line.

9.7.6 Environmental Radiation Exposure The 2009 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material (calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them.

Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data were obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. As seen in 2001, the Environmental Inc. TLD cards typically produce a slightly higher measured exposure value, although within the uncertainty of that value recorded by the TLD chips.

The reported field exposure is the arithmetic average of the four exposure values obtained minus the exposure received while the field TLD is in storage and transit.

The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per seven days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from the laboratory. The doses recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose.

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9.7.7 ISFSI Ambient Radiation Exposure Although the ISFSI fence TLDs are not considered part of the REMP, because of their location directly on site, their results can be used indirectly to determine whether the operation of the ISFSI is having an impact on the ambient environmental radiation beyond the site boundary.

Impacts are determined by comparison of fence TLD results to the results of the monitoring at PBNP site boundary and other selected locations.

10.0 RESULTS Summary of 2009 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2009, through December 31, 2009, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, and vegetation as well as TLDs. The results are summarized in Table 10-1.

Table 10-1 contains the following information:

Sample: Type of the sample medium

Description:

Type of measurement LLD: a priori lower limit of detection N: Number of samples analyzed Average: Average value +/- the standard deviation of N samples High: Highest measured value +/- 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 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 <LLD. An ND radionuclide is one for which none of the individual measurements was statistically different from zero. When one or more of the measured radionuclide concentrations was positive and statistically different from zero, the average reported in Table 10-1 is the average +/- one standard deviation.

Both the positive and negative results were used to calculate the average and standard deviation. Some of the reported averages are negative because many of the measured concentrations for that sample category were negative. The highest positive value and its 2-sigma error are reported only when one or more measured values are statistically greater than zero based on counting statistics.

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The method of determining averages follows the recommendation made in NUREG-0475 (1978), Radiological Environmental Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report, and in Health Physics Society Committee Report HPSR-1 (1980), Upgrading Environmental Radiation Data released as document EPA 520/1-80-012 and in more recent documents such as ANSI N42.23-1996, Instrument Quality Assurance for Radioassay Laboratories; ANSI N13.30-1996, Performance Criteria for Radiobioassay; DE91-013607, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance and NUREG-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

Table 10-2 contains the ISFSI fence TLD results.

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Table 10-1 Summary of Radiological Environmental Monitoring Results for 2009 Average +/- Standard Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 124 1 mrem 1.08 +/- 0.17 1.54 +/- 0.12 mR/7days Control (E-20) 4 1 mrem 1.09 +/- 0.10 1.18 +/- 0.14 mR/7days Air Gross Beta 258 0.01 0.025 +/- 0.011 0.056 +/- 0.004 pCi/m3 Control (E-20) Gross beta 50 0.01 0.026 +/- 0.011 0.052 +/- 0.004 pCi/m3 I-131 258 0.030 (0.07) ND - pCi/m3 Control (E-20) I-131 50 0.030 (0.07) ND - pCi/m3 Cs-134 20 0.01(0.05) -0.0001 +/- 0.0004 0.0014 +/- 0.0008 pCi/m3 Control (E-20) Cs-134 4 0.01(0.05) ND - pCi/m3 Cs-137 20 0.01(0.06) 0.0001 +/- 0.0003 0.0009 +/- 0.0005 pCi/m3 Control (E-20) Cs-137 4 0.01(0.06) ND - pCi/m3 Other gamma emitters 20 0.1 0.0001 +/- 0.0003 0.0009 +/- 0.0006 pCi/m3 Control (E-20) Other 4 0.1 0.0000 +/- 0.0004 0.0005 +/- 0.0004 pCi/m3 Milk Sr-89 35 5(10) ND - pCi/L Sr-90 35 1(2) 0.8 +/- 0.3 1.4 +/- 0.3 pCi/L I-131 35 0.5 ND - pCi/L Cs-134 35 5 (15) ND - pCi/L Cs-137 35 5 (18) 0.2 +/- 0.9 2.4 +/- 1.8 pCi/L Ba-La-140 35 5 (15) ND - pCi/L Other gamma emitters 35 15 0.5 +/- 1.1 3.1 +/- 2.1 pCi/L Well Water Gross beta 4 4 1.7 +/- 1.1 2.9 +/- 2.1 pCi/L H-3 4 500 (3000) ND - pCi/L Sr-89 4 5(10) ND - pCi/L Sr-90 4 1 (2) ND - 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) -0.02 +/- 1.1 1.3 +/- 1.2 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 ND - pCi/L Other gamma emitters 4 30 ND - pCi/L Algae Gross beta 6 0.25 5.29 +/- 2.28 8.76 +/- 0.8 pCi/g Co-58 6 0.25 ND - pCi/g Co-60 6 0.25 ND - pCi/g Cs-134 6 0.25 ND - pCi/g Cs-137 6 0.25 0.016 +/- 0.012 0.030 +/- 0.022 pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.

(b) ND indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equivalent to zero.

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Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2009 Average +/- Stan dard Sample Description N LLD (a) Deviatio n ( b) High +/- 2 sigma Units Lake Water Gross beta 47 4 2.2 +/- 1.3 7.6 +/- 2.1 pCi/L I-131 47 0.5 (2) ND - pCi/L Mn-54 47 10 (15) ND - pCi/L Fe-59 47 30 0.2 +/- 1.6 3.1 +/- 2.6 pCi/L Co-58 47 10(15) -0.3 +/- 0.8 2.3 +/- 1.6 pCi/L Co-60 47 10(15) 0.2 +/- 0.8 2.1 +/- 1.9 pCi/L Zn-65 47 30 -0.2 +/- 2.3 3.9 +/- 3.7 pCi/L Zr-Nb-95 47 15 -0.2 +/- 1.0 1.8 +/- 1.5 pCi/L Cs-134 47 10 (15) ND - pCi/L Cs-137 47 10 (18) 0.1 +/- 1.1 3.5 +/- 2.7 pCi/L Ba-La-140 47 15 -0.1 +/- 1.8 4.5 +/- 2.1 pCi/L Ru-103 (Other gamma) 47 30 -0.3 +/- 1.1 3.4 +/- 2.0 pCi/L Sr-89 18 5( 10) ND - pCi/L Sr-90 18 1 (2) 0.32 +/- 0.26 0.87 +/- 0.47 pCi/L H-3 18 500 (3000) 119 +/- 80 306 +/- 106 pCi/L Fish Gross beta 13 0.5 4.03 +/- 1.05 5.59 +/- 0.18 pCi/g Mn-54 13 0.13 ND - pCi/g Fe-59 13 0.26 0.002 +/- 0.017 0.042 +/- 0.016 pCi/g Co-58 13 0.13 -0.002 +/- 0.007 0.011 +/- 0.007 pCi/g Co-60 13 0.13 ND - pCi/g Zn-65 13 0.26 0.000 +/- 0.017 0.030 +/- 0.017 pCi/g Cs-134 13 0.13 -0.001 +/- 0.008 0.022 +/- 0.015 pCi/g Cs-137 13 0.15 0.031 +/- 0.020 0.073 +/- 0.022 pCi/g Other gamma emitters 13 0.5 ND - pCi/g Shoreline Gross beta 11 2 11.12 +/- 1.92 14.51 +/- 2.04 pCi/g Sediment Cs-137 11 0.15 0.017 +/- 0.009 0.027 +/- 0.011 pCi/g Soil Gross beta 16 2 31.10 +/- 6.26 42.39 +/- 3.34 pCi/g Cs-137 16 0.15 0.19 +/- 0.08 0.43 +/- 0.096 pCi/g Vegetation Gross beta 24 0.25 5.57 +/- 2.55 8.88 +/- 0.28 pCi/g I-131 24 0.06 0.000 +/- 0.007 0.014 +/- 0.008 pCi/g Cs-134 24 0.06 -0.001 +/- 0.005 0.010 +/- 0.008 pCi/g Cs-137 24 0.08 0.007 +/- 0.016 0.079 +/- 0.025 pCi/g Other gamma emitters 24 0.06 ND - pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.

(b) ND indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero.

Other gamma emitters typically refer to Co-60 if not specifically called out in the analyses.

See explanation on page 1 of the Environmental Inc, report which is Appendix A 33

Table 10-2 ISFSI Fence TLD Results for 2009 Fence Location Average +/- Standard Deviation Units North 2.36 +/- 0.21 mR/7 days East 2.35 +/- 0.40 mR/7 days South 1.20 +/- 0.14 mR/7 days West 4.63 +/- 0.48 mR/7 days 11.0 DISCUSSION 11.1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring four - five miles from the plant, at special interest areas, and at one control location, roughly 17 miles southwest of the plant. The average of the indicator TLD cards is 1.08 mR/7-days and 1.09 mR/7-days at the control location. These results are not significantly different from each other nor from those observed from 2001 through 2008 (tabulated below in Table 11-1). The change in TLD types in 2001 accounts for the increase in average TLD readings (i.e., prior to third quarter 2001 TLD LiF chips were used versus the TLD cards, see Section 9.7.6 for additional information) from 2000 to 2001. Therefore, the operation of the plant has had no effect on the ambient gamma radiation.

Table 11-1 Average Indicator TLD Results from 1993 - 2009 Year Average +/- St. Dev* Units 1993 0.82 +/- 0.15 mR/7 days 1994 0.90 +/- 0.12 mR/7 days 1995 0.87 +/- 0.13 mR/7 days 1996 0.85 +/- 0.12 mR/7 days 1997 0.87 +/- 0.11 mR/7 days 1998 0.79 +/- 0.13 mR/7 days 1999 0.79 +/- 0.21 mR/7 days 2000 0.91 +/- 0.15 mR/7 days 2001 1.06 +/- 0.19 mR/7 days 2002 1.17 +/- 0.21 mR/7 days 2003 1.10 +/- 0.20 mR/7 days 2004 1.10 +/- 0.22 mR/7 days 2005 1.04 +/- 0.21 mR/7 days 2006 1.14 +/- 0.21 mR/7 days 2007 1.08 +/- 0.20 mR/7 days 2008 1.05 +/- 0.17 mR/7 days 2009 1.08 +/- 0.17 mR/7 days

St. Dev = Standard Deviation 34

There were five new cask additions in 2009 with no significant change in the average annual ISFSI fence TLD results (Table 11-2). The west fence TLDs continue to record higher exposures. The north and east fence TLDs are statistically equal. The south fence continues to record the lowest exposures (Table 11-2). The addition of five NUHOMS casks produced no significant exposure increases at the TLD monitoring locations around the ISFSI (Table 11-3). The results continue to be higher at E-03 and E-31 which are west of the ISFSI corresponding to the higher exposure at the west fence. As expected, the values at E-03 are higher than those at E-31 with E-03 being closer to the ISFSI [see Figs. 9-1 and 9-2 for locations]. The results near the site boundary (E-31, 1.17 +/- 0.19; E-32, 1.05 +/- 0.27) are comparable to the background site E-20 (1.09 +/- 0.20) within the associated measurement error, indicating no measurable increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI.

Table 11-2 Average ISFSI Fence TLD Results (mR/7 days)

TLD FENCE LOCATION North East South West 1995 1.29 1.28 1.10 1.26 1996 2.12 1.39 1.10 1.68 1997 2.05 1.28 1.00 1.66 1998 2.08 1.37 1.02 1.86 1999 2.57 1.84 1.11 3.26 2000 2.72 2.28 1.25 5.05 2001 2.78 2.54 1.36 6.08 2002 2.79 2.74 1.42 6.46 2003 2.70 2.60 1.50 6.88 2004 2.61 2.12 1.41 6.50 2005 2.54 2.05 1.44 5.63 2006 2.73 2.35 1.38 5.80 2007 2.72 2.73 1.34 5.47 2008 2.64 2.37 1.36 5.36 2009 2.36 2.35 1.20 4.63 35

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

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.

11.2 Milk Naturally occurring potassium-40 (1378 +/- 61 pCi/l) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 1000 times higher than the next most positive radionuclide, Sr-90 (0.8 +/- 0.3 pCi/l). The annual average radionuclide concentrations in milk continue to be similar to previous years. The small positive indications for Co-60 and Cs-137 are not statistically significant. Strontium-90 results are not statistically different from previous years going back to 1997. The Sr-90 in milk results of the cycling in the biosphere after the atmospheric weapons tests of the '50s, '60s, and '70s and the Chernobyl accident. Although these tests also introduced Cs-137 into the environment, Cs-137 binds more strongly to soils and therefore less likely to get into cows and milk. Similar to 2005, 2006 and 2008, there were no airborne Sr-90 releases from PBNP during 2009. The 2009 average Sr-90 of 0.8 +/- 0.3 pCi/l is statistically equal to that of previous years: 0.9 +/- 0.4 in 2008; 0.8 +/- 0.4 in 2007; 0.9 +/- 0.3 in 2006; 0.9 +/- 0.4 in 2005; 1.1 +/- 0.4 in 2004; 1.1 +/- 0.4 in 2003; 1.1 +/- 0.7 in 2002; 1.2 +/- 0.5 in 2001; 1.2 +/- 0.6 in 2000; 1.0 +/- 0.3 in 1999; 1.1 +/- 0.5 in 1998; and 1.2 +/- 0.5 in 1997. These results are common throughout the Great Lakes region and North America. Therefore, it is concluded that the milk data for 2009 show no radiological effects of the plant operation.

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11.3 Air The average annual gross beta concentrations (plus/minus the one-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.026 +/- 0.011 pCi/m3 and 0.025 +/- 0.011 pCi/m3, respectively, and are similar to levels observed from 1993 through 2008 (Table 11-4).

Table 11-4 Average Gross Beta Measurements in Air Year Average (pCi/m3) 1993 0.022 1994 0.022 1995 0.021 1996 0.021 1997 0.021 1998 0.022 1999 0.024 2000 0.022 2001 0.023 2002 0.023 2003 0.023 2004 0.021 2005 0.024 2006 0.021 2007 0.025 2008 0.023 2009 0.025 The annual gross beta concentration variation reveals higher concentrations in the fall and winter as compared to the spring and summer. This is present again during 2009. However, as in 2006 -2008, another high period with more scatter occurs during July-September (Figure 11-1). The cause for this scatter is not known but may be due to a shift in land use or weather patterns.

Figure 11-1 2009 Airborne Gross Beta Concentration (pCi/m3) vs. Time 2009 Airborne Gross Beta 0.060 Concentration (pCi/m^3) 0.050 E-01 E-02 0.040 E-03 0.030 E-04 0.020 E-08 0.010 E-20 0.000 01 09 12 09 10

-0 11 09 7-10 09 6-

-0 09 09 08 09 07 09 06 09 05 09

-0 04 09 4-03 09 1-01-0 02 09 Date 37

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 0.025 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, or in the range of 0.001 to 0.005 pCi/m3. Therefore, because no I-131 was detected, it is concluded that the release of small amounts of radioiodine during June and October (Table 3-2) had no measurable impact on the environment.

Gamma spectroscopic analysis of quarterly composites of air particulate filters for radionuclides attributable to PBNP yielded similar results for indicator and control locations. All results for Cs-134, Cs-137, and any other radionuclide are less than the minimum detectable concentration (MDC). By comparison, the measured concentration of naturally occurring Be-7 was 0.079 +/- 0.013 pCi/m3.

Be-7 is not required to be measured by the PBNP REMP; however, it serves as a means to monitor the internal consistency of the vendors analytical program and for comparisons to radionuclides that may be in PBNP airborne effluent.

In summary, the 2009 air data do not demonstrate a significant 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). Icy conditions precluded obtaining samples from E-01, -05, and -06 in January and from E-01 in February.

There were 13 slightly positive indications of gamma emitters during 2009. Only three were statistically above the minimum detectable concentration (MDC). A positive result for Ba-La-140 was obtained at E-01 (in November) located just south of the plant and at E-05 (in August) located north of the plant. Because PBNP did not discharge Ba-La-140 during 2009, these results are determined to be false positives. Furthermore, location E-05 is, based on the current flow of the lake in the vicinity of the plant, upstream of plant discharges. The third positive result above the MDC occurred for Zn-65 at E-06, some six miles south and downstream of the plant. Although PBNP released Zn-65 a week prior to obtaining the lake water sample, the release concentration was 1000 times lower than that measured in the lake water sample, 0.0063 pCi/l vs. 3.9 pCi/l.

Therefore, the Zn-65 result at E-06 is determined to be a false positive.

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Aliquots of the monthly samples are composted quarterly and analyzed for Sr-89/90 and for tritium. No Sr-89 was detected in any of the samples.

Sr-90, because of its long half-life, still persists in Lake Michigan from radioactive fallout in the1950s and '60s. Therefore, it is not surprising that there were ten slightly positive results for Sr-90. Only two of the results were above the MDC and these were from locations upstream from PBNP. Furthermore, PBNP did not discharge Sr-89 or Sr-90 during 2009. Therefore, the positive results are not due to PBNP.

Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. The quarterly composite lake water samples collected and analyzed for H-3 in 2009 ranged from ND to 306 pCi/l.

Although 10 of the 16 composites showed results above zero, only three of these results were above the MDC. Two of the three occurred upstream of PBNP and therefore are unlikely to result from PBNP discharges. The third result from south of PBNP is at roughly 1.5% of the drinking water standard. Based on these results and their occurrences, it is concluded that PBNP liquid discharges produced a minimal, if any, impact on the waters of Lake Michigan.

11.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. None of the cobalt radionuclides discharged by PBNP was detected. Neither was Cs-134. Four of the six samples had positive indications of Cs-137, but only one at 0.029 +/- 0.017 pCi/g was statistically above the MDC. Because fallout Cs-137 from 1950s and 60s weapons testing is known to still persist in Lake Michigan, the one positive Cs-137 result could be the result of recycling of fallout Cs-137 from the 1950s and 60s in the lake. By contrast to the low level of Cs-137, the average concentrations of naturally occurring Be-7 and K-40 are higher:

0.89 and 5.29 pCi/g, respectively. Therefore, the algae monitoring results indicate only a minor, if any, effect by PBNP upon the environs.

11.6 Fish The analyses of 13 fish produced 15 results above zero. Of these 15, six were below the MDC. Of the remaining nine, eight were for Cs-137. The highest Cs-137 concentration 0.073 +/- 0.022 is comparable to the 0.070, 0.049 and 0.055 pCi/g found in 2008, 2007, and 2006 but is lower than the high of 0.172 pCi/g in 2005 and considerably lower than the 2.8 pCi/g seen in PBNP in the mid-1970s during the Chinese weapons tests. It is not possible to determine whether this Cs-137 represents PBNP effluent or the recycling of fallout Cs-137 from the 1950s and 60s. The only other result greater than the MDC was for Zn-65 in a fish from March. None of the other radionuclides in PBNP effluent were found in fish.

By comparison, the concentration of naturally occurring K-40 (1.16-4.05 pCi/g) is about 55 times higher than the highest Cs-137 concentration. Based on these results, it is concluded that there is, at most, a minor indication of a plant effect.

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11.7 Well Water No plant related radionuclides were detected in well water during 2009, as all results were not significantly different from zero. The one slightly positive value was below the MDC. The gross beta values result from naturally occurring radionuclides. Therefore, it is concluded that there is no evidence of PBNP effluents are 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. The main contributor to this worldwide distribution is the weapons testing in the 1950s and 1960s with lesser amounts from Chinese atmospheric nuclear tests in the 1970s and the 1986 Chernobyl accident. Soil is an integrating sample media, in that it is a better indicator of long term buildup of Cs-137 as opposed to current deposition for local sources. The main modifiers of soil Cs-137 concentration levels are erosion and radioactive decay. All samples for 2009 had low levels of Cs-137. The results from the indicator sites are comparable to those from the background site some 17 miles away in the low /Q sector. This is expected for the Cs-137 source being atmospheric fallout as discussed above. Therefore, 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 about 1% of the levels of naturally occurring K-40.

Table 11-5 Average Gross Beta Concentrations in Soil Year Activity (pCi/g) 1993 23.6 1994 19.4 1995 18.0 1996 19.4 1997 22.8 1998 20.0 1999 23.1 2000 22.1 2001 23.5 2002 21.9 2003 22.5 2004 24.3 2005 29.1 2006 27.4 2007 31.0 2008 30.0 2009 31.1 40

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. Three of the 11 samples have Cs-137 concentrations statistically different from zero. The Cs-137 concentrations of the shoreline sediment are about one-tenth of that found in soils. This is expected because Cs-137 in the geological media is bound to clay as opposed to the sand found on the beach. Wave action winnows clay particles from the beach leaving the heavier sand; hence the lower Cs-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 300 times higher than the Cs-137 that is attached to soil/sand 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. Because Lake Michigan sediments are a known reservoir of fallout Cs-137, the shoreline sediment data indicate no radiological effects from plant operation.

11.10 Vegetation The naturally occurring radionuclides Be-7 and K-40 are found in all of the 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 knocks neutrons or protons off the target atom's nucleus producing a radionuclide of lower mass.) In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. Cs-137 can be present 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. The only location where Cs-137 was detected above the MDC was at E-06, a campground area in the Point Beach State Forest. The highest Cs-137 concentration of 0.079 pCi/g is approximately 6% of the average vegetation Be-7 concentration of 1.38 pCi/g and 2% of the average K-40 concentration of 4.72 pCi/g.

As has been demonstrated at other sites in the United States, which are far from any nuclear plants, 1950s and 60s fallout Cs-137 is present in the ash produced by burning the wood in fireplaces. Typically, campground fires are put out using water and the ashes are spread on the ground. The ash acts as a fertilizer, releasing the cesium and potassium into the soil where they are available for uptake by growing plants and trees.

PBNP released no airborne Cs-137 effluent prior to the collection of the two vegetation samples with positive Cs-137 results. That, and given that there is no measurable Cs-137 in the air samples, leads to the conclusion that the two measurable Cs-137 concentrations are not due to PBNP effluents. The Cs-137 results from E-06 demonstrate that Cs-137 fallout from the Chernobyl accident 41

and from atmospheric weapons tests continues to be recycled in the environment by the spreading of wood ash at camp sites.

Based on the 2009 vegetation sampling results, it is concluded that no effect from PBNP effluents are indicated.

11.11 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2009. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. It continues to be conservative for the purpose of calculating doses via the grass-cow-milk pathway to ensure that the milk sampling locations remain as conservative as practicable.

12.0 REMP CONCLUSION Based on the analytical results from the 814 environmental samples, and from 128 sets of TLDs that comprised the PBNP REMP for 2009, PBNP effluents had no discernable, permanent effect on the surrounding environs. These results demonstrate that PBNP continues to have good controls on fuel integrity and on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a.

42

Part D GROUNDWATER MONITORING 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium. During 2009 the sampling program consisted of six beach drains, six intermittent stream and bog locations, four drinking water wells, four façade wells, eight yard electrical manholes, six ground water monitoring wells, and the Unit 2 facade subsurface drainage (SSD) system sump.

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 the observation that after modifications were made to the pool, 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.

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 sites 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, three other drinking water wells also are monitored. The Site Boundary Control Center well, located at the plant entrance, the Warehouse 6 well, on the north side of the plant, and the EIC well, located south of the plant. These wells do not draw water from the top 20 - 30 feet of soil which is known to contain H-3. These wells monitor the deeper (200 - 350 feet), drinking water aquifer from which the main plant well draws its water. The two soil layers are separated by a gray, very dense till layer of low permeability identified by hydrological studies.

Manholes in the plant yard and for the subsurface drainage (SSD) system under the plant are available for obtaining ground water samples. The plant yard manholes for accessing electrical conduits are susceptible to ground water in-leakage. Therefore, a number of these were sampled. The SSD were designed to lessen hydrostatic pressure on the 43

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. A monthly composite from this sump was analyzed from January through August. In September, compositing was discontinued and individual samples were analyzed as part of the program.

In the 1990s, two wells were sunk in each units façade to monitor the groundwater levels and look at evidence of concrete integrity as part of the ISI IWE Containment Inspection Program required by 10 CFR 50.65. These wells are stand pipes which are sampled periodically for chemical analyses. Beginning in 2007, samples for the groundwater program were drawn as well. These wells are sampled at least three times a year.

The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1.

44

Figure 13-1 Groundwater Monitoring Locations 14.0 RESULTS 14.1 Streams and Bogs The results from the groundwater monitoring associated with the former retention pond are presented in Table 14-1. For the most part, the creek results are barely above the detection level. There are more positive values for the East Creek than for the West Creek or for the confluence of the two creeks south of the plant near Lake Michigan. GW-08 is a bog near the former retention pond.

Table 14-1 Intermittent Streams and Bogs H-3 Concentration (pCi/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 +/- +/- +/- +/-

Feb +/- +/- +/- +/-

Mar 80 +/- 87 249 +/- 95 144 +/- 90 223 +/- 94 +/- +/- 158 Apr 158 +/- 104 314 +/- 94 ND +/- 240 +/- 91 +/- +/- 159 May 118 +/- 89 383 +/- 101 ND +/- 709 +/- 115 ND +/- 847 +/- 120 158 Jun +/- +/- +/- +/- +/- +/-

Jul ND +/- 141 +/- 80 108 +/- 78 251 +/- 86 147

+/- ND +/- 119 +/- 77 123 +/- 77 +/- +/- 149 Aug +/- +/- +/- 119 +/- 79 +/- +/- 147 Sep 147 +/- 98 86 +/- 81 196 +/- 86 109 +/- 82 +/- +/- 153 Oct 131 +/- 96 301 +/- 103 ND +/- 427 +/- 108 +/- +/- 148 Nov 99 +/- 83 204 +/- 89 145 +/- 86 346 +/- 95 +/- +/- 149 Dec +/- +/- +/- 141 +/- 80 +/- +/- 150 A blank indicates no sample was available. Streams are sampled monthly; bogs, annually.

Values are presented as the measured value and the 95% confidence level counting error.

ND = measured value is less than the 2-sigma counting error.

The analyses of these surface water samples show low concentrations of H-3.

None of the sample from the confluence of the two creeks (GW-01), ESE of the former retention pond, and only one of the West Creek (GW-02) samples, have results above the minimum detectable concentration (MDC). In contrast, most of the results from the south section of the East Creek (GW-02), the north section near the sewage treatment plant (GW-17), and from the one bog SE of the former retention pond have results above the MDC. This indicates that the predominant H-3 flow in the top soil layer flow away from the area of the retention pond is more east to Lake Michigan than to the south. This is in agreement with site hydrological studies reported in the FSAR and the Site Conceptual Model. The East Creek concentrations are generally lower than the 300 - 350 pCi/l seen in the late 90s. The bog result is down from the 3000 pCi/l seen before the pond was remediated in 2002.

46

14.2 Beach Drains and SSD Sump The 2009 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.] Beginning in September, S-1 and S-3 were sampled more frequently than once per month. S-1 collects yard drainage from the north part of the site yard; S-3, from the south part of the site yard. Additionally, S-1 receives the output from the SSD sump located in the Unit 2 façade. 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 no longer connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant.

S-1 shows more variability than S-3 (Figure 14-1). Most S-1 H-3 concentrations are in the 300 - 500 pCi/l range and followed by concentrations in the 2000 -

7000 pCi/l range. At S-3, the H-3 concentrations are more uniform with one spike at 3688 and another at 1370 pCi/l. Possible H-3 contributions to S-1 from groundwater inleakage upstream of this discharge were investigated. Tritium concentrations in groundwater from the electrical vaults immediately west of S-1 were not detectable to very low. Similar results were obtained from a manhole along the discharge pathway from the former retention pond (see below Section 14.3). Therefore, the high concentration spikes found at S-1 are attributable to receiving discharges from the SSD sump. The reason for the two spikes at S-3 is unknown. S-3 is located in the suspected drainage path from the former retention pond area to the lake but no other monitoring site along this path has had H-3 concentrations this high.

Table 14-2 2009 Beach Drain Tritium Average H-3 Concentration (pCi/l)

Month S-1 S-7 S-8 S-9 S-10 S-3 S-11 Jan 231 +/- 81 NF +/- NF +/- NF +/- NF +/- NF +/- +/-

Feb NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- +/-

Mar NF +/- NF +/- NF +/- NF +/- NF +/- NF +/- +/-

Apr 395 +/- 98 NF +/- 575 +/- 106 482 +/- 102 304 +/- 94 240 +/- 91 +/-

May 336 +/- 96 NF +/- NF +/- 458 +/- 102 NF +/- 375 +/- 98 161 +/- 88 Jun 200 +/- 100 NF +/- NF +/- NF +/- NF +/- 362 +/- 107 38 +/- 94 Jul 362 +/- 94 NF +/- NF +/- NF +/- NF +/- 534 +/- 101 152 +/- 85 Aug 270 +/- 90 NF +/- NF +/- NF +/- +/- 422 +/- 96 +/-

Sep 1364 +/- 1392 NF +/- NF +/- NF +/- 191 +/- 94 466 +/- 215 212 +/- 95 Oct 639 +/- 320 NF +/- NF +/- 229 +/- 98 NF +/- 1415 +/- 1969 217 +/- 97 Nov 1487 +/- 2351 NF +/- NF +/- 105 +/- 87 NF +/- 413 +/- 341 144 +/- 71 Dec 1133 +/- 1224 590 +/- 103 NF +/- NF +/- 435 +/- 97 352 +/- 53 206 +/- 25 NF = no sample due to no flow 47

The data from the remaining beach drains from the plant area (S S-10) are sparse in that there is no flow unless there is precipitation or some groundwater intrusion. In contrast, at S-11 the flow appears to be mainly from groundwater.

Nine of the 14 analyses revealed low H-3 concentrations slightly above the MDC.

Figure 14-1 2009 H-3 Concentrations for S-1 and S-3 Tritium Concentrations (pCi/l)

H-3 Concentrations for S-1 and S-3 8000 Concentration (pCi/l) 7000 6000 5000 S-1 4000 S-3 3000 2000 1000 0

Ja n M -0 9 ar M - 09 ay -

Ju 09 09 l-0 9/ /10 9 24 /0 9/ /20 9 30 0 10 /20 9 10 /8/2 09 2 0 10 /15 / 09

/2 2 0 10 /2 0 09

/2 09 8/

2 11 009 11 /3/0

/1 9 11 1 /0 11 /1 9

/2 6 /0 11 0 /2 9

/2 0 11 5 /2 09

/3 00 0

12 /2 0 9

/4 09 12 /20 12 /8/2 09

/1 0 12 1 /2 09

/1 0 12 6 /2 09

/2 0 12 1 /2 09

/2 0 12 5 /2 09

/3 00 0/ 9 20 09 Date The SSD sump is located in the Unit 2 façade. The monthly results are presented in Table 14-3. The January - August data are from a single measurement of a monthly composite sample. The remaining monthly concentrations are the average of individual measurements made during that month. These results are generally higher than those from S-1, the beach drain to which the sump is pumped. The source of the higher SSD sump tritium concentrations is under investigation. The October 12 and 26 samples were gamma scanned. Both results were below the MDC.

48

Table 14-3 Unit 2 Facade Subsurface Drain Sump Average H-3 Concentration (pCi/l)

Month pCi/l 2 Jan* 510 +/- 98 Feb* 468 +/- 96 Mar* 609 +/- 109 Apr* 533 +/- 104 May* 539 +/- 105 Jun* 541 +/- 110 Jul* 473 +/- 97 Aug* 551 +/- 98 Sep+ 889 +/- 706 Oct+ 2224 +/- 2373 Nov+ 6644 +/- 15768 Dec+ 1830 +/- 1574

Monthly composites

+

Monthly average 14.3 Electrical Vault and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage as is evident by very low concentrations of H-3 (Table 14-4). The manhole series M-66 A-D run from south to north on the east side of the Unit 2 Turbine Building. M-66A is located near the Unit 2 truck bay and M-66D is just east of the emergency diesel generator building. The M-67A-D series is parallel to the M-66A-D series so that M-67A is next to M-66A but on the east side of it. MH-68 is in the west side of the EDG Building directly opposite the D manholes. Based on their proximity, it was expected that the each pair of manholes would have nearly the same H-3 concentration. This holds true for the C and D pairs but not the A pair.

49

Table 14-4 Yard Manhole Tritium Average Activity (pCi/l)

Man Hole pCi/l +/- 2 MDC MH-66A 90 +/- 38 155 MH-66B 86 +/- 52 152 MH-66C 89 +/- 25 152 MH-66D 184 +/- 84 152 MH-67A 242 +/- 25 155 MH-67B* -

MH-67C 109 +/- 83 147 MH-67D 162 +/- 85 147 MH-68 201 +/- 94 152 Average = 145 +/- 60

= not enough water to obtain a sample In addition to the yard manholes, a manhole (R-4) along the abandoned line from the remediated retention pond to the plant was checked as a possible source for carrying groundwater H-3 from the area of the remediated pond to the north side of the plant. It is postulated that the trench would provide a pathway to bring the tritiated groundwater from the pond area to the north side of the plant where it would be discharged via the S-1 beach drain. No H-3, Sr-90 or any effluent-related gamma emitters were detected.

14.4 Façade Wells and Tendon Gallery Sumps Two wells are located in each units façade. In Unit 2 there is one on each side of containment, approximately 180° apart. The Unit 1 façade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361B) corners of the façade.

No samples were collected during the first quarter of 2009. In April the sampling frequency was increased. Some samples were not collected because the well cap could not be removed.

The 2009 results are similar to those obtained in 2008. The Unit 2 continues to have low H-3 concentrations, only a few of which are above the MDC. In Unit 1 the well in the SE corner of the façade continues to have the higher H-3 concentrations, although lower than the 929 - 1169 pCi/l seen in 2008. Based on these results, the conclusion that H-3 is not evenly distributed under the plant still is valid.

50

Table 14-5 2009 Facade Well Water Tritium H-3 Concentration (pCi/l)

UNIT 1 UNIT 2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B MDC Jan NS +/- NS +/- NS +/- NS +/-

Feb NS +/- NS +/- NS +/- NS +/-

Mar NS +/- NS +/- NS +/- NS +/-

Apr 780 +/- 114 165 +/- 87 91 +/- 84 91 +/- 84 <159 May* 705 +/- 113 232 +/- 93 241 +/- 93 219 +/- 92 <154 Jun 633 +/- 106 ND +/- ND +/- ND +/- <152 Jul 466 +/- 99 ND +/- ND +/- NS +/- <147 Aug 548 +/- 114 ND +/- ND +/- NS +/- <151 Sep 535 +/- 100 ND +/- NS +/- NS +/- <152 Oct 468 +/- 110 182 +/- 97 ND +/- NS +/- <148 Nov 678 +/- 122 201 +/- 105 136 +/- 102 ND +/- <158 Dec 474 +/- 112 ND +/- ND +/- ND +/- <152 ND = not detected * = collected June 1 NS = sample not collected Further samples of the groundwater were obtained from each units tendon gallery sump in October. In contrast to the difference between the units observed in the façade well results, the Unit 2 tendon gallery sump had higher H-3 (4747 +/- 216 pCi/l) than Unit 1 (1293 +/- 141 pCi/l) tendon gallery sump. The Unit 2 tendon gallery sump also had higher Cs-137 and Co-60 (794 +/- 10 and 23.6 +/- 3.0 pCi/l) compared to the Unit 1 tendon gallery sump (43.3 +/- 5.3 and non-detectable pCi/l). Again, an uneven distribution of radionuclides in the groundwater around each unit.

The groundwater in the tendon gallery sumps is pumped to the facade sumps from where it is discharged.

14.5 Potable Water and Monitoring Wells In addition to the main plant well (Section 11.7), nine other wells are monitored for H-3. These consist of three potable water wells, GW-04, GW-05, and GW-06, and six H-3 groundwater monitoring wells, GW-11 through GW-16 installed in 2007 (Figure 13-1). The monitoring wells are located at the periphery of the area affected by diffusion from the former retention pond and known spent fuel pool leakage during the 1970s. Two of the potable water wells are for buildings close to the plant (GW-04 and GW-05) whereas, the other (GW-06) is at the Site Boundary Control Center some 3200 feet from the former retention pond. The potable water wells are from the deep aquifer whereas, the monitoring wells are in the shallow (< 30 feet), surface water aquifer above the thick, impermeable clay layer separating the two. The EIC well is sampled monthly and the other two potable wells are sampled quarterly.

The potable water wells have no H-3 (Table 14-6). Although there was one slightly positive value, it was below the MDC. It is concluded that this is a false positive.

51

The only monitoring wells to show consistent, detectable H-3 are the two (GW15, GW-16) in the flow path from the retention pond area to the lake (Table 14-7).

The highest H-3 concentrations occur at GS-15, the well closest to the former retention pond.

Table 14-6 2009 Potable Well Water Tritium H-3 Concentration (pCi/l)

Warehouse SBCC EIC WELL 6 Well Well Month GW-04 GW-05 GW-06 MDC Jan ND ND ND Feb ND Mar 104 +/- 89 <158 Apr ND ND ND May ND Jun ND Jul ND ND ND Aug ND Sep ND Oct ND ND ND Nov ND Dec NS ND=Not Detected NS=No Sample 52

Table 14-7 2009 Monitoring Well Water Tritium H-3 Concentration (pCi/l)

MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Month GW-11 GW-12 GW-13 GW-14 GW-15 GW-16 MDC Jan 105 +/- 81 ND ND 173 +/- 84 423 +/- 96 131 +/- 82 <152 Feb 108 +/- 81 ND ND 101 +/- 80 566 +/- 102 NS <151 Mar 123 +/- 98 ND 131 +/- 83 150 +/- 84 615 +/- 105 382 +/- 95 <152 Apr 90 +/- 83 ND 103 +/- 83 ND 446 +/- 100 244 +/- 91 <157 May ND ND ND +/- ND 379 +/- 99 138 +/- 88 <162 Jun ND +/- ND 116 +/- 84 ND 387 +/- 96 175 +/- 87 <149 Jul 82 +/- 75 ND 137 +/- 78 ND 423 +/- 91 215 +/- 82 <149 Aug 149 +/- 80 ND 82 +/- 76 ND 495 +/- 96 216 +/- 83 <145 Sep ND ND ND ND 452 +/- 97 230 +/- 87 <152 Oct NS NS NS NS NS NS Nov ND ND ND 174 +/- 101 410 +/- 109 272 +/- 104 <155 145 +/- 96 ND +/- ND 114 +/- 94 503 +/- 110 296 +/- 102 <147 Dec 140 +/- 103 ND 127 +/- 103 144 +/- 103 452 +/- 114 325 +/- 110 <161 NOTE: MW-01 through MW-06 obtained on 11/5/2009 and on 11/21/2009 14.6 Miscellaneous Sampling In addition to groundwater, analyses have been made of precipitation, rainwater and snow. These H-3 measurements were undertaken in order to obtain information on potential background levels of tritium. Another reason for sampling the rainwater is to determine whether it is possible to see the outwash of atmospheric H-3 releases from PBNP. A condensate sample from the air conditioner's condenser located on the roof of the South Service Building yielded 3000 pCi/l. Samplers are located at the Site Boundary Control Center (E-04),

which is located in the highest /Q sector and near the western (E-03) and northern (E-04) boundaries. Results do not indicate any significant washout of H-3 at the site boundary (Table 14-8).

53

Table 14-8 2009 Precipitation H-3 E-02 E-03 E-04 Collection DATE pCi/l 2 pCi/l 2 pCi/l 2 DATE Jan 95.3 51.6 128.2 51.6 93.1. 51.6 2/4/2009 Feb 79.6 51.6 70.9 51.6 49.6 51.6 3/4/2009 Mar 53.1 51.6 133.7 51.6 51.9 51.6 4/8/2009 Apr 100.2 51.6 54.8 51.6 38.7 51.6 5/6/2009 May 75.7 51.6 59.3 51.6 52.2 51.6 6/11/2009 June 53.2 51.6 88.9 51.6 65.1 51.6 7/8/2009 July 74.1 51.6 41.2 51.6 41.2 51.6 8/5/2009 August 29 51.6 58.9 51.6 70.2 51.6 9/9/2009 Sept 30.6 51.6 47.0 51.6 60.9 51.6 10/7/2009 Oct 60.6 51.6 45.4 51.6 57.7 51.6 11/3/2009 Nov <19.3 51.6 30.3 51.6 31.2 51.6 12/9/2009 Dec 55.5 51.6 137.5 51.6 41.2 51.6 1/7/2009 15.0 GROUNDWATER

SUMMARY

Groundwater monitoring indicates that low levels of tritium continues 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.

Except for the monitoring wells downstream from the former retention pond, the monitoring well tritium concentrations are not different from zero.

Results will continue to be evaluated to determine whether additional groundwater monitoring sites are needed.

54

APPENDIX 1 Environmental, lnc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2009

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~nvironmental,Inc.

i Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road Northbrook, I L 60062-2310 (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, 2009 Reviewed and Approved by Date 02-82-2 0 0 Distribution: K. Johansen, 1 hardcopy, 1 e-mail

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section Paqe List of Tables .............................................................................111 INTRODUCTION ................................................................... 1 LISTING OF MISSED SAMPLES ..............................................2 Appendices Interlaboratory Comparison Program Results ...........................A-1 Data Reporting Conventions ......................................................B-1 Sampling Program and Locations .............................................C-1 Graphs of Data Trends ..............................................................D-I Supplemental Analyses .............:.............................................E-1 Duplicate Analysis F-I

POINT BEACH NUCLEAR PLANT LIST OF TABLES Title Airborne Particulates and Iodine-131 Location E.01, Meteorological Tower ..............................................

Location E.02. Site Boundary Control Center ...................................

Location E.03. West Boundary .....................................................

Location E.04. North Boundary ......................................................

Location E.08. G. J . Francar Residence .............;...........................

Location E.20. Silver Lake College .................................................

Airborne Particulates. Gamma Isotopic Analyses .......................................

Milk ........................................................................................................

Well Water .............................................................................................

Lake Water ............................................................................................. 5-1 Lake Water. Analyses on Quarterly Composites ................................................ 6-1 Fish ..................................................................................................................... 7-1 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 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the final 2009 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-2'14, Ra-226 and Ac-228. Unless noted otherwise, the results reported under "Other Gammas" are for (20-60 and may be higher or lower for other radionuclides.

All concentrations, except gross beta, are decay corrected to the time of collection.

All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples.

POINT BEACH NUCLEAR PLANT 2.0 LISTING OF MISSED SAMPLES Expected Collection Sample Type Location Date Reason MI E-11 01-14-09 Funk Farm no longer in dairy cow business.

LW E-01 01-13-09 Sample not sent; assumed frozen.

LW E-05 01-43-09 Sample not sent; assumed frozen.

LW E-06 01-13-09 Sample not sent; assumed frozen.

LW E-01 02-12-09 sample lost in transit.

APIA1 E-03 04-29-09 No power to sampler.

APIA1 E-20 07-22-09 No power to sampler due to construction in area.

APIA1 E-20 07-29-09 ' No power to sampler.

APIA1 E-06 , 12-09-09 No power to sampler due to snowstorm.

LW E-33a 12-'17-09 Unable to obtain due to snow accumulation.

NOTE: Page 3 is intentionally left out.

POINT BEACH NUCLEAR PLANT 3.0 Data Tables

POINT BEACH NUCLEAR PLANT i Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-01, Meteorological Tower Units: p ~ i / m 3 Collection: Continuous, weekly exchange.

Date. Vol. Date Vol.,

Collected (m3) Gross Beta 1-131 Collected (m3) dross Beta 1-131 Required LLD Required LLD 0.010 0.030 Ist Quarter 3rd Quarter Mean e s.d. 0.035 + 0.009 < 0.01 1 +

Mean s.d. 0.025 f 0.013 < 0.012 2nd Quarter 4th Quarter

+

Mean s.d. 0.020 + 0.005 .c. 0.013 Mean rt s.d. 0.024 k 0.010 < 0.013 Cumulative Average 0.026 f 0.01 1 < 0.012 a Gross beta recounted.

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 Units: pcilrn3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.010 0.030 Ist ~ u a h e r 3rd Quarter.

+

Mean s.d. +

Mean s.d.

2nd Quarter 4th Quarter

+

)\/lean s.d. 0.018 + 0.005 < 0.013 +

Mean s.d. 0.024 i: 0.012 c 0.014 Cumulative Average 0.026 t 0.01 1 < 0.01 3 a Gross beta recounted with a result of 0.006c0.002 pcilm3.

Filter light.

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-03, West Boundary Units: p ~ i / m 3 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 Ist Quarter 3rd Quarter Mean, 5 s.d. Mean 5 s.d.

2nd Quarter 4th Quarter

+

Mean s.d. 0.017 5 0.005 < 0.012 +

Mean s.d. 0.025 + 0.01 1 < 0.013 Cumulative Averaae 0.025 + 0.011 < 0.012 a " NS" = No sample; see Table 2.0, Listing of Missed Samples.

POINT BEACH NUCLEAR PLANT Table I.Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-04, North Boundary Units: p ~ i l m 3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected .(m3) Gross Beta 1-131 Required LLD 0.0.1 0 0.030 Required LLD 0.010 -0.030

, 1st Quarter 3rd Quarter Mean k s.d. +

Mean s.d.

2nd Quarter 4th Quarter

+

Mean s.d. 0.016 f 0.005 < 0.011 +

Mean s.d. 0.024 + 0.01 1 < 0.013 Cumulative Average 0.024 f 0.01 1 < 0.01 1

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-08, G.J. Francar Residence Units: p ~ i / m 3 Collection: Continuous, weekly exchange. .

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD O.ol0 0.030 Required LLD 0.01 0 0.034 Ist Quarter 3rd Quarter Mean 4 s.d. 0.032 + 0.007 < 0.010 +

Mean s.d. . 0.024 + 0.012 < 0.012 2nd Quarter 4th Quarter

+

Mean s.d. 0.019 + 0.005 0.012 +

Mean s.d. 0.026 ~t0.0'12 <: 0.013 Cumulative Average 0.025 rt: 0.01 I < 0.012

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-20, Silver Lake Units: p ~ i / m 3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reauired LLD 0.010 0.030 Required LLD 0.01 0 0.030 Ist Quarter 3rd Quarter Mean -I- s.d. 0.034 + 0.009 < 0.010 Mean k s.d. 0.024 + 0.011 < 0.01 1 2nd Quarter 4th Quarter Mean k s.d. 0.018 + 0.004 < 0.012 Mean -I- s.d. 0.026 + 0.012 < 0.013 Cumulative Average 0.026 k 0.01 1 < 0.012 All Locations Annual Mean 4- s.d. +

0.025 0.0'1'1 < 0.012 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

Table 2. Gamma emitters in quarterly composites of air particulate filters Units: p ~ i l 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 M DC 0.01 MDC (0.10) MDC m3 Ist Quarter E-01 EAP- 1427 0.083 f 0.014 - -0.0002 f 0.0006 < 0.0005 -0.0001 f 0.0005 < 0.0006 0.0005 f 0.0006 < 0.0010 3854 E-02 - 1428 0.056 f 0.072 - 0.0014 f 0.0008 < 0.0007 -0.0002 f 0.0005 c 0.0006 -0.0001 f 0.0005 < 0.0008 3696 E-03 - 1429 0.099 f 0.015 - 0.0000 f 0.0006 4 0.0008 0.0004 f 0.0005 < 0.0007 0.00(14 f 0.0004 < 0.0008 3850 E-04 - 1430 0.080 f 0.015 - -0.0002 f 0.0004 < 0.0005 0.0001 f 0.0005 - < 0.0005 -0.0001 f 0.0006 < 0.0007 4165 E-08 - 1431 0.085 f 0.013 - -0.0003 f 0.0004 c 0.0006 -0.0002 f 0.0005 < 0.0009 -0.0002 f 0.0005 c 0.0006 3974 E-20 - 1432 0.088 f 0.012 - 0.0002 f 0.0004 < 0.0007 -0.0001 f 0.0003 c 0.0005 -0.0003 f 0.0004 c 0.0004 3975 2nd Quarter E-01 EAP- 3841 0.088 f 0.015 - 0.0000 f 0.0004 c 0.0008 0.0001 f 0.0005 < 0.0007 0.0001 f 0.0005 c 0.0007 3818 E-02 - 3842 0.090 f 0.011 - -0.0001 f 0.0002 c 0.0004 -0.0001 f 0.0003 c 0.0004 0.0001 f 0.0003 < 0.0006 3648 E-03 - 3843 0.084 f 0.016 - 0.0002 f 0.0004 c 0.0008 0.0001 f 0.0004 < 0.0007 0.0000 10.0005 < 0.0007 3521 E-04 - 3844 0.075 f 0.014 - 0.0000 f 0.0004 c 0.0002 0.0000 f 0.0005 < 0.0004 -0.0001 f 0.0005 < 0.0003 4147 E-08 - 3845 0.082 f 0.016 - -0.0004 f 0.0006 c 0.0009 0.0009 f 0,0005 < 0.0007 0.0002 f 0.0006 < 0.0007 3906 E-20 - 3846 0.088 f 0.016 - 0.0000 10.0005 c 0.0007 -0.0005 f 0.0006 < 0.0007 0.0005 f 0.0004 c 0.0008 3839 3rd Quarter E-01 EAP- 5790 0.095 f 0.014 - -0.0001 f 0.0003 c 0.0006 0.0002 10.0003 < 0.0007 0.0001 f 0.0005 < 0.0008 3859 E-02 - 5791 0.082 f 0.017 - -0.0003 f 0.0005 c 0.0005 -0.0002 f 0.0006 c 0.0006 -0.0001 f 0.0006 C 0.0005 3753 E-03 - 5792 0.090 f 0.015 - -0.0002 f 0.0004 < 0.0007 0.0001 f 0.0005 < 0.0007 -0.0002 f 0.0005 < 0.0006 3848 E-04 - 5793 0.067 f 0.012 - 0.0002 f 0.0003 c 0.0006 0.0000 f 0.0004 c 0.0007 0.0000 f 0.0004 < 0.0003 4088 E-08 - 5794 0.091 f 0.019 - 0.0000 f 0.0005 c 0.0009 -0.0001 f 0.0005 c 0.0007 0.0007 1' 0.0005 c 0.0007 3907 E-20 - 5795 0.094 f 0.020 - 0.0001 10.0006 c 0.0007 0.0000 f 0.0006 c 0.0008 0.0001 f 0.0008 < 0.0008 3323 4th Quarter E-01 EAP- 7164 0.058 f 0.013 - -0.0007 f 0.0005 c 0.0006 0.0000 f 0.0006 c 0.0008 0.0009 f 0.0006 c 0.0008 3986 E-02 - 7165 0.069 f 0.015 - 0.0001 f 0.0005 c 0.0004 0.0002 f 0.0005 < 0.0006 0:0006 f 0.0004 < 0.0005 3922 E-03 - 7166 0.059 f 0.015 - -0.0004 f 0.0005 < 0.0005 0.0001 10.0005 < 0.0007 0.0001 f 0.0005 < 0.0005 3932 E-04 - 7168 0.063 f 0.012 - 0.0000 f 0.0005 c 0.0007 0.0002 f 0.0005 c 0.0009 0.0000 f 0.0005 < 0.0006 4037 E-08 - 7169 0.072 f 0.016 - -0.0001 f 0.0005 c 0.0007 -0.0004 f 0.0006 c 0.0007 -0.0005 f 0.0009 < 0.0010 3585 E-20 - 7170 0.055 t 0.011 - -0.0002 f 0.0003 < 0.0004 0.0001 f 0.0004 < 0.0006 -0.0005 f 0.0004 0.0004 3930 Annual Mean5s.d. 0.079 f 0.013 0.0000 t 0.0004 0.0000 t 0.0003 0.0007 f 0.0004

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCilL)

E-I ILambert Dairv arm^

MDC . MDC MDC Required Collection Date 01-14-09 02-11-09 03-12-09 LLD Lab Code NSa EMI- 449 EMI- 810 K-40 1376 f 95 1365 f 99 CS-134 0.9 f 1.6 c 3.0 0.3 f 1.7 < 2.3 5.0 CS-137 0.5 f 2.0 < 2.9 0.7 f 2.0 < 3.3 5.0 Ba-La-140 -1.2 k 1.7 c1.9 0.5k1.7 < 2.7 5.0 Other (Co-60) 0.8 f 1.8 < 2.4 -0.7 f 2.0 < 2.0 15.0 Required Collection Date 04-08-09 LLD Lab Code EMI- 1224 EMI- 2084 EMI- 2814

-0.3 f 0.9 < 0.8 -0.7 f 1.0 < 0.8 5.0 0.8 _+ 0.3 < 0.5 1.1 k 0.4 < 0.5 1.O 0.15 k 0.18 < 0.31 0.07 f 0.16 < 0.28 0.5 K-40 1351 f 102 1339 i 103 CS-134 -1.5 f 1.7 < 2.5 -1.5 f 2.2 < 3.3 5.0 -

Cs-137 0.1 f 2.1 c 3.3 0.6 f 2.1 c 3.5 5.0 Ba-La-140 -0.8 f 1.7 < 2.7 - 0.5 f 2.0 c 3.0 5.0 Other (Co-60) 0.2 f 2.2 < 2.0 2.7 f 2.1 < 3.3 15.0 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

Replaced Funk Farm.

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-I 1 Lambert Dairv Farm MDC MDC MDC ' Required Collection Date 07-08-09 08-12-09 09-09-09 LLD Lab Code EMI- 3386 EMI- 4238 EMI- 4678 K-40 CS-134 CS-137 Ba-La-140 Other (Co-60)

Required Collection Date 11-11-09 LLD Lab Code EMI- 5522 EMI- 6280 EMI- 6757

-0.4 f 0.8 0.9 f 0.3 0.08 2'0.15 K-40 1200 f 102 CS-134 1.4 f 2.0 CS-137 1.6 f 2.5 Ba-La-140 0.3 f 1.8 Other (Co-60) 0.5 k 2.0

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in mill( samples Collection: Monthly Sample Description and Concentration (pCilL)

E-21 Strutz Dairy Farm MDC UDC MDC Required Collection Date 02-12-09 LLD Lab Code EMI- 90 EMI- 450 EMI- 788 K-40 Cs-134 Cs-137 Ba-La-?40 Other (Co-60)

Required Collection Date 04-08-09 LLD Lab Code EMI- 1225 EMI- 2815 K-40

, Cs-134 Cs-137 Ba-La-140 Other (Co-60)

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in mill( samples Collection: Monthly Sample Description and Concentration (pCilL)

E-21 Strutz Daiw Farm MDC MDC MDC Required Collection Date 08-12-09 LLD Lab Code EMI- 3387 EMI- 4679 K-40 CS-134 Cs-137 Ba-La-140 Other (Co-60)

Required Collection Date 10-14-09 11-11-09 LLD Lab Code EMI- 5524 EMI- 6281 EMI- 6758 K-40 1396 f 118 1376 f 1>08 1403'5 107 / - .

CS-134 -0.5 f 1.4 < 2.3 -1.6 f 1.7 < 2.2 0.8 f 1.7 < 3.1 5.0 CS-137. 1.0 i: 2.1 < 4.6 1.1 f 2.1 < 3.8 0.8 f 2.1 < 3.4 5.0 Ba-La-140 -1.4 f 1.9 < 1.3 1.7 f 1.8 < 1.2 -2.6 t 1.7 < 2.0 5.0 Other (Co-60) 1.0 f 2.2 < 3.7 -1.3 f 1.9 < 2.4 0.6 f 2.2 / < 3.8 15.0

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCilL)

E-40 Barta MDC MDC MDC Required Collection Date 01-14-09 02-1 1-09 03-1 1-09 LLD Lab Code EMI- 91 EMI- 451 EMI- 789 Sr-89 -0.5 f 1.2 < 1.0 -0.6 f 0.8 < 0.8 +

0.3 0.7 < 0.7 5.0 3-90 1.1 f 0.5 < 0.8 1.0 f 0.4 < 0.5 0.8 f 0.3 < 0.5 1.o 1-131 0.04 f 0.17 < 0.30 0.15 f 0.22 < 0.32 0.10 f 0.18 < 0.35 0.5 K-40 1343 f 103 1318 f 104 1365 f 97 0-134 0.4 f 1.5 < 3.2 0.4 f 1.7 < 2.7 -0.7 f 1.6 < 2.3 5.0 CS-137 0.0

1.8 < 2.9 -0.8 f 2.1 < 3.2 -0.6 f 1.7 < 2.4 5.0 Ba-La-140 -2.2 f 1.9 < 1.7 -0.2 f 1.6 < 1.7 -0.2 f 1.3. < 1.4 5.0 Other (Co-60) -0.1 f 2.2 < 4.2 1.8 f 2.3 < 3.6 0.1 1- 1.7 < 2.2 15.0 '

Required Collection Date 04-08-09 LLD Lab Code EMI- 1226 , EMI- 2086 EMI- 2816 K-40 CS-134 Cs-137 Ba-La-140 Other (Co-60)

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCilL)

E-40 Barta MDC MDC MDC Required Collection Date 07-08-09 08-12-09 09-09-09 LLD Lab Code EMI- 3389 EMI- 4240 EMI- 4681 Sr-89 0.8 f 1.1 < 1.1 0.5 f 1.1 < 1.0 0.1 f 0.9 < 0.8 5.0 Sr-90 0.6 f 0.3 < 0.4 0.7 f 0.3 < 0.4 0.6 f 0.3 < 0.5 1.o 1-131 -0.02 f 0.14 < 0.25 0.10 f 0.15 < 0.22 -0.12 f 0.14 < 0.27 0.5 K-40 1399 f 117 1445 f 108 1432 f 101

. CS-134 1.6 f 1.9 < 3.1 0.6 f 1,.7 < 2.5 -0.6 f 1.9 < 2.8 5.0 CS-137 -0.7 f 2.6 < 4.3 0.5 f 2.0 < 2.1 1.3 2 1.7 < 2.5 5.0 Ba-La-140 -0.1 f 1.6 < 2.8 1.8 t 1.6 < 3.2 -1.5 f 1.6 c 2.2 5.0 Other (Co-60) 1.8 f 2.4 < 3.7 0.7 f 2.2 < 1.8 0.7 i 1.8 < 1.5 15.0 Required Collection Date 10-14-09 LLD Lab Code EMI- 5525 EMI- 6282 EMI- 6759 K-40 Cs-134 CS-137 Ba-La-?40 Other (Co-60)

Sr-89 Annual Mean + s.d.

SF-90Annual Mean + s.d.

1-13'1 Annual Mean + s.d.

K-40 Annual Mean 9 s.d.

Cs-I34 Annual Mean + s.d.

Cs-I37 Annual Mean + s.d.

Ba-La Annual Mean .t s.d.

Co-60 Annual Mean + s.d.

POINT BEACH NUCLEAR PLANT Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly Ist Qtr. 2nd' Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean s.d Collection Date 10-17-09 Req.

Lab Code EWW- 139 EWW- 1657 EWW- 3633 EWW- 5642 LLD Gross Beta Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-N b-95 Cs-I 34 Cs-137 Ba-La-I40 Other (Ru-103)

MDC Data Collection Date 01-1 9-09 04-16-09 07-16-09 10-17-09 Req.

Lab Code EWW- 139 EWW- 1657 EWW- 3633 EWW- 5642 LLD Gross Beta < 3.0 <1.1 , < 3.9 <' 1.2 4.0 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-N b-95 Cs-134 CS-137 Ba-La-?40 Other (Ru-103)

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCilL MDC MDC MDC MDC Lab Code NSa NSa ELW- 799 ELW- 1653 Date Collected 01-13-09 02-12-09 03-10-09 04-16-09 Req. LLD Gross beta 3.4 f 0.9 c 1.3 1.5 f 0.6 c 0.9 4.0 1-131 -0.06 f 0.15 < 0.27 0.00 f 0.20 < 0.36 0.5 Be-7 5.3 f 14.9 c 26.9 4.8 f 14.2 c 27.0 Mn-54 0.3 f 1.3 c 2.0 1.3 f 1.9 < 2.8 10 Fe-59 0.1 f 3.5 c 5.3 -0.3 f 2.9 c 4.3 30 CO-58 -0,621.3 ~ 1 . 8 -1.Of1.5 ~2.0 10 Co-60 0.5 f 1.5 c 1.3 -0.1 f 1.8 c 2.3 10 Zn-65 -2.0 f 3.3 c 3.3 -2.2 t 4.1 c 3.6 30 Zr-Nb-95 0.5f1.4 c2.3 -0.8f1.7 ~ 1 . 8 15 CS-134 0.5 f 1.4 c 2.6 -2.2 f 1.6 < 2.0 10 CS-137 0.3 f 1.8 c 3.1 -2.2 f 1.8 < 2.0 10 Ba-La-140 -1.9f1.5 c1.2 -0.3f1.6 ~ 1 . 4 15 Other (Ru-103) 0.1 f 1.9 c 3.5 0.0 1: 1.9 c 3.9 30 Lab Code ELW- 2306 ELW- 3020 ELW- 3629 ELW- 4252 Date Collected 05-14-09 06-17-09 07-16-09 08-12-09 Req. LLD Gross beta 4.051.2 c1.9 1.6f1.1 ~2.0 1.5 f 0.6 < 0.9 2.0 f 1.1 < 1.9 4.0 1-131 0.01 f 0.20 c 0.35 0.18 f 0.19 c 0.32 0.02 f 0.16 c 0.28 0.03 f 0.25 c 0.36 0.5 Be-7 -12.9 It 14.1 < 29.7 -15.4 f 14.2 c 17.5 7.8 f 13.5 < 25.7 -5.8 f 17.0 < 20.8 Mn-54 0.8 f 1.3 c 2.0 0.5 f 1.6 c 2.1 *

-0.3 1.5 < 2.3 -0.4 f 1.7 < 3.0 10 Fe-59 -0.5 f 2.1 c 2.4 2.6 f 2.7 c 4.6 2.0 f 2.9 < 4.5 1.5 f 3.0 c 4.8 30 CO-58 -0.3 f 1.3 < 2.5 0.3 k 1.4 c 2.1 0.5 f 1.7 c 2.8 -0.2 f 1.5 < 2.2 10 CO-60 1.2 1: 1.3 c 2.2 -0.1 f 1.3 . c 2.2 0.3 t 2.0 c 3.8 0.1 f 1.8 < 0.9 10 Zn-65 -2.4 f 3.4 c 2.5 3.1 f 3.5 c 2.5 0.2 f 2.6 < 2.9 0.3 f 4.7 c 6.6 30 Zr-Nb-95 0.4 f 1.4 c 3.2 0.0 f 1.6 c 2.6 0.1 f 1.7 c 3.5 0.0 f 1.6 < 3.9 15 Cs-134 0.2 f 1.6 c 1.9 0.8 1: 1.4 c 2.3 -1.5f1.8 ~ 2 . 3 -0.2 f 1.8 < 2.5 10 CS-137 . 1.9f1.8 c3.1 0.9 f 1.8 c 2.9 0.2 f 2.0 < 3.4 -0.8 f 2.0 c 3.0 10 Ba-La-140 -5.9 f 1.7 < 2.4 -2.5 f 1.8 < 1.4 -1.4 f 2.0 ' c 2.3 0.3 f 2.0 c 3.0 15 Other (Ru-103) 0.9 f 1.5 c 3.3 0.1 f 1.7 c 3.6 -0.1 f 1.8 < 2.2 0.7 It 2.0 < 3.7 30 Lab Code ELW- 4940 ELW- 5637 ELW- 6347 ELW- 6876 Date Collected Gross beta 1-131 09-16-09 1.2 f 0.6

-0.03 f 0.14 c 0.9

< 0.26 10-17-09 1.1 f 0.6

-0.03 f 0.14

< 1.0

< 0.26 11-13-09 3.2 f 2.0 0.06 f 0.11 c 3.6

< 0.16 12-17-09 0.8 f 1.4

-0.29 f 0.22

' c 2.5 C 0.33 Req. LLD 4.0 0.5 Be-7 -9.2 f 18.8 c 33.9 7.9 f 17.7 c 30.8 2.1 f 19.6 c 32.5 1.4 f 16.51 c 23.1 Mn-54 0.6 f 1.8 c 3.2 -0.7 f 1.7 c 2.9 -0.9 f 2.4 c 3.0 -0.2 f 1.5 c 1.4 10 Fe-59 2.1 f 4.0 c 4.4 0.3 f 3.2 < 3.4 0.2 f 4 . 0 c 6.1 0.9 f 3.1 c 4.8 30 CO-58 -0.4 f 1.9 < 3.8 -0.6 i 1.7 c 2.1 -0.9 f 2.4 c 3.0 -0.3 f 1.7 < 1.5 10 Co-60 0.8 f 1.8 c 1.9 1.1 f 1.5 c 2.0 2.2 f 2.5 c 2.7 -0.5 f 2.0 c 2.9 10 Zn-65 1.9 f 4.5 c 7.5 -4.6 f 3.7 c 2.9 2.2 f 4.1 c 5.2 4.3 c 4.3' c 3.5 30 Zr-Nb-95 1.8 f 1.5 c 2.7 -1.3 f 2.1 c 3.2 1.1 f 2.3 < 4.1 1.2t1.9 c3.5 15 CS-134 -0.1 f 1.8 c 2.6 -0.6 f 1.8 c 2.8 -0.1 f 2.0 c 4.1 -0.5 f 1.8 c 2.7 10 CS-137 0.9 f 2.0 < 3.0 -0.9 f 2 . 3 c 3.1 3.5 f 2.7 c 4.3 -1.3 f 2.1 c 2.3 10 Ba-La-140 1.6 f 2.2 c 3.2 2.0 1: 1.8 c 1.9 -0.5 f 2.7 c 4.2 -0.4 f 1.8 c 2.2 15 Other (Ru-103) 3.4 f 2.0 G 3.9 0.3 f 2.1 c 4.1 -1.7 f 2.3 c 4.2 -1.0 f 2.0 c 3.5 30

POINT BEACH Table 5. Lake water, analyses tor gross beta, iodine-131 and gamma emitting isotopes.

Location: E-05 (Two Creeks Park)

Collection: Monthly composites Units: pCilL MDC MDC MDC MDC Lab Code ELW- 491 ELW- BOO ELW- 1654 Date Collected 02-12-09 03-10-09 04-16-09 Req. LLD Gross beta i.7f1.0 c1.7 2.1 f 0.7 c 1.2 1.6 f 0.6 c 0.9 4.0 '

1-131 0.18 f 0.27 c 0.47 0.08 f 0.16 c 0.28 -0.06 f 0.19 C 0.34 0.5 Be-7 -15.3 f 13.1 < 22.4 1.1 f 15.4 c 26.3 17.0f14.0 ~31.7 Mn-54 1.8f1.8 c3.4 0.6f1.4 c1.9 0.4 t 1.7 c 2.8 Fed9 3.1 t 2.6 c 3.4 -2.7 f 2.8 < 2.1 -1.2 f 3.2 c 4.0 CO-58 -0.2 f 1.5 < 2.5 -1.2f1.3 ~ 1 . 0 -0.6 f 1.4 c 2.0 Co-60 -0.3 f 1.8 < 2.4 0.221.3 c1.4 -0.6 It 1.6 c 1.3 Zn-65 -1.9 f 2.6 c 2.4 -4.3 f 3.5 < 2.5 1.6 f 2.9 c 4.1 Zr-Nb-95 -0.4 f 1.4 c 2.4 -0.1 t 1.7 < 3.1 -0.8 f 1.7 c 2.6 CS-134 0.5 f 1.3 c 2.8 -0.8 f 1.4 c 2.1 0.0 f 1.5 c 2.2 Cs-137 0.4 f 1.6 c 2.6 -0.6 f 1.7 c 2.6 -0.6 f 1.4 < 1.8 Ba-La-I 40 0.9f1.1 cl.6 -0.9 f 1.8 c 2.2 0.1f1.3 c1.9 Other (Ru-103) 0.3 f 1.5 c 3.4 -2.1 f 1.8 c 2.5 -0.9 f 1.3 c 2.2 Lab Code ELW- 2307 ELW- 3021 ELW- 3630 ELW- 4253 Date Collected 05-14-09 06-17-09 07-16-09 08-12-09 Req. LLD Gross beta 3.0 f 1.0 c 1.7 1.7 -1: 0.9 c 1.7 1.9 f 0.6 c 0.7 1.5f0.9 c1.7 4.0 1-131 0.06 f 0.23 c 0.44 0.15f0.16 ~0.24 0.08 f 0.17 < 0.29 0.20 f 0.23 c 0.35 0.5 Be-7 -13.7 f 12.9 c 23.2 9.4 f 15.8 c 29.0 5.0 f 13.2 c 27.3 0.2 f 19.9 c 32.5 Mn-54 -0.4 f 1.6 c 2.3 -1.2 f 1.7 < 2.4 -0.5 f 1.5 < 2.1 -0.8 f 1.8 < 2.0 Fe-59 -1.7 f 3.0 < 5.7 -0.2 f 2.9 < 4.1 1.6 f 2.6 c 5.2 1.6 f 3.7 c 5.5 CO-58 2.3 f 1.6 c 3.3 1.1 f 1.7 c 1.9 -0.4 f 1.7 < 3.2 -0.2

1.8 < 2.0 Co-60 -0.2 f 1.4 c 1.8 1.1f1.8 ~2.9 0.7 f 1.6 c 2.3 -1.6f1.6 ~ 1 . 5 Zn-65 -0.3 f 3.0 c 5.3 1.0

3.9 c 4.9 2.8 f 3.3 c 5.1 -0.7 f 4.7 c 5.7 Zr-Nb-95 -1.1 f 1.9 < 4.0 -0.1 f 1.8 < 2.0 0.1 f 1.8 c 3.1 1.4 f 2.0 c 4.4 Cs-134 -0.6 f 1.9 c 2.3 0.8 f 1.7 c 2.8 -0.5 f 1.4 c 1.7 0.1 f 1.9 c 3.9 CS-137 0.5 f 2.0 c 4.0 -0.4 f 1.8 c 2.7 l.0f1.9 c3.4 0.9 f 2.1 c 3.9 Ba-La-140 0.3 f 1.8 c 9.1 -0.9 f 2.0 < 2.9 -0.2 t 1.5 c 1.7

4.5 2.1 c 3.5 Other (Ru-103) -1.7 f 1.4 c 2.9 -0.4 f 2.0 < 3.3 -0.4f1.5 ~ 3 . 1 0.5 f: 2.2 c 3.6 Lab Code ELW- 4941 EL\N- 5638 ELW- 6348 ELW- 6877 Date Collected .09-16-09 10-17-09 11-13-09 . 12-17-09 Req. LLD Gross beta 1.0 f 0.5 c 0.8 0.9 f 0.5 c 0.9 3.0 f 1.8 < 3.2 2.1 f 1.3 < 2.3 4.0 1-33? 0.07 f 0.13 C 0.18 -0.06 f 0.14 < 0.27 0.09 f 0.11 c 0.16 0.12 f 0.12 < 0.17 0.5 Be-7 9.6 f 13.5 c 26.4 -3.9 f 13.9 c 21.1 -7.5 f 12.7 < 20.7 4.2 f 12.9 c 25.8 Mn-54 0.1 f 1.5 c 2.3 -0.1 f 1.6 c 2.4 -0.8 f 1.5 c 1.6 0.5 f 1.6 c 3.1 Fe-59 -0.5 f 3.2 c 6.0 -0.3 f 3.6 c 4.4 -0.4 t 2.4 c 3.8 -0.9 f 2.8 < 3.6 CO-58 -0.4 f 1.7 c 2.1 0.4 f 1.4 < 1.6 -1.0t1.6 cl.4 -0.1 f 1.5 < 2.0 CO-60 0.4 f 1.8 < 2.4. 2.1 f 1.9 < 2.7 -0.4 f 1.3 < 1.7 0.1 f 1.6 c 2.0 Zn-65 -0.5 f 3.6 c 4.0 -1.1 f 3.8 c 4.9 -0.1 f 2.8 c 3.4 1.8 f 2.9 c 3.7 Zr-Nb-95 -0.4 f 1.7 c 3.6 -2.0 t 1.8 c 2.1 -1.1 f 1.7 < 2.1 -0.9 f 1.6 c 2.7 CS-134 0.8 f 1.7 c 3.2 -0.6 f 1.6 < 2.3 O.lf1.3 ~ 1 . 8 0.2

1.3 c 2.2 Cs-137 0.6 f 1.8 c 2.9 -O.'1 t 1.8 < 3.3 0.3 f 1.5 c 3.1 -1.6f1.3 ~ 1 . 7 Ba-La-?40 0.3t1.5 c2.2 1.0fl.Q ~ 1 . 9 -0.5 f 2.0 c 2.3 -0.1r1.9 c1.8 O t h ~(Ru-103) r -0.2 t I .4 < 2.5 -1.2 f 1.6 C 2.8 0.8 f 1.4 c 2.9 -0.7 t 1.5 < 1.7

""NS'=No sample; see Table 2.0, Listing of Missed Samples.

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: pCilL MDC MDC UDC MDC Lab Code NSa ELW- 492 ELW- 801 ELW- 1655 Date Collected , 01-13-09 02-12-09 03-10-09 04-16-09 Req. LLD Gross beta 0.4 f 0.9 < 1.7 2.5 f 0.8 c 1.3 1.4 f 0.6 c 0.9 4.0 1-13? 0.05 f 0.22 < 0.39 0.02 f 0.16 C 0.28 0.05 f 0.18 < 0.32 0.5 Be-7 -3.8 1: 14.9 c 26.5 5.6 f 12.1 < 22.5 10.6 f 13.4 < 27.4 Mn-54 0.3 f 1.5 < 2.5 1.3 f 1.3 c 2.5 0.0 f 1.3 c 2.0 10 Fe-59 -2.1 f 3.1 c 3.9 2.5 f 2.0 c 2.5 2.5 f 2.7 < 5.1 30 CO-58 0.3 f 1.6 c 2.2 1.0 f 1.4 c 2.4 -0.8 f 1.6 < 2.2 10 Co-60 0.3 f 1.8 c 2.3 0.5 f 1.2 < 1.7 -0.8 f 1.5 < 1.8 10 Zn-65 0.7 f 3.7 < 4.1 2.0 t 2.7 < 4.2 3.6 f 2.8 < 2.7 30 Zr-Nb-95 -0.2 f 1.7 < 3.3 -0.1 f 1.6 c 3.0 -0.3 f 1.5 < 2.9 15 CS-134 0.4 t 1.7 c 3.1 -0.7 f 1.3 < 2.1 0.3 f 1.6 < 2.8 10 CS-137 -0.5 f 1.7 < 2.8 1.2 f 1.4 < 2.4 -1.1 f 1.7 < 2.1 10 Ba-La-140 1.7 f 2.2 c 2.9 0.8 f 1.6 c 1.5 1.3 f 1.6 c 3.1 15 Other (Ru-103) 1.1 f 1.8 < 3.2 0.6 f 1.2 c 2.5 -0.9 f 1.4 < 2.2 30 Lab Code ELW- 2308 ELW- 3022 ELW- 3631 ELW- 4254 Date Collected 05-14-09 06-17-09 07-16-09 08-12-09 Req. LLO Gross beta 2.6f1.1 ~1.9 1.7f1.0 c1.9 3.5 f 1.2 c 1.6 2.1f1.0 ~1.9 4.0 1-33? -0.63 f 0.29 < 0.49 0.04 f 0.21 < 0.38 0.15 f 0.18 < 0.31 0.22 f 0.22 < 0.32 0.5 Be-7 -0.3 f 11.4 < 27.5 -14.0 f 12.2 < 13.0 15.0 f 14.0 c 34.0 -7.7 f 16.9 < 28.3 Mn-54 05fl.l ~ 1 . 9 1.3 rn 1.3 < 2.6 0.9 f 1.4 < 2.4 -1.0 f 1.6 c 2.2 Fe-59 -1.2 f 2.1 < 2.4 -1.6 f 2.4 < 3.1 -1.7 f 2.7 < 2.4 -3.0 f 3.3 4 2.4 CO-58 -1.0 f 1.3 < 2.2 -1:9 f 1.3 < 0.9 -2.2 t 1.8 < 1.9 -0.6 f 1.6 < 2.3 Co-60 0.5 f 1.6 c 2.6 0.5 f 1.6 < 2.0 -0.7 f 1.5 , c 1.9 -0.1 f 1.7 c 2.2 Zn-65 0.5 f 2.7 c 3.6 0.4 t 2.4 < 3.0 -1.0 f 3.3 c 3.5 -1.8 f 3.8 < 3.6 Zr-Nb-95 0.3 f 1.2 < 2.7 0.7 t 1.4 < 3.1 0.6 f 1.5 c 2.2 1.0t1.8 c3.0 Cs-134 -1.7 f 1.8 < 2.0 0.0 f 1.5 c 2.1 0.9 f 1.4 < 2.7 -1.6f1.8 ~3.3 Cs-137 -0.4 f 1.$ < 2.3 -0.1 f 1.7 c 2.6 -0.7 f 1.5 < 1.8 2.0 2 1.8 < 3.3 Ba-La-140 0.621.8 ~6.1 -1.4 t 1.7 < 2.8 -0.2 f 2.0 < 4.3 -2.1 i 2.0 < 3.0 Other (Ru-103) -1.0 f 1.1 < 2.2 0.5 f 1.5 < 3.5 1.0 f 1.2 < 3.0 -1.O f 1.8 < 2.3 Lab Code ELW- 4942 ELW- 5639 ELW- 6349 ELW- 6878 Date Collected 09-16-09 10-17-09 11-13-09 12-17-09 Req. LLD Gross beta 1.1 f 0.6 < 0.9 1.2 f 0.6 < 0.9 2.8 i 1.9 c 3.6 3.8 f 1.6 / < 2.6 4.0 1-131 0.06 f 0.15 c 0.26 -0.05 f 0.18 C 0.33 0.01 f 0.14 < 0.25 0.07 f 0.15 c 0.27 0.5 Be-7 -2.7 f 12.4 < 18.4 19.7 f 15,.3 c 28.2 6.4 f 12.1 < 24.5 -4.9 f 13.1 c 19.7 Mn-54 0.1 t 1.7 c 2.4 0.4 f 1.8 < 3.1 0.4 1: 1.3 < 2.1 0.1 f 1.5 / < 2.8 Fe-59 0.4 f 2.8 c 5.2 1.7 t 3.8 < 5.9 0.4 f 2.5 < 2.9 -1.1 f 3.1 < 5.6 CO-58 -1.2 f 1.7 < 1.7 -1.0 t 1.9 < 2.6 0.6 f 1.5 . c 2.4 0.1 -1 1.5 < 2.8 CO-60 -1.4 f 1.8 < 1.4 0.5 f 2.0 < 2.3 0.5 f 1.2 c 2.3 0.3 f 1.6 c 2.7 Zn-65 0.2 f 2.9 c 2.8 -1.6 t 3.5 < 3.8 1.1f2.5 ~ 1 . 9 -0.5 f 3.0 c 4.1 Zr-Nb-95 1.2f1.7 c3.8 1.2 f 2.1 < 3.5 0.1 f 1.4 c 2.2 -3.4 f 2.0 < 2.2 Cs-134 0.3 f 1.7 < 2.8 -0.1 f 1.8 c 2.9 0.4 t 1.3 < 2.1 0.5 f 1.4 / < 2.7 Cs-137 0.4 f 1.9 c 2.7 -0.5 f 1.9 < 3.1 -0.9 'f 1.4 c 1.9 0.4 c 1.5 < 2.5 Ba-La-140 2.2 f 1.9 c 2.9 -3.8 f 2.2 < 1.4 0.1f1.5 ~ 1 . 4 -1.0 f 2.4 < 3.6 Other (Ru-103) 0.0 f 1.6 c 2.9 -0.8 f 1.9 c 2.9 -0.1 f 1.5 < 3.2 -0.6 f 1.6 c 3.4 a"I\lS"= Pio sample; see Table 2.0, Listing of blissed Samples.

POINT BEACH Table 5. Lake water, analyses tor gross beta, iodine-131 and gamma emitting isotopes.

Location: E-99(Nature Conservancy)

Collection: Monthly composltes Units: pCilL MDC MDC MDC MDC Lab Code ELW- 113 ELW- 493 ELW- 802 ELW- 1656 Date Collected 01-13-09 02-12-09 03-10-09 04-16-09 Req. LLD Gross beta 3.8f1.2 c1.6 3.1 f 1.1 < 1.7 1.4fO.6 c1.3 1.2 f 0.5 < 0.8 4.0 1-131 0.06 i 0.20 < 0.35 0.37 f 0.38 c 0.50 0.07 f 0.18 c 0.31 -0.08 f 0.17 < 0.31 0.5 Be-7 -0.7 f 16.8 , < 38.4 -10.2 f 13.7 < 23.9 -3.7 f 12.4 < 19.9 0.3 f 13.3 < 22.2 Mn-54 1.9 i 2.0 < 3.6 1.4 1: 1.8 < 2.9 -1.3 i 1.5 < 1.5 -0.5f1.5 ~1.9 Fe-59 0.4 f 3.8 c 3.7 0.9 t 3.4 < 5.6 1.5 f 2.0 < 3.2 -2.3 i 2.8 < 2.5 Co-58 0.1 f 2.1 < 2.3 -0.3 f 1.6 < 2.4 -0.5f1.2' ~ 1 . 5 I f 1.8 < 3.4 Co-60 1.8 f 2.3 < 4.0 0.2 1.7 < 2.7 -0.4 +- 1.3 < 1.5 1.Oi1.7 ~ 2 . 5 Zn-65 -2.4 f 5.0 < 5.8 -1.8 i 2.8 < 3.1 1.4 t 2.5 < 2.9 0.3. f 3.5 < 4.6 Zr-Nb-95 0.7 f 2.0 c 3.5 0.6 f 1.5 < 3.9 +

-1.0 1.2 < 1.7. 0.8 f 1.7 c 4.0 Cs-134 1.3f1.9 ~ 3 . 7 +

0.8 1.4 < 2.8 0.5 f 1.3 < 2.3 -0.3 i 1.5 < 2.3 CS-137 -1.9 f 2.4 < 3.5 0.2 f 1.6 c 3.1 1.5f1.4 ~2.7 1.2f1.9 ~3.1 Ba-La-140 0.2 f 3.1 < 7.2 1.1f1.6 ~2.2 1.5 f 1.5 c 2.8 -3.1 i 2.0 < 2.3 Other (Ru-103) 0.9 f 2.3 < 4.6 -0.7 f 1.5 < 2.7 -1.7f1.5 ~ 1 . 3 -0.2 i 1.5 < 2.6 Lab Code ELW- 2309 ELW- 3023 ELW- 3632 ELW- 4255 Date Collected 05-14-09 06-17-09 07-16-09 - 08-12-09 Req. LLD Gross beta 2.5f1.1 c1.9 1.8 f 1.0 c 1.8 2.0 f 0.6 c 0.7 2.0 f 0.9 c 1.7 4.0 1-131 -0.01 f 0.33 C 0.45 0.06 i 0.18 < 0.27 0.09 f 0.73 < 0.19 0.13 f 0.23 < 0.33 0.5 Be-7 -13.6 f 14.9 c 26.6 -4.0 f 12.2 < 23.1 1.8 f 16.2 < 27.2 2.2 i 21.8 c 40.0 Mn-54 0.9f1.1 ~ 1 . 6 -0.2 f 1.6 c 2.6 ,0.4 f 1.5 < 2.5 -0.9 i 2.0 < 3.3 Fe-59 1.5 f 2.3 < 2.7 -0.2 f 2.9 < 5.9 -1.5 f 3.1 - < 4.4 -0.5 f 4.5 < 4.7 CO-58 0.0 i 1.4 < 1.6 0.1 i 1.6 < 2.6 0.2 f 1.7 < 2.7 -0.9 f 1.7 < 1.6 Co-60 -1.4 f 1.6 c 2.1 0.321.3 ~1.4 0.2 i 1.9 < 2.4. 0.1 f 1.9 c 2.3 Zn-65 -0.6 f 3.2 < 3.2 -0.1 f 2.7 < 2.8 3.9 f 3.7 < 5.0 1.6 f 3.6 < 4.4 Zr-Nb-95 0.7 f 1.5 c 3.9 0.0 f 1.3 < 2.3 -1.3f1.7 ~ 2 . 5 -0.5 f 2.0 < 2.4 CS-134 0.4 f 1.6 < 2.6 +

-0.2 1.4 < 2.8 -0.2 i 1.8 < 2:9' -1.0 f 2.1 c-3.3 CS-137 1.0 f 1.8 < 3.4 -0.6i1.2 ~ 1 . 7 0.7 f 2.0 < 3.4 0.9 f 2.3 c 4.0 Ba-La-140 -1.1f1.8 ~2.5 2.9 f 1.5 < 3.5 0.5 f 1.9 c 3.6 -1.4 f 3.0 < 4.6 Other (Ru-103) , -0.4 f 1.6 c 3.6 -0.7 f 1.5 2.8 -0.9 f 1.7 < 2.9 0.3 t 2.2 c 4.0 Lab Code ELW- 4943 ELW- 5640 ELW- 6350 ELW- 6879 Date Collected 09-16-09 10-17-09 11-13-09 12-17-09 Req. LLD Gross beta 1.3 f 0.5 c 0.8 2.2f1.0 C1.6 7.6 f 2.1 a < 3.3 1.7 f 1.9 , < 3.7 4.0 1-131 0.10 f 0.16 c 0.27 0.09 i 0.16 c 0.28 -0.13 f 0.16 C 0.30 0.00 f 0.12 < 0.17 0.5 Be-7 -4.8 f 16.3 c 29.0 9.8 f 18.7 < 27.5 20.2 f 19.2 < 36.6 4.5 f 10.6 < 22.5 Mn-54 0.3 f 1.3 < 2.3 0.2 i 1.8 < 2.4 0.9 i 1.8 c 2.8 -0.2 It 1.3 < 1.5 Fe-59 2.2 f 3.1 c 3.7 -1.5 f 3.9 < 3.7 2.7 f 3.6 < 5.2 0.2' f 2.2 / < 3.9 CO-58 -0.1f1.3 ~ 1 . 8 -1.3f1.9 ~ 1 . 9 0.2 f 1.8 c 2.7 -0.3 i 1.4 c 2.0 Co-60 0.2f1.8 <1.6 -0.6i1.5 c1.1 0.2f1.4 ~ 1 . 6 -0.2f1.4 ~ 1 . 9 Zn-65 -5.0 f 3.7 < 3.1 1.9 t 4.2 < 5.2 -1.4 f 3.4 < 3.9 -0.3 f 2.6 < 3.9 Zr-Nb-95 -1.4 f 1.6 c 2.6 -0.7 f 1.9 < 1.8 -1.1f2.0 ~ 1 . 7 -1.4f1.4 / ~ 2 . 5 CS-134 1.2 f 1.6 c 2.3 0.5 f 1.9 < 3.0 0.7 f 1.7 < 2.9 -0.8 f 1.4 < 1.9 CS-137 0.4 f 1.7 .: 2.9 -1.1 f 2.1 < 3.0 -2.1 f 2.3 c 2.6 -0.6 f 1.5 < 1.7 Ba-La-140 0.3f1.9 ~3.0 1.5f1.9 ~2.5 -1.6 f 2.1 < 1.3 1.5f1.6' c3.7 Other (Ru-103) -2.2 f 1.9 c 2.7 0.0 i 2.1 < 3.0 1.9i2.0 ~4.1 0.3 f 1.2 c 2.6 a Gross beta recounted with a result of 6.3f1.7 pCIIL.

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-33a (Sandy Bay Pier)'

Collection: Monthly composites Units: pCilL MDC MDC MDC MDC Lab Code Date Collected Req. LLD Gross beta 4.0 1-131 0.5 Be-7 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 (3-134 CS-137 Ba-La-140 Other (Ru-103)

Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other (Ru-103)

All locations Lab Code ELW- 4944 ELW- 5641 ELW- 6351 Annual Date Collected 09-16-09 10-17-09 11-13-09 Mean s.d.

Gross beta 1.7 2 0.6 c 0.9 0.8 f 0.5 < 0.9 5.6 f 2.1 < 3.7 '2.2 t 1.3 1-131 0.13 t 0.16 < 0.27 0.12 f 0.18 < 0.34 -0.04 f 0.17 < 0.30 0.04 f 0.14 Be-7 -4.8 It 16.3 < 31.1 6.7 f 14.6 < 24.5 5.0 f 15.5 < 20.4 0.5 t 9.1 Mn-54 0.3 i 1.3 < 2.2 -0.7 t 1.6 < 2.3 -0.2 f 1.7 < 2.5 0.2 1: 0.8 Fe-59 2.2 f 3.1 < 5.7 -0.9 f 3.0 < 3.1 0.9 f 3.2 < 3.5 0.2 f 1.6 CO-58 -0.lt1.3 c1.7 -1.5 f 1.4 c 1.4 0.5 i 1.5 c 2.9 -0.3 5 0.8 Co-60 0.2

1.8 < 3.4 0.5 f 1.8 < 2.0 -1.1 k 1.5 < 1.6 0.2 t 0.8

-0.2 f 2.3 Zn-65 -5.0 t 3.7 < 2.7 -4.2 f 3.7 < 2.5 -0.2 f 3.8 < 6.0 Zr-Nb-95 -1.4 f 1.6 c 2.3 -1.2 t 1.7 c 1.9 -0.2 t 1.6 < 2.0 -0.2 t 1.0 Cs-134 1.2t1.6 e2.7 0.0 f 1.5 < 2.4 1.0t1.7 ~2.9 0.0 f 0.8 CS-137 0.4 t 1.7 2.6

0.8 2.1 c 3.7 0.9 f 2.0 < 3.0 0.1 t 1.1

-0.1 1.8 Ba-La-140 0.3 t 1.9 < 1.8 -2.4 f 1.9 < 1.3 -0.4 f 1.9 < 2.3 Other (Ru-103) -2.2 f 1.9 < 2.0 -0.9 f 2.0 < 3.5 -1.5 f 1.7 c 2.0 -0.3 t 1.1 a New location as of September 2009.

Gross beta recounted with a result of 4.521.5 pCilL.

"NS'= No sample; see Table 2.0, Listing of Missed Samples.

POINT BEACH NUCLEAR PLANT Table 6. Lake water, analyses for tritium, strontium-89 and strontium-90.

Collection: Quarterly composites of weekly grab samples Units: pCilL Location E-01 (Meteorological Tower)

Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4th Qtr. MDC Lab Code ELW- 806 ELW- 3093 ELW- 4968 ELW- 6889 Req. LLDs H-3 83282 <I49 82282 <I49 98295 <I49 120298/~153 500 Sr-89 0.50 k0.68 < 0.60 0.05 f 0.62 < 0.66 +

0.36 0.82 < 0.77 0.19 k0.74 < 0.78 5.0 Sr-90 0.00f0.32 ~ 0 . 7 0 0.33i0.27 ~ 0 . 4 9 0.3620.33 c0.62 0.1820.28 ~ 0 . 5 7 1.0 Location E-05 (Two Creeks Park)

Pedod Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 807 ELW- 3094 ELW- 4969 ELW- 6890, Req. LLDs Location E-06 (Coast Guard Station)

Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 808 ELW- 3095 ELW- 4970 ELW- 6891 Req. LLDs H-3 -10+78 <I49 124284 el49 108295 <I49 3 0 6 2 1 0 6 ~ ~ 1 5 3 500 Sr-89 0.76 20.80 < 0.61 -0.08 k0.61 < 0.65 -0.41 2 1.04 < 1.05 0.13 4 0.73 < 0.75 5.0 Sr-90 +

0.51 0.38 < 0.69 0.28 20.27 < 0.51 0.68 1.0.42 c 0.69 +

0.25 0.29 < 0.55 1.0 Location E-33 (Nature Conservancy)

Peiiod 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 809 ELW- 3096 ELW- 4971 ELW- 6892 Req. LLDs H-3 37280 <I49 64281 <I49 92294 <I49 157+84'<153 500 Sr-89 -0.46 2 0.75 < 0.58 0.05 20.60 .r 0.65 0.05 2 0.64 c 0.69 0.04 2 0.67 < 0.78 5.0 Sr-90 0.64 2 0.37 < 0.63 +

0.35 0.26 < 0.46 0.36 + 0.25 < 0.44 +

0.07 0.26 c 0.55 1.0 Location E-33a (Sandy Bay pierjb .

Period 3rd Qtr. 4th Qtr.

Lab Code ELW- 4944 ELW- 6 8 9 p Req. LLDs I Tritium Annual Mean + s.d. 419 k 8 0 Sr-89 Annual Mean + s.d. 0.16 i: 0.35 Sr-90 Annual Mean + s.d. 0.32 f 0.26 a Tritium repeated with a result of 377294 pCilL.

b Location added September 2009; 3rd quarter result on one month sample (Sept) only.

~ r i t i u mrepeated with a result of 245295 pCi1L. No December sample available for composite; see Table 2.0, page v.

Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x 1year Units: pCiIg wet Sample Description and Concentration Req.

MDC MDC MDC LLD Collection Date 03-12-09 03-12-09 03-12-09 Lab Code EF- 1116 EF- 1117 EF- I118 Type Fresh Water Drum Sucker Sucker Ratio (weffdry wt..) 5.19 Gross Beta 5.59 rt 0.t8 < 0.057 1.53 rt 0.06 < 0.024 K-40 1.16 _+ 1.16 Mn+4 -0.010 rt 0.016 < 0.024

~e-69 0.002 rt 0.034 < 0.070 CO-58 0.01 I rt 0.012 < 0.023 CO-60 -0.001 rt 0.018 < 0.028 Zn-65 0.003 rt 0.037 < 0.039 Cs-134 0.022 rt'0.015 < 0.023 Cs-137 0.008 rt 0.018 ..: 0.031 Other (Ru-103) 0.009 rt 0.016 < 0.044 Collection Date 06-20-09' 06-20-09 07-27-09 Lab Code EF- 4295 EF- 4296 EF- 4297

. Type Chinook Chinook Rainbow Trout Ratio (weffdry wt.) 3.36 3.37 4.23 Gross Beta 4.24 rt 0.09 < 0.032 Mn-54 Fe-59 CO-58 CO-60 Zn-65 Cs-134 Cs-137 Other (Ru-103)

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x / year Units: pCilg wet Sample Description and Concentration (pCi/g wet) Req.

MDC MDC MDC LLD Collection Date 07-20-09 06-20-09 12-09-09 Lab Code EF- 4298 EF- 4299 EF- 6880 Type Brown Trout Caifish Whitefish Ratio (wetldry wt.) 3.37 5.25 4.35 Gross Beta 2.89 f 0.06 < 0.018 4.16 f 0.09 c 0.033 5.22 t- 0.11 < 0.035 0.5 Mn-54 -0.003 f 0.006 < 0.008 Fe-59 0.002 f 0.015 < 0.030 CO-58 -0.001 f 0.007 < 0.016 Co-60 -0.002 f 0.009 < 0.015 Zn-65 0.010 t 0.015 < 0.013 Cs-134 -0.001,f 0.007 < 0.014 CS-137 0.039 f 0.017 Other (Ru-103) 0.006 f 0.007 < 0.015 Collection Date 12-09-09 12-09-09 12-09-09 Lab Code EF- 6881 EF- 6882 EF- 6883 Type Whitefish Whitefish Herring Ratio (wetldry wt.) 3.37 2.86 4.34 Gross Beta 443 + 0.11 < 0.039 K-40 3.41 f 0.35 Mn-54 0.001 t- 0.007 < 0.01 1 Fe-59 0.000 f 0.014 < 0.019 CO-58 -0.008 f 0.008 < 0.01 1 Co-60 0.003 f 0.009 < 0.013 Zn-65 -0.001 f 0.016 < 0.032 CS-134 -0.004 f 0.007 < 0.011 Cs-137 0.014 f 0.010/ < 0.016 Other (ku-103) 0.002 f 0.006 < 0.014

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x 1year Units: pCi1g wet Sample Description and Concentration (pCilg wet) Req.

MDC LLD Collection Date 12-09-09 Lab Code EF- 6884 Annual Type Herring Ratio (wetldry wt.) 5.68 Mean s.d.

Gross Beta 4.12 + 0.10 < 0.037 4.03 tt 1.05 K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Cs-134 Cs-137 Other (Ru-103)

POINT BEACH NUCLEAR PLANT Table 8. Radioactivity in shoreline sediment samples Collection: Semiannual Sample Description and Concentration (pCilg dry)

MDC MDC MDC Collection Date 411612009 411612009 411612009 Req.

Lab Code ESS- 1667 ESS- 1668 ESS- 1669 LLD Location Gross Beta Collection Date 411612009 411612009 Lab Code ESS- 1670 ESS- 1671 Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCi1g dry)

MDC MDC MDC Collection Date 1011712009 1011712009 1011712009 Req.

Lab Code ESS- 5643 ESS- 5644 ESS- 5645 LLD Location Gross Beta Be-7 '

K-40 CS-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date 1011712009 1011712009 1011712009 Lab Code ESS- 5616 ESS- 5647 ESS- 5648 Annual Location E-12 E-33 E-33A Mean s.d.

Gross Beta 11.23 f 2.14 c 3.03 12.26 + 2.02 c 2.82 11.26 f 1.94 2.69 4.0 11.12 4 'i.92

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sainple bescription and Concentration (pCi/g dry)

MDC MDC Collection Date 5/28/2009 5/28/2009 Req.

Lab Code ESO- 2632 ESO- 2633 ESO- 2634 a LLD Location Gross Beta Collection Date 5/28/2009 5/28/2009 5/28/2009 Lab Code . . ESO- 2635 ESO- 2636 ESO- 2637 Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date 5/28/2009 5/28/2009 Lab Code ESO- 2638 ESO- 2639 Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 a Sample recounted; revised data for K-40 and Cs-137.

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SOIL SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCi/g dry)

MDC MDC MDC Collection Date 10/28/2009 10/29/2008 10/29/2008 Req.

Lab Code ESO- 6048 ESO- 6049 ESO- 6050 LLD Location Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date 10/29/2008 10/29/2008 10/29/2008 Lab Code ESO- 6051 ESO- 6052 ESO- 6053 Location Gross Beta Be-7 K-40 Cs-I 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 Collection Date 10/29/2008 Lab Code ESO- 6056 Annual Location Mean s.d.

Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-2 14 Ra-226 Ac-228

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual

, Sample Description and Concentration (pCilg wet)

MBC MDC MDC Location E-01 E-02 E-03 Collection Date 5/28/2009 5/28/2009 5/28/2009 Lab Code EG- 2623 EG- 2624 EG- 2625 Req. LLD Ratio (wetldry) 5.45 5.45 Gross Beta 6.31 t 0.22 7.14 t 0.20 Be-7 0.27 t 0.08 0.23 t 0.13 K-40 5.10 t 0.42 4.69 t 0.45 1-131 0.009 t 0.008 Cs-134 0.005 t 0.010 Cs-137 -0.002 t 0.008 Other (Co-60) 0.003 t 0.008 Location E-04 E-06 E-08 Collection Date 5/28/2009 5/28/2009 5/28/2009 Lab Code EG- 2626 EG- 2628 EG- 2629 Req. LLD Ratio (wetldry) 9.39 4.91 5.37 Gross Beta 6.32 t 0.19 7.20 k.0.24 < 0.087 6.21 t 0.20 < 0.069 Be-7 0.33 t 0.13 0.44 t 0.21 0.27 t 0.09 < 0.18 K-40 4.13 t 0.35 4.39 t 0.46 4.22 t 0.46 1-131 -0.006 t 0.008 0.001 t 0.008 < 0.034 Cs-134 0.010 t 0.008 0.005 t 0.01 1 < 0.018 Cs-137 0.003 t 0.008 0.011 t 0.009 < 0.016 Other (Co-60) 0.005 t 0.007 -0.008 t 0.009 < 0.012 Location E-09 E-20 Collection Date 5/28/2009 5/28/2009 Lab Code EG- 2630 EG- 2631 Req. LLD Ratio (wetidry) 4.52 4.02 Gross Beta 7.69 t 0.23 8.87 t .0.26 < 0.085 Be-7 0.67 t 0.18 0.46 t 0.20 K-40 5.40 10.43 4.93 t 0.42 1-131 0.014 t 0.008 0.005 t 0.008 < 0.036 CS-134 -0.001 k 0.009 -0.004 t 0.009 < 0.015 Cs-137 0.002 t 0.009 0.003 t 0.010 < 0.017 Other (Co-60) -0.002 t 0.010 0.002 t 0.007 < 0.010

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCilg wet)

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 7/30/2009 7/30/2009 7/30/2009 Lab Code EG- 4040 EG- 4041 EG- 4042 Req. LLD Ratio (wetldry) 2.55 3.41 3.99 Gross Beta 8.08 t 0.27 8.88 t 0.28 < 0.120 7.86 r 0.19 Be-7 1.45 t 0.27 1.22 i 0.23 0.80 t 0.16 K-40 4.93 t 0.44 6.22 t 0.46 6.57 t 0.42 1-131 -0.013 t 0.008 0.005 t 0.008 < 0.023 Cs-134 0.004 t 0.008 -0.003 t 0.008 < 0,011 Cs-137 0.002 t 00.09 -0.003 f 0.009 < 0.012 Other (Co-60) 0.001 t 0.009 -0.002 t 0.010 < 0.015 Location E-04 E-06 E-08 Collection Date 7/30/2009 7/30/2009 7/30/2009 Lab Code EG- 4043 EG- 4044 EG- 4045 Req. LLD Ratio (wetldry) 2.75 4.30 4.18 Gross Beta 7.23 t 0.20 < 0.077 4.84 t 0.10 < 0.039 3.49 t 0.12 Be-7 1.24 t 0.20 0.71 t 0.18 1.54 r 0.20 K-40 4.98 t 0.46 3.04 t 0.35 2.64 t 0.30 1-131 0.012 t 0.009 < 0.024 0.001 t 0.008 < 0.026 0.006 t 0.007 Cs-134 -0.005 t 0.01 1 < 0.019 0.004 t 0.007 < 0.012 -0.005 r 0.006 Cs-137 0.000 t 0.012 < 0.019 0.024 t 0.011 < 0.018 0.008 t 0.009 Other (Co-60) 0.001 t 0.0'12 < 0.010 -0.001 t 0.007 < 0.008 0.008 t 0.008 Location E-09 E-20 Collection Date 7/30/2009 7/30/2009 Lab Code EG- 4046 EG- 4047 Req. LLD Ratio (wetldry) 2.72 Gross Beta 7.25 t 0.20 Be-7 1.42 t 0.18 K-40 4.65 t 0.36 1-131 0.000 t 0.005 CS-134 0.001 t 0.006 CS-137 0.003 t 0.006 Other (Co-60) 0.004 + 0.007

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCilg wet)

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 9/30/2009 9/30/2009 9/30/2009 Lab Code EG- 5299 EG- 5300 EG- 5301 Req. LLD Ratio (weffdry) 2.30 3.73 4.05 Gross Beta 6.44 t 0.12 8.25 t 0.21 2.25 t 0.06 . < 0.014 Be-7 2.29 i 0.26 1.51 t 0.23 K-40 5.31 t 0.48 6.43 t 0.47 1-131 -0.004 t 0.009 -0.010 t 0.008 Cs-134 -0.002 i 0.007 -0.007 t 0.007 Cs-137 0.003 t 0.008 0.001 t 0.009 Other (Co-60) -0.007 t 0.008 -0.010 t 0.01'0 Location E-04 E-06 E-08 Collection Date 9/30/2009 9/30/2009 9/30/2009 Lab Code EG- 5302 EG- 5303 EG- 5304 Req. LLD

, Ratio (weffdry) 2.56 2.41 2.48 Gross Beta 1.49 t 0.04 1.10 t 0.03 < 0.010 1.73 t 0.04 < 0.008 0.25 Be-7 K-40 1-131 Cs-134 CS-137 Other (Co-60)

Location E-09 E-20 Collection Date 9/30/2009 9/30/2009 Lab Code EG- 5305 EG- 5306 Req. LLD Ratio (weffdry) 2.44 3.01 Gross Beta 2.16 t 0.06 1.96 t 0.05 < 0.01 1 Be-7 2.47 t 0.23 1.85 t 0.25 K-40 4.17 t 0.38 5.62 t 0.48 1-73? -0.004 t 0.007 0.010 t 0.009 < 0.028 Cs-134 -0.004 t 0.007 0.004 t 0.009 < 0.016 Cs-137 0.002 t 0.008 0.006 t 0.010 < 0.019 Other (Co-60) -0.002 i 0.008 -0.005 t 0.008 < 0,007 Gross Beta Annual Mean + s.d +

5.57 2.55 Be-7 Annual Mean + s.d. +

I.38 1.08 K-40 Annual Mean + s.d. 4.72 k 1.04 1-131 Annual Mean + s.d. 0.000 k 0.007 Cs-134 Annual Mean + s.d. +

-0.001 0.005 Cs-137 Annual Mean + s.d. +

0.007 0.016 Co-60 Annual Mean + s.d. -0.001 f 0.006

POINT BEACH NUCLEAR PLANT Table 1I.Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.

Collection: Semiannual Units: .pCi/g wet Sample Description and Concentration Collection Date . 06-12-09 MDC 06-12-09 MDC Req.

Lab Code ESL- 2925 ESL- 2926 LLD Location E-05 E-12 Ratio (wet wt./di-y wt.) 8.24 5.41 Gross Beta 3.60 k 0.17 < 0.11 4.20 k 0.28 Be-7 0.83 k 0.31 1.43 _+ 0.19 K-40 2.62 k 0.56 2.41 k 0.31 CO-58 0.003 k 0.014 c 0.021 0.004 2 0.007 CO-60 -0.009 k 0.018 < 0.022 0.005 k 0.009 Cs-I 34 -0.004 k 0.015 < 0.023 -0.004 k 0.008 Cs-137 -0.002 k 0.017 c 0.023 0.014 k 0.009 Collection Date 08-06-09 08-06-09 Req.

Lab Code ESL- 4164 ESL- 4166 LLD Location E-05 ,E-12 Ratio (wet wt.1d1-y wt.) 6.37 4.54 Gross Beta 2.82 2 0.31 < 0.28 5.13 k 0.47 Be-7 0.59 k 0.35 0.98 k 0.26 K-40 1.39 0.50

_+ 2.00 _+ 0.31 CO-58 0.002 k 0.017 < 0.036 0.001 _+ 0.008 CO-60 0.015 k 0.018 < 0.033 0.006 k 0.009 Cs-I 34 -0.002 k 0.019 < 0.037 0.007 :k 0.008 Cs-I 37 0.030 k 0.022 < 0.039 0.029 k 0.017 Collection Date 10-07-09 10-07-09 Req.

Lab Code ESL- 54.03 ESL- 5404 LLD Annual Location E-05 E-12 Mean s.d.

Ratio (wet wt./dry wt.) 3.99 3.58 Gross Beta 7.22 k 0.66 < 0.53 8.76 k 0.80 Be-7 0.88 It 0.23 0.63 k 0.23 K-40 3.01 k 0.41 4.70 k 0.78 CO 0.004 _+ 0.008 < 0.012 -0.025 k 0.024 Co-60 0.008 k 0.010 < 0.016 -0.004 k 0.027 Cs-134 -0.01 1 k 0.009 < 0.013 -0.008 2 0.024 Cs-137 0.012 k 0.01 1 < 0.020 0.014 k 0.028

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 1st. Quarter, 2009 Date Annealed: - - Days in the field 88 Date Placed: 01-09-09 Days from Annealing Date Removed: 04-07-09 to Readout: 139 Date Read: 04-20-09 Davs In Location ~feld Total mR Net mR Net mR per 7 days Indicator E- 1 88 17.4 rt 1.3 10.6 rt 1.5 0.84 rt 0.12 Control E-20 In-Transit Exposure Date Annealed 12-02-08 03-1 1-09 Date Read 01-15-09 04-20-09 Total mR 8.2 rt 0.4 5.6 rt 0.6

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 2nd Quarter, 2009. ,

Date Annealed: 03-1 1-09 Days in the field 85 .

Date Placed: 04-07-09 Days from Annealing Date Removed: 07-01-09 to Readout: 118 Date Read: 07-07-09 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E- 1 85 +

14.4 0.8 +

10.2 1.1 +

0.84 0.09 E-2 85 +

19.9 1.1 +

15.7 1.3 +

1.30 0.1 I E-3 85 +

21 .I 1.5 +

16.9 1.7 +

1.39 0.14 E-4 85 +

17.2 0.2 +

13.0 0.8 +

1.07 0.06 E-5 85 +

19.3 0.4 +

15.1 0.8 +

1.25 0.07 E-6 85 +

17.3 0.6 +

13.1 1.0 +

1.08 0.08 E-7 85 +

16.1 0.5 +

11.9 0.9 0.98 C 0.07 E-8 85 +

17.2 0.6 +

13.0 1.O +

1.07 0.08 E-9 85 15.0 + 0.7 +

10.8 1.O +

0.89 0.08 E-12 85 +

18.9 1.3 +

14.7 1.5 +

1.21 0.12 E-14 85 +

18.0 1.3 +

13.8 1.5 +

1.14 0.12 E-15 85 +

21.1 1.0 +

16.9 1.2 1.39 + 0.10 E-16 85 +

17.2 0.3 +

13.0 0.8 1.07 + 0.07 E-17 85 +

17.4 1.1 +

13.2 1.3 +

1.09 0.1 1 E-18 85 +

19.0 0.4 +

14.8 0.8 +

1.22 0.07 E-22 85 18.9 + 0.5 +

14.7 0.9 +

1.21 0.07 E-23 85 +

20.1 0.7 +

15.9 1.0 1.31 + 0.08 E-24 85 +

18.3 0.2 +

14.1 0.8 +

1.16 0.06 E-25 85 +

20.2 0.5 +

16.0 0.9 +

1.32 0.07 E-26 85 +

16.5 0.6 +

12.3 1.0 +

1.02 0.08 E-27 85 20.9 + 0.5 +

16.7 0.9 1.38 + 0.07 E-28 85 +

14.5 0.1 +

10.3 0.7 +

0.85 0.06 E-29 85 +

14.7 0.5 +

10.5 0.9 0.87 + 0.07 E-30 85 +

17.1 0.2 +

12.9 0.8 +

1.06 0.06 E-3 1 85 +

19.5 0.2 +

15.3 0.8 +

1.26 0.06 E-32 85 16.6 + 0.3 +

12.4 0.8 +

1.02 0.07 E-38 85 +

16.3 0.5 +

12.1 0.9 +

I.OO 0.07 E-39 85 +

15.4 0.6 +

11.2 1.0 0.92 st 0.08 E-4 1 85 +

17.7 0.5 +

13.5 0.9 +

1.11 0.07 E-42 85 19.5 + 0.2 +

15.3 0.8 +

1.26 0.06 E-43 85 +

17.1 0.3 +

12.9 0.8 1.06 t 0.07 Control E-20 85 16.6 C 0.4 12.4 + 0.8 1.02 + 0.07 In-Transit Exposure Date Annealed 03-1 1-09 06-17-09 Date Read 04-20-09 07-08-09 Total mR

+

5.6 0.6 +

2.7 0.3

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 3rd Quarter, 2009 Date Annealed: 06-17-09 Days in the field 98

Date Placed: 07-01-09 Days from Arinealing Date Removed: 10-07-09 to Readout: 119 Date Read: 10-14-09 Days in Location Total mR Net mR Net rnR per 7 days Indicator, E-I +

0.80 0.05 E-2 +

I.22 0.08 E-3 +

1.54 0.12 E-4 +

1.17 0.10 E-5 1.19 + 0.10 E-6 +

1.11 0.12 E-7 +

1.14 0.06 E-8 +

1.06 0.07 E-9 +

1.36 0.06 E-12 +

0.88 0.1 1 E-I4 1.27 rt 0.03 E-I 5 +

1.32 0.06 E-I 6 +

1.19 0.04 E-17 1.24 i: 0.04 E-18 +

1.32 0.08 E-22 +

1.32 0.10 E-23 1.29 + 0.05 E-24 1.22 i: 0.05 E-25 +

1.23 0.04 E-26 +

1.07 0.04 E-27 1.40 ?I 0.04 E-28 +

0.80 0.03 E-29 +

0.87 0.06 E-30 1.07 + 0.08 E-3 1 1.24 1: 0.06 E-32 +

1.22 0.06 E-38 +

1.22 0.10 E-39 +

1.04 0.06 E-41 +

1.05 0.04 E-42 1.17 + 0.03 E-43 +

1.18 0.03 Control E-20 98 19.3 k 'I -

.I 16.2 + 1.2 1.16 + 0.08 In-Transit Exposure Date Annealed 06-17-09 09-13-09 Date Read 07-08-09 10-14-09 Total rnR

+

2.7 0.3 +

3.5 0.1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation 4th Quarter, 2009 Date Annealed: 09-13-09 Days in the field 91 Date Placed: 10-07-09 ' Days from Annealing Date Removed: 01-06-1 0 to Readout: 122 Date Read: 01-1 3-1 0 Days in Location Field Total mR Net mR Net mR per 7 days lndicator E-I E-2 E-3 E-4 E-5 E-6 ET7 E-8 E-9 E-I 2 E-14 E-I 5 E-1.6 E-I 7

'E-18

,E-22 E-23 E-24

. E-25 E-26 E-27 E-28 E-29

. E-30 E-3 1 E-32 E-38 E-39 E-4 1 E-42 E-43 Control E-20 In-Transit Exposure Date Annealed 09-13-09 12-01-09 Date Read 10-14-09 01-1 3-10 Total mR ITC-I 3.5 k 0.1 6.5 0.5 Annual Indicator Mean2s.d. 18.7 5 2.1 14.0 f 2.5 1-08 20.17 Annual Control Rileanfs.d. 18.8 5 2.2 14.1 f 1.8 1.09 20.10 Annual lndicatorlContro1 Mean2s 18.8 f $334 14.0 f 2.5 4.08 50.17

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Intermittent Streams Sample ID GW-02 Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCi1L) (PCIIL) Date Lab Code (pCilL) (~cVL) 01-28-09 NSa 02-28-09 NSa 03-26-09 EWW-1017 249 f 95 458 04-29-09 EWW-2002 314 4 94 <I58 05-28-09 EWW-2617 ' 383 f 101 458 07-02-09 .EWW-3362 141 f 80 447 07-30-09 EWW-4050 64 f 74 <I49 09-30-09 EWW-5283 86 f 81 <I54 10-28-09 EWW-6044 301 f 103 <I48 11-25-09 EWW-6548 204 -+ 89 <749 12-23-09 12-23-09 Mean + s.d. Mean + s.d.

Sample ID GW-03 GW-17 Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCiIL) (pcVL) Date Lab Code (pCi/L) (pc'i~)

01-28-09 NSa 01-28-09 NSa 02-28-09 NSa 02-28-09 NSa 03-26-09 EWW-1018 144 f 90 <I58 03-26-09 EWW-1020 223 f 94 < I 58 04-29-09 EWW-2003 34 f 80 <I58 04-29-09 EWW-2006 240 f 91 458.

05-28-09 EWW-2618 66 4 87 <I58 05-28-09 EWW-2622 709 f 115 9158 07-02-09 EWW-3363 108 f 78 <I47 07-02-09 EWW-3365 251 f 86 447 07-30-09 EWW-4051 119 f 77 <I49 07-30-09 EWW-jO53 123 f 77 <I49 09-30-09 EWW-5284 196 f 86 <I54 08-26-09 EWW-4512 119 f 79 447 10-28-09 EWW-6045 66 f 93 <I48 09-30-09 EWW-5286 109 -+ 82 <I54 11-25-09 EWW-6549 145 3.86 <I49 10-28-09 EWW-6047 427 f 108 <I48 12-23-09 . NSC 11-25-09 EWW-6551 346 f 95 449 12-30-09 EWW-7271 141 f 80 450 Mean + s.d. 110 s 5 3 Mean + s.d. 283 f 192 Sample ID GW-04 (ElC Well) GW-11 (MW-1)

Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCilL) (pCilL) Date Lab Code (pCiIL) (pCi/L) 01-28-09 EWW-274 -50 f 72 <I52 01-23-09 EWW-275 105 f 8 1 <I52 02-25-09 EWW-614 -11 f 7 7 <148 02-26-09 EWW-733 108 f 8 1 <I51 03-26-09 EWW-1019 104 f 89 <I58 03-30-09 EWW-1165 123 f 98 <I52 04-29-09 EWW-2005 47 f 81 <I58 04-16-09 EWW-1660 90 f 83 <I57 05-28-09 EWW-2619 -9 f 83 <I58 05-26-09 EWW-2555 7 f 81 462 07-30-09 EWW-4052 -23 f 69 <I49 06-17-09 EWW-3024 76 f 82 <I49 08-26-09 EWW-4511 -26 f 72 447 07-30-09 EWW-4054 82 f 75 <I49 09-30-09 EWW-5285 6 f 77 454 08-17-09 .EWW-4357 149 f 80 445 10-28-09 EWW-6046 19 f 90 <I48 09-16-09 EWW-5093 50 f 7 8 <I52 1 1-25-09 EWW-6550 45 f 81 <I49 11-05-09 EWW-6199 41 f 96 <I55 12-23-09 NSC 11-21-09 EWW-6472 145 f 96 <I47 12-23-09 EWW-7113 140f103 461 Mean + s.d. 10 f 4 5 Mean + s.d. 93 f 44 a "NS" = no sample; streams frozen.

"NS" = no sample; creek dried up.

C 1, NS" = no sample; not sent.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCilL Wells (conf.)

Sample ID GW-12 (MW-2) GW-13 (MW-6)

Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCi/L) (PCW Date Lab Code (pCilL) (PCW

.01-23-09 EWW-276 59 f 78 452 01-23-09 EWW-277 36 f 77 el52 02-26-09 EWW-734 14f76 451 02-26-09 EWW-735 60 f 78 451 03-30-09 EWW-1166 60 1:79 452 03-30-09 EWW-1167 131 f 8 3 < I 52 04-16-09 EWW-1661 -51 f 75 <I57 04-16-09 EWW-1662 103 f 8 3 457 05-26-09 EWW-2557 -74 f 76 < I 62 05-26-09 EWW-2558 66 f 84 < I 62 06-17-09 EWW-3025 3 f 78 449 06-17-09 EWW-3026 116 f 8 4 < I 49 07-30-09 EWW-4055 12 f 71 449 07-30-09 EWW-4056 137 f 78 449 08-17-09 EWW-4358 -25 f .70 445 08-12-09 EWW-4359 82 f 76 445 09-16-09 EWW-5094 -19 f 74 452 09-16-09 EWW-5095 52 f 78 < I 52 11-05-09 EWW-6200 43 f 96 < I 55 11-05-09 EWW-6201 94 f 98 455 11-21-09 EWW-6473 60 f 92 447 11-21-09 EWW;6474 93 f 93 447 12-23-09 EWW-7114 38 k 99 <I61 12-23-09 EWW-7115 127 f 103 461 Mean + s.d. 10 f 45 Mean + s.d. 91 f 33 Sample ID GW-14 (MW-5) GW-15 (MW-4)

Collection MDC t Collection Tritium MDC Date Lab Code Tritium (pCilL) (pci/~) Date Lab Code (pCilL) (pci/~)

01-23-09 EWW-278 173 f 84 ~ 1 5 2 ~ 01-23-09 EWW-279 423 f 96 el52 02-26-09 EWW-736 101 k 8 0 <I51 02-26-09 EWW-737 566 f 102 <I51 03-30-09 EWW-1168 150 f 84 <I52 03-30-09 EWW-1170 615f105 <I52 04-16-09 EWW-1664 -10 f 77 7157 04-16-09 EWW-1665 446 f 100 457 05-26-09 EWW-2559 70 f 84 <I62 05-26-09 EWW-2560 379 f 99 < I 62 06-17-09 EWW-3028 50 f 8 1 el49 06-17-09 EWW-3029 387 f 96 <I49 07-30-09 EWW-4058 56 f 73 <I49 07-30-09 EWW-4059 423 f 91 <I49 08-17-09 EWW-4360 70 f 76 <I45 08-17-09 EWW-4361 495 f 96 <I45 09-16-09 EWW-5096 22 f 76 <I52 09-16-09 EWW-5097 452 f 97 <I52 11-05-09 EWW-6202 174 f 101 ~ 1 5 5 ~11-05-09 EWW-6203 410 f 109 <I55 11-21-09 EWW-6476 114 f 94 el47 11-21-09 EWW-6477 503 f 110 <I47 12-23-09 EWW-7116 144 f 103 <I61 12-23-09 EWW-7117 4522114 461 Mean + s.d. 93 f 60 Mean + s.d. 463 f 71 Sample ID GW-16 (MW-3)

Collection MDC Date Lab Code Tritium (pCilL) (pcii~)

01-23-09 EWW-280 33Lf8Z1 <I52 03-30-09 EWW-1171 382 f 95 <I52 04-16-09 EWW-1666 244 f 91 457 05-26-09 EWW-2561 138 f 88 < I 62 '

06-17-09 EWW-3030 175 f 87 <I49 07-30-09 EWW-4060 215 ct 82 <I49 08-17-09 EWW-4362 216 f 83 <I45 09-16-09 EWW-5098 230 f 87 <I52 11-05-09 EWW-6204 272 f 104 <I55 11-21-09 EWW-6478 296 f 102 <I47 12-23-09 EWW-7118 325f110 <I61 Mean + s.d. 239 f 77

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCilL Beach Drains Sample ID Collection MDC Collection Tritium MDC Date Lab Code Tritium ( p ~ i l ~ (pCi/L)

) Date Lab Code (pCilL) (PCW 01-09-09 EW-79 01-09-09 NSa 02-09-09 02-09-09 NSa 03-09-09 03-09-09 NSa 04-09-09 EW-1340 04-09-09 240 91+

05-07-09 EW-2163 05-07-09 375 98+

06-12-09 EW-2927 06-12-09 +

362 go7 07-09-09 EW-3439 07-09-09 534 -1 101 08-06-09 EW-4178 08-06-09 422 96+

09-10-09 EW-4742 09-10-09 669 4 113 09-16-09 EW-4945 09-24-09 488 f 98 09-24-09 EW-5088 09-30-09 241 f 102 09-30-09 EW-5280 10-08-09 235 98+

10-08-09 EW-5421 10-22-09 +

3688 193 10-22-09 EW-5855 10-28-09 323 90+

10-28-09 EW-6041 11-03-09 +

353 109 11-03-09 EW-6143 11-11-09 275 k 106 11-11-09 EW-6283 11-13-09 313 f 108 11-13-09 EW-6338 11-16-09 188 f 91 11-16-09 EW-6455 11-18-09 261 94+

II- j8-09 EW-6456 11-20-09 371 99+

11-20-09 E\N-6457 11-23-09 305 96+

11-23-09 EW-6458 11-25-09 1370 f 144 11-25-09 EW-6645 11-27-09 +

301 109 11-27-09 EW-6646 11-30-09 +

389 112 11-30-09 EW-6694 12-02-09 +

326 109 12-02-09 EW-6695 12-04-09 328 t 109 12-04-09 EW-6696 12-07-09 392 f 107 12-07-09 EW-6869 322 -1 95 12-08-09 EW-6760 450'+ 109.

12-08-09 EW-6870 381 f 107 12-11-09. EW-6871 +

379 108 12-16-09 EW-6925 377 P 108 12-18-09 EW-6926 281 t 104 12-21-09 EW-6927 287 f 90 12-30-09 EW-7030 Mean + s.d. Mean + s.d.

" "NS" = no sample; drains frozen.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCi1L Beach Drains Sample ID S-7 / 5-8 Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCi1L) (~CIIL) Date Lab Code (pCi/L) (~CIIL) 01-09-09 NSa 01-09-09 NSa 02-09-09 NSa 02-09-09 NSa 03-09-09 NSa 03-09-09 NSa 04-09-09 NS~ 04-09-09 EW-I342 575 t 106 <I58 05-07-09 NSC 05-07-09 NSC 06-1 2-09 NSC 06-1 2709 NSC 07-09-09 NSC 07-09-09 NSc 08-06-09 NSC 08-06-09 NSC 09-1 0-09 NSC 09-1 0-09 NSC 10-28-09 NSC 10-28-09 NSC 11-30-09 NSC 11-30-09 NSC 12-28-09 EW-7032 590 t 103 <I53 12-08-09 NS~

Mean + s.d. Mean + s.d.

Sample ID S-9 S-10 .'

Collection MDC Collection Tritium MDC Date Lab Code Tritium (pCi1L) (pCi/L) Date Lab Code (pCilL) IpCilL) 01-09-09 02-09-09 03-09-09 04-09-09 05-07-09 06-12-09 07-09-09 08-06-09 09-1 0-09 10-08-09 11-23-09 12-08-10 Mean + s.d.

Sample ID S-II*

Collection MDC Date Lab Code Tritium (pCi/L) (~CIIL) 461 12-02-09 EW-6701 I 88 t 104

<I 52 12-04-09 EW-6702 224 + 105 447 12-08-09 NS~

<I41 444

<I 56 -

<I 58

<I 56

<I 59

<I 58 Mean + s.d. 157 t66 a "NS" = no sample;.drains frozen.

"NS = no sample; no flow.

'"NS" = No sample; sample nbt received.

~ocationrecently added.'

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCilL Sample ID U2 F a ~ a d eSubsurface Drain Sump Collection Date Lab Code Tritium (pCilL) MDC (PCW 01-02-09 EW-7544 510 f 98 <I44 11-13-09 EW-6403 831 f 127 <I58 02-1 1-09 EW-490 468 f 9 6 , <I44 11-18-09 EW-6630 54050 f 650 a <I64 03-06-09 EW-869 609 f 109 <I53 11-20-09 EW-6631 51 14 f 221 <I64 04-07-09 EW-1390 533 f 104 < I 59 11-23-09 EW-6632 1218 f 138 <I64 05-05-09 EW-2199 539 f 105 el61 11-25-09 EW-6633 1204 f 138 <I64 06-01-09 EW-3016 541 f 110 <I45 11-27-09 EW-6635 946 f 131 <I58 07-02-09 E\N-3709 473 f 97 <I49 11-30-09 EW-6636 1441 f 146 el58 08-01-09 EW-4370 551 f 9 8 <I45 12-02-09 EW-6637 1017 f 134 <I58 09-02-09 EW-4779 1701 f 1 4 9 <I51 12-04-09 EW-261 1015f120 el55 09-17-09 EW-5092 546 f 101 <I52 12-07-09 EW-263 848 f 114 <I55 09-28-09 EW-6395 421 f 113 <I59 12-09-09 EW-264 787 f 112 <I55 10-05-09 EW-6396 333 f 110 <I59 12-11-09 EW-265 919 f 117 <I55 10-07-09 EW-5923 1070 f 131 <I59 12-14-09 EW-266 1477 f 1 3 5 <I55 10-12-09 EW-6397 6162 f 247 <I59 12-16-09 EW-267 1388 f 133 <I55 10-19-09 EW-6398 853 f 128 <I59 12-18-09 EW-268 5166 f 222 <I55 10-26-09 EW-6399 2704 f 178 < I 58 12-21-09 EW-269 4657 f 212 <I55 11-02-09 EW-6400 2040 f 162 <I58 12-23-09 EW-270 798 f 112 <I58 11-08-09 EW-6495 2638 f 173 <I47 12-25-09 EW-271 3724 f 193 <I55 11-09-09 EW-6401 2125 f 164 <I58 12-28-09 EW-272 1118 f 123 <I55 11-11-09 EW-6402 1473 f 147 <I58 12-30-09 EW-273 875 f 115 <155 Mean + s.d. 2872 f 11354 Msasahoiles Sample ID MH-66D MH-68 Collection Collection Date Lab Code Tritium (pCi1L) MDC Date Lab Code Tritium (pCiIL) MDC (pCilL) ( P C ~

Mean + s.d. 184 f 8 4 Mean + s.d.

Sample ID MH-66B MH-66C Collection Collection Lab Code Tritium (pCi1L) MDC Lab Code -Tritium (pCilL) MDC Date (PCW Date (pCi/L)

Mean -> s.d. 86 f 52 Mean + s.d. 89 f 25

~vln-oon IVI n-o I A Co'lection Lab Code Tritium (pCilL) MGC Collection Lab Code Tritium (pCilL) MGC Date (PCW Date (PC'/'-)

Mean + s.d. Mean + s.d Sample ID MH-67C MH-67D Collection Col'ection Lab Code Tritium (pCilL) MDC Lab Code Tritium (pCi1L) MDC Date (PWL) Date (pcilL) a Tritium recounted with a result of 54,5031-683 pCi1L; reanalyzed with a result of 55,731f655 pCilL.

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections)

Sample ID GW-05 (WH 6 Well) GW-06 (SBCC Well)

Collection Tritium MDC Collection Tritium MDC Date Lab Code (pCi1L) (pCilL) Date Lab Code (pCilL) (PCIIL) 01-19-09 EWW-137 -24 f74 0143 01-19-09 EWW-138 -39 f 73 <I43 04-1 6-09 EWW-1658 42 f 80 0157 04-16-09 EWW-1659 35 f 80 0157 07-02-09 EWW-3364 -40 f 70 0147 07-15-09 EWW-3635 -9 i69 0149 07-1 5-09 EWW-3634 -17 f 69 <I49 10-17-09 EWW-5634 -56 f 81 0159 10-17-09 EWW-5633 -45 f 81 0159 Mean + s.d. -17 f 35 Mean + s.d. -17 f 40 Sample ID GW-09 1Z-361A GW-09 12-36?B Collection Tritium MDC Collection Tritium MDC Date Lab Code (pCilL) ( P C ~ Date Lab Code (pCi1L) (PCVL) 04-14-09 EWW-1990 780 rt 114 < I 59 04-14-09 EWW-1991 165 f 87 0159 06-01-09 EWW-2730 705 f 113 0154 06-01-09 EWW-2731 232 5 93 0154 06-17-09 EWW-3190 633 106+ < I 50 06-17-09 EWW-3191 58 n 82 < I 50 07-08-09 EWW-3435 466 f 99 0147 07-08-09 EWW-3436 32 f 79 0147 08-1 1-09 EWW-4780. 548+114 451 08-1 1-09 EWW-4781 94 2 96 451 09-17-09 EWW-5090 535 k 100 0152 09-17-09 EWW-5091 -50 4 72 0152 10-21-09 EWW-5928 468 2 110 < I 50 10-21-09 EWW-5929 182 f 97 446 11-26-09 EWW-6638 678 122+ < I 58 11-26-09 EWW-6639 201 2 105 e l 58 12-14-09 EWW-6963 474 f 112 0152 12-14-09 EWW-6964 83 k 96 < I 52 Mean + s.d. 587 f 116 Mean + s.d. 111 2 9 1 Sample ID GW-10 2Z-361A GW-10 22-361 B Collection Tritium MDC Collection Tritium MDC Date Lab Code (pCiIL) ( P C ~ Date . Lab Code (pCilL) (PC~/L) 04-14-09 EWW-1992 91 f 84 0159 04-14-09 EWW-1993 91 f 84 el59 06-01-09 EWW-2732 241 f 93 0154 06-01-09 EWW-2734 219f92 0154 06-1 7-09 EWW-3192 -46 f 76 0150 06-17-09 EWW-3193 64 2 82 450 07-08-09 EWW-3437 -42 f 75 e l 47 07-0.8-09 NSa 08-1 1-09 EWW-4782 -16 91+ < I 51 08-1 1-09 NSa 10-21-09 EWW-5930 25 t. 90 e l 46 10-21-09 NSa 11-26-09 EWWI-6640 136 102 e l 58 11-26-09 EWW-6641 66 f 99 0158 12-14-09 EWW-6965 66 f 95 0152 12-14-09 EWW-6966 34294 <I52 I\llean + s.d. 57 f 99 Mean + s.d. 95 f 72 (Annual Collections)

- - Units = pCilL t

Bogs

--r-Sample ID GW-07 (North Bog) GWI-08 EIC Bog Collection Tritium MDC Collection Tritium MDC Date Lab Code (pCilL) (~CVL) Date Lab Code (pCiIL) (pCi/L) 05-28-09 EWW-2620 44 k 86 458 05-28-09 EWW-2621 847 2 120 0158 a "NS" = No sample; unable to open.

--.L.

Midwest Laboratory

/ an Allegheny l'echnologles Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2009 through December, 2009

Interlaboratow Com~arisonProqram 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 progr'am 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 International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples

) are prepared using 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-5 lists 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 Pi-6 were obtained through participation in the Mixed Analyte Performance valuation 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 .t 2 sigma.

Out-of-limit results are explained directly below the result.

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to I 0 0 pcilliter or kg 5.0 pcilliter

> 100 pCi/liter or kg 5% of known value strontium-8gb 5.0 pcilliter 10% of known value strontium-9ob 5.0 pcilliter 10% of known value Potassium-40 5% of known value Gross alpha 5.0 pcilliter 25% of known value Gross beta 5.0 pcilliter 5% of known value Tritium *lo =

169.85 x 10% of known value Radium-226,-228 r 0.1 pcilliter 15% of known value Plutonium 2 0.1 pcilliter, gram, or sample 10% of known value Iodine-?31, 6. pCi/liter lodine-l 2gb 10% of-known value 6 pcilliter 15% of known value 10 pcilliter 10% of known value Other Analyses -- 20% of known value jL a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004, Laboratow limit.

TABLE A-I. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code . Date Analysis Laboratory ERA control

~esult~ ResultC Limits Acceptance STW-1181 Sr-89 Pass STW-1181 Sr-90 Pass STW-1182 Ba-133 Pass STW-1182 Co-60 Pass STW-1182 CS-134 Pass STW-1182 'I Cs-137 Fail STW-1182 21-65 Pass STW-1183 Gr. Alpha Pass STW-I 183 Gr. Beta Pass STW-1184 1-131 Pass STW-1185 Ra-226 Pass STW-I 185 Ra-228 Pass STW-1185 Uranium Pass STW-1186 H-3 Fail STW-1193 Sr-89 Pass STW-I 193 Sr-90 Pass STW-1194 Ba-I33 Pass STW-1194 Co-60 Pass

'8 i STW-1194 Cs-134 Pass STW-1194 CS-137 Pass STW-1194 Zn-65 Pass STW-1195 Gr. Alpha Pass STW-I 195 Gr. Beta Pass STW-I 196 1-131 Pass STW-1197 Ra;226 Pass STW-1197 Ra-228 Pass STW-1197 Uranium Pass STW-I 198 H-3 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

Unless othewise indicated, the laboratory result is given as the mean 4 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.

All gamma -emitters showed a low bias. A large plastic bun found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount In a different beaker, Cs-137, 155.33 t 14.55 pCilL.

Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCilL.

Reanalysis results were acceptable, 19,170 pCilL.

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO,: Dy-Cards).

mR Lab Code Date Known Lab Result Control Description Value -1.2 sigma , Limits Acceptance Environmental. Inc.

40 cm. Pass 50 cm. Pas's 60 cm. Pass 70 cm. Pass 90 cm. Pass 90 cm. Pass I 0 0 cm. Pass 110 cm. Pass 120 cm. Pass 150 cm. Pass Environmental, Inc.

40 cm. Pass 50 cm. Pass 60 cm. Pass.

60 cm. Pass 75 cm. Pass 90 cm. Pass 90 cm. Pass 100 cm. Pass 120 cm. sass 120 cm. Pass 150 cm. Pass 180 cm. Pass 180 cm. Pass

TABLE A-3. In-House "Spike" Samples Concentration (PC~IL)~

Lab Code " Date Analysis Labaratary results Known Control 2s. n=l Activitv Limits Acceptance Ra-226 Pass Gr. Alpha Pass Gr. Beta Pass Ra-228 Pass U-238 Pass Ni-63 Pass C-14 Pass CS-134 Pass CS-137 Pass Sr-90 Pass 1-131 Pass I-131(G) Pass 1-131 Pass I-131(G) Pass CO-60 Pass Cs-134 Pass Cs-137 Pass Sr-90 Pass Cs-134 Pass Cs-137 Pass 1-131(G) Pass 1-131(G) Pass CS-134 Pass Gr. Alpha Pass Gr. Beta Pass Ra-228 Pass U-238 Pass H-3 Pass Ra-226 Pass CS-134 Pass Cs-137 Pass 1-131 Pass 1-131(G) Pass Sr-90 Pass Fe-55 Pass SPW-3448 711412009 Cs-137 171-06 rt 9.21 166.10 149.49 - 182.71 Pass SPW-3497 711512009 Ni-63 179.99 rt 3.06 210.40 147.28 - 273.52 Pass SPW-3499 711512009 Tc-99 +

29.61 0.81 32.34 20.34 - 44.34 Pass SPMi-3582 711712009 Cs-134 32.86 13.72 31.89 21.89 - 41 .89 Pass SPMI-3582 711712009 Cs-I 37 182.49 2 10.54 . 166.10 149.49 - 182.71 Pass SPAP-3595 711712009 Cs-134 13.01 4 3.00 12.75 2.75 - 22.75 Pass SPAP-3595 711712009 Cs-137 110.63 k 6.58 110.73 -

99.66 121.80 Pass 1

TABLE A-3. In-House "Spike" Samples Concentration (PC~IL)~

Lab Code Date Analysis Laboratory results Known Control 2s, n=l Activity LimitsC Acceptance SPF-3597 711712009 Cs-I 34 0.53 k 0.03 0.51 0.31 - 0.71 Pass SPF-3597 711712009 Cs-I 37 . 2.43 k0.05 2.22 1.33 -3.10 Pass SPW-3599 711712009 H-3 63246.00 rt 725.00 62495.00 49996.00 - 74994.00 Pass SPW-12643 81312009 Ra-228 38.1 8 k 2.72 40.54 28.38 - 52,70 Pass W-80709 8/7/2009 Ra-226 16.28 4 0.41 16.77 11.74 - 21.80 Pass W-81009 811012009 Gr. Alpha 20.58 5 0.44 20.08 10.04 - 30.12 Pass W-81009 811012009 Gr. Beta 44.44 1- 0.40 45.60 35.60 - 55.60 Pass W-100109 101112009 Ra-226 Pass W-I 02709 1012712009 Gr. ~ l p h a Pass W-102709 I012712009 Gr. Beta Pass SPW-5964 I012812009 U-238 Pass SPW-I 2647 11i612009 Ra-228 Pass SPAP-6769 1211412009 Gr. Beta Pass SPAP-6774 1211412009 CS-134 Pass SPAP-6774 12/14/2009 CS-137 Pass SPF-6776 1211412009 CS-134 Pass SPF-6776 12/14/2009 CS-137 Pass SPW-6780 12/14/2009 Tc-99 Pass SPMI-6782 ., I211412009 CO-60 Pass SPMI-6782 1211412009 , Cs-134 Pass SPMI-6782 1211412009 CS-137 Pass SPW-6784 1211412009 Co-60 Pass SPW-6784 1211412009 CS-134 Pass SPW-6784 1211412009 CS-137 Pass a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (p~ilm3),and solid samples (pCilg).

Laboratow codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),

CH (charcoal canister), F (fish).

Results are based on single determinations.

d ~ o n t r olimits l are established from the precision values listed in Attachment A of this report, adjusted to t 20.

Control limits based on the laboratory limit, Attachment A ("OtherAnalysesW).

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

TABLE A-4. In-House "Blank" Samples Concentration ( P C ~ I L ) ~

Lab Code Sample Date ~nal~sis~ Laboratory results (4.660) Acceptance Type LLD ActivityG Criteria (4.66 a)

Water Ra-226 Water Ra-228 Water Gr. Alpha Water Gr. Beta Water U-238 Water Ni-63 Water C-14.

Milk Cs-134 Milk Cs-137 Milk 1-131 Milk I-131(G)

Milk Sr-90 Water CO-60 Water Cs-134 Water Cs-137 Water 1-131 Water I-131(G)

Water Sr-90 Air Filter Gr. Beta Air Filter Cs-134 Air Filter Cs-137 Water Ni-63 Fish CS-134 Fish CS-137 Water Gr. Alpha Water Gr. Beta Water Ra-228 Water U-238 Water Ra-226 Milk Sr-90 Milk Cs-134 Milk CS-137 Milk 1-131 Milk 1-131(G)

Water . Ni-63

TABLE A-4. In-House "Blank" Samples Concentration ( P C ~ I L ) ~

Lab Code Sample Date ~nal~sis~ Laboratory results (4,660) Acceptance Type LLD ActivityC Criteria (4.66 0)

Water Ni-63 Water Tc-99 Milk 1-131(G)

Air Filter CS-134 Air Filter Cs-I 37 Fish Co-60 Fish Cs-134 Fish Cs-137 Water H-3 Water Ra-228 Water Ra-226 Water Gr. Alpha Water Gr. Beta Water Ra-226 Water Gr. Alpha Water Gr. Beta Water U-238 Water Ra-228 Air Filter Gr. Beta Air Filter Cs-137 Fish CS-134 Fish CS-137 Water Ni-63 Water Tc-99 Milk CS-134 Milk CS-137 Milk 1-131(G)

Water CS-134 Water. CS-137 Water 1-131(G)

" Liquid sample results are reported in pCi/Liter, air filters( pcilfilter), charcoal (pCi1charcoal canister), and solid samples (pcilkg).

1-131(G); iodine-?31 as analyzed by gamma spectroscopy.

Activity reporfed is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)=

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Be-7 0.063 1 0.012 0.065 f 0.01 0 0.064 f 0.008 Pass K-40 1.34 f 0.21 1.13 f 0.13 1.24 rt 0.12 Pass Be-7 . 0.34 rt 0.12 0.39 f 0.08 0.37 f 0.07 Pass Gr. Beta 4.34 f 0.1 1 4.38 f 0.12 4.36 f 0.08 Pass K-40 3.16 f 0.26 3.00 rt 0.16 3.08 f 0.15 Pass Ra-226 2.97 f 0.22 2.76 f 0.21 2.87 rt 0.15 Pass Ra-228 3.13 C 0.71 3.55 f 0.81 3.34 f 0.54 Pass Gr. Alpha 101.90 -C 6.50 101.70 f 6.10 101.80 f 4.46 Pass Gr. Beta 97.80 f 3.50 94.00 f 3.20 95.90 f 2.37 Pass Gr. Beta 1.43 f 0.58 1.41 f 0.54 1.42 f 0.40 Pass Gr. Beta 2.09 f 0.58 2.33 C 0.63 2.21 f 0.43 Pass Gr. Beta 1.51 f 0.56 1.61 f 0.57 1.56 rt 0.40 Pass Gr, Beta 2.72 f 0.65 3.06 f 0.69 2.89 f 0.47 Pass Gr. Beta ' 2.66 f 0.68 2.1 6 C 0.67 2.41 f 0.48 Pass Beta-K40 3.90 f 2.30 1.70 f 2.50 2.80 rt 1.70 Pass H-3 597.00 f 292.00 507.00 rt 288.00 +

552.00 205.07 Pass Ra-226 8.20 f 0.20 8.30 f 0.20 8.25 f 0.14 Pass K-40 1286.50 f 111.60 1471.70 rt 111.50 1379.10 f 78.88 Pass Sr-90 0.67 rt 0.31 0.36 f 0.36 +

0.52 0.24 Pass Gr. Beta 13.59 f 2.32 17.33 f 2.69 15.46 f 1.78 Pass H-3 7143.00 f 262.00 7262.00 f 264.00 ' 7202.50 f 185.97 Pass Be-7 0.076 f 0.012 0.075 f 0.014 0.076 f 0.009 Pass Gr. Beta 1.40 f 0.55 1.86 f 0.62 1.63 f 0.41 Pass WW-I 102,1103 Gr. Beta Pass XWW-1174,1175 H-3 Pass AP-1462,1463 Be-7 Pass SL-2024, 2025 Be-7 Pass SL-2024, 2025 Gr. Beta Pass SL-2024, 2025 K-40 Pass SO-2045,2046 Gr. Alpha Pass SO-2045,2046 Gr. Beta Pass SO-2045,2046 Sr-90 Pass mi-2251,2252 K-40 Pass mi-2381,2382 K-40 Pass SWT-2534,2535 Gr. Beta Pass G-2626,2627 Gr. Beta Pass G-2626,2627 K-40 Pass WW-2732,2733 H-3 Pass

TABLE A-5. In-House "Duplicate" Samples Concentration (pCilL)=

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Be-7 Pass Gr.Beta Pass K-40 Pass Be-7 Pass Ra-226 Pass Ra-228 Pass Gr.Alpha Pass K-40 Pass Ra-226 Pass Ra-228 Pass K-40 Pass Be-7 Pass Gr. Beta Pass K-40 Pass Be-7 Pass CS-137 Pass K-40 Pass Ac-228 Pass Pb-214 Pass K-40 Pass Be-7 Pass K-40 Pass Be-7 Pass K-40 Pass

TABLE A-5. In-House "Duplicate" Samples Concentration ( P C ~ I L ) ~

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Gr. Beta Pass K-40 Pass Be-7 Pass Gr. Alpha Pass K-40 Pass H-3 pass K-40 Pass Ra-226 Pass Ra-228 Pass Ra-226 Pass

~a-228 Pass Ra-226 Pass Ra-228 Pass Ac-228 Pass Pb-214 Pass Gr. Alpha Pass Gr. Beta Pass K-40 . Pass Gr. Beta Pass Sr-90 Pass H-3 Pass H-3 Pass Gr. Beta Pass Ra-226 Pass Ra-228 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCilL, except for air filters (pCilFilter), food products, vegetation, soil, sediment (pcilg).

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration '

Kiiown Control Lab Code Date Analysis Laboratory result Activity Limits Acceptance STW-1170 ' Fail STW-I 170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-I 170 Pass STW-1170 Pass STW-1170 Pass STW-1170 Pass STW-1.170 Pass STW-1170 Pass STW-1170 Pass STW-1171 01/01/09 Gr. Alpha 0.56 k 0.06 ' 0.64 0.00 - 1.27 Pass STW-1171 01/01/09 Gr. Beta 1.29 rt 0.05 1.27 0.64 - 1.91 Pass STSO-1172 Pass STSO-1 172 Pass STSO-1 172 Pass STSO-I 172 Pass STSO-1 172 Pass STSO-1 172 Pass STSO-1 172 Pass STSO-1172 Pass STSO-1 172 Pass STSO-1 172 Pass STSO-1 172 Pass STVE-1173 01/01/09 Co-57 2.75 k 0.1 1 2.36 1.65 - 3.07 Pass STVE-1173 01/01/09 CP-60 0.06 k 0.09 0.00 0.00 - 1.OO Pass STVE-1173 01101109 Cs-I 34 3.49 0.22 3.40 2.38 - 4.42 Pass STVE-1173 01101109 Cs-137 1.01 5 0.1 I 0.93 0.65 - 1.21 Pass STVE-1173 01/01/09 Mn-54 2.52 k 0.14 2.30 1.61 - 2.99 Pass STVE-1173 01101109 Zn-65 1.52 2 0.18 1.35 0.95 - 1.76 Pass

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration Known Control Lab Code Date Analysis Laboratory result Activity Limits Acceptance Fail Pass Pass Pass Pass Pass Fail Pass Gr. Alpha Pass Gr. Beta Pass STSO-1 188 Pass STSO-1 188 Pass STSO-I 188 Pass STSO-I 188 Pass, STSO-1 188 Pass STSO-1 188 Pass STSO-I 188 Pass STSO-1 188 Pass STSO-1 188 ' Fail STSO-1 188 Pass STSO-I 188 Pass STSO-1 188 Pass Gr. Alpha Pass Gr. Beta Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STAP-1190 Pass STVE-1190 Pass S N E - I 190 Pass SNE-1190 Pass STVE-I 190 Pass STVE-1190 Pass STVE-1190 Pass

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration '

Known Control Lab Code Date Analysis Laboratory result Activity Limits Acceptance STW-1191 07/01/09 Gr. Alpha 0.88 f 0.07 1.05 -

0.00 2.09 Pass STW-1191 07/01/09 Gr. Beta 7.29 5 0.10 7.53 3.77 - 11.30 Pass STW-1192 -

0.73 1.35 Pass STW-1192 25.60 - 47.60 Pass STW-I 192 -

10.80 20.00 Pass STW-1192 22.50 - 41.90 Pass STW-1192 28.80 - 53.60 Pass STW-1192 42.60 - 79.00 Pass STW-1192 443.90 - 824.30 Pass STW-1192 0.00 - 1.OO Pass STW-1192 30.90 - 57.50 Pass STW-1192 -

0.00 0.05 Pass STW-I 192 -

1.15 2.13 Pass STW-I 192 -

9.09 16.89 Pass STW-1192 -

7.00 13.00 Pass STW-1192 -

7.00 13.00 Pass STW-1192 2.07 - 3.85 Pass STW-1192 2.12 - 3.94 Pass STW-1192 18.80 - 35.00 Pass a Results obtained by Environmental, Inc.. Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, ldaho Operations office, ldaho Falls, ldaho Results are reported in units of Bqlkg (soil), BqlL (water) or Bqltotal sample (filters, vegetation).

Laboratory codes as follows: STW (water), STAP (air filter), STSO (soii), STVE (vegetation).

MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) ,

and control limits as defined by the MAPEP.

Included in the testing series as a "false positive".

'No errors were found in procedure or calculation. There was not enough sample for a reanalysis. Americium-241 in water was included in the ERA studies (Tbl. A-7) and also in the second round of MAPEP testing. Both analysis results were acceptable.

One determination was eliminated from the average, due to poor recovery. Average of three determinations. 0.25 t 0.03 pcilfilter.

No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 rt 0.12 Bqlfilter.

' Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 t 28.6 Bqlkg.

TABLE A-7. interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance STAP-1176 03123109 Am-241 47.20 f 3.10 . 55.4 32.4 - 76.0 Pass STAP-1176 03/23/09 Go-60 543.60 C 8.90 490.0 379.0 - 612.0 Pass STAP-1176 03/23/09 Cs-134 941.30 C 30.70 865.0 563.0 - 1070.0 Pass STAP-1176 03/23/09 Cs-I 37 . 850.60 C 19.40 724.0 544.0 - 951.O Pass STAP-1176 Mn-54 Pass STAP-1176 Pu-238 Pass STAP-1176 Pu-239140 Pass STAP-1176 Sr-90 Pass STAP-1176 U-23314 Pass

.STAP-1176 U-238 Pass STAP-I 176 Uranium Pass STAP-1176 Zn-65 Pass STAP-1177 03/23/09 Gr. Alpha 76.30 C 3.47 63.8 33.1 - 96.0 Pass STAP-I 177 03/23/09 Gr. Beta 98.50 C 3.04 80.7 ' 49.7 - 118.0 Pass STSO-1 178 Ac-228 . Pass STSO-1 178 Am-241 Pass STSO-I 178 Bi-212 Pass STSO-1 178 Bi-214 Pass STSO-1 178 CO-60 Pass .

STSO-1 178 CS-134 Pass STSO-I 178 Cs-137 Pass STSO-1 178 K-40 Pass STSO-1 178 Mn-54 Pass STSO-1 178 Pb-212 Pass STSO-1 178 Pb-214 Pass STSO-1 178 Pu-238 Pass STSO-1 178 Pu-239140 Pass STSO-I 178 Sr-90 Pass STSO-1178 U-23314 Pass STSO-1178 Uranium Pass STSO-1 178 Zn-65 Pass

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCilL)

Lab Code Date Analysis Laboratory . ERA Control

. Result Result Limits Acceptance STVE-1179 Am-241 Pass STVE-1179 Cm-244 Pass STVE-1179 Co-60 Pass STVE-1179 C s - I 34 Pass STVE-1179 Cs-137 Pass STVE-1179 K-40 Pass STVE-I 179 Mn-54 Pass STVE-1179 Sr-90 Pass STVE-1179 U-23314 Pass STVE-1179 U-238 Pass STVE-1179 Uranium Pass STVE-1179 21-1-65 Pass STW-1180 Am-242 Pass STW-1180 CO-60 Pass STW-1180 Cs-134 . . Pass STW-1180 Cs-137 Pass STW-1 180 Fe-55 Pass STW-1180 Mn-54 Pass S T W - I 180 Pu-238 Pass STW-1180 Pu-239140 Pass STW-1180 Sr-90 Pass STW-1180 U-23314 . Pass STW~l180 U-238 Pass STW-1180 Uranium Pass STW-1180 21-1-65 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

Laboratory codes as follows: STW (water); STAP (air filter), STSO (soil), STVE (vegetation).

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.

lncluded in the testing series as a "false positive". No activity expected.

The analysis was repeated by leaching and total dissolution methods. Total dissolution yielded results within expected range.

Results of the reanalysis: U-233,4, 1655 t 95 pCi/kg. U-238 1805 t 97 pCl/kg.

APPENDIX B DATA REPORTING CONVENTIONS

Data Reportinq 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. Sinale Measurements Each single measurement is reported as follows: xss where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: cL, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

3.0. Duplicate analvses 3.1 Individual results: For two analysis results;.xq s sq and x2 s s2 Reported result: x k s; where x = (112) (xq 1. x2) and s = (112) d s : + s:

3.2, Individual results: <Ll , 4-2 Reported result: <L, where L = lower of LI and L2 3.3. Individual results: x C s, <L Reported result: x S s if x I L ; <L otherwise.

4.0. zComoutationof Averaaes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x.1, x2 . . . are defined as follows:

4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the bllowing 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 number s are kept unchanged. As an example, 11,443 is rounded off to 21.44.

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.

POINT BEACH bIUCLEAR PLANT APPENDIX 6 SaMpling Piograrn and Locations

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)a (and ~ r e ~ u e n c y ) ~ (and ~ r e q u e n c y ) ~

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 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 8 E-1-4, 6, 9, 20 3x I year GB, GS as available Shoreline Silt 5 E-1, 5, 6, 12, 33 2x I year GB, GS Soil 8 E-1-4, 6, 8,9, 20 2x 1 year GB, GS Milk 3 E-I 1,40, 21 Monthly GS, 1-131, Sr-89-90 Algae 3x 1 year GB, GS as available Fish 1 E-13 2x 1 year GB, GS (in edible portions) as available SPECIAL COLLECTIONS AND ANALYSES Airborne Filters 4 per month Sr-89, Sr-90 1 per quarter Sr-89, Sr-90 (comp.)

Liquid 1 per month GA, Sr-89, Sr-90 Subsoil Water 4 per quarter GA, GB, H-3, GS Miscellaneous Water Samples 4-5 per year Sr-89, Sr-90 a Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.

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.

POINT BEACH NUCLEAR PLANT APPELIDIX D Graphs of Data Trends D-I

POINT BEACH Air Particulates - Gross Beta Location E-1, monthly averages 2005-2009 0.000 I : i i i : i i i i l i l : i l ~ ~ i I : I i ~ I ~ : i i ~ i : : : : : : i : i : i i i i i i : ~ ~ ~ i i ~ i ~ i ~ ~ i i 2005 2006 2007 2008 2009 Year 0.050 Location E-2, monthly averages 2005-2009 1

POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2005-2009 0.050 1 2005 2006 2007 2008 2009 Year 0.050 Location E-4, monthly averages 2005-2009 1

2006 2007 2008 2009 Year

POINT BEACH Air Particulates - Gross Beta 0.050 Location E-8, monthly averages 2005-2009 I

o.ooo-I:::ii::::::I:::::::::::I.:::::::::::t:::::I:I::::::::E:::

2005 2006 2007 2008 2009 Year Location E-20, monthly averages 2005-2009 0.050 1 0.000 I : : : : : : : : ~ : : l ~ ~ ~ : i : : : : : : ~ l l : i i : i i : : : : : ~ i : : : ~ ~ : ~ ~ : ~ : : : ~ ~ ~ : : : : l 2005 2006 2007 2008 2009 Year

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses

POINT BEACH NUCLEAR PLANT Supplemental Analyses Location U2FSSD U2FSSD U2FSSD collection' Date 10-12-09 10-26-09 10-26-09 Lab Code ELW- 6397 MDC ELW- 6399 MDC ELW- 6630 MDC Be-7 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-134 Cs-I 37 Ba-La-140 Other Gammas" a RU-103 LLDs not reached due to small sample size; only 200 mL available for analysis.

APPENDIX F DUPLICATE ANALYSES

F-1. Airborne particulate filters, duplicate analyses for gross beta.

Units: p ~ i l m "

Collection: Continuous, weekly exchange.

Date Volume Location Collected (m3) Gross Beta NOTE: Page F-3 is intentionally left out.

F-4. Milk, duplicate analyses for 1-131, Sr-89/90 and gamma isotopic.

Units; pCilL Collection: Monthly Location E-21 E-21 E-1 I Lab Code EMI- 3388 EMI- 4680 EMI- 5523 Date Collected 07-08-09 09-09-09 10-14-09

F-5. Surface WaterjWell Water, duplicate analyses for tritium.

Units: pCi/L Collections: Monthly, quarterly, quarterly composites Location GW-01 GW-14 GW-03 Collection Date 03-26-09 03-30-09 04-29-09 Lab Code EWVV-1016 EWW-1169 EWW-2004 Location GW-13 GW-1 I GW-10 2Z-361A Collection Date 04-16-09 05-26-09 06-01-09 Lab Code EWW-1663 EWW-2556 EWW-2733 Location GW-13 GW-10 2Z-361A GW-13 Collection Date 06-17-09 07-08-09 07-30-09 Lab Code EWW-3027 EWW-3438 EWW-4057 H-3 90 i: 83 1 i: 77 32 i: 72 Location GW-16 S-l MH-68 Collection Date 09-16-09 09-10-09 09-16-09 Lab Code EWW-5099 ESW-4743 ESW-5078 Location MH-66B U2FSSD GW-13 Collection Date 10-29-09 11-08-09 11-21-09 Lab Code EWW-6159 EWW-6496 EWW-6475 H-3 129 i: 84 2451 rt 168 141 rt 95 Location U2FSSD U2FSSD Collection Date 11-25-09 12-04-09 Lab Code EWW-6634 EWW-262

F.6 Sedimentlsoil, duplicate analyses for gross beta and gamma isotopic Units: pCi/g dry Collection: Semiannual .

Location E-08 Collection Date 10/29/2008 Lab Code ESO- 6054 Gross Beta 30.19 rt 2.95 F.7 Grass, duplicate analyses for gross beta and gamma isotopic Units: pCi/g dry Collection: Semiannual Location E-04 Collection Date 5/28/2009 Lab Code EG- 2627 Ratio (wet/dnj) 9.39 Gross Beta 6.48 k 0.19

F.8 Slime, duplicate analyses for gross beta and gamma isotopic Units: pCilg wet Collection: Semiannual Collection Date 08-06-09 10-07-09 Lab Code ESL- 4165 ESL- 5405 Location E-12 E-12 Ratio (wetldry) 3.58 Gross Beta F.9 Air particulates, duplicate analysis for quarterly emitting isotopes.

Collection Period 4th quarter Lab Code EAP- 71 67 Location E-03

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," Midwest Laboratow 700 Landwehr Road Noithbrnok, 1L PI!. (847) 564.0700. fax (847) 564-4 Dr. Kjeil Johansen LABORATORY REPORT NO.: 8006-100 -890 Point Beach Nuclear Plant DATE: 11-19-09 6610 Nuclear Road SAMPLES RECEIVED: 10-12-09 Two Rivers, Wisconsin 54241 Analyses for tritium, strontium-90 and gamma emitting isotopes.

Lab Code Date Collected Location Isotope Concentration (pCilL) MDA Concentration ( P C ~ I L ) ~ MDAa H-3 85 rt 91 < 144

" 2 liters of sample were filtered and suspended solids were gamma scanned as per your request.

The error given is the probable counting error at the 95% confidence level.

Less than (<), value is based on a 4.66 sigma counting error for the background sample.

-- Quality Assurance

700 Landwehr Road NorthbrooL, 11 60062-2310

. 564-0700 fax 1847) 564-4517

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Dr. Kjell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-100-885 Point Beach Nuclear Plant DATE: 09-28-2009 6610 Nuclear Road SAMPLES RECEIVED: 09-25-2009 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:

Below are the results of the analyses for tritium in five AC Condensate samples.

Sample Collection Lab Concentration I MDA (DCVL)

Description Date Code H-3 . .

OPS Office 09-08-09 EXW-5083 U2 Control Room 09-08-09 EXW-5084 North Service Bldg 09-08-09 EXW-5085 South Service Bldg 09-10-09 EXW-5086 TB 09-10-09 EXW-5087 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: k i e l l . i o h a n s e n @ ~ e x t ~ ~ ~ ~ n e r a ~ . c o m APPROVED BY: 7 - 9 . a-b'Tonv Coorlim.

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Dr. Kjell Johansen LABORATORY REPORT NO.: 8006-100 -905 Point Beach Nuclear Plant DATE: 12-10-09 6610 Nuclear Road SAMPLES RECEIVED: 12-04-09 Two Rivers, Wisconsin 54241 Well Water, analyses for gamma emitting isotopes.

Lab Code EXWW- 6643 EXWW- 6644 Collection Date 10-02-09 10-02-09 '

Location U2, Tendon Gallery U1, Tendon Gallery isotope - Activity IMDC (pCilL) Activity IMDC (pCilL)

For those isotopes where both an activity and an MDC value are given, the MDC value should be considered as the reportable value (based on a 4.66 sigma counting error for the background sample) and the activity is presented for information only. For isotopes where an activity is given, but no MDC value, the activity is considered the reportable value and the error given is the probable counting error at the 95% confidence level.

Approved:

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7W Lardweh Rmd NwULmk, U SW61.UIO I (647)56467W tar (647) 5fd4517 Mr. Richard Farrell LABORATORY REPORT NO.: 8006-100-861 Radiation Protection Mgr. DATE: 4/24/2009 Point Beach Nuclear Plant SAMPLES RECEIVED: 4110/2009 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, W I 54241

Dear Mr. Farrell:

Below are the results of the readout of supplemental TLDs deployed during the first quarter, 2009.

Period: ' 1st Quarter, 2009 Date Annealed: 12/02/08 Date Placed: 0 1109/09 Date Removed: 04/07/09 Date Read: 04/20/09 Days in the Field: 88 Days from Annealing to Readout: 139 In-transit exposure: +

7.88 0.73 Net m R Location Total mR Net mR per 7 days SGSF-North SGSF-East SGSF-South SGSF-West ISFSI-North ISFSI-East IS,FSI-South ISFSI-West Control SA Coorlim, Quality Assurance cc: K. Johansen

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6610 Nuclear Road Two Rivers, WI 54241

Dear Mr. Farrell:

Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2009.

Period: 2nd Quarter, 2009 Date Annealed: 03111109 Date Placed: 04/07/09 Date Removed: 07/02/09 Date Read: 07/08/09 Days in the Field: 86 Days from Annealing to Readout: 119 In-transit exposure: +

4.39 0.39 Net rnR Location Total mR NetmR , per 7 days Control

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I@ a 1W LanlvRtrRmd Ncrtttxmk, n W2.2310 n7)564.07W fax (M7) 564-1517 Mr. Richard Farrell LABORATORY REPORT NO.: 8006-100-897 Radiation Protection Mgr. DATE: 11I212009 Point Beach Nuclear Plant SAMPLES RECEIVED: 1011212009 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241

Dear Mr. Farrell:

elo ow are the results of the readout of supplemental TLDs deployed during the third quarter, 2009.

Period: 3rd Quarter, 2009 Date Annealed: 06117109 Date Placed: 07/02/09 Date Removed: 10107/09 Date Read: 10114/09 Days in the Field: 97:

Days from Annealing to Readout: 119 In-transit exposure: 3.03'+ 0.22 Net mR Location Total mR Net mR per 7 days Control i

SA Coorlirn, Quality Assurance APPROVED cc: K. Johansen

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7W Lardwdr Rmd IluiHmk~11 WZ.2310 ph (847) 5M.07M. fax (847) 5644217 Mr. Richard Farrell LABORATORY REPORT NO.: 8006-100-909 Radiation Protection Mgr. DATE: 1/21/2010 Point Beach Nuclear Plant SAMPLES RECEIVED: 1111/2010 .

NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road I

Two Rivers, WI 54241

Dear Mr. Farrell:

Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2009.

Period: 4th Quarter, 2009 Date Annealed: 09113109 Date Placed: 10107/09 Date Removed: 0 1107/10 Date Read: 01/13110 Days in the Field: 92 Days from Annealing to Readout: 122 In-transit exposure: +

4.07 0.36 Net rnR Location Total mR Net rnR per 7 days Control

/ SA Coorlim, Quality Assurance cc: K. Johansen

APPENDIX 2 University of Waterloo (Ontario)

Environmental Isotope Laboratory Precipitation Monitoring Results for the Point Beach Nuclear Plant Reporting Period: January - December 2009

Client: Johansen lSO# 2009072 - Environmental Isotope Lab FPL Energy Point Beach Nuclear Plant' Location: T- 31191201O 3 for 3H 1 of I Contract #I 5872

Sample Lab# 3~ Result t ID Repeat t l o c,I ;/A 1 E-02 (SBCC Rain Water) 02/04/09 2 E-03 (Tapawingo Rd West of Lakeshore Rd) 3 E-04 (North Boundary) 02/04/09 201886 X 02/04/09 201887 ,X 201888 X 29.6 40.0 28.9 8.0 8.0 8.0 9,g.=S$F~diu!

, Zp$h q . 3 6 7 C0 /

Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

1TU = 0.1 1919 Becquerels/L ~ e IA'EA, r 2000 Report.

Robert 9. Drirnrnie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 5198884732 519 888 4567 ext 32580

Client: Johansen /SO# 2009136 Environmental Isotope Lab FPL Energy Location: T - 8 311 912010 Point Beach Nuclear Plant 3 for 3H 1 of1 Contract if25473 NPL 2009-0053

Sample I~ab# ( I

'H ~ e s u l tkl lo1 ~ e ~ e ai- tl o/ ]

1 E-02 (SBCC Rain Water) 03/04/09 204063 X 15.4 8.0 y9.CaZ 25.r!

--To*% 425.v 2 E-03 (Tapawingo Rd West of Lakeshore Rd) 03/04/09 3 E-04 (North Boundary) 03/04/09 204064 X 204065 X 22.0 8.0 15.4 8.0 13.9 8.0 Y S . ~ 25'g '~

Tritium is reported in Tritium Units.

1TU = 3.221 Picocurries/L per: IAEA, 2000 Report.

1TU = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

Robert J. Drimrnie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 51 9 888 4732 519 888 4567 ext 32580

Client: Johansen /SO# 2009234 Environmental Isotope Lab FPL Engergy Point Point Nuclear Plant Location: T - 9 311912010 Contract # 25473 3 for 3H 1 of 1 NPL 2009-0096

Sample Lab#

3 H Result rt 16 Repeat rt Ia 1 E-02 (SBCC Rain Water) 04/08/09 208012 X 16.5 8.0 2 E-03 (Tapawingo Rd West of Lakeshore Rd) 04/08/09 208013 X 41.5 8.0 3 E-04 (North Boundary) 04/08/09 20'8014 X 16.1 8.0 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurriesIL per IAEA, 2000 Report.

1TU = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

Robert J. Drimmie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 5198884732 519.888 4567 ext 32580

Client: Johansen ISO# 200931 0 Environniental Isotope Lab NextEra Energy Point Beach Location: T - 1 3119/20?0 Contract #25473 3 for 3H 1 of I NPL 2009-0140 '

Sample Lab# /

'H Result t l o Repeat f l o 1 E-02 05/06/09 210024 X 31.1 8.0 1-litre bottle 2 E-03 05/06/09 210025 X 17.0 8.0 I-litre bottle 3 E-04 05/06/09 210026 X 12.0 8.0 1-litre bottle Tritium is reported in Tritium Units.

1TU = 3.221 Picocurries/L per IAEA, 2000 Report.

1TU = 0.11919 Becquerels/L per IAEA, 2000 deport.

Robert J. Drirnrnie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 519 888 4732 . 519 888 4567 ext 32580

C1ient:Johansen ISO# 2009398 Environmental Isotope Lab FPL Energy Point Beach Location: T - 9 311912010 Contract#: 25473 3 for 3H. 1 of1 NPL 2009-0173 1 E-02 (SBCC Rain Water) 06/11/09 1155 212018 X 23.5 8.0 125ml bottle 7 g 4 ~5-01~

2 E-03 (Tapawingo Rd West of Lalteshore Rd) 06111/09 1145 212019 X 3 E-04 (North Boundary) 06110109 1050 212020 X 18.4 16.2 8.0 8.0 13.4 125ml bottle 8.0 125rnl bottle S2. ly ' '

9.n92s-a Tritium is reported in Tritium Units.

1TU = 3.221 PicocurrieslL per IAE'A, 2000 Report.

1TU = 0.1 1919 BecquerelsIL per IAEA, 2000.Report.

Robert J. Drimrnie uwElLAB Manager rdrimmie@uwaterloo.ca 519 888 4567 ext 32580

Client: J o h a n s e n !SO# 2009444 Environmental Isotope Lab FPL Energy Point Beach Location: T-9 '311912010 Contract #: 25473 3 for 3H 1 of 1 NPL 2009-0205

Sample I

Tritium is reported in Tritium Units.

1TU = 3.221 PicocurrieslL p e r IAEA, 2000 Report.

I T U = 0.1 1919 BecquerelsIL' p e r IAEA, 2000 Report.

Robert J. Drimmie uwElLAB M a n a g e r T o Contact uwEILAB: rdrimmie@uwaterloo.ca 5198884732 519 888 4567 e x t 32580

Client:' Johansen ]SO# 20094.88 Environmental Isotope Lab FPL Energy Point Beach Location: T- 311 912010 Contract #: 25473 3 for 3H 1of1 NPL 2009-0238

Sample Lab# 3 H Result + 10 Repeat + Icr pH Conductivity pS/crn 1 E-02 8--5-09 0915 21471 8 X 23.0 8.0 2-E-03 8--5-09 0935 214719 X 12.8 8.0 3 E-04 8--5-09 0955 214720 X 12.8 8.0 10.9 8.0

~ritiumis reported in Tritium Units.

ITU = 3.221 PicocurrieslL pei IAEA, 2000 Report.

1TU = 0.11919 BecquerelslL per IAEA, 2000 Report.

Robert J. Drimmie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 51 9 888 4732 519 888 4567 ext 32580

Client: Johansen ISO# 2009537 Environmental Isotope Lab FPL Energy Point Beach Nuclear Plant Location: T- 311912010 Contract: 25473 3 for 3H 1of1

Sample Lab# 3~ Result +l o Repeat +l o 1 E-02 216028 X 9.0 8.0 2 E-03 216029 X 18.3 8.0 3 E-04 216030 X 21.8 8.0 23.1 8.0 Tritium is reported in Tritium Units.

1TU = 3.221 PicocurrieslL per IAEA, 2000 Report.

1TU = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

Robert J. Drimmie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.ca 5198884732 519 888 4567 ext 32580

Client: Johansen ISO# 2009633 Environmental Isotope Lab FPLE Point Beach I\luclear Plant Location: T - 311912010 Contract #: 25473 3for 3H 1 of 1 NPL 2009-0310

Sample Lab# 3~ Result rt 10 Repeat + 10 Oct. 7, 2009 I E-02 10/07109 219847 X 9.5 8.0 2 E-03 10107109 219848 X , 14.6 8.0 3 E-04 10/07/09 ' 1219849 X 18.9 8.0 20.9 8.0 Tritium is reported in Tritium Units.

I T U = 3.221 PicocurriesIL per IAEA, 2000 Report.

ITU = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

Robert J.. Drimmie uwElLAB Manager To Contact uwEILAB: rdrimmie@uwaterloo.c~

519 888 4732 519 888 4567 ext 32580

Client: Johansen ISO# 2009703 Environmental Isotope Lab FPLE Point Beach l\luclear Plant Location: T - 311 912010 Contract#: 25473 3 for 3H ?of1 NPL 2009-0350

Sample Lab# 3~ Result +lo Repeat +lo Conductivity November 3,2009 1 E-02 11-03-09 221884 X 18.8 8.0 ,~6225g 2 E-03 11-03-09 221885 X 14.1 8.0 u5.42a I' 3 E-04 11-03-09 .r25.2 221886 X 17.9 8.0 22.0 8.057.Y Tritium is reported in Tritium Units.

ITW = 3.221 PicocurriesIL per IAEA, 2000 Report.

1TU = 0.1 1919 BecquerelslL per IAEA, 2000 Report.

Rick Hkemskerk uwEILAB Manager To Contact uwEILAB: rkhmskrk@uwaterloo.ca 519 888 4732 . 51 9 888 4567 ext 35838

Client: Johansen ISO# 2009792 Environmental Isotope Lab FPLE Point Beach Nuclear Plant Location: T- 3119/2010 Contract#: 25473 3 for 3H 1 of I NPL 2009-0393 3

Sample Lab# H Result t 10 Repeat t l o December 9,2009 & 25f8 1 E-02 . 72/09/09 224345 X ~ 6 . 0.8.0 ,

4 19.7, y' $

2 E-03 12/09/09 224346 X 9.4 8.0 3).3?

3 E-04 12/09/09

' 224347 X 9.7 . 8.0 8.0 8.0 Tritium is reported in Tritium Units.

I T U = 3.221 PicocurrieslL per IAEA, 2000 Report.

I T U =.0.11919 BecquerelsLL per IAEA, 2000 Report.

Rick Heemskerk uwElLAB Manager To Contact uwEILAB: rkhmskrk@uwaterloo.ca 5198884732 519 888 4567 ext 35838

Client: Johansen ISO# 2010030 Environmental Isotope Lab FPLE Point Beach Nuclear Plant Location: T - 311912010 Contract #: 25473 3 for 3H 1 of '1 IqPL 2010-0007

Sample Lab# 3~ Result +la Repeat +la January 7,2009 1 E-02 01/07/10 226695 X 17.1 8.0 2 E-03 01/07/10 226696 X 42.7 8.0 3 E-04 01/07/10 226697 X 12.8 8.0 13.0 8.0 Tritium is reported in Tritium Units'.

1TU = 3.221 PicocurrieslL per IAEA, 2000 Report.

1TU = 0.1 1919 BecquerelsIL per IAEA, 2000 Report.

Rick Heemskerk UWEILAB'Manager To Contact uwEILAB: rkhmskrk@uwaterloo.ca 519 888 4732 519 888 4567 ext 35838

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2009 ANNUAL MONITORING REPORT ENVIRONMENTAL MANUAL REVISION 21 MAY 9, 2009 36 pages follow

EM IRO ENTAL M AL DOCUMENT TYPE: Controlled Reference CLASSIFICATION: N/A REWSION: 21 EPPE.CTIVE DATE: May 1,2009 REVIEWER: Plant operation's Review Committee (PORC) . .

APPROVAL AUTHORITY: PORC Chair .

PROCEDURE OWNER (title): Group Head OWNER GROUP: Chemistry

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1. 2009 I TABLE OP CONTENTS SECTION TITLE PAGE 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORDIG PROGRAM ADMINISTRATION ............................................................................... 5 a 1.1 ~efinitionand Basis ........................... . ..................................................................... 5 1.1.1 Defmtion ...............;........ . .....................................................................5 I 1.1.2 Basis ..................................................................................................5 1.2 Responsibilities for Program Implementation ........................................................ ...6 1.2.1 .Chemistry Functions.....................................................................................6 a . Program scope .................................................................................6

.b . Record keeping ................................................................................ 6

c. Data momtomg ............................................................................ 7 d . Data summary .................................. .. . . . ..........................7 e . Contractor communications ........................................................... 7

f. Reportable items...............................................................................

. . 8

'1.2.2 Non-Chemistry Functions .................................................. .....................9

a. Manual c.0ntrol and distribution ........................................................ 9 b.

Program coordmation...................................................................9 1.3 Quality Assurance/Quality Control .................. . . . . ..... 10 1.4 Program Revisions ...................................................................................................... 11 Page 2 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1. 2009 ENVIRONMENTAL ~\~LANuAL TABLE OF CONTENTS SECTION TITLE PAGE 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ..........................................11 2.1 Program Overview ......................................................................................................... 11 2.1.1 Purpose ............................................... ......................... ............................... 11 2.1.2 Samples......................................................................................................... 11 2.1.3 Momtomg sensitivity................................................................................... 11 2.2 Program Parameters ...................................................................................................... 12 Contamination avoidance .............................................................................12 Sample size ...................................................................................................12 Lower limit of detection ...................................................... . ................... 13 Notification levels ......................................................................................... 14 Sampling locations........................................................................................ 15 Sampling media and fieq~~ency .................................................................... 15 Sample labeling ............................................................................................ 16 Sample shppmg ............................................................................................ 16 Sample analyses and frequency .................................................................... 17 Analytical laboratory .................................................................................... 17 Assistance to the State of Wisconsin............................................................................. 17 2.4 Specification of Sampling Proced~lres..........................................................................18 Vegetation................................................................................................... 18 Therrnol~lminescentdosimeters (TLDs) ...................................................... 18 Lake water .................................................................................................. 19 Well water ..................................................................................................... 19 Air .................................................................................................................19 Milk...............................................................................................................23 Algae ............................................................................................................. 24 Fish .............................................................................................................25 Soil ................................................................................................................ 25 Shoreline Sediment ......................................................................................2 6 2.5 Milk Survey ..................................................................................................................2 6 Page 3 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL TABLE OF CONTENTS SECTION TITLE PAGE TABLE 2-1 RECOMMENDED MINIMUM SAMPLE SIZES ..................................................27 .

TABLE 2-2 SAMPLE TYPES AND ASSOCIATED L O W R LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES ............................. 25 TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ..................... 30 TABLE 2-4 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS FREQUENCY ............................................................................32 TABLE 2-5 SAMPLES COLLECTED FOR STATE OF WISCONSIN ......................................33 FIGURE 2-la RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS .....................34 FIGURE 2-lb RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ..................... 35 FIGURE 2-lc RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS .....................36 Page 4 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL, MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL,MANUAL I

1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ADMINISTRATION 1.1 Definition and Basis 1.1.1 Definition 1 I

Radiological environmental monitoring is the measurement of radioactivity in samples collected from the atmospheric, aq~~atic and terrestrial environment around the Point Beach Nuclear Plant (PBNP). Monitoring radioactivity in effluent streams at or prior to the point of discharge to the environment is not

_ part of the Radiological Environmental Monitoring Program (REMP).

1.1.2 Basis The REMP is designed to fillfill the requirements of 10 CFR 20.1302, PBNP 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.

No significant radionuclide concentrations of plant origin are expected in the plant environs beca~~se radioactivity in plant effluent is continuously monitored to ensure that releases are well below levels which are considered safe upper limits. The REMP is conducted to demonstrate compliance with applicable standards, to assess the radiological environmental irnpact of PBNP operations, and to monitor the efficacy of inplant effluent controls. The REMP, as outlined in Tables 2-2 through 2-4 is designed to provide sufficient sample types and locations to detect and to evaluate changes in environmental radioactivity.

Radioactivity is released in liquid'and gaseous effluents. Air samplers and thermoluminescent dosirneters placed at various locations provide means of detecting changes in environmental radioactivity as a restllt of plant releases to the atmosphere. Because the land area around PBNP is used primarily for farming and dairy operations, sampling of vegetation is conducted to detect changes in radiological conditions at the base of the food chain. Sampling of area-prod~~ced milk is conducted because dairy farming is a major industry in the area.

Page 5 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL Water, periphyton, and fish are analyzed to monitor radion~~clide levels in Lake Michigan in the vicinity of PBNP. Periphyton, attached algae, along with lake water samples, provide a means of detecting changes which may have a potential impact on the radion~~clide concentrations in Lake Michigan fish. Because of the migratory behavior of fish, fish sampling is of minimal value for determining radiological impact specifically related to the operation of the Point Beach Nuclear Plant. However, fish sampling is carried out as a conservative measure with emphasis on species which are of intermediate trophic level and which exhibit minimal migration in order to monitor the status of radioactivity in fish.

Vegetation, algae, and fish sampling frequencies are qualified on an "as available" basis recornpizingthat certain biological samples may occasionally be unavailable due to environmental conditions.

1.2 Responsibilities for Program Implementation 1.2.1 Chemistry F~mctions Chemistry together with Regulatory Affairs (RA) provides the Plant Manager with the technical, regulatory, licensing, and administrative stpport necessary for the implementation of the program. The Chemistry administrative functions relating to the REMP fall into the six broad areas outlined below.

a. Program scope The scope of the REMP is determined by the cognizant Chemist based on sound radiological principles for the fblfillment of PBNP Technical Specifications (TS) and the applicable Federal Regulations. Based on the scope, the Environmental M a n ~ ~(EM) a l is written to accomplish the collection and analyses of the necessary environmental samples. The EM is revised as necessary to conform to changes in procedures and scope.

Chemistry monitors the REMP effectiveness and compliance with TS and with the procedures and directives in the EM. In order to verify compliance with TS, Nuclear Oversight arranges for program audits and Supplier Assessments of the contracted radioanalytical laboratory.

b. Record keeping The monthly radioanalytical results from the contracted laboratory are reviewed by Chemistry and one copy of the monthly radioanalytical results from the contracted laboratory is kept for the lifetime of the plant.

Page 6 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL

c. Data monitoring Chemistry reviews and interprets all program analytical res~~lts on a monthly basis as they are reported. Trends, if any, are noted. Any resulting corrections, modifications and additions to the data are made by Chemistry .. Inconsistencies are investigated by Chemistry with the cooperation of Radiation Protection (RP) and contractor personnel, as reqt~ired.Un~lsualresults as evidenced by radioactivity levels exceeding administrative notification levels are also investigated. Results of the investigation will be conveyed to the Plant Manager. Chemistry will promptly inform the Plant Manager of any sample exceeding Nuclear Regulatory Commission (NRC) regulatory notification levels and will initiate an investigation. A formal report shall be provided to the Plant Manager upon completion of the investigation.

d. Data summary REMP results shall be summarized annually for inclusion in the PBNP Annual Monitoring Report. This s~unmaryadvises the Plant Manager of the radiological status of the environment in the vicinity of PBNP. The summary shall include the numbers and types of samples as well as the averages, statistical confidence limits aiid the ranges of analytical results.

Methods used in summarizing data are at the discretion of Chemistry.

e. Contractor communications ,

Comm~nicationwith the contractor regarding data, analytical proced~res, lower limits of detection, notification levels and contractual matters are normally cond~~cted by Chemistry. Communication regarding sample shipment may be done by either RP or Chemistry as appropriate.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL

f. Reportable items

1. Chemistry shall generate all technically-specified reports related to the operation of the REMP. The material included shall be sufficient to fulfill the objectives outlined in Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50. The following items and occurrences, are required to be reported in the PBNP Annual Monitoring Report:

(a) Summary and discussion of monitoring results including number and type of samples and measurements, and all detected radionuclides, except for naturally occurring radionuclides; (b) Unavailable, missing, and lost samples and plans to prevent recurrence and comments on any si,pificant portion of the REMP not conducted as indicated in Tables 2-3 throlngh 2-4.

(c) New or relocated sampling locations and reason for change; (d) LLDs that are higher than specified in Table 2-2 and factors contributing to inability to achieve specified LLDs; (e) Notification that the analytical laboratory does not participate in an interlaboratory comparison program and corrective action taken to preclude a recurrence; and (f) R e s ~ t of s the a n n ~ ~milk a l sampling program labd use census "milk survey" to visually verify that the location of grazing animals in the vicinity of the PBNP site boundary so as to ensure that the milk sampling program remains as conservative as practicable.

2. The following items are required to be reported to the NRC within 30 days of occurrence pursuant to the criteria of Section 2.2.4:

(a) Confirmed environmental radionuclide concentrations, attributable to PBNP effluents, in excess of notification levels; (b) Confirmed results of weighted stun calculations involving radion~lclideconcentrations, attributable to PBNP effluents, in environmental samples in excess of the specified notification level; and Page 8 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 (c) The report shall, to the extent possible, identify tlie cause(s) for exceeding the limit(s) and define the corrective actions taken to reduce radioactivity in effluents so that the potential dose to a member of the public will not exceed the annual limits.

3. The annual results from the contracted REW analytical laboratory as well as the laboratories analytical QAJQC results, in-house blanks, interlaboratory comparisons, etc., shall be transmitted to the NRC, Region 111, with, or as a separate concurrent s~~bmittal, the Annual Monitoring Report.

4. The Annual Monitoring Report for the previous 12 month period, or fraction thereof, ending December 3 1, shall be submitted to the NRC by April 30 of the following year.

1.2.2 Non-Chemistry Functions The primary responsibility for tlie implementation of the PBNP REMP and for any actions to be taken at PBNP, based on the results of the program, resides with the Plant Manager.

a. Manual control and distrib~~tion The distribution of the PBNP Environmental Mantlal is the responsibility of Document Control.

b. Program coordination The daily operation of the program is conducted by PBNP Radiation Protection personnel, and other qualified personnel as required, under the supervision of an RP staff member who consults, as needed, with Chemistry. The daily administrative flunctions of the RP Management Employee address those fimctions required for the effective operation of the PBNP Radiological Environmental Monitoring Program. These administrative fimctions include the following:

1. Ensuring that samples are obtained in accordance with the type and freq~lencyin Table 2-4 following procedures outlined in this manual;

2. Ensuring adequate sampling supplies and calibrated, operable equipment are available at all times;

3. Ensuring that air sampling pumps are maintained, repaired and calibrated as required and that an adequate number of backup pumps are readily available at all times; Page 9 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL

4. Reporting lost or unavailable samples as well as other potential deviations from the sampling regime in Table 2-4 via the Corrective Action Program and notifying the cognizant Chemist.

5. Assisting the State of Wisconsin in obtaining samples at co-located and other sampling sites based upon a yearly, renewable agreement; and I

6. Assisting Chemistry, as necessary, with investigations into elevated I radioactivity levels in environmental samples.

1.3 Oualitv Assurance/Quality Control Quality assurance considerations are an integral part of PBNP's Radiological Environmental Monitoring Program. The program involves the interaction of Chemistry, site quality assurance and the contracted analytical vendor. The contracted vendor shall participate in an interlaboratory comparison program. The laboratory is audited periodically, either by PBNP or by an independent third party.

Quality control for the PBNP portion of the Radiological Environmental Monitoring Program is achieved by following the procedures contained in this manual. Radiation Protection Technologists (RPTs) collect, package and ship environmental samples under the stpervision of Radiation Protection supervisors. They are advised by Radiation Protection Management who has immediate responsibility for the overall technical I operation of the environmental sampling functions. The RPTs receive classroom training as well as on-the-job training in carrying out these procedures.

An audit of the PBNP Radiological Environmental Monitoring Program and its results shall be completed periodically as a means of monitoring program effectiveness and assuring compliance with program directives. The audit shall be performed in accordance with Section 1.4 of the ODCM.

Page 10 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 1.4 Pro,~am Revisions This manual describes the current scope of the PBNP Radiological Environmental Monitoring Program. Program items or procedures periodically may be updated or changed, consistent with good radiologically monitoring practices, either to reflect new conditions or to improve program effectiveness. Technical and program features described in this manual may be changed with the approval of the PORC and Plant Manager pursuant to the requirements stated in the ODCM.

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 2.1 Program Overview 2.1.1 Purpose No si,onificant or unexpected radionuclide concentrations of plant origin are expected because each normal effluent pathway at PBNP is monitored at or before the release point. However, the REMP is conducted to verifL that pIant operations produce no si,onificant radiological impact on the environment and to demonstrate compliance with applicable standards.

2.1.2 Samples Samples for the REMP are obtained from the aquatic, terrestrial and atmospheric environment. The sample types represent l e y indicators or critical pathways identified by applying sound radiological principles to the PBNP environment.

2.1.3 Monitoring sensitivity The effectiveness of the REMP in fulfilling its purpose depends upon the ability to acc~~rately determine the nahre and origins of fluctuations in low levels of environmental radioactivity. This requires a high degree of sensitivity so that it is possible to correctly discriminate between fluctuations in background radiation levels and levels of radioactivity that may be attributable to the operation of PBNP. Therefore, personnel actively participating in the monitoring program should make every effort to minimize the possibility of contaminating environmental samples and to obtain samples of the appropriate size.

Page 11 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 2.2 Program Parameters 2.2.1 Contaniination avoidance Contamination prevents the accurate quantification of environmental radioactivity and the correct differentiation between fluctuating background radioactivity and levels of radioactivity attributable to the operation of PBNP.

Therefore, it is necessary that all personnel associated with collecting and handling radiological environmental samples talce the appropriate precautions to minimize the possibility of contaminating the samples. Some of the precautions that should be talcen and which will help to minimize contamination are listed below:

a. Equipment which has been on the controlled side, even if released clean, should not normally be used in conjunction with radiological environmental monitoring. An exception to this is the Health Physics Test Instrument WPTI) equipment used to calibrate the air flow calibrator.

b. Store sampling equipment in radiologically clean areas only;

c. Store radiological environmental samples only in radiologically clean areas when samples cannot be shipped to the contractor on the same day they are collected;

d. Treat each sample as a possible source of contamination for other samples so as to minimize the possibility of cross-contamination;

e. Radiological environmental monitoring equipment should be repaired in clean-side shops;

f. Contamination avoidance for environmental TLDs is covered in Section 2.4.2; and

g. Avoid entering contaminated areas prior to collecting environmental samples.

Sample size Sample size affects the sensitivity achievable in quantifying low levels of environmental radioactivity. Therefore, sampling personnel must attempt to attain the quantities of sample specified in Table 2-1. When a range is given, every effort should be made to obtain a quantity at the upper part of the range.

Page 12 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 2.2.3 Lower limit of detection The sensitivity reqr~iredfor a specific analysis of an environmental sample is defined in terms of the lower limit of detection (LLD). The LLD is the smallest concentration of radioactive material in a sample that will yield a net co~lnt,above system background, that will be detected with a 95% probability and have only a 5% probability of falsely concluding that a blank observation represents a real signal. Mathematically, the LLD isdefined by the formula 4.66 Sb LLD '=

E x V x 2 . 2 2 x Y XED(-XAT)

Where LLD = the a priori lower limit of detection in picocuries per nit volume or mass, as applicable;

- the standard deviation of the background counting rate or Sb the counting rate of a blank sample, as appropriate, in counts per minutes; E - counting efficiency in counts per disintegration; v - sample size in units of volume or mass, as applicable; 2.22 -

- n~unberof disintegrations per minute per picocurie; Y - the fractional chemical yield as applicable; h - the radioactive decay constant for the particular radionuclide; and AT - the elapsed time between sample collection, or the end of the collection period, and the time of counting.

Typical values of E, V, Y, and AT are used to calculate the LLD. As defined, the LLD is an a priori limit representing the capability of a measuring system and not an a posteriori limit for a particular measurement.

The required analysis for each environmental sample and the highest acceptable LLD associated with each analysis are listed in Table 2-2.

Whenever LLD values lower than those specified in Table 2-2 are reasonably achievable, the analytical contractor for the radiological environmental samples will do so. When the LLDs listed in Table 2-2 are not achieved, a description of the factors contrib~~ting to the higher LLD shall be reported in the next PBNP Annual Monitoring Report.

Page 13 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 2.2.4 Notification levels The Notification Level (NL) is that measured quantity of radioactivity in an environmental sample which, when exceeded, requires a notification of such an occurrence be made to the appropriate party. Regulatory and administrative notification levels are listed in Table 2-2.

a. Regulatory notification levels The regulatory notification levels listed in Table 2-2 represent the concentration levels at which NRC notification is required. If a measured level of radioactivity in any radiological environmental monitoring program sample exceeds the regulatory notification level listed in Table 2-2, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomaIous result. If the confirmed measured level of radioactivity remains above the notification level, a written report shall be submitted to the NRC. If more than one of the radionuclides listed in Table 2-2 are detected in any environmental medium, a weighted s ~ calclnlation m shall be performed if the measured concentration of a detected radionuclide is greater than 25%

of the notification levels. For those radionuclides with LLDs in excess of 25% of the notification level, a weighted sum calculation needs to be performed only if the reported value exceeds the LLD. Radionuclide concentration levels, called Weighted Sum Action Levels, which trigger a weighted sum calculation are listed in Table 2-2.

The weighted sum is calculated as follows:

concentration (1) concentration (2)

+

+ ... = weighted sum notification level (1) notification level (2)

If the calculated weighted sum is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result. If the confirmed calculated weighted sum remains equal to or greater than 1, a written report shall be submitted to the NRC. This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.

b. Administrative notification levels The administrative notification levels are the concentration levels at which the contracted analytical laboratory promptly notifies the cognizant Chemistry Specialist by phone, followed by a formal written comm~mication.The administrative notification levels are set lower than the NRC regulatory notification levels and lower than, or equal to, the weighted sum action levels so that the nature and origin of the increased level of environmental radioactivity may be expeditiously ascertained and corrective actions talten if required.

Page 14 of36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 2.2.5 Sampling locations A list of sampling locations and the corresponding location codes appear in Table 2-3. The locations also are shown in Fig~u-es2-la, 2-1b, and 2-lc. It is conceivable that samples may become unavailable from specified sample locations. If this were to occtur, new locations for obtaining replacement samples shall be identified and added to the Radiological Environmental Monitoring Program. If mill<or vegetation samples become unavailable from the specified sampling locations, new sampling locations will be identified within 30 days. The specific locations where samples were unavailable may be deleted from the monitoring program. A formal, written reason for the new site and its location shall be transmitted to Chemistry who will m'alce the appropriate changes to the Environmental Manual. Any significant changes in existing sampling location and the criteria for the change shall be reported in the Annual Monitoring Report for the period in which the change occurred.

Additional sampling locations may be designated if deemed necessary by c o b ~ a n t ~ c o m p a personnel.

ny Figures and tables in this manual shall be revised to reflect the changes.

2.2.6 Sampling media and frequency The sampling frequency for the environmental media required by the PBNP REMP is found in Table 2-4. In addition to samples required by the former Technical Specifications, the Radiological Environmental Monitoring Program also includes the sampling of soil and shoreline sediment. To ensure that all samples are obtained at the appropriate times, a checklist is used. The checllist provides a month-by-month indication of all samples, to be obtained at each sampling location (PBF-4121a through 4 1211). These checklists also identify the schedule for the a n n ~ ~milk a l survey and provides space for recording the date samples were shipped offsite for analysis. In addition, the checllist lists each sampling location to identify all samples, to be obtained and the collection date. Because the weekly air samples require additional information, a separate checllist is used for each individual air sampling location for calculations and other information as shown in PBF-4078.

It is recognized that on occasions samples will be lost or that samples cannot be collected at the specified frequency because of hazardous conditions, seasonable unavailability, automatic sampling equipment malfunctions and other legitimate reasons. Reasonable efforts will be made to recover lost or missed samples if warranted and appropriate. If samples are not obtained at the indicated frequency or location, the reasons or explanations for deviations from the sampling frequency specified in Table 2-4 shall be submitted to the PBNP Corrective Action Program.

Page 15 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 2.2.7 Sample labeling All samples must be properly labeled to ensure that the necessary information is conveyed to the analytical contractor and that the results are associated with the correct geographical location. Each label (PBF-4026) must contain the following:

a. Sample type;

b. Sample location from Table 2-3;

c. Date and time (as appropriate) collected; 3

d. Air samples must show the total volume in m ;volumes for water and millc are in gallons; vegetation, sediment, soil, and algae are indicated as

<I000 grams; and fish 21000 grams;

e. Analyses for routine samples are indicated as "per contract." For special samples, the Radiation Protection manager or another Radiation Protection Management Employee will designate the analyses required; and

f. Name of person collecting the sample.

A permanent or indelible ink type felt-tip marlcer shall be used.

A separate sample label is needed for each sample type and location.

Labels are securely attached to each sample container. In addition to sample labels, other identifying marlcings may be placed on sample containers as appropriate.

2.2.8 Sample shipping All environmental samples are shipped to a contractor for analysis. The samples shall be packaged and shipped in such a way as to minimize the possibility of cross-contamination, loss, spoilage and leakage. Each sample shipment shall have a typed cover letter and, when appropriate, a contractor data collection sheet, Included in the letter shall be the same information req~liredfor the sample labels as well as the specific analyses required. The original cover letter and data'collection sheet shall be sent to the contractor under separate cover; one copy of each is to be used as a packing list and a copy of each shall be lcept in the appropriate PBNP file.

Page 16 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL 2.2.9 Sample analyses and frequency The PBNP REMP samples shall be analyzed for designated parameters at the freq~lencylisted in Table 2-4. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attrib~~tableto effluents from PBNP. Typically, this entails the scanning of the spectnun from 80 to 2048 lceV and decay correcting identified radionuclides to'the time of collection. The analysis specifically includes, but is not limited to, Mn-54, Fe-59,211-65, CO-58,Co-60,Zr-Nb-95, Ru-103,I-13 1, Cs-134, Cs-137, Ba-La-140, Ce-141, and Ce-144.

2.2.10 Analytical laboratory The analyses shall be performed by a laboratory that participates in an interlaboratory crosscheclc program. If the laboratory is not participating in such a program, a report shall be made pursuant to 1.2.1.f. 1.(e). The current laboratory is:

Environmental Incorporated Midwest Laboratory 700 Landwehr Road Northbrook, IL 60062-4517 (847) 564-0700 This laboratory performs the analyses in such a manner as to attain the desired LLDs. The contracted laboratory participates in an inter-laboratory comparison crosscheclc program.

The contractor is responsible for providing prompt notification to the cognizant Chemist regarding any samples found to exceed the administrative notification levels as identified in Table 2-2.

Assistance to the State of Wisconsin As a courtesy and convenience, PBNP personnel obtain certain environmental samples for the Section of Radiation Protection, Department of Health and Family Services of the State of Wisconsin as listed in Table 2-5. A checldist is used. In addition, a State of Wisconsin air sampling data sheet is submitted with each sample obtained at Wisconsin air sampling locations serviced by PBNP personnel.

State of Wisconsin precipitation samples collected twice a month (or as available) require a state sample tag to be placed in a box with the quart cubitainer. State s~ppliedlabels for air particulate filters require start and stop time, date and beginning and ending vol~une.Fish sent to the state identify only the quarter and the year using a PBNP label (PBF-4026). The monthly lake water sample may be picked up by state personnel and in which case these samples require only that the date and location be written on the box for the cubitainer. The well water samples, 2 timeslyear, may be piclced similar to lake water samples.

Page 17 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 21 May 1,2009 ENVIRONMENTAL MANUAL Samples obtained for the State of Wisconsin are either given directly to state personnel or shipped as required. The department address is:

State Lab of Hygiene Radiochemistry Unit 2601 Agriculture Dr.

PO Box 7996 Madison, Wisconsin 53707-7996 Specification of Sampling Procedures General radiological environmental sampling procedt~resfollow the directives presented in Sections 2.1 and 2.2. Specific information for handling individual sample types follow.

2.4.1 Vegetation Vegetation samples consist of green, growing grasses and weeds and are obtained three times per year, as available, fiom specified locations. New growth, not dead vegetation, should be used because these samples are indicators of recent atmospheric deposition. Use a scissors or other sharp cutting tool to cut the grasses and weeds off as close to the ground as possible.

Do not include plant roots and take care not to contaminate the sample with soil. Total sample collected should exceed 500 grams and ideally should be 1000 grams. Place entire sample in an appropriate container, such as a plastic bag (tape the bag shut) and label the container as described in Section 2.2.7.

2.4.2 Thermol~minescentdosimeters (TLDs)

TLDs capable of multiple, independent measurements of the same exposure are posted at locations specified in Table 2-4 and are changed quarterly. The utmost care in handling is required to minimize unnecessary exposure during transit, storage and posting because the TLDs begin recording all radiation fiom the moment they are annealed (heated to rezero) at the contractor's laboratory. Packages of TLDs in transit should be marked "DO NOT X-RAY. "

Transportation control (TLDs) shall accompany the new batch in transit fiom the contractor's laboratory to the plant. The control TLDs shall accompany the batch during brief storage and subsequent posting. The same control TLDs shall accompany the "old" or exposed batch on its way back to the contractor. Therefore, each control represents the sum of approximately half the in-transit exposure of the two batches. This control system is able to identify any unusual in-transit exposure.

Page 18 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL Environmental TLDs should never be brought into the plant RCA or any other area with elevated radiation, but may be stored for brief periods in a shielded enclostlre in the RP Office Area or other low background area, such as the Energy Information Center or the Site Bo~mdaryControl Center. The contractor is to time shipments to coincide as closely as possible with the beginning of a calendar q~larter.TLDs should be shipped back to the contractor immediately or within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of removal. The contractor is instructed to process the samples immediately upon receipt. The contractor shall report removal data and cumulative readings in mR for all locations and control, correct for in-transit exposure and express results in net mlU7 days.

Labels of the exposed set for shipment to contractor should show both posting and removal dates.

2.4.3 Lake water Lalce water samples are obtained monthly at specified locations. The contractor is responsible for the compositing for quarterly analyses. Collect approximately 8000 ml of lake water in the required number of cubitainers, or other appropriate containers, at each location and label as directed in Section 2.2.7.

Also, lalce water is collected for the State of Wisconsin pursuant to Table 2-5.

The sample is collected, labeled, and forwarded to the appropriate State agency.

2.4.4 Well water Well water samples are obtained quarterly fiom the single onsite well.

Sample should be obtained fiom PW-SO, T-90 Hydro-pne~maticTank Drain After purging 8 gallons, collect approximately 8000 ml of well water using the req~riredn ~ ~ m bof e rcubitainers or other appropriate containers. Label as directed in Section 2.2.7.

2.4.5 Air

a. Sample collection Air filters are changed weekly at specified locations and placed.in glassine envelopes for shipment to the vendor for analyses. Take preca~rtionsto avoid loss of collected material and to avoid contamination when handling filters. Washing hands before leaving the plant to change filters is a recommended practice.

Page 19 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 Both particulate filters and charcoal cartridges are employed at each sampling location. Particulate filters are analyzed for gross beta activity after waiting for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow for the decay of short-lived radon and thoron daughter products. The contractor makes quarterly composites of the weeldy particulate samples for gamma isotopic analyses.

A regulated pump (Eberline Model RAS-1 or equivalent) is used at each air sampling location. Because of the automatic flow regulation, rotarneter readings at the beginning and ending of the sampling period should be nearly identical. Substantial differences in readings usually require some investigation to determine the cause. The rotameters attached to the pumps are calibrated in liters per minute. When new filters are installed, flow rate should be about 28-30 lpm. Flow rates less than 26 Ipm or greater than 32 Ipm require that the pump regulator be readjusted. The correct flow rate is determined by multiplying the rotameter reading by the correction factor indicated on the calibration sticker affixed to the rotarneter.

Some pumps are equipped with an elapsed time meter which reads in hours. Forrn PBF-4078 is used for recording pertinent air sampling data for each location. At a normal filter change, the following procedure will apply:

1. Record "date off" and "time.off."

2. Record rotameter reading for end of period (R2),

3. Turn off pump, if necessary, and record hour meter reading or actual time for end of period (t2).

4. Before removing the filter, label the sample envelope as directed in Section 2.2.7. Also enter any other pertinent information at this time. Always write data on the envelope before inserting the particulate filter in the envelope.

5. Remove particulate filter being careful to handle filter only by edges, place in the glassine envelope.

6. Remove charcoal cartridge, place in plastic bag, and label as directed in Section 2.2.7.

7. Install new charcoal cartridge and particulate filter being sure to check the charcoal cartridge for breaks and the particulate filter for holes in the filter surface. Discard unacceptable filter media.

Page 20 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009

8. Record "date on."

9. Record hour meter reading or time for beginning of period (tl).

10. T t m pump on (if necessary).

11. Perform weeldy gross leak test by blocking the air flow with a large rubber stopper. (For this test only, the rotameter ball may register zero or drop all the way to the bottom. The difference between zero and the bottom is not significant.)

12. Record rotameter reading for beginning of period (R1).

13. Record correction factor as indicated on calibration sticker affixed to rotameter (C).

14. Observe that the starting rotameter reading (R1) is close to the previous ending reading (R2). A substantial.differenceindicates need for further investigation because the regulator will generally maintain constant flow regardless of filter loading. T 3

15. Calculate total vol~unefor period and enter on data sheet (m ). (This step may be performed at a later time.)

16. Any ~musualconditions or observations should be referenced under

(*) and recorded under "*NOTESMat the bottom of the data sheet.

Air samples are collected for the State of Wisconsin at two locations, one of which is co-located with a PBNP air sampling site. They are handled in a manner similar to PBNP samples except that no charcoal cartridges are involved. However, state samplers are equipped with volume integrating meters. Therefore, clock time must be recorded in addition to the ending and beginning volumes.

Label and forward samples to the State.

Page 21 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009

b. Air sampling system description The air monitoring equipment for the PBNP air sampling program consists of a Regulated Rate Control System. The Regtllated Rate Control System is used at PBNP beca~~se of its simplicity and reliability. It is designed to minimize both calibration diff~cultiesand the potential for lealcs. The regulated rate control system includes a pump, a flow regulator, the appropriate filter holders and a minimum of tubing. Also, it may include an elapsed time meter. In this system, the total volume sampled can be' calculated simply and accurately from the elapsed time and the flow rate which is lcept constant by the regulator regardless of filter loading.

The air samplers are Eberline Model RAS-1 (or equivalent) and have built-in rotameters which read in liters per minute. The systems also include an Eberline WPH-1 (or equivalent) weatherproof housing and an iodine cartridge holder and mo~mtinglcit and may include an electric hour meter. Glass fiber, 47 mm diameter, particulate filters capable of collecting 95% of 1 micron diameter particles and iodine impregnated charcoal cartridges (Scott or equivalent) constitute the filter media.

c. Calibration Calibrate the pump rotameter at initial installation and at yearly intervals thereafter by connecting a laboratory-quality reference flow meter with NIST traceable calibration to the filter face with the particulate filter and charcoal cartridge in position. Upon completion, a calibration sticker indicating the correction factor is affixed to, or near, the built-in rotameter.

The results are recorded on Form PBF-4020.

d. Inspection and maintenance Weekly gross leak checlcs shall be accomplished as indicated in the appropriate PBNP procedure.

Page 22 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL For normal operation, the regulators should be adjusted to maintain a true flow rate of 28-30 liters per minute. Adjustments are made by h d g the screw marlced FLOW ADJUST located on the side of the regulator body:

co~mtercloclcwiseincreases flow, cloc1.wise decreases flow. Flow rates shouId be observed at all filter changes. Flow rates less than 26 Ipm or more than 32 lpm require readjustment of the regulator. Particular attention should be paid to flow rate readings with the "old," loaded filter and with new, unused filters in position. Because of the regulator, the difference in flow should be barely perceptible, perhaps no more than one lpm. Si,dficant differences in flow rates require further investigation to determine the cause.

Preventive maintenance shall be performed as indicated in the appropriate PBNP procedure on all environmental air samplers and the results recorded on Form PBF-4020.

e. Pump repair and replacement The p u p s can operate for long periods of time with rninhal or no maintenance. The vane assembly of the pump is most susceptible to failure, indicated by excessive noise or inability to maintain sufilcient flow across loaded filters. At least one standby pump should be available for temporary service during the repair period. In the event of motor failures due to causes other than defective connections, complete replacement of the unit may be necessary. All pump repairs should be done in a clean-side shop with clean tools.

2.4.6 Milk Beca~lseof iodine decay and protein binding of iodine in aging millc samples, speed is imperative in processing and samples m~lstbe lcept cool to avoid degradation and spoilage of the samples. Millc samples are obtained monthly in conj~mctionwith the State of Wisconsin Milk Sampling Program from three individual dairy farmers located north, south, and west of the site. Millc sampling data can also be obtained from the Kewaunee Nuclear Power Plant, whose radiological environmental monitoring program includes samples taken from a dairy in Green Bay, W. This location could act as a control location.

Beca~~se two of the three sites are co-located, the PBNP piclcup is coordinated to coincide with the State arranged schedule. The piclcup usually will be the first Wednesday of the month.

The following sequence should be followed:

a. After verifyingthe State millc pickup date with the Manitowoc Public Health Department (Mr. Mark Chatenka, phone number 683-4454), notify dairies of piclc~~p date.

Page 23 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONENTAL MANUAL Revision 2 1 May 1,2009

b. ~e'kaulsethe milk must be ltept cool, but not frozen, fill enough c~~bitainers, or other appropriate containers, with water and freeze to be able to put one in each shipping container. Fill the containers with water and freeze the day preceding the piclcup.

c. The milk from the Strutz farm (E-21) must be piclted up before 0900 because that is the time the Strutz milk is shipped. A late arrival may mean a missed sample. Milk from sites E-11 and E-40 may be piclted up any time after the Strutz pickup.

d. Identify yourself and the nature of your business at each milk piclcup site.

Collect two one-gallon samples from each site, using a fimnel if necessary.

If shipment cannot occur on the collection day, store the mill<in a clean-side refrigerator overnight. DO NOT FREEZE.

e. Complete a PBNP sample tag according to Section 2.2.7 for each gallon sample and place in the box with the sample. Do not seal the box. Place the samples in insulated containers and hull them over to Ready Stores personnel for shipment. Make sure that the cover letter and, as appropriate, the contractor data collection sheets are sent according to Section 2.2.8 of this manual.

2.4.7 Algae Filamentous algae are collected from pilings or roclts three times per year, as available, from two locations. The long, grassy, dark green algae can normally be cut with scissors. The shorter, light green algae normally must be scraped from roclts or pilings. When scraping algae, be careful not to include pieces of rock in the sample. The sample can be lightly rinsed in the same medium in which it is growing. This rinse will help rid the sample of pieces of rock and gravel that may have been inadvertently collected with the sample. Because roclts and sediment contain naturally occurring radioactive materials, their inclusion may give false sample results. Collect between 100 and 1000 gm of algae. A sample greater than 500 gm is preferred. Place the algae in a wide-mouth poly bottle or other appropriate container and label the container as director in Section 2.2.7. The algae must be kept cool to prevent spoilage.

Page 24 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 2.4.8 Fish Fish are obtained three times per year (March, August and December) as available either from the traveling screens as washed into the fish basket or by other methods as required. For any given sampling period, three fish, or a sufficient n~mberto yield at least 1000 gm of fillets, should be provided.

Place fish in plastic bags and tape andlor tie tightly closed. Fish are stored briefly in a radiologically clean freezer. It may be desirable in warm weather to coordinate milk and fish sampling, thereby allowing simultaneous shipment in insulated containers. Pack fish samples with ice if needed. Label bags as directed in Section 2.2.7, being sure to indicate fish species when possible.

Following packaging of fish, remove and discard any fish left in the freezer.

This avoids sending fish that are not representative of the sampling period.

Fish are obtained f o ~times r per year (March, June, September and December) for the State of Wisconsin. Fish sampling for the State is performed in the same manner as that for the plant. Approximately four fish should be. sent to the state at each sampling period.

2.4.9 Soil Soil integrates atmospheric deposition and acts as a reservoir for long-lived radion~lclides.Although soil sampling is a poor technique for assessing small incremental releases' and for monitoring routine releases, it does provide a means of monitoring lpng-term trends in atmospheric deposition in the vicinity of PBNP. Therefore, soil samples are obtained two times per year from specified locations.

Clear the vegetation from a 6" x 6" area, being carefill to leave the top layer of soil relatively intact. Remove root bound soil by shalcing the soil onto the cleared area or into the sample container before discarding the roots. W e n necessary, it is preferable to leave some roots in the soil rather than to lose the top layer of soil.

Remove the soil to a depth of three inches. If necessary, expand the area, instead of digging deeper, to obtain the required amount of sample. If an area larger than 6" x 6" is used, notify Chemistry of the area used. The minim~m acceptable quantity is 500 grams. Place the entire soil sample in a wide-mouth poly bottle or another appropriate container. If a plastic bag is used, seal the bag with tape. Label the sample as directed in Section 2.2.7.

Page 25 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL This proced~ureassumes that the samples are obtained from ~mdistuubedland; land that has not been plowed within approximately the last 25 years. If the land has been plowed, the soil should be sampled to the plow depth which typically is eight inches. Place the soil in a clean bucket or appropriate size plastic bag, homogenize the soil and place 1000 grams of the well mixed soil sample in a plastic bag, or other appropriate container, and label as described above.

2.4.10 Shoreline Sediment Shoreline sediment consisting of sand and smaller grain size material is sampled two times per year from specified locations. The 1000 gram sample is collected, from beach areas near the water ridge. At each location collect representative samples of sediment types roughly in proportion to their occtlrrence. For example, at E-06 avoid collecting a sample which consists excl~usivelyof the dark-brown to black sediments which occtu in layers t p to several inches thick. Package the sample in a wide-mouth poly bottle or other appropriate container and label as described in Section 2.2.7.

2.5 Milk Strvey The milk sampling program is reviewed annually, including a visual verification of animal grazing in the vicinity of the site boundary, to ensure that sampling locations remain as conservative as practicable. The verification is conducted each stunrner by co,pizant PBNP personnel. Becatuse it is already assumed that milk animals may graze LIPto the site boundary, it is only necessary to verify that these animals have not moved onto the site. No animal census is req~uired.Upon 'completion of the visual check, RP personnel will notify Chemistry in writing. To ensure performance of the annual verification, "milk review" is identified on the sampling checklist (i.e., the PBF-4121a-1 series).

Page 26 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 TABLE 2-1 e RECOMMENDED MINIMUM SAMPLE SIZES Sample T w e -

Size Vegetation 100-1000 gm Lake Water 8 liters (2 gal).

Air Filters 250 h3 Well Water 8 liters (2 gal)

Mill< 8 liters (2 gal)

Algae 100-1000 gm Fish (edible portions) 1000 p Soil 500-1000Q ,

Shoreline Sediment 500-1000 gm Page 27 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES NOTIFICATION LEVELS WEIGHTED SAMPLE REPORTING NRC PBNP@) SUM TYPE UNIT PARAMETER LLD") (Regulatory) (Admin.) ACTION LEVEL Vegetation pCUg wet Gross Beta 0.25 --- 60 ---

CS-137 0.08 2 0.40 0.50 CS-134 0.06 1 0.20 0.25 1-13 1 0.06 0.1 0.06 0.06 0.25 --- 2.0 ---

Shoreline P C U ~dry Gross Beta Sediment and Cs-137 Soil other(')

Algae pCUg wet Gross Beta CS-137 CS-134 Co-5 8 Co-60 other(')

Fish pCi/g wet Gross Beta CS-137 CS-134 Co-58 Co-60 Mn-54 Fe-59 Zn-65 TLDs mR/7 days Gamma Exposure 5mW7 days

~altewater(~) p ~ i / ~ - ~ . ~ . (Gross d ) Beta and Well Water Cs-134 CS-137 Fe-59 Zn-65 Zr-Nb-95 Ba-La-140 Co-58 Co-60 Page 28 of 36 I N F O W T I O N USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 TABLE 2::!

Lakewater p ~ i / L - ~ . ~ . ' d Mn-54

' 15 1,000 100 250 and Well Water 1-131 2 --- 2 ---

(Continued) Other 30 --- 100 ---

H-3 3,000 30,000 3,000 7,500 Sr-89 10 --- 50 ---

Sr-90 2 --- 20 ---

Milk Air Filter p~i/m3 Gross Beta 0.01 --- 1.O ---

1-131 0.07 0.9 0.09 0.2 CS-137 0.06 20 2.0 5.0 CS-134 0.05 10 1.O 2.5 other@) 0.1 --- 1.O ---

(a) The LLDs in this column are the maximum acceptable values.

(b) The values in this column are not technical specifications.

(c) Other refers to non-specified identifiable gamma emitters.

(d) T.S. =total solids.

(e) No drinking water Page 29 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Code Location Description E-0 1 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, the TLD is on South side of Two Creeks Road, West of Lakeshore Road on first pole West of Lakeshore.

E-06 Point Beach State Park - Water and shoreline sediment samples at the Coast Guard Station; soil and vegetation &om the Point Beach State Park campground area N of the Coast Guard Station and on the West side of County Road 0; TLD located South of lighthouse on telephone pole.

WPSC Substation on County Rt. V, about 0.5 Miles West of Hwy. 42 G. J. Francar Property, at the SE Comer of the Intersection of Cty. B and Zander Road Nature Conservancy, East side of Hwy 42. Comer of Hwy 42 and Cty. BB. On pole North side of Entrance.

PBNP Site Well Lambert Dairy Farm, 1523 Tapawingo Road, 0.5 miles West of Saxonburg Road Discharge Flume / Pier, U-l side Pumphouse South Boundary, about 0.2 miles East of Site Boundary Control Center Southwest Comer of Site WSW, Hwy. 42, Residence, about 0.25 miles North of Nuclear Road North of Mishicot, Cty. B and Assman Road, NE Comer of Intersection NW of Two Creeks at Zander and Tannery Roads Reference Location, 17 miles SW, at Silver Lake College Local Dairy Farm just South of Site (R. Strutz) on Lakeshore and Irish Roads West Side of Hwy. 42, about 0.25 miles North of Johanek Road Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy. 42 North Side of County Rt. V, near intersection of Saxonburg Road South Side of County Rt. BB, about 0.5 miles West of Norman Road 804 Tapawingo Road, about 0.4 miles East of Cty. B. North Side of Road NE comer of Saxonburg and Nuclear Roads, Southwest Comer, about 4 Miles WSW TLD on westernmost pole between the 2nd and 3rd parking lots, On microwave tower fence NE comer at Intersection of Tapawingo and Lakeshore Roads.

On utility pole North side of Tapawingo Road closest to the gate at the West property line Page 30 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL '

TABLE On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate in line with first designated treeline 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.

Lalce M,ichiganshoreline accessed from SE corner of I W P parking lot. Sample South of creek.

On tree West of former Retention Pond site On tree East of former Retention Pond site Local Dairy Farm, about 1.8 miles north of intersection of Highway 42 and Nuclear Road (Manitowoc County), on West side of Highway 42.

E-4 1 NW comer of Woodside and Nuclear Roads (Icewaunee Co.)

E-42 NW comer of Church and Division, East of Mishicot E-43 West Side of Tannery Road South of Elmwood (7th pole South of Elmwood)

E-TC Transportation Control; Reserved for TLDs Page 31 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 TABLE 2-4 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS FREQUENCY Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05, TLD Quarterly Exposure -06, -07, -08, -09, -12,

-14, -15, -16, -17, -18,

-20, -22, -23, -24, -25,

-26, -27, -28, -29, -30,

-31, -32,

-38, -39, -TC Vegetation Gross Beta 3dyr as available Gamma,Isotopic Analysis

~lgae Gross Beta 3x1~1-as available Gamma Isotopic Analysis Fish Gross Beta 3dyr as available Gamma Isotopic Analysis (Analysis of edible portions only)

Well Water Gross Beta, H-3 Quarterly Sr-89,9O,I-131 Gamma Isotopic Analysis (on total solids)

Lake Water Gross Beta Monthly H-3, Sr-89, 90 Quarterly composite of monthly collections 1-13 1 Monthly Gamma Isotopic Analysis Monthly (on total solids)

Milk Sr-89,90 Monthly 1-131 Gamma Isotopic Analysis Air Filters Gross Beta Weelcly (particulate) 1-131 Weekly (charcoal)

Gamma Isotopic Analysis Quarterly (on composite particulate filters)

Soil Gross Beta Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, Gross Beta

-33 Gamma Isotopic Analysis Page 32 of36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL TABLE 2-5 SAMPLES COLLECTED FOR STATE OF WISCONSIN Sample T w e Location Fre~uency

1. Lake Water E-0 1 Monthly

2. Air Filters E-07 Weekly E-08

3. Fish Quarterly, As Available Twice a month, As Available

5. Milk E-11 Monthly E-40

6. Well Water E-10 2 timeslyear Page 33 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL FIGURE 2- 1a RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 34 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL FIGURE 2- 1b RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FltlRE 2-lb S I T E MAP POINT BEACH NUCLEAR PLANT TLD @TLD&AlR AAOTHER CGS FILE 10141 Page 35 of 36 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 2 1 May 1,2009 ENVIRONMENTAL MANUAL FIGURE 2- 1c RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 36 of 36 INFORMATION USE

ENCLOSURE 3 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2009 ANNUAL MONITORING REPORT RADILOGICAL EFFLUENT CONTROL MANUAL REVISION 5 JANUARY 13, 2009 34 pages follow

RECM DIOLOGICAL EFFLUENT CONTROL MANUAL DOCUMENT TYPE,: Controlled Reference CLASSIFICATION: N/A REVISION: 5 EFFECTIVEDATE: Jai1~lal-y13.: 2009 REVIEWER: Plallt Operatioil's Review Corninittee APPROVAL AUTHORITY: Plai~tMalager PROCEDURE OWNER (title): Crro~upHead OWNER GROUP: Cheillistry Veiified Cul~entCopy: ,

Sigi?ah.ure Date Time List pages used for Partid Perfo~i~lai~ce Contsolling Worlc Doc~uil~entN~ui~bers

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revision 5 Januaiy 13. 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL .

TABLE OF CONTENTS SECTlON TITLE PAGE 1.0 RADlOLOGICAL EFFLUENT CONTROL PROGRAM ............................................ 4 1.1 Bisis ................................................................................................................................ 4 1.2 Basis Statement .............................................................................................................. 5 1.3 Responsibilities ............................................................................................................ 6 1.4 M a n ~ ~Revisions al ..........................................................................................................6 1.5 . RECP Psu.ameters Reportable in tlie Anilual Monitoiing Report ...................................6 1.6 Otlier RECP Reportable Eveiits ..................................................................................... 8 1.7 Audits ............................................................................................................................. 9 t t 2.0' RADIOACTIVE EFFLUENT CONTROL ................................................: ............ 10.

2.1 Liquid Radioactive Efflttent Treatn~entSystem ............................................................ 10

2. . G ~ S ~ ORadioactive LIS Effluent Treatment System ......................................................... 10 2.3 ~ f f l ~ t eControl nt and Acco~~i~tability .............................................................................. 11 3 .0 RADIOACTIVE EFFLUENT MONITORING 1NSTRUMENTATION OPERABILlTY R,EQULREMENTS............................................................. '................ 12.

Objective ........................................................................................................................ 12 Operability Specifications ............................................................................................. 12 RADlOACTlVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .....................................................................18 Objective ........................................................................................................................18 Radioactive Monitoiiiig Ii~str~iiiientation S~~i-veillance Requirements .........................,. 18 Definitions ..................................................................................................................... 18 RADlOACTlVE EFFLUENT RELEASE LIMITS ....................................... :.............. 25 Objective ....................................................................................................................... 25 Radioactive Liquid Effluent Concentrations .................................................................25 Radioactive Effl~tentRelease Limits ..................................................................25 Radioactive Gaseous Effluent Colzceiin.atio~~s .............................................................. 26 Radioactive Gaseous Effl~~ent' Release Limits .............................................................. 26 Atn~ospl~eiic Release Rate Limitations ........................................................................ 27 Cuinulative and Pro-jected Doses ................................................................................... 28 Radioactive Effluent Treatment ................................................................................. 2 8 Total Dose ..................................................................................................................... 29 Solid Radioactive Waste ............................................................................................ 2 9 Page 2 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 Ja11ual-y 13. 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL SECTlON TlTEE PAGE 6.0 RADIOACTIVE EFFLUENT SAMPLING AND ANALYSIS REQUIREMENTS ................................................................. .................................... 29 6.1 Purpose .......................................................................................................................... 29 6.2 Radioactive Liq~lidWaste Sampling and Analysis ....................................................... 29 6.3 ' Radioactive Gaseous Waste Sail~plingand Ailalysis .................................................29 TABLE 3-1 RADlOACTlVE LIQUID EFFLUENT MONlTORING INSTRUMENTATION ...... 13 TABLE 3-2 RADIOACTIVE.GASEOUS EFFLUENT MONITORING t

INSTRUMENTATION.................................................................................................. 15 NOTATIONS FOR TABLES 3-1 AND 3-2 .........:............................................................................... 17 TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT IVlONlTORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS ................................. 19 TABLE 4-2 RADlOACTlVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREIVlENTS ................................. 2 1 NOTATIONS FOR TABLES 4-1 AND 4-2 .........................................................................................24 TABLE 6-1 RADIOACTIVE LlQUID WASTE SAMPLING AND ANALYSIS PROGRAM .............. ................................................................................. 30 NOTES FOR TABLE 6-1 ...............;................................................................................................... 32 TABLE 6-2 RADlOACTlVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ............................................... ............................... ....... 33 NOTES FOR TABLE 6-2 ........................................ .. .. .. .. . . . . .. .. . .. . . .. . .. . . . . . .. .. . . 34 Page 3 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL hlANUAL Revision 5 Ja11uai-y 13: 2009 RADIOLOGICAL EFFLUENT CONTROL W N U A L 1.0 RADIOLOGICAL EFFLUENT CONTROL PROGRAM 1.1 Basis The Radiological Eftlueilt Control Progra111 (RECP) shall col~fol~ll to 10 CFR 50.36a for the coi~trolof radioactive eftlueilts and illaiiltaiiling doses to ineillbers of the public fsoin radioactive effluents as low as reasoilably aclzievable (ALARA). The RECP also is establisl~edto coiltrol the amount and coilceiltratioizs of radioactivity in PBNP effluent p~wsuantto the follo\~ingdocuments:

1.1.1 10 CFR 50.34a-Design objectives for eq~~iprnent to col~trolreleases of radioactive illateiial ill effluents-nuclear po\ver'i.eactorsI t 1.1.2 10 CFR 50: Appeildis A: Clitelioi160-Coiltrol of releases of radioactive inateiicll to the eh\riroixnent, 1.1.3 10 CFR 50, Appendis A, Clitelio~~ 63-Monitoiing file1 and waste storage, 1.1.4 10 CFR 50, Appeildis A. Criteiion 64-hloi~ito~ii~g radioactivity releases, 1.1.5 10 CFR 20.1302-Coinpliance with dose limits for ii~dividualinei~~bers of the p~tblic.

1.1.6 10 CFR 20.1501-General.

1.1.7 PBNP General Design Ciite~ion17-hloizitoiing Radioactivity Releases, and ,

1.1.8 PBNP Geileral Design Cliteiioi~70-Contsol of releases of radioactivity to the ei~viroi~ment.

POlNT BEACH NUCLEAR PLANT !AJXR/I RADlOLOGlCAL EFFLUENT CONTROL ILlAN UAL Revision 5 Jaizuaiy 13, 2009 RADIOLOGlCAI, EFFLUENT CONTROL MANUAL.

1.2 Basis Stateilleizt Liquid effluent from tlze radioactive waste disposal systeizz is diluted by tlze circulatii~g water system piior to release to Lake Michigan. Witlz two puizzps operatiizg per uiit. tlze flow of the circulatiizg water systeizz is approximately 340.000 gpnz per unit. Operation of a single circulatiilg water puizzp per unit reduces the izoizliizal flow rate by about -10%.

Licluid waste from tlze waste disposal system izlay be discharged to the circ~datingwater system of eitlzer ~ i iviat the service water Sehllll header. Beca~~se of the low radioactivity levels in tlze circulating water discl~arge.the concentratioizs of licluid radioactive effluents at tlis poiizt are not ineas~ireddirectly. Instead. the coizceiztratioils in the circ~dating water discliarge are calculated fi.0111 tlze izzeasured coizceiztsatioiz of tlze liquid effluent. tlze disclzarge flow rate of the efflueizt and tlze izoizliilal flow ill tlze circ~datingwater system.

1 t Tlze release of radioactive materials in liquid efflueizts to ~iizrestlictedareas is monitored aizd coiltrolled to coizfoiizl to the dose objectives in Sectioiz 11.A of Appendix 1 to 10 CFR 50 and will be as lofir as reasonably- achievable (ALARA) in accordailce with the req~iireizzentsof 10 CFR Pal-ts 50.348 aizd 50.36a. The monito~ingand coiztsol also is uizdertalteiz to lteep tlze coizceiztrations of radioizuclides in PBNP liquid efflueilt released to unrestricted areas confoii~ziizgto tell tiilzes tlze maxim~une f f l ~ ~ ecoizcentsation i~t (MEC) values specified in Table 2. Col~in1112of Appendix B to 10 CFR 20.1001 -20.2402.

Furtlieiinore. the appropliate portioizs of the liil~iidradwaste treatlzient systeizzs will be.

used as required to lteep the releases ALARA.

These actioizs provide reasonable assuraizce that the resultiizg average ailn~ialdose or dose coinmitizieiit fro111 liquid effluent from each tinit of tlze Point Beaclz N~iclearPlaizt for any iizdividual in an uizrestiicted area from all patllurays of exposure will not exceed tlze 10 CFR SO. Appendix 1 dose objectives. Tlz~is,discharge of liq~iidwastes not exceeding tlzese release limits will not r e s ~ ~inl tsignificant exposure to members of tlze p~iblic because of cons~iinptionof diinltiizg water fro111 tlze Ialte. even if tlze effect of potable water treatizzeizt systeins on red~iciizgradioactive coizcentrations of the water s~ipplyis conservatively neglected.

Prior to release to the atmospl~ere~ gaseous wastes are illised in the ausiliai? b~~ildiizg vent ~ 4 t hthe flow froill at least one of two ausiliaiy building exhaust fans. Further dilutioiz tlzeiz occ~irsin the atmosplzere. Release of radionuclides to the aul~osplzeseis monitored aizd controlled so that effluents to unrestiicted areas confoim to tlze dose objectives of Sections 11.B and C of Appendix 1 to 10 CFR 50. Monito~iizgand coiztrol also is ~uzdertdltento ellsure that at the poiizt of izlaxiinuin ground coizcentratioiz at the site boundary, tlze radion~iclidecoizcentsatioi~sin tlze atmosphere will confoiiz~to the liinits specified in Table 2, Col~unn1 of Appendix B to 10 CFR 20. Furthe~more.the appropliate portions of the gaseous radwaste treatineizt system are used as required to keep tlze radioactive releases to tlze atmosplzere ALARA.

Page 5 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revisioi~5 Jan~laly13. 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL 111order to achieve the dose objectives of Appeildis 1 to 10 CFR 50 and the aforemei1tioiled coilcentration limits. the setpoii~tsfor releases to the at~llospl~ere and to Lalte Ivlichigai1 t~tilizethe metl~odologyfoui~din tlze Offsite Dose Oalculatioiz Mail~~al.

Setpoints for releases to the ati11osphere are based 011 the dilution provided by buildiilg vents as well as the highest ai111~1alaverage %/(I! at the site boundaiy. Setpoints for releases to Lalte Michigan are based 0111.4;on dil~ttionby circulatioi1 water. Together.

- control aild moilito1ii1g provide reasoilable assurance that tlze ml~ualdose from each til lit's efflueizts. to an ii1divid~alill ail ~~i~restiicted area will not exceed the dose obi ectives of Appeizdis I to 10 CFR 50.

Il?zplemei~tatioiof the RECP will lteep average aili1ual releases of radioactive matelial in PBNP efflueilts and their resultaizt coininitted effective dose equivaleizts at sinall

,percentages of the dose liinits specified in 10 CFR 20.130 1. At the same time. the methodology of ililpleillei1tiilg the RECP pel-mits the flexibility of operation. coillpatible with considerations of health and safety. to asstwe h a t the public is provided with a dependable source of power even uilder unusual operating conditioils which may temporaiily result in releases higher than such nui~~elical guides for design objectives set forth in Appendix 1 b ~ t still t writhill levels that assure that the average population exposure is equivaleizt to sinall fractions of doses from ilatural bacltground radiatioiz.

Coinpliailce \;\.it11 the provisioils of Appendis 1 to 10 CFR Part 50 constitutes adequate demonstsatioi~of confol~~lance to the standards set forth ill 40 CFR Part 190 regarding the dose comillitrneilt to iildividuals from the urai1iuin file1 cycle.

All req~tiredactioils of the Radiological Effluei~tColltrol Program shall be cond~ucted usiilg approved proced~~res. The respoilsibility for the ii~1plementationof the approved proced~~res resides with the Manager-PBNP.

Revisioils to this inail~talshall be peirfoii~~ed in accordal~cewith the ODCM Sectioi~1.3.

1.5 RECP Parameters Reportable ill the Ani1~1alMoilitoliilcr Report Info~matioi~ relative to the inoiitlzly quantities of liq~ud,gaseous, and solid radioactive effluei1ts released from PBN P and efflueilt volumes used in inaiiltaiiliilg the releases v\ritllin 10 CFR 20 limits shall be reported in the Ai~nualMonitorii~gReport as follo\vs:

1.5.1 Releases

a. Total radioactivity in cuiies released and average diluted discliarge coilcentsatioi~sof the follo\;iring release categoiies: gamma isotopic, gross alpha, tritium, and strontium (beta emitters other than tliti~un).

Page 6 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revisioil 5 Jan~iary13: 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL

b. Total volulne (ill gallol~s)of liquid waste released illto circulating water

c. Total volurne (ill gallons) of dilutioil water used.

d. The inasiinuln concel~tsationof t ~ i t i ~andm gross,gamma radioactivity released (averaged over the period of a single release).

e. Estimated montl1ly total radioactivity in curies of individual radiolluclides released based on represelltative isotopic m~alyses.

f. Semiann~ialand a l ~ l l ~ totals

~ d of i110l1tldy quailtities of individual radionuclides. as dete~inipedby isotopic analyses.

1.5.2 Releases to the Atlnosphere

a. Total gross radioactivity (in Curies): by 1nont1.r~released of: .

1. Noble Gases.

2. Halogens.

3. Pzrtic~ilates,subdivided illto beta emitters (stronti~ul?,etc.), gross alpl~a;and gamma einitters.

b. Masi~llunlrelease rate (for m ~ yone-Ilour period). -

c. Estii~latedlnoilthly total radioactivity (in Curies) released. by nuclide. for 1-13 1.1- 133. H-3. and radioactive particulates \;\rith l~alf-livesgreater thall eight days. based on represelltative mlalyses performed by beta and by gcllnma isotopic analyses.

d. Sell~ia~~ilnual and a l m ~ atotals l of rnoi~tldyisotopic radiolluclide quantities.

Solid Waste

a. The .total amount of solid waste shipped, buried, or stored (in cubic feet).

b. Estiilzated total radioactivity and isotopic coiltent (in Culies) deterlniiled

.by scaling factors: gamma isotopic and!"orother suitable aizalyses.

c. T11e dates of sl~ipinel~t and burial site if sl~ippedfor buiial.

Page 7 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revisioil 5 Jai1ual-y 13, 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL

d. The type of waste shdl be iizdicated, i.e.: dry activated waste, resinst evaporator conceiztrates, filters, scrap metal: asbestos, etc.

1.5.4 Doses '

The air doses and the doses to the liyp~thetica~l maximum exposed individ~~al calculated follotiling tl~eODCM metllodology shall be reported.

1.5.5 M&teorologicalData Meteorological data sllall be kept in file on site for review by tile NRC ~ ~ p request.

on The data available will include wind speed. vi.ind .

direction q d atmosphe~icstability. The data will be stored ill an elecqonic fo1-111for each of the parameters.

1.6 Otlier RECP Reportable Events 1.6.1 Radioactive E fflueiit Non-Treatizzei~t If tlze eftl~~enttreatineilt system for radioactive liquids or for releases to the atmospl~ereis inoperable and eftlueilts are being discllarged for 3 1 consec~~tive days uitlzout the n-eatizzei~tseq~liredto meet tlle release liiilits specified iiz Section 5.0: a special report shall be prepared and s~~bmitted to tlze Coii~izzissioiiv\itl?in thirty days w~liicliiizcl~~desthe follovi.i~zgiizforination:

a. ldeiitification of tlle illoperable eq~tipiiieiltor subsysteiil and the reasoil for inoperability .

b. Actioiis talten to restore tlze inoperable equipineilt to operable status.

c. Suizzmai-y desc1iptioiz of actions talcen to preveizt 3 recuiyeizce.

1.6.2 Radioactive Efflueiit Release Limit Esceedeilce If tlze quantity of radioactive illaterid ack~allireleased in liquid or gaseous eftlueizts d~~zing ally calendar quarter exceeds twice the q~~arterly liinit as specified in Section 5.0, a special report shall be prepared and s~~bmitted to the Coiliinissioiz tvitliiz thirty days of deteriiliiiatioi~of the release q~taiitity.

The repol-t imust desciibe tl~eextent of exposwe of iildividuals to radiation and radioactive material, includii~gas appropriate:

a. the corrective actioil(s) to be taken to reduce subseclueiit releases to preveizt recurrence of exceeding the limits: incIudiilg tlze scIzeduIe for achieviizg confo~i~iance with applicable limits, ALARA constraints:

generally applicable en~iromiieiztalstandards, and associated license conditions, Page 8 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL kMNUAL Revisioi15 Ja11uai-y 113. 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL

b. estiinates of expos~tresto a ineinber of the public, iilcluding the dose from any esterilal storage units, sucl~as the lSFSl and the SGSF, for coinpliailce wit11 40 CFR 190 limits,

c. the levels of radiation and coilcei~tratioilsof radioactive inateiials involved, and

d. the cause of the elevated exposures, dose rates, or concentrations.

If the dose to any member of the pitblic esceeds 75 mreln to the thyroid or 25 i11rei1z to the wl~olebody or ally orgm other than the -thyroid,pussuaizt to 40.CFR 190, the report shall also contain a request for a valiance from this standard to 40 CFR 190.11. I Major Ckange to Radioactive Liq~ud,Gaseous and Solid Waste Treatment Systeins Licensee initiated major chalges to tile radioactive waste treatmei~tsystems (liq~~id, gaseous, and solid) shall be reported to the U.S. Nuclear Reg~tlatoiy Cominissioi~viritll the peiiodic ~tpdateto the FSAR for the peiiod for w l ~ i c l ~

the ~tpdatesare submitted. The dis~ussioilof each chailge shall iiiclude:

a. A suininaly of the evaluatioil that led to the deteriniilatioil that the chailge could be inade ill accordailce with 10 CFR Part 50.59:

b. Inlr'oi~nationnecessar~to support the reason for the cllange: /

c. A desciiptioi~of the equipment: compoileilts and processes iilvolved and the intellaces wit11 otlzer plant systems:

d. An evaluation of the change, which shows how the predicted releases of radioactive inateiials in l i q ~ ~efilueizts id and gaseous effl~~eilts and/or quantity of solid waste will differ from those previously predicted ill the license application and aineildments thereto;

e. An evaluation of the change, which shows the expected maximum exposures to an individual in the unrestsicted area and to the general populatioil that differ from those previously estimated in the license ,

applicatioil and ainei~dinentsthereto:

f. A11 estimate of the exposure to plai~toperating persoi~~lel because of the change.

1.7 Audits The activities of the Radiological Efiluent Controls Program as desciibed in this mmlual and its i~npleinentingprocedures shall be audited ill accordance \vitl~ODCM Section 1.4.

Page 9 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revisioi? 5 Ja11ual-y 13. 20 09 2.0 RADIOACTIVE EFFLUENT CONTROL 2.1 Liauid Radioactive Efl-lueiit Treatmeilt Svsteiii The liquid radioactive efl-lueilt tseatiiient systein coilsists of those coiilponeiits or devices used to reduce radioactive illateiial in liquid efiluent. The systecll coilsists of the following:

2.1.1 blowdouql evaporator or waste evaporator, 2.1.2 polisliing deiliineralizers.

I 2.1.3 bolic acid evaporator feed demiilerqlizers.

2.1.4 boiic acid evaporators.

2.1.5 boiic acid evaporator coildellsate deinineralizers.

2.i.6 Advaiiced Liquid Processing System (ALPS) 2.2 Claseo~~s Radioactive E f l ~ ~ eTreatment nt System Tlie gaseous radioactive efiluellt t r e a t ~ ~ ~systein e n t coi~sistsof those coi~lpoiiei~tsor devices utilized to redlice radioactive inatelial in efl-lueilt released to the atmospl~ere.Tlie system coiisists of t l ~ efollonring:

2.2.1 gas decay taizlts, 2.2.2 dr~u~lining area veiltilatioil esl~austduct filter assembly, 2.2.3 Unit 1 and 2 coiltainmellt purge exllaust filter assemblies, 2.2.4 air ejector decay duct filter assembly, 2.2.5 a~~xilialy building ventilation filter assembly (i~ominal1 1:2 14 cfrl exhaust patl~uray)~

2.2.6 clzeinistiy laboratoiy exhaust duct filter assembly, 2.2.7 service buildiilg ventilation exhaust duct filter assembly, 2.2.8 a~txilia1-ybuilding ventilation filter asseinblies (noinii~al34,150 cfil-1e x l ~ a ~ ~ s t patl~way).

Page 10 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOCrlCAL EFFLUENT CONTROL MANUAL Revision 5 J a n ~ ~ a13. ~ y2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL 2.3 Efil~~ent Colltrol and Accountabilitii 2.3.1 Radiation Monitoiing System

a. Description The con~putelizedRadiation Monitoling Systenl (RMS) at Point Beaclz N~lclearPlant consists of area and process mo~itors.The effl~~ent..

moiitors are tl~oseprocess moiitors tllat are designed to detect and measure radioactivity in liquid and gaseous releases fro111 PBNP. A .

desciiption of the liquid a ~ gaseous d effluent monitors and associated isolation and contsol fi~nctionsme presented in the ODCM.

t

b. Calibration Calibration of the RMS detectors is accomplisl~edaccordiilg to tlle proced~~res of the PBNP Health Pl~ysicsCalibration Man~lal.

The metl~odologyfor detelininil~geffluent U S detector setpoints is desciibed in the ODCM.

Response to alarms received from RMS efiluent detectors is described in the PBNP W l S Alaiil1 Setpoint and Respollse Book.

e. Efiluent Detector Operability and S~wveillance Detector operability and sullieillance r e q ~ ~ i r e l ~ ~are e n addressed ts in Sections 3.0 and 4.0 of this manual.

2.3.2 Effluent Treatment Scl~einatic The licl~lidand gaseous waste processing flow paths, eq~upinent,and radiation mo~itorsare depicted in the ODCM.

2.3.3 ' Release Accoulltability Col~troland accountability of radioactivity in PBNP effl~lent'sis acconlplished by the RMS in col~jui~ction wit11 the charactelization of radionuclide disuib~~tions by laboratory analyses of grab samples fro111 the wlious waste streams. Sampling frecl~lenciesand analysis req~lirementsare set fort11 in Section 6.0 of this inan-ual. Additional aspects of grab san~plingand release accountability are desciibed in the PBNP Release Acco~ultabilityManual.

Page 11 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 January 13. 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL 3.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION OPERABILITY REOUIREMENTS 3.1 Objective The operability of detectors is specified in order to ensure that liquid and gaseous radioactive effluents are adecluately illoilitored and to ellsure that alcliil~or tiip setpoii~ts are established such that effluent releases do not exceed the values cited ill Section 5.0.

3.2 Operability Specifications 3.2.1 , The radioactive effl~uei~t ilzonito~ii~g ii~struilleiltatioilchaimels listed in Tables 3-1 and 3-2 sl~allbe operable. The alalin or tlip set~ointsof these chanilels shall be deteli~~ined and adjusted in accordai~cewid1 tile metl~odologyand parailleters in the ODDCM.

3.2.2 If fewer than the n~iilirn~un i~~uinberof radioac tive effluent moizitolii~g clzai~ilelsare operable, t l ~ eaction stateineilt listed in either Table 3-1 or 3-2 opposite the cl-ia~izelshall be talcen. Best effort shall be iliade to rehull1 a11 illopesable cl~annelto operable stahls uritllin 30 days. If the channel is not rehullled to an operable status witlzii1 30 days: the circ~u1~stai1ces of the ii~stsz~i~~ent failure and sched~ulefor repair shall be reported to the NRC Resident Ii~spector.

3.2.3 If a radioactive eftlueilt illoizitoriilg inst~zunentatioiicl~aniielalalm or tsip setpoint is found less conservative thail recl~liredby tl~eODCM, the chaililel shall be declared illoperable or the setpoint shall be chai~gedto the ODCM value or a inore coilservative value.

Page 12 of 34

P O ~ N TBEACH NUC'EAR PLANT RECM RADIOLOGlCAL EFFLUENT CONTROL MANUAL Revisioiz 5 J a n ~ ~ a l13, y 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL TABLE 3-1 RADlOACTlVE LlQUlD EFFLUENT TVlONlTORlNG LNSTRUTVENTATION Mini muin Chan~~els lnsti~~ment (herable Action

1. Liq~udRadwaste Sy stein

a. RE-223, Waste Distillate Tank Discllarge 1 Note 9 b, RE-2 18. Waste Coi~densateTank Note 9 t Discllarge

c. Waste Coildellsate Tank Discharge Flow Note 4 Meter

d. Waste Distillate Tailk Flow Rate Recorder Note 4' Stearn Ge~leratorBlowdown System

a. For Each Unit: RE-219, Stekm Geilerator Note 2 Blovirdow~Liquid Discharge, or RE-222, Blourdo~vilTank Monitor, or a-2%),

Service Water Discl~arge'

b. Steam~GeneratorB l o w d o u ~Flow

~ Note 8 Indicators ( I per steain gei~erator)

Service Water Systein RE-229, Service Water Discl~arge Note 3 (1 per tulit)

For Each. .Unit: RE-2 16, Containinent Note 3 Cooling.Fan Service Water Retu111, or RE-229, Service Water Discllarge RE-220, Spent Fuel Pool Heat Exchanger Note 3 Service Water Outlet or RE-229, Service Water Discharge (for applicable ~lilit)

Page 13 of 34

POINT BEACH NUCLEAR PLANT lxEiCIvl RADlOLOCllCAL EFFLUENT CONTROL MANUAL Revisioi15 Januaiy 13, 2009 Waste Water ~ f f l ~ ~ e i i t

a. RE-230, Waste Water Efflueilt 1 Note 3

b. Waste Water E f f l ~ ~ eCoillposite nt Saillpler 1 Note 7 C. Waste Water Efi"~1e11tFlow Deteimii~ation NA *

Waste water effluent ilow may be deteiii~inedfrom the waste water efflueilt flow i~ieter.

Page 14 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL h/JANUAL Revision 5 January 13, 2009 TABLE 3-2 RADlOACTlVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Miizinlurn Clxu~nels Operable Ac tion

1. . Gas Decay Tank Systein

a. RE-21 4, Noble Gas (Ausiliaiy B~~ildillg 1 Note 1 Vent Stack), or RE-3 15 Noble Gas (Ausilixy B~~ilding Vent SPING)

I 1

b. Gas ~ e c a T y a ~ Flow k Measuiiilg Meter 1 Note 4

a. RE-21 3. Noble Gas (A~silialyB~~ildiilg Note 6 Vent Stack) or Re-3 15, Noble Gas (Ausiliary Buildiilg Vent SPING)

b. Isoltiiletic Iodine and Particulate - Note 5 Coiltii~uousAir Smnpling System or SPING 23

3. Coi~denserAir Ejector System

a. RE-225, Noble Gas (Combined Air Note 6 E-jectorDiscl~argeMonitor): or RE-21 5, Noble gas (Air Ejector Moi~itors- 1 per unit): or RE-2 13: Noble Gas (Ausilialy Building Vent Staclt): or RE-3 15: Noble Gas (Ausiliary Buildiilg Vent SPING)

b. Flow Rate Monitor - Air E-iectors 1 Note 8 Page 15 of 34

POINT BEACH NUCLEAR PLANT RE Cb1 RADIOLOGICAL EFFLUENT CONTROL MANUAL Revisioil 5 Januai-y 13, 2009 RADIOLOGICAL EFFLUENT CONTROL M4NUAL TABLE 3-2

4. Coiltaiiunlent Purge and Vent System RE-212, Noble Gas Moilitors Note 6 (1 per ~ulit);or RE-305, Noble Gas (Purge Exhaust SPING - 1 per ~ulit)

b. 30 cfin Forced Vent Path Flow Indicators 1 Note 8 I

lodiile and Partic~~late- Contiil~~ous Air Samplers or SPIN G 2 1 /22

d. $ampler Flow Rate Measuliilg Device 1 Note 6

5. Fuel Storage and Drumming Area Ventilation

, System M - 2 2 1, Noble Gas (Drumming Area 1 Note 6 Stack), or RE-325, Noble Gas (Drumming Area SPIN%G)

b. lsolci~~etic -

Iodine and Partic~~late 1 Note 5 Coilti~~uous Air Sml~pliilgSystem or SPING.24

6. Gas Stiipper B~~ilding Vei~tilation

a. RE-224: Noble Gas (Gas Stlipper Note 6 Building):,or RE-305, (Unit 2 Purge Esliaust SPING)

b. Iodine and Particulate - Contiil~~ousAir Note 5 Sampler or SPING 22

c. Sampler Flow Rate Measulii1g Device Note 8 Page I6 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 Jai1ual-y 13, 2009 MDIOLOGICAL EFFLUENT CONTROL MANUAL NOTATIONS FOR TABLES 3-1 AND 3-2 Note 1: If the iluinber of chaiu~elsoperable is fewer tllm the i~illiinuinrequired, efilueizt releases via this pathway may coiltinue provided that psior to iizitiatii~ga,release, bvo separate sainples are ai~alyzedby two teclznically qualified people in accordai1ce with the applicable part of Table 6-2 and the release rate is reviewed by two teclu.iically clualified people.

Note 2: If the nuinber of chaimels operable is fewer thml the iniilim~inrequired. efiluei~treleases via this pathway may coiltiilue provided grab sainples are analyzed for gainina radioactivity in accordailce with Table 6-1 at least oilce ever? 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mrhen the secoildary coolant specific activity is less tl1m10.0 1 pCi/cc dose eqtvivaleilt 1-131 or once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months \v11en the activity is greater than 0.0 1 pCi/cc dose equivaleilt 1-13 1 .

t 1 Note 3: If the nuinber of chailtlels operable is fewer than the iminim~unrequired. efil~vei~t releases via this pathway inay contii~ueprovided that at least oiice every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab sai~iples are collected and ai~alyzedin accordance wit11 Table 6-1.

Note 4: If the iluinber of chaimels operable is fewer tl7.m the miniin~vinrecl~vired~ efilueilt releases via this pathway inay coiltii1~veprovided the flow rate is estimated at least oiice every ~ O L K hours dui-ii~gactual gaseous or liquid batch releases.

Note 5: If the i ~ u ~ n bof e r chaimels operable is fewer than the ininim~unrecluired. efilueilt releases via the affected pathway i ~ ~ contii~ue ay provided sainples are contin~~ously collected with ausilialy sainpliilg eq~upment.(e.g.. ally low voluine sainpler virlzicll meets the recpiremeilts of Table 6-2).

Note 6: If the iluinber of cl~aimelsoperable is fewer than the imiiliin~unrequired. efiluei~treleases via this pathway may coiltiilue provided grab samples me collected at least once per 12 l~oursand are analyzed in accordance with Table 6-2.

Note 7: If the iluinber of charu~elsoperable is fewer than the ininim~vinrequired, efiluei~treleases via this pathway map coiltiilue provided grab sLmplesa e collected twice per week and analyzed in accordailce with Table 6-1.

Note 8: If the iiulnber of chaimels operable is fewer than the minim~unrequired, efiluent releases via this pathway may contiilue provided the flow is estimated or detei-mined with a~siliaiyiildicatioil at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Note 9: If the i~uinberof ckaix~elsoperable is fewer thal the ininiinrun reiluired, efilei~treleases via this pathway shall be discontiilued iminediately (reference TRM 3.3.1).

Page 17 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 Ja11~1ai-y13, 2009 RADIOLOGICAL EFFLUENT CONTROL lLJAN UAL 4.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUlRElLlENTS 4.1 Obiective To veiify that radioactive l i q ~ ~and i d gaseous efilueilt lzzoilitoiiilg ii~sts~~mentation is demonstsated to be operable by pei-iodic inspection, testing, and calibration.

4.2 Radioactive Monitoiiiis Iilsts~~~nentatiol~ Sui+veillance Reci~ureinents Each radioactive eftluellt moilitoiiilg instruiilentation clic?~nelshall be demonstsated operable by pesfoiinailce of tlle chai11el clieck, calibration, functioilal test: and source clieck at the frequencies s,lloum in Tables 4-1 and 4-2. t 4.3 Defillitioils 4.3.1 Source Check The assessineilt of cl~alli~el response by esposillg tlze cl~al~nel detector to a sotrce of illcreased radiation.

A q~~alitative deteiininatiol~of acceptable operability by observing cllannel I bellavior d~~i-ing operation. Tlis shall illclude, urllere possible. a coi1lpalison of the cl~annelwit11 other ii~dependeiltcl-tannelsmeas~tkngthe saine valiable.

4.3.3 Ftulctional Test The illjection of a silxulated signal illto the cl~aix~el to veiifqi tllat it is operable, illcludil1g alarin al~dlortiip initiating action.

Page 18 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revision 5 Ja11~1ary13, 200')

TABLE 4-1 RADlOACTlVE LlQUlD EFFLUENT MONITORDIG 1NSTRUMENTATlON SURVEILLANCE REQUIFEMENTS Channel Fui~ctioi~al Source lnstru~~~eilt Descliptio~l Check Calibrate Test Check

1. L i q ~ ~Raduraste id System

a. RE-223: Waste Distillate Tank Discl~arge

b. RE-2 18, Waste Co~ldeilsateTank Discharge

c. Waste Co~lde~lsate Tarik Discl~argeFlow Meter

d. Waste Distillate Tank Flow Rate Recorder

2. Steal11 Generator B l o u r d o ' ~Systeill

~

a. RE-2 19, Steal11 Generator Blo~~dowil Liquid Discharge

('1 per unit)

b. , RE-222, Blourdovtri~ Tank Monitor (I per unit)

c. Steal11 Geilerator Blowdovi~~ Flow Indicator ( 1 per steam generator)

Page 19 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 January 13. 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL TABLE 3- 1 (continued) v RADIOACTIVE LlQUlD EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUlPaMENTS Cl~annel Functio~~al Source Cl~eck Calibrate -

Test Check

3. Service Water System

a. RE-229, Service Water Discharge (1 per unit)

b. RE-2 16: Coiltai~m~ent Cooliilg Fan Service Water Return (1 per unit)

c. RE-220: Spent Fuel Pool Heat Eschanger Service Water Outlet

4. Waste Water Effluent

a. RE-230, Waste Water Efflue~lt

b. Waste Water Efil~~entCo~llposite Sanlpler

c. Waste Water Efilue~ltFlow Meter Page 20 of 34

POlNT BEACH NUCLEAR PLANT RECM RADlOL.OG1CAL EFFLUENT CONTROL MANUAL Revision 5 January 13,2009 RAD1OL.OGICAL EFFLUENT CONTROL MANUAL TABLE 4-2 P\ADIOACTlVE GASEOUS EFFLUENT MONITORING 1NSTRUMENTA'TlON SURVElLLANCE REOUlJXEMENTS Channel Fu~lctio~lal Source Channel Descril~tion Checlc Cd'b c I wte Check

1. tias Decay Tank Systenl

a. RE-2 14: Noble Gas (Ausi1ial-y Building Vent Stack

b. Gas Decay Taillc Flow Meas~~ring Device

2. Ausilialy Building Ventilation Systein

a. RE-2 14, Noble Gas (Ausilialy Building Vent Stack)

b. RE-3 15, Noble Gas (A~~silialy Building SPlN ti

c. lso1unetic lodine and Particulate Contin~~ous Air Sampling System Page 21 of 34

POINT BEACH NUCLEAR PLANT RECM RADIOLOGlCAL EFFLUENT CONTROL MANUAL Revision 5

- Janua1-y 13. 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 4-2'(continued)

PtADIOACTlVE GASEOUS EFFLUENT MONlTORlNG 1NSTRUMENTATlON SURVElLLANCE REQUIREMENTS Chailnel Fui~ctioilal Source Chailnel Desc~il)tioi~ Check Calibrate -

Test Checlc

3. Coildeilser Air Ejector Systeill

a. RE-225, Noble Gas (Combined Air Ejector Discharge)

b. RE-215,NobleGas D R Q M (Air E.jectors - 1 per unit)

c. Flow Rate Monitor - Air Ejectors (1 per uiit)

4. Containment P ~ ~ r and g e Vent System

a. RE-212, Noble Gas (1 per unit) D

b. 30 cfin Vent Pat11 Flow Indicator PID

c. RE-305, Noble Gas (Purge D

~ s h a u sSPING t - 1 per ~tnit)

d. lodine and Partic~~late Coiltiiluous Air Saillpler

e. Sanlpler Flow Rate Measuling Device Page 22 of 34

POlNT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revisioi1.5 January 13. 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL TABLE 3-2 (continued)

RADIOACTIVE GASEOUS EFFLUENT MONlTORlNG INSTRUMENTATION SURVElLLANCE PXQUIREMENTS Cl~annel - Fui~ctioilal Source Channel Desclil~tion Check Calihmte -

Test Check

5. Fuel Storage ailcl Drummiilg Area Veiltilatioil Stack

a. RE-221, Noble Gas (Dr~ulnmiing Area Vent Stack)

b. RE-325, Noble Gas (Dr~~inming Area SPING)

c. lsolcinetic lodi~leand Particrrlate Conti~l~~ous Air Salllpling System .

6. Gas Shi~lperBuildiilg Veiltilatioil Systein

a. RE-224 Noble Gas

b. lodiile and Particulate Coi~til~uous Air Sampler

c. Salnpler Flow Rate Measuring Device Page.23 of 34 .

\

POlNT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revision 5 Jail~~aiy 113. 2009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL NOTATlONS FOR TABLES 4- 1 AND 4-2 D = Daily W = Weeltly (1! = Quarterly .

, PiD = Prior to or immediately ~ ~ p initiation on pf a release or daily if a release contii~uesfor illore t than one day P/W = Psior to or immediately upoil initiation of a release or weeltly if a release coiltiilues for P = Prior to or irnn~ediately.uponinitiation of a release

= Source checlc seq~~ised prior to containment purge

)$ * = The chai~ilelcalibratioil sl~alliilclude the use of standard gas saillples appropriate to the recommendations of the rnai~~fact~~rer of the gas analyzer ecl~~ipmeizt in use and include calibration poiilts in the range of interest.

NA = not applicable Page 24 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revisioiz 5

, Jalzua1-y 13, 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.0 RADIOACTIVE EFFLUENT RELEASE LIMlTS 5.1 Obiective To ensure colltrolled releases of radioactive rnate~ialsin liquid and gaseous effluelits ro unsestlicted areas are uitlzin applicable 10 CFR 20 concentration liizlits and to efts~lrethe quantities of radioactive illate~ialreleased d ~ ~ r i nmgy calendar year are suclz that restdting radiation exposures do not esceed the dose objectives of 10 CFR 50, Appeiidix 1.

5.2 Radioactive L i q ~ ~Effl~~ent id concentsations 5.2.1 Alarm setpoiiits for liq~lideffluent inolzitors shall be dete~izlinedand adjusted utilizing t4e methodologies and paranzeters given in the ODCM. ,

5.2.2 Tlze licl~~id effluent il~onitorsetpoints slla11 be establislzed to ensure that radioactive lzlateiials released as effl~tentssl~allnot result in conceiztsatioiis to unsestiicted areas in excess of tell times tlze concentratiolz values specified in Appendix B. Table 2. Column 2. of 10 CFR 20.100 1-20.2402.

5.2.3 Duiing release of radioactive liq~lideffltlents, at least one colideizser circ~datingwater pump sllall be in operation and the sesvice water return header shall be lined LIP oilly to the unit wllose circulatil~gwater pump is operating.

5.3 Radiocictive Liq~lidEfil~~ent Release Limits 5.3.1 The aixiual calc~~lated total quaiztity of radioactive mateiial above background released from PBNP in l i q ~ ~effluei~ts id shall not res~iltin ~u?restiicteda e a estimated a1111~1aldose or dose cominitlnellt from all exposure patllways to any individual in excess of 6 lnillireill to the total body or 20 millisern to any organ.

5.3.2 For the puspose of initiating t l ~ euse of tlze liq~lideffluent treatment system wllenever the pro.jected dose for a period of 3 1 days \till esceed 2% of the dose guidelines of Appendix 1 to 10 CFR 50. The 2% of the Appendix 1 val~~es, as given in Section 5.3.1, are 0.12 mrem for the ~trl~ole body and 0.4 msem for any organ.

5.3.3 Quarterly limits are defined as one-lialf of the aiinual limits.

5.3.4 Colllpliance wit11 these release limits will be demonstsated by periodic dose calculatiolzs ~tiliziilgthe rnetl~odologyof t l ~ eODCM.

Page 25 of 34

POINT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL PlANUAL Revisioi~5 Jalzuaiy 13. 2009 ItADlOLOGlCAL EFFLUENT CONTROL MANUAL 5.4 Radioactive Gaseo~ts~ f f l ~ i e iCoi~centratioi~s lt 5.4.1 Alaii~lsetpoii1ts for the gaseous effluent monitors sl~allbe deteiinined aiid adjusted utilizing tl~emetl~odologies.and parameters given in tlie ODCM.

5.4.2 Tlie gaseous efiluent moilitor setpoints are estiblished to ei~suretllat radioactive inateiials released sl~allnot result in conceiitratioi~sto unrest~icted areas ill excess of the values specified ill 10 CFR 20: Appendix B, Table 2.

5.4.3 Duiing the release of radioactive gaseous efflueilts froin the gas decay talks tllro~tghthe a~~xiliaiy building vent, at least one auxiliary building exhaust fan shall be in operation.

I 1 5.5 Radioactive Gaseous Effl~~ent Release Limits 5.5.1 Tlie aix~ualcalc~datedtotal cluantip of radioactive materials above background released fro111 PBNP to the atlnosplzere sl~allnot result in an

~tixestsictedarea estimated ailnual dose or dose coiinmitnlent froin all exposure patll~aysto any illdivid~talin excess of the folloTnring:

a. 10 illire ire in to the total body or 30 millisem to the sltin.froin gaseous efflueilts near grottild level:

b. 30 millirein to any organ fro111 all 1-13 1; 1-133, H-3 and radioactive inateiials in particulate foiil~wl~osehalf-life is > 8 days; aiid

c. Furtlieiinore, tl~eaimual air dose from gaseous effluents at any locatioli near g r o ~ u ~level, d ~7llicl1could be occ~piedby iildividuals in ~mresn-icted areas, shall not exceed 20 inillisads for gamma radiation or 40 millisads for beta radiation.

5.5.2 For the pLli-pose of iilitiatiilg the use of the atmospl1eiic effluent treatineilt system nrllenever tlze projected dose for a peiiod of 3 1 days will exceed 2% of tlie dose guideliiles of Appendix 1 to 10 CFR 50, the 2% of t l ~ eAppendix I values, as given in Sectioil5.5.1, are:

a. 0.2 mrein to the total body and 0.G mrem to the skin, and

b. 0.6 mrem to ally organ.

5.5.3 Quarterly limits are defined as one-lmlf of tlie ani~uallimits.

5.5.4 Coinpliailce wit11 these release liinits will be demoi~stsatedby peiiodic dose calculatioils utilizing the metl~odologyof the ODCM.

Page 26 of 34

POlNT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revisioiz 5 Jaiz~1ai-y13 2009 13, 5.6 ~nzzosphelicRelease Rate ~$zzitations Tlze rate of release of radioactive efflueizts to tlze atmosplzere from tlze site, \?rliiclz if continued for one yeas, shall not res~lltin dose rates at or beyoizd tlze site bounda1-y tlzat exceed tlie follotviizg values.

5.6.1 For noble gases:

a. 500 rnre~niyrto tlze total body

b. 3000 mreiniyr to tlze skin t 5.6.2 For 1- 131, 1- 133: H-3 , azd all pastjc~datefoi-111 radioiz~lclideswit11 a lzalf-life

> S days:

5.6.3 The instantaneous, limiting release rates for tlie above aizizual rates, are calculated in Section 3.10 of tlze ODCM for valious release types. Below ase default v a l ~ ~for e s valious releases. Check tlze ODCM for tlie metliodology to calculate release rates for iziore specific radion~lclidemishlres or contact the cogizizait Radiological Eizgiiieer.

a. For izoble gases, the wlzol'e body dose is liiziitiizg yielding a rate of 1.22E-0 1 Ciisec.

b. For particulates, radioiodilzes and H-3, as desclibed above, tlze release rates are 1.13E-06 Ciisec for radioiodilzes 1.30E-06 Ciisec for cesiuizzs 2.1 6E-05 Ciisec for cobalts 3.62E-0 1 Ciisec for H-3 As a conser.crative measure: tlze limitiiig release rate should be applied to tlze ~71zoleradioiz~~clide rnishlre based ~ ~ p otlie i i presence or abseizce of tlze above 11za;jor dose coiitijbutors.

Page 27 of 34

POlNT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revisioi~5 Januay 1312009 RADlOLOGlCAL EFFLUENT CONTROL MANUAL

'5.7 Cumulative and Projected Doses 5.7.1 Deteliniilatioil of cumulative and projected dose coi~tiibutiol~s from radioactive efflueilts for the cum.ent caleildar quarter and cul-seizt calendar year, in accordance wit11 the metl~odologyand paraineters of tl~eODCM, sl~all be made at least every 3 1 days.

5.7.2 Beca~lseof the length of time recluired to coillplete all facets of tl~erequired calculatioi~sand to obtain the wdioa~lalyticalresults for efflueilt salllples sent to a coiltracted analytical 1aborato1-y~the detes~llinationof the cuwent quater dose may not be finished ~ultilthe follomling quarter.

5.7.3 If the calculatioils1 required by Sections 5.3.4 or 5.5.4 exceed the coi-sespoi~diilgquarterly limit duiing any caleildar quarter, a special report A611 be prepared and submitted.

5.7.4 If the calculations required by Sectioils 5.3.4 or 5.5.4 deilzonstrate that quarterly releases exceed the quasterly limit, coi-sective actions shall be talcell to ensuse that subseq~~ent releases in that caleildar year will coi~lplywit11 quarterly and annual limits.

5.8 Radioactive Efflueilt Treatinent 5.8.1 The gaseous radioactive efflueilt treatmeilt systeill shall be operated whenever tile projected dose for a 3 1 day period. from 1-13 1. 1-133. H-3. cmd radioactive particulates with a half-life > 8 days. exceeds the values of Section 5.5.2 (2% of the Appendix 1 values). If tile gaseous effluent treahllellt systein becoilles inoperable. the efflueilt reporting requiremeilts of Section 1.6 shall apply.

a. A gas decay tanlc(s) shdl be operated \x~lle~lever required to i~iaiiltain gaseous releases \vitl-ii~lthe limits of Section 5.5.2.a.

b. The ausilialy buildiilg veiltilation exllaust charcoal filter shall be operated wheil recluired to maintain gaseous releases witl~inthe liinit of Section 5.5.2.b for radioiodines.

c. Tlie air ejector charcoal filter shall be operated when required to iniintain releases witlziil the liillit of Section 5.5.2.b for radioiodines.

5.8.2 The l i q ~ ~radioactive id efflueilt tseatment system sllall be operated wllenever the projected dose for a 3 1 day peiiod exceeds the valtles of Section 5.3.4 (2% of the Appendix 1 values). If tlie liquid efflueilt treatment systein becomes inoperable, the effluent reportiilg requirei~ientsof Section 1.6 shall apply.

Page 28 of 34

POINT BEACH NUCLEAR PLANT RECb1 RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 Januaiy 13, 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL.

5.9 Total Dose 5.9.1 Coinpliai~cewitlz the provisions of Appendis 1 to 10 CFR 50 is adequate demoi~stsationof confo~nzaiiceto the standards set forth in 40 CFR 190.

5.9.2 If the calculatioi~srequired by 5.3.3 or 5.5.4 esceed mice tlze annual dose objectives of Sectioizs 5.3 aiid 5.5 . dose calculatioils shall be perfoiilzed as described in the ODCM and slzdl incl~tdedirect radiation coiztlibutions from reactor ~mitsaiid from any outside storage tanlts in addition to effluent patlz-ways.

5.9.3 A report mill be s~tbinittedto tlze Cominissioi~v\itlli1130 days ~lpoizcon~pletion

,of tlze dose calc~~lationsreq~uredby Section 5.9.2, if tlie cqlculated dose to any ineinber of tlze general pnblic esceeds the 440 CFR 190 aimual dose limits.

5.10 Solid Radioactive Waste The solid wdwaste system sllall be ~ ~ s in e daccordance witlz tlle Process Control Program to process radioactive wastes to meet all sllipping aiid b~uialg r o ~ ~ nrecluirernents.

d If the provisions of the Process Control Program are not satisfied, sl~ipmentsof defectively processed or defectively packaged radioactive waste from the site will be suspended. Tlze Process Control Progranl slzall be used to veiify solidification of radwaste.

6.0 RADIOACTIVE EFFLUENT.SAkff LING AND ANALYSIS REOUIREiVIENTS 6.1 Purpose .

P~~rsuant to the reqt~irementsof 10 CFR 20.1302, tlze puipose of tlis section is to specify the sanzpliizg frequency, tlie ailalysis frequeizcy, and analysis req~lireinentsfor radioactive liq~iidand gaseous effluents in order to velifv that tlie concentsations and q~~aitities of radioactive inateiial released from the site in licl~~id and gaseotls effluents do not esceed the objectives specified in Sectioil5.0.

6.2 Radioactive Liquid Waste Saiizplinr and Aizal.r;sis The concentration of radioactivity in liquid waste sl~allbe deteliniiied by saizzpling and analysis in accordance mitlz Table 6-1.

6.3 Radioactive Gaseous Waste Sampliniz and Analysis Tlle coiicentratioii of radioactivity in gaseotls wastes sl~allbe deteimined by sainpliiig and analyses in accordance wit11 Table 6-2.

Page 29 of 34

POlNT BEACH NUCLEAR PLANT RECM RADIOLOGlCAL EFFLUENT CONTROL MANUAL Revision 5 January 13. 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL '

TABLE 6-1 -

RADlOACTlVE LlQUID WASTE SAMPLlNG AND ANALYSlS PROGRAM Lower Level Sampling Minimum Type of of ~etection' Licluid Release Tvve Frequency Analvsis Frequencv Activity ~ n a l ~ s i s ~ (nCi/cc)

1. Batcl~ele ease?

a. Waste Condensate Tank Prior to Prior to Release Gamma Emitters 5 x 10'

b. Waste Distillate Tank Release 1-131 1 x 10'"

c. Monitor Tanks

d. Other tanks containing radioactivity to be Monthly on composites Gross Alpha 1 1o ~

discliarged obtained from batches Tritiuin released during the current month Quarterly on composites Sr-89/90 obtained from batches released during the current quarter Page 30 of 34

Ti-C'l

'+I 0

L m

aJ 9

2 L s

3

" (U

- wC C

+A ffi aJ 2 GZ (U 9 E-g >

0 8 0 6

.-?=2 tjm

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICALEFFLUENT CONTROL MANUAL Revision 5 January 13, 2009 RADiOLOGICAL EFFLUENT CONTROL MANUAL

1. Tile piincipal ganlina enlitter for which the garnilla isotopic LLD applies is Cs-1 37. Because ganlnla isotopic analyses are pei-foiilled, the LLDs for all otlier gamma emitters are inherently deteiiilined by the operating cllaracteiistics of the counting system. All identiiiable ganlnla enlitters will be reported in the A i ~ i l ~Monitoiing al Report.

\

2. A bate11 release is the discharge of liq~udwastes of a discrete vol~ulze.Prior to sampling for analyses, each batch slzall be isolated and mised to assure representative sai~lpling.

1

3. A contii~~~ous release is tlie discharge of licl~~id wastes of a 11011-discrete volume: e.g., fro111 a volume of a systeili that has an input f l o ~duling l the release.

t t

4. A contin~lousconlposite is one in w l i c l ~the method of sampling employed res~dtsin a speciinen tllat is representative of the liq~udsreleased.

5. Identified entrained noble gases shall be reported as gaseous effluents.

Page 32 of 34

POlNT BEACH NUCLEAR PLANT RECM RADlOLOGlCAL EFFLUENT CONTROL MANUAL Revisioil5 January 13.200C)

RADIOLOGICAL EFFLUENT CONTROL MANUAL TABLE 6-2 RADIOACTIVE GASEOUS tVASTE SAMPLING AND ANALYSIS PROGRAM Lower Level Mininium Type of of ~etection' Gaseous Release Tvpe Analvsis Freq- Activity Analvsis (pCi/cc)

1. Gas Decay Tank Prior to Prior to Release Gamma Emitters 1 x lo4 Release I

2. Containment Purge or Continuous Prior to purge" Prior to Purge Gamma Eniitters Vent or Vent or Vent Tritium

3. Continuous Releases: continuous3 Weeltly Analysis Gamma Emitters of Charcoal and 1-131 '

a. Unit 1 Containment Purge and Pattictilate Samples Vent

b. Unit 2 Containment Purge and Vent

c. Drumming Area Vent Monthly Composite Gross A lplla 1 x lo-"

d. Gas stripper Building Vent of Particulate Sample

e. Auxiliary Building Vent Quarterly Composite Sr-89/90 I x 10" of Particulate Sample Noble Gas Monitor Noble gases Gross'Beta or gamma

~onthl~~ Monthly Gamma Emitters (Grab)

Montllly Tritium Page 33 of 33

POINT BEACH NUCLEAR PLANT RECM RADIOLOGICAL EFFLUENT CONTROL MANUAL Revision 5 Jai1~lai-y13, 2009 RADIOLOGICAL EFFLUENT CONTROL MANUAL NOTES FOR TABLE 6-2

1. The pii~~cipal garnilla emitters for w l ~ i cthe l ~ LLD specificatioil applies are Cs-137 in particulates and Xe-133 in gases. Beca~~se gamrna isotopic aildyses are perfoiilled, tlze.LLDs for all other gaillilla elllitters are iilhereiltly deteiiniiled by the operating characteiistics of the couiltiilg system. All identifiable gamilza elllitters will be repol-ted ill tl~eAiunual Moilitoiiilg Report.

2. Tiiti~~i~ngrab scll~~ples \;\rill be talcen every 24 l~ourswllen the refileling cavity is flooded.

3. Tlle ratio of the sample flow rate to the release flow rate shall be lcilowl or estimated for tlle time peiiod covered by each saillpling iinterval.

1 4. Tsitium grab saillples will be taken every seven days fro111 the d l - ~ ~ i ~ ~ area m i n veiltilatioil g

exhaust!speilt file1 pool area wl~enevertl~ereis spent fuel in the spent fuel pool.

Page 34 of 34

NRC-2010-0062, Annual Monitoring Report

Contents

Text

SUMMARY

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NRC-2010-0062, Annual Monitoring Report

Text

SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

Description:

SUMMARY

1.0 INTRODUCTION

Dear Mr. Farrell:

Dear Mr. Farrell:

Dear Mr. Farrell:

Dear Mr. Farrell:

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